L-2017-100, License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program .
L-2016-204, Response to Request for Additional Information 7 Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval
L-2016-172, Response to Request for Additional Information Regarding License Amendment Request 242, Changes to Snubber Surveillance Requirements, Snubber Testing Program Plan - Fifth Inspection Interval
L-2016-128, License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps
RC-16-0035, (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B
L-2016-012, Application for Technical Specification Change to Remove the 10-Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents
PLA-4061, Forwards Summary Rept of Safety Evaluations Approved During Period from 920101-921231 for SSES Unit 1 & 2
L-83-241, Final Deficiency Rept 83-007 Re High Pressure Safety Injection Pump Bearing Bracket Drain.Initially Reported on 830318.Lines & Valves Will Be Removed & Replaced.Deficiency Not Reportable Per 10CFR50.55(e)
L-2015-022, Supplement to License Amendment Request 229, Application for Technical Specification Change Re Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Progam
L-2015-040, Submittal of Fifth 10 Year Interval Inservice Inspection (ISI) Program Plan
L-2014-266, Response to NRC Technical Specifications Branch Request for Additional Information Regarding License Amendment Request No. LAR-229
RC-13-0069, Request Relief from ASME Code Requirements in VCSNS 4th Ten Year Inservice Inspection Interval
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
L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps
L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 3; Technical Specifications Bases Markups for Information Only
LR-N09-0295, Units 1 and 2, Supplement to License Amendment Request S09-06, Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components
LR-N09-0218, Unit 2 - License Amendment Request (LAR) S09-06 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
SBK-L-08005, License Amendment Request 07-04 Application for Amendment to Delete Post-Maintenance Testing Surveillance Requirement for Containment Isolation Valves
05000528/LER-1995-011, :on 951018,identified Procedural Deficiency W/Msiv & FWIV ISTs Due to Personnel Error.Verified Operability of MSIVs & FWIVs
RC-18-0118, (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange
LR-N07-0224, Reply to Notice of Violation EA-07-149 Issued on 08/14/2007
RC-06-0204, Response to NRC Questions Regarding Response to Generic Letter 96-06
LR-N06-0394, Inservice Testing (IST) Program - Third Ten Year Interval
RBG-32215, Provides Currently Identified Outage & nonoutage-related Activities to Update NRC of Util Licensing Activities in Order of Priority
NOC-AE-06002040, Technical Specifications, Bases Control Program
2CAN030602, License Amendment Request, Proposed Technical Specifications to Remove Reactor Coolant System Structural Integrity Requirements
05000272/LER-1995-005, :on 950508,eight Occurrences Revealed Lift Settings of Pressurizer Code Safety Valves on Both Units Out of Required Tolerance.Caused by Testing Intrument Error. Counseled Personnel Involved
05000272/LER-1994-008, :on 900828,determined That Several Channel Functional Testing for Both Units May Have Been Performed Late Due to Personnel Error.Surveillance Procedure Has Been Revised
PMNS20191124, Pre-Submittal Meeting with Exelon Generation Company to Discuss a Proposed License Amendment Request to Revise Technical Specification 4.0.5 for Limerick Generating Station, Units 1 and 2
05000498/LER-1993-018, :on 930707,discovered Remote Position Indication Verification Test for SI Sys Accumulator Vent & Header Valves Had Not Been Performed in 2 Yrs Due to Change to IST Plan
LR-N04-0299, Inservice Inspection Program Relief Requests S1-RR-04-V01 and V02
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
L-03-146, License Amendment Request Nos. 315 and 188
RC-03-0159, License Amendment Request - LAR 03-1864, Surveillance Requirement 4.0.5 & Associated Bases
W3F1-2003-0031, Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments
W3F1-2003-0015, License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval
RC-03-0016, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
W3F1-2003-0002, Technical Specification Bases Update to the NRC for the Period October 1, 2002 Through January 7, 2003
L-02-077, License Amendment Request No. 179
NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals
RBG-38068, Forwards Revised Response to NRC Re Violations Noted in Insp Rept 50-458/92-26 on 920705-0815.Corrective Actions:Addended Instructions to Velan Valve Co Manual Received on 920901 & Incorporated Into Util Vendor Manual
NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval
NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904
NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
1CAN069803, Forwards Relief Requests 1-98-001 & 1-98-002 Re Insps Performed During Second ten-yr ISI Interval at ANO-1,which Ending 970601
RBG-30380, Application for Amend to License NPF-47,relocating Requirements for Tech Spec 3/4.7.4, Snubbers to Tech Spec 4.0.5 & NRC Approved Rev 2 to Inservice Insp Plan
RBG-30880, Forwards Response to Request for Addl Info in Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Attachments a & B Provides Info on Inservice Insp Program
NRC-98-0096, Withdraws Request for Extension of Surveillance Interval for TS 4.0.5,as Enclosed in Encl 20 of .Enclosed TS Pages Reflect Withdrawal & Administrative Changes
RBG-25917, Application for Amend to License NPF-47,extending Surveillance Interval to First Refueling Outage Scheduled to Begin on 870915.Fee Paid
B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports
BSEP-97-0386, Forwards Amended Rept Cover Page for Form NIS-1 & Amended Form NIS-2 Rept Pages Which Include Info Re RHR Sys Head Spray Line Mod
0CAN088613, Responds to Violations Noted in Insp Repts 50-313/86-15 & 50-368/86-15.Corrective Actions:Blank Flange Installed on Line,Procedure Revised & OSHA Tags Will Be Modified to Reflect Date of Installation
RBG-29023, Requests Meeting W/Nrc During Wk of 881031 to Discuss Encl Agenda Items Re Proposed Changes to Tech Specs 3.8.1.1, AC Sources - Operating, 3.74, Snubbers & License Item 2.c(4) Re Seismic Qualification of CRD Hydraulica Controls
CY-99-027, Annual Rept for 10CFR50.59, for Jan-Dec 1998.With
B17764, Application for Amend to License NPF-49,deleting Reference to ASME Code Paragraph Iwv 3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger Contained in TS 4.4.6.2.2.e
BSEP-97-0504, Requests Approval for Bsep,Units 1 & 2,to Use Alternative to Vibration Testing Requirements of ASME BPV Code,Section XI & Asme/Ansi Operations & Maint Stds,Part 6, IST of Pumps in LWR Power Plants, IAW 10CFR50.55a(a)(3)(ii)
BSEP-97-0534, Requests Approval to Use Alternative Exam Requirements for Reactor Pressure Vessel Closure Stud Number 19 & Associated Bushing.Util Intends to Use Proposed Alternative for Remainder of Second ten-yr Inservice Insp Interval
BSEP-97-0459, Requests Approval to Use Alternative Requirements for ISI Delineated in ASME Section XI Code Case N-535.Alternative Is Needed to Extend Third Period of Second ten-yr ISI Interval to Coincide W/End of Bsep,Unit 1,refueling Outage 11
B16930, Requests One Time Relief from Requirements of 10CFR50.55A(f) for Performing Required IST of Certain Class 2 Components IAW ASME Section XI for Millstone Unit 3.Approval Requested to Support Mode 4 Operations Scheduled for Jan 1998
B17428, Requests Relief from Requirements of 10CFR50.55a(f) for Performing Required IST of Certain Class 3 Components IAW ASME Section XI for Mnps,Unit 3
B17108, Requests One Time Relief from Requirements of 10CFR50.55a(f) for Performing Required in-service Test of Certain Class 1 Components IAW ASME Section XI
