Primary containment

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

	Site	Start date	Reporting criterion	Title
ZS-2013-0195, Fire Protection Report, Amendment 13	Zion	31 July 2013		Fire Protection Report, Amendment 13
ZS-2012-0268, Quality Assurance Program Application to Transportation Activities Pursuant to 10 CFR 71.101(f) and Zionsolutions Quality Assurance Project Plan (Qapp) Periodic Update Submittal	Zion 07100956	12 July 2012		Quality Assurance Program Application to Transportation Activities Pursuant to 10 CFR 71.101(f) and Zionsolutions Quality Assurance Project Plan (Qapp) Periodic Update Submittal
ZS-2011-0166, Quality Assurance Program for the Independent Spent Fuel Storage Installation	Zion 07100950	23 February 2011		Quality Assurance Program for the Independent Spent Fuel Storage Installation
ZS-2010-0199, Submittal of Quality Assurance Project Plan, ZS-QA-10	Zion	27 July 2010		Submittal 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 Frequencies	Wolf Creek	20 April 2020		License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
WO 17-0013, Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level Scheme	Wolf Creek	16 March 2017		Response 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 Reactors	Wolf Creek	30 September 2016		Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves	Wolf Creek	23 July 2004		Revision 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 Creek	17 October 2003		Revision to Technical Specification (TS) 5.5.6, Containment Tendon Surveillance Program, and TS 5.5.16, Containment Leakage Rate Testing Program.
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions	Wolf Creek	31 May 2016		Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls	Wolf Creek	31 May 2016		Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features	Wolf Creek	31 May 2016		Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements	Wolf Creek	31 May 2016		Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant	Wolf Creek	31 May 2016		Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant
WM 16-0008, Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, Calculation No. XX-E-013, Rev 4, Post-Fire Safe Shutdown Analysis	Wolf Creek	31 May 2016		Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, Calculation No. XX-E-013, Rev 4, Post-Fire Safe Shutdown Analysis
WM 10-0017, Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical Cable	Wolf Creek	2 June 2010		Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical Cable
WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)	Watts Bar	29 October 2020		Amendment 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 36	Waterford	10 May 1988		Forwards 1987 Annual Fire Protection Rept Per Condition 2.C.9.c of License NPF-38.Rept Describes Changes to Approved Fire Protection Program as Discussed in FSAR Through Amend 36
W3P87-2524, Application for Amend to License NPF-38,implementing Change in Annulus Fire Detection Sys by Changing Number of Fire Detection Instruments & Zones of Detection Providing Indication of Fire in Annulus.Fee Paid	Waterford	11 December 1987		Application for Amend to License NPF-38,implementing Change in Annulus Fire Detection Sys by Changing Number of Fire Detection Instruments & Zones of Detection Providing Indication of Fire in Annulus.Fee Paid
W3P87-1792, Requests Concurrence to Revise Containment Integrated Leak Rate Test Duration from 24 H to Period Consistent W/Topical Rept BN-TOP-1, Testing Criteria for Integrated Leak Rate Testing of Primary Containment Structures .... Fee Paid	Waterford	6 October 1987		Requests Concurrence to Revise Containment Integrated Leak Rate Test Duration from 24 H to Period Consistent W/Topical Rept BN-TOP-1, Testing Criteria for Integrated Leak Rate Testing of Primary Containment Structures .... Fee Paid
W3P87-1630, Responds to Questions Re Fault Trees Associated W/Control Sys Single Failure Study.W/Two Oversize Drawings	Waterford	8 July 1987		Responds to Questions Re Fault Trees Associated W/Control Sys Single Failure Study.W/Two Oversize Drawings
W3P86-3303, Requests Relief from Requirements of Tech Spec 3.3.3.8 Re Performance of Fire Watch for Annulus Area Every 8 H When Certain Level of Fire Detection Instrumentation Considered Inoperable	Waterford	10 September 1986		Requests Relief from Requirements of Tech Spec 3.3.3.8 Re Performance of Fire Watch for Annulus Area Every 8 H When Certain Level of Fire Detection Instrumentation Considered Inoperable
W3P85-0130, Forwards Rept on License Condition 16 Evaluating Potential Adverse Effects of Failure of Containment Coatings on post-accident Fluid Sys	Waterford	17 January 1985		Forwards Rept on License Condition 16 Evaluating Potential Adverse Effects of Failure of Containment Coatings on post-accident Fluid Sys
W3P84-1695, Forwards Updated Operator Shift Experience Form,In Response to 840523 Request.Options for Satisfying Shift Operating Experience Requirements at 5% Power Listed.Resumes Encl	Waterford	15 June 1984		Forwards Updated Operator Shift Experience Form,In Response to 840523 Request.Options for Satisfying Shift Operating Experience Requirements at 5% Power Listed.Resumes Encl
W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program	Waterford	8 May 2024		Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program
W3F1-2021-0035, Technical Requirements Manual Update	Waterford	18 May 2021		Technical 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 Components	Waterford	13 June 2018		Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components
W3F1-2017-0082, Submittal of the Inservice Inspection Plan and Containment Inservice Inspection Plan for the Fourth 10-Year Interval	Waterford	4 December 2017		Submittal 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)	Waterford	15 November 2017		Amendment 1 to License Renewal Application (Laa)
W3F1-2017-0075, Submittal of the Inservice Testing Plan for the Fourth 10-Year Interval	Waterford	4 December 2017		Submittal of the Inservice Testing Plan for the Fourth 10-Year Interval
W3F1-2017-0046, Relief Requests Associated with the Fourth Inservice Testing Interval	Waterford	13 June 2017		Relief Requests Associated with the Fourth Inservice Testing Interval
W3F1-2017-0003, Responses to Request for Additional Information Set 10 Regarding the License Renewal Application	Waterford	19 January 2017		Responses to Request for Additional Information Set 10 Regarding the License Renewal Application
W3F1-2016-0075, Responses to Request for Additional Information Set 6 Regarding the License Renewal Application	Waterford	7 December 2016		Responses to Request for Additional Information Set 6 Regarding the License Renewal Application
W3F1-2016-0074, Responses to Request for Additional Information Set 5 Regarding the License Renewal Application	Waterford	7 December 2016		Responses to Request for Additional Information Set 5 Regarding the License Renewal Application
W3F1-2016-0041, Technical Specification Index and Bases Update to NRC for Period November 4, 2014 Through May 31, 2016	Waterford	2 June 2016		Technical Specification Index and Bases Update to NRC for Period November 4, 2014 Through May 31, 2016
W3F1-2016-0040, Technical Requirements Manual Update to the NRC	Waterford	2 June 2016		Technical Requirements Manual Update to the NRC
W3F1-2016-0031, Notification of Full Compliance with EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events	Waterford	21 July 2016		Notification of Full Compliance with EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events
W3F1-2015-0047, Provides Additional Information to Support Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Frequency to 15 Years	Waterford	18 June 2015		Provides Additional Information to Support Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Frequency to 15 Years
W3F1-2015-0028, Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years	Waterford	15 April 2015		Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years
W3F1-2015-0021, Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years	Waterford	4 May 2015		Response to Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years
W3F1-2015-0006, Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part	Waterford	17 June 2015		Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 3 of 5
W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years	Waterford	28 August 2014		License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years
W3F1-2013-0054, CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B	Waterford	9 September 2013		CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B
W3F1-2013-0048, Supplement to NFPA 805 License Amendment Request (LAR)	Waterford	18 December 2013		Supplement to NFPA 805 License Amendment Request (LAR)
W3F1-2013-0040, Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013	Waterford	9 July 2013		Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013
W3F1-2010-0010, . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations	Waterford	22 February 2010		. Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations
W3F1-2008-0004, Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel	Waterford	17 January 2008		Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel
W3F1-2007-0037, License Amendment Request NPF-38-271 to Support Next Generation Fuel	Waterford	2 August 2007		License Amendment Request NPF-38-271 to Support Next Generation Fuel
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007	Waterford	13 June 2007		Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
W3F1-2006-0065, Initial Exam - 11/2006 - Licensee Post Exam Comments	Waterford	22 November 2006		Initial Exam - 11/2006 - Licensee Post Exam Comments
W3F1-2005-0062, Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005	Waterford	1 December 2005		Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005
W3F1-2004-0110, Report of Facility Changes, Tests and Experiments and Commitment Changes	Waterford	29 November 2004		Report of Facility Changes, Tests and Experiments and Commitment Changes
W3F1-2004-0061, Supplement to Amendment Request NPF-38-249, Extended Power Uprate	Waterford	28 July 2004		Supplement to Amendment Request NPF-38-249, Extended Power Uprate
W3F1-2004-0060, Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection	Waterford	16 July 2004		Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate	Waterford	14 July 2004		Supplement to Amendment Request NPF-38-249, Extended Power Uprate
W3F1-2003-0085, Report of Facility Changes, Tests, and Experiments and Commitment Changes	Waterford	19 November 2003		Report 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, 2003	Waterford	24 July 2003		TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003
W3F1-2003-0031, Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments	Waterford	23 April 2003		Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments
W3F1-2003-0015, License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval	Waterford	11 March 2003		License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval
W3F1-2002-0107, License Amendment Request NPF-38-244, Corrections & Clarifications to Various TS Pages	Waterford	20 December 2002		License Amendment Request NPF-38-244, Corrections & Clarifications to Various TS Pages
VR-SECY-22-0046, Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson)		27 June 2022		VR-SECY-22-0046: Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson)
VR-SECY-19-0072, Denial of Petition for Rulemaking on Measurement and Control of Combustible Gas Generation and Dispersal (PRM-50-103; NRC-2011-0189) (Hanson)		12 August 2020		VR-SECY-19-0072: Denial of Petition for Rulemaking on Measurement and Control of Combustible Gas Generation and Dispersal (PRM-50-103; NRC-2011-0189) (Hanson)
ULNRC-06445, Revised Emergency Action Level Technical Basis Document	Callaway	9 July 2018		Revised Emergency Action Level Technical Basis Document
ULNRC-06433, License Amendment Request for Emergency Action Level (EAL) Changes	Callaway	4 September 2018		License 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 6	Callaway	31 August 2015		Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6
ULNRC-06230, Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6	Callaway	16 July 2015		Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6
ULNRC-06166, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program	Callaway	19 December 2014		Submittal 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 Program	Callaway	19 December 2014		Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program
ULNRC-06035, CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests	Callaway	29 August 2013		CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests
ULNRC-06034, 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fourth 120-Month Inservice Testing Interval	Callaway	23 September 2013		10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fourth 120-Month Inservice Testing Interval
ULNRC-05947, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal Application	Callaway	15 January 2013		License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal Application
ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives	Callaway	24 September 2012		Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives
ULNRC-05821, Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173)	Callaway	27 October 2011		Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173)
ULNRC-05781, Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2	Callaway	29 August 2011		Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2
ULNRC-05598, Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request LDCN 09-0008)	Callaway	20 March 2009		Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request LDCN 09-0008)
ULNRC-05309, Inoperable Channel 11 of the Loose Parts Detection System (Lpds)	Callaway	10 July 2006		Inoperable Channel 11 of the Loose Parts Detection System (Lpds)
ULNRC-05248, Submittal of Revision 23 to Pump and Valve Inservice Testing Program	Callaway	19 January 2006		Submittal of Revision 23 to Pump and Valve Inservice Testing Program
ULNRC-05237, Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)	Callaway	9 December 2005		Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)
ULNRC-05187, Inoperable Channel 3 of the Loose Parts Detection System (Lpds)	Callaway	11 August 2005		Inoperable Channel 3 of the Loose Parts Detection System (Lpds)
ULNRC-04923, License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program.	Callaway	8 December 2003		License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program.
