RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-16-187, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
LR-N17-0188, Response to Integrated Inspection Report 05000272/2017003 and 05000311/2017003
L-2015-255, License Amendment Request Containment Vacuum GOTHIC Analyses and Conforming Changes
2CAN121303, Response to Request for Additional Information Adoption of Technical Specification Task Force (TSTF)-422
NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
L-2011-237, Supplemental Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Containment and Ventilation Issues
GNRO-2011/00043, Request for Additional Information Regarding Extended Power Uprate
RC-09-0134, Response to Request for Additional Information for Generic Letter 2004-02
W3F1-2006-0052, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation, Waterford Steam Electric Station, Unit 3
05000366/LER-1980-125-03, /03L-0:on 800824,during Control Room Panel Check, 2E32-F001B Valve Found to Have No Indicating Lights.Caused by Open Fuse in Valve Control Circuit.Circuit Integrity Verified & Control Fuse Replaced
RBG-38643, Forwards Response to NRC Re Violations & Proposed Imposition of Civil Penalty Noted in Insp Rept 50-458/93-11 on 930225-0330.Corrective Actions:Surveillance Test STP-057-0401 Performed,Verifying Operation of Interlocks
L-03-135, Withdrawal of the Containment Conversion Portion (Phase 2) of License Amendment Request Nos. 300 and 172
NOC-AE-03001487, Proposed Revised Change to Containment Purge Radiation Monitoring and Withdrawal of Proposed Change to Reactor Coolant System Leakage Detection Technical Specification
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
W3F1-2002-0005, Ses, Technical Specification Bases Update to NRC for Period September 1, 2002 Through January 15, 2002
0CAN098704, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/87-22 & 50-368/87-22.Corrective Actions:Procedure for Containment Control Revised to Include Instructions for Containment Bldg Pressurization
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
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
RBG-22398, Forwards for Review,List of Changes Util Requests to Be Included in Tech Specs Re Full Power Ol.Items Represent Corrections,Clarifications & Enhancements to Tech Specs.No Amend to Present Low Power License Sought
NOC-AE-000289, Forwards Response to RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions
NG-96-2322, Application for Amend to License DPR-49,converting Std TS Re NUREG-1433.Detailed Description & Justification for Proposed TS Amend Consists of 20 Vols & Summarized in Attachment 1
ST-HL-AE-4211, Forwards Proposed Revisions to Updated FSAR to Reallocate Margin to Address Large Break LOCA Analysis for Initial Containment Temp Assumptions
ST-HL-AE-5208, Submits Response to Request for Addl Info Re Proposed Special Test Exception
AECM-84-0286, Forwards Rev 29 to Tech Spec Problem Sheets.Rev Transmitted Specifically as Update
L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3
JSP-615-92, Application for Amend to License NPF-62,changing TS 3/4.7.1.1, Shutdown Svc Water Sys (Loops A,B & C) & TS 3/4.7.2, CR Ventilation Sys, to Allow Tensioning & Detensioning Reactor Pressure Vessel Head
05000344/LER-1982-007, Updated LER 82-007/01T-0:on 820514,during Review of Revised Containment DBA Analysis,Nonconservative Spray Modeling Error Identified in Model Used to Justify Tech Spec 3.6.1.4 Re Max Positive Containment Operating Pressure
W3P87-1147, Suppl to 870729 Application for Amend to License NPF-38, Consisting of Tech Spec Change Request NPF-38-62,revising Tech Spec 3.6.1.4, Containment Sys Internal Pressure to Include 1 Psig Max Containment Internal Pressure
