| | Site | Start date | Reporting criterion | Title |
|---|
| ZS-2013-0195, Fire Protection Report, Amendment 13 | Zion | 31 July 2013 | | Fire Protection Report, Amendment 13 |
| ZS-2012-0268, Quality Assurance Program Application to Transportation Activities Pursuant to 10 CFR 71.101(f) and Zionsolutions Quality Assurance Project Plan (Qapp) Periodic Update Submittal | Zion
07100956 | 12 July 2012 | | Quality Assurance Program Application to Transportation Activities Pursuant to 10 CFR 71.101(f) and Zionsolutions Quality Assurance Project Plan (Qapp) Periodic Update Submittal |
| ZS-2011-0166, Quality Assurance Program for the Independent Spent Fuel Storage Installation | Zion
07100950 | 23 February 2011 | | Quality Assurance Program for the Independent Spent Fuel Storage Installation |
| WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies | Wolf Creek | 20 April 2020 | | License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies |
| WO 16-0045, Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors | Wolf Creek | 30 September 2016 | | Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
| WO 03-0051, Revision to Technical Specification (TS) 5.5.6, Containment Tendon Surveillance Program, and TS 5.5.16, Containment Leakage Rate Testing Program | Wolf Creek | 17 October 2003 | | Revision to Technical Specification (TS) 5.5.6, Containment Tendon Surveillance Program, and TS 5.5.16, Containment Leakage Rate Testing Program |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions | Wolf Creek | 31 May 2016 | | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls | Wolf Creek | 31 May 2016 | | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features | Wolf Creek | 31 May 2016 | | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements | Wolf Creek | 31 May 2016 | | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant | Wolf Creek | 31 May 2016 | | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant |
| WM 16-0008, Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, Calculation No. XX-E-013, Rev 4, Post-Fire Safe Shutdown Analysis | Wolf Creek | 31 May 2016 | | Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, Calculation No. XX-E-013, Rev 4, Post-Fire Safe Shutdown Analysis |
| WM 10-0017, Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical Cable | Wolf Creek | 2 June 2010 | | Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical Cable |
| WBL-19-013, 10 CFR 50.59 Summary Report | Watts Bar | 11 April 2019 | | 10 CFR 50.59 Summary Report |
| W3P89-2161, 1989 Rept of Facility Changes,Tests & Experiments Per 10CFR50.59 | Waterford | 31 December 1989 | | 1989 Rept of Facility Changes,Tests & Experiments Per 10CFR50.59 |
| W3P88-0076, Forwards 1987 Annual Fire Protection Rept Per Condition 2.C.9.c of License NPF-38.Rept Describes Changes to Approved Fire Protection Program as Discussed in FSAR Through Amend 36 | Waterford | 10 May 1988 | | Forwards 1987 Annual Fire Protection Rept Per Condition 2.C.9.c of License NPF-38.Rept Describes Changes to Approved Fire Protection Program as Discussed in FSAR Through Amend 36 |
| W3P87-2524, Application for Amend to License NPF-38,implementing Change in Annulus Fire Detection Sys by Changing Number of Fire Detection Instruments & Zones of Detection Providing Indication of Fire in Annulus.Fee Paid | Waterford | 11 December 1987 | | Application for Amend to License NPF-38,implementing Change in Annulus Fire Detection Sys by Changing Number of Fire Detection Instruments & Zones of Detection Providing Indication of Fire in Annulus.Fee Paid |
| W3P87-1792, Requests Concurrence to Revise Containment Integrated Leak Rate Test Duration from 24 H to Period Consistent W/Topical Rept BN-TOP-1, Testing Criteria for Integrated Leak Rate Testing of Primary Containment Structures .... Fee Paid | Waterford | 6 October 1987 | | Requests Concurrence to Revise Containment Integrated Leak Rate Test Duration from 24 H to Period Consistent W/Topical Rept BN-TOP-1, Testing Criteria for Integrated Leak Rate Testing of Primary Containment Structures .... Fee Paid |
| W3P87-1630, Responds to Questions Re Fault Trees Associated W/Control Sys Single Failure Study.W/Two Oversize Drawings | Waterford | 8 July 1987 | | Responds to Questions Re Fault Trees Associated W/Control Sys Single Failure Study.W/Two Oversize Drawings |
| W3P86-3303, Requests Relief from Requirements of Tech Spec 3.3.3.8 Re Performance of Fire Watch for Annulus Area Every 8 H When Certain Level of Fire Detection Instrumentation Considered Inoperable | Waterford | 10 September 1986 | | Requests Relief from Requirements of Tech Spec 3.3.3.8 Re Performance of Fire Watch for Annulus Area Every 8 H When Certain Level of Fire Detection Instrumentation Considered Inoperable |
| W3P85-0130, Forwards Rept on License Condition 16 Evaluating Potential Adverse Effects of Failure of Containment Coatings on post-accident Fluid Sys | Waterford | 17 January 1985 | | Forwards Rept on License Condition 16 Evaluating Potential Adverse Effects of Failure of Containment Coatings on post-accident Fluid Sys |
| W3P84-1695, Forwards Updated Operator Shift Experience Form,In Response to 840523 Request.Options for Satisfying Shift Operating Experience Requirements at 5% Power Listed.Resumes Encl | Waterford | 15 June 1984 | | Forwards Updated Operator Shift Experience Form,In Response to 840523 Request.Options for Satisfying Shift Operating Experience Requirements at 5% Power Listed.Resumes Encl |
| W3P82-3908, Responds to IE Info Notice 82-40 & IE Bulletin 82-04.Util Has No Bunker-Ramo Electrical Penetration Assemblies in Use or Planned for Use at Facility | Waterford | 12 January 1983 | | Responds to IE Info Notice 82-40 & IE Bulletin 82-04.Util Has No Bunker-Ramo Electrical Penetration Assemblies in Use or Planned for Use at Facility |
| W3P81-1468, Forwards marked-up Addl Info Needed for SER Input,In Response to NRC Request.Fsar Section 7.3.1.6 Draft Revision Contains Description of Changes to Emergency Feedwater Sys Controls.Revision Will Be Incorporated Into FSAR Amend 19 | Waterford | 12 June 1981 | | Forwards marked-up Addl Info Needed for SER Input,In Response to NRC Request.Fsar Section 7.3.1.6 Draft Revision Contains Description of Changes to Emergency Feedwater Sys Controls.Revision Will Be Incorporated Into FSAR Amend 19 |
| W3P81-1169, Forwards Itemized Reviews of Compliance W/Various Sections of 10CFR.Util Meets or Exceeds Requirements | Waterford | 29 April 1981 | | Forwards Itemized Reviews of Compliance W/Various Sections of 10CFR.Util Meets or Exceeds Requirements |
| W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program | Waterford | 8 May 2024 | | Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program |
| W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt | Waterford | 1 October 2021 | | Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt |
| W3F1-2021-0035, Technical Requirements Manual Update | Waterford | 18 May 2021 | | Technical Requirements Manual Update |
| W3F1-2021-0003, Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B | Waterford | 8 February 2021 | | Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B |
| W3F1-2018-0031, Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components | Waterford | 13 June 2018 | | Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components |
| W3F1-2017-0081, Amendment 1 to License Renewal Application (Laa) | Waterford | 15 November 2017 | | Amendment 1 to License Renewal Application (Laa) |
| W3F1-2017-0075, Submittal of the Inservice Testing Plan for the Fourth 10-Year Interval | Waterford | 4 December 2017 | | Submittal of the Inservice Testing Plan for the Fourth 10-Year Interval |
| W3F1-2017-0046, Relief Requests Associated with the Fourth Inservice Testing Interval | Waterford | 13 June 2017 | | Relief Requests Associated with the Fourth Inservice Testing Interval |
| W3F1-2017-0003, Responses to Request for Additional Information Set 10 Regarding the License Renewal Application | Waterford | 19 January 2017 | | Responses to Request for Additional Information Set 10 Regarding the License Renewal Application |
| W3F1-2016-0075, Responses to Request for Additional Information Set 6 Regarding the License Renewal Application | Waterford | 7 December 2016 | | Responses to Request for Additional Information Set 6 Regarding the License Renewal Application |
| W3F1-2016-0074, Responses to Request for Additional Information Set 5 Regarding the License Renewal Application | Waterford | 7 December 2016 | | Responses to Request for Additional Information Set 5 Regarding the License Renewal Application |
| W3F1-2016-0041, Technical Specification Index and Bases Update to NRC for Period November 4, 2014 Through May 31, 2016 | Waterford | 2 June 2016 | | Technical Specification Index and Bases Update to NRC for Period November 4, 2014 Through May 31, 2016 |
| W3F1-2016-0040, Technical Requirements Manual Update to the NRC | Waterford | 2 June 2016 | | Technical Requirements Manual Update to the NRC |
| W3F1-2016-0031, Notification of Full Compliance with EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events | Waterford | 21 July 2016 | | Notification of Full Compliance with EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events |
| W3F1-2015-0047, Provides Additional Information to Support Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Frequency to 15 Years | Waterford | 18 June 2015 | | Provides Additional Information to Support Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Frequency to 15 Years |
| W3F1-2015-0028, Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years | Waterford | 15 April 2015 | | Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years |
| W3F1-2015-0021, Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years | Waterford | 4 May 2015 | | Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years |
| W3F1-2015-0006, Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part | Waterford | 17 June 2015 | | Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 3 of 5 |
| W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years | Waterford | 28 August 2014 | | License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years |
| W3F1-2013-0054, CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B | Waterford | 9 September 2013 | | CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B |
| W3F1-2013-0048, Supplement to NFPA 805 License Amendment Request (LAR) | Waterford | 18 December 2013 | | Supplement to NFPA 805 License Amendment Request (LAR) |
| W3F1-2013-0040, Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013 | Waterford | 9 July 2013 | | Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013 |
| W3F1-2010-0010, . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations | Waterford | 22 February 2010 | | . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations |
| W3F1-2008-0004, Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel | Waterford | 17 January 2008 | | Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel |
| W3F1-2007-0037, License Amendment Request NPF-38-271 to Support Next Generation Fuel | Waterford | 2 August 2007 | | License Amendment Request NPF-38-271 to Support Next Generation Fuel |
| W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007 | Waterford | 13 June 2007 | | Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007 |
| W3F1-2006-0065, Initial Exam - 11/2006 - Licensee Post Exam Comments | Waterford | 22 November 2006 | | Initial Exam - 11/2006 - Licensee Post Exam Comments |
| W3F1-2005-0062, Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005 | Waterford | 1 December 2005 | | Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005 |
| W3F1-2005-0001, Review of Draft Safety Evaluation for the Extended Power Uprate | Waterford | 5 January 2005 | | Review of Draft Safety Evaluation for the Extended Power Uprate |
| W3F1-2004-0061, Supplement to Amendment Request NPF-38-249, Extended Power Uprate | Waterford | 28 July 2004 | | Supplement to Amendment Request NPF-38-249, Extended Power Uprate |
| W3F1-2004-0060, Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection | Waterford | 16 July 2004 | | Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection |
| W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate | Waterford | 14 July 2004 | | Supplement to Amendment Request NPF-38-249, Extended Power Uprate |
| W3F1-2003-0055, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003 | Waterford | 24 July 2003 | | TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003 |
| W3F1-2003-0031, Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments | Waterford | 23 April 2003 | | Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments |
| W3F1-2003-0015, License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval | Waterford | 11 March 2003 | | License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval |
| W3F1-2002-0107, License Amendment Request NPF-38-244, Corrections & Clarifications to Various TS Pages | Waterford | 20 December 2002 | | License Amendment Request NPF-38-244, Corrections & Clarifications to Various TS Pages |
| VR-SECY-24-0087, Final Revision to the Policy Statement on Abnormal Occurrence Reporting Criteria (Crowell) | | 31 March 2025 | | VR-SECY-24-0087: Final Revision to the Policy Statement on Abnormal Occurrence Reporting Criteria (Crowell) |
| VR-SECY-22-0046, Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson) | | 27 June 2022 | | VR-SECY-22-0046: Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson) |
| VR-SECY-19-0072, Denial of Petition for Rulemaking on Measurement and Control of Combustible Gas Generation and Dispersal (PRM-50-103; NRC-2011-0189) (Hanson) | | 12 August 2020 | | VR-SECY-19-0072: Denial of Petition for Rulemaking on Measurement and Control of Combustible Gas Generation and Dispersal (PRM-50-103; NRC-2011-0189) (Hanson) |
| ULNRC-06238, Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6 | Callaway | 31 August 2015 | | Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6 |
| ULNRC-06230, Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6 | Callaway | 16 July 2015 | | Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6 |
| ULNRC-06166, Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program | Callaway | 19 December 2014 | | Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program |
| ULNRC-06035, CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests | Callaway | 29 August 2013 | | CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests |
| ULNRC-06034, 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fourth 120-Month Inservice Testing Interval | Callaway | 23 September 2013 | | 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fourth 120-Month Inservice Testing Interval |