U-604633, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1	Clinton	23 May 2021		Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1
U-604555, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0	Clinton	13 July 2020		Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0
U-604457, Third Ten-Year Interval Inservice Testing Program Plan Revision 9	Clinton	21 November 2018		Third Ten-Year Interval Inservice Testing Program Plan Revision 9
U-604454, Transmittal of Revision 20 to Technical Specification Bases	Clinton	31 December 2018		Transmittal of Revision 20 to Technical Specification Bases
U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases	Clinton	22 December 2017		Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases
U-604359, Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8	Clinton	20 July 2017		Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8
U-604326, Third Ten-Year Interval Inservice Testing Program Plan Revision 7	Clinton	8 March 2017		Third Ten-Year Interval Inservice Testing Program Plan Revision 7
U-604278, Annual Radioactive Effluent Release Report for 2015	Clinton	29 April 2016		Annual Radioactive Effluent Release Report for 2015
U-604262, Third Ten-Year Interval Inservice Testing Program Plan, Revision 6	Clinton	15 February 2016		Third Ten-Year Interval Inservice Testing Program Plan, Revision 6
U-604257, Transmittal of Revision 17 to the Technical Specification Bases	Clinton	21 December 2015		Transmittal of Revision 17 to the Technical Specification Bases
U-604243, Special Report: Inoperable Post Accident Monitoring Instrumentation	Clinton	25 September 2015		Special Report: Inoperable Post Accident Monitoring Instrumentation
U-604211, 2014 Annual Radioactive Effluent Release Report	Clinton	16 April 2015		2014 Annual Radioactive Effluent Release Report
U-604075, Transmittal of Revision 14 to the Technical Specification Bases	Clinton	4 June 2012		Transmittal of Revision 14 to the Technical Specification Bases
U-604018, Annual Radioactive Effluent Release Report	Clinton	28 April 2011		Annual Radioactive Effluent Release Report
U-603987, Transmittal of Revision 13 to Technical Specification Bases	Clinton	1 October 2010		Transmittal of Revision 13 to Technical Specification Bases
U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval	Clinton	12 July 2010		Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval
U-603962, Addenda to 2009 Annual Radioactive Effluent Release Report	Clinton	7 June 2010		Addenda to 2009 Annual Radioactive Effluent Release Report
U-603953, 2009 Annual Radioactive Effluent Release Report	Clinton	28 April 2010		2009 Annual Radioactive Effluent Release Report
U-603907, Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan	Clinton	31 July 2009		Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan
U-603859, Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases	Clinton	23 May 2008		Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases
U-603858, Addenda to 2005 Annual Radioactive Effluent Release Report	Clinton	27 May 2008		Addenda to 2005 Annual Radioactive Effluent Release Report
U-603796, Submittal of Supporting Documentation for December 19, 2006 Regulatory Conference	Clinton	12 December 2006		Submittal of Supporting Documentation for December 19, 2006 Regulatory Conference
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases	Clinton	16 August 2006		Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
U-603708, Transmittal of Revision 9 to the Clinton Power Station Technical Specification Bases	Clinton	3 January 2005		Transmittal of Revision 9 to the Clinton Power Station Technical Specification Bases
U-603676, Day Post-Outage Inservice Inspection (ISI) Summary Report	Clinton	27 May 2004		Day Post-Outage Inservice Inspection (ISI) Summary Report
U-603640, Transmittal of Revision 8 to the Technical Specification Bases	Clinton	13 November 2003		Transmittal of Revision 8 to the Technical Specification Bases
U-603625, Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004	Clinton	6 January 2004		Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004
U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases	Clinton	27 November 2002		Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
U-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 Included	Clinton	8 October 1999		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 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,Encl	Clinton	20 September 1999		Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys	Clinton	24 June 1999		Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys
U-603170, Identifies Nine MOVs Being Added to CPS GL 89-10 Program & Provides Actions Being Taken to Ensure That MOVs Are Capable of Performing safety-related Function	Clinton	8 March 1999		Identifies Nine MOVs Being Added to CPS GL 89-10 Program & Provides Actions Being Taken to Ensure That MOVs Are Capable of Performing safety-related Function
U-603112, Requests Withdrawal of Application for Amend of Operating License NPF-62,submitted Via Util Ltrs & 960722	Clinton	23 November 1998		Requests Withdrawal of Application for Amend of Operating License NPF-62,submitted Via Util Ltrs & 960722
U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)	Clinton	5 October 1998		Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)
U-603061, Requests Temporary Schedular Exemption from Requirements of 10CFR50,App J,To Defer LLRT of Primary Containment Penetration 1MC-042 at CPS Until Startup from Next Scheduled Refueling outage,(RF-7)	Clinton	13 August 1998		Requests Temporary Schedular Exemption from Requirements of 10CFR50,App J,To Defer LLRT of Primary Containment Penetration 1MC-042 at CPS Until Startup from Next Scheduled Refueling outage,(RF-7)
U-603032, Application for Amend to License NPF-62,adding TS LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys	Clinton	23 October 1998		Application for Amend to License NPF-62,adding TS LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys
U-603026, Submits Response to RAI Re Illinois Power Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions	Clinton	15 June 1998		Submits Response to RAI Re Illinois Power Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
U-603025, Forwards Request for Relief from Requirements of Section XI of ASME B&PV Code,Re Performance of Leakage Testing for Selected Category a Isolation Valves During First 120-month ISI Interval	Clinton	18 June 1998		Forwards Request for Relief from Requirements of Section XI of ASME B&PV Code,Re Performance of Leakage Testing for Selected Category a Isolation Valves During First 120-month ISI Interval
U-602836, Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630	Clinton	20 October 1997		Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630
U-602786, Informs That Util Has Completed All Actions Associated W/Cal Re Condition of Protective Coatings in Primary Containment & Drywell	Clinton	16 July 1997		Informs That Util Has Completed All Actions Associated W/Cal Re Condition of Protective Coatings in Primary Containment & Drywell
U-602780, Informs of Current Status of Efforts Re Condition of Protective Coatings in Primary Containment & Drywell in Response to Confirmatory Action Ltr	Clinton	2 July 1997		Informs of Current Status of Efforts Re Condition of Protective Coatings in Primary Containment & Drywell in Response to Confirmatory Action Ltr
U-602761, Informs NRC of Actions Plant Taking to Address Condition of Protective Coatings in Plant Primary Containment & Drywell, in Response to CAL	Clinton	12 June 1997		Informs NRC of Actions Plant Taking to Address Condition of Protective Coatings in Plant Primary Containment & Drywell, in Response to CAL
U-602683, Provides Response to NRCs RAI Re Adequacy & Availabilty of Design Bases Info at Util,Per 10CFR50.54(f)	Clinton	12 February 1997		Provides Response to NRCs RAI Re Adequacy & Availabilty of Design Bases Info at Util,Per 10CFR50.54(f)
U-602628, Forwards Response to Each of Questions Contained in NRC 960808 Request for Addl Info Re 960628 Application for Amend to License NPF-62 for Removal of Inclined Fuel Transfer Sys & Primary Containment Isolation Valves	Clinton	17 September 1996		Forwards Response to Each of Questions Contained in NRC 960808 Request for Addl Info Re 960628 Application for Amend to License NPF-62 for Removal of Inclined Fuel Transfer Sys & Primary Containment Isolation Valves
U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling	Clinton	15 August 1996		Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling
U-602596, Provides Addl Info for Amend to Incorporate Proposed Change to CPS Ts, ,be Reviewed on Schedule Sufficient to Support Sixth Refueling Outage Currently Scheduled to Begin 961013	Clinton	3 July 1996		Provides Addl Info for Amend to Incorporate Proposed Change to CPS Ts, ,be Reviewed on Schedule Sufficient to Support Sixth Refueling Outage Currently Scheduled to Begin 961013
U-602587, Application for Amend to License NPF-62,allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable	Clinton	28 June 1996		Application for Amend to License NPF-62,allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable
U-602569, Application for Amend to License NPF-62,revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met	Clinton	19 April 1996		Application for Amend to License NPF-62,revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met
U-602565, Application for Amend to License NPF-62,implementing 10CFR50,App J-Option B	Clinton	1 May 1996		Application for Amend to License NPF-62,implementing 10CFR50,App J-Option B
U-602549, Application for Amend to License NPF-62,proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier	Clinton	22 February 1996		Application for Amend to License NPF-62,proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier
U-602520, Application for Amend to License NPF-62,revising TS 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation, to Eliminate Periodic Response Time Testing of Analog Trip Modules	Clinton	14 December 1995		Application for Amend to License NPF-62,revising TS 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation, to Eliminate Periodic Response Time Testing of Analog Trip Modules
U-602519, Forwards Response to NRC 950721 RAI Re IPE Submittal for Facility,	Clinton	22 November 1995		Forwards 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 Sys	Clinton	14 December 1995		Application for Amend to License NPF-62,requesting Various Proposed Changes to TS for Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys
U-602430, Forwards four-yr Updated Certification Rept for Training Simulator.Encl Rept Describes Performance Testing Planned During Next Four Yrs	Clinton	17 March 1995		Forwards four-yr Updated Certification Rept for Training Simulator.Encl Rept Describes Performance Testing Planned During Next Four Yrs
U-602417, Application for Amend to License NPF-62,changing TS 3.8.2, 3.8.5 & 3.8.8 to Revise Operability Requirements for Div 3 DG & Divs 3 & 4 Batteries,Battery Chargers & Inverters to Apply Only When HPCS Required to Be Operable	Clinton	14 February 1995		Application for Amend to License NPF-62,changing TS 3.8.2, 3.8.5 & 3.8.8 to Revise Operability Requirements for Div 3 DG & Divs 3 & 4 Batteries,Battery Chargers & Inverters to Apply Only When HPCS Required to Be Operable
U-602376, Application for Amend to License NPF-62,eliminating Selected Response Time Testing Requirements	Clinton	27 January 1995		Application for Amend to License NPF-62,eliminating Selected Response Time Testing Requirements
U-602342, Requests Approval to Use ASME Code Case N-416-1 for Performing Alternate Testing & Examination of Sys Pressure Test Following Repair &/Or Replacement of Steam Admission Valve	Clinton	9 September 1994		Requests Approval to Use ASME Code Case N-416-1 for Performing Alternate Testing & Examination of Sys Pressure Test Following Repair &/Or Replacement of Steam Admission Valve
U-602331, Withdraws 940217 Request for Listed Partial Exemptions from 10CFR50,App J & Proposed Changes to License NPF-62	Clinton	15 August 1994		Withdraws 940217 Request for Listed Partial Exemptions from 10CFR50,App J & Proposed Changes to License NPF-62