W3P87-2006, Application for Amend to License NPF-38,revising Allowable Containment Pressure Operating Range Based on Reanalysis of Limiting Peak Containment Pressure Event (Main Steam Line Break).Fee Paid
W3P88-1213, Requests Temporary Waiver of Compliance W/Tech Spec 3.6.2.2 Re Containment Cooling Fans Which Need to Be Operable in Modes 1-4.Tech Spec Change Request Revises Tech Spec 3.6.2.2 to Allow Only Two Fans to Be Operable During Modes 1-4
W3P88-0078, Provides Addl Info Re Containment Isolation Valves Necessitating Tech Spec Change Request 72,per NRC 880413 & 14 Requests
U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval
PY-CEI-NRR-1934, Application for Amend to License NPF-58,proposing Extension for One Operating Cycle of Exception to LCO 3.0.4 as Applies to TS for MSIV LCS
RS-14-127, Response to Request for Additional Information Related to License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure
RBG-22535, Submits Addl Info Re Background of 851021 & 1105 Tech Spec Change Requests,In Response to Recent NRC Request.Smoke Detections in Zones SD-102 & SD-156 Unnecessary Due to Absence of safety-related Equipment
PLA-2776, Forwards 10CFR50.59 Rept Summarizing 1985 Approved Safety Evaluations for Determining Unreviewed Safety Question
2CAN079201, Application for Amend to License NPF-6,changing TS to Revise Containment Internal Pressure,Average Air Temp & Relative Humidity Limits in TS Figure 3.6-1 & Bases & Reduce Linear Heat Rate Limit in TS Figure 3.2-1
GO2-95-194, Forwards Response to NRC Re Violations Noted in Insp Repts 50-397/95-07 & 50-397/95-13.Corrective Actions: on-coming Operator Questioned CRS & Obtained Permission to Close Valve
B16641, Application for Amend to License DPR-65,reducing Max Allowed Value for Containment Pressure Specified in TS 3.6.1.4
B12627, Informs That Backup Protection Devices Will Not Be Installed at Plant Due to Util Belief That Existing Configuration Safe & Elimination of Original Commitment Does Not Constitute Unreviewed Safety Question.Safety Evaluation Encl
05000354/LER-1987-050, :on 871204,determined Surveillance Missed for MSIV Outboard Steam Sealing Gas Test Line Isolation Valve on 871111 Test.Caused by Personnel Error.Procedure for Tracking Surveillance Testing Reinforced W/Personnel
05000327/LER-1980-041-03, /03X-3:on 800430,sample Isolation Valves 1FCV-90-108,-109,-110,-114,-115 & -116 Closed.Caused by Isolation of Nonessential Control Air to Sample Valves. Control Air Restored & Valves Reopened
05000327/LER-1980-022-03, /03X-2:on 800318,sample Isolation Valves 1-FCV-90-108,109,110,114,115 & 116 Closed,Isolating Radiation Monitors.Caused by Isolation of Nonessential Control Air to Sample Valves.Valves Reopened
05000354/LER-1999-009, :on 990820,license Condition Violation Re Min FW Temp Limits Were Noted.Caused by Lightning Strike. Recovered & Restored Plant Sys Affected by Electrical Transient
05000382/LER-1987-009, :on 870317,discovered That Instrument Used to Determine Containment Internal Pressure Not Sufficiently Accurate.Caused by Design Deficiency.Calculational Methodology Substituted
05000416/LER-1986-016, :on 860417,error Discovered in Procedure That Caused Missed Isolation Time Measurement for Containment power-operated Isolation Valve on MSIV Leakage Control Sys. Caused by Requirement Inadvertently Deleted
05000327/LER-1983-166-03, /03L-1:on 831115,primary Containment Internal Pressure Relative to Annulus Increased Above 0.3 Psig.Caused by Operator Error.Containment Vented to Reduce Pressure & Relocation of Indicator Being Evaluated
05000354/LER-1995-016, :on 950708-09,SDC Bypass Event Occurred, Rendering SDC Mode of RHR Sys Inoperable Due to Procedural non-compliance & Inadequate Operator Knowledge,Skills & Training.Special Training on Event Conducted
