RS-17-020, Response to RAI Concerning License Amendment Request to Revise Technical Specification Section 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
NOC-AE-17003501, Technical Specification Bases Control Program
NLS2017048, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
LR-N17-0188, Response to Integrated Inspection Report 05000272/2017003 and 05000311/2017003
L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b
U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases
RBG-47801, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
L-MT-13-033, Extended Power Uprate: Secy 11-0014 Use of Containment Accident Pressure - Responses to Requests for Additional Information
L-12-064, Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
NLS2011026, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve
NL-18-0206, Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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
L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360
NL-15-1898, Enclosure 6: Clean-Typed EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant
NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4
RA-15-019, Attachment 7 - EP-AA-1008, Revised Radiological Emergency Plan Annex Information for Limerick Generating Station
RA-15-019, Attachment 6 - EP-AA-1005, Revised Radiological Emergency Plan Annex Information for LaSalle County Station
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
RA-15-019, Attachment 4 - EP-AA-1003, Revised Radiological Emergency Plan Annex Information for Clinton Power Station
RA-14-032, Clinton, Unit 1, Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
NOC-AE-10002554, Technical Specification Bases Control Program (Section 6.8.3.m)
NLS2010029, Technical Specifications Bases Changes
LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
W3F1-2010-0010, . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations
RBG-46985, Unit 1, Supplement to License Amendment Request (LAR) LAR 2009-05, Dated August 10, 2009 Regarding 24-Month Fuel Cycles
GO2-09-051, Initial License Written Examination Documentation
GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1
GO2-08-122, Supplement to Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves
NOC-AE-07002228, License Amendment Request Proposed Revision to Technical Specification 3.6.1.3, Containment Air Locks
W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
NEI 99-01, Clinton, Unit 1, Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151
TSTF-05-15, TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)
GNRO-2007/00073, Technical Specification Bases Update to the NRC for Period Dated December 03, 2007
BSEP-07-0064, Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program
GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves
LR-N07-0044, Reply to Notice of Violation: EA-06-205
RS-06-141, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
PLA-6020, Proposed Amendment No. 287 and Proposed Amendment No. 255: Revision to Technical Specifications 5.5.6 & 5.5.12
L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)
GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test
2CAN020601, License Amendment Request to Modify Technical Specification Surveillance Requirement 4.6.1.1.a
NRC-89-0273, Application for Amend to License NPF-43,changing Tech Specs 3/4.4.7,3/4.6.3,3/4.6.4.2 & Definition 1.29 Re Containment Isolation Valves
05000369/LER-1981-036, Forwards LER 81-036/01T-1.Detailed Event Analysis Encl
RAIO-0817-55190, LLC Response to NRC Request for Additional Information No. 76 (Erai No. 8792) on the NuScale Design Certification Application
CNRO-2004-00035, Request for Relief GGNS-PRR-E21-02 for the Low Pressure Core Spray Pump 2nd IST Ten-Year Interval
LR-N04-0089, Request for Changes to Technical Specifications, Containment Systems - Containment Cooling System
U-603640, Transmittal of Revision 8 to the Technical Specification Bases
RBG-46179, Revisions to the Technical Requirements Manual and the Technical Specification Bases
L-2003-224, Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments
RS-03-069, Supplemental Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power Operations
RS-03-044, Request for Amendment to Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program.