U-602320, Application for Amend to License NPF-62,proposing Changes to TS 3/4.6.2.2, Drywell Bypass Leakage, to Allow Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years	Clinton	12 August 1994		Application for Amend to License NPF-62,proposing Changes to TS 3/4.6.2.2, Drywell Bypass Leakage, to Allow Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years
U-602282, Radioactive Effluent Release Rept, 930101-1231	Clinton	31 December 1993		Radioactive 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 1992	Clinton	26 October 1993		Application for Amend to License NPF-62,requesting Changes to TS to Improve & Reformat CPS TS Consistent w/NUREG-1434, Improved BWR-6 TS, Rev 0,Sept 1992
U-602028, Semiannual Radioactive Effluent Release Rept,Jan-June 1992 Clinton Power Station	Clinton	30 June 1992		Semiannual Radioactive Effluent Release Rept,Jan-June 1992 Clinton Power Station
U-601936, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1991, for Clinton Power Station	Clinton	31 December 1991		Semiannual 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 Requirements	Clinton	20 September 1991		Proposed Tech Specs Re Reactor Protection Sys Instrumentation,Containment & Reactor Vessel Isolation Control Sys & ECCS Instrumentation Surveillance Requirements
U-601830, Informs That Alternate Rod Injection & ATWS Reactor Pump Trip Sys Installed at Facility to Reduce Risk from ATWS Event,Per 10CFR50.62	Clinton	26 April 1991		Informs That Alternate Rod Injection & ATWS Reactor Pump Trip Sys Installed at Facility to Reduce Risk from ATWS Event,Per 10CFR50.62
U-601784, Proposed Tech Specs Exempting Measured Type C Leakage Rates for Feedwater Check Valves 1B21-F032A & B	Clinton	18 January 1991		Proposed Tech Specs Exempting Measured Type C Leakage Rates for Feedwater Check Valves 1B21-F032A & B
U-601504, Responds to NRC & Proposed Imposition of Civil Penalties Re Violations Noted in Insp Rept 50-461/89-06. Corrective Actions:Licensee Conducted Reinsps of Components to Ensure That Scope of Program Conservative	Clinton	8 August 1989		Responds to NRC & Proposed Imposition of Civil Penalties Re Violations Noted in Insp Rept 50-461/89-06. Corrective Actions:Licensee Conducted Reinsps of Components to Ensure That Scope of Program Conservative
U-601417, Advises That Util Completed NUREG-0737 (TMI Action Plan) Requirements,Per License Condition 2.C.(9).Brief Chronology of Status of Implementation of Dcrdr Submitted. Installation of Class 1E Power Sources Complete	Clinton	14 April 1989		Advises That Util Completed NUREG-0737 (TMI Action Plan) Requirements,Per License Condition 2.C.(9).Brief Chronology of Status of Implementation of Dcrdr Submitted. Installation of Class 1E Power Sources Complete
U-601194, Forwards Response to Ja Stevens 880505 Questions on Inservice Testing (IST) Program,Summary of Changes to IST, Relief Requests & Rev 5 to Pump & Valve Testing Program Plan	Clinton	27 May 1988		Forwards Response to Ja Stevens 880505 Questions on Inservice Testing (IST) Program,Summary of Changes to IST, Relief Requests & Rev 5 to Pump & Valve Testing Program Plan
U-601167, Forwards Addl Info Relating to Questions on Pneumatic & Hydrostatic Testing of Containment Isolation Valves & Pressure Isolation Valves.Info on Stroke Times of Certain Valves to Be Evaluated by NRC Also Encl	Clinton	18 April 1988		Forwards Addl Info Relating to Questions on Pneumatic & Hydrostatic Testing of Containment Isolation Valves & Pressure Isolation Valves.Info on Stroke Times of Certain Valves to Be Evaluated by NRC Also Encl
U-601118, Proposed Tech Specs Re Administrative Controls	Clinton	5 February 1988		Proposed Tech Specs Re Administrative Controls
U-601117, Requests one-time Exemption from Requirements of 10CFR50, App J,Paragraph III.D.3 Re Surveillance Interval Requirement for Type C Local Leak Rate Tests for Containment Isolation Valves.Fee Paid	Clinton	13 January 1988		Requests one-time Exemption from Requirements of 10CFR50, App J,Paragraph III.D.3 Re Surveillance Interval Requirement for Type C Local Leak Rate Tests for Containment Isolation Valves.Fee Paid
U-601084, Proposed Tech Specs Re Containment & Pressure Isolation Valve Surveillance Requirements	Clinton	10 December 1987		Proposed Tech Specs Re Containment & Pressure Isolation Valve Surveillance Requirements
U-601018, Semiannual Radioactive Effluent Release Rept,870228-0630	Clinton	30 June 1987		Semiannual Radioactive Effluent Release Rept,870228-0630
U-601014, Provides Requested Info Identified in D Muller Re Submittal of Facility Specific Hydrogen Control Sys Final Analysis,Including Proposed Outline for Hydrogen Control Sys Final Analysis Required by 10CFR50.44	Clinton	24 August 1987		Provides Requested Info Identified in D Muller Re Submittal of Facility Specific Hydrogen Control Sys Final Analysis,Including Proposed Outline for Hydrogen Control Sys Final Analysis Required by 10CFR50.44
U-600968, Forwards Responses to WR Butler & Rev 2 to Pump & Valve Testing Program Plan. Revised Program Will Be Implemented	Clinton	30 June 1987		Forwards Responses to WR Butler & Rev 2 to Pump & Valve Testing Program Plan. Revised Program Will Be Implemented
U-600885, Forwards marked-up Revs to Tech Specs Re Setpoints for Lpcs/ LPCI Permissive Interlocks for Full Power Ol,As Suppl to Util 870108,0204 & 0303 Ltrs.Changes Consistent W/Fsar & SER Through Suppl 7.No Change to Low Power OL Requested	Clinton	20 March 1987		Forwards marked-up Revs to Tech Specs Re Setpoints for Lpcs/ LPCI Permissive Interlocks for Full Power Ol,As Suppl to Util 870108,0204 & 0303 Ltrs.Changes Consistent W/Fsar & SER Through Suppl 7.No Change to Low Power OL Requested
U-600813, Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept	Clinton	31 December 1986		Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept
U-600689, Responds to NRC Re Violations Noted in Insp Rept 50-461/86-37.Corrective Actions:Procedure CPS 9052.02, LPCS Valve Operability Checks, Revised to Incorporate Criteria for Opening Time of LPCS Injection Valve	Clinton	25 August 1986		Responds to NRC Re Violations Noted in Insp Rept 50-461/86-37.Corrective Actions:Procedure CPS 9052.02, LPCS Valve Operability Checks, Revised to Incorporate Criteria for Opening Time of LPCS Injection Valve
U-600648, Responds to NRC Re Establishment of Emergency Communications Capability Known as Emergency Response Data Sys (Erds).Util in Process of Evaluating ERDS Requirements. Preliminary List of Plant Data for ERDS Encl	Clinton 05000000	21 July 1986		Responds to NRC Re Establishment of Emergency Communications Capability Known as Emergency Response Data Sys (Erds).Util in Process of Evaluating ERDS Requirements. Preliminary List of Plant Data for ERDS Encl
U-600601, Informs of Plans to Modify SPDS on Basis of Operator Comments Noted During 850913 Test Display of Containment Isolation Valve Status	Clinton	11 June 1986		Informs of Plans to Modify SPDS on Basis of Operator Comments Noted During 850913 Test Display of Containment Isolation Valve Status
U-600468, Forwards Justification for 851209 Request for Exemptions from 10CFR50.12,App J Final Rule Concerning Leak Test Requirements,Specifically,Msiv Leak Rate Tests & Containment Air Lock Leakage Testing	Clinton	11 March 1986		Forwards Justification for 851209 Request for Exemptions from 10CFR50.12,App J Final Rule Concerning Leak Test Requirements,Specifically,Msiv Leak Rate Tests & Containment Air Lock Leakage Testing
U-600296, Requests Exemption from 10CFR50,App J Leak Testing Requirements for MSIVs & Containment Air Lock.Justification for Exemption & marked-up Proof & Review Tech Specs Encl	Clinton	9 December 1985		Requests Exemption from 10CFR50,App J Leak Testing Requirements for MSIVs & Containment Air Lock.Justification for Exemption & marked-up Proof & Review Tech Specs Encl
U-600279, Forwards Response to 10CFR50.62 Requirements Re Reduction of ATWS Events for Light Water Cooled Nuclear Power Plants. Installation of ATWS Sys Complete.Tech Spec 3/4.1.5, Standby Liquid Control Sys, Will Be Revised	Clinton	16 October 1985		Forwards Response to 10CFR50.62 Requirements Re Reduction of ATWS Events for Light Water Cooled Nuclear Power Plants. Installation of ATWS Sys Complete.Tech Spec 3/4.1.5, Standby Liquid Control Sys, Will Be Revised
U-600275, Forwards marked-up Proof & Review Tech Specs,Per 850904 Request,Indicating Typos & Corrections to Info Submitted in 840928 & s	Clinton	2 October 1985		Forwards marked-up Proof & Review Tech Specs,Per 850904 Request,Indicating Typos & Corrections to Info Submitted in 840928 & s
U-600176, Forwards Results of post-accident Containment Venting & Corresponding plant-specific Emergency Procedure Guidelines, Per 850301 Telcon.Info Fulfills Requirements of TMI Item I.C.1 & SER (NUREG-0853) Confirmatory Issue 41	Clinton	24 July 1985		Forwards Results of post-accident Containment Venting & Corresponding plant-specific Emergency Procedure Guidelines, Per 850301 Telcon.Info Fulfills Requirements of TMI Item I.C.1 & SER (NUREG-0853) Confirmatory Issue 41
U-600083, Forwards Addl Accident Monitoring Instrumentation,Per NUREG-0737,TMI Item II.F.1.Info Complete & Adequate to Provide Confirmation That TMI Item & SER Confirmatory Issue 21 Implemented	Clinton	11 June 1985		Forwards Addl Accident Monitoring Instrumentation,Per NUREG-0737,TMI Item II.F.1.Info Complete & Adequate to Provide Confirmation That TMI Item & SER Confirmatory Issue 21 Implemented
U-600066, Forwards Responses to NRC Comments on Revised SPDS (TMI Action Plan Item I.D.2) for Review.Scheduling of Design Validation Audit in mid-Oct to Support Final Closure Requested	Clinton	12 June 1985		Forwards Responses to NRC Comments on Revised SPDS (TMI Action Plan Item I.D.2) for Review.Scheduling of Design Validation Audit in mid-Oct to Support Final Closure Requested
U-600029, Forwards List of Selected Operating Events to Be Used in Sys Function & Task Analysis,Per 850424 Responses to NRC Comments on Dcrdr Program Plan.Plan Process Fulfills Suppl 1 to NUREG-0737 Requirements	Clinton	12 June 1985		Forwards List of Selected Operating Events to Be Used in Sys Function & Task Analysis,Per 850424 Responses to NRC Comments on Dcrdr Program Plan.Plan Process Fulfills Suppl 1 to NUREG-0737 Requirements
TXX-9600, Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B	Comanche Peak	12 March 1996		Application for Amends to Licenses NPF-87 & NPF-89,changing TS 3/4.6.1 & Adding TS 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J, Option B
TXX-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 Encl	Comanche Peak	12 October 1987		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 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 Reviewed	Comanche Peak	24 April 1987		Forwards Response to Notice of Violation Item H from Insp Rept 50-446/86-02.Corrective Actions:All Cases Where CB&I Did Not Accept Original Radiograph & Did Not Classify Any Addl Work as Repair Reviewed
TXX-4703, Forwards Response to Section IV of Generic Ltr 85-12, Automatic Trip of Reactor Coolant Pumps. Determination of Pump Trip Criteria,Pump Potential Problems & Operator Training & Procedures Discussed	Comanche Peak	17 February 1986		Forwards Response to Section IV of Generic Ltr 85-12, Automatic Trip of Reactor Coolant Pumps. Determination of Pump Trip Criteria,Pump Potential Problems & Operator Training & Procedures Discussed
TXX-4182, Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review	Comanche Peak	29 May 1984		Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review
TSTF-580				Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling
TSTF-514				Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1	Technical Specifications Task Force	23 June 2021		TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
TSTF-21-01, Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling	Technical Specifications Task Force	26 January 2021		Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
TSTF-19-12, TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position.	Technical Specifications Task Force	5 November 2019		TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position.
