GNRO-2016/00062, License Amendment Request (LAR) for One Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements
L-2015-255, License Amendment Request Containment Vacuum GOTHIC Analyses and Conforming Changes
GNRO-2015/00026, Application to Revise Technical Specifications for Permanent Extension of Type C Leak Rate Testing Frequency and Reduction of Type B and C Grace Intervals
CNL-15-020, Supplement to the Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) and Response to NRC Requests for Additional Information
SBK-L-13225, Submittal of Changes to the Seabrook Station Technical Specification Bases
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
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
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
SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System
GNRO-2011/00077, Report of 10CFR50.59 Evaluations and Commitment Changes July 1, 2010 Through June 30, 2011
RA-15-019, Attachment 7 - EP-AA-1008, Revised Radiological Emergency Plan Annex Information for Limerick Generating Station
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
RS-10-039, License Amendment Request to Administratively Revise Technical Specifications
SBK-L-10074, License Amendment Request 10-02
SBK-L-06127, Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change
05000346/LER-1980-063-03, /03L-1:on 800823,safety Features Actuation Sys Indication Panel for Damper HV5442 Was Inoperable.Caused by Blown Fuse in Control Circuit.Fuse Replaced & Sys Returned to Svc
LR-N19-0004, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements
05000325/LER-1980-053-03, /03L-0:on 800607,during Normal Reactor Bldg Tour During Refueling,Inner & Outer Doors of 50-ft Air Lock Found Open.Caused by Burned Coil in Inner Door Interlock Solenoid. Coil Replaced & Air Lock Access Restored
RBG-46226, License Amendment Request for One-Time Extension of the Drywell Bypass Test Interval
GNRO-2003/00059, Supplement to Amendment Request for a One-time Extension of the Integrated Leak Rate and Drywell Bypass Test Interval
GNRO-2003/00035, Technical Specification Bases Update to the NRC for Period Dated 06/06/2003
RBG-46052, License Amendment Request, Revised Full Scope Application of NUREG-1465 Alternative Source Term Insights
GNRO-2002/00030, License Amendment Request, Corrections and Clarifications to Certain Requirerments and Information
RS-02-013, Response to Request for Additional Information Regarding Risk Aspects of Inclined Fuel Transfer System License Amendment Request for Clinton Power Station
05000395/LER-1982-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl
B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
B12443, Application for Amend to License NPF-49,changing Tech Spec 3.6.1.4 to Allow Plant Operation Above Limit of Figure 3.6-1 for Containment Sys Air Partial Pressure.Safety Evaluation Encl.Fee Paid
B17413, Application for Amend to License DPR-65,revising TS Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1,3.6.5.1,3.7.6.1 & 3.9.15 as Result of Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA
B16344, Application for Amend to License DPR-65,relocating SR for Attaining Negative Pressure in Enclosure Bldg from TS 3.6.5.1, Enclosure Bldg Filtration Sys, TS 3.6.5.2, Enclosure Bldg Integrity
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
PLA-2280, Responds to NRC Re Violations Noted in Insp Repts 50-387/84-18 & 50-388/84-22.Corrective Actions: Surveillance Procedures Changed to Include Verification Signatures When Required
RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage
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
B14820, Application for Amend to License DPR-65,revising TS 4.6.5.1.b.2,4.6.5.1.c,4.7.6.1.c.2,4.7.6.1.d,4.9.15.b.2 & 4.9.15.c to Permit Carbon Samples to Be Tested in Accordance W/Astm Std D3803-89 Vs ANSI N509-1976
PY-CEI-NRR-0469, Forwards List of Tech Spec Changes to Accompany Full Power Ol,Representing Minor Editorial Corrections,Clarifications & Enhancements.Justifications & Proposed marked-up Tech Spec Pages Also Encl
RS-03-013, Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program
05000352/LER-1989-027, :on 890423,Tech Specs Violated.Caused by Mispositioned Reactor Vessel Boundary Valve During Performance of Local Leak Rate Test Causing Draining of 400 Gallons of Reactor Vessel Inventory
