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Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events; Correction

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Information about this document as published in the Federal Register.

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AGENCY:

Nuclear Regulatory Commission.

ACTION:

Final rule; correction.

SUMMARY:

This document corrects a rule that appeared in the Federal Register on January 4, 2010 (75 FR 13), that amends the NRC's regulations to provide alternate fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) pressure vessels. This document is necessary to correct formatting and typographical errors in paragraph (g).

DATES:

The correction is effective February 3, 2010, the date the original rule becomes effective.

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FOR FURTHER INFORMATION CONTACT:

Michael T. Lesar, Chief, Rulemaking and Directives Branch, Office of Administration, Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone 301-492-3663, e-mail Michael.Lesar@nrc.gov.

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SUPPLEMENTARY INFORMATION:

In FR doc. E9-31146, published on January 4, 2010, make the following correction:

[Corrected]
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1. On page 27, paragraph (g) of § 50.61a is corrected to read as follows:

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(g) Equations and variables used in this section.

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where:

P [wt-&%] = phosphorus content

Mn [wt-%] = manganese content

Ni [wt-%] = nickel content

Cu [wt-%] = copper content

A = 1.140 × 10−7 for forgings

A = 1.451 × 10−7 for plates

A = 1.417 × 10−7 for welds

B = 102.3 for forgings

B = 102.5 for plates in non-Combustion Engineering manufactured vessels

B = 135.2 for plates in Combustion Engineering vessels

B = 155.0 for welds

φte = φt for φ ≥ 4.39 × 1010 n/cm2/sec

φte = φt × (4.39 × 1010/φ)0.2595 for φ < 4.39 × 1010 n/cm2/sec

where:

φ [n/cm2/sec] = average neutron flux

t [sec] = time that the reactor has been in full power operation

φt [n/cm2] = φ × t

f(Cue,P) = 0 for Cu ≤ 0.072

f(Cue,P) = [Cue−0.072]0.668 for Cu > 0.072 and P ≤ 0.008

f(Cue,P) = [Cue−0.072 + 1.359 × (P−0.008)]0.668 for Cu > 0.072 and P > 0.008

where:

Cue = 0 for Cu ≤ 0.072

Cue = MIN (Cu, maximum Cue) for Cu > 0.072

maximum Cue = 0.243 for Linde 80 welds

maximum Cue = 0.301 for all other materials

g(Cue,Ni,φte) = 0.5 + (0.5 × tanh {[log10 (φte) + (1.1390 × Cue)−(0.448 × Ni)−18.120]/0.629}

Equation 8: Residual (r) = measured ΔT30−predicted ΔT30 (by Equations 5, 6 and 7)

Equation 10: Maximum credible heat-average residual = 2.33σ/n0.5

where:

where:

n = number of surveillance data points (sample size) in the specific data set

σ = standard deviation of the residuals about the model for a relevant material group given in Table 5.

where:

m is the slope of a plot of all of the r values (estimated using Equation 8) versus the base 10 logarithm of the neutron fluence for each r value. The slope shall be estimated using the method of least squares.

se(m) is the least squares estimate of the standard-error associated with the estimated slope value m.

where:

r is defined using Equation 8 and σ is given in Table 5

Table 1—PTS Screening Criteria

Product form and RTMAX-X valuesRTMAX-X limits [°F] for different vessel wall thicknesses 6 (TWALL)
TWALL ≤ 9.5 in.9.5 in. < TWALL ≤ 10.5 in.10.5 in. < TWALL ≤ 11.5 in.
Axial Weld—RTMAX-AW269230222
Plate—RTMAX-PL356305293
Forging without underclad cracks—RTMAX-FO 7356305293
Axial Weld and Plate—RTMAX-AW + RTMAX-PL538476445
Circumferential Weld—RTMAX-CW8312277269
Forging with underclad cracks—RTMAX-FO9246241239
6 Wall thickness is the beltline wall thickness including the clad thickness.
7 Forgings without underclad cracks apply to forgings for which no underclad cracks have been detected and that were fabricated in accordance with Regulatory Guide 1.43.
8 RTPTS limits contribute 1×10−8 per reactor year to the reactor vessel TWCF.Start Printed Page 5497
9 Forgings with underclad cracks apply to forgings that have detected underclad cracking or were not fabricated in accordance with Regulatory Guide 1.43.

Table 2—Allowable Number of Flaws in Welds

Through-wall extent, TWE [in.]Maximum number of flaws per 1,000-inches of weld length in the inspection volume that are greater than or equal to TWEMIN and less than TWEMAX
TWEMINTWEMAX
00.075No Limit.
0.0750.475166.70.
0.1250.47590.80.
0.1750.47522.82.
0.2250.4758.66.
0.2750.4754.01.
0.3250.4753.01.
0.3750.4751.49.
0.4250.4751.00.
0.475Infinite0.00.

Table 3—Allowable Number of Flaws in Plates and Forgings

Through-wall extent, TWE [in.]Maximum number of flaws per 1,000 square-inches of inside surface area in the inspection volume that are greater than or equal to TWEMIN and less than TWEMAX. This flaw density does not include underclad cracks in forgings
TWEMINTWEMAX
00.075No Limit.
0.0750.3758.05.
0.1250.3753.15.
0.1750.3750.85.
0.2250.3750.29.
0.2750.3750.08.
0.3250.3750.01.
0.375Infinite0.00.

Table 4—Conservative Estimates for Chemical Element Weight Percentages

MaterialsPMn
Plates0.0141.45
Forgings0.0161.11
Welds0.0191.63

Table 5—Maximum Heat-Average Residual [°F] for Relevant Material Groups by Number of Available Data Points (Significance Level = 1%)

Material groupσ [°F]Number of available data points
345678
Welds, for Cu > 0.07226.435.530.827.525.123.221.7
Plates, for Cu > 0.07221.228.524.722.120.218.717.5
Forgings, for Cu > 0.07219.626.422.820.418.617.316.1
Weld, Plate or Forging, for Cu ≤ 0.07218.625.021.719.417.716.415.3

Table 6—TMAX Values for the Slope Deviation Test (Significance Level = 1%)

Number of available data points (n)TMAX
331.82
46.96
54.54
63.75
73.36
83.14
93.00
102.90
112.82
122.76
132.72
142.68
152.65
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Dated at Rockville, Maryland, this 29th day of January 2010.

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For the Nuclear Regulatory Commission.

Michael T. Lesar,

Chief, Rulemaking and Directives Branch, Division of Administrative Services, Office of Administration.

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[FR Doc. 2010-2283 Filed 2-2-10; 8:45 am]

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