LR-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual
L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Operating License, Technical Specifications, and Licensing Basis Changes
LR-N06-0394, Inservice Testing (IST) Program - Third Ten Year Interval
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
L-96-034, TER on Third 10-Yr Interval ISI Program Plan:Nppd Cns
ST-HL-AE-1929, Forwards Response to NRC 870104 Comments & Questions Re Util 851031 Submittal Concerning NUREG-0737,Item II.D.1
HL-1492, Ro:On 910214,potential Malfunction of SRVs Suspected. Caused by Turbine Trip & Reactor Scram Valve Testing. Investigation of Malfunction Planned
NRC-84-0087, Forwards Amplification of Revised Response to Reactor Sys Branch Question 6 Re Pressurizer Level.Amplification of Response to Question 15 Will Be Forwarded Under Separate Cover
NRC-84-0080, Forwards Responses to 840507 Request for Addl Info Per Reactor Sys Branch Review of Tech Specs.Info Documents Certain Objections to Timeliness & Scope of Review
AECM-83-0373, Forwards Proposed Changes to Tech Specs,Enhancing Clarity or Providing Consistency W/Plant Design & Operation,Per 821014 Confirmation of Action Ltr.Changes Involve Nshc. Justification for Determination Encl
B14918, Application for Amend to License NPF-49,relaxing Lift Setting Tolerance for Pressurizer Safety Valves & MSSVs
B14559, Application for Amend to License DPR-65,revising TS to Provide Consistency W/Proposed Changes to GL 90-06 Re Resolution of Generic Issues 70 & 94
LR-N07-0035, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate
LR-N16-0002, License Amendment Request to Amend Technical Specifications (TS) to Delete Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves (Srvs)
05000354/LER-2021-001, Safety Relief Valve (SRV) As-Found Setpoint Failures
DCL-89-226, Application for Amends to Licenses DPR-80 & DPR-82,revising Tech Specs 3.4.2.1,3.4.2.2,Table 3.7-2 & Associated Bases for Pressurizer & Main Steam Line Safety Valves
05000354/LER-1987-047, :on 871010,safety Relief Valve Failed to Close on Signal.Caused by Sand Blasting Grit in Solenoid Valve. Malfunctioning Target Rock Valve Replaced & Solenoids of Other Safety Relief Valves Inspected
05000275/LER-1986-018-01, :on 860830,pressurizer Code Safety Valves Found Out of Tech Spec Limit During Surveillance Test Procedure M-77.Caused by Failure to Drain Loop Seal Upstream of Valves Prior to Test
05000416/LER-1986-011, :on 860407,safety Relief Valve Inadvertently Lifted & Could Not Be Verified to Close within 2-minute Limiting Condition for Operation Time Limit.Unit Shut Down. on 860408,automatic Reactor Scram Actuated
05000341/LER-1986-013, :on 860513,10 of 15 RCS Safety/Relief Valves Failed Pressure Tolerance Surveillance Tech Spec Requirements.Cause Unknown.Valves Refurbished & Retested
05000354/LER-1998-008-02, :on 981115,ESFA Automatic Reactor Scram, Occurred.Caused by High Moisture Separator Level.Moisture Separator Drain Tank Dump Valves Were Tested Satisfactorily While Shutdown & Again During Restart
05000317/LER-1988-011, :on 881028,discovered That Pressurizer Code Safety Valve Performing Pressure Relief Function Above Max Value Allowed by Tech Specs.Caused by Difference in Temp Profile Conditions of Safety Relief Valves
05000341/LER-1998-010, :on 981007,SRV as Found Settings Exceed TS Setpoint Tolerance Criteria.Caused by Oxide Bonding Between Pilot Valve Disc & Seat.All 15 Pilot Valve Assemblies Were Replaced.With
05000341/LER-1997-017, :on 961025,multiple SRVs as-found Settings Were Outside of one-percent Tolerance Allowance Confirmed to Be corrosion-induced Bonding of Pilot Valve Disc & Seat.Pilots Replaced During Extended Fifth Refueling Outage
05000366/LER-1985-016, :on 850425,during Testing of Main Steam Safety Relief Valves,Four Valves Failed to Lift within Range Required by Tech Spec 3.4.2.1.Caused by Valve Pilot Setpoint Drift.Pilot Assemblies Refurbished & Retested
05000374/LER-1996-003-11, :on 960722,design Deficiency of Drywell Cooler Condensate Flow Rate Monitoring Sys,Discovered.Caused by Inadequate C/A to Eliminate long-standing Design Deficiency. Replaced Drywell Condensate Flow Rate Element
05000354/LER-1995-036, :on 951129,as Found Values for Safety Relief Valve Lift Setpoints Exceeded TS Allowable Limit.Caused by Corrosion Bonding of Pilot Disc to Pilot Seat.Srvs Inspected & Refurbished
05000445/LER-1991-026, :on 911030,discovered That Pressurizer Safety Valves Inoperable.On 911028,valves Found to Have Setpoints 1% to 4% Less than TS Setpoint Tolerance.Caused by Inadequate Methodology.Valves Reset
05000341/LER-1994-002, :on 940714,fifteen SRV Pilot Assemblies Were Removed During Fourth Refueling Outage.Caused by SRV Setpoint Pressure Upward Drift.All Fifteen SRV Pilot Assemblies Have Been Replaced
05000213/LER-1993-014, :on 930604,pressurizer Safety Valve Setpoint Drift Discovered During Surveillance Testing.Cause Unknown. Valves Readjusted & Satisfactorily Tested
LR-N16-0192, Response to Request for Additional Information Stuck Open Safety/Relief Valves
L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1
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
05000318/LER-1993-001-01, :on 930220,plant Found to Be in Condition Outside Design Basis When Pressurizer Code Safety Valve Found W/Lift Setpoints Due to Imprecision Associated W/Test Methodology.Valves Setpoints Will Be Verified
05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure
LR-N18-0065, Safety Relief Valve (SRV) As-Found Setpoint Failure
L-95-245, Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld
05000528/LER-1989-007, :on 890412,discovered Two of Four Pressurizer Code Safety Valves Out of Tech Spec Tolerance of 2,500 Psia Plus or Minus 1%.Caused by Performance Limitation.Valves Adjusted & Retested Satisfactorily
L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2
05000354/LER-2015-004, Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit
05000354/LER-2006-003, Re as Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable
05000354/LER-2004-009, Re as Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable
05000354/LER-2003-003, As Found Values for Safety Valve Lift Setpoints Exceed Technical Specification Allowable Limits
L-96-017, TER on Third 10-Yr Interval ISI Program Plan:Boston Edison Co,Pilgrim Nuclear Power Station
05000389/LER-1999-004, :on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With
05000354/LER-1995-004, :on 950308,determined That Items or Conditions Meeting Requirements of 10CFR50.73 Required to Be Reported Regardless of Any Other Notifications.Caused by Personnel Error.Reporting Requirements Reviewed
W3F1-2021-0024, Emergency Preparedness Documents
LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves