ML071860407
| ML071860407 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/20/2007 |
| From: | Maurice Heath NRC/NRR/ADRO/DLR/RLRA |
| To: | Duncan R Carolina Power & Light Co |
| Heath, M, NRR/DLR/RLRA, 415-3137 | |
| References | |
| Download: ML071860407 (8) | |
Text
July 20, 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 10 CFR 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 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
ML071860407 OFFICE PM:RLRA:DLR LA:DLR BC:RLRA:DLR NAME MHeath IKing LLund DATE 07/20/07 07/10/07 07/20/07
Enclosure SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION (RAIs)
RAI-B.2.17 (A) The applicant states that the surveillance capsule that is to be withdrawn during the 16th refueling outage would have been exposed to a neutron fluence value that is equivalent to the peak reactor pressure vessel (RPV) fluence at 55 effective full power year (EFPY). Please confirm this statement. The staff requests that the applicant provide the following information related to this test:
(1) Lead factor of the surveillance capsule (2) Identification number of the capsule, and (3) Heat number of the surveillance material in the capsule (B) Program element 6, item 2 of aging management program (AMP) B.2.17 states that the applicant intends to test one surveillance capsule after the 16th refueling outage. The staff requests that the applicant submit the following information that pertains to the test:
(1) The projected refueling outage of withdrawal (2) Projected capsule neutron fluence value at the time of withdrawal (3) Corresponding EFPY for the peak RPV fluence to equal the capsule fluence (4) The identification number of the capsule, and (5) Heat number of the surveillance material in the capsule (C) The staff requests that the applicant confirm that the withdrawal schedule of the final two capsules for the extended period of operation is consistent with the requirements, specifically the limitations on lead factor, specified in paragraph 7.6.2 of the American Society of Testing Materials E 185 (ASTM E 185), Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels.
(D) Section 5.3.1.6 of the final safety analysis report states that the applicant intends to use two standby capsules with identifications Y and Z for future tests. However, the operating experience Section of AMP B.2.17 indicates that three capsules will remain in the RPV for future tests to manage neutron embrittlement during the extended period of operation. The staff requests that the applicant provide an explanation for this inconsistency.
(E) The staff requests that the applicant include the following statements in the commitment table of the license renewal application (LRA):
(1) The applicant will notify the staff if there is any change in the withdrawal schedules of the surveillance capsules.
(2) If a standby capsule is removed from the RPV without the intent to test it, the capsule will be stored in manner which maintains it in a condition which would permit its future use, including during the period of extended operation, if necessary.
RAI-4.2.3 (Editorial Correction)
In Tables 4.2-2 and 4.2-3 of the LRA, the chemical composition values of elements Copper and Nickel for the surveillance capsule test sample representing the intermediate shell plate (heat number-B4197-2) and the RPVs intermediate shell plate (heat number-B4197-2) are identical.
However, the chemistry factors are different. The staff requests that the applicant add a footnote stating that the chemistry factor for the surveillance capsule test sample representing the intermediate shell plate is derived from the surveillance test data.
RAI-4.2.4 The staff requests that the applicant include the following items in Section 4.2.4 of the LRA:
(A) The current pressure-temperature (P-T) limits are valid through 36 EFPY. The P-T limits for the extended period of operation will be managed by using approved fluence calculations when there are changes in power of core design in conjunction with surveillance capsule results.
(B) Any change in P-T curves will be implemented by the license amendment process (i.e., modifications of technical specifications) and will meet the requirements of Title 10 of the Code of Federal Regulations Section 50.60 (10 CFR 50.60) and 10 CFR Part 50, Appendix G.
RAI-4.2.5 Since the P-T limits for the extended period of operation are not yet developed, the applicant should make a statement in the LRA that they will submit the appropriate analysis for the low temperature overpressure (LTOP) setpoints that will be valid for the license renewal period.
Any change in the LTOP setpoints will be implemented by the license amendment process (i.e.,
modifications of technical specifications) and will meet the requirements of 10 CFR 50.60 and 10 CFR Part 50, Appendix G.
RAI-4.2.6 During the audit at the Harris Nuclear Plant, the staff was informed by the applicant that one reactor vessel nozzle was projected to achieve a neutron fluence greater than 1 x 1017 n/cm2 (E > 1 MeV) at the end of the extended period of operation. This nozzle material was not listed in Tables 4.2-1, 4.2-2 and 4.2-3 of the LRA. According to Table 1V A-2 of NUREG-1801, Revision 1, ferritic materials are subject to neutron embrittlement when they are exposed to neutron fluence greater than 1 x 1017 n/cm2 (E > 1 MeV) at the end of the extended period of operation. Therefore, the staff requests that the applicant provide the following for this nozzle material and its associated welds:
(1) The RTPTS value of the nozzle material and its associated welds per the requirements of Title 10 of the Code of Federal Regulations (CFR) Section 50.61.
(2) The adjusted reference temperature value of the nozzle material and its associated welds that will be used for developing pressure-temperature limits per the requirements of 10 CFR Part 50, Appendix G.
(3) The upper shelf energy value of the nozzle material and its associated welds per the requirements of 10 CFR Part 50, Appendix G.
Letter to R. J. Duncan II from M. Heath dated July 20, 2007 DISTRIBUTION:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATION HARD COPY DLR R/F E-MAIL:
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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 Ms. Julie Keys Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-2708