RBG-39971, Requests That NRC Issue 931118 Proposed Amend to TS 4.6.1.3.f,extending Surveillance Intervals to Support Current Fuel Outage Schedule by 940202 to Avoid Unnecessary Plant Shutdown.Approval Originally Requested by 940207
RS-03-026, Request for TS Changes Related to Primary Containment Isolation Instrumentation for the Isolation Condenser System
B18800, Response to Request for Additional Information on License Basis Document Change Request 3-6-02, Containment Isolation Valves
NRC-02-0084, Response to NRC Request for Additional Information Regarding the Proposed License Amendment for a One-Time Deferral of the Primary Containment Integrated Leak Rate Test
RBG-46052, License Amendment Request, Revised Full Scope Application of NUREG-1465 Alternative Source Term Insights
U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
NRC-02-0036, Proposed Technical Specification Change (License Amendment) - Response Time Testing
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
RS-02-047, Supplemental Information Supporting a License Amendment Request to Revise Plant System Requirements During Fuel Handling Based on Alternative Source Term
05000395/LER-1982-064, Forwards LER 82-064/03L-0.Detailed Event Analysis Encl
RA-20-0165, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl
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
NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
B16595, Application for Amend to License DPR-65,incorporating Various Compliance Issues Identified in TS
PLA-2853, Monthly Operating Repts for Apr 1987
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
NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
RBG-44354, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-458/97-17.Corrective Actions:On 971030,TS 3.6.1.2 Condition C Actions Were Entered
3F0988-18, Requests Establishment of mini-purge of Reactor Bldg to Reduce Worker Exposure to Radiation & Radioactive Matl & to Assure That Every Measure Taken to Improve Individual Personnel Safety.Insps Necessary
NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0
U-602565, Application for Amend to License NPF-62,implementing 10CFR50,App J-Option B
RBG-42272, Clarifies Intent to Match SR 3.0.2 Re Extensions to Surveillance Intervals Proposed in 951024 License Amend Request 95-21,to Generic Implementing Specs in NRC
RBG-42179, Requests Relief from Section XI,Subarticle-3420, Valve Leak Rate Test Requirements & That Valve Testing Be Performed in Accordance W/Ame/Ansi OMa-1988,Part 10, IST of Valves in LWRs Power Plants, Paragraph 4.2.2.Relief Request 80 Encl
RBG-42198, Provides Clarification Re 951024 LAR 95-21,changing TS 3.6.1.1 Through 3.6.1.3 Re Containment Sys,As Discussed in 951114 Telcon W/Nrc.Updated TS Changes for LAR 95-21 Encl
HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B
RBG-42084, Application for Amend to License NPF-47,consisting of LAR 95-21,changing TS 3.6.1.1 Through 3.6.1.3 Re Containment Sys & Notifies of Intent to Implement performance-based Containment Leak Rate Testing Program
ELV-03421, Provides Response to Violations Noted in Insp Repts 50-424/91-32 & 50-425/91-32 on 911124-1221.Corrective Actions Noted:Appropriate Log Entries Made to Document Occurrence
ST-HL-AE-5135, Application for Amends to Licenses NPF-76 & NPF-80,changing TS 3.6.1.2 for Clarification of Action Station as Submitted in 950525 Request for Exemption to 10CFR50 App J & Proposed Change to TS 3.6.1.1,3.6.1.2 & 3.6.1.3
ELV-01006, Application for Amends to Licenses NPF-68 & NPF-81,changing Tech Specs 3/4.6.1.7 & 4.6.1.2f Re Containment Ventilation Sys to Clarify Action Statement & Surveillance Requirements Per NRC Info Notice 88-073
AECM-84-0286, Forwards Rev 29 to Tech Spec Problem Sheets.Rev Transmitted Specifically as Update
2CAN049511, Application for Amend to License NPF-6,revising Spec 3.6.1.3 to Allow Entry & Exit of Containment Air Locks to Perform Maint on Air Lock Components
B15013, Application for Amend to License DPR-65,revising Tech Specs Surveillance Requirement 4.6.1.2.a to Permit Flexible Schedule for Containment Leakage Type a Testing
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
B14994, Application for Amend to License DPR-65,revising SR 4.6.1.2.d.Requests That NRC Process LAR on Emergency Basis & That NRC Exercise Enforcement Discretion from Action Statements for LCOs 3.6.1.1 & 3.6.1.2
HL-4663, Forwards Partial Revision to 940225 Amend Request,Resulting from Meeting W/Nrc & Resolution of Industry Generic Issues
NL-22-0757, Units 1 & 2, 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
NLS2023007, Technical Specification Bases Changes
