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Proposed Rule

ESBWR Design Certification

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Start Preamble

AGENCY:

Nuclear Regulatory Commission.

ACTION:

Supplemental proposed rule.

SUMMARY:

The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to certify the Economic Simplified Boiling-Water Reactor (ESBWR) standard plant design. The proposed ESBWR design certification rule was published for public comment on March 24, 2011. The NRC is publishing this supplemental proposed rule to provide an opportunity for the public to comment on two matters. The first is proposed changes related to the analysis methodology supporting the ESBWR steam dryer design that were made after the close of the public comment period for the proposed ESBWR design certification rule. The second is the NRC's proposed clarification of its intent to treat 50 referenced documents within Revision 10 of the ESBWR design control document (DCD) as requirements and matters resolved in subsequent licensing and enforcement actions for plants referencing the ESBWR design certification. In addition, the supplemental proposed rule clarifies that the NRC intends to obtain approval for incorporation by reference from the Director of the Office of the Federal Register for the generic DCD and 20 publicly-available documents that are referenced in the DCD that are intended by the NRC to be requirements. The supplemental proposed rule does not offer an opportunity for public comment on this clarification of the NRC's intent. Finally, the supplemental proposed rule updates the version of the DCD (from Revision 9 to Revision 10) which the NRC proposes to obtain approval for incorporation by reference from the Office of the Federal Register. Revision 10 of the DCD was needed to address the previously described matters. The applicant for certification of the ESBWR design is GE-Hitachi Nuclear Energy (GEH).

DATES:

Submit comments by June 5, 2014. The NRC will not address any comments received after this date, except as discussed in Section I.B of the SUPPLEMENTARY INFORMATION section of this document.

ADDRESSES:

You may submit comments by any of the following methods (unless this document describes a different method for submitting comments on a specific subject):

  • Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2010-0135. Address questions about NRC dockets to Carol Gallagher; telephone: 301-287-3422; email: Carol.Gallagher@nrc.gov. For technical questions contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this proposed rule.
  • Email comments to: Rulemaking.Comments@nrc.gov. If you do not receive an automatic email reply confirming receipt, then contact us at 301-415-1677.
  • Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 301-415-1101.
  • Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.
  • Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal workdays; telephone: 301-415-1677.

For additional direction on obtaining information and submitting comments, see “Obtaining Information and Submitting Comments” in the SUPPLEMENTARY INFORMATION section of this document.

Start Further Info

FOR FURTHER INFORMATION CONTACT:

George M. Tartal, telephone: 301-415-0016, email: George.Tartal@nrc.gov; or David Misenhimer, telephone: 301-415-6590, email: David.Misenhimer@nrc.gov. Both of the Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001.

End Further Info End Preamble Start Supplemental Information

SUPPLEMENTARY INFORMATION:

Table of Contents

I. Obtaining Information and Submitting Comments

A. Obtaining Information

1. Documents Related To Changes Associated With the Analysis Methodology Supporting the ESBWR Steam Dryer Design

2. 50 Non-Public Documents Which the NRC Regards As Requirements and Are Matters Resolved

B. Additional Information on Submitting Comments

II. Background

III. Discussion

A. ESBWR Steam Dryer Design

1. Correction of Information Related to the Steam Dryer Design

2. Designation of Revised Steam Dryer Analysis Methodology as Tier 2*Start Printed Page 25716

B. Clarification of 50 Non-Public Documents Which the NRC Regards As Requirements and Are Matters Resolved Under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule

C. Clarification of 20 Publicly-Available Documents Which the NRC Regards As Requirements and Are Matters Resolved Under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule

IV. Section-by-Section Analysis

V. Plain Writing

VI. Environmental Impact: Finding of No Significant Environmental Impact: Availability

VII. Paperwork Reduction Act Statement

VIII. Regulatory Analysis

IX. Backfitting and Issue Finality

X. Procedures for Access to Sensitive Unclassified Non-Safeguards Information (Including Proprietary Information) or Safeguards Information for Preparation of Comments on the Supplemental Proposed ESBWR Design Certification Rule

XI. Availability of Documents

I. Obtaining Information and Submitting Comments

A. Obtaining Information

Please refer to Docket ID NRC-2010-0135 when contacting the NRC about the availability of information for this action. You may access publicly-available information related to this action by any of the following methods:

  • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2010-0135.
  • NRC's Agencywide Documents Access and Management System (ADAMS): You may access publicly-available documents online in the NRC Library at http://www.nrc.gov/​reading-rm/​adams.html. To begin the search, select “ADAMS Public Documents” and then select “Begin Web-based ADAMS Search.” For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this document (if that document is available in ADAMS) is provided the first time that a document is referenced.
  • NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

1. Documents Related To Changes Associated With the Analysis Methodology Supporting the ESBWR Steam Dryer Design

The documents identified in Table 1, relating to the changes associated with the analysis methodology supporting the ESBWR steam dryer design, are available to interested persons who wish to comment on the proposed changes. Some of the documents in Table 1 have two versions: a version which is publicly-available, and the (original and complete) version which is not publicly available because it contains information which is proprietary. If you need to obtain access to the non-public version of a document in order to provide comments on the proposed changes to the analysis methodology supporting the ESBWR steam dryer design, please follow the process described in Section X of the SUPPLEMENTARY INFORMATION section of this document. Before requesting access to the non-public version of any document, please obtain the publicly-available version of the document to verify if the information in the publicly-available version of a document is sufficient to allow you to comment on the proposed changes to the analysis methodology supporting the ESBWR steam dryer design.

Table 1—Documents Relating to the Changes Associated With the Analysis Methodology Supporting the ESBWR Steam Dryer Design

Document No.Document titlePublicly- available ADAMS accession No.Non-publicly available ADAMS accession No.
Supplemental proposed rule documents
Supplemental Final Safety Evaluation ReportAdvanced Supplemental Safety Evaluation Report For The Economic Simplified Boiling-Water Reactor Standard Plant DesignML14043A134ML13330A950
ESBWR DCD, Rev. 10ESBWR Design Control Document, Revision 10ML14104A929  (package)ML14104A153  (package)
NEDO-33312, Rev. 5, NEDE-33312P, Rev. 5GE Hitachi Nuclear Energy, “ESBWR Steam Dryer Acoustic Load Definition,” NEDE-33312P, Class III (Proprietary), Revision 5, December 2013, and NEDO-33312, Class I (Non-proprietary), Revision 5, December 2013ML13344B157ML13344B163
NEDO-33313, Rev. 5 NEDE-33313P, Rev. 5GE Hitachi Nuclear Energy, “ESBWR Steam Dryer Structural Evaluation,” NEDE-33313P, Class III (Proprietary), Revision 5, December 2013, and NEDO-33313, Class I (Non-proprietary), Revision 5, December 2013ML13344B158ML13344B164
NEDO-33408, Rev. 5, NEDE-33408P, Rev. 5GE Hitachi Nuclear Energy, “ESBWR Steam Dryer—Plant Based Load Evaluation Methodology, PBLE01 Model Description,” NEDE-33408P, Class III (Proprietary), Revision 5, December 2013, and NEDO-33408, Class I (Non-proprietary), Revision 5, December 2013ML13344B159ML13344B176  (part 1) ML13344B175  (part 2)
Start Printed Page 25717
Other NRC documents relevant to the safety review of the ESBWR steam dryer analysis methodology
N/ALetter from Michael E. Mayfield, NRC, to Gerald G. Head, GEH, “Economic Simplified Boiling Water Reactor Design Certification Rulemaking Schedule,” January 19, 2012ML120170304N/A
N/ANRC Staff Audit of Steam Dryer Design Methodology Supporting Chapter 3 of the Economic Simplified Boiling Water Reactor Design Certification Document, Revision #1 (Audit Plan), March 20, 2012 (PUBLIC), March 20, 2012 (PROPRIETARY)ML120790454ML120760509
N/AAudit Report of ESBWR Steam Dryer Design Methodology Supporting Chapter 3 of ESBWR Design Control Document (Audit Report), June 14, 2012 (PUBLIC), May 17, 2012 (PROPRIETARY)ML12166A127ML12137A497
N/ALetter from Kerri Kavanagh, NRC, to Gerald G. Head, GEH, “Quality Assurance Implementation Inspection of Economic Simplified Boiling Water Reactor,” March 14, 2012ML12073A165N/A
NRC Inspection Report 052010/2012-201NRC Inspection Report 05200010/2012-201 and Notice of Violation, July 6, 2012 (PUBLIC), May 31, 2012 (PROPRIETARY)ML12187A102ML12129A438
Table 1 Note: Documents whose document number contains “NEDC” or “NEDE” are non-public and documents whose document number contains “NEDO” are public.

2. 50 Non-Public Documents Which the NRC Regards as Requirements and Are Matters Resolved

In addition to Revision 10 of the ESBWR DCD, the non-public versions of the 50 documents identified in Table 2 are documents which the NRC regards as requirements and are matters resolved under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule. The documents in Table 2 are available to interested persons who wish to comment on the NRC's proposed clarification of its intent to treat these non-public documents as requirements and matters resolved in subsequent licensing and enforcement actions for plants referencing the ESBWR design certification. The NRC notes that three of the documents in Table 2 related to the ESBWR steam dryer are the same documents described in Section III.A and listed in Table 1 of the SUPPLEMENTARY INFORMATION section of this document. Accordingly, the NRC regards these three documents as requirements and are matters resolved under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule.

All of the documents in Table 2 have two versions: A version which is publicly-available, and the (original and complete) version which is not publicly available because it contains information which is either Sensitive Unclassified Non-Safeguards Information (SUNSI) (including SUNSI constituting “proprietary information” [1] ), or Safeguards Information (SGI) under Section 147 of the Atomic Energy Act of 1954, as amended. If you need to obtain access to the non-public document in order to provide comments on the NRC's proposed clarification of its intent to treat the 50 documents in Table 2 as matters resolved in subsequent licensing and enforcement actions for plants referencing the ESBWR design certification, please follow the process described in Section X of the SUPPLEMENTARY INFORMATION section of this document. Before requesting access to any non-public document, please obtain the publicly-available version of the document to verify if the information in the publicly-available version of a document is sufficient to allow you to comment on the NRC's proposed clarification of its intent to treat the 50 documents in Table 2 as matters resolved in subsequent licensing and enforcement actions for plants referencing the ESBWR design certification.