| ULNRC-05947, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal Application | Callaway | 15 January 2013 | | License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal Application |
| ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives | Callaway | 24 September 2012 | | Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives |
| ULNRC-05821, Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173) | Callaway | 27 October 2011 | | Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173) |
| ULNRC-05781, Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2 | Callaway | 29 August 2011 | | Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2 |
| ULNRC-05598, Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request LDCN 09-0008) | Callaway | 20 March 2009 | | Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request LDCN 09-0008) |
| ULNRC-05309, Inoperable Channel 11 of the Loose Parts Detection System (Lpds) | Callaway | 10 July 2006 | | Inoperable Channel 11 of the Loose Parts Detection System (Lpds) |
| ULNRC-05248, Submittal of Revision 23 to Pump and Valve Inservice Testing Program | Callaway | 19 January 2006 | | Submittal of Revision 23 to Pump and Valve Inservice Testing Program |
| ULNRC-05237, Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds) | Callaway | 9 December 2005 | | Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds) |
| ULNRC-05187, Inoperable Channel 3 of the Loose Parts Detection System (Lpds) | Callaway | 11 August 2005 | | Inoperable Channel 3 of the Loose Parts Detection System (Lpds) |
| ULNRC-04923, License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program | Callaway | 8 December 2003 | | License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program |
| U-790504, Responses by Util to Round One,Set Four Questions from Accident Analysis Branch (Emergency Planning) Re OL Application | Columbia | 4 May 1979 | | Responses by Util to Round One,Set Four Questions from Accident Analysis Branch (Emergency Planning) Re OL Application |
| U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases | Clinton | 22 December 2017 | | Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases |
| U-604257, Transmittal of Revision 17 to the Technical Specification Bases | Clinton | 21 December 2015 | | Transmittal of Revision 17 to the Technical Specification Bases |
| U-604243, Special Report: Inoperable Post Accident Monitoring Instrumentation | Clinton | 25 September 2015 | | Special Report: Inoperable Post Accident Monitoring Instrumentation |
| U-603987, Transmittal of Revision 13 to Technical Specification Bases | Clinton | 1 October 2010 | | Transmittal of Revision 13 to Technical Specification Bases |
| U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval | Clinton | 12 July 2010 | | Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval |
| U-603962, Addenda to 2009 Annual Radioactive Effluent Release Report | Clinton | 7 June 2010 | | Addenda to 2009 Annual Radioactive Effluent Release Report |
| U-603907, Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan | Clinton | 31 July 2009 | | Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan |
| U-603859, Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases | Clinton | 23 May 2008 | | Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases |
| U-603858, Addenda to 2005 Annual Radioactive Effluent Release Report | Clinton | 27 May 2008 | | Addenda to 2005 Annual Radioactive Effluent Release Report |
| U-603796, Submittal of Supporting Documentation for December 19, 2006 Regulatory Conference | Clinton | 12 December 2006 | | Submittal of Supporting Documentation for December 19, 2006 Regulatory Conference |
| U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases | Clinton | 16 August 2006 | | Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases |
| U-603708, Transmittal of Revision 9 to the Clinton Power Station Technical Specification Bases | Clinton | 3 January 2005 | | Transmittal of Revision 9 to the Clinton Power Station Technical Specification Bases |
| U-603676, Day Post-Outage Inservice Inspection (ISI) Summary Report | Clinton | 27 May 2004 | | Day Post-Outage Inservice Inspection (ISI) Summary Report |
| U-603640, Transmittal of Revision 8 to the Technical Specification Bases | Clinton | 13 November 2003 | | Transmittal of Revision 8 to the Technical Specification Bases |
| U-603625, Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004 | Clinton | 6 January 2004 | | Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004 |
| U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases | Clinton | 27 November 2002 | | Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases |
| U-603543, Part 2 of 2, Clinton Power Station, Annual Radioactive Effluent Release Report, CPS-Offsite Dose Calculation Manual | Clinton | 8 March 2002 | | Part 2 of 2, Clinton Power Station, Annual Radioactive Effluent Release Report, CPS-Offsite Dose Calculation Manual |
| U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl | Clinton | 20 September 1999 | | Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl |
| U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys | Clinton | 24 June 1999 | | Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys |
| U-603170, Identifies Nine MOVs Being Added to CPS GL 89-10 Program & Provides Actions Being Taken to Ensure That MOVs Are Capable of Performing safety-related Function | Clinton | 8 March 1999 | | Identifies Nine MOVs Being Added to CPS GL 89-10 Program & Provides Actions Being Taken to Ensure That MOVs Are Capable of Performing safety-related Function |
| U-603112, Requests Withdrawal of Application for Amend of Operating License NPF-62,submitted Via Util Ltrs & 960722 | Clinton | 23 November 1998 | | Requests Withdrawal of Application for Amend of Operating License NPF-62,submitted Via Util Ltrs & 960722 |
| U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) | Clinton | 5 October 1998 | | Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) |
| U-603061, Requests Temporary Schedular Exemption from Requirements of 10CFR50,App J,To Defer LLRT of Primary Containment Penetration 1MC-042 at CPS Until Startup from Next Scheduled Refueling outage,(RF-7) | Clinton | 13 August 1998 | | Requests Temporary Schedular Exemption from Requirements of 10CFR50,App J,To Defer LLRT of Primary Containment Penetration 1MC-042 at CPS Until Startup from Next Scheduled Refueling outage,(RF-7) |
| U-603032, Application for Amend to License NPF-62,adding TS LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys | Clinton | 23 October 1998 | | Application for Amend to License NPF-62,adding TS LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys |
| U-603026, Submits Response to RAI Re Illinois Power Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions | Clinton | 15 June 1998 | | Submits Response to RAI Re Illinois Power Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions |
| U-603025, Forwards Request for Relief from Requirements of Section XI of ASME B&PV Code,Re Performance of Leakage Testing for Selected Category a Isolation Valves During First 120-month ISI Interval | Clinton | 18 June 1998 | | Forwards Request for Relief from Requirements of Section XI of ASME B&PV Code,Re Performance of Leakage Testing for Selected Category a Isolation Valves During First 120-month ISI Interval |
| U-602836, Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630 | Clinton | 20 October 1997 | | Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630 |
| U-602786, Informs That Util Has Completed All Actions Associated W/Cal Re Condition of Protective Coatings in Primary Containment & Drywell | Clinton | 16 July 1997 | | Informs That Util Has Completed All Actions Associated W/Cal Re Condition of Protective Coatings in Primary Containment & Drywell |
| U-602780, Informs of Current Status of Efforts Re Condition of Protective Coatings in Primary Containment & Drywell in Response to Confirmatory Action Ltr | Clinton | 2 July 1997 | | Informs of Current Status of Efforts Re Condition of Protective Coatings in Primary Containment & Drywell in Response to Confirmatory Action Ltr |
| U-602761, Informs NRC of Actions Plant Taking to Address Condition of Protective Coatings in Plant Primary Containment & Drywell, in Response to CAL | Clinton | 12 June 1997 | | Informs NRC of Actions Plant Taking to Address Condition of Protective Coatings in Plant Primary Containment & Drywell, in Response to CAL |
| U-602683, Provides Response to NRCs RAI Re Adequacy & Availabilty of Design Bases Info at Util,Per 10CFR50.54(f) | Clinton | 12 February 1997 | | Provides Response to NRCs RAI Re Adequacy & Availabilty of Design Bases Info at Util,Per 10CFR50.54(f) |
| U-602628, Forwards Response to Each of Questions Contained in NRC 960808 Request for Addl Info Re 960628 Application for Amend to License NPF-62 for Removal of Inclined Fuel Transfer Sys & Primary Containment Isolation Valves | Clinton | 17 September 1996 | | Forwards Response to Each of Questions Contained in NRC 960808 Request for Addl Info Re 960628 Application for Amend to License NPF-62 for Removal of Inclined Fuel Transfer Sys & Primary Containment Isolation Valves |
| U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling | Clinton | 15 August 1996 | | Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling |
| U-602596, Provides Addl Info for Amend to Incorporate Proposed Change to CPS Ts, ,be Reviewed on Schedule Sufficient to Support Sixth Refueling Outage Currently Scheduled to Begin 961013 | Clinton | 3 July 1996 | | Provides Addl Info for Amend to Incorporate Proposed Change to CPS Ts, ,be Reviewed on Schedule Sufficient to Support Sixth Refueling Outage Currently Scheduled to Begin 961013 |
| U-602587, Application for Amend to License NPF-62,allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable | Clinton | 28 June 1996 | | Application for Amend to License NPF-62,allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable |
| U-602569, Application for Amend to License NPF-62,revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met | Clinton | 19 April 1996 | | Application for Amend to License NPF-62,revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met |
| U-602565, Application for Amend to License NPF-62,implementing 10CFR50,App J-Option B | Clinton | 1 May 1996 | | Application for Amend to License NPF-62,implementing 10CFR50,App J-Option B |
| U-602549, Application for Amend to License NPF-62,proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier | Clinton | 22 February 1996 | | Application for Amend to License NPF-62,proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier |
| U-602520, Application for Amend to License NPF-62,revising TS 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation, to Eliminate Periodic Response Time Testing of Analog Trip Modules | Clinton | 14 December 1995 | | Application for Amend to License NPF-62,revising TS 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation, to Eliminate Periodic Response Time Testing of Analog Trip Modules |
| U-602508, Application for Amend to License NPF-62,requesting Various Proposed Changes to TS for Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys | Clinton | 14 December 1995 | | Application for Amend to License NPF-62,requesting Various Proposed Changes to TS for Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys |
| U-602430, Forwards four-yr Updated Certification Rept for Training Simulator.Encl Rept Describes Performance Testing Planned During Next Four Yrs | Clinton | 17 March 1995 | | Forwards four-yr Updated Certification Rept for Training Simulator.Encl Rept Describes Performance Testing Planned During Next Four Yrs |
| U-602417, Application for Amend to License NPF-62,changing TS 3.8.2, 3.8.5 & 3.8.8 to Revise Operability Requirements for Div 3 DG & Divs 3 & 4 Batteries,Battery Chargers & Inverters to Apply Only When HPCS Required to Be Operable | Clinton | 14 February 1995 | | Application for Amend to License NPF-62,changing TS 3.8.2, 3.8.5 & 3.8.8 to Revise Operability Requirements for Div 3 DG & Divs 3 & 4 Batteries,Battery Chargers & Inverters to Apply Only When HPCS Required to Be Operable |
| U-602376, Application for Amend to License NPF-62,eliminating Selected Response Time Testing Requirements | Clinton | 27 January 1995 | | Application for Amend to License NPF-62,eliminating Selected Response Time Testing Requirements |
| U-602342, Requests Approval to Use ASME Code Case N-416-1 for Performing Alternate Testing & Examination of Sys Pressure Test Following Repair &/Or Replacement of Steam Admission Valve | Clinton | 9 September 1994 | | Requests Approval to Use ASME Code Case N-416-1 for Performing Alternate Testing & Examination of Sys Pressure Test Following Repair &/Or Replacement of Steam Admission Valve |
| U-602331, Withdraws 940217 Request for Listed Partial Exemptions from 10CFR50,App J & Proposed Changes to License NPF-62 | Clinton | 15 August 1994 | | Withdraws 940217 Request for Listed Partial Exemptions from 10CFR50,App J & Proposed Changes to License NPF-62 |
| U-602320, Application for Amend to License NPF-62,proposing Changes to TS 3/4.6.2.2, Drywell Bypass Leakage, to Allow Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years | Clinton | 12 August 1994 | | Application for Amend to License NPF-62,proposing Changes to TS 3/4.6.2.2, Drywell Bypass Leakage, to Allow Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years |
| U-602196, Application for Amend to License NPF-62,requesting Changes to TS to Improve & Reformat CPS TS Consistent w/NUREG-1434, Improved BWR-6 TS, Rev 0,Sept 1992 | Clinton | 26 October 1993 | | Application for Amend to License NPF-62,requesting Changes to TS to Improve & Reformat CPS TS Consistent w/NUREG-1434, Improved BWR-6 TS, Rev 0,Sept 1992 |
| U-602141, Responds to NRC Bulletin 93-002, Debris Plugging of ECC Suction Strainers. Only Fibrous Matls Used within Containment or Drywell,Not Located within Separate Room, Consists of Rigid Fiberglass Insulation Matl | Clinton | 9 June 1993 | | Responds to NRC Bulletin 93-002, Debris Plugging of ECC Suction Strainers. Only Fibrous Matls Used within Containment or Drywell,Not Located within Separate Room, Consists of Rigid Fiberglass Insulation Matl |
| U-601871, Proposed Tech Specs Re Reactor Protection Sys Instrumentation,Containment & Reactor Vessel Isolation Control Sys & ECCS Instrumentation Surveillance Requirements | Clinton | 20 September 1991 | | Proposed Tech Specs Re Reactor Protection Sys Instrumentation,Containment & Reactor Vessel Isolation Control Sys & ECCS Instrumentation Surveillance Requirements |
| U-601830, Informs That Alternate Rod Injection & ATWS Reactor Pump Trip Sys Installed at Facility to Reduce Risk from ATWS Event,Per 10CFR50.62 | Clinton | 26 April 1991 | | Informs That Alternate Rod Injection & ATWS Reactor Pump Trip Sys Installed at Facility to Reduce Risk from ATWS Event,Per 10CFR50.62 |