PY-CEI-NRR-2133, Application for Amend to License NPF-58,requesting Implementation of App J,Option B,Performance-based Primary Containment Leakage Rate Testing Program for Type A,B & C Leak Rate Tests
RBG-46842, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
ST-HL-AE-2541, Responds to Violations Noted in Insp Rept 50-498/88-01. Corrective Actions:Procedure 1POPO2-SI-0002 Revised to Correct Forms 3,7 & 11 to Indicate Proper Handswitch Alignments for All Modes
W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program
3F1086-05, Responds to Violations Noted in Insp Rept 50-302/86-20. Corrective Actions:Nonconforming Operations Rept Generated to Document Incident & Provide for Evaluation of Reportability & DHV-111 Returned to Required Position
AECM-86-0247, Special Rept 86-002/0:on 860711,emergency Diesel Generator 12 Tripped During Routine Surveillance.Cause Unknown. Generator Examined & Returned to Svc.Investigation Continuing
LR-N06-0437, License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
3F1290-02, Responds to NRC Re Violations Noted in Insp Rept 50-302/90-32.Corrective actions:DHV-43 Manually Seated Using Handwheel
RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
3F0692-13, Provides Justification Re Request for Temporary Waiver of Compliance for TS 3.9.4 to Allow Administrative Controls to Be Utilized for Station Air Valves & Temporary Connection Air Valves
ELV-02102, Requests Waiver Compliance from Tech Specs 3.6.1.1,3.6.1.2 & 3.6.3 to Allow Testing of Check Valve 016
B14993, Requests Schedular Exemption from Requirements of 10CFR50, App J,Sections III.D.2(a) & III.D.3,providing Temporary Relief from two-yr Schedular Requirement Associated W/Type B & C Periodic LLRTs
RS-17-162, Radiological Emergency Plan Addendum Revision
NRC-13-0001, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
AECM-90-0135, Application for Amend to License NPF-29,revising 900427 & 0705 Applications Re Changes to Tech Spec Due to Addition of Alternate DHR & Addressing NRC Concerns Re Manual Realignment of LPCI Emergency Core Cooling Subsystems
L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006
05000354/LER-2023-001, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable
05000354/LER-1989-013-02, :on 890629,failure to Perform Required Local Leak Rate Testing on Hpci/Rcic Turbine Exhaust Vacuum Relief Piping Identified.Caused by Valves Not Being Included in Scope of Inservice Test Program
05000498/LER-1989-014-01, :on 890620,discovered That Maint Activity Performed on Essential Chiller 12C Rendered Standby Diesel Generator 13 Incapable of Being Tied to 4.16 Kv ESFs Bus. Caused by Improper Work Instructions
05000416/LER-1998-004-02, :on 980625,noted That Containment Isolation Valve Had Been Opened Simultaneously During Check Valve Repairs Contrary to Ts.Caused by Inadequate Work Practices. Will Revise Protective Tagging Sys Procedure 01-S-06-1
05000440/LER-1987-048, :on 870703,containment Fire Hose Reel Inboard/ Outboard Supply Isolation Valves Discovered in Open Position Since 870622.Caused by Procedural Deficiency.Integrated Operating Instructions Will Be Reviewed & Revised
05000440/LER-1987-062, :on 870828,RHR Head Spray Containment Isolation Valve Energized in Violation of Tech Spec 3.6.4.Caused by Personnel Error.Operator Involved Counseled Re Need for Greater Attention to Detail
05000352/LER-1987-022, :on 870609,two Penetrations Containing Testable O-ring Assemblies Not Included in Surveillance Test Procedures.Caused by Procedure Deficiency.Temporary Procedure Change Made
05000440/LER-1987-061, :on 870830,Tech Specs Violated When Inner Air Lock Door Not Maintained Closed W/Outer Air Lock Door Inoperable.Caused by Bushing Failure.Bushing Replaced & Design Change for Air Lock Door Initiated
05000302/LER-1986-009, :on 860629,reactor Containment Isolation Design Basis Violated.Caused by Failure to Update Procedure OP-417 W/Necessary Administrative controls.Short-term Instruction 86-35 Issued on 860630
05000352/LER-1986-031, :on 860617,containment Leakage Test Program Determined That Total Combined Leakage of Types B & C Tests Exceeded Allowable Leak Rate Limit.Caused by Normal Wear.New Valve Seats Installed
05000275/LER-1986-011, :on 860830,containment Side Door to Personnel Airlock Opened While Outer Atmosphere Door Open,Rendering Airlock Inoperable.Caused by Excessive Wear Due to Heavy Usage.Interlocking Device Repaired
05000352/LER-1987-010, :on 870326,surveillance Test Did Not Meet Tech Spec Requirements.Caused by Inadequate Local Leak Rate Surveillance Test Procedure.Shift Supervision Notified & Temporary Procedure Change Implemented
