05000334/LER-2006-001, Re Main Steam Safety Valve Relief Tests Exceeded Technical Specification Required Setpoint Tolerance
HNP-16-029, Response to Request for Additional Information Regarding License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change
PLA-4061, Forwards Summary Rept of Safety Evaluations Approved During Period from 920101-921231 for SSES Unit 1 & 2
LR-N15-0182, License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements
PNO-I-14-003, Millstone, Unit 2. Shutdown Greater than 72 Hours Due to TS-Required Shutdown for the TDAFW
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
LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0011(Q), Rev. 53, Overhead Annunciator Window Box C6
DCL-09-062, Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15
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
Information Notice 1994-60, Potential Overpressurization of Main Steam System
05000530/LER-1994-002-01, :on 940318,13 of 20 MSSVs Setpoints Found to Be Out of Tolerance.Most Valves Exhibited Seat Wear.Valves Replaced w/pre-tested Spares & Approval to Amend TS LCO 3.7.1.1,MSSV Setpoints Received
05000528/LER-1993-009, :on 931022,determined That 18 of 20 MSSVs & 4 of 4 Pressurizer Safety Valves Setpoints (Psv) Out of Tolerence Due to Setpoint Drift.Mssvs & Psvs Lift Setpoints Adjusted within TS Limits
SBK-L-06244, Submittal of Changes to Seabrook Station Technical Specification Bases
ULNRC-05301, Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.13
LR-N06-0051, Request for Amendment to Technical Specifications Maximum Allowable Power with Inoperable Steam Line Safety Valves
W3P89-2163, Responds to Violations Noted in NRC Enforcement Action 89-192 Re Inoperable Main Steam Line Code Safety Valve. Corrective Actions:Mgt Directive Issued Providing Guidance Re Instrumentation Malfunctions During Surveillance Testing
05000346/LER-1978-124-03, /03L-0 on 781216:during Surveillance testing,13 of 18 Main Steam Safety Valves Failed to Be within +/-17 of Design Setpoint,Apparently Caused by Change in Ambient Conditions
05000325/LER-1979-076-03, /03L-0:on 791002,valve E11-F068B Failed to Open. Caused by Contacts Sticking in Relay Ri in Position Modulator,Resulting in Constant Close Signal.Relay Freed & Replacement Ordered
05000346/LER-1979-032-03, /03L-0 on 790222:main Steam Safety Valve SP17B1 Lifted Early While Unit Was About 15% Power Following Unit Runback.Cause Uncertain.Valves SP17A1/B1 Found Outside Design Setpoint.Valves Adjusted.Investigation Continuing
L-2004-193, Proposed License Amendment Request for Additional Information Response WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit
W3F1-2004-0068, Supplement to Amendment Request NPF-38-249 Extended Power Uprate
DCL-02-115, License Amendment Request (LAR) 01-08, to Modify Technical Specification 3.4.11 & Licensing Basis to Credit Automatic Actuation of Class One Power Operated Relief Valves (Porvs) Instead of Pressurizer Safety Valves (Psvs)
LR-N02-0417, Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters - Revision to Request for Change to TS Dated 06/28/2002
L-02-038, Technical Specification Bases Change Submittal
LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink
U-601261, Forwards Interpretation Re Inoperability of Sys Providing Support Function,For Comments
L-99-051, Provides Response to NRC Request to Maintain Change That Was Proposed to Be Deleted in LAR 214 & 81,submitted 980709.New Marked Up TS Pages Are Encl
B12151, Forwards Response to 851025 Request for Addl Info Re Question 440.72 Concerning three-loop Operation.Tech Specs Must Require Closure of Stop Valves in N-1 Loop Operation to Prevent Operation in Unanalyzed Condition
