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| {{#Wiki_filter:August 11, 2006Mr. William LevisSenior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038 | | {{#Wiki_filter:August 11, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 - APPROVAL OFGENERIC LETTER 2004-02 EXTENSION REQUEST (TAC NO. MC4713) | | SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 - APPROVAL OF GENERIC LETTER 2004-02 EXTENSION REQUEST (TAC NO. MC4713) |
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| ==Dear Mr. Levis:== | | ==Dear Mr. Levis:== |
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| In a June 7, 2006, updated response to the Nuclear Regulatory Commission (NRC) GenericLetter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," PSEG Nuclear LLC (PSEG or the licensee) provided updated information on its ongoing activities for resolution of the Generic Safety Issue (GSI)-191 containment sump clogging issue. In addition to reporting on certain completed additional actions taken in response to GL 2004-02, PSEG requested an extension beyond December 31, 2007, for removal of certain insulation in the containment of Salem Nuclear Generating Station (Salem), Unit No. 2, until the next refueling outage scheduled tobegin on March 12, 2008. This results in an extension of approximately 10 weeks.PSEG stated that a design change package for Salem Unit No. 2 has been issued forinstallation of a 5300 square foot strainer with 1/12-inch openings during the fall 2006 outage. | | In a June 7, 2006, updated response to the 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," PSEG Nuclear LLC (PSEG or the licensee) provided updated information on its ongoing activities for resolution of the Generic Safety Issue (GSI)-191 containment sump clogging issue. In addition to reporting on certain completed additional actions taken in response to GL 2004-02, PSEG requested an extension beyond December 31, 2007, for removal of certain insulation in the containment of Salem Nuclear Generating Station (Salem), Unit No. 2, until the next refueling outage scheduled to begin on March 12, 2008. This results in an extension of approximately 10 weeks. |
| PSEG also stated that trisodium phosphate is not used as a pH buffer at Salem, reducing theexpectation of significant quantities of chemical precipitate as discussed in NRC InformationNotice (IN) 2005-26 and IN 2005-26, Supplement 1. PSEG stated that it will remove all calciumsilicate within the loss-of-coolant accident (LOCA) zones of influence by December 31, 2007. PSEG further stated that, as a result of a planned July 2006 loop testing of representative fiber, combined with Salem-specific chemical precipitates (from interactions with the sodium hydroxide pH buffer), the new strainer design was expected to have adequate margin for chemical effects. PSEG stated that the Salem downstream-effects evaluations have been completed and have been found acceptable for ex-vessel blockage and wear of downstream components. PSEG discussed a non-Salem-specific, conservative Westinghouse initial scoping evaluation ofthe long-term core coolability of the fuel with fibrous and particulate debris in the recirculationfluid. The evaluation concluded that passage of about one cubic foot or more of fibrous debriscould result in a thin-bed effect at the bottom of the fuel. PSEG stated that testing performed with the replacement strainer design for Salem with the current (non-calcium silicate insulation)fiber load has demonstrated a fibrous debris bypass of approximately five cubic feet. PSEG stated that there were ongoing actions underway to address this discrepancy: | | PSEG stated that a design change package for Salem Unit No. 2 has been issued for installation of a 5300 square foot strainer with 1/12-inch openings during the fall 2006 outage. |
| W. Levis *PSEG discussions with Westinghouse indicated that the assumptions for the formationof a 1/8-inch fiber bed at the bottom of the fuel are conservative, and can possibly be relaxed when considering the physical characteristics of the actual fibrous debris that would bypass the strainer. The vendor test results show that 90% of the Salem bypass fibers are relatively short (.004 to .04 inches) compared to fuel bottom nozzle flow holes of 0.2 inches. The licensee stated that these fibers will not mat across the fuel bottom nozzles, as was assumed in the Westinghouse scoping evaluation.*Westinghouse is developing Salem-specific acceptance criteria to quantify theacceptable amount of fiber bypass for long-term cooling, but the analyses are not expected to be completed until as late as September 2006. PSEG stated that it expectsthe results from the Salem bypass testing to be acceptable under these revised acceptance criteria.PSEG stated that it was confident that no additional insulation would need to be removed tocomply with the expected new allowable fiber bypass acceptance criteria. However, assuming that application of the Salem-specific fiber bypass acceptance criteria results in a need to remove additional insulation, two sets of insulation would need to be replaced. PSEG requested to defer replacement of this insulation for the following reasons:*One set of insulation that would need to be replaced is the steam generator insulation.PSEG has scheduled replacement of the Salem Unit No. 2 steam generators during the spring 2008 outage. The replacement steam generators are to be insulated with custom-engineered reflective metal insulation. If the current Salem Unit No. 2 steam generators insulation were to be replaced in the normally-scheduled fall 2006 refueling outage, the new insulation would need to be removed and replaced again when the steam generators are replaced in the spring 2008 outage. PSEG stated that this wouldresult in 22 REM of additional exposure, and generation of approximately 1800 cubic feet of radiological waste.