05000440/LER-1988-035, :on 880914,primary Containment Integrity Was Compromised for 30 in That Upper Containment Airlock Inner Door Seals Were Deflated W/Outer Door Open.Caused by Failure of Door Interlock.Engineering Evaluation Initiated
05000482/LER-1986-034, :on 860604,discovered That Handwheel Lock on Containment Isolation Valve Lf FV-96 Improperly Lockwired, Causing Valve to Be Inoperable.Caused by Personnel Error. Rept Incorporated Into Required Reading
05000414/LER-1986-005-03, :on 860417,discovered Leak Rate Retest Not Performed on Containment Isolation Valve Following Maint. Caused by Personnel Error.Personnel Counseled
05000446/LER-1999-001, :on 981226,identified That TS Surveillance for Containment Integrity Verification Was Not Performed.Caused by Personnel Error.Required Surveillance Was Performed & Applicable Procedures Were Revised.With
05000344/LER-1988-030, :on 880917,safety Injection Pump Inoperable Due to Mispositioned Svc Water Valve SW-237.Cause Undetermined. Performance of Locked Valve List Verification at More Frequent Intervals Will Be Evaluated
05000328/LER-1988-020, :on 880422,ERCW Containment Isolation Valves Did Not Pass Leak Rate Test.Caused by Improper Application of Valve Usage.Work Requests Initiated to Repair Valves & Components Cleaned
05000366/LER-1988-013, :on 880415,during Performance of Functional Test Procedure to Return Hydrogen Recombiner to Svc,Failure to Test Piping Violated Primary Containment Integrity.Caused by Personnel Error.Isolation Valves Closed
05000354/LER-1988-002-02, :on 880213,primary Containment Leak Rate Testing of Recirculation Sample Inboard Isolation Valve Overdue.Caused by Personnel Error.Event Will Be Reviewed as Stated When Preparing First Refuel Outage
05000498/LER-1988-002, :on 880105,discovered Failure to Perform Local Leakage Rate Testing on Containment Isolation Valves.Caused by Lack of Training Re Required post-maintenance Testing. Valves Retested & Personnel Counseled
05000354/LER-1988-002, :on 880213,primary Containment Isolation Valves Inoperable.Caused by Failure of Inservice Insp to Notify Control Room Personnel That Surveillance Overdue.Both Inboard & Outboard Valves Reworked
05000352/LER-1997-002, :on 970123,failed to Perform Required Visual Inspections of Blind Flanges.Caused by Misinterpretation of Surveillance Requirements.Visually Inspected Blind Flanges & Incorporated These Into Surveillance Tests
05000320/LER-1985-009-01, :on 851105,during Valve line-up for Processing Fuel Transfer Canal Water,Containment Isolation Valve DWC-V-099 Discovered in Open Position Since 851103.Caused by Personnel Error
05000482/LER-1996-015, :on 961023,failure to Comply with TS 3.6.1.1, Containment Integrity Occurred.Cause Under Investigation. TSC 033-85 Was Deleted & Removed from CR on 961112
05000454/LER-1985-075, :on 850801,equipment Hatch Personnel Airlock Leakage Rate Exceeded Tech Spec Limit.Caused by Procedural Inadequacy Leading to Deficient Testing Conditions.Local Leakage Rate Testing Procedures Revised
05000341/LER-1985-056, :on 850826,determined That Leak Rate Test Not Performed After Maint on Div II Thermal Recombiner on 850620.Leak Test on 850829 Indicated Excessive Leakage. Caused by Damaged Gasket.Gasket Replaced
05000320/LER-1985-007-01, :on 850702,containment Isolation Valve Found to Be Routinely Opened Since 840413 W/O Approved Procedure. Caused by Inadvertent Deletion of Section Permitting Valve Opening
05000369/LER-1992-010-02, :on 920916,discovered That Containment Structure Mechanical Penetration M-309 Developed Steam Leak on 840720.Caused by Design Deficiency & Equipment Failure. Station Problem Rept Initiated
05000315/LER-1985-016, :on 850412,w/RCS in Mode 3,vent Inside Containment Opened to Drain Header & Vent Outside Containment Opened to Drain Hxs,Creating Flow Path from Inside to Outside Containment.Procedure Revised
05000354/LER-1992-008-02, :on 920827,containment Penetration Test Isolation Valve Opened During Implementation of Troubleshooting Plan.Caused by Procedural Inadequacy. Troubleshooting Procedure to Be Modified
05000482/LER-1992-014, :on 920817,discovered That Two Containment Isolation Valves Not Verified in Locked Closed Position from 920123-0215.Caused by Operator Error.Surveillance Procedure Re Valve Listing Revised
05000413/LER-1984-030-02, :on 841129,containment Penetration Leak Rate Test Performed Improperly.Caused by Penetration Piping Being Completely Drained.Procedures Revised
05000334/LER-1985-001, :on 850107,investigation Determined That Outside Recirculation Spray Pump a Casing Drain Valve Open from Before 841223.Caused by Breakdown in Communication Re Use of off-log-only Procedure
05000368/LER-1995-007-03, :on 951122,manual Valves Not Having Been Secured in Closed Position Identified.Caused by Error in Procedure Change Mgt Process.Lessons Learned Training Provided & Procedures Revised
