ML071590147
| ML071590147 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/11/2007 |
| From: | Maurice Heath NRC/NRR/ADRO/DLR/RLRA |
| To: | Duncan R Carolina Power & Light Co |
| Heath, M, NRR/DLR/RLRA, 415-3137 | |
| References | |
| Download: ML071590147 (7) | |
Text
June 11, 2007 Mr. Robert J. Duncan II Vice President Carolina Power & Light Company P.O. Box 165, Mail Zone 1 New Hill, NC 27562
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATION
Dear Mr. Duncan:
By letter dated November 14, 2006, Carolina Power & Light Company submitted an application pursuant to Title 10 Code of Federal Regulations Part 54, to renew the operating license for Shearon Harris Nuclear Power Plant, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Roger Stewart, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3137 or via e-mail mlh5@nrc.gov.
Sincerely,
/RA/
Maurice Heath, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Requests for Additional Information cc w/encl: See next page
ML071590147 Document Name: C:\\FileNet\\ML071590147.wpd OFFICE PM:RLRA:DLR LA:DLR BC:RLRA:DLR NAME MHeath IKing YDiaz-Sanabria for LLund DATE 06/11/07 06/11/07 06/11/07
letter to R. Duncan, from M. Heath, dated June 11, 2007
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY DLR R/F E-MAIL:
PUBLIC SSmith (srs3)
SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes MHeath SHernandez CPatel CColleli RKWild JStorch RidsOpaMail RidsOcaMailCenter
Shearon Harris Nuclear Power Plant, Unit 1 cc:
David T. Conley Associate General Counsel II -
Legal Department Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, NC 27602-1551 Resident Inspector / Harris NPS c/o U. S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, NC 27562-9998 Ms. Margaret A. Force Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, NC 27602 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, SC 29211 Ms. Beverly Hall, Section Chief Division of Radiation Protection N.C. Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721 Mr. J. Paul Fulford, Manager Performance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company Post Office Box 1551 Raleigh, NC 27602-1551 Mr. Eric McCartney Plant General Manager Shearon Harris Nuclear Power Plant Carolina Power & Light Company P. O. Box 165, Mail Zone 3 New Hill, NC 27562-0165 Mr. Chris L. Burton Director of Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, Mail Zone 1 New Hill, NC 27562-0165 Mr. Robert P. Gruber Executive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326 Chairman of the North Carolina Utilities Commission P. O. Box 29510 Raleigh, NC 27626-0510 Mr. Herb Council, Chair Board of County Commissioners of Wake County P. O. Box 550 Raleigh, NC 27602 Mr. Tommy Emerson, Chair Board of County Commissioners of Chatham County P. O. Box 87 Pittsboro, NC 27312 Mr. Thomas J. Natale, Manager Support Services Carolina Power & Light Company Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 1 New Hill, NC 27562-0165 Mr. David H. Corlett, Supervisor Licensing/Regulatory Programs Shearon Harris Nuclear Power Plant Carolina Power & Light Company P. O. Box 165, Mail Zone 1 New Hill, NC 27562-0165
Shearon Harris Nuclear Power Plant, Unit 1 cc: Mr. John H. ONeill, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037-1128 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-2708
Enclosure SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION (RAI)
RAI 2.1-1 Nonsafety-Related Affecting Safety-Related (10 CFR 54.4(a)(2)
The applicants methodology for scoping of nonsafety-related (NSR) components affecting safety related (SR) components is briefly described in license renewal application (LRA) Section 2.1.1.2 and states the following:
Shearon Harris Nuclear Power Plant (HNP) final safety analysis report (FSAR) Section 3.7.3.13 discusses the interaction of other piping with Seismic Category I piping. The following quotes are from that discussion: In the case of non-Seismic Category I piping systems attached to Seismic Category I piping systems, the dynamic effects were included in the modeling of the Seismic Category I piping up to the first anchor or system of restraints which decouples the piping and it should be noted that all seismic/non-seismic interface restraints are located in seismically analyzed structures thereby assuring that collapse of the restraint structure will not occur. Therefore, NSR systems relied upon to provide seismic support for SR structure, system, and components (SSCs) were evaluated using the following rationale.
- SR piping is in the scope of license renewal per Title 10 Code of Federal Regulations (10 CFR) 54.4(a)(1).
- SR piping is located in Seismic Category I structures at HNP.
- Therefore, the NSR/SR boundary is located in a Seismic Category I structure.
- All piping systems in Seismic Category I structures are in the scope of license renewal as discussed with respect to spatial interactions above.
Thus, it follows that NSR, seismically-connected piping is in the scope of license renewal and enveloped by the HNP scoping methodology.
Based on a review of the LRA, the applicant's scoping and screening implementation procedures, and discussions with the applicant, the NRC staff determined that additional information is required with respect to certain aspects of the applicant's evaluation of the 10 CFR 54.4(a)(2) criteria. The staff requests the applicant to provide the following information:
- The staff requests that the applicant provide the basis and further discussion to support the determination that all NSR piping systems attached to SR SSCs contain a seismic anchor at a location beyond the nonsafety/safety interface and prior to NSR piping exiting the structure, and that by extending the in-scope portion of the NSR piping system to the room boundary, there is assurance that an acceptable license renewal 10 CFR 54.4(a)(2) bounding point has been encompassed.
- Discuss the methods used to identify the specific seismic anchors for the attached NSR piping systems and the methods used to ensure that there are no exceptions to this determination.
RAI 3.0-1 Quality Assurance Program Attributes Appendix B, Aging Management Programs The NRC staff reviewed the applicants aging management programs (AMPs) in Appendix B, Aging Management Programs, of the LRA. In addition, the NRC staff reviewed each individual AMP basis document to ensure consistency in the use of the quality assurance attributes for each program. The purpose of this review was to assure that the aging management activities were consistent with the staffs guidance described in NUREG-1800, Section A.2, Quality Assurance for Aging Management Programs (Branch Technical Position IQMB-1).
Based on the NRC staffs evaluation, the descriptions and applicability of the plant-specific AMPs and their associated quality attributes provided in Appendix B, Section B.1.3, of the LRA, were determined to be generally consistent with the staffs position regarding quality assurance for aging management. However, AMP program description B2.8 contained in Appendix B, discusses Exceptions to NUREG 1801, and indicates that corrective actions is an area to which an exception is being taken. However, there is no indication or description of the use of an alternative method to the 10 CFR Part 50, Appendix B quality assurance program being applied to the area of corrective action.
The NRC staff, therefore, requests that the applicant provide the following information to address the following:
- For AMPs, as described in Appendix B of the LRA, which take exceptions in the area of corrective action, confirmation process, or administrative controls, indicate whether the exceptions include an alternative to the application of the 10 CFR Part 50, Appendix B quality assurance program as described in Section B.1.3.
If alternative approaches are identified, provide a description of sufficient detail such that the staff can determine if the quality attributes for the AMPs are consistent with the review acceptance criteria contained in NUREG-1800, Section A.2, Quality Assurance for Aging Management Programs (Branch Technical Position IQMB-1).