*The other set of insulation that would need to be replaced is the pressurizer andpressurizer piping insulation. PSEG stated that replacing this insulation will result inapproximately 50 REM of additional exposure. PSEG stated that the likelihood of a LOCA would be low during the requested extension period(January 1 to March 12, 2008). The NRC staff notes that Salem Unit No. 2 has been acceptedas leak-before-break reactor primary coolant loop plant, as was discussed in an NRC letter toPSEG dated May 25, 1994. PSEG stated that the small incremental risk during the requestedextension period resulting from not installing interim insulation would more than offset avoidance of additional radiation exposure to plant workers.The NRC has confidence that PSEG has a plan that will result in the installation of finalmodifications that provide acceptable strainer function with adequate margin for uncertainties to resolve the GSI-191 containment sump clogging issue. Further, the NRC has concl uded thatPSEG has put mitigation measures in place to adequately reduce risk for the requested short extension period. Therefore, the NRC concludes that it is acceptable to extend the completiondate for the corrective actions (specifically, the replacement of insulation on the steam generators, pressurizer, and pressurizer piping) for the issues discussed in GL 2004-02 until the completion of the Salem Unit No. 2 spring 2008 refueling outage, which is currently scheduled W. Levis to begin approximately March 12, 2008. Should PSEG elect to begin the Salem, Unit No. 2outage more than 30 days after March 12, 2008, PSEG will need to provide the NRC additionaljustification for further delay in completing corrective actions for GL 2004-02.If you have any questions regarding this matter, please contact me at 301-415-1321, or atsnb@nrc.gov.
| | PSEG also stated that trisodium phosphate is not used as a pH buffer at Salem, reducing the expectation of significant quantities of chemical precipitate as discussed in NRC Information Notice (IN) 2005-26 and IN 2005-26, Supplement 1. PSEG stated that it will remove all calcium silicate within the loss-of-coolant accident (LOCA) zones of influence by December 31, 2007. |
| Sincerely,/RA/Stewart N. Bailey, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-311 cc: See next page W. Levis to begin approximately March 12, 2008. Should PSEG elect to begin the Salem, Unit No. 2outage more than 30 days after March 12, 2008, PSEG will need to provide the NRC additionaljustification for further delay in completing corrective actions for GL 2004-02.If you have any questions regarding this matter, please contact me at 301-415-1321, or atsnb@nrc.gov.
| | PSEG further stated that, as a result of a planned July 2006 loop testing of representative fiber, combined with Salem-specific chemical precipitates (from interactions with the sodium hydroxide pH buffer), the new strainer design was expected to have adequate margin for chemical effects. PSEG stated that the Salem downstream-effects evaluations have been completed and have been found acceptable for ex-vessel blockage and wear of downstream components. |
| Sincerely,/RA/Stewart N. Bailey, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-311 cc: See next page DISTRIBUTION
| | PSEG discussed a non-Salem-specific, conservative Westinghouse initial scoping evaluation of the long-term core coolability of the fuel with fibrous and particulate debris in the recirculation fluid. The evaluation concluded that passage of about one cubic foot or more of fibrous debris could result in a thin-bed effect at the bottom of the fuel. PSEG stated that testing performed with the replacement strainer design for Salem with the current (non-calcium silicate insulation) fiber load has demonstrated a fibrous debris bypass of approximately five cubic feet. PSEG stated that there were ongoing actions underway to address this discrepancy: |
| :PUBLICRidsNrrLACRaynorRidsNrrDorlLpl1-2 RidsNrrPMSBaileyRidsAcrsAcnwMailCenterLPL1-2 R/F RidsOgcRpRidsRgn1MailCenterLWhitneyADAMS Accession Number: ML062070524 *concur by memoOFFICELPL1-2/PMLPL1-2/LASSIB/BCLPL1-2/BC (A)NAMESBailey:rsaCRaynorMScott *BPooleDATE8/11/068/11/0607/07/068/11/06OFFICIAL RECORD COPY Salem Nuclear Generating Station, Unit No. 2 cc:
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| Mr. Dennis WinchesterVice President - Nuclear Assessment PSEG Nuclear
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| P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Thomas P. JoyceSite Vice President - Salem PSEG Nuclear
| | W. Levis |
