ML060950620
| ML060950620 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| 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:
|
| References | |
| %dam200611, TAC MC9668 | |
| Download: ML060950620 (10) | |
Text
AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________
LRA AMP: __________________________ REVIEWER: ______________________
GALL AMP: XI.M31, Reactor Vessel Surveillance DATE: __________________________
Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The Code of Federal Regulations, 10 CFR Part 50, Appendix Consistent with GALL AMP: Yes No Element H, requires that peak neutron fluence at the end of the design Document(s) used to confirm Criteria:
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 Comment:
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 If surveillance capsules are not withdrawn during the period of extended operation, operating restrictions are to be established to ensure that the plant is operated under the conditions to which the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 XI.M31 Reactor Vessel Surveillance 1
Program Auditable GALL Criteria Documentation of Audit Finding Element 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 Consistent with GALL AMP: Yes No energy and pressure-temperature limits for 60 years is projected Document(s) used to confirm Criteria:
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. Comment:
- 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.
C. An applicant that determines embrittlement by using the NRC Consistent with GALL AMP: Yes No RG 1.99, Rev. 2, tables (see item 1[a], above) uses the Document(s) used to confirm Criteria:
applicable limitations in Regulatory Position 1.3 of the RG. The limits are based on material properties, temperature, material XI.M31 Reactor Vessel Surveillance 2
Program Auditable GALL Criteria Documentation of Audit Finding Element chemistry, and fluence.
Comment:
D. An applicant that determines embrittlement by using Consistent with GALL AMP: Yes No surveillance data (see item 1[b], above) defines the applicable Document(s) used to confirm Criteria:
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 Comment:
RG.
E. All pulled and tested capsules, unless discarded before Consistent with GALL AMP: Yes No August 31, 2000, are placed in storage. (Note: These Document(s) used to confirm Criteria:
specimens are saved for future reconstitution use, in case the surveillance program is reestablished.)
Comment:
F. If an applicant has a surveillance program that consists of Consistent with GALL AMP: Yes No capsules with a projected fluence of less than the 60-year Document(s) used to confirm Criteria:
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 Comment:
extended operation to monitor the effects of long-term exposure to neutron irradiation.
G. If an applicant has a surveillance program that consists of Consistent with GALL AMP: Yes No capsules with a projected fluence exceeding the 60-year fluence Document(s) used to confirm Criteria:
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 Comment:
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 XI.M31 Reactor Vessel Surveillance 3
Program Auditable GALL Criteria Documentation of Audit Finding Element 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 Consistent with GALL AMP: Yes No dosimetry to monitor neutron fluence during the period of Document(s) used to confirm Criteria:
extended operation, as part of the aging management program (AMP) for reactor vessel neutron embrittlement.
Comment:
I. The applicant may choose to demonstrate that the materials in Consistent with GALL AMP: Yes No the inlet, outlet, and safety injection nozzles are not controlling, Document(s) used to confirm Criteria:
so that such materials need not be added to the material surveillance program for the license renewal term.
Comment:
J. The reactor vessel monitoring program provides that, if future Consistent with GALL AMP: Yes No XI.M31 Reactor Vessel Surveillance 4
Program Auditable GALL Criteria Documentation of Audit Finding Element plant operations exceed the limitations or bounds specified in Document(s) used to confirm Criteria:
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 Comment:
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.
- 1. Scope of A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Program for more information. Document(s) used to confirm Criteria:
Comment
- 2. Preventive A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Actions for more information. Document(s) used to confirm Criteria:
Comment:
XI.M31 Reactor Vessel Surveillance 5
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 3. Parameters A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Monitored/ for more information. Document(s) used to confirm Criteria:
Inspected Comment:
- 4. Detection of A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Aging Effects for more information. Document(s) used to confirm Criteria:
Comment:
- 5. Monitoring A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No and Trending for more information. Document(s) used to confirm Criteria:
Comment:
- 6. Acceptance A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Criteria for more information. Document(s) used to confirm Criteria:
Comment:
- 7. Corrective A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Actions for more information. Document(s) used to confirm Criteria:
Comment:
XI.M31 Reactor Vessel Surveillance 6
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 8. A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Confirmation for more information. Document(s) used to confirm Criteria:
Process Comment:
- 9. A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Administrative for more information. Document(s) used to confirm Criteria:
Controls Comment:
- 10. Operating A. See the GALL Report, XI.M31, Reactor Vessel Surveillance, Consistent with GALL AMP: Yes No Experience for more information. Document(s) used to confirm Criteria:
Comment:
XI.M31 Reactor Vessel Surveillance 7
EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #)
1.
2.
ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #)
1.
2.
DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1.
2.
3.
4.
XI.M31 Reactor Vessel Surveillance 8