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements	Technical Specifications Task Force 99902042	16 January 2020		TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
TSTF-19-10, Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position	Technical Specifications Task Force	28 August 2019		Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements	Technical Specifications Task Force 99902042	13 December 2019		Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements.	Technical Specifications Task Force	3 July 2019		Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements.
TSTF-19-05, Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position	Technical Specifications Task Force	18 June 2019		Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
TSTF-17-18, Transmittal of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems.	Technical Specifications Task Force	19 January 2018		Transmittal of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems.
TSTF-17-16, Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2	Technical Specifications Task Force	19 December 2017		Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
TSTF-17-10, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements.	Technical Specifications Task Force	2 August 2017		TSTF Comments on Draft Safety Evaluation for Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements.
TSTF-16-10, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control, and Transmittal of Editorial Corrections to TSTF-542, Revision 2	Technical Specifications Task Force	2 November 2016		TSTF Comments on Draft Safety Evaluation for Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control, and Transmittal of Editorial Corrections to TSTF-542, Revision 2
TSTF-16-09, Technical Specifications Task Force - Revision 3 of TSTF-551, Revise Secondary Containment Surveillance Requirements.	Technical Specifications Task Force	3 October 2016		Technical Specifications Task Force - Revision 3 of TSTF-551, Revise Secondary Containment Surveillance Requirements.
TSTF-16-07, Technical Specifications Task Force - Revision 2 of TSTF-551, Revise Secondary Containment Surveillance Requirements.	Technical Specifications Task Force	12 May 2016		Technical Specifications Task Force - Revision 2 of TSTF-551, Revise Secondary Containment Surveillance Requirements.
TSTF-16-03, Technical Specifications Task Force - Comments on Draft Model Safety Evaluation of Traveler TSTF-529, Revision 3, Clarify Use and Application Rules, and Transmittal of TSTF-529, Revision 4	Technical Specifications Task Force	29 February 2016		Technical Specifications Task Force - Comments on Draft Model Safety Evaluation of Traveler TSTF-529, Revision 3, Clarify Use and Application Rules, and Transmittal of TSTF-529, Revision 4
TSTF-15-11, 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 3	Technical Specifications Task Force	21 October 2015		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 3
TSTF-15-08, Technical Specifications Task Force - Transmittal of TSTF-529, Revision 3, Clarify Use and Application Rules.	Technical Specifications Task Force	14 September 2015		Technical Specifications Task Force - Transmittal of TSTF-529, Revision 3, Clarify Use and Application Rules.
TSTF-15-07, Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements.	Technical Specifications Task Force	3 September 2015		Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements.
TSTF-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 2	Technical Specifications Task Force	3 April 2015		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 2
TSTF-14-18, Transmittal of TSTF-551, Revision 0, Address Transient Secondary Containment Conditions	Technical Specifications Task Force	30 October 2014		Transmittal of TSTF-551, Revision 0, Address Transient Secondary Containment Conditions
TSTF-14-17, Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3	Technical Specifications Task Force	31 March 2015		Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3
TSTF-14-05, Transmittal of TSTF-545, Revision 1, TS Inservice Testing Program Removal.	Technical Specifications Task Force	4 March 2014		Transmittal 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 Force	14 January 2014		Transmittal of TSTF-529, Revision 2, Clarify Use and Application Rules.
TSTF-13-15, Transmittal of TSTF-542, Revision 0, Reactor Pressure Vessel Walter Inventory Control	Technical Specifications Task Force	31 December 2013		Transmittal 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 Performed	Technical Specifications Task Force	10 September 2013		Transmittal of TSTF-541, Revision 0, Add Exceptions to Surveillance Requirements When the Safety Function Is Being Performed
TSTF-13-09, Transmittal of TSTF-545, Revision 0, TS Inservice Testing (IST) Program Removal.	Technical Specifications Task Force	4 November 2013		Transmittal of TSTF-545, Revision 0, TS Inservice Testing (IST) Program Removal.
TSTF-13-03, Transmittal of TSTF-529, Revision 1, Clarify Use and Application Rules	Technical Specifications Task Force	28 February 2013		Transmittal of TSTF-529, Revision 1, Clarify Use and Application Rules
TSTF-13-02, Submittal of TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.	Technical Specifications Task Force	21 February 2013		Submittal 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 Force	30 August 2012		Response to NRC Request for Additional Information Regarding TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation.
TSTF-12-11, Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6)	Technical Specifications Task Force	16 May 2012		Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6)
TSTF-12-08, Transmittal of TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation	Technical Specifications Task Force	29 March 2012		Transmittal 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 Force	27 March 2012		Transmittal of TSTF-538, Revision 0, Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c.
TSTF-12-05, Transmittal of Report TSTF-GG-05-01, Revision 1, Writer'S Guide for Plant-Specific Improved Technical Specifications.	Technical Specifications Task Force	14 February 2012		Transmittal 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-373	Technical Specifications Task Force	27 March 2012		Transmittal of TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373
TSTF-12-01, Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046).	Technical Specifications Task Force	22 February 2012		Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046).
TSTF-11-15, Transmittal of TSTF-529, Revision 0, Clarify Use and Application Rules	Technical Specifications Task Force	21 September 2011		Transmittal 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 Force	19 September 2011		Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition.
TSTF-11-12, Transmittal of TSTF-530, Revision 0, Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09	Technical Specifications Task Force	16 September 2011		Transmittal of TSTF-530, Revision 0, Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09
TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.	Technical Specifications Task Force	24 November 2010		Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.
TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2	Technical Specifications Task Force	6 August 2010		Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2
TSTF-10-10, Comment (1) of K. J. Schrader, D. W. Gregoire, T. W. Raidy & R. Gambrell on Behalf of Technical Specification Task Force on Proposed Model TSTF-514, Revision 1, Revise BWR Operability Requirements and Actions for RCS Leakage Instrument. (	Technical Specifications Task Force	12 May 2010		Comment (1) of K. J. Schrader, D. W. Gregoire, T. W. Raidy & R. Gambrell on Behalf of Technical Specification Task Force on Proposed Model TSTF-514, Revision 1, Revise BWR Operability Requirements and Actions for RCS Leakage Instrument. (NR
TSTF-10-07, Transmittal of TSTF-493, Revision 4, Errata, Clarify Application of Setpoint Methodology for LSSS Functions.	Technical Specifications Task Force	23 April 2010		Transmittal 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 Accumulation	Technical Specifications Task Force	29 June 2010		Transmittal 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 Force	30 March 2010		Transmittal 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 Applica	Technical Specifications Task Force	25 November 2009		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 Applicati
TSTF-09-25, Transmittal of Revised Risk-Informed End State Travelers: TSTF-422, TSTF-423, TSTF-431, and TSTF-432	Technical Specifications Task Force	22 December 2009		Transmittal 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-360	Technical Specifications Task Force	22 September 2009		Transmittal 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 Force	8 September 2009		Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.
TSTF-09-10, Transmittal of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Sections 3.1.1 - 3.7.5	Technical Specifications Task Force	18 March 2009		Transmittal 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 Instrumentation	Technical Specifications Task Force	18 February 2009		Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
TSTF-09-01, Transmittal of TSTF-515, Revision 0, Revise Post-Accident Monitoring Instrumentation Based on Reg. Guide 1.97, Rev. 4 and NEDO-33349.	Technical Specifications Task Force	20 January 2009		Transmittal of TSTF-515, Revision 0, Revise Post-Accident Monitoring Instrumentation Based on Reg. Guide 1.97, Rev. 4 and NEDO-33349.
TSTF-08-20, Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.	Technical Specifications Task Force	10 November 2008		Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.
TSTF-08-19, Transmittal of TSTF-500, Revision 1, DC Electrical Rewrite - Update to TSTF-360.	Technical Specifications Task Force	5 November 2008		Transmittal 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 Force	14 October 2008		Transmittal of TSTF-512, Revision 0, Revise SR 3.0.3 to Address SRs That Cannot Be Performed or Are Not Met.
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization	Technical Specifications Task Force	3 July 2008		Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
TSTF-08-05, TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.	Technical Specifications Task Force	4 March 2008		TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.
TSTF-08-04, TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).	Technical Specifications Task Force	19 February 2008		TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
TSTF-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 Force	18 January 2008		Response 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, 2007	Technical Specifications Task Force	10 October 2007		Response to NRC Request for Additional Information Regarding TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461), Dated June 13, 2007
TSTF-07-26, TSTF-500, Revision 0, DC Electrical Rewrite - Update to TSTF-360.	Technical Specifications Task Force	31 August 2007		TSTF-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 Force	10 July 2007		TSTF-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 Force	16 April 2007		TSTF-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 Force	9 March 2007		Revision to Implementation Guidance for TSTF-423, Technical Specifications End States, NEDC-32988-A.
TSTF-07-09, TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.	Technical Specifications Task Force	21 February 2007		TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.
TSTF-07-07, Response to NRC Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Dated November 9, 2006	Technical Specifications Task Force	7 February 2007		Response to NRC Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Dated November 9, 2006
TSTF-07-04, TSTF-446, Revision 2, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).	Technical Specifications Task Force	11 January 2007		TSTF-446, Revision 2, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
TSTF-06-28, TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461).	Technical Specifications Task Force	20 December 2006		TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461).
TSTF-06-20, TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03.		18 July 2006		TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03.
TSTF-06-11, Response to NRC Request for Additional Information Regarding TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, Dated April 7, 2006		5 June 2006		Response to NRC Request for Additional Information Regarding TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, Dated April 7, 2006
TSTF-05-17, TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A.		19 September 2005		TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A.
TSTF-05-15, TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)		21 September 2005		TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)
TSTF-05-13, Technical Specification Task Force (TSTF) Response to May 25, 2005 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Re Revision to the Completion Time in STS 3.6.1.3, Primary Containment I		25 July 2005		Technical Specification Task Force (TSTF) Response to May 25, 2005 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Re Revision to the Completion Time in STS 3.6.1.3, Primary Containment Iso
TSTF-05-12, TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability.		18 August 2005		TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability.
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity.		29 June 2005		Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity.
TSTF-05-06, TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities.		5 May 2005		TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities.
TSTF-04-16, TSTF-446, Revision 1, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).		31 January 2005		TSTF-446, Revision 1, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
TSTF-04-15, TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a.		2 December 2004		TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a.
TSTF-04-12, Submittal and Request for Fee Waiver for Review of TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.		25 April 2005		Submittal and Request for Fee Waiver for Review of TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.
TSTF-04-11, TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems		30 August 2004		TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems
TSTF-04-08, TSTF-425, Revision 0, Relocate Surveillance Frequencies to Licensee Control.		31 August 2004		TSTF-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 2003		Traveler - August 12, 2003 Transmits TSTF-423, Technical Specifications End States, NEDC-32988-A.
