ML060950620
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XI.M31 Reactor Vessel Surveillance 1
AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________
LRA AMP: __________________________
REVIEWER: ______________________
GALL AMP: XI.M31, Reactor Vessel Surveillance DATE: __________________________
Program Element Auditable GALL Criteria Documentation of Audit Finding Program Element A. The Code of Federal Regulations, 10 CFR Part 50, Appendix H, requires that peak neutron fluence at the end of the design life of the vessel will not exceed 1017 n/cm2 (E >1MeV), or that reactor vessel beltline materials be monitored by a surveillance program to meet the American Society for Testing and Materials (ASTM) E 185 Standard. However, the surveillance program in ASTM E 185 is based on plant operation during the current license term, and additional surveillance capsules may be needed for the period of extended operation. Alternatively, an integrated surveillance program for the period of extended operation may be considered for a set of reactors that have similar design and operating features in accordance with 10 CFR Part 50, Appendix H, Paragraph II.C. Additional surveillance capsules may also be needed for the period of extended operation for this alternative.
The existing reactor vessel material surveillance program provides sufficient material data and dosimetry to monitor irradiation embrittlement at the end of the period of extended operation, and to determine the need for operating restrictions on the inlet temperature, neutron spectrum, and neutron flux. If surveillance capsules are not withdrawn during the period of extended operation, operating restrictions are to be established to ensure that the plant is operated under the conditions to which the surveillance capsules were exposed.
All capsules in the reactor vessel that are removed and tested Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
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Program Element Auditable GALL Criteria Documentation of Audit Finding must meet the test procedures and reporting requirements of ASTM E 185-82, to the extent practicable, for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation. Untested capsules placed in storage must be maintained for future insertion.
An acceptable reactor vessel surveillance program consists of the following.
B. The extent of reactor vessel embrittlement for upper-shelf energy and pressure-temperature limits for 60 years is projected in accordance with the NRC Regulatory Guide (RG) 1.99, Rev. 2, Radiation Embrittlement of Reactor Vessel Materials.
When using NRC RG 1.99, Rev. 2, an applicant has a choice of the following.
- a. Neutron Embrittlement Using Chemistry Tables An applicant may use the tables in NRC RG 1.99, Rev. 2, to project the extent of reactor vessel neutron embrittlement for the period of extended operation based on material chemistry and neutron fluence. This is described as Regulatory Position 1 in the RG.
- b. Neutron Embrittlement Using Surveillance Data When credible surveillance data is available, the extent of reactor vessel neutron embrittlement for the period of extended operation may be projected according to Regulatory Position 2 in NRC RG 1.99, Rev. 2, based on best fit of the surveillance data. The credible data could be collected during the current operating term. The applicant may have a plant-specific program or an integrated surveillance program during the period of extended operation to collect additional data.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
C. An applicant that determines embrittlement by using the NRC RG 1.99, Rev. 2, tables (see item 1[a], above) uses the applicable limitations in Regulatory Position 1.3 of the RG. The limits are based on material properties, temperature, material Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
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Program Element Auditable GALL Criteria Documentation of Audit Finding chemistry, and fluence.
Comment:
D. An applicant that determines embrittlement by using surveillance data (see item 1[b], above) defines the applicable bounds of the data, such as cold leg operating temperature and neutron fluence. These bounds are specific for the referenced surveillance data. For example, the plant-specific data could be collected within a smaller temperature range than that in the RG.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
E. All pulled and tested capsules, unless discarded before August 31, 2000, are placed in storage. (Note: These specimens are saved for future reconstitution use, in case the surveillance program is reestablished.)