| U-601784, Proposed Tech Specs Exempting Measured Type C Leakage Rates for Feedwater Check Valves 1B21-F032A & B | Clinton | 18 January 1991 | | Proposed Tech Specs Exempting Measured Type C Leakage Rates for Feedwater Check Valves 1B21-F032A & B |
| U-601612, Ro:On 900212,Tech Specs 3.6.1.8 & 3.6.1.1 Entered Due to Failed Local Leak Rate Test on Primary Containment Penetration MC-102.Plant Shutdown Commenced & Notification of Unsual Event Declared.Plant Placed in Shutdown Condition | Clinton | 20 February 1990 | | Ro:On 900212,Tech Specs 3.6.1.8 & 3.6.1.1 Entered Due to Failed Local Leak Rate Test on Primary Containment Penetration MC-102.Plant Shutdown Commenced & Notification of Unsual Event Declared.Plant Placed in Shutdown Condition |
| U-601548, Proposed Tech Specs 3/4.3.10.a & B & Bases Re self-test Sys, Note to 3/4.6.1 Concerning Verification of valves,5.2.3 on Design Features of Secondary Containment & Surveillance Requirement 4.0.2 | Clinton | 20 November 1989 | | Proposed Tech Specs 3/4.3.10.a & B & Bases Re self-test Sys, Note to 3/4.6.1 Concerning Verification of valves,5.2.3 on Design Features of Secondary Containment & Surveillance Requirement 4.0.2 |
| U-601504, Responds to NRC & Proposed Imposition of Civil Penalties Re Violations Noted in Insp Rept 50-461/89-06. Corrective Actions:Licensee Conducted Reinsps of Components to Ensure That Scope of Program Conservative | Clinton | 8 August 1989 | | Responds to NRC & Proposed Imposition of Civil Penalties Re Violations Noted in Insp Rept 50-461/89-06. Corrective Actions:Licensee Conducted Reinsps of Components to Ensure That Scope of Program Conservative |
| U-601417, Advises That Util Completed NUREG-0737 (TMI Action Plan) Requirements,Per License Condition 2.C.(9).Brief Chronology of Status of Implementation of Dcrdr Submitted. Installation of Class 1E Power Sources Complete | Clinton | 14 April 1989 | | Advises That Util Completed NUREG-0737 (TMI Action Plan) Requirements,Per License Condition 2.C.(9).Brief Chronology of Status of Implementation of Dcrdr Submitted. Installation of Class 1E Power Sources Complete |
| U-601194, Forwards Response to Ja Stevens 880505 Questions on Inservice Testing (IST) Program,Summary of Changes to IST, Relief Requests & Rev 5 to Pump & Valve Testing Program Plan | Clinton | 27 May 1988 | | Forwards Response to Ja Stevens 880505 Questions on Inservice Testing (IST) Program,Summary of Changes to IST, Relief Requests & Rev 5 to Pump & Valve Testing Program Plan |
| U-601167, Forwards Addl Info Relating to Questions on Pneumatic & Hydrostatic Testing of Containment Isolation Valves & Pressure Isolation Valves.Info on Stroke Times of Certain Valves to Be Evaluated by NRC Also Encl | Clinton | 18 April 1988 | | Forwards Addl Info Relating to Questions on Pneumatic & Hydrostatic Testing of Containment Isolation Valves & Pressure Isolation Valves.Info on Stroke Times of Certain Valves to Be Evaluated by NRC Also Encl |
| U-601118, Proposed Tech Specs Re Administrative Controls | Clinton | 5 February 1988 | | Proposed Tech Specs Re Administrative Controls |
| U-601117, Requests one-time Exemption from Requirements of 10CFR50, App J,Paragraph III.D.3 Re Surveillance Interval Requirement for Type C Local Leak Rate Tests for Containment Isolation Valves.Fee Paid | Clinton | 13 January 1988 | | Requests one-time Exemption from Requirements of 10CFR50, App J,Paragraph III.D.3 Re Surveillance Interval Requirement for Type C Local Leak Rate Tests for Containment Isolation Valves.Fee Paid |
| U-601087, Responds to NRC Re Violations Noted in Insp Rept 50-461/87-32.Corrective Actions:Util Procedure 3002.01, Heatup & Pressurization, Revised to Include Channel Functional Test Requirements | Clinton | 19 November 1987 | | Responds to NRC Re Violations Noted in Insp Rept 50-461/87-32.Corrective Actions:Util Procedure 3002.01, Heatup & Pressurization, Revised to Include Channel Functional Test Requirements |
| U-601084, Proposed Tech Specs Re Containment & Pressure Isolation Valve Surveillance Requirements | Clinton | 10 December 1987 | | Proposed Tech Specs Re Containment & Pressure Isolation Valve Surveillance Requirements |
| U-601018, Semiannual Radioactive Effluent Release Rept,870228-0630 | Clinton | 30 June 1987 | | Semiannual Radioactive Effluent Release Rept,870228-0630 |
| U-601014, Provides Requested Info Identified in D Muller Re Submittal of Facility Specific Hydrogen Control Sys Final Analysis,Including Proposed Outline for Hydrogen Control Sys Final Analysis Required by 10CFR50.44 | Clinton | 24 August 1987 | | Provides Requested Info Identified in D Muller Re Submittal of Facility Specific Hydrogen Control Sys Final Analysis,Including Proposed Outline for Hydrogen Control Sys Final Analysis Required by 10CFR50.44 |
| U-600968, Forwards Responses to WR Butler & Rev 2 to Pump & Valve Testing Program Plan. Revised Program Will Be Implemented | Clinton | 30 June 1987 | | Forwards Responses to WR Butler & Rev 2 to Pump & Valve Testing Program Plan. Revised Program Will Be Implemented |
| U-600885, Forwards marked-up Revs to Tech Specs Re Setpoints for Lpcs/ LPCI Permissive Interlocks for Full Power Ol,As Suppl to Util 870108,0204 & 0303 Ltrs.Changes Consistent W/Fsar & SER Through Suppl 7.No Change to Low Power OL Requested | Clinton | 20 March 1987 | | Forwards marked-up Revs to Tech Specs Re Setpoints for Lpcs/ LPCI Permissive Interlocks for Full Power Ol,As Suppl to Util 870108,0204 & 0303 Ltrs.Changes Consistent W/Fsar & SER Through Suppl 7.No Change to Low Power OL Requested |
| U-600813, Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept | Clinton | 31 December 1986 | | Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept |
| U-600689, Responds to NRC Re Violations Noted in Insp Rept 50-461/86-37.Corrective Actions:Procedure CPS 9052.02, LPCS Valve Operability Checks, Revised to Incorporate Criteria for Opening Time of LPCS Injection Valve | Clinton | 25 August 1986 | | Responds to NRC Re Violations Noted in Insp Rept 50-461/86-37.Corrective Actions:Procedure CPS 9052.02, LPCS Valve Operability Checks, Revised to Incorporate Criteria for Opening Time of LPCS Injection Valve |
| U-600648, Responds to NRC Re Establishment of Emergency Communications Capability Known as Emergency Response Data Sys (Erds).Util in Process of Evaluating ERDS Requirements. Preliminary List of Plant Data for ERDS Encl | Clinton
05000000 | 21 July 1986 | | Responds to NRC Re Establishment of Emergency Communications Capability Known as Emergency Response Data Sys (Erds).Util in Process of Evaluating ERDS Requirements. Preliminary List of Plant Data for ERDS Encl |
| U-600601, Informs of Plans to Modify SPDS on Basis of Operator Comments Noted During 850913 Test Display of Containment Isolation Valve Status | Clinton | 11 June 1986 | | Informs of Plans to Modify SPDS on Basis of Operator Comments Noted During 850913 Test Display of Containment Isolation Valve Status |
| U-600468, Forwards Justification for 851209 Request for Exemptions from 10CFR50.12,App J Final Rule Concerning Leak Test Requirements,Specifically,Msiv Leak Rate Tests & Containment Air Lock Leakage Testing | Clinton | 11 March 1986 | | Forwards Justification for 851209 Request for Exemptions from 10CFR50.12,App J Final Rule Concerning Leak Test Requirements,Specifically,Msiv Leak Rate Tests & Containment Air Lock Leakage Testing |
| U-600296, Requests Exemption from 10CFR50,App J Leak Testing Requirements for MSIVs & Containment Air Lock.Justification for Exemption & marked-up Proof & Review Tech Specs Encl | Clinton | 9 December 1985 | | Requests Exemption from 10CFR50,App J Leak Testing Requirements for MSIVs & Containment Air Lock.Justification for Exemption & marked-up Proof & Review Tech Specs Encl |
| U-600279, Forwards Response to 10CFR50.62 Requirements Re Reduction of ATWS Events for Light Water Cooled Nuclear Power Plants. Installation of ATWS Sys Complete.Tech Spec 3/4.1.5, Standby Liquid Control Sys, Will Be Revised | Clinton | 16 October 1985 | | Forwards Response to 10CFR50.62 Requirements Re Reduction of ATWS Events for Light Water Cooled Nuclear Power Plants. Installation of ATWS Sys Complete.Tech Spec 3/4.1.5, Standby Liquid Control Sys, Will Be Revised |
| U-600275, Forwards marked-up Proof & Review Tech Specs,Per 850904 Request,Indicating Typos & Corrections to Info Submitted in 840928 & s | Clinton | 2 October 1985 | | Forwards marked-up Proof & Review Tech Specs,Per 850904 Request,Indicating Typos & Corrections to Info Submitted in 840928 & s |
| U-600176, Forwards Results of post-accident Containment Venting & Corresponding plant-specific Emergency Procedure Guidelines, Per 850301 Telcon.Info Fulfills Requirements of TMI Item I.C.1 & SER (NUREG-0853) Confirmatory Issue 41 | Clinton | 24 July 1985 | | Forwards Results of post-accident Containment Venting & Corresponding plant-specific Emergency Procedure Guidelines, Per 850301 Telcon.Info Fulfills Requirements of TMI Item I.C.1 & SER (NUREG-0853) Confirmatory Issue 41 |
| U-600083, Forwards Addl Accident Monitoring Instrumentation,Per NUREG-0737,TMI Item II.F.1.Info Complete & Adequate to Provide Confirmation That TMI Item & SER Confirmatory Issue 21 Implemented | Clinton | 11 June 1985 | | Forwards Addl Accident Monitoring Instrumentation,Per NUREG-0737,TMI Item II.F.1.Info Complete & Adequate to Provide Confirmation That TMI Item & SER Confirmatory Issue 21 Implemented |
| U-600066, Forwards Responses to NRC Comments on Revised SPDS (TMI Action Plan Item I.D.2) for Review.Scheduling of Design Validation Audit in mid-Oct to Support Final Closure Requested | Clinton | 12 June 1985 | | Forwards Responses to NRC Comments on Revised SPDS (TMI Action Plan Item I.D.2) for Review.Scheduling of Design Validation Audit in mid-Oct to Support Final Closure Requested |
| U-600029, Forwards List of Selected Operating Events to Be Used in Sys Function & Task Analysis,Per 850424 Responses to NRC Comments on Dcrdr Program Plan.Plan Process Fulfills Suppl 1 to NUREG-0737 Requirements | Clinton | 12 June 1985 | | Forwards List of Selected Operating Events to Be Used in Sys Function & Task Analysis,Per 850424 Responses to NRC Comments on Dcrdr Program Plan.Plan Process Fulfills Suppl 1 to NUREG-0737 Requirements |
| TXX-9600, Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B | Comanche Peak | 12 March 1996 | | Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B |
| TXX-6388, Forwards Response to Notice of Violation Item H from Insp Rept 50-446/86-02.Corrective Actions:All Cases Where CB&I Did Not Accept Original Radiograph & Did Not Classify Any Addl Work as Repair Reviewed | Comanche Peak | 24 April 1987 | | Forwards Response to Notice of Violation Item H from Insp Rept 50-446/86-02.Corrective Actions:All Cases Where CB&I Did Not Accept Original Radiograph & Did Not Classify Any Addl Work as Repair Reviewed |
| TXX-4703, Forwards Response to Section IV of Generic Ltr 85-12, Automatic Trip of Reactor Coolant Pumps. Determination of Pump Trip Criteria,Pump Potential Problems & Operator Training & Procedures Discussed | Comanche Peak | 17 February 1986 | | Forwards Response to Section IV of Generic Ltr 85-12, Automatic Trip of Reactor Coolant Pumps. Determination of Pump Trip Criteria,Pump Potential Problems & Operator Training & Procedures Discussed |
| TXX-4182, Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review | Comanche Peak | 29 May 1984 | | Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review |
| TSTF-580 | | | | Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling |
| TSTF-514 | | | | Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation |
| TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1 | Technical Specifications Task Force | 23 June 2021 | | TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1 |
| TSTF-21-01, Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling | Technical Specifications Task Force | 26 January 2021 | | Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling |
| TSTF-19-12, TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position | Technical Specifications Task Force | 5 November 2019 | | TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position |
| TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements | Technical Specifications Task Force
99902042 | 16 January 2020 | | TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements |
| TSTF-19-10, Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position | Technical Specifications Task Force | 28 August 2019 | | Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position |
| TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements | Technical Specifications Task Force
99902042 | 13 December 2019 | | Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements |
| TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements | Technical Specifications Task Force | 3 July 2019 | | Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements |
| TSTF-19-05, Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position | Technical Specifications Task Force | 18 June 2019 | | Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position |
| TSTF-17-18, Transmittal of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems | Technical Specifications Task Force | 19 January 2018 | | Transmittal of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems |
| TSTF-17-16, Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 | Technical Specifications Task Force | 19 December 2017 | | Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 |
| TSTF-17-10, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements | Technical Specifications Task Force | 2 August 2017 | | TSTF Comments on Draft Safety Evaluation for Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements |
| TSTF-16-10, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control, and Transmittal of Editorial Corrections to TSTF-542, Revision 2 | Technical Specifications Task Force | 2 November 2016 | | TSTF Comments on Draft Safety Evaluation for Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control, and Transmittal of Editorial Corrections to TSTF-542, Revision 2 |
| TSTF-16-09, Technical Specifications Task Force - Revision 3 of TSTF-551, Revise Secondary Containment Surveillance Requirements | Technical Specifications Task Force | 3 October 2016 | | Technical Specifications Task Force - Revision 3 of TSTF-551, Revise Secondary Containment Surveillance Requirements |
| TSTF-16-07, Technical Specifications Task Force - Revision 2 of TSTF-551, Revise Secondary Containment Surveillance Requirements | Technical Specifications Task Force | 12 May 2016 | | Technical Specifications Task Force - Revision 2 of TSTF-551, Revise Secondary Containment Surveillance Requirements |
