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| {{#Wiki_filter:October 15, 2009 | | {{#Wiki_filter:October 15, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ |
| | | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD7874 AND MD7875) | | SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD7874 AND MD7875) |
| | | The attached draft request for information (RAI) was transmitted on October 15, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). The draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with PSEG in order to clarify the licensees submittals dated April 10, 2008, October 13, 2008, and February 10, 2009, in response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow PSEG to evaluate and agree upon a schedule to respond to the RAI. |
| The attached draft request for information (RAI) was transmitted on October 15, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). The draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with PSEG in order to clarify the licensee's submittals dated April 10, 2008, October 13, 2008, and February 10, 2009, in response to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow PSEG to evaluate and agree upon a schedule to respond to the RAI. | | This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals. |
| | | Docket Nos. 50-272 and 50-311 |
| This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals. | |
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| Docket Nos. 50-272 and 50-311 | |
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| ==Attachment:== | | ==Attachment:== |
| Draft RAI | | Draft RAI |
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| October 15, 2009
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| MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | October 15, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD7874 AND MD7875) | | SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD7874 AND MD7875) |
| | | The attached draft request for information (RAI) was transmitted on October 15, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). The draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with PSEG in order to clarify the licensees submittals dated April 10, 2008, October 13, 2008, and February 10, 2009, in response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow PSEG to evaluate and agree upon a schedule to respond to the RAI. |
| The attached draft request for information (RAI) was transmitted on October 15, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). The draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with PSEG in order to clarify the licensee's submittals dated April 10, 2008, October 13, 2008, and February 10, 2009, in response to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow PSEG to evaluate and agree upon a schedule to respond to the RAI. | | This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals. |
| | | Docket Nos. 50-272 and 50-311 |
| This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals. | |
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| Docket Nos. 50-272 and 50-311 | |
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| ==Attachment:== | | ==Attachment:== |
| Draft RAI | | Draft RAI DISTRIBUTION PUBLIC LPL1-2Reading RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMSalem Resource KDesai, NRR/SRXB ACCESSION NO.: ML092880519 OFFICE PDI-2/PM NAME REnnis DATE 10/15/2009 OFFICIAL RECORD COPY |
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| DISTRIBUTION PUBLIC LPL1-2Reading RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMSalem Resource KDesai, NRR/SRXB | |
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| ACCESSION NO.: ML092880519 OFFICE PDI-2/PM NAME REnnis DATE 10/15/2009 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TO GENERIC LETTER 2008-01 SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 | |
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| By letters dated April 10, 2008, October 13, 2008, and February 10, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML081130785, ML082970217, and ML090560529, respectively), PSEG Nuclear LLC (PSEG or the licensee) provided responses to Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (ADAMS Accession No. | | DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TO GENERIC LETTER 2008-01 SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letters dated April 10, 2008, October 13, 2008, and February 10, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML081130785, ML082970217, and ML090560529, respectively), PSEG Nuclear LLC (PSEG or the licensee) provided responses to Generic Letter (GL) 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (ADAMS Accession No. ML072910759) for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. Additional information is required for the U.S. Nuclear Regulatory Commission (NRC) staff to determine that the licensee has acceptably demonstrated that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance as stated in GL 2008-01. |
| ML072910759) for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. Additional information is required for the U.S. Nuclear Regulatory Commission (NRC) staff to determine that the licensee has acceptably demonstrated "that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance" as stated in GL 2008-01. | |
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| ==Background:== | | ==Background:== |
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| Guidance on NRC staff expectations is provided by Reference 1 which is generally consistent with guidance from the Nuclear Energy Institute (NEI) provided to the nuclear industry. The NRC staff recommends that the licensee consult Reference 1 when responding to the following request for additional information: | | Guidance on NRC staff expectations is provided by Reference 1 which is generally consistent with guidance from the Nuclear Energy Institute (NEI) provided to the nuclear industry. The NRC staff recommends that the licensee consult Reference 1 when responding to the following request for additional information: |
| : 1. The GL was intended to address all modes and all operating conditions and it is not limited to events and accidents evaluated in the Updated Final Safety Analysis Report. | | : 1. The GL was intended to address all modes and all operating conditions and it is not limited to events and accidents evaluated in the Updated Final Safety Analysis Report. |
| Please confirm that all subject systems are evaluated for all modes and all operating conditions. | | Please confirm that all subject systems are evaluated for all modes and all operating conditions. |
