ML052070685

Response to NRC RAI Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation During Design Basis Accidents at Pressurized-water Reactors

ML052070685
Person / Time
Site:	Harris, Robinson
Issue date:	07/19/2005
From:	Hinnant C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PE&RAS05-061
Download: ML052070685 (3)

Text

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Progress Energy z

• C. S. Hinnant Sr. Vice President and Chief Nuclear Officer Progress Energy, Inc.

PO Box 1551 411 Fayetteville Street Mall 10 CFR 50.54(f)

Raleigh NC 27602 Serial: PE&RAS05-061 July 19, 2005 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / LICENSE NO. DPR-23 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS"

REFERENCES:

Progress Energy letter PE&RAS05-008, "Response to NRC Generic Letter 2004-02, 'Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors"' dated March 4, 2005.

Letter requesting additional information from Chandu P. Patel, Project Manager, Section 2, Project Directorate II, Division of Licensing Project Management, Office of Nuclear Reactor Regulation dated June 3, 2005.

Ladies and Gentlemen:

By letter dated June 3, 2005, Mr. Chandu Patel provided a request for additional information (RAI) regarding Progress Energy's 90-day response to the Nuclear Regulatory Commission (NRC)

Generic Letter 2004-02. Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc. (PEC), hereby responds to the RAI as follows:

NRC Request #1 - Please explain why these analyses will not be completed in time to support the September 1, 2005, response and describe the impact of not completing these analyses on your ability to meet the December 31, 2007, corrective action complete date.

PEC Response #1 - Downstream components potentially susceptible to blockage or wear will be identified by September 1, 2005. The precise impact on these components due to operation with debris-laden fluid is currently being evaluated in accordance with regulatory guidance and recently published industry guidance. Evaluations have been drafted that determine the potential for blockage of downstream piping system components. The schedule for finalizing these blockage evaluations and for completing the balance of downstream components evaluations will be provided in our September 1, 2005 generic letter response.

United States Nuclear Regulatory Commission PE&RAS-05-061 Page 2 Analyses of potential sump screen modifications are proceeding based on a screen opening size equal to or smaller than that determined from the draft blockage evaluations. The reason that all downstream evaluations will not be completed by September 1, 2005 is that the industry guidance document for evaluating downstream effects (WCAP-16406) was not issued for use until June 30, 2005.

Completion of these analyses and development of any associated design changes, by the November 7, 2006 date provided in the 90-day response, will assure that the December 31, 2007 corrective action completion date is met.

NRC Request #2 - With an incomplete analysis, it is unclear how you will be able to provide the requested information in the GL. Please describe how your September 1, 2005 response will be responsive to the information request in GL 2004-02.

PEC Response #2 - The information to be provided by September 1, 2005 will address the key issue of sump screen blockage. However, evaluation of the additional issue pertaining to downstream effects will not be completed by that date. As stated above, this will have no impact on our ability to meet the December 31, 2007 date. Our September 1, 2005 response will provide assurance that we are making substantial progress in resolving Generic Safety Issue 191 in a timely manner.

No new Regulatory Commitment is contained in this submittal.

Please refer any questions regarding this submittal to Mr. Rick Garner at (919) 546-6967.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on \LJL.'/ I'd a c5-(date)

Sincerely, CSS 4 ~2 C. S. Hinnant Senior Vice President and Chief Nuclear Officer CSH/kmh

United States Nuclear Regulatory Commission PE&RAS-05-061 Page 3 C: U.S. NRC Region II W. D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth Street, SW Atlanta, GA 30303-8931 C. P. Patel, Project Manager SHNPP and HBRSEP, NRR (Electronic Copy Only)

SHNPP Resident Inspector HBRSEP Resident Inspector