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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20024E2111983-07-20020 July 1983
Ro:On 830622,24 & 0711,PAB & Electrical Tunnel & Control Room & Cable Spreading Room Determined to Be Nonfunctional Due to Voids & Cracks in Coating of Penetration Fire Barriers
ML20052H1801982-05-12012 May 1982
Telecopy of Ro:On 820415,surveillance Test 3PC-R4 Indicated That Pressure Transmitters PT456,PT457 & PT454 Were Out of Spec Nonconservatively.Cause Not Stated
ML20051P5321982-05-0606 May 1982
RO 82-17:on 820505,air Conditioning Sys,Booster Fans for Filter Operation & Cooling Water Supply Declared Inoperable Due to Motor Failures.Also Reported Per Part 21
ML20050C2701982-03-29029 March 1982
Telecopy Message of Ro:On 820327,small Leak Discovered on Shell Side of Steam Generator 32 W/Reactor in Cold Shutdown Constituting Abnormal Degradation in Primary Containment Boundary.Cause Not Stated.Investigation Continuing
ML20050A4471982-03-25025 March 1982
Telecopy Version of Ro:On 820324,small Primary to Secondary Leak Developed in Steam Generator 33.Generator Removed from Svc & Unit Proceeding to Cold Shutdown.Total Release to Atmosphere Was Less than 0.5 Ci,W/No Iodine Released
ML20042A6641982-03-11011 March 1982
Ro:Operating Procedures Will Be Revised to Require Operability of Safeguards Equipment Necessary to Mitigate Steamline Break Transient Prior to Heating RCS Above 350 F from Cold Shutdown
ML20042A5681982-03-0808 March 1982
RO 82-009:on 820305,nitrogen Pressure in Boron Injection Tank Observed Below 90 Psig.Caused by Failure of Two Nitrogen Pressure Regulator Valves.Procedure Changed.Also Reported Per Part 21
ML20039A7621981-12-0909 December 1981
Ro:On 811208,pint Per Minute Leak Observed in Cooling Coil in Number 34 Fan Cooler Unit Motor Cooler Inside Containment.Cause Not Stated.Approved Repairs Were Immediately Performed & Leak Was Stopped
ML20011A4671981-09-29029 September 1981
Ro:On 810923,after Verifying Primary to Secondary Leakage in Number 31 Steam Generator Following RCS Hydro,Unit Proceeded from Hot Shutdown to Cold Shutdown.Verification of Calculation for Determining Leak Size Exceeded Tech Specs
ML20010G8311981-09-0808 September 1981
Ro:On 810731,transformer 11EC4 Taken Out of Svc for Repair, Deactivating Bus Section 4 Which Feeds Motor Driven Fire Pump 12.On 810801,temporary Svc Restored to Fire Pump,But W/O Automatic Start.Transformer 11EC4 Back in Svc 810819
ML18085B1681980-10-17017 October 1980
RO 80-054/01P-0:on 801016,fire Pump Failed to Start on Receipt of Automatic Signal.Situation Recurred Following Day.Cause of Failures Is Undetermined
ML0935608181977-01-12012 January 1977
RO 76-2-28(A):on 761214,boric Acid Storage Tanks Had Concentrations in Excess of Upper Limit.Caused by Inaccuracies in Sampling Technique of Concentrates Makeup to Boric Acid Storage Tanks
1983-07-20
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Category:LER)
MONTHYEARML20024E2111983-07-20020 July 1983
Ro:On 830622,24 & 0711,PAB & Electrical Tunnel & Control Room & Cable Spreading Room Determined to Be Nonfunctional Due to Voids & Cracks in Coating of Penetration Fire Barriers
ML20052H1801982-05-12012 May 1982
Telecopy of Ro:On 820415,surveillance Test 3PC-R4 Indicated That Pressure Transmitters PT456,PT457 & PT454 Were Out of Spec Nonconservatively.Cause Not Stated
ML20051P5321982-05-0606 May 1982
RO 82-17:on 820505,air Conditioning Sys,Booster Fans for Filter Operation & Cooling Water Supply Declared Inoperable Due to Motor Failures.Also Reported Per Part 21
ML20050C2701982-03-29029 March 1982
Telecopy Message of Ro:On 820327,small Leak Discovered on Shell Side of Steam Generator 32 W/Reactor in Cold Shutdown Constituting Abnormal Degradation in Primary Containment Boundary.Cause Not Stated.Investigation Continuing
ML20050A4471982-03-25025 March 1982
Telecopy Version of Ro:On 820324,small Primary to Secondary Leak Developed in Steam Generator 33.Generator Removed from Svc & Unit Proceeding to Cold Shutdown.Total Release to Atmosphere Was Less than 0.5 Ci,W/No Iodine Released
ML20042A6641982-03-11011 March 1982
Ro:Operating Procedures Will Be Revised to Require Operability of Safeguards Equipment Necessary to Mitigate Steamline Break Transient Prior to Heating RCS Above 350 F from Cold Shutdown
ML20042A5681982-03-0808 March 1982
RO 82-009:on 820305,nitrogen Pressure in Boron Injection Tank Observed Below 90 Psig.Caused by Failure of Two Nitrogen Pressure Regulator Valves.Procedure Changed.Also Reported Per Part 21
ML20039A7621981-12-0909 December 1981
Ro:On 811208,pint Per Minute Leak Observed in Cooling Coil in Number 34 Fan Cooler Unit Motor Cooler Inside Containment.Cause Not Stated.Approved Repairs Were Immediately Performed & Leak Was Stopped