TMI-17-035, Submittal of Changes to Technical Specifications Bases	Three Mile Island	13 April 2017		Submittal of Changes to Technical Specifications Bases
TMI-15-049, Submittal of Changes to Technical Specifications Bases	Three Mile Island	14 April 2015		Submittal of Changes to Technical Specifications Bases
TMI-15-048, Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program	Three Mile Island	13 April 2015		Submittal 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 Station	Oyster Creek	2 March 2015		Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating Station
TMI-14-069, Submittal of the Fifth Ten-Year Interval Inservice Testing Program	Three Mile Island	16 May 2014		Submittal of the Fifth Ten-Year Interval Inservice Testing Program
TMI-14-055, Submittal of Changes to Technical Specifications Bases	Three Mile Island	10 April 2014		Submittal 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 End	Oyster Creek	30 May 2014		Attachment 8: Discussion of Revision to the Radiological Emergency Plan Annex for Oyster Creek Nuclear Generating Station, Page Ocgs 3-76 Through End
TMI-13-105, Update 10 of the Post-Defueling Monitored Storage Safety Analysis Report	Three Mile Island	23 August 2013		Update 10 of the Post-Defueling Monitored Storage Safety Analysis Report
TMI-13-064, Submittal of Changes to Technical Specifications Bases	Three Mile Island	10 April 2013		Submittal of Changes to Technical Specifications Bases
TMI-13-050, Re-issue of Update 9 of the Post-Defueling Monitored Storage Safety Analysis Report	Three Mile Island	22 March 2013		Re-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 Requirements	Three Mile Island	4 February 2013		Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements
TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval	Three Mile Island	7 November 2012		Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval
TMI-12-068, Submittal of Changes to Technical Specifications Bases	Three Mile Island	12 April 2012		Submittal of Changes to Technical Specifications Bases
TMI-11-064, Submittal of Changes to Technical Specifications Bases	Three Mile Island	15 April 2011		Submittal 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 Controlled	Three Mile Island	27 September 2010		Response to Request for Additional Information, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled
TMI-10-046, Submittal of Changes to Technical Specifications Bases	Three Mile Island	22 April 2010		Submittal 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 Capability	Three Mile Island	15 March 2010		Response to Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability
TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)	Three Mile Island	24 March 2010		Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
TMI-09-101, Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014	Three Mile Island	14 August 2009		Submittal 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 Bases	Three Mile Island	17 April 2009		Submittal 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 Manual	Dresden	19 April 2019		Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation Manual
SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation	Dresden	8 April 2016		Submittal of Post Accident Monitoring Report Instrumentation
SVPLTR 13-0020, Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002	Dresden	6 June 2013		Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002
SVPLTR 13-0015, Offsite Dose Calculation Manual CY-DR-170-301, Rev. 12	Dresden	31 March 2012		Offsite 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 Events	Dresden	31 January 2013		Response to NRC Acknowledgement of Response to NRC Request for a Written, Response to NRC Observations and Concerns Regarding Dresden Station, Response Plan for External Flooding Events
SVPLTR 12-0022, Offsite Dose Calculation Manual	Dresden	30 April 2011		Offsite Dose Calculation Manual
SVPLTR 11-0018, Offsite Dose Calculation Manual	Dresden	31 October 2010		Offsite Dose Calculation Manual
SVPLTR 10-0037, 2011 Dresden Nuclear Power Station Initial Examination Outline Submittal	Dresden	23 September 2010		2011 Dresden Nuclear Power Station Initial Examination Outline Submittal
SVPLTR 10-0022, Revised Commitment for the Containment Leak Reduction & Control Program for Gas Systems	Dresden	15 May 2010		Revised Commitment for the Containment Leak Reduction & Control Program for Gas Systems
SVPLTR 09-0045, Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows	Dresden	2 October 2009		Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows
SVPLTR 05-0014, March 2005 Monthly Operating Report for Dresden Nuclear Power Station, Units 2 and 3	Dresden	8 April 2005		March 2005 Monthly Operating Report for Dresden Nuclear Power Station, Units 2 and 3
SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage	Quad Cities	22 September 1999		Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage
SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety	Quad Cities	13 August 1999		Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety
SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage	Quad Cities	30 June 1999		Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage
SVP-99-127, Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs	Quad Cities	16 July 1999		Application for Amends to Licenses DPR-29 & DPR-30,replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Scfh with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs in TS Section 3/4.7.D, Pcivs
SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with	Quad Cities	30 April 1999		Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with
SVP-99-038, Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable	Quad Cities	30 March 1999		Application for Amends to Licenses DPR-29 & DPR-30,allowing Alternate Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable
SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With	Quad Cities	31 January 1999		Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With
SVP-98-377, Provides Summary of NRC Commitments Completed During 15th Refueling outage,Q1R15	Quad Cities	14 January 1999		Provides Summary of NRC Commitments Completed During 15th Refueling outage,Q1R15
SVP-98-369, Confirms Completion of Installation of Larger Capacity Strainers & Reduction of Fibrous Insulation for Quad Cities 1.Actions in Response to Review of NRC SER Issued on BWROG Rept NEDO-326896 Listed	Quad Cities	18 December 1998		Confirms Completion of Installation of Larger Capacity Strainers & Reduction of Fibrous Insulation for Quad Cities 1.Actions in Response to Review of NRC SER Issued on BWROG Rept NEDO-326896 Listed
SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With	Quad Cities	31 October 1998		Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With
SVP-98-345, Forwards Response to NRC 981103 RAI Re Proposed Change to Ts,Increasing Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve	Quad Cities	9 November 1998		Forwards Response to NRC 981103 RAI Re Proposed Change to Ts,Increasing Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve
SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With	Quad Cities	15 July 1998		Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With
SVP-98-323, Provides Comeds Response to Close Open Regulatory Guide 1.97 Items.Comed Considers That with Completion of These Two Items,All Required Actions of Regulatory Guide 1.97 Are Complete	Quad Cities	13 November 1998		Provides Comeds Response to Close Open Regulatory Guide 1.97 Items.Comed Considers That with Completion of These Two Items,All Required Actions of Regulatory Guide 1.97 Are Complete
SVP-98-291, Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.6	Quad Cities	31 August 1998		Application for Amends to Licenses DPR-29 & DPR-30, Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig,Iaw SR 4.7.D.6
SVP-98-252, Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C	Quad Cities	31 July 1998		Application for Amends to Licenses DPR-29 & DPR-30, Clarifying Testing Requirements for Primary Containment Excess Flow Check Valves Contained in TS Bases 3/4.7.D & 3/4.12.C
SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2	Quad Cities	30 June 1998		Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2
SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2	Quad Cities	31 May 1998		Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2
SVP-98-196, Forwards Response to Violations Noted in Insp Repts 50-254/98-05 & 50-265/98-05.Corrective Actions:Issued Design Change Package on 971015	Quad Cities	21 May 1998		Forwards Response to Violations Noted in Insp Repts 50-254/98-05 & 50-265/98-05.Corrective Actions:Issued Design Change Package on 971015
SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2	Quad Cities	30 April 1998		Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2
SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2	Quad Cities	31 March 1998		Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2
SVP-98-114, Requests Review & Approval to 10CFR50.90 for Unreviewed Safety Question Involving Use of Station Blackout DGs & Use of Mobile Safe Shutdown Batteries in App R Ssd Analysis	Quad Cities	31 March 1998		Requests Review & Approval to 10CFR50.90 for Unreviewed Safety Question Involving Use of Station Blackout DGs & Use of Mobile Safe Shutdown Batteries in App R Ssd Analysis
SVP-98-100, Forwards Corrected Page to SE Summary SE-97-024 of 971031 Summary Rept of Changes,Tests & Experiements	Quad Cities	20 March 1998		Forwards Corrected Page to SE Summary SE-97-024 of 971031 Summary Rept of Changes,Tests & Experiements
SVP-98-095, Responds to NRC Re Violations Noted in Insp Repts 50-254/97-22 & 50-265/97-22.Corrective Actions:Procedure Qcop 2300-08 Was Walked Down & Verified by Sro,Corrected Procedure & Evaluated Effect of Longer Valve Closures Times	Quad Cities	13 March 1998		Responds to NRC Re Violations Noted in Insp Repts 50-254/97-22 & 50-265/97-22.Corrective Actions:Procedure Qcop 2300-08 Was Walked Down & Verified by Sro,Corrected Procedure & Evaluated Effect of Longer Valve Closures Times
SVP-98-087, Monthly Operating Repts for Feb 1998 for Quad Cities Nuclear Station,Units 1 & 2	Quad Cities	28 February 1998		Monthly Operating Repts for Feb 1998 for Quad Cities Nuclear Station,Units 1 & 2
SVP-98-049, Monthly Operating Repts for Jan 1998 for Quad Cities Nuclear Station,Units 1 & 2	Quad Cities	31 January 1998		Monthly Operating Repts for Jan 1998 for Quad Cities Nuclear Station,Units 1 & 2
SVP-97-267, Submits Response to Request for Info on Verification of Adequate Wall Thickness for Mark I Torus Shells for Units 1 & 2.Rept Discussing Present Matl Condition of Torus Shell & Plant Plans to Maintain Torus in Acceptable Condition Encl	Quad Cities	21 November 1997		Submits Response to Request for Info on Verification of Adequate Wall Thickness for Mark I Torus Shells for Units 1 & 2.Rept Discussing Present Matl Condition of Torus Shell & Plant Plans to Maintain Torus in Acceptable Condition Encl
SVP-94-017, Documents Results of 940214 Telcon W/Nrc,In Which Comm Ed Requested Issuance of Notice of Enforcement Discretion from TS 3.6.1.1 for Facility.Basis for Request for Enforcement Discretion Encl	Braidwood	15 March 1994		Documents Results of 940214 Telcon W/Nrc,In Which Comm Ed Requested Issuance of Notice of Enforcement Discretion from TS 3.6.1.1 for Facility.Basis for Request for Enforcement Discretion Encl
SVP-16-001, 2016 Quad Cities Nuclear Power Station Initial License Examination Forms ES-D-1	Quad Cities	2 May 2016		2016 Quad Cities Nuclear Power Station Initial License Examination Forms ES-D-1
SVP-13-080, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report	Quad Cities	26 November 2013		Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report
SVP-11-021, Clarification of License Renewal Commitment Regarding Bellows Testing	Quad Cities	7 April 2011		Clarification of License Renewal Commitment Regarding Bellows Testing
SVP-03-118, Transmittal of Lost Parts Analysis and Associated Operability Evaluation	Quad Cities	28 November 2003		Transmittal of Lost Parts Analysis and Associated Operability Evaluation