3F0688-20, Responds to NRC Ltr Re Violations Noted in Operational Safety Team Insp Rept 50-302/87-22.Corrective Actions: Temprorary Change to Section 6/6 of Design Basis Document Issued on 880329
AECM-87-0215, Forwards Addl Info for Proposed Tech Spec Changes Re Exceptions to Tech Spec 3.0.4 for Second Refueling Outage, Per 871030 Request.Proposed Methods for Complying W/Action Statements Consistent W/Methods Used at Other Plants
AECM-89-0053, Forwards Response to 890303 Request for Addl Info on Alternate DHR Sys.Advanced DHR Sys Has Sufficient Heat Removal Capability to Maintain Reactor Coolant Temp of 185 F 24 H Following Reactor Shutdown
AECM-89-0051, Application for Amend to License NPF-29,allowing One Time Exceptions to Tech Spec 3.0.4 to Support Upcoming Third Refueling Outage.Fee Paid
AECM-89-0042, Forwards Addl Info in Support of 880923 Application for Amend to License NPF-29,adding Alternate DHR Sys
AECM-89-0038, Application for Amend to License NPF-29,allowing one-time Exceptions to Tech Spec 3.0.4 in Lieu of Much Broader Scope Changes Associated W/Generic Ltr 87-09
AECM-88-0232, Submits Info Re Tech Spec Position Statements,In Response to 880928 Meeting & 881006 & 20 Telcons
NOC-AE-000335, Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-1431
B15371, Application for Amend to License DPR-65,modifying TS Re Pressurizer & Main Steam Safety Valves
ST-HL-AE-4887, Forwards Requested Summary of Calculation NC-7104,used as Basis for 940429 Proposed TS Amend,Revising TS 3.7.1.1, Turbine Cycle - Safety Valves
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
ST-HL-AE-4750, Application for Amends to Licenses NPF-76 & NPF-80,revising Max Allowable Power Range Neutron Flux High Setpoint When One or More Main Steam Safety Valves Inoperable
B14711, Application for Amend to License DPR-61,revising TS 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability
NRC-97-0084, Responds to Violations Noted in Insp Rept 50-341/97-07. Corrective Actions:Personnel Initiated DER 97-1012 & Removed MDCT Tag,Conducted Lessons Learned Meeting,Verified Enclosure Internal Strip Heater to Working & Repaired Door
05000346/LER-1977-117-03, /03L-0:on 771215,four Main Steam Safety Valves Lifted,During Trip Test.On 771221,evaluation of Startup Test Recorder Data Revealed That Main Steam Safety Valves Lifted Below Tech Spec Requirement.Caused Unknown.Valves Reset
NRC-95-0077, Forwards Revised Pump Relief Requests PR-6,PR-7 & PR-8 for IST Program for Pumps & Valves & New Pump Relief Request PR-11 for EECW Pumps,As Result of Util 950407 Response to Insp follow-up Item 95002-01
NRC-97-0080, Responds to NRC Re Violations Noted in Insp Rept 50-341/96-17.Corrective Actions:Ts Clarification Cancelled & Procedure Governing TS Clarifications Has Been Reviewed Against NRC Insp Guidelines on TS Interpretations
AECM-90-0135, Application for Amend to License NPF-29,revising 900427 & 0705 Applications Re Changes to Tech Spec Due to Addition of Alternate DHR & Addressing NRC Concerns Re Manual Realignment of LPCI Emergency Core Cooling Subsystems
L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006
L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers
DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)
CP-200800057, Supplement to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt
05000352/LER-1988-042, :on 881223,inoperability of Plant Sys Due to Unacceptable Physical Separation Between safety-related Cabling Determined.Caused by Personnel Error.Plant Procedure Will Incorporate Consolidated Open Items List.W/Undated Ltr
05000413/LER-1989-003-03, :on 890221,jumper Used to Check Relay Contacts Short Circuited,Resulting in Closure of Steam Generator 2C MSIV & Opening of 3 2C Code Safety Relief Valves.Caused by Mgt Deficiency.Setpoint Recalibr