B17468, Requests Relief from Performing Inservice Volumetric Exams of Inaccessible Portions of RPV flange-to-shell Weld,Per 10CFR50.55a(g)
U-601217, Responds to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Revised Inservice Exam Program Plan Encl
NRC-88-0084, Deletes Commitment Made in to Change Actuator on RCIC Valve F012,in Response to IE Bulletin 85-003.Design Change to RCIC Sys Will Be Implemented During Local Leak Rate Test Outage to Remove Power to RCIC Valve F012
B15064, Requests Relief from Performing Volumetric Exam of Inner Radius of SG Main Steam Nozzle
2CAN088502, Application for Amend to License NPF-6,clarifying Tech Spec Re Adequate Flow Path from Discharge of Sodium Hydroxide Addition Pump to Containment Spray Pump Discharge.Flow Requirement Changed to 13 Gpm.Nshc Involved
NOC-AE-00278, Requests Enforcement Discretion from Provisions of TS 4.0.5 That Apply to Inservice Testing Requirements of Section XI of ASME BPV Code for Containment Isolation Valves
NOC-AE-000278, Requests Enforcement Discretion for Provisions of TS 4.0.5, as TS Applies to Inservice Testing Requirements of Section IX of ASME Boiler & Pressure Vessel Code for Containment Isolation Valves.Supporting Info,Encl
NOC-AE-000281, Requests Enforcement Discretion from TS 4.0.5,as TS Applies to Inservice Testing Requirements of Section XI of ASME Boiler & Pressure Vessel Code for Containment Isolation Valves.Supporting Info,Encl
NOC-AE-000280, Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code
ST-HL-AE-2109, Forwards Appeals Statements Re Proposed Tech Specs Rejected by Nrc.Rereview of Info & Incorporation in Proof & Review Tech Specs Requested
ST-HL-AE-1867, Forwards Justification for Proposed Tech Specs Identified for Further Comment or Resolution During 861117-21 Site Visit.Pending NRC Agreement,Revs Will Be Included in Future FSAR or Fire Hazards Analysis Rept Amend
1CAN059607, Forwards Proposed TS Changes Extending Surveillance Test Interval for Reactor Trip Breakers,Reactor Trip Modules & Electronic Trip Relays
1CAN089605, Requests Relief for ASME Relief on ANO-1 Core Flood Nozzle Examinations
RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves
B15783, Provides Response to Violations Noted in Insp Rept 50-336/96-04.Corrective actions:pre-job Briefings Ensure Workers Understand Job Scope Prior to Beginning Work Including Work Procedures Involved
1CAN069602, Forwards Relief Request 96-001 for Application of Alternative Insp Approach for ASME Class 1 B-D pressure- Retaining full-penetration nozzle-to-vessel Welds & Nozzle Inner Radius Sections in SGs
B15475, Requests Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components Per ASME Section XI for Facility.Isi Program Relief Requests IR-20 & IR-22 Encl
3F0684-17, Responds to NRC Re Violations Noted in IE Insp Rept 50-302/84-14.Corrective Actions:Enhanced Inservice Testing Program Will Be Available in Control Room for Implementation by 841031
BSEP-95-0422, Forwards Rev 0 to Rept of 1994-1995 ISI at Brunswick Steam Electric Plant Unit 1
RBG-41636, Provides Addl Info Re Valve Relief Request VRR-71
ST-HL-AE-5077, Application for Amend to Licenses NPF-76 & NPF-80,revising LCO 3.4.2.2 & Table 3.7-2 of TSs by Relaxing Lift Setting Tolerance of Pressurizer Safety Valves from +1% to +2% & MSSV from +1% to +3%
NRC-95-0019, Forwards Response to NRC Re Violations Noted in Insp Rept 50-341/95-02.Corrective Actions:Valves Disassembled & Inspected Per Procedure 47.000.13, Pep Check Valve Insp Procedure
BSEP-94-0518, Forwards Amended Pages for NIS-1 Rept Re in-service Insp Program
RBG-34-927, Corrects Typos in 910411 Application for Amend to License NPF-47,changing Tech Specs 4.0.5,3.4.3.1 & 3.4.3.2 Per Generic Ltr 88-01 Re Inservice Insp of Piping Susceptible to IGSCC
BSEP-94-0358, Forwards Rev 0 to Rept of 1992 Through 1994 ISI at Brunswick Steam Electric Plant Unit 2
RBG-34-790, Forwards Revised TS 4.0.5,3.4.3.1 & 3.4.3.2 Re Unidentified Drywell Leakage Sump Flow Monitoring,Per Generic Ltr 88-01 & Discussions W/Nrc.Util Accepts Original Generic Ltr Guidance
B14918, Application for Amend to License NPF-49,relaxing Lift Setting Tolerance for Pressurizer Safety Valves & MSSVs
BSEP-94-0285, Submits Results of Insp Re Core Spray Spargers & Associated Piping,Per IE Bulletin 80-13
HL-1446, Application for Amends to Licenses DPR-57 & NPF-5 Revising Tech Specs Re Generic Ltr 88-01, NRC Position on IGSCC Austenitic Stainless Steel Piping
BSEP-94-0150, Forwards Rept of 1991-1994 ISI at Brunswick Steam Electric Plant Unit 1, Rev 0,per TS 4.0.5 & ASME Boiler & Pressure Vessel Code,Section XI
RBG-40684, Responds to NRC Re Violations Noted in Insp Rept 50-458/94-10.Corrective actions:re-examined Two Welds
RBG-40630, Responds to Violations Noted in Insp Rept 50-458/94-06. Corrective Actions:Procedure Upgrade Program Initiative Underway
B14705, Responds to IR 50-336/93-19.Corrective Actions:Missing Brace Replaced & Radiation Monitor Procedures Will Be Revised as Necessary by 940131
ULNRC-02925, Special Rept 93-05:on 931020,valid Diesel Generator B Failure Occurred Due to Intermittent Speed Switch Opening Field Flashing Current Limiting Resistor.Surveillance Tests Currently Performed at Least Once Per 31 Days for DG B
RBG-39796, Application for Amend to License NPF-47,revising Applicable Tech Specs for one-time Extension Re Valve Leak Rate Testing
W3P89-3090, Responds to Violations Noted in NRC Enforcement Action EA 89-069 & to Civil Penalty.Corrective Actions:Standing Instruction Issued to Provide Instructions to Operators on Testing Requirements for Appropriate Pumps W/Fixed Lines
W3P88-1800, Responds to Violations Noted in Insp Rept 50-382/88-19. Corrective Actions:Operating Procedure OP-4-020 Revised to Change Sequence in Which Operator Responds to Bypassed & Inoperable Status Indication Sys
PY-CEI-NRR-1473, Submits Schedule for Response to NRC SER on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
PY-CEI-NRR-1918, NPP,940101-1231 Annual Rept
PY-CEI-NRR-1756, Forwards Annual Rept of 10CFR50.59 Safety Evaluations for 1993
NOC-AE-13002954, Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191
L-2015-284, Inservice Inspection Program, Fifth Ten Year Interval, Response to Request for Additional Information for Relief Request No. 3
B16647, Requests Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Section XI for Unit 3
1CAN069703, Requests Withdrawal of Previously Submitted Relief Requests 96-003 & 96-004.New Relief Request 96-003 for Alternative to Use Id Intiated UT Exam Approach for Subject Welds,Encl
RC-18-0089, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping
L-2010-122, Proposed License Amendment, Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections
BSEP-83-3317, Responds to NRC Re Violations Noted in IE Insp Repts 50-324/83-30 & 50-325/83-30.Corrective Actions: Procedure Revised to Require Using Position Indications on Motor Control Ctr or Observation of Valve Stem Travel
BSEP-97-0277, Application for Amends to Licenses DPR-62 & DPR-71, Clarifying TS 4.0.5.f Re Use of NRC Staff Approved Alternatives to Recommendations of GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping
L-2004-008, Proposed License Amendment to Revise Technical Specifications Surveillance Requirements 4.0.5
B17113, Informs That Second 120-month Interval of Unit 3 IST Program Began 980207 & Will Extend Through Apr 22,2006. Revised Commitment,Encl
05000336/LER-1998-025, Forwards LER 98-025-00,documenting Condition Discovered at Mnps,Unit 2,on 981111.Commitments Made by Util,Encl
0CAN038607, Responds to Violations Noted in Insp Repts 50-313/86-02 & 50-368/86-02.Corrective Actions:Independent Qa/Qc Organization Established to Ensure Insp of Anchor Bolts & Emergency Feedwater Pump Surveillance Will Be Revised
