Primary containment

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Primary Containment is the 3rd barrier to stop the release of radiological material. It is typically called the Drywell and Suppression Chamber

 SiteStart dateReporting criterionTitle
ZS-2013-0195, Fire Protection Report, Amendment 13Zion31 July 2013Fire 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 SubmittalZion
07100956		12 July 2012Quality 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 InstallationZion
07100950		23 February 2011Quality Assurance Program for the Independent Spent Fuel Storage Installation
ZS-2010-0199, Submittal of Quality Assurance Project Plan, ZS-QA-10Zion27 July 2010Submittal of Quality Assurance Project Plan, ZS-QA-10
WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesWolf Creek20 April 2020License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
WO 17-0013, Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level SchemeWolf Creek16 March 2017Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level Scheme
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 ReactorsWolf Creek30 September 2016Operating 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 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation ValvesWolf Creek23 July 2004Revision to Technical Specification 3.6.3, Containment Isolation Valves
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 Creek17 October 2003Revision 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 QuestionsWolf Creek31 May 2016Wolf 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 ControlsWolf Creek31 May 2016Wolf 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 FeaturesWolf Creek31 May 2016Wolf 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 RequirementsWolf Creek31 May 2016Wolf 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 PlantWolf Creek31 May 2016Wolf 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 AnalysisWolf Creek31 May 2016Wolf 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 CableWolf Creek2 June 2010Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical Cable
WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)Watts Bar29 October 2020Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)
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 36Waterford10 May 1988Forwards 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 PaidWaterford11 December 1987Application 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 PaidWaterford6 October 1987Requests 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 DrawingsWaterford8 July 1987Responds 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 InoperableWaterford10 September 1986Requests 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 SysWaterford17 January 1985Forwards 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 EnclWaterford15 June 1984Forwards Updated Operator Shift Experience Form,In Response to 840523 Request.Options for Satisfying Shift Operating Experience Requirements at 5% Power Listed.Resumes Encl
W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to AdoptWaterford1 October 2021Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt
W3F1-2021-0035, Technical Requirements Manual UpdateWaterford18 May 2021Technical Requirements Manual Update
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 ComponentsWaterford13 June 2018Supplemental 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
W3F1-2017-0082, Submittal of the Inservice Inspection Plan and Containment Inservice Inspection Plan for the Fourth 10-Year IntervalWaterford4 December 2017Submittal of the Inservice Inspection Plan and Containment Inservice Inspection Plan for the Fourth 10-Year Interval
W3F1-2017-0081, Amendment 1 to License Renewal Application (Laa)Waterford15 November 2017Amendment 1 to License Renewal Application (Laa)
W3F1-2017-0075, Submittal of the Inservice Testing Plan for the Fourth 10-Year IntervalWaterford4 December 2017Submittal of the Inservice Testing Plan for the Fourth 10-Year Interval
W3F1-2017-0046, Relief Requests Associated with the Fourth Inservice Testing IntervalWaterford13 June 2017Relief Requests Associated with the Fourth Inservice Testing Interval
W3F1-2017-0003, Responses to Request for Additional Information Set 10 Regarding the License Renewal ApplicationWaterford19 January 2017Responses 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 ApplicationWaterford7 December 2016Responses 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 ApplicationWaterford7 December 2016Responses 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, 2016Waterford2 June 2016Technical 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 NRCWaterford2 June 2016Technical 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 EventsWaterford21 July 2016Notification 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 YearsWaterford18 June 2015Provides 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 YearsWaterford15 April 2015Response 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 YearsWaterford4 May 2015Response 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. PartWaterford17 June 2015Application 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 YearsWaterford28 August 2014License 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 8-120BWaterford9 September 2013CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B
W3F1-2013-0048, Supplement to NFPA 805 License Amendment Request (LAR)Waterford18 December 2013Supplement 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, 2013Waterford9 July 2013Technical 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 OperationsWaterford22 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 FuelWaterford17 January 2008Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel
W3F1-2007-0037, License Amendment Request NPF-38-271 to Support Next Generation FuelWaterford2 August 2007License 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 06/01/2007Waterford13 June 2007Technical 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 CommentsWaterford22 November 2006Initial 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, 2005Waterford1 December 2005Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005
W3F1-2004-0110, Report of Facility Changes, Tests and Experiments and Commitment ChangesWaterford29 November 2004Report of Facility Changes, Tests and Experiments and Commitment Changes
W3F1-2004-0061, Supplement to Amendment Request NPF-38-249, Extended Power UprateWaterford28 July 2004Supplement to Amendment Request NPF-38-249, Extended Power Uprate
W3F1-2004-0060, Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage DetectionWaterford16 July 2004Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power UprateWaterford14 July 2004Supplement to Amendment Request NPF-38-249, Extended Power Uprate
W3F1-2003-0085, Report of Facility Changes, Tests, and Experiments and Commitment ChangesWaterford19 November 2003Report of Facility Changes, Tests, and Experiments and Commitment Changes
W3F1-2003-0055, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003Waterford24 July 2003TS 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 AttachmentsWaterford23 April 2003Ses 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 IntervalWaterford11 March 2003License 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 PagesWaterford20 December 2002License Amendment Request NPF-38-244, Corrections & Clarifications to Various TS Pages
VR-SECY-22-0046, Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson)27 June 2022VR-SECY-22-0046: Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson)
VR-SECY-21-0072, SRM-SECY-21-0072: Enclosure - Proposed Report to Congress on the Need for the Continuation or Modification of the Price-Anderson Act12 October 2021SRM-SECY-21-0072: Enclosure - Proposed Report to Congress on the Need for the Continuation or Modification of the Price-Anderson Act
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 2020VR-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-06696, Enclosure 6: Proposed Final Safety Analysis Report Changes (Mark-up - for Info Only)Callaway1 December 2021Enclosure 6: Proposed Final Safety Analysis Report Changes (Mark-up - for Info Only)