05000339/LER-1989-005, :on 890314,main Steam Safety Valves Setpoints Out of Tolerance Per Tech Specs 3.7.1.1.Cause Undetermined. Valves Refurbished & Retested Until Setpoint within Allowable Tech Specs
05000414/LER-1989-003, :on 890221,reactor Trip on Steam Generator 2C lo-lo Level Due to Mgt Deficiency.Troubleshooting Review Guideline Provided.Open Setpoint for 2SV7 Recalibrated
05000338/LER-1989-009-01, :on 890515,main Steam Line Code Safety Valves as Found Set Pressures Found to Be Outside Lift Set Pressure Tolerance.Cause of Event Not Determined.Valves Refurbished & Retested by Wyle Labs
05000339/LER-1989-005-02, :on 890314,main Steam Safety Valve (MSSV) Setpoints Out of Tolerance Allowed by Tech Spec 3.7.1.1. Cause Not Determined.Mssv Refurbished & Retested to Ensure Pressures within Allowable Limit
05000327/LER-1987-060, :on 870827,inadvertent Diesel Generator Start Occurred.Caused by Inadequate Procedure During Shutdown Board 1B-B Maint.Energized Studs on Shutdown Board 1B-B Taped to Prevent Shorting Studs Together
05000423/LER-1987-036-01, :on 871031,setpoint Drift on Main Steam Safety Valves Discovered.Cause Unknown.Valves Reset to Tech Spec Requirements.Untested Valves Will Be Tested or Replaced Prior to Resuming Power Operations
05000339/LER-1987-008-02, :on 870913 & 15,pressurizer Code Safety Valves as Found Set Pressures Found to Be Out of Tolerance.Cause Unknown.Valves Readjusted & Repaired to within Correct Setpoint Tolerance Allowed by Tech Spec 3.4.3
05000338/LER-1987-009, :on 870508,main Steam Safety Valve Setpoints Discovered Below Tech Spec Limits.Cause Unknown.Setpoints Readjusted
05000213/LER-1994-015, :on 940616,main Steam Safety Valve Pilot Valves Exceeded Lift Setpoints.Caused by Seat Adhesion.Readjusted Setpoints for Pilot Valves MS-V-1613-2B & MS-SV-1613-3A
05000334/LER-1986-002, :on 860516 & 17,main Steam Safety Valve Lift Settings Outside Tech Spec Limits & Automatic Reactor Trip Occurred.Caused by Setpoint Drift & Neutron Flux Detector Failure.Valves Reset.Detector Replaced
05000368/LER-1999-001, :on 990108,TS Requirements for as-lift Settings of MSSV Were Not Met.Caused by Errors in Determination of Effective Seating Area by Vendor During Test Device Qualification.Replaced All Mssvs.With
05000354/LER-1999-002, :on 990206,discovered That Flowpath Verification for B Safety Auxiliaries Cooling Sys Had Not Been Performed.Caused by Personnel Error.Performed Flowpath Verification.With
05000346/LER-1998-001-02, :on 980407,main Steam Safety Valves Setpoints Were Outside of TS Allowable Values.Cause Will Be Investigated.Setpoint of Valve Adjusted to Be within Allowable Value
05000338/LER-1998-005-01, :on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With
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
05000338/LER-1997-002-02, :on 970515,set Pressure for One MSSV Was Found Outside Setpoint Tolerance Due to Setpoint Variance.Mssv That Failed Was Disassembled,Inspected,Repaired,Reassembled & Tested Satisfactorily
05000327/LER-1997-005-01, :on 970319,two of Six Tested Main Steam Safety Relief Valves Not within TS Setpoint Tolerance.Appropriate LCOs Entered & Valves Found Outside TS Setpoint Tolerance Adjusted to within TS Tolerance & Retested
05000416/LER-1985-039, :on 851017,inadvertent Loss of Power to ESF Bus Caused Inoperability of Div 2 Safety Sys.Caused by Personnel Error.Electrical Personnel Instructed on Relationship of Protective Circuit to Feeder Breakers
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
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
05000311/LER-1985-007, :on 850407,during Heatup Following Refueling Outage,Four Steam Generator Safety Valves Prematurely Lifted & Gagged Shut.Caused by Incorrect Lift Settings.Valves Reset