SVP-03-096, Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program	Quad Cities	11 September 2003		Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program
SVP-03-019, Fourth Interval Inservice Inspection Program Plan	Quad Cities	7 February 2003		Fourth Interval Inservice Inspection Program Plan
SVP-03-008, Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program Plan	Quad Cities	17 January 2003		Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program Plan
ST-HL-AE-5313, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Option B of 10CFR50,App J for Both Units & Proposing to Amend TS 4.6.1.1,3.6.1.2,4.6.1.2,3.6.1.3, 4.6.1.3,4.6.1.7.2,4.6.1.7.3 & Bases 3/4.6.1.2 & 3/4.6.1.3	South Texas	1 May 1996		Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Option B of 10CFR50,App J for Both Units & Proposing to Amend TS 4.6.1.1,3.6.1.2,4.6.1.2,3.6.1.3, 4.6.1.3,4.6.1.7.2,4.6.1.7.3 & Bases 3/4.6.1.2 & 3/4.6.1.3
ST-HL-AE-5046, Application for Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors & Amend to Licenses NPF-76 & NPF-80,replacing Current Specified Intervals W/Ref to 10CFR50 App J	South Texas	16 March 1995		Application for Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors & Amend to Licenses NPF-76 & NPF-80,replacing Current Specified Intervals W/Ref to 10CFR50 App J
ST-HL-AE-4066, Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks	South Texas	4 August 1992		Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks
ST-HL-AE-2279, Forwards Revised Pages 3.6.A-1,3.6.A-2,9.2.9 & 9.2.10 from FSAR Amend 61.Pages Revised to Correct Misprinting of Obverse Pages.Replacement Pages Will Be Included in Future Amend	South Texas	25 June 1987		Forwards Revised Pages 3.6.A-1,3.6.A-2,9.2.9 & 9.2.10 from FSAR Amend 61.Pages Revised to Correct Misprinting of Obverse Pages.Replacement Pages Will Be Included in Future Amend
ST-HL-AE-2259, Forwards Addl Info Re Thermal Relief Capacity for Component Cooling Water Subsystem Providing Cooling Water to Reactor Coolant Pump,Reactor Coolant Drain Tank & Excess Letdown Hxs,Per C Tinkler Request	South Texas	17 June 1987		Forwards Addl Info Re Thermal Relief Capacity for Component Cooling Water Subsystem Providing Cooling Water to Reactor Coolant Pump,Reactor Coolant Drain Tank & Excess Letdown Hxs,Per C Tinkler Request
ST-HL-AE-2232, Forwards Final Draft Tech Specs & Technical Changes W/ Justifications.Tech Specs Consistent W/Fsar.Ser & as-built Facility W/Exceptions,Editorial Changes & Corrections Noted on Encl marked-up Pages	South Texas	5 June 1987		Forwards Final Draft Tech Specs & Technical Changes W/ Justifications.Tech Specs Consistent W/Fsar.Ser & as-built Facility W/Exceptions,Editorial Changes & Corrections Noted on Encl marked-up Pages
ST-HL-AE-2198, Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept	South Texas	31 March 1987		Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept
ST-HL-AE-2182, Responds to Questions Raised in 870505 Meeting W/Nrc Re Util Compliance W/Gdc 56 & 57 & SRP 6.2.4 Concerning Remote Manual Isolation of Primary Containment Isolation Valves Following Dba.Revised Response to Generic Ltr 85-12 Encl	South Texas	29 May 1987		Responds to Questions Raised in 870505 Meeting W/Nrc Re Util Compliance W/Gdc 56 & 57 & SRP 6.2.4 Concerning Remote Manual Isolation of Primary Containment Isolation Valves Following Dba.Revised Response to Generic Ltr 85-12 Encl
ST-HL-AE-2096, Forwards Changes & Justifications for Changes in Proof & Review Tech Specs in Listed Areas,Including Definitions, Setpoints & Bases	South Texas	20 April 1987		Forwards Changes & Justifications for Changes in Proof & Review Tech Specs in Listed Areas,Including Definitions, Setpoints & Bases
ST-HL-AE-1984, Forwards,For Info & Use,Comments & Justifications for Changes Proposed in Proof & Review Tech Specs	South Texas	16 March 1987		Forwards,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 Amend	South Texas	9 March 1987		Forwards Annotated Revs to FSAR App 3.6.A Re Isolation Valve Cubicle (Ivc) Subcompartment Analysis.Changes Update Ivc Pressure & Temp Analysis Results.Revs Will Be Incorporated in Future FSAR Amend
ST-HL-AE-1923, Requests That Encl Proposed Deletions & Changes to Specific Tech Specs Be Made in Final Proof & Review Tech Specs. Affected FSAR Pages Which Will Be Included as Part of FSAR Amend 58 Encl	South Texas	13 March 1987		Requests That Encl Proposed Deletions & Changes to Specific Tech Specs Be Made in Final Proof & Review Tech Specs. Affected FSAR Pages Which Will Be Included as Part of FSAR Amend 58 Encl
ST-HL-AE-1710, Forwards marked-up FSAR Pages Re Deletion of Containment Spray Sump Additive Tank.Requests NRC Review Changes as Soon as Possible to Avoid Impacting Project Schedule	South Texas	28 August 1986		Forwards marked-up FSAR Pages Re Deletion of Containment Spray Sump Additive Tank.Requests NRC Review Changes as Soon as Possible to Avoid Impacting Project Schedule
ST-HL-AE-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 SER	South Texas	29 July 1986		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 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 Amend	South Texas	22 October 1985		Forwards Response to Draft SER or FSAR Item F 3.8-2 Re Identification of Codes,Stds & Specs Applicable to Design. Changes Will Be Incorporated in Future FSAR Amend
ST-HL-AE-1388, Forwards Response to Draft SER & FSAR Items Re Chapter 7A,Item II.B.3 Concerning post-accident Sampling Capability. Marked-up FSAR Pages to Be Included in Future FSAR Amend Also Encl	South Texas	14 October 1985		Forwards Response to Draft SER & FSAR Items Re Chapter 7A,Item II.B.3 Concerning post-accident Sampling Capability. Marked-up FSAR Pages to Be Included in Future FSAR Amend Also Encl
SNRC-2018, Responds to NRC Re Violations Noted in Insp Rept 50-322/92-04.Corrective Actions:On 920701,LIPA Submitted Ltr Entitled, Facility Status at Time of Decommissioning Order Issuance Relative to Shoreham Decommissioning Plan	Shoreham	4 January 1993		Responds to NRC Re Violations Noted in Insp Rept 50-322/92-04.Corrective Actions:On 920701,LIPA Submitted Ltr Entitled, Facility Status at Time of Decommissioning Order Issuance Relative to Shoreham Decommissioning Plan
SNRC-1904, Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991	Shoreham	30 March 1992		Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991
SNRC-1899, Requests Amend to License NPF-82 Adding New License Condition to Authorize Decommissioning of Shoreham	Shoreham	22 January 1992		Requests Amend to License NPF-82 Adding New License Condition to Authorize Decommissioning of Shoreham
SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990	Shoreham	31 December 1990		10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990
SNRC-1583, Forwards Supplemental Info Re Temp Profile Inside Primary Containment Used for Environ Qualification	Shoreham	12 April 1989		Forwards Supplemental Info Re Temp Profile Inside Primary Containment Used for Environ Qualification
SNRC-1578, Provides Info Re Temp Profile Inside Primary Containment Used for Environ Qualification.Results of Review of Actual Test Temps Indicate Sufficient Margin Exists to Envelope Supporting Calcuation & Environ Qualification Profile	Shoreham	4 April 1989		Provides Info Re Temp Profile Inside Primary Containment Used for Environ Qualification.Results of Review of Actual Test Temps Indicate Sufficient Margin Exists to Envelope Supporting Calcuation & Environ Qualification Profile
SNRC-1573, Submits Proposed Actions for Issues Discussed at Operational Readiness Assessment Team Insp Exit Meeting.Util Committed to Completing ASME Bolting Corrective Actions & Having Documentation to Demonstrate Prior to Startup	Shoreham	31 March 1989		Submits Proposed Actions for Issues Discussed at Operational Readiness Assessment Team Insp Exit Meeting.Util Committed to Completing ASME Bolting Corrective Actions & Having Documentation to Demonstrate Prior to Startup
SNRC-1561, Responds to 10CFR50.63 Re Station Blackout (SBO) Rule.Util Has Determined That in Unlikely Event of Sbo,Station Possesses Sufficient Independent & Diverse Alternate Ac Power Capacity	Shoreham	14 April 1989		Responds to 10CFR50.63 Re Station Blackout (SBO) Rule.Util Has Determined That in Unlikely Event of Sbo,Station Possesses Sufficient Independent & Diverse Alternate Ac Power Capacity
SNRC-1552, Forwards Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Engineering Study Verified That Instrument Air Receivers & Accumulators Designed Per ANSI & ASME Codes	Shoreham	21 February 1989		Forwards Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Engineering Study Verified That Instrument Air Receivers & Accumulators Designed Per ANSI & ASME Codes
SNRC-1546, Forwards 10CFR50.59 Rept for 1988.During Reporting Period, Emergency Operating Procedures Updated to Comply W/Recommendations of BWR Owners Group Emergency Procedure Guidelines,Rev 4.Procedure Change Notices Encl	Shoreham	14 March 1989		Forwards 10CFR50.59 Rept for 1988.During Reporting Period, Emergency Operating Procedures Updated to Comply W/Recommendations of BWR Owners Group Emergency Procedure Guidelines,Rev 4.Procedure Change Notices Encl
SNRC-1464, Forwards Comments W/Supporting Documentation Re post-NRC Written Operator Exams,To Assist in Evaluating Responses to Exam Questions	Shoreham	20 May 1988		Forwards Comments W/Supporting Documentation Re post-NRC Written Operator Exams,To Assist in Evaluating Responses to Exam Questions
SNRC-1444, Responds to NRC Re Violations Noted in Insp Rept 50-322/88-01.Corrective Actions:Change to Station Procedure Sp 84.654.03 Approved,Cautioning Against Overpressurizing Test Vols Utilizing Water	Shoreham	18 April 1988		Responds to NRC Re Violations Noted in Insp Rept 50-322/88-01.Corrective Actions:Change to Station Procedure Sp 84.654.03 Approved,Cautioning Against Overpressurizing Test Vols Utilizing Water
SNRC-1429, Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment	Shoreham	31 December 1987		Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment
SNRC-1424, Forwards Shoreham Nuclear Power Station PRA W/Supplemental Containment Sys, in Response to NRC Questions.Requests Concurrence W/Quality Group Categorization by 880408	Shoreham	2 March 1988		Forwards Shoreham Nuclear Power Station PRA W/Supplemental Containment Sys, in Response to NRC Questions.Requests Concurrence W/Quality Group Categorization by 880408
SNRC-1397, Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl	Shoreham	4 December 1987		Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl
SNRC-1376, Responds to Re Violations Noted in Insp Rept 50-322/87-10.Corrective Actions:Two Solenoid Operated Valve Splices Removed & Replaced W/Approved Splices & Electrical Maint Personnel Instructed Re Proper Requirements	Shoreham	30 September 1987		Responds to Re Violations Noted in Insp Rept 50-322/87-10.Corrective Actions:Two Solenoid Operated Valve Splices Removed & Replaced W/Approved Splices & Electrical Maint Personnel Instructed Re Proper Requirements
SNRC-1370, Responds to NRC Bulletin 87-001 Re Thinning of Pipe Walls. Programs for Monitoring Wall Thickness of Carbon Steel Pipes in Safety & nonsafety-related Portions of Condensate, Feedwater & Connected high-energy Piping Sys Discussed	Shoreham	14 September 1987		Responds to NRC Bulletin 87-001 Re Thinning of Pipe Walls. Programs for Monitoring Wall Thickness of Carbon Steel Pipes in Safety & nonsafety-related Portions of Condensate, Feedwater & Connected high-energy Piping Sys Discussed
SNRC-1367, Requests Concurrence W/Proposed Supplemental Containment Sys Plan & Response to Encl NRC Concerns,W/Understanding That NRC Reserves Right to Review & Comment on Detailed Design Submittal	Shoreham	28 August 1987		Requests Concurrence W/Proposed Supplemental Containment Sys Plan & Response to Encl NRC Concerns,W/Understanding That NRC Reserves Right to Review & Comment on Detailed Design Submittal
SNRC-1348, Forwards Addl Info Re Low Power Operation at 25%,per 870616 Request.Info Should Close Out Correspondence in View of NRC Cancellation of Util 25% Power Request	Shoreham	4 August 1987		Forwards Addl Info Re Low Power Operation at 25%,per 870616 Request.Info Should Close Out Correspondence in View of NRC Cancellation of Util 25% Power Request