ULNRC-06636, Enclosure 6 - FSAR Markups (for Information Only)Callaway28 September 2021Enclosure 6 - FSAR Markups (for Information Only)
ULNRC-06445, Revised Emergency Action Level Technical Basis DocumentCallaway9 July 2018Revised Emergency Action Level Technical Basis Document
ULNRC-06433, License Amendment Request for Emergency Action Level (EAL) ChangesCallaway4 September 2018License Amendment Request for Emergency Action Level (EAL) Changes
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 6Callaway31 August 2015Response 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 6Callaway16 July 2015Response 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, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing ProgramCallaway19 December 2014Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program
ULNRC-06166, Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing ProgramCallaway19 December 2014Callaway, 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 TestsCallaway29 August 2013CFR 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 IntervalCallaway23 September 201310 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 ApplicationCallaway15 January 2013License 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 AlternativesCallaway24 September 2012Responses 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)Callaway27 October 2011Union 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-2Callaway29 August 2011Callaway 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)Callaway20 March 2009Proposed 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)Callaway10 July 2006Inoperable Channel 11 of the Loose Parts Detection System (Lpds)
ULNRC-05248, Submittal of Revision 23 to Pump and Valve Inservice Testing ProgramCallaway19 January 2006Submittal of Revision 23 to Pump and Valve Inservice Testing Program
ULNRC-05237, Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)Callaway9 December 2005Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)
ULNRC-05187, Inoperable Channel 3 of the Loose Parts Detection System (Lpds)Callaway11 August 2005Inoperable 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.Callaway8 December 2003License 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-604788, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 3Clinton12 December 2023Fourth Ten-Year Interval Inservice Testing Program Plan Revision 3
U-604703, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 2Clinton14 April 2022Fourth Ten-Year Interval Inservice Testing Program Plan Revision 2
U-604633, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1Clinton23 May 2021Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1
U-604555, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0Clinton13 July 2020Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0
U-604457, Third Ten-Year Interval Inservice Testing Program Plan Revision 9Clinton21 November 2018Third Ten-Year Interval Inservice Testing Program Plan Revision 9
U-604454, Transmittal of Revision 20 to Technical Specification BasesClinton31 December 2018Transmittal of Revision 20 to Technical Specification Bases
U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification BasesClinton22 December 2017Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases
U-604359, Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8Clinton20 July 2017Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8
U-604326, Third Ten-Year Interval Inservice Testing Program Plan Revision 7Clinton8 March 2017Third Ten-Year Interval Inservice Testing Program Plan Revision 7
U-604278, Annual Radioactive Effluent Release Report for 2015Clinton29 April 2016Annual Radioactive Effluent Release Report for 2015
U-604262, Third Ten-Year Interval Inservice Testing Program Plan, Revision 6Clinton15 February 2016Third Ten-Year Interval Inservice Testing Program Plan, Revision 6
U-604257, Transmittal of Revision 17 to the Technical Specification BasesClinton21 December 2015Transmittal of Revision 17 to the Technical Specification Bases
U-604243, Special Report: Inoperable Post Accident Monitoring InstrumentationClinton25 September 2015Special Report: Inoperable Post Accident Monitoring Instrumentation
U-604211, 2014 Annual Radioactive Effluent Release ReportClinton16 April 20152014 Annual Radioactive Effluent Release Report
U-604075, Transmittal of Revision 14 to the Technical Specification BasesClinton4 June 2012Transmittal of Revision 14 to the Technical Specification Bases
U-604018, Annual Radioactive Effluent Release ReportClinton28 April 2011Annual Radioactive Effluent Release Report
U-603987, Transmittal of Revision 13 to Technical Specification BasesClinton1 October 2010Transmittal of Revision 13 to Technical Specification Bases
U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year IntervalClinton12 July 2010Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval
U-603962, Addenda to 2009 Annual Radioactive Effluent Release ReportClinton7 June 2010Addenda to 2009 Annual Radioactive Effluent Release Report
U-603953, 2009 Annual Radioactive Effluent Release ReportClinton28 April 20102009 Annual Radioactive Effluent Release Report
U-603907, Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection PlanClinton31 July 2009Submittal 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 BasesClinton23 May 2008Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases
U-603858, Addenda to 2005 Annual Radioactive Effluent Release ReportClinton27 May 2008Addenda to 2005 Annual Radioactive Effluent Release Report
U-603796, Submittal of Supporting Documentation for December 19, 2006 Regulatory ConferenceClinton12 December 2006Submittal of Supporting Documentation for December 19, 2006 Regulatory Conference
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications BasesClinton16 August 2006Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
U-603708, Transmittal of Revision 9 to the Clinton Power Station Technical Specification BasesClinton3 January 2005Transmittal of Revision 9 to the Clinton Power Station Technical Specification Bases
U-603676, Day Post-Outage Inservice Inspection (ISI) Summary ReportClinton27 May 2004Day Post-Outage Inservice Inspection (ISI) Summary Report
U-603640, Transmittal of Revision 8 to the Technical Specification BasesClinton13 November 2003Transmittal of Revision 8 to the Technical Specification Bases
U-603625, Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004Clinton6 January 2004Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004
U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification BasesClinton27 November 2002Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept IncludedClinton8 October 1999Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
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,EnclClinton20 September 1999Provides 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 SysClinton24 June 1999Forwards 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 FunctionClinton8 March 1999Identifies 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 & 960722Clinton23 November 1998Requests 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)Clinton5 October 1998Proposed 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)Clinton13 August 1998Requests 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 SysClinton23 October 1998Application 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 ConditionsClinton15 June 1998Submits 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 IntervalClinton18 June 1998Forwards 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 950430-970630Clinton20 October 1997Forwards 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 & DrywellClinton16 July 1997Informs 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 LtrClinton2 July 1997Informs 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 CALClinton12 June 1997Informs 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)Clinton12 February 1997Provides 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 ValvesClinton17 September 1996Forwards 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- RefuelingClinton15 August 1996Proposed 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 961013Clinton3 July 1996Provides 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 OperableClinton28 June 1996Application 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 MetClinton19 April 1996Application 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 BClinton1 May 1996Application 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 BarrierClinton22 February 1996Application 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 ModulesClinton14 December 1995Application 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-602519, Forwards Response to NRC 950721 RAI Re IPE Submittal for Facility,Clinton22 November 1995Forwards Response to NRC 950721 RAI Re IPE Submittal for Facility,