Start Printed Page 25718

Table 2—50 Non-Public Documents Which the NRC Regards as Requirements and are Matters Resolved Under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule

Document No.Document titlePublicly- available ADAMS accession No.Non-publicly available ADAMS accession No.
NEDE-33391, NEDO-33391GE Hitachi Nuclear Energy, “ESBWR Safeguards Assessment Report,” NEDE-33391, Class III (Safeguards, Security-Related, and Proprietary), Revision 3, March 2010, and NEDO-33391, Class I (Non-safeguards, Non-security related, and Non-proprietary), Revision 3, March 2014ML14093A138N/A (Safeguards information cannot be placed in ADAMS)
NEDC-31959P, NEDO-31959GE Nuclear Energy, “Fuel Rod Thermal-Mechanical Analysis Methodology (GSTRM),” NEDC-31959P (Proprietary), April 1991, and NEDO-31959 (Non-proprietary), April 1991ML14093A145ML14093A146
NEDC-32992P-A, NEDO-32992-AGE Nuclear Energy, J. S. Post and A. K. Chung, “ODYSY Application for Stability Licensing Calculations,” NEDC-32992P-A, Class III (Proprietary), July 2001, and NEDO-32992-A, Class I (Non-proprietary), July 2001ML14093A250ML012610605
NEDC-33139P-A, NEDO-33139-AGlobal Nuclear Fuel, “Cladding Creep Collapse,” NEDC-33139P-A, Class III (Proprietary), July 2005, and NEDO-33139-A, Class I (Non-proprietary), July 2005ML14094A227ML14094A228
NEDE-31758P-A, NEDO-31758-AGE Nuclear Energy, “GE Marathon Control Rod Assembly,” NEDE-31758P-A (Proprietary), October 1991, and NEDO-31758-A (Non-proprietary), October 1991ML14093A142ML14093A143
NEDC-32084P-A, NEDO-32084-AGE Nuclear Energy, “TASC-03A, A Computer Program for Transient Analysis of a Single Channel,” NEDC-32084P-A, Revision 2, Class III (Proprietary), July 2002, and NEDO-32084-A, Class 1 (Non-proprietary), Revision 2, September 2002ML100220484ML100220485
NEDC-32601 P-A, NEDO-32601-AGE Nuclear Energy, “Methodology and Uncertainties for Safety Limit MCPR Evaluations,” NEDC-32601P-A, Class III (Proprietary), and NEDO-32601-A, Class I (Non-proprietary), August 1999ML14093A216ML003740145
NEDC-32983P-A, NEDO-32983-AGE Nuclear Energy, “GE Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluations,” Licensing Topical Report NEDC-32983P-A, Class III (Proprietary), Revision 2, January 2006, and NEDO-32983-A, Class I (Non-proprietary), Revision 2, January 2006ML072480121ML072480125
NEDC-33075P-A, NEDO-33075-AGE Hitachi Nuclear Energy, “General Electric Boiling Water Reactor Detect and Suppress Solution—Confirmation Density,” NEDC-33075P-A, Class III (Proprietary), and NEDO-33075-A, Class I (Non-proprietary), Revision 6, January 2008ML080310396ML080310402
NEDC-33079P, NEDO-33079GE Nuclear Energy, “ESBWR Test and Analysis Program Description,” NEDC-33079P, Class III (Proprietary), Revision 1, March 2005, and NEDO-33079, Class I (Non-proprietary), Revision 1, November 2005ML053460471ML051390233
NEDC-33083P-A, NEDO-33083-AGE Nuclear Energy, “TRACG Application for ESBWR,” NEDC-33083P-A, Revision 1, Class III (Proprietary), September 2010, and NEDO-33083-A, Revision 1, Class I (Non-proprietary), September 2010ML102770606ML102770608
NEDC-33237P-A, NEDO-33237-AGlobal Nuclear Fuel, “GE14 for ESBWR—Critical Power Correlation, Uncertainty, and OLMCPR Development,” NEDC-33237P-A, Revision 5, Class III (Proprietary), and NEDO-33237-A, Revision 5, Class I (Non-proprietary), September 2010ML102770246ML102770244
NEDC-33238P, NEDO-33238Global Nuclear Fuel, “GE14 Pressure Drop Characteristics,” NEDC-33238P, Class III (Proprietary), and NEDO-33238, Class I (Non-proprietary), December 2005ML060050328ML060050330
NEDC-33239P-A, NEDO-33239P-AGlobal Nuclear Fuel, “GE14 for ESBWR Nuclear Design Report,” NEDC-33239P-A, Class III (Proprietary), and NEDO-33239-A, Class I (Non-proprietary), Revision 5, October 2010ML102800405ML102800408  (part 1) ML102800425  (part 2)
NEDC-33240P-A, NEDO-33240-AGlobal Nuclear Fuel, “GE14E Fuel Assembly Mechanical Design Report,” NEDC-33240P-A, Revision 1, Class III (Proprietary), and NEDO-33240-A, Revision 1, Class I (Non-proprietary), September 2010ML102770060ML102770061
NEDC-33242P-A, NEDO-33242-AGlobal Nuclear Fuel, “GE14 for ESBWR Fuel Rod Thermal-Mechanical Design Report,” NEDC-33242P-A, Revision 2, Class III (Proprietary), and NEDO-33242-A, Revision 2, Class I (Non-proprietary), September 2010ML102730885ML102730886
NEDC-33326P-A, NEDO-33326-AGlobal Nuclear Fuel, “GE14E for ESBWR Initial Core Nuclear Design Report,” NEDC-33326P-A, Revision 1, Class III (Proprietary), and NEDO-33326-A, Revision 1, Class I (Non-proprietary), September 2010ML102740191ML102740193  (part 1) ML102740194  (part 2)
Start Printed Page 25719
NEDC-33374P-A, NEDO-33374-AGE-Hitachi Nuclear Energy, “Safety Analysis Report for Fuel Storage Racks Criticality Analysis for ESBWR Plants,” NEDC-33374P-A, Revision 4, Class III (Proprietary), September 2010, and NEDO-33374-A, Revision 4, Class I (Non-proprietary), September 2010ML102860687ML102860688
NEDC-33456P, NEDO-33456Global Nuclear Fuel, “Full-Scale Pressure Drop Testing for a Simulated GE14E Fuel Bundle,” NEDC-33456P, Class III (Proprietary), and NEDO-33456, Class I (Non-proprietary), Revision 0, March 2009ML090920867ML090920868
NEDE-10958-PA, NEDO-10958-AGeneral Electric Company, “General Electric Thermal Analysis Basis Data, Correlation and Design Application,” NEDE-10958-PA, Class III (Proprietary), and “General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application,” NEDO-10958-A, Class I (Non-proprietary), January 1977ML102290144ML092820214
NEDE-24011-P-A-16, NEDO-24011-A-16Global Nuclear Fuel, “GESTAR II General Electric Standard Application for Reactor Fuel,” NEDE-24011-P-A-16, Class III (Proprietary), and NEDO-24011-A-16, Class I (Non-proprietary), Revision 16, October 2007ML091340077ML091340081
NEDE-24011-P-A-US-16, NEDO-24011-A-US-16Global Nuclear Fuel, “GESTAR II General Electric Standard Application for Reactor Fuel, Supplement for United States,” NEDE-24011-P-A-US-16, Class III (Proprietary), and NEDO-24011-A-US-16, Class I (Non-proprietary), Revision 16, October 2007ML091340080ML091340082
NEDE-30130-P-A, NEDO-30130-AGeneral Electric Company, “Steady State Nuclear Methods,” NEDE-30130-P-A, Class III (Proprietary), April 1985, and NEDO-30130-A, Class I (Non-proprietary), May 1985ML14104A064ML070400570
NEDE-31152P, NEDO-31152Global Nuclear Fuel, “Global Nuclear Fuels Fuel Bundle Designs,” NEDE-31152P, Revision 9, Class III (Proprietary), May 2007, and NEDO-33152, Revision 9, Class I (Non-proprietary), May 2007ML071510287ML071510289
NEDE-32176P, NEDO-32176GE Hitachi Nuclear Energy, J. G. M. Andersen, et al., “TRACG Model Description,” NEDE-32176P, Revision 4, Class III (Proprietary), January 2008, and NEDO-32176, Class I (Non-proprietary), Revision 4, January 2008ML080370271ML080370276
NEDE-33083 Supplement 1P-A, NEDO-33083 Supplement 1-AGE Hitachi Nuclear Energy, B.S. Shiralkar, et al, “TRACG Application for ESBWR Stability Analysis,” NEDE-33083, Supplement 1P-A, Revision 2, Class III (Proprietary), September 2010, and NEDO-33083, Supplement 1-A, Revision 2, Class I (Non-proprietary), September 2010ML102770552ML102770550
NEDE-33083 Supplement 2P-A, NEDO-33083 Supplement 2-AGE Hitachi Nuclear Energy, “TRACG Application for ESBWR Anticipated Transient Without Scram Analyses,” NEDE-33083, Supplement 2P-A, Revision 2, Class III (Proprietary), October 2010 and NEDO-33083, Supplement 2-A, Revision 2, Class I (Non-proprietary), October 2010ML103000353ML103000355
NEDE-33083 Supplement 3P-A, NEDO-33083 Supplement 3-AGE Hitachi Nuclear Energy, “TRACG Application for ESBWR Transient Analysis,” NEDE-33083, Supplement 3P-A, Revision 1, Class III (Proprietary), and NEDO-33083, Supplement 3-A, Revision 1, Class I (Non-proprietary), September 2010ML102770606ML102770608
NEDE-33197P-A, NEDO-33197-AGE Hitachi Nuclear Energy, “Gamma Thermometer System for LPRM Calibration and Power Shape Monitoring,” NEDE-33197P-A, Revision 3, Class III (Proprietary), and NEDO-33197-A, Revision 3, Class I, (Non-proprietary), October 2010ML102810320ML102810341
NEDE-33217P, NEDO-33217GE Hitachi Nuclear Energy, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan,” NEDE-33217P, Class III (Proprietary), and NEDO-33217, Class I (Non-proprietary), Revision 6, February 2010ML100480284ML100480285
NEDE-33220P, NEDO-33220GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Allocation of Function Implementation Plan,” NEDE-33220P, Class III (Proprietary), and NEDO-33220, Class I (Non-proprietary), Revision 4, February 2010ML100480209ML100480202
NEDE-33221P, NEDO-33221GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Task Analysis Implementation Plan,” NEDE-33221P, Class III (Proprietary), and NEDO-33221, Class I (Non-proprietary), Revision 4, February 2010ML100480212ML100480213
NEDE-33226P, NEDO-33226GE Hitachi Nuclear Energy, “ESBWR—Software Management Program Manual,” NEDE-33226P, Class III (Proprietary), Revision 5, February 2010, and NEDO-33226, Class I (Non-proprietary), Revision 5, February 2010ML100550837ML100550844
Start Printed Page 25720
NEDE-33243P-A, NEDO-33243-AGE Hitachi Nuclear Energy, “ESBWR Control Rod Nuclear Design,” NEDE-33243P-A, Revision 2, Class III (Proprietary), September 2010, and NEDO-33243- A, Revision 2, Class I (Non-proprietary), September 2010ML102740171ML102740178
NEDE-33244P-A, NEDO-33244-AGE Hitachi Nuclear Energy, “ESBWR Marathon Control Rod Mechanical Design Report,” NEDE-33244P-A, Class III (Proprietary), Revision 2, September 2010, and NEDO-33244-A, Revision 2, Class I (Non-proprietary), September 2010ML102770208ML102770209
NEDE-33245P, NEDO-33245GE Hitachi Nuclear Energy, “ESBWR—Software Quality Assurance Program Manual,” NEDE-33245P, Class III (Proprietary), Revision 5, February 2010, and NEDO-33245, Class I (Non-proprietary), Revision 5, February 2010ML100550839ML100550847
NEDE-33259P-A, NEDO-33259-AGE Hitachi Nuclear Energy, “Reactor Internals Flow Induced Vibration Program,” NEDE-33259P-A, Class III (Proprietary), Revision 3, October 2010, and NEDO-33259-A, Class I (Non-proprietary), Revision 3, October 2010ML102920241ML102920248
NEDE-33261P, NEDO-33261GE Hitachi Nuclear Energy, “ESBWR Containment Load Definition,” NEDE-33261P, Class III (Proprietary), and NEDO-33261, Class I (Non-proprietary), Revision 2, June 2008ML082600720ML082600721
NEDE-33268P, NEDO-33268GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Human-System Interface Design Implementation Plan,” NEDE-33268P, Class III (Proprietary), and NEDO-33268, Class I (Non-proprietary), Revision 5, February 2010ML100480179ML100480180
NEDE-33276P, NEDO-33276GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Verification and Validation Implementation Plan,” NEDE-33276P, Class III (Proprietary), and NEDO-33276, Class I (Non-proprietary), Revision 4, February 2010ML100480182ML100480183
NEDE-33295P, NEDO-33295GE Hitachi Nuclear Energy, “ESBWR Cyber Security Program Plan,” NEDE-33295P, Class III (Proprietary), Revision 2, September 2010, and NEDO-33295, Class I (Non-proprietary), Revision 2, September 2010ML102880103ML102880104
NEDE-33304P, NEDO-33304GE Hitachi Nuclear Energy, “GEH ESBWR Setpoint Methodology,” NEDE-33304P, Class III (Proprietary), and NEDO-33304, Class I (Non-proprietary), Revision 4, May 2010ML101450251ML101450253
NEDE-33312P, NEDO-33312GE Hitachi Nuclear Energy, “ESBWR Steam Dryer Acoustic Load Definition,” NEDE-33312P, Class III (Proprietary), Revision 5, December 2013, and NEDO-33312, Class I (Non-proprietary), Revision 5, December 2013ML13344B157ML13344B163
NEDE-33313P, NEDO-33313GE Hitachi Nuclear Energy, “ESBWR Steam Dryer Structural Evaluation,” NEDE-33313P, Class III (Proprietary), Revision 5, December 2013, and NEDO-33313, Class I (Non-proprietary), Revision 5, December 2013ML13344B158ML13344B164
NEDE-33408P, NEDO-33408GE Hitachi Nuclear Energy, “ESBWR Steam Dryer—Plant Based Load Evaluation Methodology, PBLE01 Model Description,” NEDE-33408P, Class III (Proprietary), Revision 5, December 2013, and NEDO-33408, Class I (Non-proprietary), Revision 5, December 2013ML13344B159ML13344B176 (part 1) ML13344B175 (part 2)
NEDE-33440P, NEDO-33440GE Hitachi Nuclear Energy “ESBWR Safety Analysis- Additional Information,” NEDE-33440P, Class III (Proprietary), and NEDO-33440, Class I (Non-proprietary), Revision 2, March 2010ML100920316ML100920317  (part 1) ML100920318  (part 2)
NEDE-33516P-A, NEDO-33516-AGE Hitachi Nuclear Energy, “ESBWR Qualification Plan Requirements for a 72-Hour Duty Cycle Battery,” NEDE-33516P-A, Revision 2, Class III (Proprietary), September 2010, and NEDO-33516-A, Revision 2, Class I (Non-proprietary), September 2010ML102880499ML102880500
NEDE-33536P, NEDO-33536GE Hitachi Nuclear Energy, “Control Building and Reactor Building Environmental Temperature Analysis for ESBWR,” NEDE-33536P, Class III (Security-Related and Proprietary), Revision 1, October 2010, and NEDO-33536, Class I (Non-security Related and Non-proprietary), Revision 1, October 2010ML102780329ML102780330
NEDE-33572P, NEDO-33572GE Hitachi Nuclear Energy, “ESBWR ICS and PCCS Condenser Combustible Gas Mitigation and Structural Evaluation,” NEDE-33572P, Class II (Proprietary), Revision 3, September 2010, and NEDO-33572, Revision 3, Class I (Non-proprietary), September 2010ML102740579ML102740566
Start Printed Page 25721
Letter w/attachmentLetter from R. J. Reda (GE) to R. C. Jones, Jr. (NRC), MFN 098-96, “Implementation of Improved Steady-State Nuclear Methods,” Class III (Proprietary), July 2, 1996, and Letter from J. G. Head (GEH) to NRC Document Control Desk, MFN 098-96 Supplement 1, Class I (Non-proprietary), March 31, 2014ML14093A140ML14094A240
Table 2 Note: Documents whose document number contains “NEDC” or “NEDE” are non-public and documents whose document number contains “NEDO” are public.