RBG-40771, Submits Interim Relief Request Re one-time Temporary Relief Extending Test Frequency & Postponing Testing Required by ASME
PY-CEI-NRR-1368, Forwards Rev 3 to Pump & Valve Inservice Testing Program Plan
05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open
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
L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers
05000368/LER-1989-010, :on 890425,discovered That Valve Stroke Surveillance Test for LPSI Sys & Refueling Water Tank Had Not Been Performed.Caused by Personnel Incorrectly Indicating Tests as Already Performed
05000454/LER-1998-011-01, :on 980409,integral Attachment Welds Were Not Inspected IAW ASME Code Due to Deficient ISI Program Plan. Cause of Event Unknown.Byron Site Engineering & Operation Dept Evaluated Operability Issues
05000498/LER-1989-010-01, :on 890327,discovered That post-maint Stroke Time Test of Charging Pump Recirculation Valve Not Performed.Caused by Personnel Error.Night Orders Issued Re Importance of Operability Tracking Log
05000302/LER-1989-002, :on 890101,discovered That Five Valves Could Not Be Tested in Closed Direction Due to Configuration of Check Valves & Piping.Caused by Personnel Error.Mod to Allow Testing of Valves Being Developed
05000369/LER-1989-005-02, :on 890309,charging Pump Recirculation Valves Not Being Tested,Per Inservice Test Requirement.Caused by Inappropriate Action.Performance Personnel Submitted Rev to Inservice Test Submittal
05000338/LER-1998-003-02, :on 980804,noted That Ten Svc Water Pipe Supports Had Been Inspected During First ISI Interval.Caused by Personnel Error.Completed Changes to Insp Isometric Drawings & Changes to ISI Program
05000366/LER-1987-017-02, :on 871119,determined HPCI Sys Not Functioning Correctly in Automatic Mode.Caused by Defective Amplifier Card & Solder Joint Due to Equipment Aging.Card Replaced, Joint Repaired & Controller Amplifier Calibr
05000483/LER-1998-007, :on 980722,noted Failure to Verify Integrity of Balancing Devices on Psvs Per TS 4.0.5.Caused by Personnel Not Being Aware That Subject Psvs Had Balancing Devices.Will Continue to Test & Refurbish Valves Offsite
05000458/LER-1987-020, :on 860606 & 1129,post-maint Exercise Tests Missed on ASME Valves 1E21*AOVF006 & 1B21*AOVF032B, Respectively.Caused by ASME Valve Repair/Replacement Program Deficiencies.Plant Procedures Revised
05000382/LER-1998-013, :on 980701,IST Valve Surveillances Were Missed. Caused by Inadequate Processing of Info Transferred Between Operations Procedure Group & Programs Engineering.Procedure Revised
05000482/LER-1987-045, :on 871002,determined That on Four Occasions Between 861118 & 1207,ASME Boiler & Pressure Vessel Code Piping Not Properly Pressure Tested Following Repair.Caused by Inadequate Procedure.Procedures Revised
05000423/LER-1998-027, :on 980416,determined That Unmonitored Flowpaths Existed for Diesel Fuel Oil Transfer Pumps During IST Testing.Caused by Program & Process Re Deficiencies. Review of Past Surveillance Results Conducted
05000339/LER-1987-011-02, :on 870916,surveillance Tests for Obtaining Bearing Temps on Quench Spray Pumps a & B Not Performed. Caused by Inadequate Scheduling Controls.Tests Placed on Periodic Test Scheduling Sys
05000373/LER-1997-028, :on 970618,missed RHR Sys Increased Frequency Surveillance Resulted in Operation to Be Outside of TS Requirements Due to Personnel Error.Improved Procedures Governing Station Surveillances
05000423/LER-1998-017, :on 980227,3SIL*V15 Testing Was Contrary to TS 4.0.5 Requirements.Caused by Program & Process Deficiencies. Submittal of Relief Request to Allow Extension of Disassembly & Insp Interval for 3SIL*V15 Was Submitted
05000382/LER-1997-023, :on 970708,EDG Fuel Sys Surveillance Was Missed Due to Failure of Personnel to Determine Intended Start & End Dates for SR 4.8.1.1.2.h.2 Interval.Submitted Application for Emergency Amend for Removal of SR
05000423/LER-1997-044, :on 970701,missed TS Surveillance of ESFAS Purge Isolation Instrumentation Occurred.Cause of Missed TS Surveillance Was Not Including Condition Surveillance Triggering Mechanisms in Cooldown.Ts Change Prepared
05000413/LER-1998-003-01, :on 980218,omission in Retest Manual Leads to Failure to Perform Required Retest Prior to Restoring Ci Valves to Svc.Retest Manual Will Be Updated to Reflect Specific TS Requirements for Ci Valves
05000423/LER-1998-021, :on 980318,discovered That Several Manual Valves & Check Valve Tests Were Not Included in IST Program. Caused by Lack of Clear Documentation.Satisfactorily Tested & Included Reported Valves in IST Program
05000423/LER-1998-011, :on 980218,failed to Adequately Test Turbine Driven Auxiliary Feedwater Pump.Caused by Inadequate Interface Among Organization.Tdafw Pump Will Be Tested
05000423/LER-1998-020, :on 980320,identified That Daily Channel Check of Radioactive Liquid Effluent Waste Neutralization Sump Monitor Had Not Been Performed.Caused by Poorly Written Procedure.Revised Implementation Documents
05000423/LER-1998-010, :on 980211,failed to Meet TS Definition of Analog Channel Operational Test of Unit 1 Main Stack Noble Gas Activity Monitor.Caused by Inadequate Verification of Compliance W/Unit 3 Ts.Procedures Will Be Revised
05000483/LER-1987-010, :on 870528,discovered That RHR Check Valves Not Tested as Required by Tech Spec 4.0.5.Caused by Personnel Error.Relief Requested for Testing Approved & Personnel Counseled
05000413/LER-1987-019, :on 870501,two Work Requests Were Discovered Failing to Specify Retest Requirements.Caused by Personnel Failure to Specify Retest Requirements on Implementation Plan.Incident Reviewed W/Appropriate Personnel
05000400/LER-1987-003, :on 870113,cooldown Initiated Due to Inoperable motor-driven 1A-SA Auxiliary Feedwater Pump.Caused by Assembly Error During Initial Installation of Pump.Flow Test Frequency Changed & Pump Repaired
05000325/LER-1997-009-02, :on 970714,missed Increased Frequency IST Requirement Was Discovered.Caused by Failure of IST Program. Enhancements to IST Program Procedures & Review of Recently Completed IST Surveillance Tests
05000414/LER-1987-005-01, :on 870202,steam Generator 2D Blowdown Containment Isolation Valve Failed to Meet Stroke Time. Caused by Mgt/Qa Deficiency Resulting in Erroneous Tech Spec Interpretation.Interpretation Deleted
05000275/LER-1986-008-01, :on 860415,flow Control Valve Surveillance Test Interval Exceeded.Caused by Personnel Error.Alert Status Board Used to Increase Emphasis on Updating & Validation of Surveillances
05000323/LER-1985-027-01, :on 851106,surveillance Test Interval of Tech Specs 4.0.5,4.6.3.3 & 4.0.2 Exceeded When Full Stroke Test Not Performed on Valve FCV-678.Caused by Personnel Error. Personnel Counseled
05000373/LER-1987-011-01, :on 870307,HPCS Water Leg Pump Discharge Check Valve Failed to Close on Reverse Flow.Caused by Surface Irregularities on Valve Seat.Valve Repaired
05000382/LER-1999-003-02, :on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With
05000416/LER-1987-004, :on 870227,operations Personnel Discovered Delinquent Condensate & Refueling Water Storage & Transfer Sys Valve Operability Surveillance.Caused by Personnel Error.Surveillance Completed on 870227
05000327/LER-1986-031, :on 860714,discovered Inadequate Procedures for Visual Local Stroke Timing of ASME Section XI Valves.Caused by Improper Preparation & Review of Implementing Procedures. Procedures Will Be Revised
05000395/LER-1997-005, :on 971024,failure to Perform ASME Section XI Code Surveillance Test at Increased Frequency Noted.Caused by Personnel Confusion.Review Was Performed to Determine If Procedural Guidance Was Clear Enough