05000352/LER-1989-043, :on 890628 & 29,refuel Floor HVAC Sys Isolated Due to Inadequate Differential Pressure Between Outside & Refuel Floor Atmospheres.Caused by Procedural Deficiency. Secondary Containment Isolation Switches Reset
05000352/LER-1989-014, :on 890216,isolation of Refuel Floor Secondary Containment & Initiation of Standby Gas Treatment Sys,Esf Occurred.Caused by Boiler Malfunction.Auxiliary Operator at Auxiliary Boiler Encl Restored Three Boilers
05000352/LER-1989-024, :on 890407,craftsman Removed Packing from Wrong Valve Creating Potential for Draining Reactor Vessel.Caused by Failure to Interpret Info Provided on Maint Request Form. Leak Isolated
05000346/LER-1997-011, :on 970825,emergency Ventilation Sys Rendered Inoperable by Maint on Room Isolation Valve Occurred.Caused by Misinterpretation of Tech Spec.Preventive Maint Activities Revised
05000410/LER-1987-002, :on 870109,trains of Standby Gas Treatment Sys Automatically Initiated.Caused by Failure to Adequately Review Markup.Operators Cleared Red Markup & Restored Power to Inlet Dampers
05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
05000346/LER-1986-018, :on 860407,during Stringing of Temporary Instrumentation Cables,Fire/Negative Pressure Breached. Caused by Inadequate Technical Supervision.Test Engineer Released & Test Leader Suspended W/O Pay
05000410/LER-1986-012, :on 861128 & 29,series of Related Automatic Initiations of Standby Gas Treatment Sys Occurred.Caused by Clogged Filters & Personnel Error.Approx 50% of First Stage Filters Replaced & Training Mod Initiated
05000346/LER-1986-005, :on 851221,discovered Inadequate Axial Seam Overlap on 93 as-installed Bisco Boot Seals.Caused by Lack of Clarity in Bisco Procedure Sp 505.New Installation Procedure MP 1700.29 Approved
05000458/LER-1988-009, :on 880301,unsealed Fire Barrier Penetration Discovered in Control Bldg Fire Wall on 70 Ft Elevation. Caused by Open Hatchway Between Fire Areas & Unqualified Penetration Seal.Fire Watch Established
05000458/LER-1988-010, :on 880325,surveillance Requirement for Tech Spec 3.6.5 Not Properly Performed While Unit Operating. Caused by Inadequate Procedure Review.Procedure Revised & Review Performed on Operations
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000328/LER-1988-003-02, :on 880119,discovered Ice Buildup in Flow Passages of Ice Condenser Due to Sublimation.Cause Not Determined.Ice Condenser Defrosted & Special Maint Instruction Performed
05000341/LER-1996-014, :on 961004,Div 2 UHS cross-connect Valve de-energized.Caused by Loose Set Screw on Valve Operator Spline bushing.Cross-connect Path Established & Valves Will Also Be Modified W/Set Screw Recess
05000373/LER-1996-010-06, :on 960829,determined Conditions Outside of Design Basis.Caused by Inadequate Standards for TS Clarifications.Implemented Development of TS Clarifications & Evaluates TS Interpretations
05000341/LER-1985-013, :on 850428,secondary Containment Integrity Not Established During Core Alterations for CRD Friction Test. Caused by Personnel Misunderstanding Applicability of Requirement.Procedure Change Initiated
05000346/LER-1996-003, :on 960328,discovered Discrepancy in SRs for Testing of Absorbent Matl in Evs.Caused by Deficiencies in Testing of nuclear-grade Activated Charcoal.Submitted Emergency Amend Request to Revise SRs
05000353/LER-1992-006-02, :on 920621,operations Personnel Observed Loss of Reactor Enclosure Secondary Containment Causing Blowout Panel to Actuate.Caused by Design Defienciency.Mod to Raise Unit 1 Setpoint Completed
05000327/LER-1984-019, :on 840307,analysis of Ice Condenser Weights Indicated One group-row Average Basket Weight Below Design Limit of 1,080 Lb.Caused by Normal Sublimination of Ice. Mod to Tech Specs Initiated
05000353/LER-1991-012-04, :on 910627,two Floor Drain Plugs Associated W/ Reactor Enclosure,Removed Rendering Enclosure Inoperable. Caused by Personnel Error.Maint Personnel Received Training & Counseling
05000353/LER-1991-012, :on 910627,two Floor Drain Plugs Associated W/Reactor Enclosure (Re) Secondary Containment (Sc) Removed, Rendering Re Sc Inoperable.Caused by Personnel Error. Corrective Actions Included Counseling
05000346/LER-1983-065-03, /03L-0:on 831117,Channel 1 Essential Conduit 38609A-1-1/2 Inch Inadequately Supported for Approx 30 Ft. Caused by Original Const Installation Error.Addl Supports Installed by 830909
