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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2022-031, License Amendment Request, Revise License Condition to Eliminate Cyber Security Plan Requirements2022-09-14014 September 2022 License Amendment Request, Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2022-016, License Amendment Request: Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-07-12012 July 2022 License Amendment Request: Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages ML21152A1122021-06-0101 June 2021 Page Change Instructions and Retyped Pages for the Palisades Plant Appendix a Permanently Defueled Technical Specifications and Appendix B Environmental Protection Plan ML21152A1132021-06-0101 June 2021 Palisade Nuclear Plant - Proposed Technical Specifications Bases Changes ML21152A1102021-06-0101 June 2021 Evaluation of the Proposed Changes PNP 2020-042, and Big Rock Point Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2020-12-23023 December 2020 and Big Rock Point Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19149A3032019-05-28028 May 2019 Enclosure Attachment 1 to Pnp 2019-028: Renewed Facility Operating License Page Markups ML19149A3042019-05-28028 May 2019 Enclosure Attachment 1 (Continued) to Pnp 2019-028: Operating License Page Change Instructions and Retyped Renewed Facility Operating License Pages ML19149A3022019-05-28028 May 2019 Enclosure to Pnp 2019-028: Response to Request for Additional Information - License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications PNP 2019-007, License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications2019-03-0808 March 2019 License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 ML18305B3212018-11-0101 November 2018 License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications ML18305B3222018-11-0101 November 2018 License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications - Proposed Operating License Change PNP 2018-040, License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications - Proposed Renewed Facility Operating License Page Changes (Markup)2018-11-0101 November 2018 License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications - Proposed Renewed Facility Operating License Page Changes (Markup) ML18270A3252018-09-27027 September 2018 Attachment 4: Page Change Instructions and Revised Pages, and Appendix a Technical Specifications ML18270A3232018-09-27027 September 2018 Attachment 2: Probabilistic Risk Assessment Technical Adequacy ML18270A3242018-09-27027 September 2018 Attachment 3: Proposed Changes and Appendix a Technical Specifications Pages ML18270A3262018-09-27027 September 2018 Attachment 5: Proposed Technical Specification Bases Changes ML18270A3222018-09-27027 September 2018 Attachment 1: Description and Evaluation of Technical Specifications Changes ML18270A3282018-09-27027 September 2018 Attachment 7: Traveler TSTF-425 Versus Pnp RFOL SR Applicability Cross Reference Table ML18270A3272018-09-27027 September 2018 Attachment 6: No Significant Hazards Consideration PNP 2018-025, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b.2018-09-27027 September 2018 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b. ML18152A9292018-05-30030 May 2018 License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement PNP 2018-004, Supplement to License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications2018-01-24024 January 2018 Supplement to License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications PNP 2017-066, License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications2017-11-0101 November 2017 License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications PNP 2017-059, License Amendment Request Supplement - Cyber Security Plan Implementation Schedule2017-10-17017 October 2017 License Amendment Request Supplement - Cyber Security Plan Implementation Schedule PNP 2017-035, License Amendment Request - Administrative Controls for a Permanently Defueled Condition2017-07-27027 July 2017 License Amendment Request - Administrative Controls for a Permanently Defueled Condition PNP 2017-007, License Amendment Request, Cyber Security Plan Implementation Schedule2017-03-30030 March 2017 License Amendment Request, Cyber Security Plan Implementation Schedule PNP 2016-046, License Amendment Request for Editorial and Administrative Changes to Technical Specifications2016-11-0909 November 2016 License Amendment Request for Editorial and Administrative Changes to Technical Specifications PNP 2016-049, License Amendment Request: Control Rod Drive Exercise Surveillance2016-08-22022 August 2016 License Amendment Request: Control Rod Drive Exercise Surveillance PNP 2016-005, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing.2016-07-11011 July 2016 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing. PNP 2016-001, License Amendment Request - Revision to the Requirements for Steam Generator Tube Inspections and Repair Criteria in the Cold Leg Tube Sheet Region2016-03-0303 March 2016 License Amendment Request - Revision to the Requirements for Steam Generator Tube Inspections and Repair Criteria in the Cold Leg Tube Sheet Region PNP 2015-035, License Amendment Request - Cyber Security Plan Implementation Schedule2015-06-11011 June 2015 License Amendment Request - Cyber Security Plan Implementation Schedule PNP 