05000336/LER-1998-025-01, :on 981111,noted That Several Check Valves Had Not Been Tested IAW ASME Section XI Criterion.Caused by Inadequate Design Basis Flow Requirement Specifications for IST Check Valves.Applicable IST Sps Will Be Revised
05000275/LER-1984-038, :on 860415,during Surveillance Test Review, Discovered That on 841015,interval for Performing Valve Stroke Timing Test of 10% Atmospheric Dump Valves Exceeded. Caused by Procedural Deficiency.Test Completed on 850106
BSEP-97-0480, Requests Approval to Use ASME Section XI Code Case N-547 as Alternative to ASME Boiler & Pressure Vessel Code Requirements for ASME Code Class 1,2,3 Components,Including Supports.Basis for Request & Commitments Provided
05000445/LER-1999-001-01, :on 990510,discovered That Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures.Caused by Less than Adequate Procedures.Revised Circuit Testing Procedures
05000354/LER-1998-007-02, :on 981009,standby Liquid Control Pump Inoperability Was Noted Due to Incorrectly Performed Ist. Caused by Personnel Error.Revised Test Procedure. with
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
05000336/LER-1998-020-01, :on 980929,noted SI Recirculation Header Piping Components Did Not Fully Satisfy ISI Requirements.Caused by Lack of ISI Test Program Ownership.Revised Applicable SI Leakage Test Procedure
05000382/LER-1987-031, :on 871021,containment Atmosphere Purge Isolation Valves 103 & 205 Exceeded Required Stroke Time Surveillance.Caused by Inadequate Administrative Controls. Procedures Adequately Revised
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
05000369/LER-1988-020-02, :on 880912,actuator Disconnected from Valve Stem at Actuator to Valve Stem Coupling.Caused by Mgt Deficiency Due to Poor Planning/Scheduling by Operations. Operations Personnel Manually Opened Valve
05000302/LER-1988-011, :on 880422,discovered That Inservice Testing Program Quarterly Valve Stroke Testing Only Partially Completed in First Quarter 1988.Caused by Defective Procedure.Master Surveillance Plan Revised
05000369/LER-1988-006-02, :on 880328,nuclear Svc Water Sys Isolation Valve Not Tested Following Maint Per Tech Spec 4.0.5.Caused by Personnel Error.Signs Affixed to ESF Valves to Inform Personnel of Required Testing Following Maint
05000338/LER-1998-004-01, :on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With
05000339/LER-1988-019, :on 880407,surveillance Test for Steam Generator Surface Sample Line Outside Containment Isolation Valve Not Performed within Interval Allowed by Tech Specs. Caused by Personnel Error.Program Modified
05000458/LER-1985-054, :on 851127,vibration Discovered in Alert Range for Standby Svc Water Pumps 1SWP P2B,P2C & P2D & LPCS Pump 1E21 PC001.Caused by Personnel Error.Personnel Trained on Use of Green Sheet
05000338/LER-1998-003, :on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With
05000344/LER-1988-005, :on 880331,required Test Interval for Chilled Water Return Valves Exceeded.Caused by Personnel Error. Plant Engineering Test 9-4 Will Be Revised by 880630 to Provide Improved Guidance on Scheduling Tests
05000354/LER-1998-005-03, :on 980810,discovered That Two Nitrogen Gas Supply Check Valves to B hydrogen-oxygen Analyzer Were Not Being Tested.Caused by Missed Ist.Ist Data Base Is Being Reviewed to Assure Completeness & Accuracy.With
05000338/LER-1988-015, :on 880322,discovered That RHR Pumps Not Tested During Steam Generator Tube Rupture Outage.Caused by Administrative Error.Station Deviation Rept Submitted to Responsible Dept to Reschedule Missed Test
05000413/LER-1997-005-01, :on 970623,violation of TS 4.0.5 Was Determined.Caused by Inadequate Surveillance Procedure. Affected Check Valves Were Successfully Tested for Reverse Flow Prevention
05000336/LER-1997-024-02, :on 970619,violation of TS 4.0.5,ASME Section XI Surveillance Requirements Was Determined.Caused by Misinterpretation & Wrong Assumption.Appropriate Procedure Will Be Revised
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
05000498/LER-1988-012, :on 880129,limiting Value for Stroke Time on Valve CV-FCV-0205 Found Omitted from Inservice Test Plan. Caused by Inadequate Administrative Control.Temporary Procedure ITSP03-CV-0001 Corrected Deficiency
05000498/LER-1988-011, :on 880127,nonperformance of Scheduled Surveillance Test on Essential Chilled Water Pump 11B Discovered.Caused by Inadequate Control of Test Packages. Procedure Rev Underway
05000346/LER-1978-091-03, /03L-0:on 780815,svc Water Sys Valve Test Notrmed Performed within Required Time Limit.Caused by Personnel Misinterpreting Surveillance Test Schedule.Test Schedule Computer Program Modified,Alleviating Confusion
05000454/LER-1992-006-07, :on 920728,discovered That Pump Discharge Check Valves in Component Cooling & RHR Sys Not Being Tested,As Required by GL 89-04.Caused by Personnel Error.Affected Valves Backflow Tested W/No Problems Noted
05000295/LER-1997-009-01, :on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training
05000369/LER-1986-005, :on 860207,during Insp Exit Interview, Determined That Containment Sump Isolation Valves 1NI-184B & 1NI-185A Not Visually Inspected at Least Once to Verify Remote Position Indication
05000275/LER-1985-036, :on 851119,discovered That Safety Injection & Charging Pump Suction Crosstie Valve Surveillances Not Performed Since 850814.Caused by Personnel Error.Test Performed
05000369/LER-1985-032-01, :on 851018,QA Surveillance Revealed That Chemical & Vol Control Sys Valves 1NV-223 & 2NV-223 Not Partially Stroked.Caused by Lack of Relevant Procedures. Partial Stroke Requirement Will Be Deleted
05000416/LER-1985-035, :on 850911,four motor-operated Valves & Two Drain Line Check Valves of MSIV Leakage Control Sys Not Tested Per Tech Specs 4.6.1.4.6 & 4.0.5.Caused by Delay in Issuing/Administering Procedure
05000416/LER-1985-049, :on 851222,review of 850914 Quarterly Surveillance Revealed That Valve Isolation Time Greater than Tech Spec Limit & Criteria Erroneously Marked Acceptable. Caused by Personnel Error
05000275/LER-1985-037, :on 851030 & 1101,missed Surveillances of Containment Spray Pumps Occurred.Caused by Engineer Failing to Increase Surveillance Test Frequency When Pumps Reached Alert Range
05000336/LER-1997-005-02, :on 970204,inservice Test Instrumentation Did Not Meet Ansi/Asme Chapter XI Requirements.Caused by Inadequate Administrative Structure for IST Program. Procedure to Administer IST Program Was Implemented
05000295/LER-1997-002-01, :on 970117,containment Isolation Valves Were Not Tested Prior to Leaving Cold Shutdown.Caused by Mgt Deficiencies in TS Implementation Process.Containment Isolation Valves Will Be Verified Tested Prior to Mode 4
05000354/LER-1995-033-01, :on 951114,TS Surveillance Requirement Implementation Deficiencies Occurred.Caused by Lack of Documentation of Annunciation for Previous Surveillances. SDV Bypass Logic Were Satisfactorily Tested
05000528/LER-1985-045, :on 850703,insp & Tests of ASME Code Class Component Not Reviewed within 96 H.Caused by Failure to Keep Engineers Appraised of Testing.Engineers Now Placed on Distribution List for Test Schedules
05000387/LER-1985-029, :on 850910,inservice Insp Surveillance Requirements of Tech Spec 4.0.5 Not Performed within Required Time Frame.Caused by Plant Engineering Group Error. Surveillance Completed
05000373/LER-1996-019-04, :on 961210,RHR Sys Containment Spray Isolation Valves Not Tested IAW ASME Section XI Requirements.Caused by Personnel Error.Procedure LOS-RH-Q2 Revised to Test CS Isolation Valves IAW IST Program
05000423/LER-1996-050-01, :on 961211,chill Water Pump Suction Pressure Gauges (3HVK-P126A & 3HVK-P126B) Did Not Meet Instrument Range Requirements.Caused by Inadequate Administrative Structure for IST Program.Procedure Change Implemented
05000295/LER-1996-011-01, :on 960327,missed Inservice Testing Requirements for 1AOV-BD0008 & 1A0V-S18870A Resulting from Deficient Procedure.Procedures Revised to Address post-maint Testing
