05000286/LER-2015-003, Regarding Technical Specification Prohibited Condition Caused by Failure to Meet Containment Fan Cooler Unit Service Water (SW) Flow Rate Due to Improper SW Surveillance Test Configuration
05000530/LER-2010-002, Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Obstruction
05000286/LER-2005-005, Technical Specification Prohibited Condition Due to Mode Change Without Performing Required Actions with the 32 Containment Fan Cooler Unit Inoperable
NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances
MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension
PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases
MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension
MNS-15-073, Response to NRC Letter Dated August 27, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension
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
NL-14-1870, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
NL-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
L-14-405, License Amendment Request for Proposed Revision of Technical Specification 3.6.6, Containment Spray and Air Cooling Systems
NL-14-1016, Response to Request for Additional Information on Plant Vogtle License Amendment Request to Revise Tech Specs to Implement NEI 06-09, Rev. 0, Risk Informed Tech Specs Initiative 4b, Risk-Managed Tech Specs Guidelines.
NL-13-2479, Response to Request for Additional Information Regarding Technical Specification 3.7.14, Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System Condition a Completion Time Extension
PNP 2012-087, Proposed Alternative - Request for Relief from Immediate ASME Code Flaw Repair of Service Water System Manual Valve MV-SW136
NL-12-1002, License Amendment Request for Incorporation of Previously NRC Approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-439-A, Rev. 2, Eliminate Second Completion Times Limiting
DCL-12-076, Response to NRC Second Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, Ts
ULNRC-05804, Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025)
L-11-141, License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System
CNS-18-031, Notice of Enforcement Discretion (NOED) Request
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
RA-15-019, Attachment 3 - EP-AA-1002, Revised Radiological Emergency Plan Annex Information for Byron Station
RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3A, 3B, Cover - by 3-74
RA-14-032, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pa
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8
NRC 2010-0097, Response to Request for Additional Information on License Amendment Request 261, Supplement 5, Extended Power Uprate
1CAN060901, Submittal of Amendment 22 to Safety Analysis Report, Current Technical Requirements Manual (TRM) and the Current Technical Specification (TS) Bases
ULNRC-05551, Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
DCL-08-087, Response to Request for Additional Information on License Amendment Request 07-05, Revision to Technical Specification 3.5.2 and Revision to Technical Specification 3.6.6
NL-08-136, Nine Month Response to NRC Generic Letter 2008-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
NL-08-1340, Nine-Month Response to NRC Generic Letter 2008-01
1CAN070801, Transmittal of Analysis of Proposed Technical Specification Change Sodium Hydroxide Tank Concentration
NEI 99-01, Wolf Creek Nuclear 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
NEI 99-01, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3A, 3B, Cover - by 3-74
NEI 99-01, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pa
NRC 2009-0022, 2009 Point Beach Initial License Examination Proposed Dynamic Simulator Scenarios
TSTF-03-09, Traveler - November 10, 2003 - Transmits TSTF-430, R.1, AOT Extension to 7 Days for LPI and Containment Spray (BAW-2295-A, Rev. 1)
CP-200700022, License Amendment Request (LAR) 2007-008 to Technical Specification 3.6.7, Spray Additive System
ULNRC-05445, One-Time Completion Time Extension for Essential Service Water (ESW) System
L-90-005, Relief Request 3-43 for Temporary Repair to Service Water Pipe
NL-07-120, Response to Request for Additional Information Regarding Relief Request 3-43 for Temporary Repair to Service Water Pipe
NL-07-0117, Technical Specifications Amendment Request Engineered Safety Feature Room Coolers
BYRON 2006-0013, Byron June 2006 Examination Outline Submittal
RS-05-155, Request for a License Amendment to Technical Specification 3.6.6,Containment Spray and Cooling Systems, Surveillance Requirement SR 3.6.6.3
RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
RA-18-0198, (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
NRC-2014-0028, Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014
NRC-2012-0275, FRN, Withdrawal of an Amendment Request, Revise Surveillance Requirement 3.6.6.3 for Cooling Water Flow Rate in Technical Specification 3.6.6, Containment Spray and Cooling Systems
NRC-2010-0309, FRN: General Notice. Biweekly Notice, Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations, NRC-2010-0309
RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS
NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)
CNL-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