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 SysClinton14 December 1995Application 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 YrsClinton17 March 1995Forwards 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 OperableClinton14 February 1995Application 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 RequirementsClinton27 January 1995Application 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 ValveClinton9 September 1994Requests 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-62Clinton15 August 1994Withdraws 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 YearsClinton12 August 1994Application 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-602282, Radioactive Effluent Release Rept, 930101-1231Clinton31 December 1993Radioactive Effluent Release Rept, 930101-1231
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 1992Clinton26 October 1993Application 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-602028, Semiannual Radioactive Effluent Release Rept,Jan-June 1992 Clinton Power StationClinton30 June 1992Semiannual Radioactive Effluent Release Rept,Jan-June 1992 Clinton Power Station
U-601936, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1991, for Clinton Power StationClinton31 December 1991Semiannual Radioactive Effluent Release Rept,Jul-Dec 1991, for Clinton Power Station
U-601871, Proposed Tech Specs Re Reactor Protection Sys Instrumentation,Containment & Reactor Vessel Isolation Control Sys & ECCS Instrumentation Surveillance RequirementsClinton20 September 1991Proposed 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 10CFR50.62Clinton26 April 1991Informs 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 & BClinton18 January 1991Proposed Tech Specs Exempting Measured Type C Leakage Rates for Feedwater Check Valves 1B21-F032A & B
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 ConservativeClinton8 August 1989Responds 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 CompleteClinton14 April 1989Advises 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 PlanClinton27 May 1988Forwards 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 EnclClinton18 April 1988Forwards 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 ControlsClinton5 February 1988Proposed 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 PaidClinton13 January 1988Requests 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-601084, Proposed Tech Specs Re Containment & Pressure Isolation Valve Surveillance RequirementsClinton10 December 1987Proposed Tech Specs Re Containment & Pressure Isolation Valve Surveillance Requirements
U-601018, Semiannual Radioactive Effluent Release Rept,870228-0630Clinton30 June 1987Semiannual 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 10CFR50.44Clinton24 August 1987Provides 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 ImplementedClinton30 June 1987Forwards 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 RequestedClinton20 March 1987Forwards 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 ReptClinton31 December 1986Reactor 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 ValveClinton25 August 1986Responds 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 EnclClinton
05000000		21 July 1986Responds 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 StatusClinton11 June 1986Informs 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 TestingClinton11 March 1986Forwards 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 EnclClinton9 December 1985Requests 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 RevisedClinton16 October 1985Forwards 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 & sClinton2 October 1985Forwards 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 41Clinton24 July 1985Forwards 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 ImplementedClinton11 June 1985Forwards 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 RequestedClinton12 June 1985Forwards 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 RequirementsClinton12 June 1985Forwards 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 BComanche Peak12 March 1996Application 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-6844, Informs That Field Verification Method (Fvm) for Unit 2 Sys Will Be Issued to Support Completion of Walkdowns,Generation of DCAs & Installation of Cable Grips by 881231,in Response to Notice of Violation.Draft FSAR EnclComanche Peak12 October 1987Informs That Field Verification Method (Fvm) for Unit 2 Sys Will Be Issued to Support Completion of Walkdowns,Generation of DCAs & Installation of Cable Grips by 881231,in Response to Notice of Violation.Draft FSAR Encl
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 ReviewedComanche Peak24 April 1987Forwards 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 DiscussedComanche Peak17 February 1986Forwards 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 ReviewComanche Peak29 May 1984Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review
TSTF-580Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling
TSTF-514Revise 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 1Technical Specifications Task Force23 June 2021TSTF 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 CoolingTechnical Specifications Task Force26 January 2021Transmittal 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 Force5 November 2019TSTF 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 RequirementsTechnical Specifications Task Force
99902042		16 January 2020TSTF 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 PositionTechnical Specifications Task Force28 August 2019Transmittal 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 RequirementsTechnical Specifications Task Force
99902042		13 December 2019Technical 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 Force3 July 2019Draft 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 PositionTechnical Specifications Task Force18 June 2019Transmittal 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 Force19 January 2018Transmittal 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 3.6.3.2Technical Specifications Task Force19 December 2017Technical 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 Force2 August 2017TSTF 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 2Technical Specifications Task Force2 November 2016TSTF 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 Force3 October 2016Technical 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 Force12 May 2016Technical 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 4Technical Specifications Task Force29 February 2016Technical 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-15-11, TSTF Comments on Draft Model Safety Evaluation of Traveler TSTF-545, TS Inservice Testing Program & Clarify SR Usage Rule Application to Section 5.5 Testing and Transmittal of TSTF-545, Revision 3Technical Specifications Task Force21 October 2015TSTF Comments on Draft Model Safety Evaluation of Traveler TSTF-545, TS Inservice Testing Program & Clarify SR Usage Rule Application to Section 5.5 Testing and Transmittal of TSTF-545, Revision 3
TSTF-15-08, Technical Specifications Task Force - Transmittal of TSTF-529, Revision 3, Clarify Use and Application Rules.Technical Specifications Task Force14 September 2015Technical 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 Force3 September 2015Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements.
TSTF-15-03, Response to NRC Comments Regarding TSTF-545, Revision 1, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing and Submittal of TSTF-545, Revision 2Technical Specifications Task Force3 April 2015Response to NRC Comments Regarding TSTF-545, Revision 1, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing and Submittal of TSTF-545, Revision 2
TSTF-14-18, Transmittal of TSTF-551, Revision 0, Address Transient Secondary Containment ConditionsTechnical Specifications Task Force30 October 2014Transmittal 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 3Technical Specifications Task Force31 March 2015Technical 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-14-05, Transmittal of TSTF-545, Revision 1, TS Inservice Testing Program Removal.Technical Specifications Task Force4 March 2014Transmittal of TSTF-545, Revision 1, TS Inservice Testing Program Removal.
TSTF-14-02, Transmittal of TSTF-529, Revision 2, Clarify Use and Application Rules.Technical Specifications Task Force14 January 2014Transmittal of TSTF-529, Revision 2, Clarify Use and Application Rules.
TSTF-13-15, Transmittal of TSTF-542, Revision 0, Reactor Pressure Vessel Walter Inventory ControlTechnical Specifications Task Force31 December 2013Transmittal of TSTF-542, Revision 0, Reactor Pressure Vessel Walter Inventory Control
TSTF-13-12, Transmittal of TSTF-541, Revision 0, Add Exceptions to Surveillance Requirements When the Safety Function Is Being PerformedTechnical Specifications Task Force10 September 2013Transmittal of TSTF-541, Revision 0, Add Exceptions to Surveillance Requirements When the Safety Function Is Being Performed
TSTF-13-09, Transmittal of TSTF-545, Revision 0, TS Inservice Testing (IST) Program Removal.Technical Specifications Task Force4 November 2013Transmittal of TSTF-545, Revision 0, TS Inservice Testing (IST) Program Removal.
TSTF-13-03, Transmittal of TSTF-529, Revision 1, Clarify Use and Application RulesTechnical Specifications Task Force28 February 2013Transmittal of TSTF-529, Revision 1, Clarify Use and Application Rules
TSTF-13-02, Submittal of TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.Technical Specifications Task Force21 February 2013Submittal of TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.
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 Force30 August 2012Response 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 Force16 May 2012Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6)
TSTF-12-08, Transmittal of TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas AccumulationTechnical Specifications Task Force29 March 2012Transmittal of TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation
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 Force27 March 2012Transmittal 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, Writer'S Guide for Plant-Specific Improved Technical Specifications.Technical Specifications Task Force14 February 2012Transmittal of Report TSTF-GG-05-01, Revision 1, Writer'S Guide for Plant-Specific Improved Technical Specifications.
TSTF-12-04, Transmittal of TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373Technical Specifications Task Force27 March 2012Transmittal 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 Force22 February 2012Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046).
TSTF-11-15, Transmittal of TSTF-529, Revision 0, Clarify Use and Application RulesTechnical Specifications Task Force21 September 2011Transmittal of TSTF-529, Revision 0, Clarify Use and Application Rules
TSTF-11-13, Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition.Technical Specifications Task Force19 September 2011Transmittal 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 87-09Technical Specifications Task Force16 September 2011Transmittal 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 Force24 November 2010Submittal 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 2Technical Specifications Task Force6 August 2010Submittal 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 Force12 May 2010Comment (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-10-07, Transmittal of TSTF-493, Revision 4, Errata, Clarify Application of Setpoint Methodology for LSSS Functions.Technical Specifications Task Force23 April 2010Transmittal of TSTF-493, Revision 4, Errata, Clarify Application of Setpoint Methodology for LSSS Functions.
TSTF-10-05, Transmittal of TSTF-523, Revision 0, Generic Letter 2008-01, Managing Gas AccumulationTechnical Specifications Task Force29 June 2010Transmittal of TSTF-523, Revision 0, Generic Letter 2008-01, Managing Gas Accumulation
TSTF-10-04, Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.Technical Specifications Task Force30 March 2010Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.
TSTF-09-26, Comment (2) of Kenneth J. Schrader, John Messina, Thomas W. Raidy and Wendy E. Croft on Behalf of Technical Specifications Task Force on Proposed Model Safety Evaluation for Plant-Specific Adoption of Traveler-493, Rev. 4, Clarify ApplicaTechnical Specifications Task Force25 November 2009Comment (2) of Kenneth J. Schrader, John Messina, Thomas W. Raidy and Wendy E. Croft on Behalf of Technical Specifications Task Force on Proposed Model Safety Evaluation for Plant-Specific Adoption of Traveler-493, Rev. 4, Clarify Applicati
TSTF-09-25, Transmittal of Revised Risk-Informed End State Travelers: TSTF-422, TSTF-423, TSTF-431, and TSTF-432Technical Specifications Task Force22 December 2009Transmittal of Revised Risk-Informed End State Travelers: TSTF-422, TSTF-423, TSTF-431, and TSTF-432
TSTF-09-20, Transmittal of TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360Technical Specifications Task Force22 September 2009Transmittal of TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
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 Force8 September 2009Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.
TSTF-09-10, Transmittal of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Sections 3.1.1 - 3.7.5Technical Specifications Task Force18 March 2009Transmittal of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Sections 3.1.1 - 3.7.5
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 InstrumentationTechnical Specifications Task Force18 February 2009Transmittal 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 Force20 January 2009Transmittal 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 Force10 November 2008Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.
TSTF-08-19, Transmittal of TSTF-500, Revision 1, DC Electrical Rewrite - Update to TSTF-360.Technical Specifications Task Force5 November 2008Transmittal of TSTF-500, Revision 1, DC Electrical Rewrite - Update to TSTF-360.
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 Force14 October 2008Transmittal 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 StandardizationTechnical Specifications Task Force3 July 2008Transmittal 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 Force4 March 2008TSTF-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 Force19 February 2008TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
TSTF-08-01, Response to NRC June 25, 2007 Request for Additional Information Regarding TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions.Technical Specifications Task Force18 January 2008Response to NRC June 25, 2007 Request for Additional Information Regarding TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions.
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, 2007Technical Specifications Task Force10 October 2007Response 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-07-26, TSTF-500, Revision 0, DC Electrical Rewrite - Update to TSTF-360.Technical Specifications Task Force31 August 2007TSTF-500, Revision 0, DC Electrical Rewrite - Update to TSTF-360.
TSTF-07-22, TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.Technical Specifications Task Force10 July 2007TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.
TSTF-07-14, TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions.Technical Specifications Task Force16 April 2007TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions.
TSTF-07-11, Revision to Implementation Guidance for TSTF-423, Technical Specifications End States, NEDC-32988-A.Technical Specifications Task Force9 March 2007Revision 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 Force21 February 2007TSTF-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, 2006Technical Specifications Task Force7 February 2007Response 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 Force11 January 2007TSTF-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 Force20 December 2006TSTF-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 2006TSTF-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, 20065 June 2006Response 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 2005TSTF-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 2005TSTF-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 I25 July 2005Technical 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 2005TSTF-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 2005Submittal 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 2005TSTF-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 2005TSTF-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 2004TSTF-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 2005Submittal 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 Subsystems30 August 2004TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems
TSTF-04-08, TSTF-425, Revision 0, Relocate Surveillance Frequencies to Licensee Control.31 August 2004TSTF-425, Revision 0, Relocate Surveillance Frequencies to Licensee Control.
TSTF-03-02, Traveler - August 12, 2003 Transmits TSTF-423, Technical Specifications End States, NEDC-32988-A.12 August 2003Traveler - August 12, 2003 Transmits TSTF-423, Technical Specifications End States, NEDC-32988-A.
TMI-17-035, Submittal of Changes to Technical Specifications BasesThree Mile Island13 April 2017Submittal of Changes to Technical Specifications Bases
TMI-15-049, Submittal of Changes to Technical Specifications BasesThree Mile Island14 April 2015Submittal of Changes to Technical Specifications Bases
TMI-15-048, Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing ProgramThree Mile Island13 April 2015Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program
TMI-15-034, Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating StationOyster Creek2 March 2015Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating Station
TMI-14-069, Submittal of the Fifth Ten-Year Interval Inservice Testing ProgramThree Mile Island16 May 2014Submittal of the Fifth Ten-Year Interval Inservice Testing Program
TMI-14-055, Submittal of Changes to Technical Specifications BasesThree Mile Island10 April 2014Submittal of Changes to Technical Specifications Bases
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 EndOyster Creek30 May 2014Attachment 8: Discussion of Revision to the Radiological Emergency Plan Annex for Oyster Creek Nuclear Generating Station, Page Ocgs 3-76 Through End
TMI-13-105, Update 10 of the Post-Defueling Monitored Storage Safety Analysis ReportThree Mile Island23 August 2013Update 10 of the Post-Defueling Monitored Storage Safety Analysis Report
TMI-13-064, Submittal of Changes to Technical Specifications BasesThree Mile Island10 April 2013Submittal of Changes to Technical Specifications Bases
TMI-13-050, Re-issue of Update 9 of the Post-Defueling Monitored Storage Safety Analysis ReportThree Mile Island22 March 2013Re-issue of Update 9 of the Post-Defueling Monitored Storage Safety Analysis Report
TMI-12-169, Request for Amendment to Eliminate Certain Technical Specification Reporting RequirementsThree Mile Island4 February 2013Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements
TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) IntervalThree Mile Island7 November 2012Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval
TMI-12-068, Submittal of Changes to Technical Specifications BasesThree Mile Island12 April 2012Submittal of Changes to Technical Specifications Bases
TMI-11-064, Submittal of Changes to Technical Specifications BasesThree Mile Island15 April 2011Submittal of Changes to Technical Specifications Bases
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 ControlledThree Mile Island27 September 2010Response 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-10-046, Submittal of Changes to Technical Specifications BasesThree Mile Island22 April 2010Submittal of Changes to Technical Specifications Bases
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 CapabilityThree Mile Island15 March 2010Response 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)Three Mile Island24 March 2010Application 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, 2014Three Mile Island14 August 2009Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014
TMI-09-052, Submittal of Changes to Technical Specifications BasesThree Mile Island17 April 2009Submittal of Changes to Technical Specifications Bases
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 19-0020, Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation ManualDresden19 April 2019Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation Manual
SVPLTR 16-0017, Submittal of Post Accident Monitoring Report InstrumentationDresden8 April 2016Submittal of Post Accident Monitoring Report Instrumentation
SVPLTR 13-0020, Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002Dresden6 June 2013Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002
SVPLTR 13-0015, Offsite Dose Calculation Manual CY-DR-170-301, Rev. 12Dresden31 March 2012Offsite Dose Calculation Manual CY-DR-170-301, Rev. 12
