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Issue date | Title | Topic | |
---|---|---|---|
ML17037C177 | 19 December 1975 | Letter Enclosing a Corrected Attachment to License Amendment No. 11 Change No. 27 to the Technical Specifications Provisional Operating License No. DPR-16 | |
ML17037C183 | 3 November 1975 | Letter Regarding Application for Amendment to Technical Specifications and an Inadvertent Error Not Made on the Persons Listed in the Certificate of Service | |
ML17037C271 | 29 July 1975 | Letter Enclosing a Report on Environmental Qualification Test Results Applicable to the Main Steam Isolation Valve Position Switch | |
ML17037C272 | 21 January 1975 | Letter Transmitting Four Proposed Changes to the Technical Specifications Concerning Changes in Plant Organization and Set Points for Reactor Water Levels | |
ML17037C333 | 21 April 1972 | Letter Responding to the March 21, 1972 Letter Requesting Additional Information Regarding Proposed Changes to the Technical Specifications and Bases | |
ML17037C335 | 18 June 1971 | Letter Responding to the April 14, 1971 Letter Regarding Change No. 4 to the Technical Specifications and Enclosing a New Printing with Changes No. 1 and 3 and a Number of Additional Changes | Fuel cladding |
ML17037C337 | 9 December 1969 | Letter Enclosing Change Request No. 2 Requesting a Modification to the Safety Limit on Fuel Cladding Integrity and Advising That the Change Has Been Reviewed and Bears the Approval of the Station Operations Review Committee ... | Fuel cladding |
ML17037C413 | 22 July 1977 | Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization | |
ML17037C414 | 18 July 1977 | Letter Enclosing an Application for Amendment to Operating License and Proposed Changes to the Technical Specifications to Provide for More Flexible Operation and Concerning Load Line Limit Analysis | Fuel cladding |
ML17037C416 | 14 July 1977 | Application for Amendment to Operating License and Proposed Change to Technical Specification Concerning the Emergency Cooling System | |
ML17037C418 | 19 May 1977 | Letter Enclosing an Application to Amend Operating License and a Requested Change in the Technical Specifications Relating to Instrumentation Used to Monitor Drywell Suppression Chamber Differential Pressure and Suppression .. | |
ML17037C433 | 8 August 1977 | Letter Regarding Surveillance Requirements and Limiting Conditions for Operations and Requesting an Application for Amendment to the Operating License That Will Change the Technical Specifications | Fuel cladding |
ML17037C434 | 4 March 1977 | Letter Regarding a Preliminary Review of the December 7, 1976 Request for Technical Specification Changes to Reactor Operating Limits After Reload for Cycle 5 Operation and Requesting Additional Information to Complete Review | Shutdown Margin |
ML17037C439 | 30 September 1976 | Letter Requesting Submittal of an Application for License Amendment to Incorporate the Requirements of the Model Technical Specifications | |
ML17037C453 | 19 January 1976 | Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications (Appendix a) to Clarify Cloride and Oxygen Levels | |
ML17037C454 | 8 September 1975 | Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications Correcting Errors in a Submittal Made August 15, 1975 in Connection with Reload Cycle 5 | |
ML17037C456 | 11 August 1975 | Letter Transmitting Application for Amendment to Technical Specifications to Provide Reporting Intervals and Organizational Information Consistent with Appendix a of License Nos. DPR-63 and DPR-59 | |
ML17037C458 | 27 March 1975 | Letter Responding to the February 15, 1975 Correspondence Concerning the Steam Quenching Vibration Phenomenon and Advising an Investigation Is in Progress and Will Be Submitted by May 30, 1975 | |
ML17037C459 | 27 February 1975 | Letter Transmitting an Application for Amendment to Technical Specifications to Correct Errors in the Current Appendix a and to Provide for the Addition of the Reactor Building Extension | |
ML17037C460 | 18 November 1974 | Proposed Changes to the Technical Specifications Concerning the Addition of a Surveillance Requirement for the Seismic Snubbers for the Emergency Cooling System | |
ML17037C461 | 25 September 1974 | Letter Transmitting Amendment to the Operating License Consisting of Changes to the Technical Specifications. Changes Increase the Safety Margin for the Isolation Function for the Emergency Condensers | |
ML17037C462 | 15 February 1974 | Letter Transmitting Proposed Changes to Technical Specifications for the Maintenance of Pressure Suppression Chamber Integrity | |
ML17037C468 | 23 September 1975 | Letter Regarding a Stress Assisted Corrosion Problem and an Enclosed Safety Evaluation by the Office of NRR - Supporting Amendment to License No. DPR-63 and Changes to the Technical Specifications Inoperable Control Rod .. | Overtravel |
ML17037C475 | 10 December 1974 | Letter Regarding Review of Technical Specifications Related to Installed Filter Systems and Requesting a Submittal of Application for Amendment to Technical Specifications in Conformance with Model Specifications | |
ML17037C478 | 22 October 1974 | Letter Requesting Submittal of an Application for an Amendment to the Facility Operating License to Revise the Administrative Controls Section of the Technical Specifications | |
ML17037C513 | 31 January 1974 | Letter Submitting Description of Proposed Modification. Change Consists of Providing an Extension to the Existing Reactor Building to Facilitate Spent Fuel Handling Operations | |