SNRC-1305, Rept of Changes,Tests & Experiments Completed During 1985, Per 10CFR50.4 & 50.59	Shoreham	31 December 1985		Rept of Changes,Tests & Experiments Completed During 1985, Per 10CFR50.4 & 50.59
SNRC-1303, Proposes Method for Determining Operability of Primary Containment Air Cooler Condensate Flow Indication Sys,In Response to NRC Questions Raised During Review of 851116 Application for License Amend.Figure 13.5.1-2 Encl	Shoreham	30 March 1987		Proposes Method for Determining Operability of Primary Containment Air Cooler Condensate Flow Indication Sys,In Response to NRC Questions Raised During Review of 851116 Application for License Amend.Figure 13.5.1-2 Encl
SNRC-1296, Forwards Updated SAR for Shoreham Nuclear Power Station & Rev 6 to Plant Design Assessment Rept for Safety Relief Valves & LOCA Loads.... Encl Proprietary Suppl to Assessment Rept Withheld (Ref 10CFR2.790)	Shoreham	2 December 1986		Forwards Updated SAR for Shoreham Nuclear Power Station & Rev 6 to Plant Design Assessment Rept for Safety Relief Valves & LOCA Loads.... Encl Proprietary Suppl to Assessment Rept Withheld (Ref 10CFR2.790)
SNRC-1261, Rev 1 to Transient Analysis Lesson Plan	Shoreham	30 May 1986		Rev 1 to Transient Analysis Lesson Plan
SNRC-1243, Requests Temporary Exemption from Requirements of 10CFR50.44(c)(3)(i) Re Inerting of Containment.Exemption Necessary Due to Publication & Effectiveness of Commission Final Rule on Specific Exemptions	Shoreham	27 March 1986		Requests Temporary Exemption from Requirements of 10CFR50.44(c)(3)(i) Re Inerting of Containment.Exemption Necessary Due to Publication & Effectiveness of Commission Final Rule on Specific Exemptions
SNRC-1239, Forwards Addl Info in Support of License Change Request 2. Change Requested to Reduce Personnel Exposure to Radiation During Power Ascension Test Program.Drywell Air Cooler Condensate Flow Indication Sys Described	Shoreham	18 March 1986		Forwards Addl Info in Support of License Change Request 2. Change Requested to Reduce Personnel Exposure to Radiation During Power Ascension Test Program.Drywell Air Cooler Condensate Flow Indication Sys Described
SNRC-1215, Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage	Shoreham	12 November 1985		Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage
SNRC-1209, Forwards Response to WR Butler Re Review of Eg&G Evaluation of Implementation of Rev 2 to Reg Guide 1.97 Concerning Emergency Response Capability	Shoreham	23 October 1985		Forwards Response to WR Butler Re Review of Eg&G Evaluation of Implementation of Rev 2 to Reg Guide 1.97 Concerning Emergency Response Capability
SNRC-1169, Informs That Based on General Physics Job/Task Analysis,Util Position That Tdi Emergency Diesel Generators Can Be Effectively Operated w/3300 Kw Qualified Load Substantiated. General Physics Recommendations to Improve Procedures Encl	Shoreham	6 May 1985		Informs That Based on General Physics Job/Task Analysis,Util Position That Tdi Emergency Diesel Generators Can Be Effectively Operated w/3300 Kw Qualified Load Substantiated. General Physics Recommendations to Improve Procedures Encl
SNRC-1158, Forwards Revised Fire Hazard Analysis Rept Sections in Response to Items Noted in Insp Rept 50-322/84-46,per Util 850129 Commitment.Changes Do Not Decrease Level of Fire Protection at Facility	Shoreham	5 April 1985		Forwards Revised Fire Hazard Analysis Rept Sections in Response to Items Noted in Insp Rept 50-322/84-46,per Util 850129 Commitment.Changes Do Not Decrease Level of Fire Protection at Facility
SNRC-1150, Forwards Addl Info Re Operator Training,In Response to NRC 850205 Request.Reasonable Assurance Exists That Loads in Excess of Qualified Load Will Not Be Imposed Upon Tdi Emergency Diesel Generators by Operators	Shoreham	4 April 1985		Forwards Addl Info Re Operator Training,In Response to NRC 850205 Request.Reasonable Assurance Exists That Loads in Excess of Qualified Load Will Not Be Imposed Upon Tdi Emergency Diesel Generators by Operators
SNRC-1130, Deficiency Rept Re Failure to Install HVAC Penetration Seals to Protect Two Trains of Redundant Safe Shutdown Motor Control Ctrs.Initially Reported on 841129.Sealing of Gaps Completed on 841208	Shoreham	28 December 1984		Deficiency Rept Re Failure to Install HVAC Penetration Seals to Protect Two Trains of Redundant Safe Shutdown Motor Control Ctrs.Initially Reported on 841129.Sealing of Gaps Completed on 841208
SNRC-1105, Forwards Exemption Requests for Containment Isolation, MSIV-App J Testing,Seismic Qualifications & Remote Shutdown, Per NRC Request Resulting from Commission Order CLI-84-8	Shoreham	9 November 1984		Forwards Exemption Requests for Containment Isolation, MSIV-App J Testing,Seismic Qualifications & Remote Shutdown, Per NRC Request Resulting from Commission Order CLI-84-8
SNRC-1104, Forwards Requested Addl Info Re Various Aspects of Newly Developed Qualified Load for Tdi Diesel Generators,Per 841026 Telcon	Shoreham	19 November 1984		Forwards Requested Addl Info Re Various Aspects of Newly Developed Qualified Load for Tdi Diesel Generators,Per 841026 Telcon
SNRC-1101, Forwards Addl Info Re FSAR Chapter 13, Conduct of Operations, Submitted as Part of Amend 51 to License Application.Resumes for Watch Engineers Assigned to Shift Crews Encl,Per Reg Guide 1.8	Shoreham	12 November 1984		Forwards Addl Info Re FSAR Chapter 13, Conduct of Operations, Submitted as Part of Amend 51 to License Application.Resumes for Watch Engineers Assigned to Shift Crews Encl,Per Reg Guide 1.8
SNRC-1092, Forwards Revised FSAR Sections,Providing Detailed Technical Bases & Methods Utilized in Developing Qualified Load of 3,300 Kw,In Response to Section 4.6 of SER on Tdi Owners Group Program Plan.Revs to Be Included in Fsar,Rev 34	Shoreham	22 October 1984		Forwards Revised FSAR Sections,Providing Detailed Technical Bases & Methods Utilized in Developing Qualified Load of 3,300 Kw,In Response to Section 4.6 of SER on Tdi Owners Group Program Plan.Revs to Be Included in Fsar,Rev 34
SNRC-1085, Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR	Shoreham	25 September 1984		Amend 51 to License Application,Consisting of Rev 3 to Fsar. One Oversize Figure Encl.Aperture Card Available in PDR
SNRC-1082, Submits Status of Evaluation Re IE Info Notice 84-17, Problems W/Liquid Nitrogen Cooling Components Below Nil Ductility Temp & GE Svc Info Ltr SIL-402, Wetwell/Drywell Inerting	Shoreham	18 September 1984		Submits Status of Evaluation Re IE Info Notice 84-17, Problems W/Liquid Nitrogen Cooling Components Below Nil Ductility Temp & GE Svc Info Ltr SIL-402, Wetwell/Drywell Inerting
SNRC-1078, Forwards Revs to FSAR Chapter 13, Conduct of Operations & Section 17.2, QA During Operations Phase, Reflecting Operational Readiness.Revs Will Be Included in Forthcoming Rev 33 to FSAR	Shoreham	5 September 1984		Forwards Revs to FSAR Chapter 13, Conduct of Operations & Section 17.2, QA During Operations Phase, Reflecting Operational Readiness.Revs Will Be Included in Forthcoming Rev 33 to FSAR
SNRC-1044, Forwards News Release Re Changes in Util Mgt,Resumes of Leonard,Steiger,Smith,Youngling,Kubinak,Greene,J Scalice, D Terry,J Schmitt & Ja Notaro & Two Charts Reflecting Revised Organization	Shoreham	8 May 1984		Forwards News Release Re Changes in Util Mgt,Resumes of Leonard,Steiger,Smith,Youngling,Kubinak,Greene,J Scalice, D Terry,J Schmitt & Ja Notaro & Two Charts Reflecting Revised Organization
SNRC-1026, Forwards Supplemental Motion for Low Power OL	Shoreham	21 March 1984		Forwards Supplemental Motion for Low Power OL
SNRC-1014, Provides Justification for Deletion of Station Blackout Test & Completion of Program for Training During Low Power Testing,Per TMI Item I.G.1,in Response to Generic Ltr 83-24	Shoreham	16 February 1984		Provides Justification for Deletion of Station Blackout Test & Completion of Program for Training During Low Power Testing,Per TMI Item I.G.1,in Response to Generic Ltr 83-24
SNRC-1012, Clarifies Sept 1983 Draft Technical Evaluation Rept of Phase II Submittal of Control of Heavy Loads,Per 840109 Telcon. Safe Load Paths for Reactor Bldg Closed Loop Cooling Water Pumps Revised	Shoreham	5 March 1984		Clarifies Sept 1983 Draft Technical Evaluation Rept of Phase II Submittal of Control of Heavy Loads,Per 840109 Telcon. Safe Load Paths for Reactor Bldg Closed Loop Cooling Water Pumps Revised
SECY-24-0087, Enclosure - Abnormal Occurrence Reporting - Issuance FRN		22 October 2024		SECY-24-0087: Enclosure - Abnormal Occurrence Reporting - Issuance FRN
SECY-23-0076, Weekly Information Report Week Ending August 18, 2023		28 August 2023		SECY-23-0076: Weekly Information Report Week Ending August 18, 2023
SECY-19-0024, VR-SECY-19-0024: Report to Congress on Abnormal Occurrences: Fiscal Year 2018		30 April 2019		VR-SECY-19-0024: Report to Congress on Abnormal Occurrences: Fiscal Year 2018
SECY-11-0124, Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 3		17 July 2013		Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 3
SECY-04-0233, Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire		22 December 2004		SECY-04-0233Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire
SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan	Seabrook	4 January 2022		Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan
SBK-L-19129, Submittal of Changes to the Seabrook Station Technical Specification Bases	Seabrook	31 December 2019		Submittal of Changes to the Seabrook Station Technical Specification Bases
SBK-L-19049, License Amendment Request 19-01, Application to Revise the Technical Specifications Associated with Emergency Core Cooling System Accumulators	Seabrook	4 June 2019		License Amendment Request 19-01, Application to Revise the Technical Specifications Associated with Emergency Core Cooling System Accumulators
SBK-L-18195, Submittal of Changes to the Seabrook Station Technical Specification Bases	Seabrook	18 December 2018		Submittal of Changes to the Seabrook Station Technical Specification Bases
SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program	Seabrook	28 February 2018		0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program
SBK-L-18027, 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 Program	Seabrook	28 February 2018		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 Program
SBK-L-17185, License Amendment Request 17-04: Remove Limitation to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications	Seabrook	1 December 2017		License Amendment Request 17-04: Remove Limitation to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications
SBK-L-16181, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program	Seabrook	23 December 2016		License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program
SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency	Seabrook	27 October 2016		Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors	Seabrook	27 October 2016		Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
SBK-L-16022, Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction	Seabrook	23 February 2016		Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction
SBK-L-15228, Submittal of Changes to the Technical Specification Bases	Seabrook	5 January 2016		Submittal of Changes to the Technical Specification Bases
SBK-L-14184, Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program	Seabrook	11 December 2014		Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program
SBK-L-14086, Nextera Energy Seabrook - Letter Regarding Response to Requests for Additional Information for the Review of the License Renewal Application Set 20 Relating to the Alkali-Silica Reaction (ASR) Monitoring Program	Seabrook	15 May 2014		Nextera Energy Seabrook - Letter Regarding Response to Requests for Additional Information for the Review of the License Renewal Application Set 20 Relating to the Alkali-Silica Reaction (ASR) Monitoring Program
SBK-L-14024, License Amendment Request (LAR) - 14-01, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler - 523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated.	Seabrook	24 June 2014		License Amendment Request (LAR) - 14-01, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler - 523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated.