05000338/LER-1993-002, :on 930120,as-found Set Pressures for One Pressurizer Safety Valve & Two MSSVs Found Outside TS Setpoint Tolerances.Caused by Setpoint Drift.Valves Will Be Refurbished at Wyle Labs
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
05000334/LER-1996-001-01, :on 960320,main Steam Valve Setpoints Not within Specification.Caused by Relatively Small Amount of Normal Setpoint Drift.C/A:Main Steam Safety Valve Adjustment Performed
05000338/LER-1996-001-01, :on 960216,MS & Pressurizer SV Setpoints Out of Tolerance Due to Setpoint Drift.Adjusted Pressurizer SVs 01-RC-SV-1551A & 01-RC-SV-1551C
05000334/LER-1984-011, :on 841012,eight Main Steam Safety Valve Lift Settings Found Outside Tech Spec Limits.Caused by Setpoint Drift.Valves Adjusted & Tested
05000361/LER-1989-010, :on 890520,concluded That Main Steam Safety Valve (MSSV) Flow Capacity Less than Nameplate Rating.Mssvs Ring Settings Changed to Be Consistent W/New Recommended Generic Settings
05000443/LER-1995-007, :on 951103,MSSV Setpoint Testing Failed.Reset Four MSSVs to Required Setpoint & Retested Satisfactorily at Plant
05000339/LER-1992-003-02, :on 920306,as-found Set Pressures for Three Pressurizer Safety Valves & 8 of 15 MSSV Found Outside of TS Setpoint Tolerances.Caused by Setpoint Drift.Pressurizer Loop Seal Modified & Setpoint May Be Increased
05000368/LER-1995-005-03, :on 951004,MSSV Setpoints Not within TS Tolerance During Operation Due to Failure to Adequately Specify Environ Conditions for Use in Vendor Procedures for Testing Setpoint Adjustment.Adjusted Setpoints
05000387/LER-1983-162-03, /03L-0:on 831128,RHR B Svc Water Motor Operated Valve HV11210B Would Not Operate in Open Direction for Suppression Pool Cooling.Caused by Failure of Auxiliary Contact in Circuit Breaker Valves
05000339/LER-1995-001-03, :on 950403,MS & Pressurizer Safety Valve Setpoints Out of Tolerance Due to Setpoint Drift. Refurbished & Retested Safety Valves to within Allowable Limits of TS at Wyle Labs
05000416/LER-1983-186-03, /03L-0:on 831122,standby Svc Water Pump a Declared Inoperable Due to Low Cooling Water Flow Through Pump. Caused by Sediment in Supply/Return Line Restricting Cooling Flow Through Pump a
05000325/LER-1983-036-03, During Reactor Startup, Control Power Supply Fuse on Motor Operator Breaker of Sys Flow Control Valve 1-E11-F068 Blew.Caused by Broken Open Position Lamp.Fuse Replaced
05000327/LER-1983-048-03, /03L-0:on 830328,discovered That on 820911 & 830108,certain Main Steam Safety Relief Valves Failed to Meet Required Setpoint Criteria.Caused by Normal Aging of Valve Spring & Ambient Temp Variations.Valves Adjusted
05000382/LER-1991-003-01, :on 861126,improper Testing of Main Steam Safety Valves Noted.Caused by Incorrect Vendor Supplied Data & Procedural Inadequacy.Procedure MM-007-015 Revised & Other Surveillance Procedures Reviewed
05000324/LER-1982-098-03, /03L-0:on 821027,measured Vibration Reading of 2B RHR Svc Water Pump Exceeded 1.5 Mils Vibration.Caused by Failed Gasket at Pump Rear Bearing Housing Allowing Loss of Casing Oil,Resulting in Increased Operating Temp
05000338/LER-1991-002, :on 910125,two Pressurizer Safety Valves & 7 of 15 Main Steam Safety Valves Foud Outside Setpoint Tolerances Allowed by Tech Specs.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted
05000339/LER-1990-005-02, :on 901005,pressurizer & Main Steam Safety Valve Setpoints Found Out of Tolerance Due to Setpoint Drift
05000325/LER-1981-074-03, /03L-0:on 811115,running Temp of Pump Motor to RHRSW Pump 1B Significantly Exceeded Norm & RHRSW Subsystem Declared Inoperable.Caused by Partial Disintegration of Pump Motor Sacrificial Anode Zinc & Zinc Accumulation in Orif
