NL-05-023, 90-Day Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
| ML050660254 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/28/2005 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-04-002, NL-05-023 | |
| Download: ML050660254 (7) | |
Text
Enteray Nuclear Northeast Indian Point Energy Center 450 Broadway
--- Entergy P.O. Box 249 Buchanan, NY 10511-0249 Fred Dacimo Site Vice President Administration February 28, 2005 Re: Indian Point Units No. 2 and 3 Docket Nos. 50-247 and 50-286 NL-05-023 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-Pl-17 Washington, DC 20555-0001
SUBJECT:
90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors
References:
- 1. NRC Generic Letter 2004-02, 'Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors", dated September 13, 2004.
Dear Sir:
This letter provides Entergy Nuclear Operations (Entergy), Inc. 90-day response to NRC Generic Letter (GL) 2004-02 (Reference 1) for Indian Point Unit 2 and Indian Point Unit 3. The information requested by the Generic Letter is provided in Attachment 1.
Commitments being made by Entergy are listed in Attachment 2 to this letter. If you have any questions or require additional information, please contact Mr. Patric W. Conroy, Licensing Manager at 914-734-6668.
I declare under penalty of perjury that the foregoing is true and correct. Executed on 02-28-05.
Fred R. Dacimo Site Vice President cc: next page Indian Point Energy Center
NL-05-023 Docket Nos. 50-247 and 50-286 Page 2 of 2 : 90-day response to NRC Generic Letter 2004-02 : Commitments in 90-day Response to NRC Generic Letter 2004-02 cc:
Mr. Patrick D. Milano, Senior Project Manager Project Directorate I, Division of Reactor Projects I/l1 U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555 Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector's Office Indian Point IP 2 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511-0059 Resident Inspector's Office Indian Point IP 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, NY 12223
ATTACHMENT 1 TO NL-05-023 90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 DOCKETS 50-247 AND 50-286
NL-05-023, Attachment I Docket Nos. 50-247 and 50-286 Page 1 of 2 90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors Requested Information Item:
All addressees are requested to provide the following information:
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:
(a) 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.
(b) 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.
Entercy Response:
The safety evaluation providing guidance for performing the evaluation requested by GL 2004-02 was issued December 6, 2004 (Reference 1) and the following provides the requested information.
(a) Entergy plans to follow the guidance of the Nuclear Energy Institute (NEI) document titled "Pressurized-Water Reactor Sump Performance Evaluation Methodology", as approved and supplemented by the Reference 1 NRC Safety Evaluation, to analyze the susceptibility of the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions to the adverse effects of post-accident debris blockage and operation with debris-laden fluids identified in GL 2004-02.
In February 2005 Entergy began the formal analysis using the guidance of Reference 1. No exceptions to the Safety Evaluation have been identified to date. However, as the analysis develops, the current licensing basis or plant specific features may require that exceptions be taken. Entergy will notify the NRC of any such exceptions in a timely manner. The analysis is scheduled to be completed by September 1, 2005.
NL-05-023, Attachment 1 Docket Nos. 50-247 and 50-286 Page 2 of 2 (b) Containment walkdowns, to support the analysis of susceptibility of the ECCS and CSS recirculation functions to the adverse effects of debris blockage identified in GL 2004-02, were completed for Unit 2 in November 2004. These walkdowns were performed in accordance with the guidance provided in the NEI document titled "Pressurized-Water Reactor (PWR) Sump Performance Methodology", (Reference 2) and NEI 02-01 (Reference 3).
The corresponding Unit 3 containment walkdowns will be performed using guidance provided in NEI 02-01 (Reference 3). In addition, the walkdowns will include sampling for latent debris (dust and lint) using guidance in NEI 04-07 and the NRC Safety Evaluation (Reference 1). These walkdowns will be completed by April 30, 2005.
References
- 1. Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Nuclear Energy Institute Guidance Report (NEI 04-07) "Pressurized Water Reactor Sump Performance Evaluation Methodology", dated December 6, 2004.
- 2. Nuclear Energy Institute Proposed Document NEI 04-07, "Pressurized-Water Reactor (PWR) Sump Performance Methodology", dated May 28, 2004.
- 3. Nuclear Energy Institute Report NEI 02-01, "Condition Assessment Guidelines: Debris Sources Inside PWR Containments", Revision 1, dated September, 2002
ATTACHMENT 2 TO NL-05-023 Commitments in 90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 DOCKETS 50-247 AND 50-286
NL-05-023, Attachment 2 Docket Nos. 50-247 and 50-286 Page 1of 1 Number Commitment Due Date 1 Complete Indian Point Unit 3 containment walkdowns to support the April 30, analysis of susceptibility of the ECCS and CSS recirculation functions 2005 to the adverse effects of debris blockage identified in Generic Letter 2004-02.
2 Complete the analyses of the susceptibility of the ECCS and CSS September recirculation functions for Indian Point Unit 2 and Unit 3 to the adverse 1, 2005 effects of post accident debris blockage and operation with debris-laden fluids identified in Generic Letter 2004-02.