2014-111, Revised License Condition - License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2014-12-18018 December 2014 Revised License Condition - License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors PNP 2014-091, Supplement to License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times2014-12-0909 December 2014 Supplement to License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times ML14237A1442014-12-0808 December 2014 Issuance of Amendment Cyber Security Plan Implementation Schedule ML14211A5252014-07-29029 July 2014 WCAP-17628-NP, Revision 1, Palisades, Alternate Pressurized Thermal Shock (PTS) Rule Evaluation. PNP 2014-049, License Amendment Request to Implement 10 CFR 50.61 a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.2014-07-29029 July 2014 License Amendment Request to Implement 10 CFR 50.61 a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events. PNP 2014-042, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process2014-06-11011 June 2014 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process PNP 2013-086, License Amendment Request - Cyber Security Plan Implementation Schedule2013-12-30030 December 2013 License Amendment Request - Cyber Security Plan Implementation Schedule PNP 2013-044, License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times2013-06-25025 June 2013 License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times PNP 2012-074, License Amendment Request - Technical Specifications Change to Add LCO 3.0.8 on the Lnoperability of Snubbers2012-09-0606 September 2012 License Amendment Request - Technical Specifications Change to Add LCO 3.0.8 on the Lnoperability of Snubbers PNP 2012-046, License Amendment Request - Cyber Security Plan Implementation Schedule Milestones2012-06-20020 June 2012 License Amendment Request - Cyber Security Plan Implementation Schedule Milestones PNP 2012-005, License Amendment Request - Replacement of Spent Fuel Pool Region 1 Storage Racks2012-02-28028 February 2012 License Amendment Request - Replacement of Spent Fuel Pool Region 1 Storage Racks PNP 2011-058, License Amendment Request to Revise Calculated Peak Containment Internal Pressure2011-08-16016 August 2011 License Amendment Request to Revise Calculated Peak Containment Internal Pressure PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years PNP 2011-002, License Amendment Request for Spent Fuel Pool Region I Criticality2011-01-31031 January 2011 License Amendment Request for Spent Fuel Pool Region I Criticality 2023-12-14
[Table view] Category:Technical Specification
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages ML21152A1132021-06-0101 June 2021 Palisade Nuclear Plant - Proposed Technical Specifications Bases Changes RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls PNP 2019-017, Submittal of Changes to Technical Specifications Bases2019-03-21021 March 2019 Submittal of Changes to Technical Specifications Bases PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. ML18270A3222018-09-27027 September 2018 Attachment 1: Description and Evaluation of Technical Specifications Changes ML18270A3242018-09-27027 September 2018 Attachment 3: Proposed Changes and Appendix a Technical Specifications Pages ML18270A3252018-09-27027 September 2018 Attachment 4: Page Change Instructions and Revised Pages, and Appendix a Technical Specifications ML18270A3262018-09-27027 September 2018 Attachment 5: Proposed Technical Specification Bases Changes PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases2017-11-0808 November 2017 Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases PNP 2016-046, License Amendment Request for Editorial and Administrative Changes to Technical Specifications2016-11-0909 November 2016 License Amendment Request for Editorial and Administrative Changes to Technical Specifications PNP 2014-088, Report to NRC of Changes to Technical Specifications Bases2014-09-15015 September 2014 Report to NRC of Changes to Technical Specifications Bases PNP 2014-042, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process2014-06-11011 June 2014 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases2012-11-0909 November 2012 Report to NRC of Changes to Technical Specifications Bases PNP 2011-032, Report to NRC of Changes of Technical Specifications Bases2011-04-25025 April 2011 Report to NRC of Changes of Technical Specifications Bases PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ML1020105792010-07-20020 July 2010 License Amendment Request for Emergency Diesel Generator Fuel Oil and Lube Oil Systems ML0930604142009-11-0202 November 2009 Report of Changes to Technical Specifications Bases ML0913501812009-05-14014 May 2009 Supplement to License Amendment Request: Changes to Technical Specification Administrative Controls Section ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0822703122008-08-14014 August 2008 Report of Changes to Technical Specifications Bases ML0723203952007-08-16016 August 2007 Report of Changes to Technical Specifications Bases ML0722201032007-07-25025 July 2007 Submittal of Technical Specifications Bases Changes ML0718002162007-06-28028 June 2007 License Amendment Request: Replacement of Containment Sump Buffer ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator ML0631803592006-11-0606 November 2006 License Amendment Request: Realistic Large Break