ML060950218

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GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (Audit Worksheet, GALL Report AMP)
ML060950218
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 03/22/2006
From: Morgan M
NRC/NRR/ADRO/DLR/RLRC
To:
Office of Nuclear Reactor Regulation
morgan M NRR/NRC/DLR/RLRC, 415-2232
Shared Package
ML060950189 List: ... further results
References
%dam200611, TAC MC9668
Download: ML060950218 (6)


Text

X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 1

AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________

LRA AMP: __________________________

REVIEWER: ______________________

GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary DATE: __________________________

Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. In order not to exceed the design limit on fatigue usage, the aging management program (AMP) monitors and tracks the number of critical thermal and pressure transients for the selected reactor coolant system components. The AMP addresses the effects of the coolant environment on component fatigue life by assessing the impact of the reactor coolant environment on a sample of critical components for the plant.

Examples of critical components are identified in NUREG/CR-6260. The sample of critical components can be evaluated by applying environmental life correction factors to the existing ASME Code fatigue analyses. Formulae for calculating the environmental life correction factors are contained in NUREG/CR-6583 for carbon and low-alloy steels and in NUREG/CR-5704 for austenitic stainless steels. As evaluated below, this is an acceptable option for managing metal fatigue for the reactor coolant pressure boundary, considering environmental effects. Thus, no further evaluation is recommended for license renewal if the applicant selects this option under 10 CFR 54.21(c)(1)(iii) to evaluate metal fatigue for the reactor coolant pressure boundary Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

1. Scope of Program A. The program includes preventive measures to mitigate fatigue cracking of metal components of the reactor coolant pressure boundary caused by anticipated cyclic strains in the material.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 2

Program Element Auditable GALL Criteria Documentation of Audit Finding Comment

2. Preventive Actions A. Maintaining the fatigue usage factor below the design code limit and considering the effect of the reactor water environment, as described under the program description, will provide adequate margin against fatigue cracking of reactor coolant system components due to anticipated cyclic strains.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

3. Parameters Monitored/

Inspected A. The program monitors all plant transients that cause cyclic strains, which are significant contributors to the fatigue usage factor. The number of plant transients that cause significant fatigue usage for each critical reactor coolant pressure boundary component is to be monitored. Alternatively, more detailed local monitoring of the plant transient may be used to compute the actual fatigue usage for each transient.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

4. Detection of Aging Effects A. The program provides for periodic update of the fatigue usage calculations.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

5. Monitoring and Trending A. This program monitors a sample of high fatigue usage locations. This sample is to include the locations in NUREG/CR-6260, as a minimum, or to propose alternatives based on plant location.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 3

Program Element Auditable GALL Criteria Documentation of Audit Finding

6. Acceptance Criteria A. The acceptance criteria involves maintaining the fatigue usage below the design code limit considering environmental fatigue effects as described under the program description.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

7. Corrective Actions A. The program provides for corrective actions to prevent the usage factor from exceeding the design code limit during the period of extended operation. Acceptable corrective actions include repair of the component, replacement of the component, and a more rigorous analysis of the component to demonstrate that the design code limit will not be exceeded during the extended period of operation.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

A. For programs that monitor a sample of high fatigue usage locations, corrective actions include a review of additional affected reactor coolant pressure boundary locations. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the corrective actions.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

8.

Confirmation Process A. Site quality assurance procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of Appendix B to 10 CFR Part

50. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process and administrative controls.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

9.

Administrative Controls A. Site quality assurance procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of Appendix B to 10 CFR Part

50. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process and administrative controls.

Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

Comment:

10. Operating Experience A. The program reviews industry experience regarding fatigue cracking. Applicable experience with fatigue cracking is to be Consistent with GALL AMP:

Yes No Document(s) used to confirm Criteria:

X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 4

Program Element Auditable GALL Criteria Documentation of Audit Finding considered in selecting the monitored locations.

Comment:

X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 5

EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #)

1.
2.

ENHANCEMENTS Item Number Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed (Identifier, Para.# and/or Page #)

1.
2.

DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number)

Title Revision and/or Date

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4.

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