Throughout the development of the ESBWR design certification rule, the NRC may post additional documents related to this rule, including public comments, on the Federal rulemaking Web site at http://www.regulations.gov under Docket ID NRC-2010-0135. The Federal rulemaking Web site allows you to receive alerts when changes or additions occur in a docket folder. To subscribe: (1) Navigate to the docket folder (NRC-2010-0135); (2) click the “Sign up for Email Alerts” link; and (3) enter your email address and select how frequently you would like to receive emails (daily, weekly, or monthly).

Documents that are not publicly available because they are considered to be SUNSI or SGI may be available to interested persons who may wish to comment on the changes associated with the analysis methodology supporting the ESBWR steam dryer design. Such persons shall follow the procedures described in Section X of the SUPPLEMENTARY INFORMATION section of this document in order to obtain access to those documents.

B. Additional Information on Submitting Comments

General Information

Please include Docket ID NRC-2010-0135 in the subject line of your comment submission, in order to ensure that the NRC is able to make your comment submission available to the public in this docket.

The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information.

If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS.

Comments Based Upon a Review of Non-Public Documents Obtained Under the Procedures in Section X of the SUPPLEMENTARY INFORMATION Section of This Document

The NRC strongly encourages commenters, submitting comments based upon a review of non-public documents to which the commenter obtained access under the procedures in Section X of the SUPPLEMENTARY INFORMATION section of this document, to avoid submitting comments with non-public information derived from those non-public documents. In many cases, effective arguments may be presented by referring to the location of relevant information in those documents. In other cases, a summary of the key information in the document, and a reference to the portion of the document supporting the comment, will provide adequate basis for the comment without disclosing non-public information. However, if the comment must include non-public information, the commenter must submit the comments in accordance with § 2.390 of Title 10 of the Code of Federal Regulations (10 CFR). The NRC recommends preparing two versions of your comment submission—one public and one non-public, and submitting an affidavit with your comment submission explaining, with specificity, why the information in your comment submission should be regarded as non-public.

Scope of Comments

The NRC is limiting the scope of the supplemental proposed rule to two areas, which are further discussed in Section III of the SUPPLEMENTARY INFORMATION section of this document:

  • Proposed changes related to the analysis methodology supporting the ESBWR steam dryer design that were made after the close of the public comment period for the proposed ESBWR design certification rule (76 FR 16549; March 24, 2011).
  • The NRC's proposed clarification of its intent to treat 50 non-public documents referenced in the ESBWR DCD as requirements and matters resolved in subsequent licensing and enforcement actions for plants referencing the ESBWR design certification.

The NRC will not address in a final rule any comments submitted that are outside the scope of this supplemental proposed rule. For example, comments on Revision 10 of the ESBWR DCD which do not relate to the changes in the analysis methodology supporting the ESBWR steam dryer design which were made after the close of the public comment period for the proposed ESBWR design certification rule, would be regarded as outside the scope of the commenting opportunity with respect to the steam dryer analysis methodology.