05000354/LER-1995-034, :on 951110,TS Violation Occurred Due to Failure to Follow Rod Sequence Control Sys Surveillance Procedures. Revised Procedures
05000354/LER-1995-035, :on 951120,failed to Lock Reactor Mode Switch in Opcon 5,missed SRM Surveillance & Missed Suppression Chamber Level Surveillance Due to Inadequate Procedures. Revised Procedures
05000354/LER-1995-031, :on 951110,plant Shut Down Due to Inability to Perform Surveillance 4.6.2.1,drywell to Suppression Chamber Pressure Decay Test.Vacuum Breakers Will Be Tested & Testing Methodology Will Be Revised
05000374/LER-1984-068, :on 840906,internal Bellows Seal of HPCS Discharge Relief Valve 2E22-F035 Failed.Caused by Hydraulic Forces on Seal Inherent in Sys Design.Cold Shutdown Achieved & Valve Repaired & Tested
05000498/LER-1992-002-01, :on 920124,discovered That Containment Integrity Requirements Violated Since 911018 Due to Leaking Handhole Cover on Secondary Side of SG 1C.Caused by Misinterpretation of Ts.Guidance Added to TS
05000413/LER-1995-003-01, :on 950727,failed to Perform TS Surveillance Due to Unanticipated Interaction of Sys.Reviewed All Penetrations to Determine Similar Situations Exist in Valves
05000413/LER-1995-003-03, :on 950727,failed to Perform TS Surveillance Due to Unanticipated Interaction of Sys.Reviewed All Penetrations to Determine Whether Similar Situations Exist in Valves Omitted from Containment Integrity Boundary
05000414/LER-1990-011, :on 900711,discovered That Tagout Record Sheet for Closure of Valve 2NC-61 Had Been Active.Caused by Design Deficiency Due to Lack of Documentation on Relief Paths. Valve 2NC-61 Reopened Prior to Mode 4
05000482/LER-1992-005, :on 920227,notified That Containment Penetration Vent & Drain Valves May Not Have Been Included in Surveillance Test Procedure STS GP-007 Due to Inadequate Attention to Detail.Subj Procedure Revised
05000374/LER-1984-030-01, :on 840615,HPCS Declared Inoperable as Result of HPCS Discharge Relief Valve 2E22-F035 Internal Bellows Seal Failure.Caused by Hydraulic Force on Seal.Valve Repaired & Tested Operational
05000373/LER-1983-133-03, /03L-0:on 831024,both Personnel Access Doors Opened at Same Time for About 90 S,Allowing Personnel to Exit Drywell.Personnel Could Not Open Outer Airlock Door Due to Slipped Cam.Caused by Two Loose Screws
05000374/LER-1991-006, :on 910321,primary Containment Integrity Declared Inoperable During Surveillance Testing.Caused by Procedural Deficiency.Operator Determined Cause of Dual Indication & Valves Closed
05000414/LER-1995-002-04, :on 950420,determined That Containment Integrity Would Not Be Ensured During Calibrations Involving Containment Pressure Sensing Transmitters.Caused by Procedural Inadequacy.Procedure Created
05000424/LER-1991-013-02, :on 911125,analyzer Pump Began to Unexpectedly Cycle on & Off,Resulting in Opening of Hydrogen Monitor Isolation Valves.Caused by Personnel Error.Shift Superintendent Counseled & Procedure Revised
05000482/LER-1991-011, :on on 910718,determined That Quarterly CCW Inservice Valve Test Not Completely Performed on 910514. Caused by Status Sheet Incorrectly Initialed to Signify Test Completed.Individual Counseled
05000353/LER-1991-013-02, :on 910717,condition Prohibiting Tech Specs Where Surveillance Requirement Not Met & Primary Containment Integrity Not Verified.Caused by Personnel Error.Procedures Revised
05000366/LER-1991-018, :on 910604,error Found in FSAR Results in Missed Tech Spec Surveillances.Caused by Error in Fsar. Local Leak Rate Penetration Test Performed & Applicable Surveillance Procedures Revised
05000395/LER-1983-084-03, /03L-0:on 830722,licensee Notified NRC Inspector That Surveillance Test Procedure 115.001 Did Not Adequately Address Tech Spec.Caused by Inadequate Procedure.Revised Procedure to Be Issued 830820
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
05000328/LER-1994-005-02, :on 940419,determined Containment Leak Rate TS Limits Exceeded.Caused by Failure of Relief Valve Bellows & Check Value Leaking Through Seat.Failed Valve Replaced.W/
05000324/LER-1979-028-03, /03L-0 on 790510:south Torus Hatch Was Open During Reactor Startup for Physics Testing Following Refueling Outage.Caused by Operating Procedure Deficiency.Procedures to Be Revised to Require Visual Insp
05000445/LER-1990-033, :on 900926,personnel Error Lead to Momentary Loss of Containment Integrity
05000456/LER-1994-003-05, :on 940311,as Found Integrated Leak Rate Test Failures Occurred.Caused by Preservice Const Deficiencies. Missing Caps on Emergency Hatch Concrete Vent Pipes Installed & Test Reperformed Satisfactorily