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
F. If an applicant has a surveillance program that consists of capsules with a projected fluence of less than the 60-year fluence at the end of 40 years, at least one capsule is to remain in the reactor vessel and is tested during the period of extended operation. The applicant may either delay withdrawal of the last capsule or withdraw a standby capsule during the period of extended operation to monitor the effects of long-term exposure to neutron irradiation.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
G. If an applicant has a surveillance program that consists of capsules with a projected fluence exceeding the 60-year fluence at the end of 40 years, the applicant withdraws one capsule at an outage in which the capsule receives a neutron fluence equivalent to the 60-year fluence and tests the capsule in accordance with the requirements of ASTM E 185. Any capsules that are left in the reactor vessel provide meaningful metallurgical data (i.e., the capsule fluence does not significantly exceed the vessel fluence at an equivalent of 60 years). For example, in a reactor with a lead factor of three, after 20 years the capsule test specimens would have received Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
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Program Element Auditable GALL Criteria Documentation of Audit Finding a neutron exposure equivalent to what the reactor vessel would see in 60 years; thus, the capsule is to be removed because further exposure would not provide meaningful metallurgical data. Other standby capsules are removed and placed in storage. These standby capsules (and archived test specimens available for reconstitution) would be available for reinsertion into the reactor if additional license renewals are sought (e.g.,
80 years of operation). If all surveillance capsules have been removed, operating restrictions are to be established to ensure that the plant is operated under conditions to which the surveillance capsules were exposed. The exposure conditions of the reactor vessel are monitored to ensure that they continue to be consistent with those used to project the effects of embrittlement to the end of license. If the reactor vessel exposure conditions (neutron flux, spectrum, irradiation temperature, etc.) are altered, then the basis for the projection to 60 years is reviewed; and, if deemed appropriate, an active surveillance program is re-instituted. Any changes to the reactor vessel exposure conditions and the potential need to re-institute a vessel surveillance program is discussed with the NRC staff prior to changing the plant's licensing basis.
H. Applicants without in-vessel capsules use alternative dosimetry to monitor neutron fluence during the period of extended operation, as part of the aging management program (AMP) for reactor vessel neutron embrittlement.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
I. The applicant may choose to demonstrate that the materials in the inlet, outlet, and safety injection nozzles are not controlling, so that such materials need not be added to the material surveillance program for the license renewal term.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
J. The reactor vessel monitoring program provides that, if future Consistent with GALL AMP:
Yes No
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Program Element Auditable GALL Criteria Documentation of Audit Finding plant operations exceed the limitations or bounds specified in item 2 or 3, above (as applicable), such as operating at a lower cold leg temperature or higher fluence, the impact of plant operation changes on the extent of reactor vessel embrittlement will be evaluated and the NRC will be notified. An applicant without capsules in its reactor vessel is to propose reestablishing the reactor vessel surveillance program to assess the extent of embrittlement. This program will consist of (1) capsules from item 6, above; (2) reconstitution of specimens from item 4, above; and/or (3) capsules made from any available archival materials; or (4) some combination of the three previous options. This program could be a plant-specific program or an integrated surveillance program.
Reactor vessel surveillance program is plant-specific, depending on matters such as the composition of limiting materials, availability of surveillance capsules, and projected fluence levels. In accordance with 10 CFR Part 50, Appendix H, an applicant submits its proposed withdrawal schedule for approval prior to implementation. Thus, further staff evaluation is required for license renewal.
Document(s) used to confirm Criteria:
Comment:
- 1. Scope of Program A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment
- 2. Preventive Actions A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
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Program Element Auditable GALL Criteria Documentation of Audit Finding
- 3. Parameters Monitored/
Inspected A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
- 4. Detection of Aging Effects A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
- 5. Monitoring and Trending A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
- 6. Acceptance Criteria A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
- 7. Corrective Actions A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
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Program Element Auditable GALL Criteria Documentation of Audit Finding
- 8.
Confirmation Process A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
- 9.
Administrative Controls A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
- 10. Operating Experience A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, for more information.
Consistent with GALL AMP:
Yes No Document(s) used to confirm Criteria:
Comment:
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EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #)
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ENHANCEMENTS Item Number Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed (Identifier, Para.# and/or Page #)
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DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number)
Title Revision and/or Date
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