Loss-of-Coolant Accident ML0628303852006-09-25025 September 2006 Alternative Source Term- Proposed License Amendment ML0623000332006-08-17017 August 2006 Report of Changes to Technical Specifications Bases ML0524102132005-08-22022 August 2005 Report of Changes to Technical Specifications Bases ML0425904452004-09-0202 September 2004 Report of Changes to Technical Specifications Bases ML0421604082004-08-0202 August 2004 Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0330001112003-10-17017 October 2003 Report of Changes to Technical Specifications Bases ML0328900502003-10-0606 October 2003 License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information ML0316110532003-06-0303 June 2003 License Amendment Request: Increase Rated Thermal Power ML0303805792003-01-22022 January 2003 Technical Specifications and Bases ML0231701012002-10-31031 October 2002 Report of Changes to Technical Specifications Bases ML0207201012002-03-0101 March 2002 License Amendment Request, Surveillance Requirement Frequency for Containment Spray Nozzle Inspections ML0205901512002-02-26026 February 2002 Amendment No. 207 Retechnical Specification on Spent Fuel Pool Boron Concentration ML18344A3791978-06-15015 June 1978 Proposed Technical Specification Changes on Power Distribution Limits ML18353B1461978-03-0909 March 1978 Iodine Removal System - Proposed Technical Specification Changes ML18353A8671978-02-22022 February 1978 Letter Proposed Technical Specifications Change on Heatup and Cooldown Curves for Cycle 3 Operation ML18353A8741978-02-21021 February 1978 Letter Proposed Technical Specifications Change on Steam Generator Operating Allowance ML18347A1881978-01-0303 January 1978 Proposed Technical Specifications Changes Relating to Overpressure Protection System ML18353B1451977-11-11011 November 1977 Transmittal of Technical Specification - Deletion of Annual Operating Report ML18353B1471977-11-10010 November 1977 Proposed Technical Specification Changes for Steam Generator Inservice Inspection 2023-12-14
[Table view] Category:Amendment
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0718002162007-06-28028 June 2007 License Amendment Request: Replacement of Containment Sump Buffer ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator ML0631803592006-11-0606 November 2006 License Amendment Request: Realistic Large Break Loss-of-Coolant Accident ML0628303852006-09-25025 September 2006 Alternative Source Term- Proposed License Amendment ML0421604082004-08-0202 August 2004 Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0328900502003-10-0606 October 2003 License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information ML0316110532003-06-0303 June 2003 License Amendment Request: Increase Rated Thermal Power ML0205901512002-02-26026 February 2002 Amendment No. 207 Retechnical Specification on Spent Fuel Pool Boron Concentration ML18344A3791978-06-15015 June 1978 Proposed Technical Specification Changes on Power Distribution Limits ML18347A1881978-01-0303 January 1978 Proposed Technical Specifications Changes Relating to Overpressure Protection System ML18353B1471977-11-10010 November 1977 Proposed Technical Specification Changes for Steam Generator Inservice Inspection ML18347A1711977-09-26026 September 1977 Additional Information Relating to Power Increase Request ML18348A7651976-11-16016 November 1976 Proposed Change to Technical Specification to Modify Spent Fuel Storage Facility ML18347A5511976-10-0808 October 1976 Transmitting Proposed Change to Tech Spec Concerning Operability & Surveillance Requirements for Hydraulic Shock Suppressors ML18347A6601976-06-0909 June 1976 Re Cpc'S 5/25/1976 Event Report, Requesting Change to Tech Spec to Operation of Diesel Generator with One High-Pressure Safety Injection Pump Out of Service ML18348A7701976-03-12012 March 1976 Proposed Change to Technical Specification to Modify Requirements for Testing of Primary System Pump Combinations & for Load Testing of Diesel Generators ML18348A7751976-02-25025 February 1976 Proposed Change to Technical Specification to Delete Requirement for Operation of Fuel Pool Charcoal Adsorber After I-131 Level in Irradiated Fuel Has Decayed by Factor of 10 ML18348A7761976-01-30030 January 1976 Proposed Change to Technical Specification to Generalize Tech Spec to Allow for Reactor Refueling Without Requiring Additional Tech Spec Changes ML18348A7801976-01-30030 January 1976 Proposed Change to Technical Specification to Revise Steam Generator Tube Plugging Criteria ML18348A7861975-03-10010 March 1975 Proposed Change to Technical Specification Based on Eddy-Current Inspection of Steam Generator 2023-12-14
[Table view] |
Text
consumers Power company*
General Offices: 212 West Michigan Avenue, Jackson, Michigan .49201
- Area Code 517 788-0550 January 3, 1978 Director of Nuclear Reactor Regulation Att: Mr Albert Schwencer, Chief Operating Reactors Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET.50-255 - LICENSE DPR PALISADES PLANT - OVERPRESSURE PROTECTION SYSTEM Attached are proposed.Technical Specifications changes relating to the Palisades Plant overpressure protection system. The purpose of these proposed changes are to meet requirements established by the NRC staff in their l_etter of July 18, 1977 which documented the review of plant specific reports concerning low-temperature reactor vessel overpressure p~otection systems.