| TSTF-16-03, Technical Specifications Task Force - Comments on Draft Model Safety Evaluation of Traveler TSTF-529, Revision 3, Clarify Use and Application Rules, and Transmittal of TSTF-529, Revision 4 | Technical Specifications Task Force | 29 February 2016 | | Technical Specifications Task Force - Comments on Draft Model Safety Evaluation of Traveler TSTF-529, Revision 3, Clarify Use and Application Rules, and Transmittal of TSTF-529, Revision 4 |
| TSTF-15-08, Technical Specifications Task Force - Transmittal of TSTF-529, Revision 3, Clarify Use and Application Rules | Technical Specifications Task Force | 14 September 2015 | | Technical Specifications Task Force - Transmittal of TSTF-529, Revision 3, Clarify Use and Application Rules |
| TSTF-15-07, Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements | Technical Specifications Task Force | 3 September 2015 | | Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements |
| TSTF-14-18, Transmittal of TSTF-551, Revision 0, Address Transient Secondary Containment Conditions | Technical Specifications Task Force | 30 October 2014 | | Transmittal of TSTF-551, Revision 0, Address Transient Secondary Containment Conditions |
| TSTF-14-17, Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3 | Technical Specifications Task Force | 31 March 2015 | | Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3 |
| TSTF-14-02, Transmittal of TSTF-529, Revision 2, Clarify Use and Application Rules | Technical Specifications Task Force | 14 January 2014 | | Transmittal of TSTF-529, Revision 2, Clarify Use and Application Rules |
| TSTF-13-12, Transmittal of TSTF-541, Revision 0, Add Exceptions to Surveillance Requirements When the Safety Function Is Being Performed | Technical Specifications Task Force | 10 September 2013 | | Transmittal of TSTF-541, Revision 0, Add Exceptions to Surveillance Requirements When the Safety Function Is Being Performed |
| TSTF-13-03, Transmittal of TSTF-529, Revision 1, Clarify Use and Application Rules | Technical Specifications Task Force | 28 February 2013 | | Transmittal of TSTF-529, Revision 1, Clarify Use and Application Rules |
| TSTF-12-15, Response to NRC Request for Additional Information Regarding TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation | Technical Specifications Task Force | 30 August 2012 | | Response to NRC Request for Additional Information Regarding TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation |
| TSTF-12-11, Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6) | Technical Specifications Task Force | 16 May 2012 | | Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6) |
| TSTF-12-06, Transmittal of TSTF-538, Revision 0, Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c | Technical Specifications Task Force | 27 March 2012 | | Transmittal of TSTF-538, Revision 0, Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c |
| TSTF-12-05, Transmittal of Report TSTF-GG-05-01, Revision 1, Writers Guide for Plant-Specific Improved Technical Specifications | Technical Specifications Task Force | 14 February 2012 | | Transmittal of Report TSTF-GG-05-01, Revision 1, Writers Guide for Plant-Specific Improved Technical Specifications |
| TSTF-12-04, Transmittal of TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373 | Technical Specifications Task Force | 27 March 2012 | | Transmittal of TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373 |
| TSTF-12-01, Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046) | Technical Specifications Task Force | 22 February 2012 | | Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046) |
| TSTF-11-13, Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition | Technical Specifications Task Force | 19 September 2011 | | Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition |
| TSTF-11-12, Transmittal of TSTF-530, Revision 0, Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09 | Technical Specifications Task Force | 16 September 2011 | | Transmittal of TSTF-530, Revision 0, Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09 |
| TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation | Technical Specifications Task Force | 24 November 2010 | | Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation |
| TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2 | Technical Specifications Task Force | 6 August 2010 | | Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2 |
| TSTF-10-10, Comment (1) of K. J. Schrader, D. W. Gregoire, T. W. Raidy & R. Gambrell on Behalf of Technical Specification Task Force on Proposed Model TSTF-514, Revision 1, Revise BWR Operability Requirements and Actions for RCS Leakage Instrument. ( | Technical Specifications Task Force | 12 May 2010 | | Comment (1) of K. J. Schrader, D. W. Gregoire, T. W. Raidy & R. Gambrell on Behalf of Technical Specification Task Force on Proposed Model TSTF-514, Revision 1, Revise BWR Operability Requirements and Actions for RCS Leakage Instrument. (Nr |
| TSTF-10-04, Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month | Technical Specifications Task Force | 30 March 2010 | | Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month |
| TSTF-09-18, Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation | Technical Specifications Task Force | 8 September 2009 | | Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation |
| TSTF-09-03, Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation | Technical Specifications Task Force | 18 February 2009 | | Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation |
| TSTF-09-01, Transmittal of TSTF-515, Revision 0, Revise Post-Accident Monitoring Instrumentation Based on Reg. Guide 1.97, Rev. 4 and NEDO-33349 | Technical Specifications Task Force | 20 January 2009 | | Transmittal of TSTF-515, Revision 0, Revise Post-Accident Monitoring Instrumentation Based on Reg. Guide 1.97, Rev. 4 and NEDO-33349 |
| TSTF-08-20, Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners | Technical Specifications Task Force | 10 November 2008 | | Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners |
| TSTF-08-18, Transmittal of TSTF-512, Revision 0, Revise SR 3.0.3 to Address SRs That Cannot Be Performed or Are Not Met | Technical Specifications Task Force | 14 October 2008 | | Transmittal of TSTF-512, Revision 0, Revise SR 3.0.3 to Address SRs That Cannot Be Performed or Are Not Met |
| TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization | Technical Specifications Task Force | 3 July 2008 | | Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization |
| TSTF-08-05, TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners | Technical Specifications Task Force | 4 March 2008 | | TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners |
| TSTF-08-04, TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) | Technical Specifications Task Force | 19 February 2008 | | TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) |
| TSTF-07-27, Response to NRC Request for Additional Information Regarding TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461), Dated June 13, 2007 | Technical Specifications Task Force | 10 October 2007 | | Response to NRC Request for Additional Information Regarding TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461), Dated June 13, 2007 |
| TSTF-07-22, TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control | Technical Specifications Task Force | 10 July 2007 | | TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control |
| TSTF-07-11, Revision to Implementation Guidance for TSTF-423, Technical Specifications End States, NEDC-32988-A | Technical Specifications Task Force | 9 March 2007 | | Revision to Implementation Guidance for TSTF-423, Technical Specifications End States, NEDC-32988-A |
| TSTF-07-09, TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control | Technical Specifications Task Force | 21 February 2007 | | TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control |
| TSTF-07-07, Response to NRC Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Dated November 9, 2006 | Technical Specifications Task Force | 7 February 2007 | | Response to NRC Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Dated November 9, 2006 |
| TSTF-07-04, TSTF-446, Revision 2, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) | Technical Specifications Task Force | 11 January 2007 | | TSTF-446, Revision 2, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) |
| TSTF-06-28, TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461) | Technical Specifications Task Force | 20 December 2006 | | TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461) |
| TSTF-06-20, TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03 | | 18 July 2006 | | TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03 |
| TSTF-06-11, Response to NRC Request for Additional Information Regarding TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, Dated April 7, 2006 | | 5 June 2006 | | Response to NRC Request for Additional Information Regarding TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, Dated April 7, 2006 |
| TSTF-05-17, TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A | | 19 September 2005 | | TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A |
| TSTF-05-15, TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046) | | 21 September 2005 | | TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046) |
| TSTF-05-13, Technical Specification Task Force (TSTF) Response to May 25, 2005 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Re Revision to the Completion Time in STS 3.6.1.3, Primary Containment I | | 25 July 2005 | | Technical Specification Task Force (TSTF) Response to May 25, 2005 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Re Revision to the Completion Time in STS 3.6.1.3, Primary Containment Iso |
| TSTF-05-12, TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability | | 18 August 2005 | | TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability |
| TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity | | 29 June 2005 | | Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity |
| TSTF-05-06, TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities | | 5 May 2005 | | TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities |
| TSTF-04-16, TSTF-446, Revision 1, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) | | 31 January 2005 | | TSTF-446, Revision 1, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) |
| TSTF-04-15, TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a | | 2 December 2004 | | TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a |
| TSTF-04-12, Submittal and Request for Fee Waiver for Review of TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control | | 25 April 2005 | | Submittal and Request for Fee Waiver for Review of TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control |
| TSTF-04-11, TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems | | 30 August 2004 | | TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems |
| TMI-15-034, Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating Station | Oyster Creek | 2 March 2015 | | Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating Station |
| TMI-14-046, Attachment 8: Discussion of Revision to the Radiological Emergency Plan Annex for Oyster Creek Nuclear Generating Station, Page Ocgs 3-76 Through End | Oyster Creek | 30 May 2014 | | Attachment 8: Discussion of Revision to the Radiological Emergency Plan Annex for Oyster Creek Nuclear Generating Station, Page Ocgs 3-76 Through End |
| TMI-12-169, Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements | Crane | 4 February 2013 | | Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements |
| TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval | Crane | 7 November 2012 | | Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval |
| TMI-10-080, Response to Request for Additional Information, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled | Crane | 27 September 2010 | | Response to Request for Additional Information, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled |
| TMI-10-023, Response to Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability | Crane | 15 March 2010 | | Response to Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability |
| TMI-10-021, 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) | Crane | 24 March 2010 | | 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) |
| TMI-09-101, Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014 | Crane | 14 August 2009 | | Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014 |
| TI 2515/193, Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | | | | |
| SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation | Dresden | 8 April 2016 | | Submittal of Post Accident Monitoring Report Instrumentation |
| SVPLTR 13-0020, Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002 | Dresden | 6 June 2013 | | Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002 |
| SVPLTR 13-0005, Response to NRC Acknowledgement of Response to NRC Request for a Written, Response to NRC Observations and Concerns Regarding Dresden Station, Response Plan for External Flooding Events | Dresden | 31 January 2013 | | Response to NRC Acknowledgement of Response to NRC Request for a Written, Response to NRC Observations and Concerns Regarding Dresden Station, Response Plan for External Flooding Events |
| SVPLTR 10-0037, 2011 Dresden Nuclear Power Station Initial Examination Outline Submittal | Dresden | 23 September 2010 | | 2011 Dresden Nuclear Power Station Initial Examination Outline Submittal |
| SVPLTR 10-0022, Revised Commitment for the Containment Leak Reduction & Control Program for Gas Systems | Dresden | 15 May 2010 | | Revised Commitment for the Containment Leak Reduction & Control Program for Gas Systems |
| SVPLTR 09-0045, Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows | Dresden | 2 October 2009 | | Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows |
| SVPLTR 05-0014, March 2005 Monthly Operating Report for Dresden Nuclear Power Station, Units 2 and 3 | Dresden | 8 April 2005 | | March 2005 Monthly Operating Report for Dresden Nuclear Power Station, Units 2 and 3 |
| SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage | Quad Cities | 22 September 1999 | | Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage |
| SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety | Quad Cities | 13 August 1999 | | Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety |
| SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage | Quad Cities | 30 June 1999 | | Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage |
| SVP-99-127, Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs | Quad Cities | 16 July 1999 | | Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs |
| SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with | Quad Cities | 30 April 1999 | | Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with |
| SVP-99-038, Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable | Quad Cities | 30 March 1999 | | Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable |
| SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With | Quad Cities | 31 January 1999 | | Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With |
| SVP-98-377, Provides Summary of NRC Commitments Completed During 15th Refueling outage,Q1R15 | Quad Cities | 14 January 1999 | | Provides Summary of NRC Commitments Completed During 15th Refueling outage,Q1R15 |
| SVP-98-369, Confirms Completion of Installation of Larger Capacity Strainers & Reduction of Fibrous Insulation for Quad Cities 1.Actions in Response to Review of NRC SER Issued on BWROG Rept NEDO-326896 Listed | Quad Cities | 18 December 1998 | | Confirms Completion of Installation of Larger Capacity Strainers & Reduction of Fibrous Insulation for Quad Cities 1.Actions in Response to Review of NRC SER Issued on BWROG Rept NEDO-326896 Listed |
| SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With | Quad Cities | 31 October 1998 | | Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With |
| SVP-98-345, Forwards Response to NRC 981103 RAI Re Proposed Change to Ts,Increasing Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve | Quad Cities | 9 November 1998 | | Forwards Response to NRC 981103 RAI Re Proposed Change to Ts,Increasing Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve |
| SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With | Quad Cities | 15 July 1998 | | Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With |
| SVP-98-323, Provides Comeds Response to Close Open Regulatory Guide 1.97 Items.Comed Considers That with Completion of These Two Items,All Required Actions of Regulatory Guide 1.97 Are Complete | Quad Cities | 13 November 1998 | | Provides Comeds Response to Close Open Regulatory Guide 1.97 Items.Comed Considers That with Completion of These Two Items,All Required Actions of Regulatory Guide 1.97 Are Complete |
| SVP-98-291, Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.6 | Quad Cities | 31 August 1998 | | Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.6 |
| SVP-98-273, Responds to NRC Re Violations Noted in Insp Repts 50-254/98-11 & 50-265/98-11.Corrective Actions:Compensatory Measures Are in Place That Eliminate or Minimize Possible Fire That Could Affect 125Vdc & 4KV Equipment at Same Time | Quad Cities | 31 August 1998 | | Responds to NRC Re Violations Noted in Insp Repts 50-254/98-11 & 50-265/98-11.Corrective Actions:Compensatory Measures Are in Place That Eliminate or Minimize Possible Fire That Could Affect 125Vdc & 4KV Equipment at Same Time |
| SVP-98-252, Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C | Quad Cities | 31 July 1998 | | Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C |
| SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 | Quad Cities | 30 June 1998 | | Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 |
| SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 | Quad Cities | 31 May 1998 | | Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 |
| SVP-98-196, Forwards Response to Violations Noted in Insp Repts 50-254/98-05 & 50-265/98-05.Corrective Actions:Issued Design Change Package on 971015 | Quad Cities | 21 May 1998 | | Forwards Response to Violations Noted in Insp Repts 50-254/98-05 & 50-265/98-05.Corrective Actions:Issued Design Change Package on 971015 |
| SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 | Quad Cities | 30 April 1998 | | Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 |
| SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 | Quad Cities | 31 March 1998 | | Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 |
| SVP-98-114, Requests Review & Approval to 10CFR50.90 for Unreviewed Safety Question Involving Use of Station Blackout DGs & Use of Mobile Safe Shutdown Batteries in App R Ssd Analysis | Quad Cities | 31 March 1998 | | Requests Review & Approval to 10CFR50.90 for Unreviewed Safety Question Involving Use of Station Blackout DGs & Use of Mobile Safe Shutdown Batteries in App R Ssd Analysis |
| SVP-98-100, Forwards Corrected Page to SE Summary SE-97-024 of 971031 Summary Rept of Changes,Tests & Experiements | Quad Cities | 20 March 1998 | | Forwards Corrected Page to SE Summary SE-97-024 of 971031 Summary Rept of Changes,Tests & Experiements |
| SVP-98-095, Responds to NRC Re Violations Noted in Insp Repts 50-254/97-22 & 50-265/97-22.Corrective Actions:Procedure Qcop 2300-08 Was Walked Down & Verified by Sro,Corrected Procedure & Evaluated Effect of Longer Valve Closures Times | Quad Cities | 13 March 1998 | | Responds to NRC Re Violations Noted in Insp Repts 50-254/97-22 & 50-265/97-22.Corrective Actions:Procedure Qcop 2300-08 Was Walked Down & Verified by Sro,Corrected Procedure & Evaluated Effect of Longer Valve Closures Times |
| SVP-98-087, Monthly Operating Repts for Feb 1998 for Quad Cities Nuclear Station,Units 1 & 2 | Quad Cities | 28 February 1998 | | Monthly Operating Repts for Feb 1998 for Quad Cities Nuclear Station,Units 1 & 2 |
| SVP-98-049, Monthly Operating Repts for Jan 1998 for Quad Cities Nuclear Station,Units 1 & 2 | Quad Cities | 31 January 1998 | | Monthly Operating Repts for Jan 1998 for Quad Cities Nuclear Station,Units 1 & 2 |
| SVP-97-267, Submits Response to Request for Info on Verification of Adequate Wall Thickness for Mark I Torus Shells for Units 1 & 2.Rept Discussing Present Matl Condition of Torus Shell & Plant Plans to Maintain Torus in Acceptable Condition Encl | Quad Cities | 21 November 1997 | | Submits Response to Request for Info on Verification of Adequate Wall Thickness for Mark I Torus Shells for Units 1 & 2.Rept Discussing Present Matl Condition of Torus Shell & Plant Plans to Maintain Torus in Acceptable Condition Encl |
| SVP-94-017, Documents Results of 940214 Telcon W/Nrc,In Which Comm Ed Requested Issuance of Notice of Enforcement Discretion from TS 3.6.1.1 for Facility.Basis for Request for Enforcement Discretion Encl | Braidwood | 15 March 1994 | | Documents Results of 940214 Telcon W/Nrc,In Which Comm Ed Requested Issuance of Notice of Enforcement Discretion from TS 3.6.1.1 for Facility.Basis for Request for Enforcement Discretion Encl |
| SVP-16-001, 2016 Quad Cities Nuclear Power Station Initial License Examination Forms ES-D-1 | Quad Cities | 2 May 2016 | | 2016 Quad Cities Nuclear Power Station Initial License Examination Forms ES-D-1 |
| SVP-13-080, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report | Quad Cities | 26 November 2013 | | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report |
| SVP-11-021, Clarification of License Renewal Commitment Regarding Bellows Testing | Quad Cities | 7 April 2011 | | Clarification of License Renewal Commitment Regarding Bellows Testing |
| SVP-03-118, Transmittal of Lost Parts Analysis and Associated Operability Evaluation | Quad Cities | 28 November 2003 | | Transmittal of Lost Parts Analysis and Associated Operability Evaluation |
| SVP-03-096, Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program | Quad Cities | 11 September 2003 | | Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program |
| SVP-03-019, Fourth Interval Inservice Inspection Program Plan | Quad Cities | 7 February 2003 | | Fourth Interval Inservice Inspection Program Plan |
| SVP-03-008, Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program Plan | Quad Cities | 17 January 2003 | | Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program Plan |
| ST-HL-AE-5313, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Option B of 10CFR50,App J for Both Units & Proposing to Amend TS 4.6.1.1,3.6.1.2,4.6.1.2,3.6.1.3, 4.6.1.3,4.6.1.7.2,4.6.1.7.3 & Bases 3/4.6.1.2 & 3/4.6.1.3 | South Texas | 1 May 1996 | | Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Option B of 10CFR50,App J for Both Units & Proposing to Amend TS 4.6.1.1,3.6.1.2,4.6.1.2,3.6.1.3, 4.6.1.3,4.6.1.7.2,4.6.1.7.3 & Bases 3/4.6.1.2 & 3/4.6.1.3 |
| ST-HL-AE-5046, Application for Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors & Amend to Licenses NPF-76 & NPF-80,replacing Current Specified Intervals W/Ref to 10CFR50 App J | South Texas | 16 March 1995 | | Application for Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors & Amend to Licenses NPF-76 & NPF-80,replacing Current Specified Intervals W/Ref to 10CFR50 App J |
| ST-HL-AE-4458, Forwards Response to NRC Bulletin 93-002.Util Conducted Review of Relevant Sys/Component Drawings,Procedures, Calculation,Related Operating Experience Repts & Design Basis Documents | South Texas | 2 June 1993 | | Forwards Response to NRC Bulletin 93-002.Util Conducted Review of Relevant Sys/Component Drawings,Procedures, Calculation,Related Operating Experience Repts & Design Basis Documents |
| ST-HL-AE-4364, Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Implement Revised UFSAR Chapter 15 Accident Analysis, Increasing Peaking Factor Limits.Westinghouse Proprietary Repts WCAP-11273 & WCAP-13441 Encl.Repts Withheld | South Texas | 27 May 1993 | | Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Implement Revised UFSAR Chapter 15 Accident Analysis, Increasing Peaking Factor Limits.Westinghouse Proprietary Repts WCAP-11273 & WCAP-13441 Encl.Repts Withheld |
| ST-HL-AE-4066, Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks | South Texas | 4 August 1992 | | Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks |
| ST-HL-AE-2279, Forwards Revised Pages 3.6.A-1,3.6.A-2,9.2.9 & 9.2.10 from FSAR Amend 61.Pages Revised to Correct Misprinting of Obverse Pages.Replacement Pages Will Be Included in Future Amend | South Texas | 25 June 1987 | | Forwards Revised Pages 3.6.A-1,3.6.A-2,9.2.9 & 9.2.10 from FSAR Amend 61.Pages Revised to Correct Misprinting of Obverse Pages.Replacement Pages Will Be Included in Future Amend |
| ST-HL-AE-2259, Forwards Addl Info Re Thermal Relief Capacity for Component Cooling Water Subsystem Providing Cooling Water to Reactor Coolant Pump,Reactor Coolant Drain Tank & Excess Letdown Hxs,Per C Tinkler Request | South Texas | 17 June 1987 | | Forwards Addl Info Re Thermal Relief Capacity for Component Cooling Water Subsystem Providing Cooling Water to Reactor Coolant Pump,Reactor Coolant Drain Tank & Excess Letdown Hxs,Per C Tinkler Request |
| ST-HL-AE-2232, Forwards Final Draft Tech Specs & Technical Changes W/ Justifications.Tech Specs Consistent W/Fsar.Ser & as-built Facility W/Exceptions,Editorial Changes & Corrections Noted on Encl marked-up Pages | South Texas | 5 June 1987 | | Forwards Final Draft Tech Specs & Technical Changes W/ Justifications.Tech Specs Consistent W/Fsar.Ser & as-built Facility W/Exceptions,Editorial Changes & Corrections Noted on Encl marked-up Pages |
| ST-HL-AE-2198, Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept | South Texas | 31 March 1987 | | Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept |
| ST-HL-AE-2182, Responds to Questions Raised in 870505 Meeting W/Nrc Re Util Compliance W/Gdc 56 & 57 & SRP 6.2.4 Concerning Remote Manual Isolation of Primary Containment Isolation Valves Following Dba.Revised Response to Generic Ltr 85-12 Encl | South Texas | 29 May 1987 | | Responds to Questions Raised in 870505 Meeting W/Nrc Re Util Compliance W/Gdc 56 & 57 & SRP 6.2.4 Concerning Remote Manual Isolation of Primary Containment Isolation Valves Following Dba.Revised Response to Generic Ltr 85-12 Encl |
| ST-HL-AE-2096, Forwards Changes & Justifications for Changes in Proof & Review Tech Specs in Listed Areas,Including Definitions, Setpoints & Bases | South Texas | 20 April 1987 | | Forwards Changes & Justifications for Changes in Proof & Review Tech Specs in Listed Areas,Including Definitions, Setpoints & Bases |
| ST-HL-AE-1971, Forwards Annotated Revs to FSAR App 3.6.A Re Isolation Valve Cubicle (Ivc) Subcompartment Analysis.Changes Update Ivc Pressure & Temp Analysis Results.Revs Will Be Incorporated in Future FSAR Amend | South Texas | 9 March 1987 | | Forwards Annotated Revs to FSAR App 3.6.A Re Isolation Valve Cubicle (Ivc) Subcompartment Analysis.Changes Update Ivc Pressure & Temp Analysis Results.Revs Will Be Incorporated in Future FSAR Amend |
| ST-HL-AE-1923, Requests That Encl Proposed Deletions & Changes to Specific Tech Specs Be Made in Final Proof & Review Tech Specs. Affected FSAR Pages Which Will Be Included as Part of FSAR Amend 58 Encl | South Texas | 13 March 1987 | | Requests That Encl Proposed Deletions & Changes to Specific Tech Specs Be Made in Final Proof & Review Tech Specs. Affected FSAR Pages Which Will Be Included as Part of FSAR Amend 58 Encl |
| ST-HL-AE-1710, Forwards marked-up FSAR Pages Re Deletion of Containment Spray Sump Additive Tank.Requests NRC Review Changes as Soon as Possible to Avoid Impacting Project Schedule | South Texas | 28 August 1986 | | Forwards marked-up FSAR Pages Re Deletion of Containment Spray Sump Additive Tank.Requests NRC Review Changes as Soon as Possible to Avoid Impacting Project Schedule |
| ST-HL-AE-1447, Forwards Response to Draft SER or FSAR Item F 3.8-2 Re Identification of Codes,Stds & Specs Applicable to Design. Changes Will Be Incorporated in Future FSAR Amend | South Texas | 22 October 1985 | | Forwards Response to Draft SER or FSAR Item F 3.8-2 Re Identification of Codes,Stds & Specs Applicable to Design. Changes Will Be Incorporated in Future FSAR Amend |
| ST-HL-AE-1388, Forwards Response to Draft SER & FSAR Items Re Chapter 7A,Item II.B.3 Concerning post-accident Sampling Capability. Marked-up FSAR Pages to Be Included in Future FSAR Amend Also Encl | South Texas | 14 October 1985 | | Forwards Response to Draft SER & FSAR Items Re Chapter 7A,Item II.B.3 Concerning post-accident Sampling Capability. Marked-up FSAR Pages to Be Included in Future FSAR Amend Also Encl |
| SNRC-2044, Forwards 10CFR50.59 Rept for 920101-0611. Activities Performed During Reporting Period Permitted by Possession Only License | Shoreham | 26 March 1993 | | Forwards 10CFR50.59 Rept for 920101-0611. Activities Performed During Reporting Period Permitted by Possession Only License |
| SNRC-2018, Responds to NRC Re Violations Noted in Insp Rept 50-322/92-04.Corrective Actions:On 920701,LIPA Submitted Ltr Entitled, Facility Status at Time of Decommissioning Order Issuance Relative to Shoreham Decommissioning Plan | Shoreham | 4 January 1993 | | Responds to NRC Re Violations Noted in Insp Rept 50-322/92-04.Corrective Actions:On 920701,LIPA Submitted Ltr Entitled, Facility Status at Time of Decommissioning Order Issuance Relative to Shoreham Decommissioning Plan |