The NRC notes that some of the documents listed in Tables 1 and 2 in Section I.A of the SUPPLEMENTARY INFORMATION section of this document contain SUNSI, SGI, or proprietary information and, therefore, are not publicly available. For each of those non-publicly available documents, GEH has created a publicly-available version of the document. If a commenter needs to review the material in a non-publicly available document in order to submit comments, the commenter should first review the publicly-available version of the document. If the commenter determines, after reviewing the publicly-available version, that access to the non-public document is needed in order to provide meaningful comments within the scope of comments as previously described, then the Start Printed Page 25722commenter should seek access to the non-public document in accordance with the procedures in Section X of the SUPPLEMENTARY INFORMATION section of this document.

Late-filed Comments

The NRC will not be obligated to address any comments received after June 5, 2014, nor will the NRC entertain any requests for extension of the public comment period unless the commenter is approved to access SUNSI or SGI as described in Section X of the SUPPLEMENTARY INFORMATION section of this document, because of the substantial delays in the ESBWR rulemaking. If a commenter is approved to access SUNSI or SGI, the public comment period will be extended exclusively for that commenter, but limited to the matters for which access to SUNSI or SGI is necessary to make informed comments.

II. Background

ESBWR Design Certification and March 2011 Proposed Rule

Subpart B of 10 CFR part 52 sets forth the process for obtaining standard design certifications. On August 24, 2005 (70 FR 56745; September 28, 2005), in accordance with subpart B of 10 CFR part 52, GEH submitted its application for certification of the ESBWR standard plant design to the NRC. The NRC formally accepted the application as a docketed application for design certification (Docket No. 52-010) on December 1, 2005 (70 FR 73311; December 9, 2005). The pre-application information submitted before the NRC formally accepted the application can be found in ADAMS under Docket No. PROJ0717 (Project No. 717).

The application for design certification of the ESBWR design has been referenced in the following combined license (COL) applications as of the date of this document: (1) Detroit Edison Company, Fermi Unit 3, Docket No. 52-033 (73 FR 73350; December 2, 2008); (2) Dominion Virginia Power, North Anna Unit 3, Docket No. 52-017 (73 FR 6528; February 4, 2008); (3) Entergy Operations, Inc., Grand Gulf Unit 3, Docket No. 52-024 (73 FR 22180; April 24, 2008) (APPLICATION SUSPENDED); (4) Entergy Operations, Inc., River Bend Unit 3, Docket No. 52-036 (73 FR 75141; December 10, 2008) (APPLICATION SUSPENDED); and (5) Exelon Nuclear Texas Holdings, LLC, Victoria County Station Units 1 and 2, Docket Nos. 52-31 and 52-032 (73 FR 66059; November 6, 2008) (APPLICATION WITHDRAWN).

On March 24, 2011 (76 FR 16549), the NRC published a proposed rule that would certify the ESBWR design in the Commission's regulations. The public comment period closed on June 7, 2011. The NRC received six comment submissions from members of the public. In addition, on September 9, 2011, the Commission issued a Memorandum and Order, CLI-11-05, 74 NRC 141, referring these comment submissions to the NRC staff for consideration as comments on the proposed ESBWR design certification rule. Id. at 176.

Issues on the Analytical Methodology for Design of the ESBWR Steam Dryer

Following the close of the public comment period on the proposed ESBWR design certification rule, the NRC staff identified issues applicable to the ESBWR steam dryer structural analysis. These issues were the result of NRC consideration of information obtained during the NRC's review of a license amendment request for a power uprate at an operating boiling-waterreactor (BWR) nuclear power plant. As this BWR power uprate used the same methodology for steam dryer analysis as was being proposed for the ESBWR, the NRC staff needed to resolve these issues before moving forward with the ESBWR design. The NRC informed GEH by letter dated January 19, 2012 (ADAMS Accession No. ML120170304), that it identified issues “relevant to the conclusions in its Final Safety Evaluation Report (FSER) [ADAMS Accession No. ML103070392] issued in support of the ESBWR [design certification] rulemaking. Specifically, errors have been identified in the benchmarking GEH used as a basis for determining fluctuating pressure loads on the steam dryer, and errors have been identified in a number of GEH's modeling parameters. These errors may affect the conclusions in the staff's FSER and need to be addressed before we complete the ESBWR [design certification].” Consequently, the NRC staff informed GEH that the rulemaking was on hold until the errors were adequately addressed.

In March 2012, the NRC staff conducted an audit of the GEH steam dryer analysis methodology at the GEH facility in Wilmington, North Carolina. In addition, in April 2012, the NRC staff performed a vendor inspection at that facility of the quality assurance program for GEH engineering methods. As a result of the audit and inspection, the NRC staff submitted requests for additional information (RAIs) to support a supplemental FSER. In addressing these RAIs, GEH made a number of significant changes in Revision 10 to the ESBWR DCD and in the supporting documentation. Those changes did not result in modifications to the overall design of the steam dryer but did result in replacing relevant sections in the DCD, withdrawing referenced licensing topical reports (LTRs) and replacing them with new engineering reports, designating the new engineering reports as Tier 2* information, and adding new Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC). References to publicly-available documents associated with the development of the supplemental FSER, including RAIs and responses, public meeting notices and summaries, etc., are listed in the NRC's supplemental FSER (ADAMS Accession No. ML14043A134). Because these changes to the ESBWR steam dryer description in the DCD and supporting documentation occurred after the close of the public comment opportunity on the proposed ESBWR design certification rule, the NRC is publishing this supplemental proposed rule to provide an opportunity for public comment on these changes.

The NRC notes that GEH made several other changes in Revision 10 to the ESBWR DCD which are not related to the ESBWR steam dryer analysis methodology. The NRC is not providing an opportunity for public comments on these other changes, and the NRC will explain in a final ESBWR design certification rule why these additional ESBWR DCD changes did not require a supplemental comment opportunity. The NRC will not be obligated to provide responses to any comments submitted in this supplemental comment opportunity which address matters unrelated to the changes to the ESBWR steam dryer analysis methodology.

III. Discussion

This section describes the changes that the NRC made to the proposed ESBWR design certification rule text and the changes GEH made to the analysis methodology supporting the ESBWR steam dryer design. A more detailed description of the changes to the analysis methodology and compliance with the NRC's regulations can be found in the NRC's supplemental FSER. This section also clarifies the NRC's intention that 50 non-public documents referenced in the ESBWR DCD are considered to be requirements and matters resolved under paragraph VI, ISSUE RESOLUTION, of the ESBWR design certification rule. This section also clarifies which documents would contain binding requirements for the ESBWR design and the NRC's intention Start Printed Page 25723to clarify in the final ESBWR design certification rule that these documents would be incorporated by reference.

A. ESBWR Steam Dryer Design

1. Correction of Information Related to the Steam Dryer Design

Following the issuance of the FSER for the ESBWR design certification on March 9, 2011, the NRC staff identified issues applicable to the ESBWR steam dryer structural analysis based on information obtained during the NRC's review of a license amendment request for a power uprate at an operating BWR nuclear power plant. Consequently, the NRC staff communicated to GEH that it was concerned that the basis for its FSER on the ESBWR DCD and the safety evaluation reports on these topical reports was no longer valid. Specifically, errors were identified in the benchmarking GEH used as a basis for determining fluctuating pressure loading on the steam dryer, and errors were identified in a number of GEH's modeling parameters. The NRC staff subsequently issued RAIs and held multiple public meetings to identify issues and clarify the steam dryer analysis methodology. The NRC staff also conducted an audit of the GEH steam dryer analysis methodology at the GEH facility in Wilmington, North Carolina, in March 2012, and a vendor inspection at that facility of the quality assurance program for GEH engineering methods in April 2012.

To document the resolution of those issues, GEH revised the ESBWR DCD by removing references to the LTRs which address the ESBWR steam dryer structural evaluation and to reference new engineering reports that describe the updated ESBWR steam dryer analysis methodology. The following four LTRs were removed by GEH (public and proprietary versions cited):

  • NEDE-33313 and NEDE-33313P, “ESBWR Steam Dryer Structural Evaluation,” all revisions;
  • NEDE-33312 and NEDE-33312P, “ESBWR Steam Dryer Acoustic Load Definition,” all revisions;
  • NEDC-33408 and NEDC-33408P, “ESBWR Steam Dryer-Plant Based Load Evaluation Methodology,” all revisions; and
  • NEDC-33408, Supplement 1, and NEDC-33408P, Supplement 1, “ESBWR Steam Dryer—Plant Based Load Evaluation Methodology Supplement 1,” all revisions.

To replace the information formerly provided by the four LTRs, GEH revised the ESBWR DCD to reference three new engineering reports (public and proprietary versions cited):

  • NEDO-33312 and NEDE-33312P, Rev. 5, December 2013, “ESBWR Steam Dryer Acoustic Load Definition;”
  • NEDO-33408 and NEDE-33408P, Rev. 5, December 2013, “ESBWR Steam Dryer—Plant Based Load Evaluation Methodology—PBLE01 Model Description;” and
  • NEDO-33313 and NEDE-33313P, Rev. 5, December 2013, “ESBWR Steam Dryer Structural Evaluation.”

The following DCD sections were revised by GEH to correct errors and provide additional information related to the design and evaluation of the structural integrity of the ESBWR reactors pressure vessel internals related to the steam dryer:

  • Tier 1, Chapter 2, Section 2.1, “Nuclear Steam Supply;”
  • Tier 1, Chapter 2, Section 2.1.1, “Reactor Pressure Vessel and Internals;”
  • Tier 2, Chapter 1, Tables 1.6-1, 1.9-21, and 1D-1;
  • Tier 2, Chapter 3, Section 3.9.2, “Dynamic Testing and Analysis of Systems, Components and Equipment;”
  • Tier 2, Chapter 3, Section 3.9.5, “Reactor Pressure Vessel Internals;”
  • Tier 2, Chapter 3, Section 3.9.9, “COL Information;”
  • Tier 2, Chapter 3, Section 3.9.10, “References;” and
  • Tier 2, Chapter 3, Appendix 3L, “Reactor Internals Flow Induced Vibration Program.”