05000414/LER-1990-011-03, :on 900711,Tech Spec Requiring Operability of Containment Penetration Violated.Caused by Inappropriate Actions & Defective Procedure.Valve Repaired & Replaced & Personnel Trained Re Types of Sys Relief Paths
05000327/LER-1993-028, :on 931104,identified Containment Isolation Valves Not Verified Closed or Secured Due to Inadequate Engineering Practices.Subj Plug & Vent Valves Verified Closed or Plugged by Operations Personnel
NG-98-0052, Forwards Pages Omitted from Re Response to Questions on Section 3.6 of DAEC Improved TS Conversion
RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
AECM-90-0056, Application for Amend to License NPF-29,changing Tech Specs to Address Addition of Alternate DHR Sys & Manual Realignment of LPCI Emergency Core Cooling Subsystems During Plant Shutdown
05000346/LER-1981-062-03, /03L-0:on 811004,during Containment Integrity Monthly Test,Valve SA535 Found Open.Caused by Lack of Control.Valve Opened to Provide Station Air for Contractor Working in Room.Valve Closed & Tagged
05000346/LER-1978-051-03, /03L-1:on 780511,during Local Leak Rate Test, Containment Vacuum Relief Valve Cv 5076 Found to Have Excessive Leakage.Caused by Valve Wafer Not Properly Seated Against Valve Liner.Valve Repaired by Vendor
05000395/LER-2019-004, 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1
05000461/LER-1990-001, :on 900212,drywell Purge Sys Containment Penetration Failed Local Leak Rate Test.Caused by Failure to Remove Cosmolene from Surface of Valve Prior to Initial Installation.Valves Replaced
05000369/LER-1981-061, Forwards LER 81-061/03L-0.Detailed Event Analysis Encl
NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
05000320/LER-1980-048-03, /03L-0:on 801017,after Sampling a Core Flood Tank, Inner Containment Isolation Valve CF-V115 Failed to Close. Apparently Caused by Motor & Control Circuits Grounding Out, Induced by Water Leakage.Valve Closed & Deactivated
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
RA-15-019, Attachment 9 - EP-AA-1007, Revised Radiological Emergency Plan Annex Information for Peach Bottom Atomic Power Station
PY-CEI-NRR-1576, Application for Amend to License NPR-58,changing TS 3.6.1.2, Primary Containment Leakage & Revising as-found Value of Overall Integrated Primary Containment Leakage Rate.Request for Exemption Re Primary Containment Leakage Rate Also
05000366/LER-1980-138-03, /03L-0:on 801027,leakage on Torus Purge Inlet Outboard Isolation Valve 2T48-F324 Found Such That Test Vol Could Not Be Pressurized.Caused by Worn O Rings.Shaft & Housing for O Rings Cleaned.O Rings Replaced
LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
05000325/LER-1981-051-03, /03L-0:on 810422,investigation Revealed That 31- Day Surveillance Frequency for Verification of All Equipment Hatches Had Not Been Implemented.Caused by Oversight in Assessing Testing Requirements.Procedure Revised
05000327/LER-1980-100-03, /03L-0:on 800623,containment Isolation & Purge Exhaust Valves FCV-30-37 & FCV-30-40 Found to Have Excessive Leakage.Caused by Debris Under Seating Surface. Debris Was Blown Out & Valves Restested
05000344/LER-1989-023, :on 890918,determined That Tech Spec 3.6.1.1, Containment Integrity Violated When in Modes 1-4.Cause Appears to Be Combination of Procedural Inadequacies.Test 5-2 Will Be Revised
05000320/LER-1980-020-01, /01L-0:on 800522,during Containment Entry, Violation of Containment Integrity Occurred Via Bulkhead Makeup Valve E.Caused by Procedural Deficiencies.Procedures Revised
05000302/LER-1978-011-03, /03L-0:on 780201,during Mode 3 Operation,Primary Containment Integrity Not Maintained When Nitrogen Valve NGV-81 Open for 3-h 42 Minutes.Caused by Oversight of Tech Spec 3.6.1 1 Requirements.Personnel Instructed
L-2002-089, Application for Amendments to Revise TS to Incorporate Line Item Improvements Associated with Handling of Recently Irradiated Fuel Assemblies
05000325/LER-1980-018-03, /03L-0:on 800213,during Surveillance Tour,B Loop of Core Spray Was Found Draining from Torus After Being Placed Under Clearance for Maint.Caused by Open FO-10B Valve,Pump Vents & Drain valves.FO-10B Valve Was Shut
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 215
B16834, Application for Amend to License DPR-65,correcting Various TS Compliance Issues,Including Modifying Definition of Azimuthal Power Tilt,Changing Wording of SR 4.1.1.1.2 & Changing Applicability of TS 3.1.3.4
05000302/LER-1979-018-03, /03L-0 on 790301:inner Airlock Door Found Unlatched.Caused by Inadequate Latching Design.Corrective Action Will Be Determined Upon Results of Engineering Info Request
CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water.
TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements
LR-N990330, Application for Amends to Licenses DPR-70 & DPR-75,replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
05000272/LER-1998-007, :on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves Identified
LR-N980350, Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2
LR-N990252, Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.6.1, Containment Integrity, by Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
LR-N970298, Forwards Description of Proposed TS Changes Identified by Pse&G Which Do Not Impact Restart or Operation of Units
HNP-98-091, Application for Amend to License NPF-63,revising TS 3/4.6.1.3 to Be Consistent with NUREG-1431,rev 1 Std Tech Specs,W Plants, Dtd Apr 1995 & to Clarify Requirements for Locking Air Lock Door Shut
HNP-97-162, Forwards Response to Violations Noted in Insp Rept 50-400/97-04.Corrective Actions:Missile Shield Blocks Were Reinstalled on 970406 within Time Require by Action Statement
05000272/LER-1916-006, Regarding Technical Specification (TS) for Containment Integrity Not Met
05000400/LER-1987-014, :on 870314,three Pressure Gauges Installed, Placed in Svc & Opened on Three Drain Lines Whose Isolation Valves Considered Containment Isolation Valves in Violation of Tech Specs.Caused by Personnel Error
05000272/LER-1917-001, Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications
RS-17-164, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000316/LER-1978-087-03, /03L-0 on 781110:Containment Integrity Was Broken by Disassembling an NESW Check Valve While Reactor Plant Was in Mode 3.Early Start of Repair Has Been Reviewed by Personnel to Prevent Future Mistake
L-94-044, Forwards Rev 4 to Second Ten-Yr ISI Interval IST Program, Utilizing Testing Approach of Asme/Ansi OM-1987,Part 10
05000397/LER-1997-006, :on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for Sp
GO2-94-042, Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000298/LER-1917-004, Regarding Torus to Drywall Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function
05000389/LER-1989-004-02, :on 890605,leak Rate on Containment Penetration 10 Exceeded Allowance,Per Tech Spec 4.6.1.7.3. Caused by Personnel Error.Technical Manual Change Request Submitted
L-96-244, Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
L-96-245, Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
L-97-287, Verifies That Containment Structural Integrity & Containment Leakage Rates Are Acceptable by TS SRs 4.6.1.6 & 4.6.1.2, Respectively.Next Periodic ILRT Is Due Before May 2003. Basis of Util Decision Encl,For Info
BSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A
NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing
NMP2L2595, Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee
05000333/LER-2012-009, Regarding Containment Atmosphere Dilution (CAD) System Valves Misaligned for Ascension Into Mode 2
RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
TSTF-12-01, Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046)
05000298/LER-2011-007, For Cooper Nuclear Station, Regarding Primary Containment Lost Safety Function Due to Open Drywell Vacuum Breaker
05000311/LER-2011-001, Regarding 21SW122 Isolation Function Inoperable Greater than Allowed by Technical Specification
L-12-065, Submittal of Shield Building Root Cause Evaluation
L-02-094, Technical Specifications Bases Change Submittal
RS-07-118, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
RS-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
05000333/LER-2005-003, Re Plant Shutdown Due to Through-Wall Crack in Torus
JAFP-05-0102, Request for Approval of Relief Request No. RR-37. Alternative Test Per 10 CFR 60.55a (a)(3)(I) from 1998 Edition of ASME Section XI as Supplemented by the 1892 Edition ASME Section Xl Through 1992 Addenda for
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
05000316/LER-2004-004, Re Failure to Comply with Containment Integrity Requirements Specified in Technical Specifications 3.0.4, 3.6.1.1, 3.6.1.2 and 3.6.3.1
05000272/LER-2004-003, Regarding Completion of Plant Shutdown to Comply with Technical Specifications - 3.6.1.1 Containment Integrity
05000311/LER-2004-004, Regarding Technical Specification Required Plant Shutdown Following Loss of 2B 230-Volt Vital Bus