| | * PSEG discussions with Westinghouse indicated that the assumptions for the formation of a 1/8-inch fiber bed at the bottom of the fuel are conservative, and can possibly be relaxed when considering the physical characteristics of the actual fibrous debris that would bypass the strainer. The vendor test results show that 90% of the Salem bypass fibers are relatively short (.004 to .04 inches) compared to fuel bottom nozzle flow holes of 0.2 inches. The licensee stated that these fibers will not mat across the fuel bottom nozzles, as was assumed in the Westinghouse scoping evaluation. |
| | * Westinghouse is developing Salem-specific acceptance criteria to quantify the acceptable amount of fiber bypass for long-term cooling, but the analyses are not expected to be completed until as late as September 2006. PSEG stated that it expects the results from the Salem bypass testing to be acceptable under these revised acceptance criteria. |
| | PSEG stated that it was confident that no additional insulation would need to be removed to comply with the expected new allowable fiber bypass acceptance criteria. However, assuming that application of the Salem-specific fiber bypass acceptance criteria results in a need to remove additional insulation, two sets of insulation would need to be replaced. PSEG requested to defer replacement of this insulation for the following reasons: |
| | * One set of insulation that would need to be replaced is the steam generator insulation. |
| | PSEG has scheduled replacement of the Salem Unit No. 2 steam generators during the spring 2008 outage. The replacement steam generators are to be insulated with custom-engineered reflective metal insulation. If the current Salem Unit No. 2 steam generators insulation were to be replaced in the normally-scheduled fall 2006 refueling outage, the new insulation would need to be removed and replaced again when the steam generators are replaced in the spring 2008 outage. PSEG stated that this would result in 22 REM of additional exposure, and generation of approximately 1800 cubic feet of radiological waste. |
| | * The other set of insulation that would need to be replaced is the pressurizer and pressurizer piping insulation. PSEG stated that replacing this insulation will result in approximately 50 REM of additional exposure. |
| | PSEG stated that the likelihood of a LOCA would be low during the requested extension period (January 1 to March 12, 2008). The NRC staff notes that Salem Unit No. 2 has been accepted as leak-before-break reactor primary coolant loop plant, as was discussed in an NRC letter to PSEG dated May 25, 1994. PSEG stated that the small incremental risk during the requested extension period resulting from not installing interim insulation would more than offset avoidance of additional radiation exposure to plant workers. |
| | The NRC has confidence that PSEG has a plan that will result in the installation of final modifications that provide acceptable strainer function with adequate margin for uncertainties to resolve the GSI-191 containment sump clogging issue. Further, the NRC has concluded that PSEG has put mitigation measures in place to adequately reduce risk for the requested short extension period. Therefore, the NRC concludes that it is acceptable to extend the completion date for the corrective actions (specifically, the replacement of insulation on the steam generators, pressurizer, and pressurizer piping) for the issues discussed in GL 2004-02 until the completion of the Salem Unit No. 2 spring 2008 refueling outage, which is currently scheduled |
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| P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George H. GellrichPlant Support Manager PSEG Nuclear
| | W. Levis to begin approximately March 12, 2008. Should PSEG elect to begin the Salem, Unit No. 2 outage more than 30 days after March 12, 2008, PSEG will need to provide the NRC additional justification for further delay in completing corrective actions for GL 2004-02. |
| | If you have any questions regarding this matter, please contact me at 301-415-1321, or at snb@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 cc: See next page |
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| P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Carl J. FrickerPlant Manager - Salem PSEG Nuclear - N21
| | W. Levis to begin approximately March 12, 2008. Should PSEG elect to begin the Salem, Unit No. 2 outage more than 30 days after March 12, 2008, PSEG will need to provide the NRC additional justification for further delay in completing corrective actions for GL 2004-02. |
| | If you have any questions regarding this matter, please contact me at 301-415-1321, or at snb@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 cc: See next page DISTRIBUTION: |
| | PUBLIC RidsNrrLACRaynor RidsNrrDorlLpl1-2 RidsNrrPMSBailey RidsAcrsAcnwMailCenter LPL1-2 R/F RidsOgcRp RidsRgn1MailCenter LWhitney ADAMS Accession Number: ML062070524 *concur by memo OFFICE LPL1-2/PM LPL1-2/LA SSIB/BC LPL1-2/BC (A) |
| | NAME SBailey:rsa CRaynor MScott |
| | * BPoole DATE 8/11/06 8/11/06 07/07/06 8/11/06 OFFICIAL RECORD COPY |
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| P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Darin BenyakDirector - Regulatory Assurance PSEG Nuclear - N21
| | Salem Nuclear Generating Station, Unit No. 2 cc: |
