ML050610168
| ML050610168 | |
| Person / Time | |
|---|---|
| Site: | Farley, Vogtle  |
| Issue date: | 02/25/2005 |
| From: | Stinson L Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-04-002, NL-05-0290 | |
| Download: ML050610168 (8) | |
Text
L M. Stinson (Mike)
Southern Nuclear Vice President Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.51 81 Fax 205.992.0341 February 25, 2005 SOUTHERN A COMPANY Energy to Serve Youtr World' NL-05-0290 Docket Nos.:
50-348 50-424 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Z 0q-DZ_
Response to N
-B44d in-2OO4X 6 "Potential Impact of Debris Blockage on Emergencv Recirculation During Design Basis Accidents at Pressurized-Water Reactors" Ladies and Gentlemen:
Pursuant to the requirements of Nuclear Regulatory Commission (NRC) Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," issued to the Southern Nuclear Operating Company (SNC) on September 13, 2004, SNC hereby submits Enclosures I and 2 which constitute the required 90-day responses for Joseph M. Farley Nuclear Plant (FNP) Units I and 2 and Vogtle Electric Generating Plant (VEGP) Units I and 2.
Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Swt1orn7 to and subscribed before me tlis )6 daysof r uT -!
2005.
'7 -otaoV Psublic May conzinission epires: 1& ~-a 41/CO LMS/DWM/sdl
U. S. Nuclear Regulatory Commission NL-05-0290 Page 2
Enclosures:
- 1. Farley Nuclear Plant Response to Generic Letter 2004-02
- 2. Vogtle Electric Generating Plant Response to Generic Letter 2004-02 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. L. M. Stinson, Vice President - Plant Farley Mr. D. E. Grissette, Vice President - Plant Vogtle Mr. J. R. Johnson, General Manager - Plant Farley Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CFA04.054; CVC7000; LC# 14222 U. S. Nuclear Regulatorv Commission Dr. W. D. Travers, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. C. Gratton, NRR Project Manager - Vogtle Mr. C. A. Patterson, Senior Resident Inspector - Farley Mr. G. J. McCoy, Senior Resident Inspector - Vogtle Farley Nuclear Plant Response to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors"
Farley Nuclear Plant Response to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" Within 90 days of the date of the safety evaluation report providing the guidance for performing the requested evaluation, addressees are requested to provide information regarding their planned actions and schedule to complete the requested evaluation. The information should include the following:
(1) A description of the methodology that is used or will be used to analyze the susceptibility of the ECCS and CSS recirculation functions for your reactor to the adverse effects identified in this generic letter of post-accident debris blockage and operation with debris-laden fluids identified in this generic letter. Provide the completion date of the analysis that will be performed.
FNP Response to Item 1:
Southern Nuclear Operating Company (SNC) intends to address the issues required by GL 2004-02 using methodology developed by NEI and documented in Guidance Report NEI 04-07, as amended by the NRC's Safety Evaluation Report on these guidelines as the basis of the analysis. However, SNC may substitute simplifying assumptions, alternative methodologies or inputs, hardware-specific head loss correlations, and/or plant-specific information as appropriate. Structural analysis will follow commonly used analytical techniques and widely accepted engineering practices. In the event that a hardware solution for FNP is determined to be relatively insensitive to some results of certain analyses, those may not be performed.
This analysis is scheduled to be completed by September 1, 2005.
Industry efforts are under way to evaluate coating failures, the effects of chemical reactions in containment during a LOCA, and the downstream effects of debris laden fluid. To the extent that information from these efforts becomes available and is applicable to Farley specific parameters, SNC will utilize it as part of the analysis.
However, if the information from these activities is not available, SNC will address these issues using appropriate assumptions and methodologies.
Page I of 2
Farley Nuclear Plant Response to NRC Generic Letter 2004-02,
'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (2) A statement of whether you plan to perform a containment walkdown surveillance in support of the analysis of the susceptibility of the ECCS and CSS recirculation functions to the adverse effects of debris blockage identified in this generic letter. Provide justification if no containment walkdown surveillance will be performed. If a containment walkdown surveillance will be performed, state the planned methodology to be used and the planned completion date.
FNP Response to Item 2:
Containment walkdowns have been completed at Farley Units I and 2 to support the analysis of debris blockage as identified in the Generic Letter. The walkdowns were performed by SNC and contractor personnel using the guidelines provided in NEI 02-01, "Condition Assessment Guidelines, Debris Sources Inside Containment," Revision 1.
Page 2of 2 Vogtle Electric Generating Plant Response to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors"
Vogtle Electric Generating Plant Response to NRC Generic Letter 2004-02,
'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" Within 90 days of the date of the safety evaluation report providing the guidance for performing the requested evaluation, addressees are requested to provide information regarding their planned actions and schedule to complete the requested evaluation. The information should include the following:
(1) A description of the methodology that is used or will be used to analyze the susceptibility of the ECCS and CSS recirculation functions for your reactor to the adverse effects identified in this generic letter of post-accident debris blockage and operation with debris-laden fluids identified in this generic letter. Provide the completion date of the analysis that will be performed.
VEGP Response to Item 1:
Southern Nuclear Operating Company (SNC) intends to address the issues required by GL 2004-02 using methodology developed by NEI and documented in Guidance Report NEI 04-07, as amended by the NRC's Safety Evaluation Report on these guidelines as the basis of the analysis. However, SNC may substitute simplifying assumptions, alternative methodologies or inputs, hardware-specific head loss correlations, and/or plant-specific information as appropriate. Structural analysis will follow commonly used analytical techniques and widely accepted engineering practices. In the event that a hardware solution for VEGP is determined to be relatively insensitive to some results of certain analyses, those may not be performed.
This analysis is scheduled to be completed by September 1, 2005.
Industry efforts are under way to evaluate coating failures, the effects of chemical reactions in containment during a LOCA and the downstream effects of debris laden fluid. To the extent that information from these efforts becomes available and is applicable to VEGP specific parameters, SNC will utilize it as part of the analysis.
However, if the information from these activities is not available, SNC will address these issues using appropriate assumptions and methodologies.
Page I of 2
Vogtle Electric Generating Plant Response to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (2) A statement of whether you plan to perform a containment walkdown surveillance in support of the analysis of the susceptibility of the ECCS and CSS recirculation functions to the adverse effects of debris blockage identified in this generic letter. Provide justification if no containment walkdown surveillance will be performed. If a containment walkdown surveillance will be performed, state the planned methodology to be used and the planned completion date.
VEGP Response to Item 2:
Containment walkdowns have been completed at VEGP Units 1 and 2 to support the analysis of debris blockage as identified in the Generic Letter. The walkdowns were performed by SNC and contractor personnel using the guidelines provided in NEI 02-01, "Condition Assessment Guidelines, Debris Sources Inside Containment," Revision 1.
Page 2 of 2