ML051250309

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Results of the Severe Accident Mitigation Alternative (SAMA) Review for Arkansas Nuclear One, Unit 2
ML051250309
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/04/2005
From: Kuo P
NRC/NRR/DRIP/RLEP
To: Berkow H
NRC/NRR/DLPM/LPD4
Williamson A, RLEP/DRIP/NRR, 415-1878
Shared Package
ML051250317 List:
References
NUREG/BR-0184
Download: ML051250309 (3)


Text

May 4, 2005 MEMORANDUM TO: Hebert Berkow, Project Director Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Pao-Tsin Kuo, Program Director /RA/

License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation

SUBJECT:

RESULTS OF THE SEVERE ACCIDENT MITIGATION ALTERNATIVE (SAMA) REVIEW FOR ARKANSAS NUCLEAR ONE, UNIT 2 The staff has recently completed its final writing session and published the Environmental Impact Statement (EIS) for Arkansas Nuclear One, Unit 2 (ANO-2) to support Entergys license renewal application. Using the guidance in NUREG/BR-0184, the staff concluded two of the SAMAs (AC/DC-16 and CW-06) are cost-beneficial, while two additional SAMAs (CW-27 and CC-20) are within a factor of two of being cost-beneficial. The two cost beneficial SAMAs involve procedural changes to emphasize steps in plant recovery following station black out (AC/DC-16) and procedural changes to increase time before reactor coolant pump seal failure during loss of service water sequences (CW-06). The two SAMAs within a factor of two of being cost-beneficial involve the installation of backwash filters to existing service water system strainers (CW-27) and replacing a containment sump valve (2CV-5649-1 or 2CV-5650-2) with an air-operated valve (CC-20).

As a result of this review, the staff concluded that further evaluation of these SAMAs by Entergy may be warranted. However, the SAMAs do not relate to adequately managing the effects of aging during the period of extended operation, and therefore, will not be pursued further under the license renewal program for ANO-2 pursuant to 10 CFR Part 54. Therefore, I am forwarding the results of this evaluation to you so that you may further consider the results of the review, and determine whether it should be further evaluated under current operating plant analysis programs.

The staffs review of SAMAs for ANO-2 is discussed in Chapter 5 and Appendix G of the final Supplement 19 to NUREG-1437, ?Generic Environmental Impact Statement for License Renewal of Nuclear Plants, pertaining to ANO-2. Enclosed is a copy of this document. If you have any questions concerning this matter, please contact the Senior Environmental Project Manager for the ANO-2 License Renewal Project, Mr. Thomas J. Kenyon at 301-415-1120 or by email at TJK@nrc.gov.

Docket No.: 50-368

Attachment:

As stated

May 4, 2005 MEMORANDUM TO: Hebert Berkow, Project Director Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Pao-Tsin Kuo, Program Director /RA/

License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation

SUBJECT:

RESULTS OF THE SEVERE ACCIDENT MITIGATION ALTERNATIVE (SAMA) REVIEW FOR ARKANSAS NUCLEAR ONE, UNIT 2 The staff has recently completed its final writing session and published the Environmental Impact Statement (EIS) for Arkansas Nuclear One, Unit 2 (ANO-2) to support Entergys license renewal application. Using the guidance in NUREG/BR-0184, the staff concluded two of the SAMAs (AC/DC-16 and CW-06) are cost-beneficial, while two additional SAMAs (CW-27 and CC-20) are within a factor of two of being cost-beneficial. The two cost beneficial SAMAs involve procedural changes to emphasize steps in plant recovery following station black out (AC/DC-16) and procedural changes to increase time before reactor coolant pump seal failure during loss of service water sequences (CW-06). The two SAMAs within a factor of two of being cost-beneficial involve the installation of backwash filters to existing service water system strainers (CW-27) and replacing a containment sump valve (2CV-5649-1 or 2CV-5650-2) with an air-operated valve (CC-20).

As a result of this review, the staff concluded that further evaluation of these SAMAs by Entergy may be warranted. However, the SAMAs do not relate to adequately managing the effects of aging during the period of extended operation, and therefore, will not be pursued further under the license renewal program for ANO-2 pursuant to 10 CFR Part 54. Therefore, I am forwarding the results of this evaluation to you so that you may further consider the results of the review, and determine whether it should be further evaluated under current operating plant analysis programs.

The staffs review of SAMAs for ANO-2 is discussed in Chapter 5 and Appendix G of the final Supplement 19 to NUREG-1437, ?Generic Environmental Impact Statement for License Renewal of Nuclear Plants, pertaining to ANO-2. Enclosed is a copy of this document. If you have any questions concerning this matter, please contact the Senior Environmental Project Manager for the ANO-2 License Renewal Project, Mr. Thomas J. Kenyon at 301-415-1120 or by email at TJK@nrc.gov.

Distribution: See next page Adams accession nos.:

Docket No.: 50-368 1. Memo to H. Berkow, ML051250309

Attachment:

As stated 2. Nureg-1437, Suppl. 19, Generic Environmental Impact Statement for License Renewal of Nuclear Plant, ANO-2 Final: ML051080538

3. Pkg: ML051250317 Document name: E:\Filenet\ML051250309.wpd OFFICE RLEP:GS RLEP:LA RLEP:PM RLEP:SC RLEP:PD NAME AWilliamson MJenkins TKenyon AKugler PTKuo DATE 04/28/05 05/4/05 05/3/05 05/4/05 05/4/05 OFFICIAL RECORD COPY

DISTRIBUTION: SAMA Memo to: H. Berkow, Re: ANO-2 FSEIS Dated: May 4, 2005 Accession No: Pkg: ML051250317 PTKuo AKugler TKenyon AWilliamson GSuber DHolland RPalla KLeigh (PNNL)

Dneitzel (PNNL)

RLEP R/F Mtschiltz