The Palisades Plant specific analysis was submitted on June 24, 1977 and supple-mented on November 28, 1977. Attachments 1 and 2 of this letter provide an update of the Palisades Plant "overpressure protection subsystem" and responses to the July 18, 1977 staff "positions."
~~(/?~mcuJ David P Hoffman Assistant Nuclear Licensing Administrator CC:. JGKeppler, USNRC
CONSUMERS POWER *COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Speci-fications contained in Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972 for the Palisades Plant be changed as described in Section I below:
I. Changes A. Add the following paragraph:
"3.1.1.i. During the cooldown of the primary coolant system, the
.cold leg temperature shall not be decreased below 225°F until the overpressure protection system is enabled for operation at the low set point of 400 psia. The over-pressure protection system shall remain in the armed condition whenever the PCS co~d leg temperature is below 225°F and the primary coolant system is not otherwise protected from overpressurization."
B. Add the following paragraph:
"3.1.1.h. During cooldown, at least one PCP must be in operation until there are equilibrium conditions (That 2_ Tcold + 2°F) in the PCS and the PCS is 180°F or less."
C. To the end of BASIS section of 3.1.1, add:
"The Palisades Plant overpressurization analysis(5) had identified design bases transients that must be protected against to assure that 10 CFR 50, Appendix G limits are not exceeded. Current control is accomplished by utilizing an overpressure protection system during particular PCS conditions.
(5),Palisades Plant Overpressurization Analysis,' Energy Incorporated, June, 1977."
D. Add the following paragraph:
"3. 3. 3 Whenever the pressurizer pressure is below 1, 400 psia., and the PCS is not otherwise protected from overpressurization, the control system fuses in their fuse holders for the HPSI pumps (P66A, P66B and P66C) are to be removed from- the circuit."
E. Add to. Table 4.1. 3:
"TABLE 4 .1. 3 Surveillance Channel Description Function Frequency Surveillance Method
- 15. PCS Overpres- A. Test R A. Introduce simulate signal sure Protec- levels sufficient for system tion System operations. Observe sole-noid actuation ..
B. Calibrate R B.
(1) Temper- (1) Apply known resistances ature for temperature devices.
(2) Pressure (2) Apply known pressures."
II. Discussion The above Technical Specifications changes are being proposed to complete requirements identified by the staff in their review of the plant specific reports concerning low-temperature reactor vessel overpressure protection systems.
III. Conclusion Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board have reviewed these proposed Technical Specifi-cations changes and recommend their approval.
CONSUMERS POWER COMPANY C R Bilby, Production & Transmission Sworn and subscribed to before me this 3rd day of January 1978. /.': ,,-'.' .,, .
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y Public Jackson County, ichigari My commission expires July 9, 1979.
ATTACHMENT 1 PALISADES PLANT PRIMARY COOLANT SYSTEM OVER~RESSURIZATION SUBSYSTEM DESCRIPTION PREPARED BY ENERGY INCORPORATED NOVEMBER 1977 FOR CONSUMERS POWER COMPANY
PALISADES PLANT PRIMARY COOLANT SYSTEM OVERPRESSURIZATION PROTECTION SUBSYSTEM
- Purpose The Primary Coolant System Overpressurization Subsystem is designed to provide automatic pressure relief of the primary coolant system whenever the conditions of low temperature (250°F or lower) and high pressure (400 psia or higher) exist concurrently.