05000327/LER-1984-009-01, :on 840128,high Radiation Alarm Actuated, Causing Containment Ventilation Isolation to Occur.Caused by Root Valve on Pressurizer Leaking Through Packing.Valve Backseated
05000395/LER-1983-107-03, /03L-0:on 830914,reactor Bldg Internal Pressure Dropped Below Tech Spec Min.Caused by Change of Ambient Temp.Reactor Bldg Minipurge Supply Activated to Return Pressure to within Limits
05000395/LER-1983-130-03, /03L-0:on 831124,containment Bldg Internal Pressure Was Negative 1.2 Psig.Caused by Personnel Error & Inadequate Procedure.Exhaust Fan Secured & Supply Fan Started.Operating Procedure Revised
05000328/LER-1983-166-03, /03L-0:on 831115,primary Containment Internal Pressure Relative to Annulus Increased Above +0.3 Psig. Caused by Personnel Error.Containment Vented to Reduce Pressure Below 0.3 Psid
05000346/LER-1994-004, :on 941014,discovered That Containment Hydrogen Purge Inlet Screen Not Installed.Suspect Screen Installed During Plant Const But Removed During Maint & Not Replaced. Screen Replaced During Ninth Refueling Outage
05000327/LER-1983-119-03, /03L-0:on 830910,containment Internal Pressure Limit for Annulus Pressure Exceeded.Caused by Normal Air Leakage Into Containment W/O Venting.Containment Pressure Returned to within Limit
05000389/LER-1983-053-03, /03L-0:on 830909,while in Hot Shutdown,Containment Pressure Exceeded 0.4 Psig Limit.Caused by Heatup & High Pressure.Pressure Released by Purge After Obtaining Waste Gas Release Permit
05000328/LER-1983-033-03, /03L-0:on 830307,containment Internal Pressure Limit of +.3 Psid Relative to Annulus Exceeded.Caused by Reopening of Annulus Vacuum Fan Exhaust Dampers.Containment Vent Performed
05000370/LER-1983-011-03, /03L-0:on 830427,PORV Block Valve 2NC-31B Declared Inoperable Due to Steam Leaking Past Shaft to Containment Atmosphere.Caused by Failure of Packing Gland Eye Bolts.Valve Closed & Actuator Deenergized
PY-CEI-NRR-1831, Emergency Application for Amend to License NPF-58,adding Exception to Provisions of LCO 3.0.4 as Applies to TS 3.6.1.4, MSIV Leakage Control Sys for Duration of Fifth Cycle of PNPP Unit 1 Operation
05000352/LER-1994-005, :on 841026,determined That Main Steam Valve Did Not Have Proper Seismic Interference Clearance Which Could Cause Electrical Fault.Caused by Installation Error.Mov Power,Control Cable & Conduit Were re-routed
05000458/LER-1994-002, :on 940111,containment Airlock Rendered Handle Locking Solenoid Mechanism & Interlock Inoperable.Caused by Personnel Error.Maint & Mgt Center Supervision Disciplined Concerning Inadequate Communications
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
NG-98-0052, Forwards Pages Omitted from Re Response to Questions on Section 3.6 of DAEC Improved TS Conversion
05000344/LER-1981-030, Forwards LER 81-030/03L-0.Detailed Event Analysis Encl
05000344/LER-1981-030-03, /03L-0:on 811202,during Review of Plant Problem Rept,Containment Pressure Indicators PI-10075 & PI-10076 Determined Not Reading Gauge Pressure as Indicated.Caused by Improper Design & Installation.Procedural Change Initiated
05000458/LER-1993-004, :on 930324,deficiency Discovered in Locking of Reactor Bldg Door.Caused by Lack of Understanding of TS Requirements for Locking Airlock Door.Operator Aids Posted & Permanent Locking Device Installed on Doors
05000366/LER-1981-074-03, /03L-0:on 810731,valve 2E32-F003K Failed to Operate When Cycled.Caused by Torque Switch Cam Limit Lobe Failing to Torque Motor Out When Closing,Causing Motor to Overheat.Switch & Motor Replaced
B134698, Provides Clarification Re Lowest Flow Acceptance Criterion for Hydrogen Recombiners Included in NRC SER Based on 891201 & 900119 Submittals