Text
Enteray Nuclear Northeast Indian Point Energy Center 450 Broadway
--- Entergy P.O. Box 249 Buchanan, NY 10511-0249 Fred Dacimo Site Vice President Administration February 28, 2005 Re: Indian Point Units No. 2 and 3 Docket Nos. 50-247 and 50-286 NL-05-023 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-Pl-17 Washington, DC 20555-0001
SUBJECT:
90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors
References:
- 1. NRC Generic Letter 2004-02, 'Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors", dated September 13, 2004.
Dear Sir:
This letter provides Entergy Nuclear Operations (Entergy), Inc. 90-day response to NRC Generic Letter (GL) 2004-02 (Reference 1) for Indian Point Unit 2 and Indian Point Unit 3. The information requested by the Generic Letter is provided in Attachment 1.
Commitments being made by Entergy are listed in Attachment 2 to this letter. If you have any questions or require additional information, please contact Mr. Patric W. Conroy, Licensing Manager at 914-734-6668.
I declare under penalty of perjury that the foregoing is true and correct. Executed on 02-28-05.
Fred R. Dacimo Site Vice President cc: next page Indian Point Energy Center
NL-05-023 Docket Nos. 50-247 and 50-286 Page 2 of 2 : 90-day response to NRC Generic Letter 2004-02 : Commitments in 90-day Response to NRC Generic Letter 2004-02 cc:
Mr. Patrick D. Milano, Senior Project Manager Project Directorate I, Division of Reactor Projects I/l1 U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555 Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector's Office Indian Point IP 2 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511-0059 Resident Inspector's Office Indian Point IP 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, NY 12223
ATTACHMENT 1 TO NL-05-023 90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 DOCKETS 50-247 AND 50-286
NL-05-023, Attachment I Docket Nos. 50-247 and 50-286 Page 1 of 2 90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors Requested Information Item:
All addressees are requested to provide the following information:
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:
(a) 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.
(b) 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.
Entercy Response:
The safety evaluation providing guidance for performing the evaluation requested by GL 2004-02 was issued December 6, 2004 (Reference 1) and the following provides the requested information.
(a) Entergy plans to follow the guidance of the Nuclear Energy Institute (NEI) document titled "Pressurized-Water Reactor Sump Performance Evaluation Methodology", as approved and supplemented by the Reference 1 NRC Safety Evaluation, to analyze the susceptibility of the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions to the adverse effects of post-accident debris blockage and operation with debris-laden fluids identified in GL 2004-02.
In February 2005 Entergy began the formal analysis using the guidance of Reference 1. No exceptions to the Safety Evaluation have been identified to date. However, as the analysis develops, the current licensing basis or plant specific features may require that exceptions be taken. Entergy will notify the NRC of any such exceptions in a timely manner. The analysis is scheduled to be completed by September 1, 2005.
NL-05-023, Attachment 1 Docket Nos. 50-247 and 50-286 Page 2 of 2 (b) Containment walkdowns, to support the analysis of susceptibility of the ECCS and CSS recirculation functions to the adverse effects of debris blockage identified in GL 2004-02, were completed for Unit 2 in November 2004. These walkdowns were performed in accordance with the guidance provided in the NEI document titled "Pressurized-Water Reactor (PWR) Sump Performance Methodology", (Reference 2) and NEI 02-01 (Reference 3).
The corresponding Unit 3 containment walkdowns will be performed using guidance provided in NEI 02-01 (Reference 3). In addition, the walkdowns will include sampling for latent debris (dust and lint) using guidance in NEI 04-07 and the NRC Safety Evaluation (Reference 1). These walkdowns will be completed by April 30, 2005.
References
- 1. Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Nuclear Energy Institute Guidance Report (NEI 04-07) "Pressurized Water Reactor Sump Performance Evaluation Methodology", dated December 6, 2004.
- 2. Nuclear Energy Institute Proposed Document NEI 04-07, "Pressurized-Water Reactor (PWR) Sump Performance Methodology", dated May 28, 2004.
- 3. Nuclear Energy Institute Report NEI 02-01, "Condition Assessment Guidelines: Debris Sources Inside PWR Containments", Revision 1, dated September, 2002
ATTACHMENT 2 TO NL-05-023 Commitments in 90-Day Response to NRC Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 DOCKETS 50-247 AND 50-286
NL-05-023, Attachment 2 Docket Nos. 50-247 and 50-286 Page 1of 1 Number Commitment Due Date 1 Complete Indian Point Unit 3 containment walkdowns to support the April 30, analysis of susceptibility of the ECCS and CSS recirculation functions 2005 to the adverse effects of debris blockage identified in Generic Letter 2004-02.
2 Complete the analyses of the susceptibility of the ECCS and CSS September recirculation functions for Indian Point Unit 2 and Unit 3 to the adverse 1, 2005 effects of post accident debris blockage and operation with debris-laden fluids identified in Generic Letter 2004-02.