General Two redundant and separate overpressurization protection channels are provided. A channel includes a power operated pressure relief valve (PORV), a temperature loop, a pressure loop, a control switch and indicator lights. The channels are identified as channel 11 A11 and channel 11 8 11
- Figure 1. is a logic diagram for channel 11 A11
- Pressure relief for the primary coolant system is ac.complished by the automatic opening of power operated relief valves (PORV) PRV-10428 and/or PRV-10438. The automatic opening will occur when the primary system temperature is less than 250°F and the pressure is equal to (or greater than) 400 psia.
Two redundant and separate pressure and temperature control loops will be utilized.
Each control loop will be powered from a separate power source. Channel
.separation will be provided either by distance or physical barriers separating wire and equip.ment.
Three annunciators are provided and are labeled:
KEY SIHTCH HS-Ol05A I
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{OVERPRESSURE ,_____._.~ IND I CA TOR MID . ~ PROTECTION LIGHT l~ . CIRCUIT A -.,.,.....,,, ..... ~*------
ARMED M0-1042A OPEN I *.
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ANNUNCIATOR i--en- PORV OPEN T::. 250F l PSX-0105A-l (PR~r6~
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PTR-Oll 5A LOOP - AND I - ACTUATED
- . ACTUATED P.?_ 400 PSIA RED PT-Ol05A PSX-0105/\-2 IflDICATOR LOOP LIGHT ACTUATED FIGURE -1
(1) 11 NO PCS PROTECTIOW (2) "PCS PRESSURE 375 PSIA" (3) 11 PORV OPEN" The first annunciator will advise the operator to arm the system (if it has not already been done) when the primary coolant system (PCS) decreases to a temperature of 300°F as the syst~m is cooled down from an operating -1 I
I condition. Figure 2 is a logic diagram for the 11 No PCS Protection" annunciator.
The second annunciator advises the operator of an approaching high pressure condition whenever the PCS is in a water solid condition.
The third annunciator advises the operator that the pressure has increased to 400 psia and the PORV's have been opened.
A key lock switch is provided for arming each channel. Indicator lights on the control' panel light to inform the operator that (1) the isolation valves are open, (2) the overpressurization system is armed and (3) the overpressurization system has been activited.
Figure 3 shows the arrangement of controls and indicator lights.
Detailed Description Figures 4a and 4b show the schematic diagrams for actuation of pressure relief channel "A". Pressure relief channel 11 8 11 will be identical. The operation of channel 11 A11 is described in detail below (refer to Figures 4a and 4b).
To provide PCS pressure relief, both the isolation valve M0-1042A and PORV PRV-10428 must be open. M0-1042A is opened by using the existing control switches located on control panel section C-02. When M0-1042A T< 300F PTTf--0 l l 5f\
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NO PCS PROTECTION NAtlD OVERPRESSURE PROTECTIOf'I c IRCUIT "/\,II NOT .l\RMED a
- v 1.WEf:PRESSURE PROTECT! OrJ CIRCUIT "B" iJOT f\RtlED FIGURE 2
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is open, contact POS...,L closes actuating relay POSX-0105A-l. One contact of POSX-0105A-l actuates a position indication light on panel C-02. The other contact of POSX-Ol05A-l is in the channel 11 A11 11 Armed 11 circuit.
The Over Pressure Protection System channel 11 A11 is in an 11 Armed 11 condition if key lock switch HS-Ol05A is closed and the POSX-Ol05A-l armed contact is closed (the POSX-0105A-l armed contact will close when M0-1042A is open). When channe 1 11 N' is 11 A.rmed 11 , a white 1 i ght on pane 1 C-12 wi 11 be illuminated and automatic opening of PRV-10428 will result upon low-low primary coolant temperature (250°:F) arid high-high pressure (400 psia).
During system shutdown the pressure and temperature will be decreased.
When the temperature in loop lA decreases to 250°F (as sensed by TS-0115),
the LOW PCS TEMP-A contact opens and provides an annunciation unless both pressure relief channels A and 8 are armed. If both channels A and 8 are armed, contacts POSX-OlOSA-2 and POSX-01058-2 will be closed and the annunciator is not received.