The revisions to these documents enhance the detailed design and evaluation process related to the structural integrity of the steam dryer in several ways. For example, the source of data used to benchmark the analysis methodology was changed in Revision 10 to the ESBWR DCD to a different operating nuclear power plant for which the NRC recently authorized an extended power uprate. In addition, the details of the design methodology were made more restrictive in several respects, including limiting the analysis method for fillet welds and using more conservative data and assumptions. The changes also designate additional information as Tier 2* and clarify regulatory process steps for completing the detailed design and startup testing of the ESBWR steam dryer, including COL information items to be satisfied by a COL applicant, ITAAC to be met by a COL licensee, and model license conditions that can be proposed by a COL applicant. References to the relevant documents associated with the changes made to the steam dryer analysis methodology are listed in Section I.A of the SUPPLEMENTARY INFORMATION section of this document.

The NRC staff has reviewed the revised ESBWR DCD sections, new GEH engineering reports, and RAI responses and prepared a supplemental FSER. The supplemental FSER concludes that Revision 10 to the ESBWR DCD and the referenced engineering reports provide sufficient information to support the adequacy of the design basis for the ESBWR reactor internals. The supplemental FSER also concludes that the design process for reactor internals is acceptable and meets the requirements of 10 CFR part 50, appendix A, General Design Criteria 1, 2, 4, and 10; 10 CFR 50.55a; and 10 CFR part 52. Finally, the supplemental FSER concludes that the ESBWR design documentation in Revision 10 to the ESBWR DCD is acceptable and that GEH's application for design certification meets the requirements of 10 CFR part 52, subpart B, that are applicable and technically relevant to the ESBWR standard plant design. The NRC concludes, based on the review of application materials in the March 2011 FSER and the supplemental FSER, that the ESBWR steam dryer design meets all applicable NRC requirements and can be incorporated by reference in a combined license application.

This supplemental proposed rule provides an opportunity to comment on the proposed changes related to the analysis methodology supporting the ESBWR steam dryer design. Documents relevant to the proposed changes related to the analysis methodology supporting the ESBWR steam dryer design are listed in Table 1, Section I.A of the SUPPLEMENTARY INFORMATION section of this document. The NRC notes that three of these documents are also listed in Table 2. These three non-publicly available documents—addressing the ESBWR steam dryer analysis methodology—are intended by the NRC to be requirements and matters resolved under Paragraph VI, ISSUE RESOLUTION, of the proposed ESBWR design certification rule. The status of the non-public documents identified in Table 2 as requirements and matters resolved is discussed in Section III.B of the SUPPLEMENTARY INFORMATION section of this document.

2. Designation of Revised Steam Dryer Analysis Methodology as Tier 2*

The NRC proposes to designate the revised ESBWR steam dryer analysis methodology as Tier 2* information throughout the life of any license referencing the ESBWR design certification rule. This is a change from Revision 9 of the ESBWR DCD, which identified much of this information (in its earlier form before the revisions reflected in Revision 10) as Tier 2. Therefore, the ESBWR steam dryer Start Printed Page 25724analysis methodology was not identified as Tier 2* information in the proposed ESBWR design certification rule under paragraph VIII.B.6.b of appendix E of 10 CFR part 52. References to the DCD are listed in Table 1, Section I.A of the SUPPLEMENTARY INFORMATION section of this document.

In this supplemental proposed rule, the NRC is proposing to designate the revised ESBWR steam dryer analysis methodology as Tier 2* for two reasons. First, as described in Section III.A.1 of the SUPPLEMENTARY INFORMATION section of this document, the NRC's experience with other applications using this methodology highlighted the importance of the proper application of the steam dryer analysis methodology. Therefore, the NRC believes that it is necessary to review any changes a referencing applicant or licensee proposes to the methodology from that which the NRC previously reviewed and approved. Second, in Revision 10 of the ESBWR DCD, GEH revised the designation of this methodology to Tier 2* and, therefore, the rule's designation would be consistent with the GEH's designation in the DCD.

This supplemental proposed rule provides an opportunity to comment on the proposed designation as Tier 2* of certain information related to the analysis methodology supporting the ESBWR steam dryer design. Documents relevant to the proposed designation as Tier 2* of certain information related to the analysis methodology supporting the ESBWR steam dryer design are also listed in Table 1, Section I.A of the SUPPLEMENTARY INFORMATION section of this document.

B. Clarification of 50 Non-Public Documents Which the NRC Regards as Requirements and Are Matters Resolved Under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule

In Tier 2, Section 1.6 of Revision 9 of the ESBWR DCD, GEH stated that a number of referenced documents are incorporated by reference, in whole or in part, in the ESBWR DCD Tier 2. Accordingly, the NRC questioned whether these documents contain binding requirements and whether they should also be incorporated by reference in the ESBWR design certification rule. The NRC reviewed these document references and determined that, while many of these documents do contain binding requirements and should be incorporated by reference, some of those documents do not contain binding requirements and therefore should be considered as references only.

To address the NRC's concerns, GEH revised Section 1.6 of Revision 10 of the ESBWR DCD to clearly identify documents containing requirements, and which documents are references which do not contain binding requirements. Table 1.6-1 of the DCD lists the GE and GEH documents which the NRC regards as requirements for the ESBWR design, and are, therefore, incorporated by reference into the ESBWR DCD. Table 1.6-2 of the DCD lists the non-GE and non-GEH documents which the NRC regards as requirements for the ESBWR design, and are, therefore, incorporated by reference into the ESBWR DCD. The NRC notes that GEH's incorporation by reference of the documents in Tables 1.6-1 and 1.6-2 into the ESBWR DCD is not the same as the Director of the Office of the Federal Register's approval of incorporation by reference under 1 CFR part 51. Table 1.6-3 of the DCD lists information which is general reference material and which the NRC does not consider to be a requirement of the ESBWR design certification rule. The documents in Table 1.6-3 of the DCD are not incorporated by reference into the ESBWR DCD by GEH, and the NRC does not intend to obtain approval from the Director of the Office of the Federal Register for incorporation by reference of the documents in Table 1.6-3 of the DCD.

The NRC also notes that many of these documents containing requirements also contain either SUNSI (proprietary information, and security-related information subject to non-disclosure under 10 CFR 2.390(a)(7)(vi)) or SGI. For each of these documents containing SUNSI or SGI there is a corresponding, publicly-available version. In this supplemental proposed rule, the NRC is clarifying that the NRC intends the 50 non-public documents in Table 2 of Section I.A of the SUPPLEMENTARY INFORMATION section of this document to be both requirements and matters resolved under paragraph VI, ISSUE RESOLUTION, of the ESBWR design certification rule.

C. Clarification of 20 Publicly-Available Documents Which the NRC Regards As Requirements and Are Matters Resolved Under Paragraph VI, ISSUE RESOLUTION, of the ESBWR Design Certification Rule

In Section III of the proposed ESBWR design certification rule (proposed appendix E to 10 CFR part 52), the NRC proposed that Revision 9 of the ESBWR DCD be the sole document which would be incorporated by reference, as a binding requirement, into the Commission's regulations for the ESBWR design certification. However, as previously described, after the proposed rule was issued and the public comment period had expired, the NRC determined that 20 documents listed in Table 1.6-1 of Revision 9 to the ESBWR DCD, publicly available in their entirety, were regarded by the NRC as requirements and matters resolved under Paragraph VI, ISSUE RESOLUTION, of the proposed ESBWR design certification rule. However, the NRC did not clearly identify in proposed paragraph III.A of the proposed ESBWR design certification rule identifying these publicly-available documents as approved by the Director of the Office of the Federal Register for incorporation by reference. The NRC is clarifying that it intends to obtain approval for incorporation by reference from the Director of the Office of the Federal Register under 1 CFR 51.9 for the 20 documents listed in Table 3 of Section III.C of the SUPPLEMENTARY INFORMATION section of this document.

Table 3—20 Publicly-Available Documents to be Approved for Incorporation by Reference Into the ESBWR Design Certification Rule (10 CFR part 52, appendix E) by the Director of the Office of the Federal Register.