ULNRC-05174, Union Electric Co., Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems
DCL-05-099, Response to Requested Information, Part 2 of NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ET 14-0034, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
1CAN022001, License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate
DCL-04-096, Emergency License Amendment Request 04-03, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems
ULNRC-04917, Revision of License Amendment Request OL-1225 Regarding Proposed Changes to Technical Specifications for Extension of Required Action Completion Times for Diesel Generators
NL-03-1740, Request to Revise Technical Specifications Containment Equipment Hatch
ULNRC-04866, License Amendment Request OL-1225 Revision to TSs for Extension of Required Action Completion Time for Diesel Generators
ULNRC-04851, CFR 50.59 Summary Report, July 2001 - December 2002
NRC 2003-0033, Technical Specification Bases Revisions
RS-02-205, Response to Request for Additional Information Supporting a License Amendment Request Revising TS Surveillance Requirements for Containment Spray Nozzles
NRC 2002-0108, Technical Specification Bases Revisions
NL-02-130, Response to Request for Additional Information Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS)
RNP-RA/02-0109, Response to Request for Additional Information on Technical Specifications Change Regarding Containment Vessel Spray Nozzle Test Frequency
RS-02-045, Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles
RNP-RA/02-0018, Request for Amendment, Modification of TS Requirements for Containment Vessel Spray Nozzle Testing Specified by Surveillance Requirement (SR) 3.6.6.8
NL-20-0275, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
1CAN072001, Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate
L-20-144, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
CP-202000365, Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump
CP-202000585, (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump
RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
3F1097-04, Application for LAR 217,Rev 0 to DPR-72,addessing Rev to Description of Electrical Controls for Operating Reactor Bldg Recirculation Sys fan/cooler,AHF-1C,as Discussed in FSAR & Improved TS Bases
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
NSD-NRC-97-5468, Forwards W Responses to RAIs 640.153 & 640.154 Re Comments on Passive Containment Cooling Sys in Rev 3 of AP600 Certified Design Matl,As Requested in from Staff. Responses Closes Open Items 6053,6054 & 6183
3F1297-11, Application for Amend to License DPR-72,revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal
NSD-NRC-98-5535, Forwards Revised Response to FSER Open Item 480.1084F Related to Comments on Passive Containment Cooling Sys from Containment Sys Branch Re Rev 3 of AP600 Certified Design Matl,Including ITAAC
NSD-NRC-97-5485, Forwards Responses to FSER Open Items on AP600.Summary of Encl Responses Provided in Table 1
ULNRC-06702, Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505
L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response
NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,
L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3
CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-
3F1006-02, License Amendment Request 293, Revision 0 Revised Improved Technical Specification (ITS) 3.7.7, Nuclear Services Closed Cycle Cooling Water (SW) System
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle.
NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks
NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)
05000247/LER-2008-002, Re. Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Engineered Safety Feature Actuation System Automatic Actuation Logic & Actuation Relay Caused
RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
DCL-08-002, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
CP-202000575, (CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating
2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
3F1296-09, Forwards 10CFR50.59(b)(2) Rept of Evaluations Which Have Resulted in No Unreviewed Safety Questions for Mods or Procedure Changes
CNL-19-086, Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
NL-08-0987, Emergency Technical Specification (TS) Revision Request Regarding TS 3.6.6, Containment Spray and Cooling Systems
CNL-17-104, Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)
L-08-236, License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System
DCL-14-058, License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294)
NL-07-123, Response to Third Request for Additional Information Regarding Relief Request 3-43 for Temporary Repair to Service Water Pipe
CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications
TSTF-17-04, Technical Specifications Task Force - Transmittal of TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
NL-07-129, Proposed Changes to the Technical Specifications Regarding Replacement of the Sodium Hydroxide Buffer with Sodium Tetraborate Decahydrate
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
DCL-08-059, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (Revision 1)
BYRON 2008-0055, Submittal of 2008 Byron Initial License Examination Post-Examination Comments