When the PCS temperature is at 250°F or below the LOW PCS TEMP-A contact (TS-0115) is closed, and if the PCS pressure rises to 375 psia (as sensed by PT-OlOSA), a high pressure contact (PS-Ol05A) will close actuating relay PSX-Ol05A-3 and an annunciator, alerting the operator of approaching high PCS pressure, will be received. If the pressure continues to rise and reaches a value of 400 psia, the high-high pressure contact will close actuating relays PSX-OlOSA-1 and PSX-OlOSA-2. A ~ontact of PSX-OlOSA-1 closes to actuate SV-10428 which operates PRV-10428. A 11 second contact of PSX-lOlSA-1 closes to actuate the annunciator PORV
. ) OPEN 11
- A contact of PSX-OlOSA-2 closes to actuate a red light on panel C-12.
This light will remain illuminated until it is reset by operator initiation of PB/0105A.
Equipment Two new pressure transmitters (Rosemount Model 1151) will be installed for the pressure control loop. Radiation levels have been established for the installed locations which are below the rated capabilities of the transmitters.
Existing temperature control loops will be utilized. Rochester Instrument System Model ET-215 solid state electronic alarm modules will be installed to provide the contact closures required for actuation of the overpressuriiation system relays.
The relays to be used are Allen-Bradley series 700 AC control relays.
ATTACHMENT 2 The July 18, 1977 NRC letter contained the eight staff positions. Consumers Power has addressed these items previously in the submittal of the Palisades Plant specific report and supplements. To consolidate our position, the following responses are provided:
- 1. 6T Across Steam Generator: A number of licensees are assuming a maximum 6T across the steam generator in their analyses of energy addition transients.
However, the licensees are not specifying how they will limit the 6T nor how they will monitor the 6T.
Staff Position: Certain energy addition scenarios may be eliminated by admin-istrative methods. The methods for maintaining less than a specified 6T across the steam generator shoul~ be clearly spelled out as well as the means of monitoring this maximum 6T.
Response
The worst case PCS overpressure event as revealed by the specific plant analy-sis is the start of a primary coolant pump with a 6T of 70°F. This 6T of 70°F is the temperature differential that could exist between the steam generator in total and the rest of the primary system after the primary coolant pumps have been shut down and shutdown cooling has reduced the rest of the primary system to 120°F.
The plant operating procedures dictate that the last primary coolant pump shall not be shut down until the PCS has reached a temperature of 160°F to 180°F. Since the secondary side of the steam generator is vented to the condenser and its physical construction is designed expressly to transfer heat across the primary to secondary interface, the wate'T on both sides of the unit will assume the same temperature. Furthermore, an analysis, by energy*incorporated concerning the residual heat in the steam generator for extremely conservative conditions, shows the temperature of the water on the primary side will rise only 2°F after the PCP has been shut down three hours.
Therefore, present temperature monitoring instrumentation is adequate to determine the temperature of the steam generator when the last primary coolant pump is shut down and the physical characteristics of the unit will ensure that its temperature does not increase with time. The temperature differ-ential that must be considered is then that which exists in the PCS when the last primary coolant pump is shut down and that which exists when shutdown cooling is secured. Worse Case is 180°F - 120°F = 60°F. The specific plant analysis considered a 6T = 70°F and determined that ~ PORV was capable of mitigating this event. Th~s analysis leads us to the conclusion that tempera-ture monitoring of secondary side of the steam generator is of no value and will not be implemented. Proposed Technical Specification 3.1.1.h. supports our conclusions.
.e
- 2. Isolation Valve Alarm: The upstream isolation valve from the PORVs must be open for the overpressure protection system to properly function. Some means should be provided to insure proper alignment of the isolation valve during overpressure protect~on system operation.
Staff Position: The position of the upstream isolation valve should be wired into the overpressure pro~ection alarm so that the alarm will not clear unless the system is enabled and the isolation valve is open.
Response
The overpressure protection system is designed to ensure that the isolation valves M0-1042A and M0-1043A must be open to allow the arming of.the system.
If, in fact, they are not opened, the "armed" indicating light will not illumi-nate when the keylock switch is turned to the "on" position and the annunciator window "no PCS *protection" will alarm when the PCS temperature decreases below 300°F.
- 3. PORV Train Separability: A number of licensees have designed systems with one set point switch and one hi/low reset switch for both PORVs.
Staff Position: In order to assure redundancy of the PORVs, each should have an independent keylock enable/disable switch and a hi/low reset switch or similar arrangement. Additionally, the PORVs should be connected to separate vital buses or power supplies.