05000366/LER-1982-084-03, /03L-0:on 820813,D RHR Svc Water Pump Declared Inoperable Due to Failure to Meet Min Discharge Pressure & Flow Requirements.Caused by Stuck Open Check Valve in B Pump Discharge Flow Path.Check Valve Rebuilt & Reinstalled
05000366/LER-1982-095-03, /03L-0:on 820817,RHR Svc Water Loop a Strainer Inlet Valve Inadvertently Closed.Caused by Personnel Error. Valve Immediately Reopened.Responsible Personnel Reprimanded
05000416/LER-1994-003-02, :on 940310,unacceptable Vibration Reading Were Obtained During Run SSW Pump Declared Inoperable.Caused by Accelerated Degradation of Carbon Steel Bolts in Coupling. SSW Pumps Were Disassembled
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
05000456/LER-1994-004-05, :on 940309,improper Value for Mean Seat Area Was Used in Trevitest Calculation for MSSV Setpoints.Caused by Programmatic Deficiency.Mssvs Will Be Reset on or Before 940409
05000325/LER-1982-047-03, During RHRSW Operability Test,Vibration of 3.2 Mils Measured for 1B RHRSW Pump.On 820420,during Suppression Cooling,Smoke Observed Emanating from Pump Bearing Housing
05000366/LER-1982-030-03, /03L-0:on 820420,loop a Rhr,Rhr Svc Water Flow Indicators & RHR Heat Exchanger Svc Water Pressure Control Valve Controller Declared Inoperable.Caused by de-energization of Instruments.Instruments re-energized
05000325/LER-1982-019-03, /03L-0:on 820415,while Performing Routine Monthly Calibr of RHRSW Suction Header Pressure Switches,B Subsystem Pressure Switch Actuated Intermittently in Response to Applied Test Signal
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000324/LER-1982-029-03, /03L-0:on 820203,discovered Suction Header Low Pressure Lockout Rendering Divs I & II RHR Svc Water Subsystem Inoperable.Caused by Loss of Operating Fluid Level in Diaphragm Housing of Suction Header Pressure Switch
PY-CEI-NRR-1174, Provides Justification Re Events Leading to Declaration of Alert on 900403 Due to Loss of Emergency Svc Water When Manway Flange Gasket Leak Developed at Pump a Discharge Strainer,In Response to Ocre 900406 Petition
05000324/LER-1982-005-01, /01T-0:on 820116,both RHR Svc Water Loops Inoperable,Rendering RHR Shutdown & Suppression Pool Cooling Modes Inoperable.Caused by Loop Pumps Failure Due to Plugging of Sensing Line to Suction Header Pressure Switch
05000334/LER-1981-106-03, /03L-0:on 811228,lift Settings on Seven of 15 Main Steam Safety Valves Exceeded Tech Spec Limits.Caused by Valve Type 370 RAX-RT21 Life Setpoint Drift.Settings Readjusted
05000302/LER-1981-081-03, /03L-0:on 811222,while Maintaining Steam Header Pressure for Turbine testing,MSV-35 Code Relief Was Continuously Relieving Approx 50 Lb Below Tech Spec Setpoint.Caused by Setpoint Drift.Valve Lift Setpoint Reset
05000361/LER-1993-001-01, :on 930208,engineer Notified That MSSV Inoperable Due to Removal of Insulation from Valve Body. Caused by 930204 Removal of Insulation to Investigate Leak in Discharge Flange.Warning Signs Added
AECM-90-0056, Application for Amend to License NPF-29,changing Tech Specs to Address Addition of Alternate DHR Sys & Manual Realignment of LPCI Emergency Core Cooling Subsystems During Plant Shutdown
05000414/LER-1990-004-02, :on 900202,Tech Spec 3.0.3 Entered as Result of Two Channels of Power Range Nuclear Instrumentation Being Out of Acceptable Range.Caused by Defective Procedure.New Procedure Developed
05000423/LER-1989-036, :on 900302,discovered That Requirements of Action Statement for Inoperable Safety Valve Not Met on 890512.Caused by Procedural Inadequacy.Safety Valve Test Procedure Revised
