ML071860407

Requests for Additional Information for the Review of the Shearon Harris Nuclear Power Plant, Unit 1, License Renewal Application

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, 2007Mr. Robert J. Duncan IIVice 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 THESHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATION

Dear Mr. Duncan:

By letter dated November 14, 2006, Carolina Power & Light Company submitted an applicationpursuant 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 mutuallyagreeable 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 ManagerLicense Renewal Branch A Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-400

Enclosure:

Requests for Additional Informationcc w/encl: See next page

ML071860407OFFICEPM:RLRA:DLRLA:DLRBC:RLRA:DLRNAMEMHeathIKingLLund DATE07/20/0707/10/0707/20/07 EnclosureSHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1LICENSE RENEWAL APPLICATIONREQUESTS FOR ADDITIONAL INFORMATION (RAIs)RAI-B.2.17(A) The applicant states that the surveillance capsule that is to be withdrawn during the 16 threfueling outage would have been exposed to a neutron fluence value that is equivalent to thepeak reactor pressure vessel (RPV) fluence at 55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 theapplicant intends to test one surveillance capsule after the 16th refueling outage. The staffrequests 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 twocapsules for the extended period of operation is consistent with the requirements, specificallythe 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 twostandby 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 ofthe surveillance capsules. (2) If a standby capsule is removed from the RPV without the intent to test it, thecapsule 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 andNickel for the surveillance capsule test sample representing the intermediate shell plate (heat number-B4197-2) and the RPV's 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-4.2.4The 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-Tlimits 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-4.2.5Since the P-T limits for the extended period of operation are not yet developed, the applicantshould 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-4.2.6During the audit at the Harris Nuclear Plant, the staff was informed by the applicant that onereactor vessel nozzle was projected to achieve a neutron fluence greater than 1 x 10 17 n/cm 2 (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 10 17 n/cm 2 (E > 1 MeV) at the end of the extended period ofoperation. 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 requirementsof Title 10 of the Code of Federal Regulations (CFR) Section 50.61. (2) The adjusted reference temperature value of the nozzle material and its associatedwelds that will be used for developing pressure-temperature limits per the requirementsof 10 CFR Part 50, Appendix G.(3) The upper shelf energy value of the nozzle material and its associated welds per therequirements of 10 CFR Part 50, Appendix G.

Letter to R. J. Duncan II from M. Heath dated July 20, 2007DISTRIBUTION:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATIONHARD COPYDLR R/F E-MAIL:PUBLICSSmith (srs3)

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MHeath SHernandez LRegner Shearon Harris Nuclear Power Plant, Unit 1 cc:David T. ConleyAssociate General Counsel II -

Legal Department Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, NC 27602-1551Resident Inspector / Harris NPSc/o U. S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, NC 27562-9998Ms. Margaret A. ForceAssistant Attorney General State of North Carolina Post Office Box 629 Raleigh, NC 27602Public Service CommissionState of South Carolina Post Office Drawer 11649 Columbia, SC 29211Ms. Beverly Hall, Section ChiefDivision of Radiation Protection N.C. Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721Mr. J. Paul Fulford, ManagerPerformance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company Post Office Box 1551 Raleigh, NC 27602-1551Mr. Eric McCartneyPlant General Manager Shearon Harris Nuclear Power Plant Carolina Power & Light Company P. O. Box 165, Mail Zone 3 New Hill, NC 27562-0165Mr. Chris L. BurtonDirector of Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, Mail Zone 1 New Hill, NC 27562-0165Mr. Robert P. GruberExecutive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326Chairman of the North Carolina Utilities Commission P. O. Box 29510 Raleigh, NC 27626-0510Mr. Herb Council, ChairBoard of County Commissioners of Wake County P. O. Box 550 Raleigh, NC 27602Mr. Tommy Emerson, ChairBoard of County Commissioners of Chatham County P. O. Box 87 Pittsboro, NC 27312Mr. Thomas J. Natale, ManagerSupport Services Carolina Power & Light Company Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 1 New Hill, NC 27562-0165Mr. David H. Corlett, SupervisorLicensing/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:-2-Mr. John H. O'Neill, Jr.Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037-1128Ms. Julie KeysNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-2708