| | | Mr. Dennis Winchester Township Clerk Vice President - Nuclear Assessment 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. Thomas P. Joyce Radiation Protection Programs Site Vice President - Salem NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. George H. Gellrich Mr. Brian Beam Plant Support Manager 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 J. Fricker U.S. Nuclear Regulatory Commission Plant Manager - Salem 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. Darin Benyak U.S. Nuclear Regulatory Commission Director - Regulatory Assurance Drawer 0509 PSEG Nuclear - N21 Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Mr. Steven Mannon Manager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038}} |
| P.O. Box 236 Hancocks Bridge, NJ 08038Mr. James MallonManager - Licensing 200 Exelon Way, KSA 3-E Kennett Square, PA 19348Mr. Steven MannonManager - Regulatory Assurance
| |
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| P.O. Box 236 Hancocks Bridge, NJ 08038Jeffrie J. Keenan, EsquirePSEG Nuclear - N21 | |
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| P.O. Box 236 Hancocks Bridge, NJ 08038Township ClerkLower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038Mr. Paul Bauldauf, P.E., Asst. DirectorRadiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415Mr. Brian BeamBoard of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406Senior Resident InspectorSalem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038}} | |
Letter Sequence Other |
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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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and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only)
IR 05000272/20230102023-10-12012 October 2023
Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010
LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023
and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement
ML23249A2612023-09-0606 September 2023
License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000272/20230052023-08-31031 August 2023
Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005)
ML23233A0762023-08-21021 August 2023
Requalification Program Inspection
ML23192A8212023-08-14014 August 2023
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location
2024-09-23
[Table view] |
Text
August 11, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 - APPROVAL OF GENERIC LETTER 2004-02 EXTENSION REQUEST (TAC NO. MC4713)
Dear Mr. Levis:
In a June 7, 2006, updated response to the 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," PSEG Nuclear LLC (PSEG or the licensee) provided updated information on its ongoing activities for resolution of the Generic Safety Issue (GSI)-191 containment sump clogging issue. In addition to reporting on certain completed additional actions taken in response to GL 2004-02, PSEG requested an extension beyond December 31, 2007, for removal of certain insulation in the containment of Salem Nuclear Generating Station (Salem), Unit No. 2, until the next refueling outage scheduled to begin on March 12, 2008. This results in an extension of approximately 10 weeks.
PSEG stated that a design change package for Salem Unit No. 2 has been issued for installation of a 5300 square foot strainer with 1/12-inch openings during the fall 2006 outage.
PSEG also stated that trisodium phosphate is not used as a pH buffer at Salem, reducing the expectation of significant quantities of chemical precipitate as discussed in NRC Information Notice (IN) 2005-26 and IN 2005-26, Supplement 1. PSEG stated that it will remove all calcium silicate within the loss-of-coolant accident (LOCA) zones of influence by December 31, 2007.
PSEG further stated that, as a result of a planned July 2006 loop testing of representative fiber, combined with Salem-specific chemical precipitates (from interactions with the sodium hydroxide pH buffer), the new strainer design was expected to have adequate margin for chemical effects. PSEG stated that the Salem downstream-effects evaluations have been completed and have been found acceptable for ex-vessel blockage and wear of downstream components.
PSEG discussed a non-Salem-specific, conservative Westinghouse initial scoping evaluation of the long-term core coolability of the fuel with fibrous and particulate debris in the recirculation fluid. The evaluation concluded that passage of about one cubic foot or more of fibrous debris could result in a thin-bed effect at the bottom of the fuel. PSEG stated that testing performed with the replacement strainer design for Salem with the current (non-calcium silicate insulation) fiber load has demonstrated a fibrous debris bypass of approximately five cubic feet. PSEG stated that there were ongoing actions underway to address this discrepancy:
W. Levis
- PSEG discussions with Westinghouse indicated that the assumptions for the formation of a 1/8-inch fiber bed at the bottom of the fuel are conservative, and can possibly be relaxed when considering the physical characteristics of the actual fibrous debris that would bypass the strainer. The vendor test results show that 90% of the Salem bypass fibers are relatively short (.004 to .04 inches) compared to fuel bottom nozzle flow holes of 0.2 inches. The licensee stated that these fibers will not mat across the fuel bottom nozzles, as was assumed in the Westinghouse scoping evaluation.