| SNRC-1904, Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991 | Shoreham | 30 March 1992 | | Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991 |
| SNRC-1899, Requests Amend to License NPF-82 Adding New License Condition to Authorize Decommissioning of Shoreham | Shoreham | 22 January 1992 | | Requests Amend to License NPF-82 Adding New License Condition to Authorize Decommissioning of Shoreham |
| SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 | Shoreham | 31 December 1990 | | 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 |
| SNRC-1692, Requests Interim Relief from Primary Containment Leak Rate Testing Requirements of 10CFR50.54(o) & App J,III.D.1-3 Pending NRC Disposition of Lilco 891208 Request for Exemption from Same Requirements | Shoreham | 13 March 1990 | | Requests Interim Relief from Primary Containment Leak Rate Testing Requirements of 10CFR50.54(o) & App J,III.D.1-3 Pending NRC Disposition of Lilco 891208 Request for Exemption from Same Requirements |
| SNRC-1658, Responds to T Murley Re 10CFR2.206 Petitions. Requests in Shoreham-Wading River School District & Scientists & Engineers for Secure Energy & Long Island Assn Petitions for Return to Status Quo Ante Should Be Denied | Shoreham | 10 November 1989 | | Responds to T Murley Re 10CFR2.206 Petitions. Requests in Shoreham-Wading River School District & Scientists & Engineers for Secure Energy & Long Island Assn Petitions for Return to Status Quo Ante Should Be Denied |
| SNRC-1644, Advises of Intention to Defer Further Primary Containment Leak Rate Testing Consistent w/10CFR50,App J & Requirements of License NPF-82.Facilities Tech Specs Do Not Require That Primary Containment Integrity Be Maintained | Shoreham | 3 November 1989 | | Advises of Intention to Defer Further Primary Containment Leak Rate Testing Consistent w/10CFR50,App J & Requirements of License NPF-82.Facilities Tech Specs Do Not Require That Primary Containment Integrity Be Maintained |
| SNRC-1583, Forwards Supplemental Info Re Temp Profile Inside Primary Containment Used for Environ Qualification | Shoreham | 12 April 1989 | | Forwards Supplemental Info Re Temp Profile Inside Primary Containment Used for Environ Qualification |
| SNRC-1578, Provides Info Re Temp Profile Inside Primary Containment Used for Environ Qualification.Results of Review of Actual Test Temps Indicate Sufficient Margin Exists to Envelope Supporting Calcuation & Environ Qualification Profile | Shoreham | 4 April 1989 | | Provides Info Re Temp Profile Inside Primary Containment Used for Environ Qualification.Results of Review of Actual Test Temps Indicate Sufficient Margin Exists to Envelope Supporting Calcuation & Environ Qualification Profile |
| SNRC-1573, Submits Proposed Actions for Issues Discussed at Operational Readiness Assessment Team Insp Exit Meeting.Util Committed to Completing ASME Bolting Corrective Actions & Having Documentation to Demonstrate Prior to Startup | Shoreham | 31 March 1989 | | Submits Proposed Actions for Issues Discussed at Operational Readiness Assessment Team Insp Exit Meeting.Util Committed to Completing ASME Bolting Corrective Actions & Having Documentation to Demonstrate Prior to Startup |
| SNRC-1561, Responds to 10CFR50.63 Re Station Blackout (SBO) Rule.Util Has Determined That in Unlikely Event of Sbo,Station Possesses Sufficient Independent & Diverse Alternate Ac Power Capacity | Shoreham | 14 April 1989 | | Responds to 10CFR50.63 Re Station Blackout (SBO) Rule.Util Has Determined That in Unlikely Event of Sbo,Station Possesses Sufficient Independent & Diverse Alternate Ac Power Capacity |
| SNRC-1552, Forwards Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Engineering Study Verified That Instrument Air Receivers & Accumulators Designed Per ANSI & ASME Codes | Shoreham | 21 February 1989 | | Forwards Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Engineering Study Verified That Instrument Air Receivers & Accumulators Designed Per ANSI & ASME Codes |
| SNRC-1546, Forwards 10CFR50.59 Rept for 1988.During Reporting Period, Emergency Operating Procedures Updated to Comply W/Recommendations of BWR Owners Group Emergency Procedure Guidelines,Rev 4.Procedure Change Notices Encl | Shoreham | 14 March 1989 | | Forwards 10CFR50.59 Rept for 1988.During Reporting Period, Emergency Operating Procedures Updated to Comply W/Recommendations of BWR Owners Group Emergency Procedure Guidelines,Rev 4.Procedure Change Notices Encl |
| SNRC-1464, Forwards Comments W/Supporting Documentation Re post-NRC Written Operator Exams,To Assist in Evaluating Responses to Exam Questions | Shoreham | 20 May 1988 | | Forwards Comments W/Supporting Documentation Re post-NRC Written Operator Exams,To Assist in Evaluating Responses to Exam Questions |
| SNRC-1444, Responds to NRC Re Violations Noted in Insp Rept 50-322/88-01.Corrective Actions:Change to Station Procedure Sp 84.654.03 Approved,Cautioning Against Overpressurizing Test Vols Utilizing Water | Shoreham | 18 April 1988 | | Responds to NRC Re Violations Noted in Insp Rept 50-322/88-01.Corrective Actions:Change to Station Procedure Sp 84.654.03 Approved,Cautioning Against Overpressurizing Test Vols Utilizing Water |
| SNRC-1429, Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment | Shoreham | 31 December 1987 | | Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment |
| SNRC-1424, Forwards Shoreham Nuclear Power Station PRA W/Supplemental Containment Sys, in Response to NRC Questions.Requests Concurrence W/Quality Group Categorization by 880408 | Shoreham | 2 March 1988 | | Forwards Shoreham Nuclear Power Station PRA W/Supplemental Containment Sys, in Response to NRC Questions.Requests Concurrence W/Quality Group Categorization by 880408 |
| SNRC-1397, Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl | Shoreham | 4 December 1987 | | Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl |
| SNRC-1376, Responds to Re Violations Noted in Insp Rept 50-322/87-10.Corrective Actions:Two Solenoid Operated Valve Splices Removed & Replaced W/Approved Splices & Electrical Maint Personnel Instructed Re Proper Requirements | Shoreham | 30 September 1987 | | Responds to Re Violations Noted in Insp Rept 50-322/87-10.Corrective Actions:Two Solenoid Operated Valve Splices Removed & Replaced W/Approved Splices & Electrical Maint Personnel Instructed Re Proper Requirements |
| SNRC-1370, Responds to NRC Bulletin 87-001 Re Thinning of Pipe Walls. Programs for Monitoring Wall Thickness of Carbon Steel Pipes in Safety & nonsafety-related Portions of Condensate, Feedwater & Connected high-energy Piping Sys Discussed | Shoreham | 14 September 1987 | | Responds to NRC Bulletin 87-001 Re Thinning of Pipe Walls. Programs for Monitoring Wall Thickness of Carbon Steel Pipes in Safety & nonsafety-related Portions of Condensate, Feedwater & Connected high-energy Piping Sys Discussed |
| SNRC-1367, Requests Concurrence W/Proposed Supplemental Containment Sys Plan & Response to Encl NRC Concerns,W/Understanding That NRC Reserves Right to Review & Comment on Detailed Design Submittal | Shoreham | 28 August 1987 | | Requests Concurrence W/Proposed Supplemental Containment Sys Plan & Response to Encl NRC Concerns,W/Understanding That NRC Reserves Right to Review & Comment on Detailed Design Submittal |
| SNRC-1348, Forwards Addl Info Re Low Power Operation at 25%,per 870616 Request.Info Should Close Out Correspondence in View of NRC Cancellation of Util 25% Power Request | Shoreham | 4 August 1987 | | Forwards Addl Info Re Low Power Operation at 25%,per 870616 Request.Info Should Close Out Correspondence in View of NRC Cancellation of Util 25% Power Request |
| SNRC-1305, Rept of Changes,Tests & Experiments Completed During 1985, Per 10CFR50.4 & 50.59 | Shoreham | 31 December 1985 | | Rept of Changes,Tests & Experiments Completed During 1985, Per 10CFR50.4 & 50.59 |
| SNRC-1303, Proposes Method for Determining Operability of Primary Containment Air Cooler Condensate Flow Indication Sys,In Response to NRC Questions Raised During Review of 851116 Application for License Amend.Figure 13.5.1-2 Encl | Shoreham | 30 March 1987 | | Proposes Method for Determining Operability of Primary Containment Air Cooler Condensate Flow Indication Sys,In Response to NRC Questions Raised During Review of 851116 Application for License Amend.Figure 13.5.1-2 Encl |
| SNRC-1296, Forwards Updated SAR for Shoreham Nuclear Power Station & Rev 6 to Plant Design Assessment Rept for Safety Relief Valves & LOCA Loads.... Encl Proprietary Suppl to Assessment Rept Withheld (Ref 10CFR2.790) | Shoreham | 2 December 1986 | | Forwards Updated SAR for Shoreham Nuclear Power Station & Rev 6 to Plant Design Assessment Rept for Safety Relief Valves & LOCA Loads.... Encl Proprietary Suppl to Assessment Rept Withheld (Ref 10CFR2.790) |
| SNRC-1261, Rev 1 to Transient Analysis Lesson Plan | Shoreham | 30 May 1986 | | Rev 1 to Transient Analysis Lesson Plan |
| SNRC-1243, Requests Temporary Exemption from Requirements of 10CFR50.44(c)(3)(i) Re Inerting of Containment.Exemption Necessary Due to Publication & Effectiveness of Commission Final Rule on Specific Exemptions | Shoreham | 27 March 1986 | | Requests Temporary Exemption from Requirements of 10CFR50.44(c)(3)(i) Re Inerting of Containment.Exemption Necessary Due to Publication & Effectiveness of Commission Final Rule on Specific Exemptions |
| SNRC-1239, Forwards Addl Info in Support of License Change Request 2. Change Requested to Reduce Personnel Exposure to Radiation During Power Ascension Test Program.Drywell Air Cooler Condensate Flow Indication Sys Described | Shoreham | 18 March 1986 | | Forwards Addl Info in Support of License Change Request 2. Change Requested to Reduce Personnel Exposure to Radiation During Power Ascension Test Program.Drywell Air Cooler Condensate Flow Indication Sys Described |
| SNRC-1215, Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage | Shoreham | 12 November 1985 | | Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage |
| SNRC-1209, Forwards Response to WR Butler Re Review of Eg&G Evaluation of Implementation of Rev 2 to Reg Guide 1.97 Concerning Emergency Response Capability | Shoreham | 23 October 1985 | | Forwards Response to WR Butler Re Review of Eg&G Evaluation of Implementation of Rev 2 to Reg Guide 1.97 Concerning Emergency Response Capability |
| SNRC-1169, Informs That Based on General Physics Job/Task Analysis,Util Position That Tdi Emergency Diesel Generators Can Be Effectively Operated w/3300 Kw Qualified Load Substantiated. General Physics Recommendations to Improve Procedures Encl | Shoreham | 6 May 1985 | | Informs That Based on General Physics Job/Task Analysis,Util Position That Tdi Emergency Diesel Generators Can Be Effectively Operated w/3300 Kw Qualified Load Substantiated. General Physics Recommendations to Improve Procedures Encl |
| SNRC-1158, Forwards Revised Fire Hazard Analysis Rept Sections in Response to Items Noted in Insp Rept 50-322/84-46,per Util 850129 Commitment.Changes Do Not Decrease Level of Fire Protection at Facility | Shoreham | 5 April 1985 | | Forwards Revised Fire Hazard Analysis Rept Sections in Response to Items Noted in Insp Rept 50-322/84-46,per Util 850129 Commitment.Changes Do Not Decrease Level of Fire Protection at Facility |
| SNRC-1150, Forwards Addl Info Re Operator Training,In Response to NRC 850205 Request.Reasonable Assurance Exists That Loads in Excess of Qualified Load Will Not Be Imposed Upon Tdi Emergency Diesel Generators by Operators | Shoreham | 4 April 1985 | | Forwards Addl Info Re Operator Training,In Response to NRC 850205 Request.Reasonable Assurance Exists That Loads in Excess of Qualified Load Will Not Be Imposed Upon Tdi Emergency Diesel Generators by Operators |
| SNRC-1130, Deficiency Rept Re Failure to Install HVAC Penetration Seals to Protect Two Trains of Redundant Safe Shutdown Motor Control Ctrs.Initially Reported on 841129.Sealing of Gaps Completed on 841208 | Shoreham | 28 December 1984 | | Deficiency Rept Re Failure to Install HVAC Penetration Seals to Protect Two Trains of Redundant Safe Shutdown Motor Control Ctrs.Initially Reported on 841129.Sealing of Gaps Completed on 841208 |
| SNRC-1105, Forwards Exemption Requests for Containment Isolation, MSIV-App J Testing,Seismic Qualifications & Remote Shutdown, Per NRC Request Resulting from Commission Order CLI-84-8 | Shoreham | 9 November 1984 | | Forwards Exemption Requests for Containment Isolation, MSIV-App J Testing,Seismic Qualifications & Remote Shutdown, Per NRC Request Resulting from Commission Order CLI-84-8 |
| SNRC-1104, Forwards Requested Addl Info Re Various Aspects of Newly Developed Qualified Load for Tdi Diesel Generators,Per 841026 Telcon | Shoreham | 19 November 1984 | | Forwards Requested Addl Info Re Various Aspects of Newly Developed Qualified Load for Tdi Diesel Generators,Per 841026 Telcon |
| SNRC-1101, Forwards Addl Info Re FSAR Chapter 13, Conduct of Operations, Submitted as Part of Amend 51 to License Application.Resumes for Watch Engineers Assigned to Shift Crews Encl,Per Reg Guide 1.8 | Shoreham | 12 November 1984 | | Forwards Addl Info Re FSAR Chapter 13, Conduct of Operations, Submitted as Part of Amend 51 to License Application.Resumes for Watch Engineers Assigned to Shift Crews Encl,Per Reg Guide 1.8 |
| SNRC-1092, Forwards Revised FSAR Sections,Providing Detailed Technical Bases & Methods Utilized in Developing Qualified Load of 3,300 Kw,In Response to Section 4.6 of SER on Tdi Owners Group Program Plan.Revs to Be Included in Fsar,Rev 34 | Shoreham | 22 October 1984 | | Forwards Revised FSAR Sections,Providing Detailed Technical Bases & Methods Utilized in Developing Qualified Load of 3,300 Kw,In Response to Section 4.6 of SER on Tdi Owners Group Program Plan.Revs to Be Included in Fsar,Rev 34 |
| SNRC-1085, Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR | Shoreham | 25 September 1984 | | Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR |
| SNRC-1082, Submits Status of Evaluation Re IE Info Notice 84-17, Problems W/Liquid Nitrogen Cooling Components Below Nil Ductility Temp & GE Svc Info Ltr SIL-402, Wetwell/Drywell Inerting | Shoreham | 18 September 1984 | | Submits Status of Evaluation Re IE Info Notice 84-17, Problems W/Liquid Nitrogen Cooling Components Below Nil Ductility Temp & GE Svc Info Ltr SIL-402, Wetwell/Drywell Inerting |
| SNRC-1078, Forwards Revs to FSAR Chapter 13, Conduct of Operations & Section 17.2, QA During Operations Phase, Reflecting Operational Readiness.Revs Will Be Included in Forthcoming Rev 33 to FSAR | Shoreham | 5 September 1984 | | Forwards Revs to FSAR Chapter 13, Conduct of Operations & Section 17.2, QA During Operations Phase, Reflecting Operational Readiness.Revs Will Be Included in Forthcoming Rev 33 to FSAR |