U-601572, Responds to NRC Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room
05000327/LER-1980-160-03, /03L-0:on 800926,containment Differential Pressure Re Annulus Exceeded Tech Spec Limits During RCS Heatup. Caused by Containment Atmosphere Heatup & Normal Control Air Leakage.Pressure Reduced by Venting
05000346/LER-1977-081-03, /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified
05000346/LER-1978-083-03, /03L-1 on 780720:containment vessel-to-annulus Differential Pressure Exceeded Tech Spec Limit by 1 Inch. Purge of Containment Bldg Commenced.Caused by Inadequate Monitoring of Pressure Increase by Shift Check
HNP-96-064, Application for Amend to License NPF-63,proposing to Implement Change to Bases for TSs 3/4.6.1.4 & 3/4.6.1.6 Revising Calculated Peak Pressure for MSLB Event
05000400/LER-1993-003, :on 930628,discovered Possible Design Deficiency in Containment Vacuum Relief Sys Due to Inconsistent Interpretation of Ts.Reduced Containment Vacuum Relief Automatic Actuation Setpoint
05000530/LER-1992-002-02, :on 920722,RCS Leakage Monitor Declared Inoperable to Investigate Sampling Discrepancy.Inleakage Due to Cracked Gasket Was Periodically Diluting Gaseous Sample. Monitor Repaired & Returned to Svc
GO2-96-172, Submits Comments on Draft SE of Proposed Improved Tech Specs
GO2-93-207, Informs That on 930726,control Room Received Main Steam Leakage Control Board W Trouble Alarm (S2-2.2) Due to Power Lost to Power Panel E-PP-7BC.Blown Fuses in Regulating Transformer That Feeds E-PP-7BC Replaced
05000335/LER-1998-009, :on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With
05000461/LER-2016-001, Regarding Continuous Containment Purge Exhaust Fan Trip Due to Invalidated Assumptions in Work Planning Resulted in an Unanalyzed Condition of Primary to Secondary Containment Differential Pressure & Safety
2CAN031303, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2 ‘‘Change in Technical Specifications End States (CE NPSD-1186)
BSEP 05-0055, Response to Request for Additional Information - License Renewal (NRC TAC Nos. MC4639 and MC4640)
BSEP 05-0050, Response to Request for Additional Information - License Renewal
2CAN050404, Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application
PNO-II-93-043, on 930831,steam Leak from SG Drain Line Caused Personnel Injury & Ice Condenser Actuation.Plant Cooldown Initiated,Per TS 3.6.1.4.Plant Now in Cold Shutdown.Licensee Planning to Repair Steam Leak & Inspect Ice Condenser
L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States
05000416/LER-1988-008, :on 880208,MSIV Leakage Control Sys Dilution Air Inlet Found Sealed W/Tape.Cause of Event Uncertain.Tape Removed,Walkdown Insp of Inboard & Outboard MSIV Subsystems Conducted & Warning Sign Placed at Inlet
05000327/LER-1983-018-03, /03L-0:on 830201,containment Internal Differential Pressure Exceeded 0.3 Psig Relative to Annulus Pressure. Caused by Failure of Emergency Gas Treatment Sys Suction Damper to Open Causing High Vacuum in Annulus
05000328/LER-1983-017-03, /03L-0:on 830201,at 100% Power,Containment Pressure for Annulus Discovered to Be Greater than +0.3 Psi. Caused by Normal Air Leakage Into Containment W/O Venting. Personnel Reminded to Vent Containment
05000327/LER-1983-040-03, /03L-0:on 830319,containment Internal Pressure Exceeded Tech Spec Limits.Caused by Normal Air Leakage Into Containment W/O Venting.Personnel Reminded to Request Vent Packages on More Timely Basis
05000458/LER-1993-023, :on 930922,discovered Improper Engagement of Containment Airlock Door Handwheel Locking Mechanism Due to Inadequate Testing & Acceptance Criteria Supporting Plant Mod.Interlock Levers Modified