SBK-L-13225, Submittal of Changes to the Seabrook Station Technical Specification Bases	Seabrook	12 December 2013		Submittal of Changes to the Seabrook Station Technical Specification Bases
SBK-L-13147, Administrative Changes to License Amendment Requests in NRC Review	Seabrook	31 July 2013		Administrative Changes to License Amendment Requests in NRC Review
SBK-L-13071, License Amendment Request 13-03	Seabrook	28 May 2013		License Amendment Request 13-03
SBK-L-13028, License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical Specifications	Seabrook	1 March 2013		License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical Specifications
SBK-L-12266, Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System	Seabrook	31 January 2013		Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System
SBK-L-12185, Supplement 3 to Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal Application	Seabrook	13 September 2012		Supplement 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 System	Seabrook	2 July 2012		Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System
SBK-L-12054, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System	Seabrook	15 March 2012		Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System
SBK-L-12053, Supplement 2 to Severe Accident Mitigation Alternatives Analysis, License Renewal Application	Seabrook	19 March 2012		Supplement 2 to Severe Accident Mitigation Alternatives Analysis, License Renewal Application
SBK-L-12052, Submittal of Changes to Technical Specification Bases	Seabrook	16 February 2012		Submittal of Changes to Technical Specification Bases
SBK-L-11233, Response to Request for Additional Information - Set 17	Seabrook	17 November 2011		Response to Request for Additional Information - Set 17
SBK-L-11186, License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure - Temperature Limits and the Cold Overpressure Protection Setpoints	Seabrook	17 November 2011		License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure - Temperature Limits and the Cold Overpressure Protection Setpoints
SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System	Seabrook	16 September 2011		Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System
SBK-L-11141, Submittal of Special Report Regarding Containment Enclosure Building Structural Integrity	Seabrook	11 July 2011		Submittal of Special Report Regarding Containment Enclosure Building Structural Integrity
SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program	Seabrook	22 June 2011		Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program
SBK-L-11066, License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation	Seabrook	21 April 2011		License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation
SBK-L-11015, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 8	Seabrook	3 February 2011		Response 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 Application	Seabrook	13 January 2011		Response to Request for Additional Information, NextEra Energy License Renewal Application
SBK-L-10236, Submittal of Changes to the Technical Specification Bases	Seabrook	30 December 2010		Submittal of Changes to the Technical Specification Bases
SBK-L-10204, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs	Seabrook	17 December 2010		Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs
SBK-L-10143, Response to Request for Additional Information Regarding License Amendment Request (LAR) 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System.	Seabrook	24 August 2010		Response to Request for Additional Information Regarding License Amendment Request (LAR) 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System.
SBK-L-10097, License Amendment Request 10-03	Seabrook	28 June 2010		License Amendment Request 10-03
SBK-L-10074, License Amendment Request 10-02	Seabrook	14 May 2010		License Amendment Request 10-02
SBK-L-08216, Submittal of Changes to Technical Specification Bases	Seabrook	16 December 2008		Submittal of Changes to Technical Specification Bases
SBK-L-07139, Response to Request for Additional Information for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes	Seabrook	7 August 2007		Response to Request for Additional Information for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes
SBK-L-06127, Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change	Seabrook	7 June 2006		Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change
SBK-L-06065, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.	Seabrook	28 April 2006		Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.
SBK-L-06059, License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.	Seabrook	7 August 2006		License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.
SBK-L-05197, License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval.	Seabrook	29 September 2005		License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval.
SBK-L-04121, Submittal of Changes to the Seabrook Station Technical Specification Bases	Seabrook	2 December 2004		Submittal of Changes to the Seabrook Station Technical Specification Bases
SBK-L-04053, License Amendment Request 04-07, Revision to Technical Specification Surveillance Requirement 4.6.1.3b, Containment Air Lock Interlock	Seabrook	10 January 2005		License Amendment Request 04-07, Revision to Technical Specification Surveillance Requirement 4.6.1.3b, Containment Air Lock Interlock
SBK-L-04050, Submittal of Changes to the Plant Technical Specification Bases	Seabrook	2 September 2004		Submittal of Changes to the Plant Technical Specification Bases
Regulatory Guide 7.9		31 January 1980		Standard Format & Content of Part 71 Applications for Approval of Packaging of Type B,Large Quantity & Fissile Radioactive Material
Regulatory Guide 1.96		30 June 1976		Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants
Regulatory Guide 1.82		6 September 2005		Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident
Regulatory Guide 1.77		31 May 1974		Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors
Regulatory Guide 1.7		30 September 1976		Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident
Regulatory Guide 1.68		31 January 1977		Regulatory Guide 1.68.1, Revision 1, Preoperational and Initial Startup Testing of Feedwater and Condensate System for Boiling Water Reactor Power Plants
Regulatory Guide 1.52		31 July 1976		Design, 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 1.3		30 June 1974		Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors
Regulatory Guide 1.232		27 February 2018		Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors
Regulatory Guide 1.206		3 October 2018
Regulatory Guide 1.195		31 May 2003		Methods and Assumptions for Evaluating Radiological Consequences of Design-Basis Accidents at Light-Water Nuclear Power Reactors
Regulatory Guide 1.194		1 June 2003		Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants
Regulatory Guide 1.189		28 February 2018		Rev. 3, Fire Protection for Nuclear Power Plants
Regulatory Guide 1.183		1 July 2000		Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
Regulatory Guide 1.158		28 February 1989		(Task Ee 006-5) Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants
Regulatory Guide 1.141		31 July 2010		Containment Isolation Provisions for Fluid Systems
Regulatory Guide 1.140		30 June 2001		(Revision 2), Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
Regulatory Guide 1.120		30 June 1976		Fire Protection Guidelines for Nuclear Power Plants
Regulatory Guide 1.117		30 April 1978		Rev 1,Tornado Design Classification
Regulatory Guide 1.11		31 March 2010		Instrument Lines Penetrating the Primary Reactor Containment
RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591	Dresden	21 October 2024		Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591
RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed	Quad Cities	6 June 2024		Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed
RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation	Clinton	9 May 2024		Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion	Quad Cities	5 April 2024		Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion
RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing	Clinton	13 January 2023		Application to Adopt TSTF-332, ECCS Response Time Testing
RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval	Dresden	1 November 2022		Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration	Dresden Nine Mile Point Clinton Quad Cities LaSalle	3 October 2022		Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves	Clinton	24 May 2022		Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling	Clinton	24 May 2022		Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock	Clinton	7 April 2022		Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock
RS-22-011, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval	Quad Cities	17 February 2022		Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval
RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements	Calvert Cliffs Dresden Peach Bottom Nine Mile Point Byron Braidwood Limerick Ginna Clinton Quad Cities FitzPatrick LaSalle	4 January 2022		Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel	Dresden Clinton Quad Cities LaSalle	19 August 2021		Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel
RS-21-066, Amendment 23 to Fire Protection Report, Volume 3, Cross Reference from Old to New Configurations of Fppdp	Dresden	21 June 2021		Amendment 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 Requirements	Peach Bottom Nine Mile Point Byron Braidwood Limerick Ginna Clinton Quad Cities FitzPatrick LaSalle	30 June 2021		Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b	LaSalle	31 March 2021		Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RS-21-036, Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition	Dresden	16 March 2021		Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency	Clinton	24 February 2021		License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology	LaSalle	10 February 2021		Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology
RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1	Byron	17 December 2020		Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1
RS-20-139, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69	Clinton	24 November 2020		Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69
RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)	LaSalle	29 October 2020		Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)
RS-20-132, License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition	Dresden	29 October 2020		License 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 Flowchart	Braidwood	13 October 2020		EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart
RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements	Dresden Clinton Quad Cities LaSalle	18 November 2020		Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568	Dresden Peach Bottom Nine Mile Point Limerick Quad Cities LaSalle	3 September 2020		Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568
RS-20-052, 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 4b	Clinton	30 April 2020		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 4b
RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3	Quad Cities	1 April 2020		Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3
RS-20-038, Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance	Dresden	6 May 2020		Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance
RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process	Dresden Peach Bottom Nine Mile Point Limerick Quad Cities LaSalle	30 April 2020		License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process
RS-20-028, 1 to Updated Safety Analysis Report, CPS Tsb	Clinton	31 March 2020		1 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 2020		Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)
RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues	Byron Braidwood Ginna	6 February 2020		Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
RS-20-001, Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer	Clinton	14 January 2020		Request for License Amendment Regarding Automatic Operation of Transformer Load Tap Changer
RS-19-101, 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...	Dresden	30 October 2019		Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...
RS-19-098, Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report	Quad Cities	21 October 2019		Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report
RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.	Byron Braidwood	24 September 2019		License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.
RS-19-076, Supplement to License Amendment Request to Increase Technical Specifications Allowable MSIV Leakage Rates	Quad Cities	22 July 2019		Supplement to License Amendment Request to Increase Technical Specifications Allowable MSIV Leakage Rates
RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control	Dresden Clinton	18 June 2019		Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program	Calvert Cliffs Dresden Peach Bottom Nine Mile Point Palisades Byron Braidwood Limerick Ginna Clinton Quad Cities FitzPatrick LaSalle	25 June 2019		Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
RS-19-023, Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.1	Quad Cities	5 March 2019		Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.1
RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control	Dresden Peach Bottom Nine Mile Point Byron Braidwood Limerick Ginna Quad Cities FitzPatrick LaSalle	14 June 2019		Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control
RS-18-131, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions	LaSalle	14 December 2018		Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
RS-18-113, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...	Peach Bottom	28 September 2018		Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...
RS-18-106, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions	Limerick	14 November 2018		Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
RS-18-103, Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation	Clinton	29 August 2018		Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation
RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...	Peach Bottom	28 August 2018		Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...
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