Response
The overpressure protection system has two independent and redundant channels "A" and "B," each with its own keylock arming switch and alarm reset push button. Also, each channel derives its power from separate vital power buses.
Channel "A" is connected through fuses to bus Y30 breaker #7 and channel "B" is connected through fuses. to bus Y to breaker #7.
- 4. Circuit Diagrams: Licensees have not been submitting detailed circuit dia-grams with their plant specific reports.
Staff Position: Licensees should submit a detailed diagram of the overpres-sure protection circuitry with their plant specific reports for review by NRC.
Response
Detailed diagrams, schematics, and system operating description are included in the report "Palisades Plant Primary Coolant System Overpressurization Sub-system Description" and the construction package. This information is an attachment to this letter.
- 5. PORV Valve Cycling: Cycling of PORVs has not been addressed in the Combustion Engineering generic or plant specific reports.
Staff Position:. The results of your transient .pressure analysis should be extended beyond the first pressure cycle. The capabilities of the PORVs with regard to pressure cycling should be .discussed in detail. If the valves do not cycle, the consequences of pressure undershoot and its effect on reactor coolant pumps should be discussed.
Response
The PCS overpressure protection system is designed to open the PORVs, PRV-1042B and PRV-1043B, whenever the PCS temperature is less than 250°F and the pressure exceeds 400 psia. Further, the valves will close when the PCS pressure de-creases to 400 psia. This circuit configuration will produce valve cycling with a cycle time of 31 seconds and will result in approximately 20 valve opening-closing cycles before credit can be taken for operator action at the.
10-minute mark. This cycle time can be increased to 80 seconds or approxi-mately 7 cycles if the circuit dead band is increased to allow the PCS pressure to sag to 200 psia. A PCS pressure of 200 psia is considered the lowest pres-sure level that can be tolerated before appreciable primary coolant pump seal degradation will be experienced.
Considered opinion is that 20 valve cycles will not be any more damaging to the valve than 7 cycles, simply because if damage to the valve occurs it will take place in the first few cycles of operation. Any foreign material in the system in the vicinity of the valve will pass over its seat in the initial operation of the valve. The valve testing program should reveal the degrada-tion effects, if any, that cycling will have on the valve.
- 6. IEEE 279 and Seismic Criteria: IEEE 279 and Seismic Criteria should be con-sidered in the design of the overpressure protection system. Deviations from these standards should be clearly described and detailed justification should be provided.
Response
The PCS overpressure protection system design in regard to IEEE 279 and Seismic Criteria has been clearly addressed.in the plant specific analysis. This sys-tem has been designed to comply with the requirements of the original plant design under which it was licensed to operate. There is no single failure of a component or system or single event that has been identified in our analysis as capable of both causing an overpressure event and defeating the protection afforded against such events.
- 7. Testability: The program for testing the PORVs for low pressure protection system operability is not addressed in the plant specific reports.
Staff Position: The control circuitry from pressure sensor to valve solenoid should be tested prior to each heatup or cooldown. The PORVs should be stroked during each refueling. Deviations from this criterion should be justified.
Response
The location of the valve and its solenoid in addition to its physical con-struction/operation makes testing the PCS overpressure protection system during operation.prior to cooldown not possible. The electrical portion of the sys-tem will be tested and calibrated during each refueling outage. And since the valve itself is pilot-operated, it cannot be stroked without a pressure differ-ential existing across it. Therefore, the valve testing and frequency will be in compliance with the applicable requirements of ASME Code Section XI, Sub-section IWV, and addressed in the Palisades Plant Inservice Inspection Program.
- 8. Technical Specifications: The overpressure protection system is not being designed to mitigate the consequences of certain scenarios. This may be accept-able if the scenario is made extremely improbable by appropriate administrative measures. However, these administrative procedures have not been discussed in the reports reviewed thus far.
Staff Position: If a scenario is to be administratively eliminated or miti-gated, the actions required to change the scenario should be placed in the Technical Specifications. A draft of the Technical Specifications should be provided with the plant specific report or soon after it is submitted. Some items which should probably be included in the Technical Specifications are:
- a. Enabling/disabling the Overpressure Protective System.
- b. Maintaining maximum ~T across the steam generator.
- c. Disabling pumps, accumulators, heaters.
- d. Testing PORV and control circuitry.
- e. Testing ECCS with head off.
Response
Proposed Technical Specifications changes are attached which address the staff position.