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MONTHYEARML0603801012006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors Project stage: RAI ML0620705242006-08-11011 August 2006 Approval of Generic Letter 2004-02 Extension Request Project stage: Other ML0729502752007-10-24024 October 2007 Draft Open Items from Staff Audit of Corrective Actions to Address Generic Letter 2004-02 Project stage: Draft Other LR-N07-0304, Request for Extension of Completion Dates for Corrective Actions Required by NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2007-12-10010 December 2007 Request for Extension of Completion Dates for Corrective Actions Required by NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request LR-N08-0043, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-02-29029 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request LR-N08-0139, Request for Extension to Complete Generic Letter 2004-02 Testing2008-06-26026 June 2008 Request for Extension to Complete Generic Letter 2004-02 Testing Project stage: Request ML0818305512008-06-30030 June 2008 Draft Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Draft RAI ML0820400132008-07-31031 July 2008 Approval of Request for Extension of Completion Date for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0821705062008-08-12012 August 2008 Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02 Project stage: Acceptance Review ML0833000792008-12-17017 December 2008 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2009-03-31031 March 2009 Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0933802422009-12-0404 December 2009 Draft Request for Additional Information Project stage: Draft RAI ML1002205202010-02-0404 February 2010 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI ML1003411882010-02-17017 February 2010 Notice of Forthcoming Meeting with PSEG Nuclear LLC (PSEG) Regarding Response to Generic Letter 2004-02 for Salem Nuclear Generating Station, Unit Nos. 1 and 2 Project stage: Request ML1007704112010-04-0707 April 2010 Summary of Meeting with PSEG Nuclear LLC, Regarding Response to Generic Letter 2004-02 for Salem Nuclear Generating Station, Unit Nos. 1 and 2 Project stage: Meeting ML1015401372010-05-27027 May 2010 Draft Salem, Units 1 and 2, Updated Supplemental Response to Generic Letter 2004-02 ML1015405252010-06-0808 June 2010 Notice of Meeting with PSEG Nuclear LLC, Regarding Response to Generic Letter 2004-02 for Salem Nuclear Generating Station, Units 1 and 2 Project stage: Meeting ML1018004772010-07-14014 July 2010 Summary of Category 1 Public Meeting with PSEG Nuclear LLC, Regarding Response to Generic Letter 2004-02 for Salem Nuclear Generating Station, Units 1 and 2 Project stage: Meeting ML14113A2022014-04-30030 April 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (Tac Nos. MC4712 and MC4713) Project stage: Other 2008-08-12
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Text
July 31, 2008 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - APPROVAL OF REQUEST FOR EXTENSION OF COMPLETION DATE FOR GENERIC LETTER 2004-02 CORRECTIVE ACTIONS (TAC NOS. MC4712 AND MC4713)
Dear Mr. Levis:
By letter dated June 26, 2008, as supplemented by letter dated July 10, 2008, PSEG Nuclear LLC (PSEG) requested an extension to the date to complete certain corrective actions associated with Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors, for Salem Nuclear Generating Station, Unit Nos. 1 and 2. Specifically, PSEG requested to extend the due date from June 30, 2008, until December 31, 2008, for completion of the corrective actions and an additional 90 days (i.e., until March 31, 2009) to provide an updated response to the GL.
As discussed in the enclosed evaluation, the Nuclear Regulatory Commission staff concludes that the proposed extension is acceptable. If you have any questions, please contact me at 301-415-1420.