Document No.Document titleADAMS accession No.
BC-TOP-3-ABechtel, “Tornado and Extreme Wind Design Criteria for Nuclear Power Plants,” Topical Report BC-TOP-3-A, Revision 3, August 1974ML14093A218
BC-TOP-9ABechtel, “Design of Structures for Missile Impact,” Topical Report BC-TOP-9A, Revision 2, September 1974ML14093A217
GEZ-4982AGeneral Electric Large Steam Turbine Generator Quality Control Program, GEZ-4982A, Revision 1.2, February 7, 2006ML14093A215
Start Printed Page 25725
NEDO-11209-04AGE Nuclear Energy, “GE Nuclear Energy Quality Assurance Program Description,” Class I (Non-proprietary), NEDO-11209-04A, Revision 8, March 31, 1989ML14093A209
NEDO-31960-AGE Nuclear Energy, “BWR Owners' Group Long-Term Stability Solutions Licensing Methodology,” NEDO-31960-A, November 1995ML14093A212
NEDO-31960-A Supplement 1GE Nuclear Energy, “BWR Owners' Group Long-Term Stability Solutions Licensing Methodology,” NEDO-31960-A, Supplement 1, Class I (Non-proprietary), November 1995ML14093A211
NEDO-32465-AGE Nuclear Energy and BWR Owners' Group, “Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications,” NEDO-32465-A, Class I (Non-proprietary), August 1996ML14093A210
NEDO-33181GE Hitachi Nuclear Energy, “NP-2010 COL Demonstration Project Quality Assurance Program,” NEDO-33181, Revision 6, August 2009ML100110150
NEDO-33219GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Functional Requirements Analysis Implementation Plan,” NEDO-33219, Class I (Non-proprietary), Revision 4, February 2010ML100350104
NEDO-33260GE Hitachi Nuclear Energy, “Quality Assurance Requirements for Suppliers of Equipment and Services to the GEH ESBWR Project,” NEDO-33260, Revision 5, April 2008ML100110150
NEDO-33262GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Operating Experience Review Implementation Plan,” NEDO-33262, Class I (Non-proprietary), Revision 3, January 2010ML100340030
NEDO-33266GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Staffing and Qualifications Implementation Plan,” NEDO-33266, Class I (Non-proprietary), Revision 3, January 2010ML100350167
NEDO-33267GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Human Reliability Analysis Implementation Plan,” NEDO-33267, Class I (Non-proprietary), Revision 4, January 2010ML100330609
NEDO-33277GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Human Performance Monitoring Implementation Plan,” NEDO-33277, Class I (Non-proprietary), Revision 4, January 2010ML100270770
NEDO-33278GE Hitachi Nuclear Energy, “ESBWR Human Factors Engineering Design Implementation Plan,” NEDO-33278, Class I (Non-proprietary), Revision 4, January 2010ML100270468
NEDO-33289GE Hitachi Nuclear Energy, “ESBWR Reliability Assurance Program,” NEDO-33289, Class I (Non-proprietary), Revision 2, September 2008ML100110150
NEDO-33337GE Hitachi Nuclear Energy, “ESBWR Initial Core Transient Analyses,” NEDO-33337, Class I (Non-proprietary), Revision 1, April 2009ML091130628
NEDO-33338GE Hitachi Nuclear Energy, “ESBWR Feedwater Temperature Operating Domain Transient and Accident Analysis,” NEDO-33338, Class I (Non-proprietary), Revision 1, May 2009ML091380173
NEDO-33373-AGE-Hitachi Nuclear Energy, “Dynamic, Load-Drop, and Thermal-Hydraulic Analyses for ESBWR Fuel Racks,” NEDO-33373-A, Revision 5, Class I (Non-proprietary), October 2010ML102990226  (part 1) ML102990228  (part 2)
NEDO-33411GE Hitachi Nuclear Energy, “Risk Significance of Structures, Systems and Components for the Design Phase of the ESBWR,” NEDO-33411, Class I (Non-proprietary), Revision 2, February 2010ML100610417

The NRC would obtain approval from the Director of the Office of the Federal Register for incorporation by reference of these documents before the NRC issues a final rule for the ESBWR design certification. Consistent with the Office of the Federal Register's requirements, the NRC would, in the final rule, correct paragraph III.A of appendix E to 10 CFR part 52 by identifying in a table all of the publicly-available documents which are approved for incorporation by reference by the Director of the Office of the Federal Register. Therefore, these documents would be regarded as legally-binding requirements by virtue of publication in the Federal Register of the Director of the Office of the Federal Register's approval of incorporation by reference.

The NRC is not requesting public comment in this supplemental proposed rule on the additional documents (i.e., those other than as described in Section I of the SUPPLEMENTARY INFORMATION section of this document) that would be incorporated by reference in this rulemaking. The NRC will explain in a final ESBWR design certification rule why the changes to paragraph III.A, reflecting the Director of the Office of the Federal Register's approval for incorporation by reference of these 20 additional documents, did not require a supplemental comment opportunity.

IV. Section-by-Section Analysis

The following section-by-section analysis discusses two proposed revisions to the NRC's regulations that were not part of the proposed ESBWR design certification rule published on March 24, 2011 (76 FR 16549), which address the changes related to the analysis methodology supporting the ESBWR steam dryer design that were made after the close of the public comment period for the proposed Start Printed Page 25726ESBWR design certification rule. No section-by-section analysis is provided for the NRC's proposed clarification of its intent to treat 50 referenced documents within the ESBWR DCD as requirements and matters resolved in subsequent licensing and enforcement actions for plants referencing the ESBWR design certification. This is because the NRC's proposed clarification does not require any change to the revision to the language of the proposed ESBWR design certification rule which was previously published for public comment, other than the revision of the ESBWR DCD from Revision 9 to Revision 10, which includes clarifying changes in Section 1.6 of the ESBWR DCD (described in Section III.B of the SUPPLEMENTARY INFORMATION section of this document).

Appendix E, Paragraph III.A

This paragraph identifies the version of the ESBWR DCD which is approved for incorporation by reference by the Director of the Office of the Federal Register, and therefore is considered to be a legally-binding regulation by virtue of the rulemaking process. In this supplemental proposed rule, the NRC proposes to revise this paragraph to update the generic DCD revision number from Revision 9 to 10, provide the ADAMS accession number for Revision 10 of the DCD, and update the name and address of the GEH contact from whom a member of the public could obtain copies of the generic DCD. In addition, editorial changes were made in this paragraph to improve clarity.

Appendix E, Paragraph VIII.B.6.b

This paragraph identifies Tier 2* information which retains that status throughout the duration of a license referencing the ESBWR design certification rule. In this supplemental proposed rule, the NRC proposes to add the ESBWR steam dryer analysis methodology to paragraph VIII.B.6.b.(8). As a result, this methodology would be designated as Tier 2* and that status would continue throughout the duration of a license referencing this appendix. A licensee referencing this appendix would be subject to the change controls as specified in paragraph VIII.B.6.b with respect to the ESBWR steam dryer analysis methodology.

V. Plain Writing

The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal agencies to write documents in a clear, concise, and well-organized manner. The NRC has written this document to be consistent with the Plain Writing Act as well as the Presidential Memorandum, “Plain Language in Government Writing,” published June 10, 1998 (63 FR 31883). The NRC requests comment on the supplemental proposed rule with respect to the clarity and effectiveness of the language used.

VI. Environmental Impact: Finding of No Significant Environmental Impact: Availability

In the proposed ESBWR design certification rule published on March 24, 2011, the NRC made available for public comment a draft Environmental Assessment (ADAMS Accession No. ML102220247) for the ESBWR design addressing various design alternatives to prevent and mitigate severe accidents. This supplemental proposed rule does not materially change the ESBWR design nor does it affect the NRC's prior evaluation of design alternatives to prevent and mitigate severe accidents. Therefore, the NRC has not prepared a supplemental environmental assessment for this supplemental proposed rule, nor is the NRC seeking additional public comment on the environmental assessment already prepared to support the proposed ESBWR design certification rule.

VII. Paperwork Reduction Act

The proposed ESBWR design certification rule, published on March 24, 2011, contains new or amended information collection requirements that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq) (PRA). The proposed rule was submitted to the Office of Management and Budget (OMB) for review and approval of the information collection requirements under clearance number 3150-0151. Public comments regarding the information collection requirements were requested in conjunction with the proposed rule.

This supplemental proposed rule does not contain any new or amended information collection requirements not already identified in the March 24, 2011, proposed rule and, therefore, is not subject to the requirements of the PRA. As a result, the supplemental proposed rule will not be submitted to OMB for approval. Further, the NRC is not seeking further public comment on the potential impact of the information collections contained in or the issues outlined in the PRA section of the ESBWR design certification proposed rule.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.

VIII. Regulatory Analysis

The NRC has not prepared a regulatory analysis for this supplemental proposed rule. As discussed in the proposed ESBWR design certification rule, the NRC does not prepare regulatory analyses for design certification rulemakings. This supplemental proposed rule does not materially change the regulatory nature of this design certification rulemaking. Accordingly, the Commission concludes that preparation of a regulatory analysis for this supplemental proposed rule to certify the ESBWR standard plant design is neither required nor appropriate.

IX. Backfitting and Issue Finality

The NRC has determined that this supplemental proposed rule does not constitute backfitting as defined in the backfit rule under 10 CFR 50.109, nor is it inconsistent with any of the finality provisions for design certifications under 10 CFR 52.63. This design certification does not impose new or changed requirements on existing 10 CFR part 50 licensees, nor does it impose new or changed requirements on existing design certification rules in appendices A through D to 10 CFR part 52. Therefore, a backfit analysis was not prepared for this supplemental proposed rule.

X. Procedures for Access to Sensitive Unclassified Non-Safeguards Information (Including Proprietary Information) and Safeguards Information for Preparation of Comments on the Supplemental Proposed ESBWR Design Certification Rule

This section contains instructions regarding how interested persons who wish to comment on the proposed design certification, with respect to any of the 50 non-publicly available documents (including the three documents addressing the analysis methodology supporting the ESBWR steam dryer design), may request access to those documents in order to prepare their comments within the scope of this supplemental proposed rule. These documents, which are listed in Table 2 of Section I.A of the SUPPLEMENTARY INFORMATION section of this document, contain SUNSI (including proprietary information [2] and security-related Start Printed Page 25727information [3] ) and, in one case, SGI. Requirements for access to SGI are primarily set forth in 10 CFR parts 2 and 73. This document provides information specific to this supplemental proposed rule; however, nothing in this document is intended to conflict with the SGI regulations.

Interested persons who desire access to SUNSI information on the ESBWR design constituting proprietary information should first request access to that information from GEH, the design certification applicant. A request for access should be submitted to the NRC if the applicant does not either grant or deny access by the 10-day deadline described in the following section.

One of the 50 non-publicly available documents in Table 2, NEDE-33536P, contains proprietary information and security-related information. Another of the non-publicly available documents in Table 2, NEDE-33391, contains proprietary information, security-related information, and SGI. If you need access to proprietary information in one or both of these two documents in order to develop comments within the scope of this supplemental proposed rule, then your request for access should first be submitted to GEH in accordance with the previous paragraph. By contrast, if you need access to the security-related information and/or SGI in one or both of those documents in order to provide comments within the scope of this supplemental proposed rule, then your request for access to the security-related information and/or SGI must be submitted to the NRC as described further in this section. Therefore, if you need access to proprietary information as well as security-related information and/or SGI in one or both of those documents, then you should pursue access to the information in separate requests submitted to GEH and the NRC.