| : 2. Please demonstrate that adequate net positive suction head margin exists when air ingestion effects are considered in the calculations for the residual heat removal, safety injection, and containment spray pumps. | | : 2. Please demonstrate that adequate net positive suction head margin exists when air ingestion effects are considered in the calculations for the residual heat removal, safety injection, and containment spray pumps. |
| : 3. Please briefly summarize the revised fill and vent procedures with respect to guidance for instrumentation lines. Also briefly discuss the details of any confirmatory testing followed by fill procedures. | | : 3. Please briefly summarize the revised fill and vent procedures with respect to guidance for instrumentation lines. Also briefly discuss the details of any confirmatory testing followed by fill procedures. |
| : 4. Training was not identified in the GL but it is considered to be a necessary part of applying procedures and other activities when addressing issues identified in the GL. | | : 4. Training was not identified in the GL but it is considered to be a necessary part of applying procedures and other activities when addressing issues identified in the GL. |
| Please briefly discuss training. | | Please briefly discuss training. |
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| ==REFERENCES:== | | ==REFERENCES:== |
| : 1. Letter from William H. Ruland (NRC) to James H. Riley (NEI), "Preliminary Assessment of Responses to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," and Future Nuclear Regulatory Commission Staff Review Plans", dated May 28, 2009 (ADAMS Accession No. ML091390637). | | : 1. Letter from William H. Ruland (NRC) to James H. Riley (NEI), Preliminary Assessment of Responses to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, and Future Nuclear Regulatory Commission Staff Review Plans, dated May 28, 2009 (ADAMS Accession No. ML091390637). |
| Attachment}} | | Attachment}} |
Letter Sequence Draft RAI |
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MONTHYEARLR-N08-0074, Three-Month Response to NRC Generic Letter 08-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2008-04-10010 April 2008 Three-Month Response to NRC Generic Letter 08-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Request LR-N08-0073, Transmittal of Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems2008-04-10010 April 2008 Transmittal of Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems Project stage: Request ML0817801202008-09-0808 September 2008 Units 1 & 2-Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, & Containment Spray Systems, Proposed Alternative Course of Action (Tac MD7835, MD7874, & MD7875) Project stage: Other ML0905605292009-02-10010 February 2009 Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 Unit 1 Response,Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems Project stage: Request ML0928805192009-10-15015 October 2009 Draft Request for Additional Information Project stage: Draft RAI ML1113800682011-06-0202 June 2011 Closeout of Generic Letter 2008-01,Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems Project stage: Other 2009-10-15
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October 15, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD7874 AND MD7875)
The attached draft request for information (RAI) was transmitted on October 15, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). The draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with PSEG in order to clarify the licensees submittals dated April 10, 2008, October 13, 2008, and February 10, 2009, in response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow PSEG to evaluate and agree upon a schedule to respond to the RAI.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals.
Docket Nos. 50-272 and 50-311
Attachment:
Draft RAI
October 15, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD7874 AND MD7875)
The attached draft request for information (RAI) was transmitted on October 15, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (PSEG or the licensee). The draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with PSEG in order to clarify the licensees submittals dated April 10, 2008, October 13, 2008, and February 10, 2009, in response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow PSEG to evaluate and agree upon a schedule to respond to the RAI.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's submittals.
Docket Nos. 50-272 and 50-311
Attachment:
Draft RAI DISTRIBUTION PUBLIC LPL1-2Reading RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMSalem Resource KDesai, NRR/SRXB ACCESSION NO.: ML092880519 OFFICE PDI-2/PM NAME REnnis DATE 10/15/2009 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TO GENERIC LETTER 2008-01 SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letters dated April 10, 2008, October 13, 2008, and February 10, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML081130785, ML082970217, and ML090560529, respectively), PSEG Nuclear LLC (PSEG or the licensee) provided responses to Generic Letter (GL) 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (ADAMS Accession No. ML072910759) for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. Additional information is required for the U.S. Nuclear Regulatory Commission (NRC) staff to determine that the licensee has acceptably demonstrated that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance as stated in GL 2008-01.
Background:
Guidance on NRC staff expectations is provided by Reference 1 which is generally consistent with guidance from the Nuclear Energy Institute (NEI) provided to the nuclear industry. The NRC staff recommends that the licensee consult Reference 1 when responding to the following request for additional information:
- 1. The GL was intended to address all modes and all operating conditions and it is not limited to events and accidents evaluated in the Updated Final Safety Analysis Report.
Please confirm that all subject systems are evaluated for all modes and all operating conditions.
- 2. Please demonstrate that adequate net positive suction head margin exists when air ingestion effects are considered in the calculations for the residual heat removal, safety injection, and containment spray pumps.
- 3. Please briefly summarize the revised fill and vent procedures with respect to guidance for instrumentation lines. Also briefly discuss the details of any confirmatory testing followed by fill procedures.
- 4. Training was not identified in the GL but it is considered to be a necessary part of applying procedures and other activities when addressing issues identified in the GL.
Please briefly discuss training.
REFERENCES:
- 1. Letter from William H. Ruland (NRC) to James H. Riley (NEI), Preliminary Assessment of Responses to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, and Future Nuclear Regulatory Commission Staff Review Plans, dated May 28, 2009 (ADAMS Accession No. ML091390637).
Attachment