05000324/LER-1981-106-03, /03L-0:on 811014,during Mod Work on Svc Water Outlet Line on RHR Heat Exchanger,Hairline Cracks Discovered in Structural Steel Framework of Line Pipe Support.Caused by Piping Vibration Causing Fatigue Failure of Support Stee
05000324/LER-1981-078-03, /03L-0:on 810804,RHR SW Subystem Pump a Would Not Start Due to Pump Suction Header Low Pressure Lockout Signal from Header Pressure Switch.Caused by Loose Plug in Switch Diaphragm Housing,Allowing Diaphragm Fluid to Leak
05000366/LER-1981-063-03, /03L-0:on 810625,following Maint on Clogged Motor Cooling Water Line,Rhr Svc Water Pump 2E11-C001A Failed to Meet Acceptance Criteria for Operability.Caused by Debris Obstructing Flow.Preventative Maint Performed
05000346/LER-1981-034-03, /03L-0:on 810601,found That When Unit Experienced Power Swing During Turbine Generator Control Valve Test, Main Steam Line Code Safety Valves Lifted Early.Cause Unknown.Investigation Will Be Done in Upcoming Outage
05000324/LER-1980-117-03, /03L-0:on 801227,RHR Svc Water Pump 2C Vibrations Exceeded Tech Specs.Caused by Pump Diffuser Antirotating Pin Dislodging from Casing & Embedding Between Diffuser Vane & Pump Impeller.Pin Replaced
05000382/LER-1989-018, :on 890921,while Testing Main Steam Safety Valve,Lift Pressure Found to Be Below Tech Spec Allowable Value.Caused by Error in Judgement by Plant Supervisors. Event Will Be Discussed by Superintendent
05000336/LER-2024-002, Two Main Steam Safety Valves Failed to Lift within the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
05000346/LER-1979-020-03, /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily
05000346/LER-1979-018-03, /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily
05000324/LER-1979-073-03, /03L-0:on 790813,RHR Pump Breaker 2A Was Erroneously Racked Out,Making Both Loops of Sys Inoperable. Caused by Incorrect Prepration of Tag & tag-out Sheet by Control Operator.Personnel Instructed
05000324/LER-1979-071-03, /03L-0:on 790808,RHR Sys Pump 2D Vibrated at Level Higher than Allowable Limit During RHR Sys Operational Component Test.Caused by Spring Part Lodged in Vane of Impeller.Part Removed,Pump Inspected & Tested
05000346/LER-1979-049-03, /03L-1:on 790331,during Surveillance Testing Nine of 18 Main Steam Safety Valves Found Outside Design Setpoint Range.Caused by Changing Ambient Conditions,Valve Liftings from Previous Trips & Vibrations.Valves Adjusted
05000498/LER-2018-001, Main Steam Safety Valve as Left Settings Outside of Required Range Contrary to Technical Specifications Due to Inadequate Procedure
05000250/LER-2018-002, As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits
L-95-002, Forwards Response to NRC 941117 RAI Re Proposed License Amends Submitted by 940719 & 1020 Ltrs,Revising TS 3/4.7.1.1 & Associated Bases Which Addresses Max Allowable Reactor Thermal Power Operation W/Inoperable MSSVs
L-94-176, Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves
L-94-223, Forwards Revs to 940719 Proposed License Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1.1 & Associated Bases, Which Address Max Allowable Reactor Thermal Power Operation W/Inoperable Mssvs,Per Recent Conversation W/Nrc
05000315/LER-1997-004, :on 970228,main Steam Safety Valve Exceeds Allowable Lift Setpoint.Caused by Setpoint Drift.Valve Was Reset to Proper Setpoint
05000316/LER-1994-006-01, :on 940906,six MSSVs Failed to Meet TS Lift Setpoint Requirements.Caused by Galling Between Valve Disk & Nozzle.Nrr Issued TS Amend 167 to Unit 2 Ts,Increasing MSSV Tolerance on 940909
05000315/LER-1994-001, :on 940203,04 & 05,13 of 20 MSSVs Lift Settings Found Out of Tolerance.Caused by Mild Galling Between Disk & Nozzle Components.Valve Mfg Recommended That Nozzle & Disc Seatingsurfaces Have Grey Matt Finish