05000413/LER-1996-008-01, :on 950307,closure Response Time Was Exceeded for MSIV 1SM1,B Train.Caused by Spurious Failures of B Train Exhaust Solenoid Valve for 1SM1.Valves Used in Pnuematic Controls for Unit 1 Have Been Replaced
05000374/LER-1996-006-08, :on 960918,Unit 2A & 2B RHR SW Pumps Not Tested Per ASME Section XI Due to Human Performance Error. Tested RHR SW Pumps IAW Special Test LST-96-069 in Full Compliance W/Asme/Ansi Part 6
05000423/LER-1996-032-01, :on 960910,HPSI Rv Piping Hydrostatic Test Was Found to Be non-compliance W/Asme Code Due to Personnel Error.Performed Test at Required Test Frequency
05000334/LER-1981-029-01, /01T-0:on 810325,discrepancy Noted Between Plant Mod Manual & Tech Spec 4.0.5 During Review of Inservice Insp Requirements.Caused by Misinterpretation of NRC Endorsement of ASME XI Code as Authorization to Invoke Tech Spec
05000443/LER-1992-023, :on 921112 & 16,three safety-related Components,Within Scope of IST Program,Not Tested Prior to Entry Into Mode 4.Caused by Personnel & Procedure Error. Using Proper Documentation Will Be Stressed
05000443/LER-1992-016, :on 920904,determined That Results for 920904 & 05 MSSV Setpoint Test,Indicated That Nine MSSVs Outside Acceptance Criteria in TS 3.7.1.1.Caused by Metallurgical Bonding.Six of Nine MSSVs Reset
05000354/LER-1996-033, :on 951114,two Events Occurred Due to Identification of TS Surveillance Test Inadequacy.Caused by Ineffective Procedures.Tssip Review Will Be Completed
05000423/LER-1996-024-02, :on 960712,IST of Stop Check Valve in Steam Supply to Turbine Driven AFW Pump Was Missed Due to Programmatic Weakness.Completed Insp of Motor Operated Stop Check Valve (3MSS*MOV17D)
05000327/LER-1996-008-01, :on 960709,failed to Perform Quarterly Backseat/Closure Test on Five Check Valves.Caused by Personnel Error.Test Procedure Written & Performed on Subject Check Valves
05000425/LER-1992-012-02, :on 920729,determined That Interval from Previous Quarterly ASME Valve Stroke Time Testing to 920719 Testing Exceeded Allowable Interval.Caused by Procedure Inadequacy.Procedure 00404-C Revised
05000498/LER-1996-002-01, :on 960507,failure to Meet Requirements of Tech Specs Occurred.Caused by Inattention to Detail During Documentation & Review of Testing Results.Feedback from Event Given to Individuals Involved
05000336/LER-1996-012-01, :on 960228,SIS Drain Stop Valves Failed to Meet Functional Requirements of Ts.Caused by Personnel Error & Inadequate Retest Requirements.C/A:Valve 2-SI-618 Modified & Safety Related Solenoid Valves Inspected
05000317/LER-1992-006, :on 920623,noticed That Valve Found in Alert Range Not Placed in Supplemental Test Program for Monthly Testing.Caused by Personnel Error.New Set of Administrative Procedures Scheduled for Implementation
05000498/LER-1992-006-01, :on 920318,discovered That All Four Auxiliary Feedwater Flow Control Valves in Closed Position Following Reactor Trip on 920314.Caused by Inattention to Detail. Valves Opened & Reactor Trip Procedure Revised
05000352/LER-1992-013, :on 920624,determined That RHR HX Failed Heat Transfer Capacity Test,Per Generic Ltr 89-13.Caused by HX Fouling & Leaking RHR HX 1B Bypass Valve.Restricting Orifice Removed to Allow Increased Flow
05000334/LER-1984-013, :on 841024,cooling Water Pump Declared Inoperable.Caused by Flow Instrument Out of Calibr.Test Procedure Modified to Meet ASME Requirements
05000443/LER-1992-004, :on 920325,discrepancy Identified W/Manner in Which Valve Closure Stroke Time Testing Performed for 20 Valcor solenoid-operated Valves.Caused by Design & Testing Inadequacies.Design Change Implemented
05000346/LER-1992-003, :on 920323,discovered That Component Cooling Water Pump 2 Placed in Svc on 920319 W/O Performing Deferred Quarterly Surveillance Test.Caused by Inadequate Programmatic Controls.Procedures Revised
05000334/LER-1995-009, :on 951107,ASME Valves Not Tested within TS Surveillance Interval.Caused by Scheduling of Ost Based on Completion Date of Previous Performance.Scheduled Performances Based on Start & Completion
05000443/LER-1995-007, :on 951103,MSSV Setpoint Testing Failed.Reset Four MSSVs to Required Setpoint & Retested Satisfactorily at Plant
05000272/LER-1995-026, :on 951023,MSSV Failed Lift Set Test.Cause Under Investigation.Appropriate Enhancements Will Be Made to Safety Valve Program Based on Results of Root Cause Determination
05000413/LER-1991-031, :on 911202,TS 4.0.5 Was Violated as Result of Inappropriate Action Due to Missed Iwv ISI Stroke Time Test of Valve.New Stroke Time Test for Valve to Verify Acceptance Criteria Was Performed
05000354/LER-1995-013, :on 950627,discovered Condidtion Prohibited by TS Due to Missed Surveillance in Accordance W/Requirements of TS 4.0.5.Surveillance Considered Overdue as of 950427. Surveillance Scheduling Sys Updated
05000425/LER-1995-005, :on 950627,incorrect Train Identification Resulted in Missed TS Surveillance Test.Caused by Cognitive Personnel Error on Part of Uss.Counseled Uss on Importance of Accuracy in Identifying Components
05000348/LER-1991-011, :on 911023,discovered That Component Cooling Water Valve Inservice Test Contained Inadequate Sys Lineup to Determine If Valve Would Seat Against Reverse Flow.Caused by Procedural Inadequacy.Procedures Revised
05000334/LER-1983-036-03, /03L-0:on 831104,reactor Coolant Pump Thermal Barrier CCR Isolation Valves TV-CC-107A,B & C Not Stroked as Outlined in Inservice Insp Program.After 1980 Inservice Insp Rev,Valves Inadvertently Omitted
05000338/LER-1991-016, :on 910722,charging Pump Temporary Flow Meter Discovered Outside ASME XI Accuracy Requirements.Caused by Personnel Error.Charging Pump Ref Data Measured W/Miniflow Recirculation Line Isolated
05000395/LER-1991-005, :on 910624,surveillance Test Procedure Re Main Steam Valve Operability Test Missed.Caused by Personnel Error.Valves Retested & Frequency of Scheduled Test,Per Tech Spec 4.0.5,increased
05000339/LER-1991-003-03, :on 910522,determined Surveillance Test on Four Safety Injection Sys Accumulator Nitrogen Sypply & Vent Valves Missed.Caused by Personnel Error.Affected Valves Successfully Tested
05000338/LER-1991-013, :on 910522,determined That Stroke Time Surveillance Requirements for Closed Direction Testing of 4 Quench Spray Pump Discharge MOVs Not Performed.Caused by Personnel Error.Valves Stroke Tested
05000325/LER-1982-101-03, /03L-0:on 820920,valve Time Testing Not Covered in Operability Test of Loops a & B of Lpci/Rhr Sys PTS 08.2.2C & 26.Caused by Personnel Oversight During Procedural Development.Procedures Revised
05000324/LER-1991-004, :on 910218,invalid First Interval Hydrostatic Test Boundary on Reactor Pressure Vessel Identified.Cause Unknown.Technical Support in-service Insp Personnel Revising PT-80.1
05000334/LER-1994-006-01, :on 940623,identified That Containment Isolation Valve Had Exceeded Its Limiting Stroke Time.Caused by Personnel Error.Involved Personnel Were Counseled.W/
05000353/LER-1994-006-01, :on 940520,identified That B Inboard & Outboard MSIVs Out of Surveillance.Caused by Less than Adequate Evaluation & Review of Procedure.Msiv Surveillance Test Review
05000373/LER-1990-013-06, :on 901207,discovered That 8 Valves Left Out of Operating Surveillance LOS-RH-Q2 Re RHR & RHR Svc Water Valve Inservice Test for Operating Conditions 1,2 & 3.Caused by Procedural Deficiency.Procedure Revised
05000414/LER-1991-002, :on 910106,work Completed on Valve 2NM-197B & Valve Declared Operable Although Surveillance Expired on 901218.Caused by Inappropriate Action.Valve Stroke Time Tested & Printouts Will Be Reviewed
05000443/LER-1994-001, :on 940125,reactor Trip & Safety Injection Occurred Due to Inadvertent MSIV Closure.Caused by Contaminated Hydraulic Fluid,Sticking Main Dump Valve & Related Hardware Issues