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 EventsDresden31 January 2013Response 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 12-0022, Offsite Dose Calculation ManualDresden30 April 2011Offsite Dose Calculation Manual
SVPLTR 11-0018, Offsite Dose Calculation ManualDresden31 October 2010Offsite Dose Calculation Manual
SVPLTR 10-0037, 2011 Dresden Nuclear Power Station Initial Examination Outline SubmittalDresden23 September 20102011 Dresden Nuclear Power Station Initial Examination Outline Submittal
SVPLTR 10-0022, Revised Commitment for the Containment Leak Reduction & Control Program for Gas SystemsDresden15 May 2010Revised 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 BellowsDresden2 October 2009Revised 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 3Dresden8 April 2005March 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 BlockageQuad Cities22 September 1999Confirms 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 & SafetyQuad Cities13 August 1999Forwards 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 LeakageQuad Cities30 June 1999Forwards 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, PcivsQuad Cities16 July 1999Application 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. withQuad Cities30 April 1999Summary 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 InoperableQuad Cities30 March 1999Application 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).WithQuad Cities31 January 1999Quarterly 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,Q1R15Quad Cities14 January 1999Provides 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 ListedQuad Cities18 December 1998Confirms 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.WithQuad Cities31 October 1998Summary 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 ValveQuad Cities9 November 1998Forwards 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).WithQuad Cities15 July 1998Summary 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 CompleteQuad Cities13 November 1998Provides 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.6Quad Cities31 August 1998Application 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-98-252, 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.CQuad Cities31 July 1998Application 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 & 2Quad Cities30 June 1998Monthly 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 & 2Quad Cities31 May 1998Monthly 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 971015Quad Cities21 May 1998Forwards 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 & 2Quad Cities30 April 1998Monthly 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 & 2Quad Cities31 March 1998Monthly 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 AnalysisQuad Cities31 March 1998Requests 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 & ExperiementsQuad Cities20 March 1998Forwards 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 TimesQuad Cities13 March 1998Responds 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 & 2Quad Cities28 February 1998Monthly 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 & 2Quad Cities31 January 1998Monthly 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 EnclQuad Cities21 November 1997Submits 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 EnclBraidwood15 March 1994Documents 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-22-057, Response to Apparent Violation EA-22-062 and Preliminary White Finding Regarding the Failure of One Electromatic Relief ValveQuad Cities15 September 2022Response to Apparent Violation EA-22-062 and Preliminary White Finding Regarding the Failure of One Electromatic Relief Valve
SVP-16-001, 2016 Quad Cities Nuclear Power Station Initial License Examination Forms ES-D-1Quad Cities2 May 20162016 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 ReportQuad Cities26 November 2013Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report
SVP-11-021, Clarification of License Renewal Commitment Regarding Bellows TestingQuad Cities7 April 2011Clarification of License Renewal Commitment Regarding Bellows Testing
SVP-03-118, Transmittal of Lost Parts Analysis and Associated Operability EvaluationQuad Cities28 November 2003Transmittal 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 ProgramQuad Cities11 September 2003Submittal 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 PlanQuad Cities7 February 2003Fourth Interval Inservice Inspection Program Plan
SVP-03-008, Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program PlanQuad Cities17 January 2003Quad-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 & 3/4.6.1.3South Texas1 May 1996Application 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 JSouth Texas16 March 1995Application 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-4066, Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air LocksSouth Texas4 August 1992Proposed 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 AmendSouth Texas25 June 1987Forwards 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 RequestSouth Texas17 June 1987Forwards 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 PagesSouth Texas5 June 1987Forwards 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 ReptSouth Texas31 March 1987Reactor 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 EnclSouth Texas29 May 1987Responds 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 & BasesSouth Texas20 April 1987Forwards Changes & Justifications for Changes in Proof & Review Tech Specs in Listed Areas,Including Definitions, Setpoints & Bases
ST-HL-AE-1984, Forwards,For Info & Use,Comments & Justifications for Changes Proposed in Proof & Review Tech SpecsSouth Texas16 March 1987Forwards,For Info & Use,Comments & Justifications for Changes Proposed in Proof & Review Tech Specs
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 AmendSouth Texas9 March 1987Forwards 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 EnclSouth Texas13 March 1987Requests 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 ScheduleSouth Texas28 August 1986Forwards 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-1704, Forwards Amended marked-up Pages to 860115 Draft Rev 5 to STS (NUREG-0452).Amends Include Editorial Changes,Revs to Reflect Plant Current Design & Additions to Meet Conditions Identified in SERSouth Texas29 July 1986Forwards Amended marked-up Pages to 860115 Draft Rev 5 to STS (NUREG-0452).Amends Include Editorial Changes,Revs to Reflect Plant Current Design & Additions to Meet Conditions Identified in SER
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 AmendSouth Texas22 October 1985Forwards 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 EnclSouth Texas14 October 1985Forwards 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-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 PlanShoreham4 January 1993Responds 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 1991Shoreham30 March 1992Forwards 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 ShorehamShoreham22 January 1992Requests 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 1990Shoreham31 December 199010CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990