05000315/LER-1995-002-01, :on 950620,21,22 & 23,nine MSSVs Lift Settings Found to Exceed TS Limit.Caused by Mild Galling Between Disc & Nozzle Components.Eight of MSSVs W/Initial High Lift Setpoint Had Subsequent Lifts within TS Limit
05000315/LER-1992-006-02, :on 920618 & 19,10 of 20 Main Steam Safety Valve Lift Settings Found Outside of TS Tolerances.Caused by Setpoint Drift.Valves Reset to Acceptable Values & Retested Satisfactorily
05000316/LER-1992-003, :on 920219,20 & 21,7 of 20 Main Steam Safety Valve Lift Setting Found Outside of TS Established Limits. Caused by Setpoint Drift.Setpoint Ranges Reset & Maint Procedure for Valve Repair Revised
05000315/LER-1992-006, :on 920618 & 19,10 of 20 Main Steam Safety Valve Lift Settings Found Outside Plus or Minus 1% Limit Established by Ts.Caused by Setpoint Drift.Ts Change to Be Submitted to Increase Tolerance Limits
05000315/LER-1990-013, :on 901017,18 & 19,11 of 20 Main Steam Safety Valve Lift Setpoints Out of TS Specified Range.Caused by Setpoint Drift.Valves Reset to Acceptable Values & Retested Satisfactorily
05000315/LER-1989-002-01, :on 890303,failure of MSIVs to Meet Tech Spec Lift Setpoint Requirements Occurred.Safety Valve Setpoints Reset within Specified Ranges
05000316/LER-1990-006, :on 900625,failure of Facility Main Steam Safety Valves to Meet Tech Spec Lift Setpoint Requirements. Caused by Incompatibility of Required Setpoint Tolerance & Repeatability.Tech Spec Change Requested
05000316/LER-1988-004, :on 880420,discovered Six of Twenty Main Steam Safety Valves Lift Setpoints Out of Spec During Surveillance Testing.Caused by Testing Method & Setpoint Drift.Safety Valves Setpoints Reset
05000315/LER-1986-020, :on 851102,main Steam Safety Valves Discovered Out of Spec During Surveillance Testing.Caused by Lack of Procedural Instructions.Safety Valves Setpoints Reset
05000528/LER-1998-004, :on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three MSSVs & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7
05000530/LER-1997-003, :on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions
05000530/LER-1994-002, :on 940317,main Steam Safety Valve Setpoints Found Out of Tolerance.Valves Adjusted,Certified & Returned to Svc
05000529/LER-1993-002, :on 930518,determined That 15 of 20 MSSV & 4 of 4 Pressurizer Safety Valves as-found Relief Settings Out of Tolerence Limits.Valves Exhibited Seat Wear.Efforts to Enhance MSSV Setpoint Repeatability Continuing
05000530/LER-1992-005-02, :on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility
05000529/LER-1991-005-02, :on 911009,determined That 11 of 20 Main Steam Safety Valve as-found Relief Settings Out of Tolerance Specified in TS 3.7.1.1.Caused by Setpoint Drift.Valves Adjusted & Successfully Retested
05000529/LER-1991-005, :on 911009,determined That Main Steam Safety Valves Out of Tolerence,Per TS 3.7.1.1 & on 911104 & 05, Determined That Pressurizer Safety Valves Out of Tolerence. Caused by Setpoint Drift.Valves Adjusted
05000530/LER-1992-005-01, Forwards LER 92-005-01 Re Main Steam Safety Valve as-found Relief Settings Out of Tolerance Limits in TS 3.7.1.1.Suppl Updates Valve Testing Schedule in Section Iii.B & Provides Main Steam & Pressurizer Safety Valve Test Res
05000335/LER-1999-004-01, :on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With
05000368/LER-1997-005-01, :on 970604,MSSV as-found Lift Values Did Not Meet TS Requirements Due to Combination of Maint,Testing & Design Factors.Mssv Were Replaced W/Valves That Had Been Fully Inspected & Tested at NWS
05000423/LER-2011-002, Regarding Failure of Two Main Steam Safety Valves to Lift within the Acceptance Criteria
05000423/LER-2008-002, Unit 3 Failure of Four Main Steam Safety Valves to Lift within the Acceptance Criteria