| SNRC-1044, Forwards News Release Re Changes in Util Mgt,Resumes of Leonard,Steiger,Smith,Youngling,Kubinak,Greene,J Scalice, D Terry,J Schmitt & Ja Notaro & Two Charts Reflecting Revised Organization | Shoreham | 8 May 1984 | | Forwards News Release Re Changes in Util Mgt,Resumes of Leonard,Steiger,Smith,Youngling,Kubinak,Greene,J Scalice, D Terry,J Schmitt & Ja Notaro & Two Charts Reflecting Revised Organization |
| SNRC-1026, Forwards Supplemental Motion for Low Power OL | Shoreham | 21 March 1984 | | Forwards Supplemental Motion for Low Power OL |
| SNRC-1014, Provides Justification for Deletion of Station Blackout Test & Completion of Program for Training During Low Power Testing,Per TMI Item I.G.1,in Response to Generic Ltr 83-24 | Shoreham | 16 February 1984 | | Provides Justification for Deletion of Station Blackout Test & Completion of Program for Training During Low Power Testing,Per TMI Item I.G.1,in Response to Generic Ltr 83-24 |
| SNRC-1012, Clarifies Sept 1983 Draft Technical Evaluation Rept of Phase II Submittal of Control of Heavy Loads,Per 840109 Telcon. Safe Load Paths for Reactor Bldg Closed Loop Cooling Water Pumps Revised | Shoreham | 5 March 1984 | | Clarifies Sept 1983 Draft Technical Evaluation Rept of Phase II Submittal of Control of Heavy Loads,Per 840109 Telcon. Safe Load Paths for Reactor Bldg Closed Loop Cooling Water Pumps Revised |
| SECY-23-0076, Weekly Information Report Week Ending August 18, 2023 | | 28 August 2023 | | SECY-23-0076: Weekly Information Report Week Ending August 18, 2023 |
| SECY-22-0046, SRM-SECY-22-0046: Enclosure 1 - Report to Congress on Abnormal Occurrences: Fiscal Year 2021 | | 27 June 2022 | | SRM-SECY-22-0046: Enclosure 1 - Report to Congress on Abnormal Occurrences: Fiscal Year 2021 |
| SECY-19-0024, VR-SECY-19-0024: Report to Congress on Abnormal Occurrences: Fiscal Year 2018 | | 30 April 2019 | | VR-SECY-19-0024: Report to Congress on Abnormal Occurrences: Fiscal Year 2018 |
| SECY-18-0031, Enclosure 1 - Report to Congress on Abnormal Occurrences Fiscal Year 2017 (NUREG-0090 Vol.40) | | 28 February 2018 | | SECY-18-0031: Enclosure 1 - Report to Congress on Abnormal Occurrences Fiscal Year 2017 (NUREG-0090 Vol.40) |
| SECY-11-0124, Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 3 | | 17 July 2013 | | Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 3 |
| SECY-04-0233, Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire | | 22 December 2004 | | SECY-04-0233Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire |
| SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan | Seabrook | 4 January 2022 | | Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan |
| SBK-L-19129, Submittal of Changes to the Seabrook Station Technical Specification Bases | Seabrook | 31 December 2019 | | Submittal of Changes to the Seabrook Station Technical Specification Bases |
| SBK-L-19049, License Amendment Request 19-01, Application to Revise the Technical Specifications Associated with Emergency Core Cooling System Accumulators | Seabrook | 4 June 2019 | | License Amendment Request 19-01, Application to Revise the Technical Specifications Associated with Emergency Core Cooling System Accumulators |
| SBK-L-18195, Submittal of Changes to the Seabrook Station Technical Specification Bases | Seabrook | 18 December 2018 | | Submittal of Changes to the Seabrook Station Technical Specification Bases |
| SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program | Seabrook | 28 February 2018 | | 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program |
| SBK-L-18027, 9 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program | Seabrook | 28 February 2018 | | 9 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program |
| SBK-L-17185, License Amendment Request 17-04: Remove Limitation to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications | Seabrook | 1 December 2017 | | License Amendment Request 17-04: Remove Limitation to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications |
| SBK-L-16181, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program | Seabrook | 23 December 2016 | | License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program |
| SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency | Seabrook | 27 October 2016 | | Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency |
| SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors | Seabrook | 27 October 2016 | | Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
| SBK-L-16022, Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction | Seabrook | 23 February 2016 | | Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction |
| SBK-L-15228, Submittal of Changes to the Technical Specification Bases | Seabrook | 5 January 2016 | | Submittal of Changes to the Technical Specification Bases |
| SBK-L-14184, Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program | Seabrook | 11 December 2014 | | Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program |
| SBK-L-14086, Nextera Energy Seabrook - Letter Regarding Response to Requests for Additional Information for the Review of the License Renewal Application Set 20 Relating to the Alkali-Silica Reaction (ASR) Monitoring Program | Seabrook | 15 May 2014 | | Nextera Energy Seabrook - Letter Regarding Response to Requests for Additional Information for the Review of the License Renewal Application Set 20 Relating to the Alkali-Silica Reaction (ASR) Monitoring Program |
| SBK-L-14024, License Amendment Request (LAR) - 14-01, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler - 523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated | Seabrook | 24 June 2014 | | License Amendment Request (LAR) - 14-01, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler - 523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated |
| SBK-L-13225, Submittal of Changes to the Seabrook Station Technical Specification Bases | Seabrook | 12 December 2013 | | Submittal of Changes to the Seabrook Station Technical Specification Bases |
| SBK-L-13147, Administrative Changes to License Amendment Requests in NRC Review | Seabrook | 31 July 2013 | | Administrative Changes to License Amendment Requests in NRC Review |
| SBK-L-13028, License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical Specifications | Seabrook | 1 March 2013 | | License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical Specifications |
| SBK-L-12266, Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System | Seabrook | 31 January 2013 | | Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System |
| SBK-L-12185, To Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal Application | Seabrook | 13 September 2012 | | To Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal Application |
| SBK-L-12124, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System | Seabrook | 2 July 2012 | | Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System |
| SBK-L-12054, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System | Seabrook | 15 March 2012 | | Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System |
| SBK-L-12053, To Severe Accident Mitigation Alternatives Analysis, License Renewal Application | Seabrook | 19 March 2012 | | To Severe Accident Mitigation Alternatives Analysis, License Renewal Application |
| SBK-L-12052, Submittal of Changes to Technical Specification Bases | Seabrook | 16 February 2012 | | Submittal of Changes to Technical Specification Bases |
| SBK-L-11233, Response to Request for Additional Information - Set 17 | Seabrook | 17 November 2011 | | Response to Request for Additional Information - Set 17 |
| SBK-L-11186, License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure - Temperature Limits and the Cold Overpressure Protection Setpoints | Seabrook | 17 November 2011 | | License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure - Temperature Limits and the Cold Overpressure Protection Setpoints |
| SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System | Seabrook | 16 September 2011 | | Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System |
| SBK-L-11141, Submittal of Special Report Regarding Containment Enclosure Building Structural Integrity | Seabrook | 11 July 2011 | | Submittal of Special Report Regarding Containment Enclosure Building Structural Integrity |
| SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program | Seabrook | 22 June 2011 | | Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program |
| SBK-L-11066, License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation | Seabrook | 21 April 2011 | | License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation |
| SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal Application | Seabrook | 13 January 2011 | | Response to Request for Additional Information, NextEra Energy License Renewal Application |
| SBK-L-10236, Submittal of Changes to the Technical Specification Bases | Seabrook | 30 December 2010 | | Submittal of Changes to the Technical Specification Bases |
| SBK-L-10204, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs | Seabrook | 17 December 2010 | | Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs |
| SBK-L-10143, Response to Request for Additional Information Regarding License Amendment Request (LAR) 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System | Seabrook | 24 August 2010 | | Response to Request for Additional Information Regarding License Amendment Request (LAR) 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System |
| SBK-L-10097, License Amendment Request 10-03 | Seabrook | 28 June 2010 | | License Amendment Request 10-03 |
| SBK-L-10074, License Amendment Request 10-02 | Seabrook | 14 May 2010 | | License Amendment Request 10-02 |
| SBK-L-08216, Submittal of Changes to Technical Specification Bases | Seabrook | 16 December 2008 | | Submittal of Changes to Technical Specification Bases |
| SBK-L-07139, Response to Request for Additional Information for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes | Seabrook | 7 August 2007 | | Response to Request for Additional Information for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes |
| SBK-L-06127, Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change | Seabrook | 7 June 2006 | | Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change |
| SBK-L-06065, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | Seabrook | 28 April 2006 | | Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process |
| SBK-L-06059, License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes | Seabrook | 7 August 2006 | | License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes |
| SBK-L-05197, License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval | Seabrook | 29 September 2005 | | License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval |
| SBK-L-04121, Submittal of Changes to the Seabrook Station Technical Specification Bases | Seabrook | 2 December 2004 | | Submittal of Changes to the Seabrook Station Technical Specification Bases |
| SBK-L-04053, License Amendment Request 04-07, Revision to Technical Specification Surveillance Requirement 4.6.1.3b, Containment Air Lock Interlock | Seabrook | 10 January 2005 | | License Amendment Request 04-07, Revision to Technical Specification Surveillance Requirement 4.6.1.3b, Containment Air Lock Interlock |
| SBK-L-04050, Submittal of Changes to the Plant Technical Specification Bases | Seabrook | 2 September 2004 | | Submittal of Changes to the Plant Technical Specification Bases |
| Regulatory Guide 7.9 | | 31 January 1980 | | Standard Format & Content of Part 71 Applications for Approval of Packaging of Type B,Large Quantity & Fissile Radioactive Material |
| Regulatory Guide 7.10 | | 30 June 1986 | | Rev. 1, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material |
| Regulatory Guide 1.97 | | 31 May 1983 | | Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant & Environs Conditions During & Following Accident |
| Regulatory Guide 1.96 | | 30 June 1976 | | Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants |
| Regulatory Guide 1.77 | | 31 May 1974 | | Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors |
| Regulatory Guide 1.57 | | 30 June 1973 | | Design Limits and Loading Combinations for Metal Primary Reactor Containment Systems Components |
| Regulatory Guide 1.52 | | 30 June 2001 | | (Revision 3), Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants |
| Regulatory Guide 1.33 | | 28 February 1978 | | Quality Assurance Program Requirements (Operation) |
| Regulatory Guide 1.3 | | 30 June 1974 | | Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors |
| Regulatory Guide 1.195 | | 31 May 2003 | | Methods and Assumptions for Evaluating Radiological Consequences of Design-Basis Accidents at Light-Water Nuclear Power Reactors |
| Regulatory Guide 1.194 | | 1 June 2003 | | Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants |
| Regulatory Guide 1.16 | | 31 August 1975 | | Reporting of Operating Information - Appendix a Technical Specifications |
| Regulatory Guide 1.158 | | 28 February 1989 | | (Task Ee 006-5) Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants |
| Regulatory Guide 1.141 | | 30 April 1978 | | Containment Isolation Provisions for Fluid Systems |
| Regulatory Guide 1.140 | | 30 June 2001 | | (Revision 2), Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants |
| Regulatory Guide 1.117 | | 30 April 1978 | | Rev 1,Tornado Design Classification |
| Regulatory Guide 1.11 | | 31 March 2010 | | Instrument Lines Penetrating the Primary Reactor Containment |
| RS-25-085, Subsequent License Renewal Application Affected Changes | Dresden | 28 April 2025 | | Subsequent License Renewal Application Affected Changes |
| RS-25-055, Supplement No. 4 - Changes to the Clinton Power Station, Unit 1, License Renewal Application | Clinton | 25 March 2025 | | Supplement No. 4 - Changes to the Clinton Power Station, Unit 1, License Renewal Application |
| RS-25-013, Supplement No. 3 - Changes to License Renewal Application | Clinton | 30 January 2025 | | Supplement No. 3 - Changes to License Renewal Application |
| RS-25-010, Constellation Energy Generation - Application to Revise Technical Specifications to Adopt TSTF-597, Revision 0, Eliminate LCO 3.0.3 Mode 2 Requirement | Peach Bottom
Nine Mile Point
Limerick
Clinton
FitzPatrick
LaSalle | 31 January 2025 | | Constellation Energy Generation - Application to Revise Technical Specifications to Adopt TSTF-597, Revision 0, Eliminate LCO 3.0.3 Mode 2 Requirement |
| RS-24-133, Supplement No. 2 - Changes to the Clinton Power Station, Unit 1 - License Renewal Application | Clinton | 20 December 2024 | | Supplement No. 2 - Changes to the Clinton Power Station, Unit 1 - License Renewal Application |