ML17037C516 | 22 January 1974 | Letter Submitting Analyses Which Determine Effects of Fuel Densification and Appropriate Changes to Technical Specifications for Fuel to Be Inserted During Spring 1974 Refueling | |
ML17037C519 | 13 December 1973 | Informs That Results of Generic Analyses Are Reported in General Electric'S NEDO-20181 | |
ML17037C523 | 11 January 1973 | Letter Submitting Report Describing Proposed Change for NMP Unit 1 on Access Platform Be Added to the Refueling Bridge Structure to Expedite Refueling Operation and Also Enhance Safety | |
ML17037C554 | 4 April 1973 | Letter Requesting Change to Technical Specifications Regarding the Removal of All Baffling from within the Torus and to Begin Installation of Rams Head on the Existing Electromatic Relief Valve Discharge Piping | |
ML18018B046 | 22 March 1978 | Letter Transmitting an Application for Amendment to Appendix a of the Operating License | |
ML18018B070 | 23 November 1973 | Responses to Questions Relating to Changes to the Technical Specifications | Safe Shutdown High Radiation Area Ultimate heat sink Hydrostatic Coatings Scram Discharge Volume Earthquake Fuel cladding |
ML18018B080 | 22 August 1969 | Appendix a to Provisional Operating License DPR-17 Technical Specifications and Bases | Shutdown Margin Scram Discharge Volume Overtravel Earthquake Power-Operated Valves Fuel cladding |
ML22292A131 | 5 October 2022 | 5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69 | |
ML22298A011 | 25 October 2022 | License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. | Reactor Vessel Water Level Post Accident Monitoring |
NMP1L3010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) | 26 March 2015 | Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) | Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Squib Surveillance Frequency Control Program Scram Discharge Volume Excess Flow Check Valve Recently irradiated fuel Offsite Circuit |
NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) | 12 May 2015 | Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) | |
NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance | 18 March 2016 | License Amendment Request - Reactivity Anomalies Surveillance | Shutdown Margin Anticipated operational occurrence |
NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. | 12 August 2022 | License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. | Surveillance Frequency Control Program |
NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b | 15 December 2022 | License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b | Hot Short Safe Shutdown High winds Reactor Vessel Water Level Mission time Tornado Missile Safe Shutdown Earthquake Internal Flooding Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Operator Manual Action Zebra Mussel Emergency Lighting FLEX Fukushima Dai-Ichi Seismically rugged Surveillance Frequency Control Program Scram Discharge Volume Large early release frequency Excess Flow Check Valve Flooding Focused Evaluation Earthquake Turbine Missile Offsite Circuit Seismic Walkdown Report |
NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change | 17 November 2014 | License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change | Anticipated operational occurrence |
NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual | 23 March 2015 | License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual | Stroke time Squib |
NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request | 24 September 2015 | Supplemental Information Regarding TSTF-425 License Amendment Request | Shutdown Margin Ultimate heat sink Squib Surveillance Frequency Control Program Scram Discharge Volume Offsite Circuit |
NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 | 28 February 2017 | License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 | Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Stroke time Water Inventory Control Post Accident Monitoring Operating Basis Earthquake Surveillance Frequency Control Program Scram Discharge Volume Power Operated Valves Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Scaffolding |
NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note | 22 August 2017 | License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note | |
NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 | 12 January 2018 | Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 | Water Inventory Control |
NMP2L2693, Technical Specification Bases, Rev. 57 | 24 October 2018 | Technical Specification Bases, Rev. 57 | |
NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 | 12 December 2019 | Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 | Surveillance Frequency Control Program |
NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control | 26 May 2021 | License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control | Safe Shutdown Anticipated operational occurrence Surveillance Frequency Control Program Offsite Circuit |
NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements | 30 September 2021 | Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements | Reactor Vessel Water Level Ultimate heat sink Stroke time Water Inventory Control Operating Basis Earthquake Surveillance Frequency Control Program Control of Heavy Loads Power Operated Valves Fuel cladding Offsite Circuit Scaffolding |