AEP-NRC-2016-29, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 and to Request an Alternative to the ASME Code
DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
05000313/LER-1988-027, :on 880422,containment Isolation Valve Inoperable.Caused by Lack of Documentation of Design Basis Info for Sys Piping Temp & Pressures in Original Plant Design.Design Change Package Developed
05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With
NSD-NRC-98-5554, Forwards W Responses to FSER Open Items on AP600.Summary of Enclosed Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column of Oits Encl in Table 1
CP-202000305, (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water
05000220/LER-1984-019, :on 850722,24 Occurrence Repts Initiated in Early 1984 Discovered Unsent.Caused by Personnel Deviating from Established Program.Methods Used to Initiate,Review, Track & Close Out Occurrence Repts Reviewed
NSD-NRC-97-5484, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses Is Provided in Table 1
05000413/LER-1990-015, :on 900402,Tech Spec 3.0.3 Entered When Both Trains of Containment Valve Injection Water Sys Rendered Inoperable.Caused by Supervisor Incorrectly Denoting Valve Position.Valves 1RN-493 & 494 Closed
05000414/LER-1990-006, :on 900321,discovered That Nuclear Svc Water Sys Assured Makeup Source to Containment Valve Injection Water Sys Surge Chamber 2A Would Not Provide Adequate Flow. Caused by Clogged Pipe
05000323/LER-2019-001, Containment Spray Inoperable in Mode 4
NL-17-0447, Response to Request for Additional Information on Technical Specifications Change to Adopt Risk Informed Completion Times
05000312/LER-1981-037, Forwards LER 81-037/03L-0.Detailed Event Analysis Submitted
NEI 99-01, Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document
3F1197-09, Provides Description of Control Complex Habitability Envelope Inleakage Testing & Revisions to Calculational Methodology Used for Determining CR Operator Dose at Plant, Unit 3.W/plan for Resolving Discrepancies & Commitments
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000289/LER-1976-044, Forwards LER 76-044/03L.Provides Supplemental Info
RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
05000414/LER-2018-002, Condition Prohibited by Technical Specifications (TS) Due to Failure of the 2A Diesel Generator (DG)
05000266/LER-2016-003, Regarding Operation or Condition Prohibited by Technical Specifications
05000247/LER-2015-004, Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Flawed Elbow on the 21 Fan Cooler Unit Service Water Motor Cooling Return Pipe
AEP-NRC-2016-07, License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation
MNS-15-062, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an a Train Nuclear Service Water System (Nsws) Degraded Condition
05000445/LER-2014-003, Regarding Safety Chiller Inoperable for Longer than Allowed by Technical Specifications
DCL-15-007, Response to NRC Request for Additional Information Regarding License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision, 1.
GO2-15-019, Emergency License Amendment Associated with Technical Specifications 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A, Request for CT Extension on RHR-B Inoperability
NL-14-1703, Response to Request for Additional Information on LAR to Revise Technical Specifications to Implement NEI-06-09, Rev 0, Risk Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications Guidelines
05000328/LER-2014-002, Regarding Containment Vacuum Relief Valve Inoperable Resulting in a Condition Prohibited by Technical Specifications
DCL-14-078, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.8.1, AC Sources - Operating
05000413/LER-2014-001, Unit Regarding Condition Prohibited by Technical Specifications (TS) and Notice of Enforcement Discretion (NOED) Due to Misaligned Connecting Rod Bearing on Diesel Generator (DG) 1A
NL-13-1540, Response to Request for Additional Information on License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Rev. 0, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications
05000413/LER-2012-001-01, Regarding Automatic Reactor Trip Due to Faulted Reactor Coolant Pump Motor Cable Resulted in Zone G Relay Lockout and Subsequent Loss of Offsite Power and Emergency Diesel Generator Automatic Start for Both Units
ET 12-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems
ULNRC-05927, Withdrawal of Application for Amendment to Facility Operating License NPF-30 for Revising Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, LDCN 09-0025
05000482/LER-2012-003, Regarding B Train ECCS and Containment Spray System Inoperable Due to Damaged Watertight Containment Spray Pump Door Seal
WO 12-0035, Application for License Amendment to Revise Technical Specification 3.6.6, Containment Spray and Cooling Systems
05000247/LER-2011-003, Regarding Technical Specification (TS) Violation for Entry Into TS 3.0.3 for 3 Inoperable Fan Cooler Unit Trains and Failure to Correct within 1 Hour and Actions Taken for Plant Shutdown
05000413/LER-2011-001, For Catawba Nuclear Station, Unit 1 Regarding Technical Specification Violation Involving Notice of Enforcement Discretion Due to Failure of Diesel Generator Mechanical Governor
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