05000237/LER-2003-006, Regarding Torus Purge Valve Open in Conjunction with the Drywell Purge Valve in Mode 2
B18818, Response to a Request for Additional Information License Basis Document Change Request 2-14-01 Containment Isolation, Reactor Building Closed Cooling Water, & Service Water Surveillance Requirements
B18663, License Basis Document Change Request 3-6-02, Containment Isolation Valves
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RS-07-117, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
LR-N04-0343, Revised Request for Changes to Technical Specifications Containment Systems - Containment Cooling System
05000277/LER-2014-003, Regarding Containment Leakage Limit Exceeded Due to Through-Seat Leakage of Feed Water Check Valves
GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update
B18696, License Basis Document Change Request 2-17-02, Containment Systems
RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control
JSP-078-92, Application for Amend to License NPF-62,changing TSs to Delete Component Lists,As Recommended in Generic Ltr 91-08 & Deleting Reactor Vessel Specimen Withdrawal Schedule,As Recommended by Generic Ltr 91-01
A02456, Application to Amend License DPR-65,revising Tech Specs to Allow Startup & Power Operation W/One Inoperable Reed Switch Position Indicator Per Control Element Assembly Group
JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision
LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
B16240, Annual Repts for 10CFR50.59 PORV & SV Challenges Primary Coolant Specific Activity Analysis Occupational Radiation Exposure for 1996
GNRO-2011/00072, Technical Requirements Manual and Technical Specification Bases Update
NL-15-0820, Hatch, Units 1 and 2 - Emergency Plan, Revision 37
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times
JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
NL-21-0722, Units 1 and 2, License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates
05000354/LER-2023-001-01, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable
05000354/LER-2023-001-02, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable
CNL-25-041, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line.
05000302/LER-1981-031-01, /01T-0:on 810624,notification Was Received That Containment Isolation Valves Were Operating Less Conservatively than Vendor re-evaluation for safety-related Application.Caused by Inadequacy of Valve Operators
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
BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl
GO2-96-132, Requests Amend to Ts,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of Nhsc or Environ Assessment Provided in Rev a
05000328/LER-1988-018, :on 880330,improper Maint of Containment Integrity Resulted in Noncompliance W/Tech Spec.Caused by Lack of Available Regulatory Guidance Re Use of Threaded Caps During Const of Plant.Cap Design Changed
05000320/LER-1986-002-01, :on 860103,discovered Containment Isolation Valve DW-V-139 Open.Cause Not Identified.Valve Locked Closed.As Precautionary Measure,Double Valve Isolation Outside Containment Will Be Maintained
05000440/LER-1986-077, :on 861101,primary Containment Integrity Not Maintained in Support of Maint Work on CRD Mechanisms,Per Tech Spec 3.6.1.1.2.Caused by Personnel Error.Operator Counseled Re Reviewing Work Packages
05000373/LER-1984-059-01, :on 841002,HPCS Discharge Relief Valve Bellows Failed.Cause Undetermined.Hpcs Relief Valve Repaired
05000354/LER-1992-006-02, :on 920525,suppression Chamber Inoperable Due to Suppression Chamber to Drywell Vacuum Breaker Failures. Inoperable Vacuum Breakers Repaired & Bypass Leakage Surveillance Completed Satisfactorily
05000346/LER-1984-002, :on 840119,fuel Transfer Tube 1-1,drain SF69 Opened & Uncapped & Tube 1-2,drain SF68 Partially Opened & Uncapped.Caused by Defective Procedures.Capped Valves Reevaluated & Change Request Imposed
L-09-218, Submittal of Technical Specification Bases, Revision 7
RA-14-032, Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Page PBAPS 3-77 Through End
RA-14-032, Attachment 7: Discussion of Revision to the Radiological Emergency Plan Annex for Limerick Generating Station. LGS 3-70 Page LGS 3-155
JAFP-23-0060, Emergency Plan Document Revisions
JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change