05000499/LER-1991-002-01, :on 910131,discovered That ASME Section XI Pressure Test of Completed Work Package for Weld Repairs on AFW Pump 24 Steam Supply Line Not Performed.Caused by Inadequate Procedures.Procedures Revised
05000445/LER-1990-044, :on 901130,reactor Operator Performed Test on Wrong Train of Charging Sys Due to Procedural Inadequacy. Results for Previously Performed Tests & Enhancements of Test Info on Work Orders Reviewed
05000339/LER-1990-006-02, :on 901015,pressurizer Power Operated Relief Valves Not Properly Tested Due to Personnel Error
05000336/LER-1994-004-02, :on 940319,failure to Perform Adequate ASME Leakage Test Discovered.Caused by Personnel Error & Procedural Deficiency.Valve Bypassed & Isolated
05000334/LER-1982-055-03, /03L-0:on 821130,Operations Surveillance Test 1.47.3A Not Performed within 25% Max Allowable Extension & ASME Oct & Nov Monthly Valve Restroking Not Conducted.Caused by Human Error.Present Scheduler Trained
05000324/LER-1982-089-03, /03L-0:on 820722,review of Plant Maint Procedure Revealed That post-maint Testing of Primary Containment Isolation Valves Per App J Was Not Established.Caused by Administrative Oversight.Procedure Revised
05000413/LER-1990-027-01, :on 901127,determined That Tech Spec 4.0.5 Violation Reportable Re Failure to Retest Reactor Coolant Check Valves as Part of Inservice Testing Program on 891201. Caused by Inappropriate Action.Program Revised
05000424/LER-1990-018-01, :on 900907,discovered That Surveillance Required by Tech Spec 4.0.5 & ASME Section XI Inadequately Performed.Caused by Procedure Inadequacy.Procedure Corrected & Operability of Check Valve Reverified
05000443/LER-1994-001-01, :on 940125,reactor Trip & Safety Injection Occurred Due to Inadvertent MSIV Closure.Caused by Hydraulic Fluid Contamination,Sticking Main Dump Valve & Related Hardware Issues.Msivs Disassembled & Inspected
05000443/LER-1994-003, :on 940217,determined That MSSV Setpoint Testing Conducted in Sept 1992 Reportable Per 10CFR50.72(b)(1)(ii)(A) & (B) Due to Insufficient UFSAR Loss of Load/Turbine Trip Analysis
05000455/LER-1990-004-10, :on 900701,discovered That Process Sampling Containment Isolation Valve Not Placed on Increased Test Frequency.Caused by Personnel Error.Procedure Revised to Require Mgt Concurrence on Technical Changes
05000498/LER-1994-004, :on 940119,determined Surveillance Performed to Comply W/Sr 4.4.4.1.b for Rvs Needed to Be Enhanced Because PORVs Not Tested from Mcb.Procedure 1(2)PSP03-RC-0010 Replaced w/OPSP03-RC-0010
05000373/LER-1993-019-03, :on 931204,TS Surveillance Missed Due to Inoperability of SRVs 1B21-F013B & 1B21-F013J.Caused by Misinterpretation of TS Requirements.Correct ASME XI Section Determined & Procedures Revised
05000336/LER-1993-010-02, :on 931029,unit Failed to Perform post-work ASME Leakage Test on Valve 2-CH-223.Caused by Personnel Error.Leakage Test Repeated & Found Satisfactory
05000334/LER-1993-014, :on 931021,identified That Surveillance Test Conducted on 930731 Stroked Valve to Closed Position Resulting in Missed Surveillance.Caused by Personnel Error. Involved Individual Received Written Reprimand
05000499/LER-1993-009-01, :on 930426,Tech Spec Violation Occurred Due to Use of Inappropriate Ref Value Data for RHR Pump Inservice Test.Surveillance Procedures Revised to Include Appropriate Ref Values
05000482/LER-1993-007, :on 930413,determined That Surveillance Test Procedure Re RHR Sys Inservice Pump B Test Not Accomplished by 930410.Caused by Lack of Oversight of Surveillance program.Past-due Notice Proceduralized
05000338/LER-1990-006, :on 900504,casing Cooling Pump Not Put Into Alert Status & Surveillance Missed.Caused by Personnel Error.Pump 1-RS-P-3B Placed in Alert Status
05000416/LER-1990-005, :on 900406,discovered That Current Surveillance Practices for Stroke Testing Fresh Air Makeup Intake Valves Could Have Resulted in Unfiltered Pathway.Administrative Controls Placed on Valves
05000498/LER-1993-013, :on 930408,TS 3.1.2.1 & 3.1.2.3 Violated. Caused by Use of Less than Effective Sys for Tracking Inoperable TS Equipment & Actions During Outage.Temporary Labels Placed on Control Board
05000354/LER-1993-002-02, :on 930323,discovered That Required post-maint Retest Activities Not Performed for Several Valves Repaired During Outage.Caused by Personnel Error.New Recurring Tasks Will Be Established When Frequency Changes
B14384, Discusses 18-month TS Surveillance Activities,As Followup to 930115 Application for Amend to License NPF-49,revising SR Functional Tests for Snubbers.Results of Investigation of All Required 18-month Surveillances Listed
U-601703, Proposed Tech Specs 4.0.5,3/4.4.3.1, RCS Leakage Detection Sys, 3/4.4.3.2, Operational Leakage, 3/4.8.3.1, Onsite Power Distribution Sys-Operating & 3/4.8.1.1, AC Sources - Operating
05000346/LER-1981-050-03, /03L-0:on 810820,containment Isolation Valves Cv 124,CV 125,NN 58,SA 502 & IA 501 Not Tested Prior to 810812.Caused by Procedure Inaccuracy.Procedures ST 5099.08 & Sp 1102.01 Modified to Test Valves in Cold Shutdown
05000382/LER-1994-005-01, :on 940415,dicovered That Several Valves Were Not Being Tested Per Requirements of ASME Section Xi.Caused by Inappropriate Action.Corrective Action:Pump & Valve Team Has Been Formed to Perform in Depth Reviews
05000445/LER-1990-026, :on 900828,surveillance Missed Due to Inadequate Procedural Requirements.Caused by Inadequate Manual Surveillance Scheduling Methods.Station Procedures Revised
2CAN018305, Submits Formal Documentation of 830106 Telcon Re Inadvertent Safety Sys Actuation Due to Potential PPS Design Problem
05000325/LER-1982-095-03, /03L-0:on 820803,review Revealed That RHR Shutdown Cooling Suction Valves F008 & F009 & Vessel Head Spray Valves F022 & F023 Not Tested on Quarterly Basis Per Inservice Insp Requirement.Caused by Program Logic Error
05000344/LER-1983-006-03, /03L-0:on 830317,four Main Steam Nonreturn Check Valves Found Stuck Open.Analysis Completed on 830524 Showed Possible Insufficient Torque to Close Valves.Caused by Packing Induced Friction.Packing adjusted.W/830608ltr
05000302/LER-1990-003, :on 900220,instrument Fluctuation Noted During Surveillance of Chilled Water Pump.Caused by Location of Flow Element within Chilled Water Sys.Relief Request Submitted & Field Problem Rept Generated
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
RBG-32948, Application for Amend to License NPF-47,revising Tech Specs 4.0.5,3.4.3.1 & 3.4.3.2 to Address IGSCC Concerns Identified in Generic Ltr 88-01
ST-HL-AE-4392, Responds to Violations Noted in Insp Repts 50-498/92-36 & 50-499/92-36.Corrective Actions:Corrective Maint Completed on power-range Neutron Flux Instrument NI-44 & Reload Initial Startup Testing Procedure Will Be Revised
NRC-90-0010, Responds to NRC Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised
05000498/LER-1989-022-01, :on 891205,discovered That ASME Section XI Pressure Test of Train C of Component Cooling Water Sys Not Performed Prior to Returning Sys to Svc.Sys Inoperable from 890909-1206.Test Control Procedures Revised
05000461/LER-1989-039, :on 891212,operations Shift Supervisor Notified That Three HPCS Suction Valves Not Tested within Max Surveillance Time Interval.Caused by Personnel Error. Surveillance Procedure Revised
05000354/LER-1989-019-02, :on 891004,inadequate Instrumentation Used on Core Spray Pumps for ASME Section XI Testing.Caused by Inadequate Design Change Package.Event Reviewed W/Station Inservice Testing Engineer
PY-CEI-NRR-1129, Jan-Dec 1989 Annual Rept
L-02-078, License Amendment Request Nos. 307 & 178
05000416/LER-1989-015, :on 891030,no Data or Evidence Found for Stroke Time Test Required to Be Performed Following Maint on Bettis Actuator for Isolation Damper QSZ51F001.Caused by Personnel Error.Programmatic Enhancements Initiated