SNRC-1583, Forwards Supplemental Info Re Temp Profile Inside Primary Containment Used for Environ QualificationShoreham12 April 1989Forwards 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 ProfileShoreham4 April 1989Provides 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 StartupShoreham31 March 1989Submits 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 CapacityShoreham14 April 1989Responds 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 CodesShoreham21 February 1989Forwards 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 EnclShoreham14 March 1989Forwards 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 QuestionsShoreham20 May 1988Forwards 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 WaterShoreham18 April 1988Responds 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 AssessmentShoreham31 December 1987Semiannual 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 880408Shoreham2 March 1988Forwards 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 EnclShoreham4 December 1987Forwards 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 RequirementsShoreham30 September 1987Responds 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 DiscussedShoreham14 September 1987Responds 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 SubmittalShoreham28 August 1987Requests 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 RequestShoreham4 August 1987Forwards 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 & 50.59Shoreham31 December 1985Rept 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 EnclShoreham30 March 1987Proposes 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)Shoreham2 December 1986Forwards 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 PlanShoreham30 May 1986Rev 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 ExemptionsShoreham27 March 1986Requests 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 DescribedShoreham18 March 1986Forwards 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 OutageShoreham12 November 1985Forwards 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 CapabilityShoreham23 October 1985Forwards 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 EnclShoreham6 May 1985Informs 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 FacilityShoreham5 April 1985Forwards 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 OperatorsShoreham4 April 1985Forwards 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 841208Shoreham28 December 1984Deficiency 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-84-8Shoreham9 November 1984Forwards 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 TelconShoreham19 November 1984Forwards 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 1.8Shoreham12 November 1984Forwards 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 34Shoreham22 October 1984Forwards 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 PDRShoreham25 September 1984Amend 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 InertingShoreham18 September 1984Submits 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 FSARShoreham5 September 1984Forwards 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 OrganizationShoreham8 May 1984Forwards 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 OLShoreham21 March 1984Forwards 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 83-24Shoreham16 February 1984Provides 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 RevisedShoreham5 March 1984Clarifies 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, 202328 August 2023SECY-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 202127 June 2022SRM-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 201830 April 2019VR-SECY-19-0024: Report to Congress on Abnormal Occurrences: Fiscal Year 2018
SECY-11-0124, Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 317 July 2013Station 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 Fire22 December 2004SECY-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 PlanSeabrook4 January 2022Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan
SBK-L-19129, Submittal of Changes to the Seabrook Station Technical Specification BasesSeabrook31 December 2019Submittal 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 AccumulatorsSeabrook4 June 2019License 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 BasesSeabrook18 December 2018Submittal 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 ProgramSeabrook28 February 20180 - 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, Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J ProgramSeabrook28 February 2018Supplement 59 - 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 SpecificationsSeabrook1 December 2017License 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 ProgramSeabrook23 December 2016License 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 FrequencySeabrook27 October 2016Response 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 ReactorsSeabrook27 October 2016Response 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 ReactionSeabrook23 February 2016Response 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 BasesSeabrook5 January 2016Submittal 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 ProgramSeabrook11 December 2014Supplement 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 ProgramSeabrook15 May 2014Nextera 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.Seabrook24 June 2014License 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 BasesSeabrook12 December 2013Submittal of Changes to the Seabrook Station Technical Specification Bases
SBK-L-13147, Administrative Changes to License Amendment Requests in NRC ReviewSeabrook31 July 2013Administrative Changes to License Amendment Requests in NRC Review
SBK-L-13071, License Amendment Request 13-03Seabrook28 May 2013License Amendment Request 13-03
SBK-L-13028, License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical SpecificationsSeabrook1 March 2013License 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 SystemSeabrook31 January 2013Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System
SBK-L-12185, Supplement 3 to Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal ApplicationSeabrook13 September 2012Supplement 3 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 SystemSeabrook2 July 2012Response 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 SystemSeabrook15 March 2012Response 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, Supplement 2 to Severe Accident Mitigation Alternatives Analysis, License Renewal ApplicationSeabrook19 March 2012Supplement 2 to Severe Accident Mitigation Alternatives Analysis, License Renewal Application
SBK-L-12052, Submittal of Changes to Technical Specification BasesSeabrook16 February 2012Submittal of Changes to Technical Specification Bases
SBK-L-11233, Response to Request for Additional Information - Set 17Seabrook17 November 2011Response 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 SetpointsSeabrook17 November 2011License 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 SystemSeabrook16 September 2011Response 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 IntegritySeabrook11 July 2011Submittal 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 ProgramSeabrook22 June 2011Submittal 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 InstrumentationSeabrook21 April 2011License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation
SBK-L-11015, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 8Seabrook3 February 2011Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 8
SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal ApplicationSeabrook13 January 2011Response to Request for Additional Information, NextEra Energy License Renewal Application
SBK-L-10236, Submittal of Changes to the Technical Specification BasesSeabrook30 December 2010Submittal of Changes to the Technical Specification Bases
SBK-L-10204, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management ProgramsSeabrook17 December 2010Response 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.Seabrook24 August 2010Response 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 10-03Seabrook28 June 2010License Amendment Request 10-03
SBK-L-10074, License Amendment Request 10-02Seabrook14 May 2010License Amendment Request 10-02