Submitting a Request to the NRC for Access

Within 10 days after publication of this supplemental proposed rule, any individual or entity who, in order to submit comments on the supplemental proposed ESBWR design certification rule, believes access to information in this rulemaking docket that the NRC has categorized as SUNSI or SGI is necessary may request access to such information. Requests for access to SUNSI or SGI submitted more than 10 days after publication of this document will not be considered absent a showing of good cause for the late filing explaining why the request could not have been filed earlier.

The individual or entity requesting access to the information (hereinafter, the “requester”) shall submit a letter requesting permission to access SUNSI and/or SGI to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Attention: Rulemakings and Adjudications Staff, Washington, DC 20555-0001. The expedited delivery or courier mail address is: Office of the Secretary, U.S. Nuclear Regulatory Commission, Attention: Rulemakings and Adjudications Staff, 11555 Rockville Pike, Rockville, Maryland 20852. The email address for the Office of the Secretary is rulemaking.comments@nrc.gov. The requester must send a copy of the request to the design certification applicant at the same time as the original transmission to the NRC using the same method of transmission. Requests to the applicant must be sent to Jerald G. Head, Senior Vice President, Regulatory Affairs, GE-Hitachi Nuclear Energy, 3901 Castle Hayne Road, MC A-18, Wilmington, North Carolina 28401, email: jerald.head@ge.com. For purposes of complying with this requirement, a “request” includes all the information required to be submitted to the NRC as set forth in this section.

The request must include the following information:

1. The name of this design certification, ESBWR Design Certification; the rulemaking identification number, RIN 3150-AI85; the rulemaking docket number, NRC-2010-0135; and a Federal Register citation to this supplemental proposed rule at the top of the first page of the request.

2. The name, address, email or FAX number of the requester. If the requester is an entity, the name of the individual(s) to whom access is to be provided, then the address and email or FAX number for each individual, and a statement of the authority granted by the entity to each individual to review the information and to prepare comments on behalf of the entity must be provided. If the requester is relying upon another individual to evaluate the requested SUNSI and/or SGI and prepare comments, then the name, affiliation, address and email or FAX number for that individual must be provided.

3.a. If the request is for SUNSI, the requester's need for the information in order to prepare meaningful comments on the supplemental proposed design certification must be demonstrated. Each of the following areas must be addressed with specificity:

i. The specific issue or subject matter on which the requester wishes to comment;

ii. An explanation why information which is publicly available, including the publicly-available versions of the application and design control document, and information on the NRC's docket for the design certification application is insufficient to provide the basis for developing meaningful comment on the supplemental proposed ESBWR design certification rule with respect to the issue or subject matter described in paragraph 3.a.i. of this section; and

iii. Information demonstrating that the individual to whom access is to be provided has the technical competence (demonstrable knowledge, skill, experience, education, training, or certification) to understand and use (or evaluate) the requested information for a meaningful comment on the supplemental proposed ESBWR design certification rule with respect to the issue or subject matter described in paragraph 3.a.i. of this section.

b. If the request is for SUNSI constituting proprietary information, then a chronology and discussion of the requester's attempts to obtain the information from the design certification applicant, and the final communication from the requester to the applicant and the applicant's response with respect to the request for access to proprietary information must be submitted.

4. Based on an evaluation of the information submitted under paragraph 3 of this section, the NRC staff will determine within 10 days of receipt of the written access request whether the requester has established a legitimate need for SUNSI access.

4.a. If the request is for SGI, then the requester's “need to know” the SGI as required by 10 CFR 73.2 and 10 CFR 73.22(b)(1) must be demonstrated. Consistent with the definition of “need to know” as stated in 10 CFR 73.2 and 10 CFR 73.22(b)(1), each of the following areas must be addressed with specificity:

i. The specific issue or subject matter on which the requester wishes to comment;

ii. An explanation why information which is publicly available, including the publicly-available versions of the application and design control document, and information on the NRC's docket for the design certification Start Printed Page 25728application is insufficient to provide the basis for developing meaningful comment on the proposed design certification with respect to the issue or subject matter described in paragraph 4.a.i. of this section, and that the SGI requested is indispensable in order to develop meaningful comments; [4] and

iii. Information demonstrating that the individual to whom access is to be provided has the technical competence (demonstrable knowledge, skill, experience, education, training, or certification) to understand and use (or evaluate) the requested SGI, in order to develop meaningful comments on the proposed design certification with respect to the issue or subject matter described in paragraph 4.a.i. of this section.

b. A completed Form SF-85, “Questionnaire for Non-Sensitive Positions,” must be submitted for each individual who would have access to SGI. The completed Form SF-85 will be used by the NRC's Office of Administration to conduct the background check required for access to SGI, as required by 10 CFR part 2, subpart G, and 10 CFR 73.22(b)(2) to determine the requester's trustworthiness and reliability. For security reasons, Form SF-85 can only be submitted electronically through the electronic Questionnaire for Investigations Processing (e-QIP) Web site, a secure Web site that is owned and operated by the Office of Personnel Management. To obtain online access to the form, the requester should contact the NRC's Office of Administration at 301-415-7000.[5]

c. A completed Form FD-258 (fingerprint card), signed in original ink, and submitted under 10 CFR 73.57(d). Copies of Form FD-258 may be obtained by writing the Office of Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; by calling 301-415-3710 or 301-492-7311; or by email to Forms.Resource@nrc.gov. The fingerprint card will be used to satisfy the requirements of 10 CFR part 2, 10 CFR 73.22(b)(1), and Section 149 of the Atomic Energy Act of 1954, as amended, which mandates that all persons with access to SGI must be fingerprinted for a Federal Bureau of Investigation identification and criminal history records check;

d. A check or money order in the amount of $238.00 [6] payable to the U.S. Nuclear Regulatory Commission for each individual for whom the request for access has been submitted; and

e. If the requester or any individual who will have access to SGI believes they belong to one or more of the categories of individuals relieved from the criminal history records check and background check requirements, as stated in 10 CFR 73.59, the requester should also provide a statement specifically stating which relief the requester is invoking, and explaining the requester's basis (including supporting documentation) for believing that the relief is applicable. While processing the request, the NRC's Office of Administration, Personnel Security Branch, will make a final determination whether the stated relief applies. Alternatively, the requester may contact the Office of Administration for an evaluation of their status prior to submitting the request. Persons who are not subject to the background check are not required to complete the SF-85 or Form FD-258; however, all other requirements for access to SGI, including the need to know, are still applicable.

Copies of documents and materials required by paragraphs 4.b., 4.c., 4.d., and 4.e., as applicable, of this section must be sent to the following address: Office of Administration, U.S. Nuclear Regulatory Commission, Personnel Security Branch, Mail Stop TWF-03B46M, Washington, DC 20555-0012.

These documents and materials should not be included with the request letter to the Office of the Secretary, but the request letter should state that the forms and fees have been submitted as required.

5. To avoid delays in processing requests for access to SGI, all forms should be reviewed for completeness and accuracy (including legibility) before submitting them to the NRC. The NRC will return incomplete or illegible packages to the sender without processing.

6. Based on an evaluation of the information submitted under paragraphs 3.a. and 3.b., or 4.a., 4.b., 4.c., and 4.e. of this section, as applicable, the NRC staff will determine within 10 days of receipt of the written access request whether the requester has established a legitimate need for SUNSI access or need to know the SGI requested.

7. For SUNSI access requests, if the NRC staff determines that the requester has established a legitimate need for access to SUNSI, the NRC staff will notify the requester in writing that access to SUNSI has been granted; provided, however, that if the SUNSI consists of proprietary information (i.e., trade secrets or confidential or financial information), the NRC staff must first notify the applicant of the NRC staff's determination to grant access to the requester not less than 10 days before informing the requester of the NRC staff's decision. If the applicant wishes to challenge the NRC staff's determination, it must follow the procedures in paragraph 12 of this section. The NRC staff will not provide the requester access to disputed proprietary information until the procedures in paragraph 12 of this section are completed.

The written notification to the requester will contain instructions on how the requester may obtain copies of the requested documents, and any other conditions that may apply to access to those documents. These conditions will include, but are not necessarily limited to, the signing of a protective order setting forth terms and conditions to prevent the unauthorized or inadvertent disclosure of SUNSI by each individual who will be granted access to SUNSI. Claims that the provisions of such a protective order have not been complied with may be filed by calling the NRC's toll-free safety hotline at 1-800-695-7403. Please note: Calls to this number are not recorded between the hours of 7:00 a.m. to 5:00 p.m. Eastern Time. However, calls received outside these hours are answered by the NRC's Incident Response Operations Center on a recorded line. Claims may also be filed via email sent to NRO_Allegations@nrc.gov, or may be sent in writing to the U.S. Nuclear Regulatory Commission, ATTN: Timothy Frye, Mail Stop T7-D24, Washington, DC 20555-0001.

8. For requests for access to SGI, if the NRC staff determines that the requester has established a need to know the SGI, the NRC's Office of Administration will then determine, based upon completion of the background check, whether the proposed recipient is trustworthy and reliable, as required for access to SGI by 10 CFR 73.22(b). If the NRC's Office of Administration determines that the individual or individuals are trustworthy and reliable, the NRC will promptly notify the requester in writing. Start Printed Page 25729The notification will provide the names of approved individuals as well as the conditions under which the SGI will be provided. Those conditions will include, but are not necessarily limited to, the signing of a protective order by each individual who will be granted access to SGI. Claims that the provisions of such a protective order have not been complied with may be filed by calling the NRC's toll-free safety hotline at 800-695-7403. Please note: Calls to this number are not recorded between the hours of 7:00 a.m. to 5:00 p.m. Eastern Time. However, calls received outside these hours are answered by the NRC's Incident Response Operations Center on a recorded line. Claims may also be filed via email sent to NRO_Allegations@nrc.gov, or may be sent in writing to the U.S. Nuclear Regulatory Commission, ATTN: Timothy Frye, Mail Stop T7-D24, Washington, DC 20555-0001. Because SGI requires special handling, initial filings with the NRC should be free from such specific information. If necessary, the NRC will arrange an appropriate setting for transmitting SGI to the NRC.