- Westinghouse is developing Salem-specific acceptance criteria to quantify the acceptable amount of fiber bypass for long-term cooling, but the analyses are not expected to be completed until as late as September 2006. PSEG stated that it expects the results from the Salem bypass testing to be acceptable under these revised acceptance criteria.
PSEG stated that it was confident that no additional insulation would need to be removed to comply with the expected new allowable fiber bypass acceptance criteria. However, assuming that application of the Salem-specific fiber bypass acceptance criteria results in a need to remove additional insulation, two sets of insulation would need to be replaced. PSEG requested to defer replacement of this insulation for the following reasons:
- One set of insulation that would need to be replaced is the steam generator insulation.
PSEG has scheduled replacement of the Salem Unit No. 2 steam generators during the spring 2008 outage. The replacement steam generators are to be insulated with custom-engineered reflective metal insulation. If the current Salem Unit No. 2 steam generators insulation were to be replaced in the normally-scheduled fall 2006 refueling outage, the new insulation would need to be removed and replaced again when the steam generators are replaced in the spring 2008 outage. PSEG stated that this would result in 22 REM of additional exposure, and generation of approximately 1800 cubic feet of radiological waste.
- The other set of insulation that would need to be replaced is the pressurizer and pressurizer piping insulation. PSEG stated that replacing this insulation will result in approximately 50 REM of additional exposure.
PSEG stated that the likelihood of a LOCA would be low during the requested extension period (January 1 to March 12, 2008). The NRC staff notes that Salem Unit No. 2 has been accepted as leak-before-break reactor primary coolant loop plant, as was discussed in an NRC letter to PSEG dated May 25, 1994. PSEG stated that the small incremental risk during the requested extension period resulting from not installing interim insulation would more than offset avoidance of additional radiation exposure to plant workers.
The NRC has confidence that PSEG has a plan that will result in the installation of final modifications that provide acceptable strainer function with adequate margin for uncertainties to resolve the GSI-191 containment sump clogging issue. Further, the NRC has concluded that PSEG has put mitigation measures in place to adequately reduce risk for the requested short extension period. Therefore, the NRC concludes that it is acceptable to extend the completion date for the corrective actions (specifically, the replacement of insulation on the steam generators, pressurizer, and pressurizer piping) for the issues discussed in GL 2004-02 until the completion of the Salem Unit No. 2 spring 2008 refueling outage, which is currently scheduled
W. Levis to begin approximately March 12, 2008. Should PSEG elect to begin the Salem, Unit No. 2 outage more than 30 days after March 12, 2008, PSEG will need to provide the NRC additional justification for further delay in completing corrective actions for GL 2004-02.
If you have any questions regarding this matter, please contact me at 301-415-1321, or at snb@nrc.gov.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 cc: See next page
W. Levis to begin approximately March 12, 2008. Should PSEG elect to begin the Salem, Unit No. 2 outage more than 30 days after March 12, 2008, PSEG will need to provide the NRC additional justification for further delay in completing corrective actions for GL 2004-02.
If you have any questions regarding this matter, please contact me at 301-415-1321, or at snb@nrc.gov.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 cc: See next page DISTRIBUTION:
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NAME SBailey:rsa CRaynor MScott
- BPoole DATE 8/11/06 8/11/06 07/07/06 8/11/06 OFFICIAL RECORD COPY
Salem Nuclear Generating Station, Unit No. 2 cc:
Mr. Dennis Winchester Township Clerk Vice President - Nuclear Assessment 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. Thomas P. Joyce Radiation Protection Programs Site Vice President - Salem NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. George H. Gellrich Mr. Brian Beam Plant Support Manager 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 J. Fricker U.S. Nuclear Regulatory Commission Plant Manager - Salem 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. Darin Benyak U.S. Nuclear Regulatory Commission Director - Regulatory Assurance Drawer 0509 PSEG Nuclear - N21 Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Mr. Steven Mannon Manager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