W3P89-2131, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-382/89-26.Corrective Action:Procedure OP-903-030 Revised to Incorporate Requirements of ASME Section XI,IWP-3500
05000346/LER-1978-078-03, /03L-0:on 780713,ST 5099.08 & ST 5099.11 Not Performed Per Tech Spec 4.0.5 & Not Included in Computer Schedule.St 5099.08 Incorporated in Test Program on 780727. Passive Valves Identified & Operational Log Used
05000366/LER-1979-117-03, /03L-0:on 791031,water Pump 2P41-C001A Did Not Perform as Required.Caused by Normal Wear on Pump Impellers. Repaired to Specs & Placed in Svc
05000316/LER-2078-058-03, Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0
05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
LR-N980137, Forwards Responses to NRC Questions Re Electrical Power Sources During Shutdown
05000311/LER-1998-008-01, :on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised Procedure
05000272/LER-1997-001, :on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With
05000311/LER-1997-007-01, :on 970623,TS 4.0.5 ISI Requirement to Perform Radiography of Check Valves 2CC195 & 2CC210 Every 92 Days Determined to Have Been Missed.Caused by Personnel Error. Check Valves Subsequently Tested
05000272/LER-1997-001-02, :on 970117,discovered Inadequate IST Surveillance of B Injection Inlet Valves.Caused by Inadequate Communication Between EOP & Ist.Reviewed Salem EOPs for Similar Problems
05000272/LER-1997-008, :on 970321,inadequate Surveillance Testing of PORV Accumulators & Check Valves Was Attributed to Lack of Adequate Controls for Development & Maintenance of TS Surveillance Procedures.New Procedure Made
05000311/LER-1996-010-02, :on 960819,TS 4.0.5 Surveillance for Two Pressurizer Welds Was Missed Due to Insufficient Verification & Validation of Entry of Data Into Database. Exam of Pressurizer Spray Nozzle Was Completed
05000272/LER-1996-026, :on 961002,inadequate Testing of RHR Hot Leg Flow Path Discovered.Caused by Inadequate IST Program & Lack of Program Maint.Completed Procedure Revs to Ensure Adequate IST Program Maint & Implementation
05000272/LER-1995-026-01, :on 951023,main Steam Safety Valves Failed Lift Set Test.Caused by Use of Furmanite Trevitest Equipment That Had Inaccuracies.Rebuilt MSSV That Failed Lift Setpoint Test or Exceeded Allowable Seat Leakage Limits
05000272/LER-1995-018, :on 950720,improper Range Gauges Used for Ist. Caused by Inadequate IST Program & Lack of IST Program Maint & Implementation Processes & Associated Controls.Issued Stop Work Order by QA 950731
05000311/LER-1990-032, :on 900809,inservice Testing Program Discovered Not in Compliance.Caused by Inadequate Administrative Control.Review of Administrative Controls for Compliance W/Surveillance Frequency Changes Initiated
05000272/LER-1990-023-01, :on 900725,discovered That Surveillance of Svc Water Sys Check Valves Not Completed Per Inservice Testing Program Manual Requirements.Caused by Inadequate Administrative Controls.Program Modified
05000272/LER-1987-008-02, :on 870603,failure to Take Vibration Measurements Required by Inservice Testing (IST) Program Discovered.Caused by Inadequate Upgrade of IST Surveillance Procedures.Procedures Will Be Revised
05000255/LER-1990-015, :on 900706,inservice Test Not Run & Appropriate Pump Performance Values Not Reconfirmed within 7 Day Limiting Condition of Operation Period of Tech Spec 3.4.2. Caused by Personnel Error
RC-18-0105, (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 for a Service Water
05000410/LER-1999-010-01, For Nine Mile Point, Unit 2, Regarding Two Standby Liquid Control Valves Not Tested as Required by Technical Specification 4.0.5 and LER 99-010-01, Supplement 1, Unit 2 Reactor Trip Due to a Feedwater Master
HNP-97-177, Informs That Plant Intends to Extend First ten-yr Interval for Both ISI & IST Program by Five Months by Extending Current Interval End Date of 970901 to 980201
05000400/LER-1996-021, :on 961107,inadequate post-maint Testing Following Repairs on Containment Isolation Valve 1SP-208 Identified.Caused by Misinterpretation of ASME Code. Procedures Revised
05000400/LER-1991-001-01, :on 910225,Tech Spec Violation Due to Missed Surveillance Testing for Control Room HVAC Check Valves. Caused by Procedural Deficiency.Event Will Be Reviewed & ISI Personnel to Perform Comprehensive Review
05000400/LER-1991-001, :on 910103,operations Personnel Identified Procedural Deficiency That Resulted in Check Valves Not Being Tested as Required.Caused by Procedural Deficiency. Procedure Revised to Incorporate Testing
HNP-99-070, Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC
05000400/LER-1987-057, :on 870929,deficiency in Surveillance Test Procedures Covering Diesel Generator Fuel Oil Transfer Pumps Revealed.Caused by Misinterpretation of Relief Granted by Nrc.Procedure Revised
05000250/LER-1994-003-03, :on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced
L-94-047, Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482
05000251/LER-1992-003, :on 920224,27 & 0313,post Maint Testing of Valve & Refueling Water Purification Pump Was Not Completed in Accordance W/Asme Requirements.Caused by Cognitive Personnel Error.Valves Tested Successfully
05000251/LER-1992-003-01, :on 920224 & 27,discovered That Component Cooling Water Channel Head Drain Valves Not Post Installation Tested Per ASME Code & Ts.Caused by Personnel Error.Personnel Trained & Records Revised
05000315/LER-1998-057, :on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With
05000316/LER-1999-002-01, :on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
05000316/LER-1999-002, Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
05000529/LER-1998-004-01, :on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve Reviewed
05000528/LER-1997-006-01, :on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program
05000528/LER-1993-006, :on 930505,determined That Original Design of Shutdown Suction Isolation Valve Motor Control Circuits May Not Meet Requirements for Overload Protection Bypass.Cause Under Investigation.Lco 3.8.4.2 Entered & Mods Completed
05000530/LER-1988-002, :on 880109,ASME Surveillance Interval Exceeded for Containment Isolation Valve.Caused by Personnel Error. Individual Will Receive Appropriate Counseling &/Or Disciplinary Action
05000529/LER-1988-002, :on 880118,ASME Section XI Surveillance Test Interval Exceeded.Caused by Inadequate Administrative Controls Established for Tracking of Partially Completed Surveillance Tests.Controls Established
05000528/LER-1987-027, :on 870728,unit Entered Mode 4 (Hot Shutdown) W/O Meeting Surveillance Requirements for Containment Spray Sys Train B Pump.Caused by Personnel Error.Train a Pump Tests Verified & Procedure Revised
05000530/LER-1989-011-01, :on 891206,discovered That Quarterly ASME Surveillance Testing on Train a of Air Start Sys Check Valve for Train B Emergency Diesel Generator Not Performed.Caused by Insufficient Controls.Procedure Revised
GO2-94-266, Informs NRC of Intent to Extend First 10-yr ISI & Test Interval for No Longer than Six Months
05000397/LER-1991-036, :on 911226,missed ASME Section XI Test for Fuel Pool Cooling Relief Valve FPC-RV-117B Violated TS Sections 4.0.2 & 4.0.5.Cause Not Identified.Required Surveillance Testing Performed on FPC-RV-117B
GO2-93-009, Amends Response to NRC Re Violations in Insp Rept 50-397/92-25.Corrective Actions:All Appropriate Plant Personnel Will Be Made Aware of Changes to Section 11.4 of PPM 1.3.7 & Necessity for Changes by 930122
05000397/LER-1991-013, :on 910507,non-compliances W/Tech Specs Identified as Part of Program of Surveillance Procedure Verification.Further Evaluation Performed.Quality Action Team to Be Chartered to Evaluate Program