| RS-24-106, Request RV-04, Proposed Alternative to Modify Reactor Pressure Vessel Safety Relief Valve Testing Sampling Requirements Per Inservice Test Program | LaSalle | 25 November 2024 | | Request RV-04, Proposed Alternative to Modify Reactor Pressure Vessel Safety Relief Valve Testing Sampling Requirements Per Inservice Test Program |
| RS-24-102, Supplement to 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, and TSTF-591 | Dresden | 21 October 2024 | | Supplement to 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, and TSTF-591 |
| RS-24-101, License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair | Quad Cities | 4 November 2024 | | License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair |
| RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed | Quad Cities | 6 June 2024 | | Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed |
| RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation | Clinton | 9 May 2024 | | Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation |
| RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion | Quad Cities | 5 April 2024 | | Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion |
| RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF | Quad Cities | 19 March 2024 | | Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF |
| RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation | Clinton | 21 August 2023 | | Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation |
| RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges | Quad Cities | 24 April 2023 | | Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges |
| RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing | Clinton | 13 January 2023 | | Application to Adopt TSTF-332, ECCS Response Time Testing |
| RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval | Dresden | 1 November 2022 | | Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval |
| RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration | Dresden
Nine Mile Point
Clinton
Quad Cities
LaSalle | 3 October 2022 | | Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration |
| RS-22-085, Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis | LaSalle | 12 January 2023 | | Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis |
| RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station | Quad Cities | 25 May 2022 | | Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station |
| RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves | Clinton | 24 May 2022 | | Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves |
| RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling | Clinton | 24 May 2022 | | Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling |
| RS-22-056, Constellation Radiological Emergency Plan Addendum Revision | Quad Cities | 21 April 2022 | | Constellation Radiological Emergency Plan Addendum Revision |
| RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock | Clinton | 7 April 2022 | | Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock |
| RS-22-011, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval | Quad Cities | 17 February 2022 | | Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval |
| RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements | Calvert Cliffs
Dresden
Peach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
Ginna
Clinton
Quad Cities
FitzPatrick
LaSalle | 4 January 2022 | | Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements |
| RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel | Dresden
Clinton
Quad Cities
LaSalle | 19 August 2021 | | Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel |
| RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements | Peach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
Ginna
Clinton
Quad Cities
FitzPatrick
LaSalle | 30 June 2021 | | Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements |
| RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b | LaSalle | 31 March 2021 | | Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b |
| RS-21-036, Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition | Dresden | 16 March 2021 | | Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition |
| RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency | Clinton | 24 February 2021 | | License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency |
| RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology | LaSalle | 10 February 2021 | | Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology |
| RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1 | Byron | 17 December 2020 | | Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1 |
| RS-20-139, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 | Clinton | 24 November 2020 | | Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 |
| RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) | LaSalle | 29 October 2020 | | Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) |
| RS-20-126, EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart | Braidwood | 13 October 2020 | | EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart |
| RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements | Dresden
Clinton
Quad Cities
LaSalle | 18 November 2020 | | Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements |
| RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 | Dresden
Peach Bottom
Nine Mile Point
Limerick
Quad Cities
LaSalle | 3 September 2020 | | Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 |
| RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 | Quad Cities | 1 April 2020 | | Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 |
| RS-20-038, Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance | Dresden | 6 May 2020 | | Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance |
| RS-20-031, License Amendment Request - Application to 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, Using the Consolidated Line Item Improvement Process | Dresden
Peach Bottom
Nine Mile Point
Limerick
Quad Cities
LaSalle | 30 April 2020 | | License Amendment Request - Application to 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, Using the Consolidated Line Item Improvement Process |
| RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) | Calvert Cliffs
Peach Bottom
Nine Mile Point
Braidwood
Limerick
Ginna
Clinton | 28 February 2020 | | Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) |
| RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues | Byron
Braidwood
Ginna | 6 February 2020 | | Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues |
| RS-20-001, Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer | Clinton | 14 January 2020 | | Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer |
| RS-19-116, Relief Requests Associated with the Fourth Inservice Inspection Interval | Clinton | 16 December 2019 | | Relief Requests Associated with the Fourth Inservice Inspection Interval |
| RS-19-098, Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report | Quad Cities | 21 October 2019 | | Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report |
| RS-19-076, Supplement to License Amendment Request to Increase Technical Specifications Allowable MSIV Leakage Rates | Quad Cities | 22 July 2019 | | Supplement to License Amendment Request to Increase Technical Specifications Allowable MSIV Leakage Rates |
| RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control | Dresden
Clinton | 18 June 2019 | | Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control |
| RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program | Calvert Cliffs
Dresden
Peach Bottom
Nine Mile Point
Palisades
Byron
Braidwood
Limerick
Ginna
Clinton
Quad Cities
FitzPatrick
LaSalle | 25 June 2019 | | Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program |
| RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control | Dresden
Peach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
Ginna
Quad Cities
FitzPatrick
LaSalle | 14 June 2019 | | Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control |
| RS-18-131, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | LaSalle | 14 December 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions |
| RS-18-113, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident. | Peach Bottom | 28 September 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident. |
| RS-18-106, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | Limerick | 14 November 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions |
| RS-18-103, Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation | Clinton | 29 August 2018 | | Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation |
| RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from . | Peach Bottom | 28 August 2018 | | Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from . |
| RS-18-089, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109) | Quad Cities | 14 August 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109) |
| RS-18-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Quad Cities | 14 August 2018 | | Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) |
| RS-18-060, Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . | Peach Bottom | 29 June 2018 | | Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . |
| RS-18-059, Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident | Limerick | 29 June 2018 | | Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident |
| RS-18-058, Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under . | LaSalle | 22 June 2018 | | Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under . |
| RS-18-052, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | Limerick | 7 June 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions |
| RS-18-051, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | Limerick | 7 June 2018 | | Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
| RS-18-036, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | LaSalle | 9 May 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions |
| RS-18-030, Relief Requests Associated with the Fourth Inservice Inspection Interval | Braidwood | 19 March 2018 | | Relief Requests Associated with the Fourth Inservice Inspection Interval |
| RS-18-028, License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator | LaSalle | 19 April 2018 | | License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator |
| RS-18-022, Response to NRC Request for Additional Information for Request for License Amendment to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program | Dresden | 14 February 2018 | | Response to NRC Request for Additional Information for Request for License Amendment to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program |
| RS-18-005, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation | Clinton | 9 January 2018 | | License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation |
| RS-18-003, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | Dresden | 12 January 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions |
| RS-18-001, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) | Peach Bottom | 5 January 2018 | | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) |
| RS-17-164, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control | Clinton | 20 December 2017 | | Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control |
| RS-17-162, Radiological Emergency Plan Addendum Revision | LaSalle | 15 November 2017 | | Radiological Emergency Plan Addendum Revision |
| RS-17-157, Supplemental Information Regarding the Third Interval Containment Inservice Inspection (Cisi) Schedule for LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals | LaSalle | 8 November 2017 | | Supplemental Information Regarding the Third Interval Containment Inservice Inspection (Cisi) Schedule for LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals |
| RS-17-155, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . | Peach Bottom | 15 December 2017 | | Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . |
| RS-17-153, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . | Limerick | 15 December 2017 | | Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . |
| RS-17-152, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . | LaSalle | 15 December 2017 | | Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable . |
| RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control | Clinton | 15 November 2017 | | Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control |
| RS-17-133, Additional Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals | LaSalle | 3 October 2017 | | Additional Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals |
| RS-17-131, Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals | LaSalle | 27 September 2017 | | Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals |
| RS-17-130, Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies | Quad Cities | 28 September 2017 | | Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 8, Electric Power | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 8, Electric Power |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant | Quad Cities | 19 October 2017 | | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant |
| RS-17-125, Relief Request RV-2 Associated with the Fourth Inservice Testing Interval | Byron | 25 September 2017 | | Relief Request RV-2 Associated with the Fourth Inservice Testing Interval |
| RS-17-111, Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies | Quad Cities | 27 July 2017 | | Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies |
| RS-17-101, Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis | LaSalle | 28 July 2017 | | Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis |
| RS-17-099, Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch) | LaSalle | 8 August 2017 | | Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch) |
| RS-17-098, Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) | LaSalle | 17 July 2017 | | Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) |
| RS-17-096, Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) | Peach Bottom | 28 August 2017 | | Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) |
| RS-17-086, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control | Dresden | 13 July 2017 | | Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control |
| RS-17-082, Dresden, Units 1, 2 and 3 - Updated Final Safety Analysis Report (Ufsar), Revision 12 and Fire Protection Report (Fpr), Amendment 21 | Dresden | 21 June 2017 | | Dresden, Units 1, 2 and 3 - Updated Final Safety Analysis Report (Ufsar), Revision 12 and Fire Protection Report (Fpr), Amendment 21 |
| RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program | Dresden | 21 June 2017 | | Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program |