ML032090434
ML032090434 | |
Person / Time | |
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Site: | Hope Creek |
Issue date: | 07/03/2003 |
From: | Tosch K State of NJ, Dept of Environmental Protection, Bureau of Nuclear Engineering |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML032090434 (2) | |
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Category:Letter
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Action Level Technical Bases Document (Clean Version) LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)2010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) ML1100503992010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix2010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix ML1100503752010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100504022010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1025802422010-09-0808 September 2010 License Amendment Request H10-01:, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction2010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505182010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505002010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment2010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling2010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling ML1100505162010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling LR-N10-0355, Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment2010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment ML1100504772010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer2010-04-21021 April 2010 Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations2010-04-21021 April 2010 Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations ML1100505062010-04-21021 April 2010 Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations ML1100505052010-04-21021 April 2010 Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 252010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504172010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504742010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup2010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature2010-03-0505 March 2010 Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature 2023-03-29 Category:Amendment MONTHYEARLR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021
[Table view]License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling2020-05-0707 May 2020 License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling LR-N17-0124, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-09-21021 September 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N09-0290, Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)2009-12-21021 December 2009 Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) ML0936401982009-12-21021 December 2009 Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) LR-N09-0237, License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components2009-11-0404 November 2009 License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components ML0836501692008-12-30030 December 2008 Correction to Amendment No. 175 Regarding Technical Specification Requirements for Inoperable Inverters ML0834601362008-12-0303 December 2008 New Jersey Department of Environmental Protection'S Bureau of Nuclear Engineering Comment on PSEG Nuclear Llc'S License Amendment Request to Remove Restrictions on Operation of the Hydrogen Water Chemistry System at Low Power. ML0834504962008-11-18018 November 2008 License Amendment Request (LAR) H08-04 ML0812306232008-05-14014 May 2008 Tec Spec Pages for Amendment No 174 ML0812306002008-05-14014 May 2008 Operating License Pages LR-N07-0163, License Amendment Request to Remove Turbine First Stage Pressure Values from Technical Specifications2007-07-26026 July 2007 License Amendment Request to Remove Turbine First Stage Pressure Values from Technical Specifications LR-N06-0437, License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications2006-11-15015 November 2006 License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications LR-N06-0286, Request for License Amendment Extended Power Uprate2006-09-18018 September 2006 Request for License Amendment Extended Power Uprate LR-N05-0432, Request for Change to Technical Specifications on Standby Liquid Control System2005-10-11011 October 2005 Request for Change to Technical Specifications on Standby Liquid Control System LR-N05-0030, Request for Change to Technical Specifications Relocation of Overcurrent Protective Devices2005-10-11011 October 2005 Request for Change to Technical Specifications Relocation of Overcurrent Protective Devices LR-N05-0266, Request for Change to Technical Specifications Correction of Containment Requirements During Handling of Irradiated Fuel and Core Alterations2005-10-0707 October 2005 Request for Change to Technical Specifications Correction of Containment Requirements During Handling of Irradiated Fuel and Core Alterations LR-N04-0454, Request for Change to Technical Specifications to Revise Scram Discharge Volume Vent and Drain Line Requirements Using the Consolidated Line Item Improvement Process2005-02-25025 February 2005 Request for Change to Technical Specifications to Revise Scram Discharge Volume Vent and Drain Line Requirements Using the Consolidated Line Item Improvement Process LR-N04-0350, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Primary Containment Hydrogen/Oxygen Concentration Analyzer and Monitor Channels Using the Consolidated Line Item.2004-10-0101 October 2004 Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Primary Containment Hydrogen/Oxygen Concentration Analyzer and Monitor Channels Using the Consolidated Line Item. LR-N04-0062, Request for License Amendment Arts/Mellla Implementation2004-06-0707 June 2004 Request for License Amendment Arts/Mellla Implementation LR-N04-0183, Request for Change to Technical Specifications Safety Limit Minimum Critical Power Ratio2004-04-27027 April 2004 Request for Change to Technical Specifications Safety Limit Minimum Critical Power Ratio LR-N03-0405, Request for Change to Technical Specifications Regarding Reactor Protection System Instrumentation, Control Rod Block Instrumentation, Source Range Monitors, and Power Distribution Limits Surveillance Requirements2003-10-24024 October 2003 Request for Change to Technical Specifications Regarding Reactor Protection System Instrumentation, Control Rod Block Instrumentation, Source Range Monitors, and Power Distribution Limits Surveillance Requirements ML0320904342003-07-0303 July 2003 License Change Request to Eliminate Post Accident Sampling System Technical Specifications Requirements ML0310700882003-04-16016 April 2003 Technical Specification Page 6-16b, Amendment 147 LR-N02-0417, Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters - Revision to Request for Change to TS Dated 06/28/20022003-01-18018 January 2003 Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters - Revision to Request for Change to TS Dated 06/28/2002 LR-N02-0343, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.2002-10-23023 October 2002 Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area. LR-N02-0069, Request for License Amendment A.C. Sources - Operating2002-08-20020 August 2002 Request for License Amendment A.C. Sources - Operating ML0222606802002-08-13013 August 2002 Technical Specifications for Amendment 139 Use of Existing Pressure-Temperature Curves Through Cycle 12 (Tac No. MB4685) ML0210504542002-04-0303 April 2002 Request for Change to Technical Specifications Reactor Coolant Chemistry 2021-05-07 |
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e;tnte of aidu Jtrt g James E. McGreevey Department of Environmental Protection Bradley M.Campbell Governor Division of Environmental Safety and Health Commissioner Radiation Protection and Release Prevention Element Bureau of Nuclear Engineering P.O. Box 415 Trenton, New Jersey 08625-0415 Tel (609) 984-7700 Fax (609) 984-7513 July 3, 2003 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
Subject:
Hope Creek Generating Station Docket No. 50-354 License Change Request H02-01 1 Request to Eliminate the Post Accident Sampling System Technical Specification Requirements PSEG Nuclear LLC submitted the proposed change to the Hope Creek Technical Specifications by letter to the NRC dated March 13, 2003. The proposed change would delete Technical Specification 6.8.4.c, "Post Accident Sampling", and thereby eliminate the requirements to have and maintain the post accident sampling system at Hope Creek.
We noted, that in Attachment I to the March 13 letter, PSEG commits to develop and maintain contingency plans for obtaining and analyzing highly radioactive samples of reactor coolant, containmentsump and containmentatmosphere. Based on a conversation we had with PSEG Hope Creek Chemistry Personnel on June 20, 2003, it is our understanding that PSEG will install the shielding required to allow sampling of the normal sampling points during accident conditions based on an engineering evaluation.
It is our expectation, that following an accident the radionuclide mix be characterized within a reasonable period of time, say within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by whatever means available. This mix must be defined prior to consideration of protective action recommendations being developed for ingestion pathway issues. We believe that the federal Department of Energy with their role in post accident radiation surveys and assessment would have timilai needs.
I would also recommend that the federal Department of Energy be consulted as to their expectations for sampling. If you need to discuss the subject further, please contact me at (609) 984-7700 or Elliot Rosenfeld at (609) 984-7548.
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Sincerely, Kent W. Tosch, Manager Bureau of Nuclear Engineering C: Dr. Jill Lipoti, DEP Dennis Zannoni, DEP Dr. Robert Bores, NRC Richard Ennis, NRC Licensing Project Manager Mel Gray, Sr Resident Inspector Gabor Salamon, PSEG Nuclear LLC Don Daigler, DOE FRMAC