Sincerely,
/ra/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
Evaluation cc w/encl: See next page
ML082040013 *By memo dated 7/17/08 OFFICE LPL1-2/PM LPL 1-2/LA SSIB/BC LPL1-2/BC NAME REnnis ABaxter MScott* HChernoff (JLamb for) 7/28/08 7/29/08 DATE 7/17/08 7/31/08 Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Thomas Joyce Township Clerk Senior Vice President - Operations Lower Alloways Creek Township PSEG Nuclear Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Dennis Winchester Radiation Protection Programs Vice President - Nuclear Assessment NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. Robert Braun Mr. Brian Beam Site Vice President - Salem Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Carl Fricker U.S. Nuclear Regulatory Commission Vice President - Operations Support 475 Allendale Road PSEG Nuclear King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. George Gellrich U.S. Nuclear Regulatory Commission Plant Manager - Salem Drawer 0509 PSEG Nuclear Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Steven Mannon Manager - Salem Regulatory Assurance PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR EXTENSION OF COMPLETION DATE FOR GENERIC LETTER 2004-02 CORRECTIVE ACTIONS SALEM NUCLEAR GENERATING STATION, UNIT NOS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated June 26, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081910152), as supplemented by letter dated July 10, 2008, PSEG Nuclear LLC (PSEG or the licensee) requested an extension to the date to complete certain corrective actions associated with Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors, for Salem Nuclear Generating Station (Salem),
Unit Nos. 1 and 2. The stated intent of this extension was to allow PSEG additional time to complete strainer performance testing, chemical testing, final analysis, and all licensing activities to address GL 2004-02. PSEG requested an extension from June 30, 2008, until December 31, 2008, for completion of the corrective actions and an additional 90 days (i.e., until March 31, 2009) to provide an updated response to the GL.
The NRC had previously approved an extension for completion of corrective actions associated with GL 2004-02 for Salem from December 31, 2007, until June 30, 2008 (reference NRC letter dated December 21, 2007, ADAMS Accession No. ML073532115).
PSEG stated in their June 26, 2008, letter that the request for an additional extension is due to a delay in completing vendor testing to determine strainer head losses associated with postulated debris loading of the strainer and incorporation of the results into net positive suction head (NPSH) calculations for the two units. The licensee explained that testing at Control Components Inc. (CCI) is being repeated to provide a prototypical test configuration and to resolve NRC staff concerns with previous testing practices. In addition to the repeated testing, PSEG is planning to perform bench top chemical testing to determine the time at which chemical precipitants may form in the post-loss-of-coolant accident (LOCA) containment sump pool.
PSEG stated that the chemical testing is anticipated to show that significant chemical effects will not occur until the sump pool is somewhat subcooled providing additional NPSH margin.
As stated in the June 26, 2008, letter, PSEG is requesting an extension until December 31, 2008, for completion of the following activities:
- Strainer performance testing and test documentation that confirms Salem's debris loading does not adversely impact pump NPSH margins.
Enclosure
- Bench top chemical testing and documentation of the testing to show the timing of precipitate formation in the post-LOCA containment sump fluid. PSEG stated that the combination of the strainer testing results and chemical bench top test results are anticipated to demonstrate that pump NPSH margins are not adversely affected in the post-LOCA environment.
- Following completion of the strainer performance testing and chemical bench top testing, and documentation of these tests, incorporation of the results into the emergency core cooling system (ECCS) NPSH evaluation. The NPSH evaluation is anticipated to be completed by December 31, 2008.
- Submittal of a revised GL 2004-02 response documenting these actions to the NRC not later than March 31, 2009.
The NRC has based its reviews for granting extensions to the due date for completion of GL 2004-02 corrective actions on the criteria stated in SECY-06-0078. Specifically, an extension may be granted if:
- the licensee has a plant-specific technical/experimental plan with milestones and schedule to address outstanding technical issues with enough margin to account for uncertainties, and
- the licensee identifies mitigative measures to be put in place prior to December 31, 2007, and adequately describes how these mitigative measures will minimize the risk of degraded ECCS and containment spray system (CSS) functions during the extension period.
The SECY also states that for proposed extensions beyond several months, a licensees request will more likely be accepted if the proposed mitigative measures include temporary physical improvements to the ECCS sump or materials inside containment to better ensure a high level of ECCS sump performance.
With regard to the first extension criterion, PSEG has provided a plant-specific technical/experimental plan, with milestones and schedules, to complete the GL 2004-02 corrective actions. In light of the new developments, and in order to meet the regulatory requirements, PSEG stated that it has scheduled the following activities:
- Completion of strainer performance testing to support final evaluation of ECCS performance by December 31, 2008.