05000395/LER-1983-106-03, /03L-0:on 830904,post-accident Hydrogen Analyzer Panel a (XPN-7215A) Declared Inoperable When Calibr Rotometer Ball Bearing Indicator Lodged in Pressure Regulator.Caused by Personnel Error
05000387/LER-1983-150-03, /03L-0:on 831022,while at 100% Power,Reactor Bldg Heating & Ventilation (H&V) Heaters 1E252A,B,C & D Failed to Energize.Manual Initiation Unsuccessful.Zone 1 H&V Sys Shut Down.Caused by Disengaged Pneumatic Line
05000353/LER-1991-012-02, :on 910624,two Normally Locked in Place Floor Drain Plugs Associated W/Reactor Encl Secondary Containment Removed by Maint Personnel.Caused by Personnel Error. Personnel Retrained & Counseled
05000352/LER-1991-012, :on 910508,reactor Encl Overpressurized & Blowout Panel Opened Due to Failure of C Reactor Encl HVAC Supply Air Fan.Fan Power Supply Breaker Trip Coil Replaced & Satisfactorily Tested
05000324/LER-1983-029-03, /03L-0:on 830220,routine Surveillance During Plant Operation Revealed Audible Evidence of Airflow Through Both Doors of Reactor Bldg 50-ft Elevation.Caused by 1 1/2 Inch Diameter Hole in Outer Door.Hole in Door Sealed
05000325/LER-1983-010-03, /03L-0:on 830120,routine Surveillance Revealed Water Leaking Into Reactor Bldg at 17-ft Elevation Via Secondary Containment Penetration/Fire Barrier Seal R1-1-049.Caused by Degradation Due to Exposure to Rainwater
05000369/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl
05000352/LER-1991-001-01, :on 910107,3 of 4 Reactor Encl HVAC Supply & Exhaust Air Fans Tripped,Resulting in High Positive Air Pressure.Plant Shutdown on 910108.Caused by Failure of Discharge Dampers to Open Fully.Coil Replaced
05000328/LER-1982-087-03, /03L-0:on 820709 & 13,one Point of Ice Condenser Ice Bed Temp Exceeded 27 F.Caused by Loss of Cold Air Through Uncovered Floor Drains & Unseated Inlet Doors & Humidity Entering Through Open Drain Line.Temp Reduced
05000370/LER-1993-006-03, :on 930830,secondary Side Steam Generator Leak Caused Increase in Lower Containment Pressure,Resulting in TS Required Shutdown & ESF Actuation Due to Failure to Follow Procedure.Injection Pipe Cap Installed
05000327/LER-1993-001, :on 930124,Unit 1 Ice Bed Temperature Recorder in MCR Declared Inoperable.Caused by Ineffective Communication.Appropriate Personnel Involved W/Event Have Been Counseled
05000325/LER-1982-006-03, /03L-0:on 820205,during Secondary Containment Integrity Verification,Flow Rate Could Not Be Achieved within Tech Specs Limit.Caused by Failure to Maintain Greater than 25-inch Vacuum Due to Penetration Air Leaks
05000346/LER-1982-004-03, /03L-0:on 820122,door 108 to Detergent Waste Drain Tank & Pump Room Found Open.Caused by Worker Disregarding Sign on Door.New Signs Will Be Added to Elaborate Requirement to Close Door
05000346/LER-1981-076-03, /03L-0:on 811130 & 1201,Door 306 Was Found Open. Caused by Installation Error.Closing Mechanism Adjusted to Exert Larger Force on Door
05000324/LER-1983-005-03, /03L-0:on 830110,both Personnel Secondary Containment Airlock Doors,Located on 50-ft Elevation Northeast Wall,Found Inoperable Due to Excessive Leakage Past Seals.Caused by Damaged Sealing Gaskets
05000328/LER-1983-107-03, /03L-0:on 830805,Group 1 Row 1 Average Ice Basket Weight Found Below Min.Caused by Sublimation of Ice in Crane Wall Area.Addl Ice Added
05000317/LER-1990-008, :on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308
05000440/LER-1990-003, :on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement Implemented
05000443/LER-1990-008, :on 900209,latching Mechanism for Door Entering Containment Encl Bldg Failed,Rendering Emergency Air Cleanup Sys Inoperable.Plant Cooldown Initiated,Latching Mechanism Repaired & Door Returned to Svc
05000328/LER-1981-107-03, /03L-0:on 810831,while in Mode 3,on Two Occasions, Ice Condenser Lower Inlet Doors Were Opened Slightly & Ice Bed Temp Exceeded 27 F.Caused by High Differential Pressure. Doors Closed & Temp Returned to Normal
05000327/LER-1981-082-03, /03L-0:on 810719,one Location of Ice Condenser Ice Bed Was Discovered Exceeding 27 F.Caused by Numerous Opening of Doors While Work Was Being Performed.Doors Closed & Unnecessary Traffic Suspended.Chiller Packages Adjusted
05000325/LER-1981-005-03, /03L-0:on 810101,during Normal Surveillance, Discovered Secondary Containment 20 Ft Elevation Inner Air Lock Door Inoperable Due to Missing Gasket Sealing Matl. Caused by High Personnel Traffic.Gasket Replaced