05000397/LER-1987-033, :on 871218,plant Tech Spec Sections 4.0.5 Re ASME Valve in-service Testing Requirements & 3.6.3 Concerning Containment Valve Operability Not Met.Caused by Personnel Error.No Corrective Action
GO2-85-817, Application for Amend to License NPF-21,revising Tech Spec 3/4.3.5, RCIC Sys Actuation Instrumentation, Reflecting Downgrade Resulting from Mods to Automatic Depressurization Sys Logic
GO2-85-255, Forwards Request for Relief for Exams Found Impractical During Preservice Insp Program.Written Response Granting Relief from ASME Section XI Requirements Requested
GO2-92-250, Responds to NRC Re Violations Noted in Insp Rept 50-397/92-25.Corrective Actions:Log Sheet for Pink Copy of Mwr Will Be Proceduralized by 921130
GO2-94-186, Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program
05000389/LER-1996-004-02, :on 960923,operation Prohibited by TS Occurred. Caused by Cognitive Personnel Error.Fpl Verified That a Successful Stroke Time Surveillance Was Conducted on FCV-25-7 & FCV-25-8
L-86-353, Forwards Response to 860818 Request for Addl Info Re Proposed Tech Specs to Incorporate Revised Pressure Temp & Low Temp Overpressure Protection Limits for RCS
L-92-131, Provides Response to Violations Noted in Insp Repts 50-335/92-05 & 50-389/92-05.Corrective Actions:Pump & Valve Program Changed to Failsafe Stroke Valves Quarterly & IST Program Reviewed by IST Engineer & Site QA
05000410/LER-1990-021-01, :on 901026,TS Violation Re RHR Sys Valve Tests Not Included in Inservice Test Pump/Valve Program Plan Occurred
2CAN121601, Response to Request for Additional Information License Amendment Request for Adoption of TSTF-545, TS Inservice Testing Program & Clarify SR Usage Rule Application to Section 5.5
05000395/LER-2014-001, V. C. Summer Nuclear Station Unit 1, Regarding Component Cooling System Emergency Makeup B Valve Failed to Stroke Open Rendering Train of Component Cooling Inoperable
PLA-3336, Responds to NRC Re Violations Noted in Insp Repts 50-387/89-33 & 50-388/89-31.Corrective Actions:Rhr Svc Water Pump 2P506B Remains in Inoperable Status Until Cause of Deviation Determined & Condition Corrected
05000336/LER-2009-004, Regarding Overdue ASME Code Required Inservice Test Did Not Meet Acceptance Criteria
L-2009-262, Proposed License Amendment Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections
NUREG-1431, Issuance of Amendments Regarding Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 (TS 07-05)
LR-N09-0237, License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components
05000272/LER-2008-002, Missed Containment Spray Valve Surveillance Per Technical Specification 4.0.5
L-2009-033, Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels
05000334/LER-2007-001, Re Valve Testing Program Change Inadvertently Leads to Condition Beyond Design Basis During Test
LR-N074224, PSEG Reply to Notice of Violation, EA-07-149, Dated 09/13/07
LR-N05-0424, Attachment 1, Calculation S-1-SJ-MDC-1539, Revision 2, Accumulator Pressure Decay Time During Discharge Test
B18952, Changes to Technical Specifications Bases
B18900, CFR 50.59 and Commitment Change Report for 2002
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
ET 02-0012, Annual 10 CFR 50.59 Evaluation Report
05000361/LER-1984-039, :on 840712,inservice Insp Test of Unit 2 & 3 Component Cooling Water Outlet Valves (HV-6500 & HV-6501) Missed.Caused by Administrative Oversight.Procedural Controls Validated
1CAN050807, Inservice Inspection Plan for the Fourth 10 - Year Interval
NUREG-1431, Informs Utils That Staff Has Incorporated TS Bases Provided by Ltr Into Utils Ts.Rev to TS Bases Encl
05000400/LER-1993-004-02, :on 930413,discovered That Two CR Ventilation Dampers Not Tested within Required Surveillance Interval Due to Personnel Error.Operations Surveillance Test OST-1131 Revised & Event Reviewed by ISI Personnel
HNP-97-073, Informs of Intention to Extend First ten-yr Interval for Both ISI and Inservice Testing Programs by Four Months by Extending Current Interval End Date of 970501 to 970901
L-94-108, Application for Amend to License NPF-16,revising TS Section 3/4.7.1.1,turbine Cycle,Safety Valves to Delete Ref to 1974 Edtion of ASME Code & Refer to Testing in Accordance W/Ts 4.0.5,ISI & IST Spec
05000272/LER-1995-005-01, :on 900508,seven Occurrences Noted That Revealed Lift Settings of Pressurizer Code Safety Valves on Both Units Out of Required Tolerance.Util Supplemented Rept W/Results of Vendor Conducted Root Cause
RC-18-0082, Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping
ULNRC-03267, Forwards Addl Info Re 941209 Application for Amend to License NPF-42,revising TS 4.3.2.2 & 4.7.1.2.1 & Bases for TS 3/4.7.1.2 for Auxiliary Feedwater Sys,Per Telcon
05000412/LER-1998-010-01, :on 980421,noted That non-safety Related Mechanical Seal Assembly Was Installed in Quench Spray Pump a 2QSS-P21A.Caused by Inadequate Knowledge & Training. Replacement Gland Seal Plates Were Procured
05000395/LER-1998-005, :on 980430,inadequate ASME Code Relief Valve Surveillance Testing Was Determined.Caused by Failure to Upgrade IST Implementing Procedures to Address Addl Test Requirements.Initiated Review
05000369/LER-1989-023, :on 890831,ESF Actuation Occurred When Nuclear Svc Water to Auxiliary Feedwater Isolation Valve Repositioned to Open.Caused by Improperly Following Correct Procedure.Signal to Valve 1CA-86 Cleared
NG-99-1296, Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors.Approves mark-up to Draft Revision 2 to NUREG-1022 with Description & Basis for Each Change for Review & Consideration
05000423/LER-1998-019, :on 980313,documented Max Required Accident Condition Flow Through Check Valves within Inservice Test Program Versus Results of Surveillance Testing.Cauesd by Program & Process Related Deficiencies.Procedures Revised
05000338/LER-1988-011, :on 880311,post-mod Testing Not Performed as Required by Two Tech Specs.Caused by Inadequacy of Original Engineering Work Request.Investigation Performed to Determine If Valves Been Stroke Time Tested
AECM-89-0010, Rept of 10CFR50.59 Safety Evaluations for June-Dec 1988
B15052, Responds to NRC Re Violations Noted in Insp Rept 50-423/94-24 on 940817-0926.Corrective Actions:Review Team Established to Explore Potential Failure Mechanisms & to Identify Potential Solutions
AECM-90-0198, Forwards Response to Recommendations Noted in NRC Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
05000250/LER-1998-003-02, :on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves
05000336/LER-1999-010, :on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators
05000373/LER-1986-042-01, :on 861204,HPCS Water Leg Discharge Check Valve Failed to Close on Reverse Flow as Designed During Performance of LOS-HP-Q1.Caused by Accumulation of Magnetite on Valve Disc.Valve Internals Cleaned
05000336/LER-1996-043-02, :on 961231,flow Indicators to East & West DC Switchgear Rcs Were Approx 29% Lower than Indicator Flow. Caused by Inadequate Flow Instrument Design Documentation. Elements Orifice Dimensions Verified
05000354/LER-1996-004, :on 960229,discovered Required IST Surveillances for D Safety Auxiliaries Cooling Sys Pump & B Station Svc Water Pump Not Performed.Caused by Less than Adequate Oversight.Instruction Provided
05000458/LER-1995-002-02, :on 950321,IST Surveillance of EDG Air Receiver Check Valves Was Deficient Due to Inadequate Procedure.Two Deficient STPs Were Corrected & Four Affected EDG Air Receiver Tank Inlet Valves Properly Tested
05000424/LER-1993-011, :on 930924,failure to Perform Leak Rate Testing Following Maint Occurred.Caused by Inadequate Safety Evaluation for FSAR Change.Fsar Revised
B18629, Response to Request for Additional Information Technical Specifications Change Request 3-2-00 Emergency Diesel Generator Allowed Outage Time