SBK-L-08216, Submittal of Changes to Technical Specification BasesSeabrook16 December 2008Submittal 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 ChangesSeabrook7 August 2007Response 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 ChangeSeabrook7 June 2006Emergency 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.Seabrook28 April 2006Application 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.Seabrook7 August 2006License 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.Seabrook29 September 2005License 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 BasesSeabrook2 December 2004Submittal 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 InterlockSeabrook10 January 2005License 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 BasesSeabrook2 September 2004Submittal of Changes to the Plant Technical Specification Bases
Regulatory Guide 7.931 January 1980Standard Format & Content of Part 71 Applications for Approval of Packaging of Type B,Large Quantity & Fissile Radioactive Material
Regulatory Guide 1.9630 June 1976Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants
Regulatory Guide 1.826 September 2005Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident
Regulatory Guide 1.7731 May 1974Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors
Regulatory Guide 1.730 September 1976Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident
Regulatory Guide 1.6831 January 1977Regulatory Guide 1.68.1, Revision 1, Preoperational and Initial Startup Testing of Feedwater and Condensate System for Boiling Water Reactor Power Plants
Regulatory Guide 1.5231 July 1976Design, Testing, and Maintenance Criteria for Engineered-safety-feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants
Regulatory Guide 1.330 June 1974Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors
Regulatory Guide 1.23227 February 2018Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors
Regulatory Guide 1.2063 October 2018
Regulatory Guide 1.19531 May 2003Methods and Assumptions for Evaluating Radiological Consequences of Design-Basis Accidents at Light-Water Nuclear Power Reactors
Regulatory Guide 1.1941 June 2003Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants
Regulatory Guide 1.18928 February 2018Rev. 3, Fire Protection for Nuclear Power Plants
Regulatory Guide 1.1831 July 2000Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
Regulatory Guide 1.15828 February 1989(Task Ee 006-5) Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants
Regulatory Guide 1.14131 July 2010Containment Isolation Provisions for Fluid Systems
Regulatory Guide 1.14030 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 1.12030 June 1976Fire Protection Guidelines for Nuclear Power Plants
Regulatory Guide 1.11730 April 1978Rev 1,Tornado Design Classification
Regulatory Guide 1.1131 March 2010Instrument Lines Penetrating the Primary Reactor Containment
RS-23-121, Sixth Ten-Year Interval Inservice Testing ProgramDresden30 November 2023Sixth Ten-Year Interval Inservice Testing Program
RS-23-089, Sixth Ten-Year Interval Inservice Testing ProgramQuad Cities5 September 2023Sixth Ten-Year Interval Inservice Testing Program
RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation InstrumentationClinton21 August 2023Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
RS-23-059, 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 4bQuad Cities8 June 2023License 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
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 FlangesQuad Cities24 April 2023Submittal 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 TestingClinton13 January 2023Application to Adopt TSTF-332, ECCS Response Time Testing
RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing IntervalDresden1 November 2022Submittal 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 PenetrationDresden
Nine Mile Point
Clinton
Quad Cities
LaSalle		3 October 2022Nine 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 AnalysisLaSalle12 January 2023Application 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 StationQuad Cities25 May 2022Constellation 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 ValvesClinton24 May 2022Request 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 CoolingClinton24 May 2022Request 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 RevisionQuad Cities21 April 2022Constellation 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 AirlockClinton7 April 2022Request 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 IntervalQuad Cities17 February 2022Submittal 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 RequirementsCalvert Cliffs
Dresden
Peach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
Ginna
Clinton
Quad Cities
FitzPatrick
LaSalle		4 January 2022Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-107, 5 to Technical Requirements ManualQuad Cities21 October 20215 to Technical Requirements Manual
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 DieselDresden
Clinton
Quad Cities
LaSalle		19 August 2021Response 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-21-066, Amendment 23 to Fire Protection Report, Volume 3, Cross Reference from Old to New Configurations of FppdpDresden21 June 2021Amendment 23 to Fire Protection Report, Volume 3, Cross Reference from Old to New Configurations of Fppdp
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage RequirementsPeach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
Ginna
Clinton
Quad Cities
FitzPatrick
LaSalle		30 June 2021Application 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 4bLaSalle31 March 2021Response 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 ConditionDresden16 March 2021Response 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 FrequencyClinton24 February 2021License 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 MethodologyLaSalle10 February 2021Application 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 9.5-1Byron17 December 2020Amendment 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 50.69Clinton24 November 2020Response 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)LaSalle29 October 2020Response 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-20-132, License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ConditionDresden29 October 2020License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-20-126, EP-AA-111-F-02, Rev. 1, Braidwood PAR FlowchartBraidwood13 October 2020EP-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) EnhancementsDresden
Clinton
Quad Cities
LaSalle		18 November 2020Application 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-568Dresden
Peach Bottom
Nine Mile Point
Limerick
Quad Cities
LaSalle		3 September 2020Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568
RS-20-052, Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Extended Completed Times-RITSTF Initiative 4bClinton30 April 2020Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Extended Completed Times-RITSTF Initiative 4b
RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3Quad Cities1 April 2020Emergency 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 SurveillanceDresden6 May 2020Response 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 ProcessDresden
Peach Bottom
Nine Mile Point
Limerick
Quad Cities
LaSalle		30 April 2020License 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-20-029, Submittal of Revision 24 to Updated Final Safety Analysis Report and Revision 9 to Fire Protection ReportLaSalle13 April 2020Submittal of Revision 24 to Updated Final Safety Analysis Report and Revision 9 to Fire Protection Report
RS-20-028, 1 to Updated Safety Analysis Report, CPS TsbClinton31 March 20201 to Updated Safety Analysis Report, CPS Tsb
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 2020Relief 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 IssuesByron
Braidwood
Ginna		6 February 2020Application 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 ChangerClinton14 January 2020Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer
RS-19-101, 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...Dresden30 October 2019Seismic 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...
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