9. Release and Storage of SGI. Prior to providing SGI to the requester, the NRC staff will conduct (as necessary) an inspection to confirm that the recipient's information protection system is sufficient to satisfy the requirements of 10 CFR 73.22. Alternatively, recipients may opt to view SGI at an approved SGI storage location rather than establish their own SGI protection program to meet SGI protection requirements.

10. Filing of Comments on the Supplemental Proposed ESBWR Design Certification Rule. Any comments in this rulemaking proceeding that are based upon the disclosed SUNSI or SGI information must be filed by the requester no later than 25 days after receipt of (or access to) that information, or the close of the public comment period, whichever is later. The commenter must comply with all NRC requirements regarding the submission of SUNSI and SGI to the NRC when submitting comments to the NRC (including marking and transmission requirements).

11. Review of Denials of Access.

a. If the request for access to SUNSI or SGI is denied by the NRC staff, the NRC staff shall promptly notify the requester in writing, briefly stating the reason or reasons for the denial.

b. Before the NRC's Office of Administration makes an adverse determination regarding the trustworthiness and reliability of the proposed recipient(s) of SGI, the NRC's Office of Administration, as specified by 10 CFR 2.705(c)(3)(iii), must provide the proposed recipient(s) any records that were considered in the trustworthiness and reliability determination, including those required to be provided under 10 CFR 73.57(e)(1), so that the proposed recipient is provided an opportunity to correct or explain information.

c. Appeals from a denial of access must be made to the NRC's Executive Director for Operations (EDO) under 10 CFR 9.29. The decision of the EDO constitutes final agency action under 10 CFR 9.29(d).

12. Predisclosure Procedures for SUNSI Constituting Trade Secrets or Confidential Commercial or Financial Information. The NRC will follow the procedures in 10 CFR 9.28 if the NRC staff determines, under paragraph 7 of this section, that access to SUNSI constituting trade secrets or confidential commercial or financial information will be provided to the requester. However, any objection filed by the applicant under 10 CFR 9.28(b) must be filed within 15 days of the NRC staff notice in paragraph 7 of this section rather than the 30-day period provided for under that paragraph. In applying the provisions of 10 CFR 9.28, the applicant for the design certification rule will be treated as the “submitter.”

XI. Availability of Documents

The documents related to the ESBWR steam dryer analysis methodology for which the NRC is seeking public comment are listed in Table 1, Section 1.A of the SUPPLEMENTARY INFORMTION section of this document. The documents which the NRC regards as requirements and are matters resolved under Paragraph VI, ISSUE RESOLUTION, of the ESBWR design certification rule, and for which the NRC is seeking public comment on the NRC's proposed clarification of its intent to treat these non-public documents as requirements and matters resolved, are listed in Table 2, Section 1.A of the SUPPLEMENTARY INFORMATION section of this document.

The documents to be treated by the NRC as requirements in the final ESBWR design certification rule, but the NRC is not seeking public comment, are listed in Table 3, Section III.C of the SUPPLEMENTARY INFORMATION section of this document. Additional documents relevant to the proposed ESBWR design certification rule, for which an opportunity for public comment was provided in the proposed ESBWR design certification rule (76 FR 16549; March 24, 2011), are listed in Table 4. These documents have not changed since the publication of the proposed ESBWR design certification rule for public comment. The NRC is not seeking public comment on these documents in this supplemental proposed rule; they are listed in Table 4 for the benefit of the reader.

Table 4—Documents Relevant to the ESBWR Design Certification Rule, for Which an Opportunity for Public Comment Was Provided in the ESBWR Proposed Rule

Document No.Document titlePublicly available ADAMS accession No.Non-publicly available ADAMS accession No.
Proposed Rule Documents
SRM-SECY-11-0006Staff Requirements Memorandum for SECY-11-0006, “Staff Requirements—SECY-11-0006—Proposed Rule—Economic Simplified Boiling-Water Reactor Design Certification,” dated March 8, 2011ML110670047N/A
SECY-11-0006SECY-11-0006, “Proposed Rule-Economic Simplified Boiling-Water Reactor Design Certification,” dated January 7, 2011ML102220172N/A
Proposed Rule Federal Register NoticeFederal Register Notice—Proposed Rule—ESBWR Design CertificationML102220215N/A
Proposed Rule Environmental AssessmentDraft Environmental Assessment—Proposed Rule—ESBWR Design CertificationML102220247N/A
Start Printed Page 25730
Final Safety Evaluation ReportESBWR Final Safety Evaluation Report, dated March 9, 2011ML103070392 (package)N/A
Start List of Subjects

List of Subjects in 10 CFR Part 52

  • Administrative practice and procedure
  • Antitrust
  • Backfitting
  • Combined license
  • Early site permit
  • Emergency planning
  • Fees
  • Inspection
  • Limited work authorization
  • Nuclear power plants and reactors
  • Probabilistic risk assessment
  • Prototype
  • Reactor siting criteria
  • Redress of site
  • Reporting and recordkeeping requirements
  • Standard design
  • Standard design certification
  • Incorporation by reference
End List of Subjects

For the reasons set out in the preamble and under the authority of the Atomic Energy Act of 1954, as amended; the Energy Reorganization Act of 1974, as amended; and 5 U.S.C. 552 and 553, the NRC is proposing to adopt the following amendments to 10 CFR Part 52.

Start Part

PART 52—LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS

End Part Start Amendment Part

1. The authority citation for 10 CFR part 52 continues to read as follows:

End Amendment Part Start Authority

Authority: Atomic Energy Act secs. 103, 104, 147, 149, 161, 181, 182, 183, 185, 186, 189, 223, 234 (42 U.S.C. 2133, 2201, 2167, 2169, 2232, 2233, 2235, 2236, 2239, 2282); Energy Reorganization Act secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Government Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L. 109-58, 119 Stat. 594 (2005).

End Authority Start Amendment Part

2. In appendix E to 10 CFR part 52, as proposed to be added March 24, 2011 (76 FR 16549):

End Amendment Part Start Amendment Part

A. Revise paragraph III.A.

End Amendment Part Start Amendment Part

B. Add new paragraph VIII.B.6.b.(8).

End Amendment Part

The revision and addition read as follows:

Appendix E to Part 52—Design Certification Rule for the ESBWR Design.

* * * * *

III. Scope and Contents

A. Incorporation by reference approval. All Tier 1, Tier 2 (including the availability controls in Appendix 19ACM), and the generic TS in the ESBWR DCD, Revision 10, dated April 2014, “ESBWR Design Control Document,” are approved for incorporation by reference by the Director of the Office of the Federal Register under 5 U.S.C. 552(a) and 1 CFR part 51. You may obtain copies of the generic DCD from Jerald G. Head, Senior Vice President, Regulatory Affairs, GE-Hitachi Nuclear Energy, 3901 Castle Hayne Road, MC A-18, Wilmington, NC 28401, telephone: 1-910-819-5692. You can view the generic DCD online in the NRC Library at http://www.nrc.gov/​reading-rm/​adams.html. In ADAMS, search under ADAMS Accession No. ML14104A929. If you do not have access to ADAMS or if you have problems accessing documents located in ADAMS, contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 1-301-415-3747, or by email at PDR.Resource@nrc.gov. The generic DCD can also be viewed at the Federal rulemaking Web site, http://www.regulations.gov, by searching for documents filed under Docket ID NRC-2010-0135. A copy of the DCD is available for examination and copying at the NRC's PDR located at Room O-1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. A copy also is available for examination at the NRC Library located at Two White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852, telephone: 301-415-5610, email: Library.Resource@nrc.gov. All approved material is available for inspection at the National Archives and Records Administration (NARA). For information on the availability of this material at NARA, call 1-202-741-6030 or go to http://www.archives.gov/​federal-register/​cfr/​ibrlocations.html.

* * * * *

VIII. * * *

B. * * *

6. * * *

b. * * *

(8) Steam dryer pressure load analysis methodology.

* * * * *
Start Signature

Dated at Rockville, Maryland, this 23rd day of April, 2014.

For the Nuclear Regulatory Commission.

Mark A. Satorius,

Executive Director for Operations.

End Signature End Supplemental Information

Footnotes

1.  For purposes of this discussion, “proprietary information” constitutes trade secrets or commercial or financial information that are privileged or confidential, as those terms are used under the Freedom of Information Act and the NRC's implementing regulation at part 9 of Title 10 of the Code of Federal Regulations.

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2.  For purposes of this discussion, “proprietary information” constitutes trade secrets or commercial or financial information that are privileged or confidential, as those terms are used under the Freedom of Information Act and the NRC's implementing regulation at 10 CFR part 9.

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3.  For purposes of this discussion, “security-related information” means information subject to non-disclosure under 10 CFR 2.390(a)(7)(vi).

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4.  Broad SGI requests under these procedures are unlikely to meet the standard for need to know. Furthermore, NRC staff redaction of information from requested documents before their release may be appropriate to comport with this requirement. The procedures in this notice of proposed rulemaking do not authorize unrestricted disclosure or less scrutiny of a requester's need to know than ordinarily would be applied in connection with either adjudicatory or non-adjudicatory access to SGI.

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5.  The requester will be asked to provide his or her full name, social security number, date and place of birth, telephone number, and email address. After providing this information, the requester usually should be able to obtain access to the online form within one business day.

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6.  This fee is subject to change pursuant to the Office of Personnel Management's adjustable billing rates.

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[FR Doc. 2014-10246 Filed 5-5-14; 8:45 am]

BILLING CODE 7590-01-P