- Completion of chemical bench top testing and documentation by October 31, 2008.
- Final analysis of ECCS performance incorporating the results of strainer and chemical bench top testing by December 31, 2008.
PSEG stated that it had completed other corrective actions for Salem Unit Nos. 1 and 2 that were included in PSEGs extension request letter dated December 10, 2007 (ADAMS Accession No. ML073531261) and PSEGs GL 2004-02 supplemental response dated February 29, 2008 (ADAMS Accession No. ML080800469).
With regard to the second extension criterion, the licensee stated in its letter dated June 26, 2008, that modifications, mitigation measures, compensatory measures, and/or favorable conditions are in effect at Salem Unit Nos. 1 and 2, minimizing the risk of degraded ECCS and CSS functions during the extension period. The NRC staff evaluation of the previous extension request and interim extension request concluded that PSEG had put mitigation measures in place to adequately reduce risk for the previous requested extension periods (June 30, 2008),
as stated in the NRC extension approval letter cited above.
Following receipt of the PSEG extension request letter dated June 26, 2008, the NRC staff conducted a phone call on June 30, 2008, with PSEG personnel to obtain clarification regarding the time required for PSEG to complete the required testing, the technical basis for the testing, and the current test results and how they apply to the NPSH margins at Salem Units 1 and 2.
The staff also stated that it expects that PSEG will continue near-term testing until a demonstrated acceptable plant configuration is identified. In addition, the staff stated that it expects that PSEG will expeditiously take the actions necessary so that both units will meet the configuration which has been shown to result in adequate NPSH margins. The staff requested that PSEG provide additional information detailing the contingency measures planned. The staff also requested that PSEG provide the results of strainer head loss testing conducted to date.
These requests were sent to the licensee in a draft request for information (RAI) dated June 30, 2008 (ADAMS Accession No. ML081830551). PSEGs letter LR-N08-0160 dated July 10, 2008, provided a response to the NRCs draft RAI. The NRC staff has reviewed the information in PSEGs response and has concluded that the licensee has a reasonable plan for showing adequate ECCS NPSH. Additionally, in the event that testing shows that the current configuration may not result in adequate NPSH, PSEG has contingency plans in place that the licensee expects will resolve sump performance issues.
The NRC staff believes that PSEG has a reasonable plan for Salem that should result in the completion of final GL 2004-02 corrective actions that provide acceptable strainer function with adequate margin for uncertainties. The staff finds that the additional time requested in the June 26, 2008, letter to complete testing and evaluations is considered to be of low safety concern. This finding is based on the mitigation measures and plant improvements already in place, and staff review of the recent testing conducted by PSEG that indicates that NPSH margins will be acceptable (with chemical precipitation, and its additional head loss, delayed until sump pool temperatures are reduced providing the additional required NPSH margin).
Based on the licensee having satisfactorily addressed the NRC GL 2004-02 due date extension criteria as discussed above, the NRC staff finds it is acceptable to extend the completion date for GL 2004-02 corrective actions associated with strainer performance testing, chemical bench top testing, final analysis and related NPSH calculations, as described in this enclosure, for Salem Unit Nos. 1 and 2 from June 30, 2008, to December 31, 2008. While the NRC accepts this date as reasonable allowance for contingencies regarding completion of remaining activities to address GL 2004-02, the NRC expects PSEG to place a high priority on completing remaining actions and updating the plants licensing basis as soon as possible.
The NRC staff expects that PSEG will provide an updated GL 2004-02 supplemental response within 90 days of the completion of the actions described in the extension request, and not later than March 31, 2009.
The NRC staff notes that PSEGs July 10, 2008, letter discusses plans to complete any needed contingent modifications by April 2010. The NRC staff expects PSEG to contact the NRC if the need for additional modifications is identified. This letter should not be construed as approval of the proposed April 2010 date.
Principal Contributor: S. Smith