05000250/LER-2006-002, As-Found Cycle 21 Main Steam Safety Valve Setpoint Outside Technical Specification Limits
05000250/LER-2004-002, Regarding As-Found Cycle 20 Main Steam Safety Valve Setpoint Outside Technical Specification Limits
05000251/LER-2003-002, Regarding As-Found Cycle 20 Main Steam Safety Valve Setpoint Outside Technical Specification Limits
05000250/LER-2003-004, Re As-Found Cycle 19 Main Steam Safety Valve Setpoints Outside Technical Specification Limits
05000346/LER-2002-006, For Davis Besse Unit No.1, Regarding Emergency Diesel Generator Exhaust Piping Not Adequately Protected from Potential Tornado-Generated Missiles
B18785, Request for Additional Information: Licensing Basis Document Change Request 2-12-02, Unit 2 Technical Specification Change Operation with Main Steam Line Code Safety Valves Inoperable
05000346/LER-2002-001, Main Steam Valve Setpoints Greater than Allowable Values
05000389/LER-2001-002, As-Found Cycle 12 Main Steam Safety Valve Setpoints Outside Technical Specification Limits
05000368/LER-1999-001-01, :on 990108,four Main Steam Safety Valves as- Found Lift Values Failed to Meet TS Requirements.Cause of Evaluation in progress.Short-term & long-term Corrective Actions Will Be Described in Suppl to Rept.With
05000400/LER-1989-023-01, :on 891223,significant Difference Between Actual & Indicated Reactor Power Level for power-range Nuclear Instruments Noted.Caused by Installation of Low Leakage Core Loading Pattern W/O Adjustments
05000315/LER-1994-003, :on 940311,main Steam Safety Valve Test Inaccuracy Due to Miscalculation of Valve Seat Area by Vendor.Mssvs Retested After Entering Mode 3
AECM-83-0565, Forwards marked-up Proposed Changes to Tech Specs Per 821020 Confirmation of Action Ltr.Changes Intended to Enhance Clarity or Provide Consistency W/Plant Design & Operation. Justification for NSHC Encl
05000336/LER-2024-002-01, For Millstone, Unit 2, Two Main Steam Safety Valves Failed to Lift within the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2
05000334/LER-1995-004, :on 950301,five MSSV Determined by Testing to Be Outside TS 3.7.1.1 Tolerance of +1%-3%.Caused by Vendor Provision in Incorrect Mean Seat Area Data Used.Made Adjustments on Six Affected Safety Valves
AECM-89-0010, Rept of 10CFR50.59 Safety Evaluations for June-Dec 1988
05000315/LER-1987-011, :on 870624,main Steam Safety Valves Lift Setpoints Found Out of Spec.Caused by Setpoint Drift.Safety Valves Setpoints Reset within Specified Ranges
05000529/LER-1993-002-01, :on 930518,determined That 15 Out of 20 MSSV & Pressure Safety Valves Out of Tolerence Limit Specified in TS 3.7.1.1 & 3.4.2.2.Cause of Setpoint Drift Being Investigated.Valve Setpoints Readjusted
05000324/LER-1981-111-03, /03L-0:on 811013,during Attempt to Place a RHRSW Subsys Into Svc for Suppression Pool Cooling,Noted Inability to Start Pump Due to Pressure Header Low Pressure Lockout Signal from Switch.Caused by Low Fluid Level
05000423/LER-1989-010-01, :on 890512,setpoint Drift Identified While Testing Main Steam Safety Valves.Cause Unknown.Setpoints on Valves Reset to Tech Spec Requirements
GO2-96-132, Requests Amend to Ts,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of Nhsc or Environ Assessment Provided in Rev a
0CAN069801, Responds to Violations Noted in Insp Repts 50-313/98-01 & 50-368/98-01.Corrective Actions:Plant Maint Rule Program Was Revised,Conducted Assessment of Past Availability Performance & Established Unavailability Criteria
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
05000445/LER-1991-024, :on 911004,main Steam Safety Valves Had Lift Setpoints Less than Setpoint Tolerance Allowed by Ts.Caused by Inadequate Procedure.Setpoint Verification Procedure Revised