05000424/LER-2010-001, For Vogtle Electric Generating Plant, Regarding Breaker Failure Results in 1B Train Containment Cooling System Being Declared Inoperable
05000414/LER-2010-001, Regarding Reactor Mode Change with Limiting Condition for Operation 3.6.6 Not Met in Violation of Limiting Condition for Operation 3.0.4
05000346/LER-2009-001, Regarding Containment Air Cooler Fans Inoperable Due to Misapplication of Potter and Brumfield Rotary Relays
DCL-08-098, Supplement Response to Request for Additional Information on License Amendment Request 07-05, Revision to Technical Specification 3.5.2 - Increase in Completion Time for Emergency Core Cooling System from 72 Hours to 14
AEP-NRC-2008-43, Nine-Month Response to NRC Generic Letter 2008-01 Issued Pursuant to 10 CFR 50.54(f), Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
NL-08-0994, Supplemental Information Supporting Acceptance Review of Emergency Technical Specification (TS) Revision Request Regarding TS 3.6.6, Containment Spray and Cooling Systems
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
05000247/LER-2007-002, Regarding Technical Specification Prohibited Condition Due to Exceeding Containment Air Temperature Limit Allowed Outage Time as a Result of Changes in Instrument Uncertainty
05000255/LER-2006-008, Re Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
05000362/LER-2005-002, Emergency Containment Cooling Inoperable for Longer than Allowed by Technical Specifications
TSTF-05-10, TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco
3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle
DCL-04-097, Response to NRC Request for Additional Information Regarding Emergency License Amendment Request 04-03, Revision to Technical Specification 3.6.6. Containment Spray and Cooling Systems
05000456/LER-2004-002, Regarding 1 C Reactor Containment Fan Cooler Discovered to Be Inoperable Greater than Required Technical Specification Allowed Outage Time
05000482/LER-2004-001, Regarding Inadequate Verification of Valve Position Following Testing Results in Technical Specifications Violation
05000390/LER-2003-006, Containment Spray Pump Inoperable Due to Open Breaker
05000255/LER-2003-004, Inoperable Train of Containment Cooling - Condition Prohibited by Technical Specifications
05000483/LER-2003-005, Failure of Both Containment Spray Pumps Due to Air Binding
05000390/LER-2003-002, Failure in Power Distribution Panel in Reactor Protection Panel 1-R-9
05000413/LER-2003-004, A Containment Spray System Inoperable for Longer than Technical Specifications Allow Due to Heat Exchanger Fouling
05000301/LER-2003-001, For Point Beach Nuclear Plant Unit 2 Regarding Containment Accident Fan Backdraft Damper Failure Results in Condition Prohibited by TS 3.6.6.C
BW030008, Request for Notice of Enforcement Discretion for Technical Specification 3.5.2, Emergency Core Cooling Systems - Operating
ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves
NL-13-078, Proposed License Amendment Regarding Technical Change Traveler TSTF-432-A Revision 1
NEI 99-01, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
TSTF-18-04, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater (AFW) System, TS 3.8.1, Ac...
DCL-11-059, Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Sys
TSTF-12-06, Transmittal of TSTF-538, Revision 0, Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
DCL-16-104, Technical Specification Changes for License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1..
L-25-024, 10 CFR 50.55a Request BV-ISI-2025-01, Quench Spray Pinhole Leak
RS-22-057, Constellation Radiological Emergency Plan Addendum Revision
DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1
DCL-11-059, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, .
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
NL-14-1297, Request for Enforcement Discretion from Technical Specification 3.3.6, Containment Spray and Cooling Systems
ULNRC-06651, License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02
CP-202100394, Supplement to License Amendment Request (LAR) 20-006
WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves
L-2025-020, License Amendment Request 279, Extend Surveillance Test Intervals in Support of Transition to 24 Month Fuel Cycles
NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions
3F0407-06, 2006 Technical Specifications Bases Control Program
RS-02-143, Units 1 & 2 Additional Information Supporting License Amendment Request on Technical Specifications Surveillance Requirement for Containment Spray Nozzles
NSD-NRC-97-5263, Forwards W Responses to Comments on AP600 TS Re Containment Sys.Response to Question 68 Re TS 3.6.9 for Ph Adjustment, Is Still in Progress W/Completion Scheduled for 970825
NSD-NRC-96-4739, Forwards Draft Mark Up of Chapter 54 of AP600 Probabilistic Risk Assessment (PRA) Covering Low Power & Shutdown PRA Assessment.Pra Section Revised to Incorporate Commitments Westinghouse Made in Response to RAIs
CPSES-200502434, Licence Amendment Request (LAR) 05-010, Revision to Technical Specification 3.3.2, ESFAS Instrumentation, 3.5.2, ECCS-Operating, and 3.6.7, Spray Additive System
NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1
05000446/LER-2025-001, (Cpnpp), Containment Spray Pump Declared Inoperable Due to Misaligned Breaker