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
05000324/LER-1981-005-03, /03L-0:on 810113,during Normal Surveillance, Secondary Containment 20-ft Elevation Outer Air Lock Personnel Door Found Not Sealing.Caused by Heavy Personnel Traffic Through Door.Gasket Repaired
05000346/LER-1977-082-03, /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned
05000346/LER-1977-094-03, /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested
05000346/LER-1978-004-03, /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened
05000324/LER-1979-081-03, /03L-0:on 790926,both Doors to Reactor Bldg Breezeway Airlock Could Be Opened Simultaneously.Caused by Loose Door Position Solenoids Preventing Interlock Feature from Working.Lock Washers Installed to Ensure Tightness
05000316/LER-1991-009-01, :on 911112,ice Condenser Flow Passage Insp Did Not Include Entire Flow Area Assumed in Analyses Presented in Updated Fsar.Caused by Inadequate Definition of TS Insp Requirements.Test Procedures Revised
GO2-92-148, Requests Withdrawal of Request for Waiver of Compliance from TS 3.6.5.1.a to Facilitate Testing of Movs,Per Generic Ltr 89-10,per .Problems W/Test Equipment Cannot Be Resolved within Time Frame to Support Testing
GO2-92-130, Requests Waiver of Compliance from TS 3.6.5.1.a Re Secondary Containment Integrity & 3.6.3.a Re Primary Containment Isolation Valves,Per Generic Ltr 89-10
05000397/LER-1987-003, :on 870331,operations Shift Supervisor Notified That Two Spare Conduit Penetrations Between Reactor Bldg & Radwaste Bldg Open.Caused by Inattention to Detail by Operations Shift Supervisor.Caps Replaced
05000354/LER-2016-004, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment
05000353/LER-2015-004, Regarding Valid Manual Actuation of the Primary Containment Isolation System
05000353/LER-2013-003, Regarding Inoperable Reactor Enclosure Secondary Containment Integrity Due to Open Airlock
05000352/LER-2012-003, Regarding Valid Manual Actuation of the Primary Containment Isolation System Due to Ventilation System Trip
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
RS-07-075, Withdrawal of Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program
RS-06-151, Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program
RS-03-185, Additional Information Supporting the Request for Amendment to Technical Specifications 3.6.5.1, Drywell, and 5.5.13, Primary Containment Rate Testing Program
05000315/LER-2002-008, Failure to Complete Unit Shutdown as Required by Technical Specification 3.6.5.1
05000316/LER-2003-004, From Cook, Unit 2, Regarding Weight of Ice Basket Below Minimum Allowed in TS 3.6.5.1
GNRO-2003/00029, One Time Extension on Integrated Leak Rate Test & Drywell Bypass Test Interval
05000315/LER-1990-004-01, :on 900508,reactor Operator Inadvertently Started Containment Recirculation Fan Instead of Hydrogen Recombiner During Surveillance Test.Caused by Inadequate Work Practice.Condenser Restored
05000315/LER-1990-004, :on 900508,inadvertent Operation of Wrong Control Switch Occurred Due to Personnel Error
RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
05000328/LER-1988-003, :on 880119,discovered Ice Buildup in Flow Passage of Ice Condenser.Caused by Failure to Convert Original Design Requirements Into Verifiable,Repeatable Surveillance Requirements.Condenser Defrosted
05000387/LER-1984-024, :on 840422,unit Operation Continued Beyond Time Limit Specified in Tech Spec 3.6.5.1 W/Reactor Bldg Ventilation Zone I cross-connected to Zones II & Iii. Procedural Changes Implemented
05000324/LER-1983-010-03, /03L-0:on 830119,during Plant Operation,Both Doors of Reactor Bldg 20-ft Elevation Personnel Air Lock Opened Simultaneously.Caused by Misalignment of Inner Door Due to Normal Wear Preventing Proper Bolt Engagement
05000346/LER-1982-056-03, /03L-0:on 821104,breaker BF114 Tripped,Causing Loss of Power to F12 Series Motor Control Ctrs.Caused by Ground in Jockey Fire Pump Motor When Pump Seized.Pump Rebuilt & Motor Replaced
05000387/LER-1984-006, :on 840125,discovered That Performance of Weekly Source & Intermediate Range Monitors W/Unit in Mode 5 Constitutes Core Alteration.Core Alterations Prohibited Per Tech Specs.Tech Spec Change in Progress
L-09-218, Submittal of Technical Specification Bases, Revision 7
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