HNP-11-096, Request for License Amendment Measurement Uncertainty Recapture Power Uprate Response to Request for Additional Information (RAI 10)

Request for License Amendment Measurement Uncertainty Recapture Power Uprate Response to Request for Additional Information (RAI 10)

ML11308A028
Person / Time
Site:	Harris
Issue date:	10/28/2011
From:	Holbrook K Progress Energy Co, Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-11-096
Download: ML11308A028 (5)

Text

jProgress Energy 10 CFR 50.90 October 28, 2011 HNP-1 1-096 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63

Subject:

REQUEST FOR LICENSE AMENDMENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI # 10)

References:

1. Letter from C.L. Burton (PEC) to the U.S. NRC, "Request for License Amendment, Measurement Uncertainty Recapture Power Uprate," dated April 28, 2011.

2. Letter from B. Mozafari (U.S. NRC) to W. Jefferson Jr. (CP&L), "Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate (TAC No. ME6169)" dated October 14, 2011 (RAI #10).

Ladies and Gentlemen:

By letter dated April 28, 2011, as supplemented on June 23, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc. (PEC), requested approval from the U.S. Nuclear Regulatory Commission (NRC) to increase the core thermal power level of Shearon Harris Nuclear Power Plant, Unit 1 (HNP) from 2,900 megawatts thermal (MWt) to 2,948 MWt, an increase of approximately 1.66 percent over the present licensed power level and to change the power plant technical specifications accordingly.

The staff determined that additional information is needed to complete its review. Questions were provided to CP&L in Reference 2, which requested that responses be provided by October 28, 2011. Those responses are provided in the enclosure to this letter.

CP&L has concluded that the information provided in this response meets the intent of the original submittal (Reference 1) and does not impact the conclusions of the: 1) Technical Analysis, 2) No Significant Hazards Consideration under the standards set forth in 10 CFR 50.92(c), or 3) Environmental Consideration as provided in the original submittal.

Progress Energy Carolinas, Inc.

Harris Nuclear Plant F'2 1

P.

H.

Box 165276 New Hill, NC 27562

U.S. Nuclear Regulatory Commission Page 2 HNP-1 1-096 In accordance with 10 CFR 50.91 (b), HNP is providing the state of North Carolina with a copy of this response.

This document contains no new Regulatory Commitments.

Please refer any questions regarding this submittal to Mr. David Corlett, Supervisor - HNP Licensing/Regulatory Programs, at (919) 362-3137.

I declare under penalty of perjury that the foregoing is true and correct. Executed on October 28, 2011.

Sincerely, Keith Holbrook Manager, Support Services Harris Nuclear Plant

Enclosure:

Harris Nuclear Plant Response to Request for Additional Information (RAI #10) cc:

Regional Administrator, USNRC/Region II Project Manager, Harris Nuclear Plant, USNRC/NRR Resident Inspector, Harris Nuclear Plant, USNRC Section Chief, NC Division of Environmental Health

HNP-1 1-096 Enclosure SHEARON HARRIS NUCLEAR POWER PLANT / UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 LICENSE AMENDMENT REQUEST MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE TAC ME6169 HARRIS NUCLEAR PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI #10)

(3 PAGES)

U.S. Nuclear Regulatory Commission Page 2 of 3 HNP-l 1-096 Enclosure Question 1 Table Matrix-i of NRC RS-001, Revision 0, "Review Standard for Extended Power Uprates,"

provides the staff's basis for evaluating the potential for extended power uprates to induce aging effects on reactor vessel (RV) internals. Depending on the magnitude of the projected RV internals fluence, Table Matrix-I may be applicable to the MUR application. In the Notes to Table Matrix-1, the staff states that guidance on the neutron irradiation-related threshold for irradiation-assisted stress corrosion cracking for pressurized water reactor RV internal components are given in BAW-2248A, "Demonstration of the Management of Aging Effects for the Reactor Vessel Intemals," and WCAP-14577, Revision 1-A, "License Renewal Evaluation:

Aging Management for Reactor Internals." The Notes to Table Matrix-1 state that for thermal and neutron embrittlement of cast austenitic stainless steel, stress corrosion cracking, and void swelling, licensees will need to provide plant-specific degradation management programs or participate in industry programs to investigate degradation effects and determine appropriate management programs. The BAW-2248A report and the WCAP-14577, Revision 1-A have been superseded by the MRP-227 report, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," which summarized the industry's most current recommended inspection and evaluation guidelines for RV internals. The safety evaluation dated June 22, 2011, lists the limitations and conditions imposed by the staff on use of the MRP-227 report. Please confirm the establishment of an inspection plan to manage the age-related degradation in the HNP, Unit 1 RV internals, or whether participation is planned in the industry's initiatives on age-related degradation of PWR RV internals, including submittal of a plant-specific program consistent with the MRP-227 report guidelines. For the former case, discuss your management of the above-mentioned aging effects on RV internals and demonstrate that the management is appropriate to ensure integrity and operability of RV internals to the end of license.

Response 1 Participation is planned in the industry's initiatives on age-related degradation of pressurized water reactor vessel internals, including submittal of a plant-specific program consistent with the MRP-227 report guidelines.

CP&L committed the following in its letter from C.J. Gannon (PEC), to USNRC "Application for Renewal of Operating License", dated November 14, 2006:

"In accordance with the guidance of NUREG-1801, Rev. 1, regarding aging management of reactor vessel internals components, HNP will: (1) participate in the industry programs for investigating and managing aging effects on reactor internals (such as Westinghouse Owner's Group and Electric Power Research Institute materials programs), (2) evaluate and implement the results of the industry programs as applicable to the reactor intemals, and (3) upon completion of these programs, but not less than 24 months before entering the period of extended operation, submit an inspection plan for reactor internals to the NRC for review and approval."

U.S. Nuclear Regulatory Commission Page 3 of 3 HNP-1 1-096 Enclosure Question 2,Section IV. 1.C.v, "Effect on Upper Shelf Energy Calculation," states that all RV materials have Charpy upper shelf energy (USE) greater than the 50 ft-lb acceptance criteria of 10 CFR Part 50, Appendix G, including the power uprate. Provide the specific Charpy USE value calculated for the limiting beltline material for 55 effective full power years neutron fluence, including the power uprate.

Response 2 As stated in Enclosure 2,Section IV. 1.C.v, the limiting beltline material is intermediate shell plate B4197-2. The predicted Charpy upper shelf energy for intermediate shell plate B4197-2 at 55 effective full power years neutron fluence, including the power uprate, is 53.0 ft-lb.