ML20011A4671981-09-29029 September 1981
Ro:On 810923,after Verifying Primary to Secondary Leakage in Number 31 Steam Generator Following RCS Hydro,Unit Proceeded from Hot Shutdown to Cold Shutdown.Verification of Calculation for Determining Leak Size Exceeded Tech Specs
ML20010G8311981-09-0808 September 1981
Ro:On 810731,transformer 11EC4 Taken Out of Svc for Repair, Deactivating Bus Section 4 Which Feeds Motor Driven Fire Pump 12.On 810801,temporary Svc Restored to Fire Pump,But W/O Automatic Start.Transformer 11EC4 Back in Svc 810819
ML18085B1681980-10-17017 October 1980
RO 80-054/01P-0:on 801016,fire Pump Failed to Start on Receipt of Automatic Signal.Situation Recurred Following Day.Cause of Failures Is Undetermined
ML0935608181977-01-12012 January 1977
RO 76-2-28(A):on 761214,boric Acid Storage Tanks Had Concentrations in Excess of Upper Limit.Caused by Inaccuracies in Sampling Technique of Concentrates Makeup to Boric Acid Storage Tanks
1983-07-20
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8501999-10-14014 October 1999
Safety Evaluation Supporting Amend 197 to License DPR-64
ML20206U2551999-02-0909 February 1999
Safety Evaluation Supporting Amend 187 to License DPR-64
ML20236Y1571998-08-0303 August 1998
Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated
ML20236V4281998-07-13013 July 1998
Safety Evaluation of TRs WCAP-14333P & WCAP-14334NP, PRA of RPS & ESFAS Test Times & Completion Times. Repts Acceptable
ML20236T5511998-06-24024 June 1998
Consolidated Edison Co of Ny,Indian Point Unit 2,Drill Scenario Number 1998C
ML20248B2371998-03-31031 March 1998
Revised Monthly Operating Rept for March 1998 for Indian Point Station Unit 2
ML17264A9381997-07-10010 July 1997
Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process
ML18153A1431997-06-10010 June 1997
Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem
ML20210E3591997-03-27027 March 1997
Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A
ML1005008001997-02-28028 February 1997
Conditional Extension of Rod Misalignment TS for Indian Point 3.
ML20115J3981996-07-22022 July 1996
Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl
ML20096E5101995-12-31031 December 1995
Resubmitted Rev 13 to QA Program
ML17059A3611994-07-0606 July 1994
Emergency Action Level Verification & Validation Rept.
ML17311A0181994-05-13013 May 1994
New York State EAL Upgrade Project Verification & Validation Rept.
ML20029C7801994-03-31031 March 1994
Monthly Operating Rept for Mar 1994 for Indian Point Unit 1. W/940415 Ltr
ML20056E5171993-08-31031 August 1993
Technical Review Rept, Tardy Licensee Actions
ML20062J2281993-07-23023 July 1993
Consolidated Edison Co of Ny Indian Point Unit 2,Drill Scenario 1993
ML20118A2681992-12-31031 December 1992
Consolidated Edison Co of Ny Indian Point,Unit 2 Exercise Scenario,1992
ML20125C7161992-12-0707 December 1992
Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML20096H2301992-05-21021 May 1992
Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested
ML20079F9181991-05-31031 May 1991
Structural Evaluation of Indian Point,Units 2 & 3 Pressurizer Surge Lines,Considering Effects of Thermal Stratification
ML20059E9461990-08-31031 August 1990
Nonproprietary Rev 2 to Indian Point 2 Tube Fatigue Reevaluation
ML20059G2011990-07-31031 July 1990
Final Rept on Steam Generator Insp, Repair & Restoration Efforts During 1990 Midcycle Insp
ML20058K4151990-06-30030 June 1990
Steam Generator Insp,Repair & Restoration Program Presentation to Nrc
ML20058K4121990-06-30030 June 1990
Status Rept,Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to Nrc
ML20043A4891990-05-30030 May 1990
Nonproprietary Indian Point Unit 2 Steam Generator Insp, Repair & Restoration Program.
ML20042F1441989-12-31031 December 1989
New York Power Authority Annual Rept for 1989. W/900430 Ltr
ML19332B9371989-11-30030 November 1989
Nonproprietary Info Presented to NRC Re Indian Point Unit 2 Steam Generator Secondary Side Loose Objects.
ML19332D6661989-10-31031 October 1989
Nonproprietary Rev 2 to Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage.
ML20247J8161989-07-31031 July 1989
Safety Evaluation for UHS Temp Increase to 95 F at Indian Point Unit 3
ML20248B3171989-06-30030 June 1989
Rev 1 to Nonproprietary WCAP-12294, Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept,Spring 1989 Outage
ML20248D3631989-06-30030 June 1989
Rev 1,to Indian Point Unit 3 Reactor Vessel Fluence & Ref Temp PTS Evaluations
ML20247N5331989-05-31031 May 1989
Nonproprietary Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage
ML20247J8071989-05-31031 May 1989
Containment Margin Improvement Analysis for Indian Point Unit 3
ML20247G5171989-04-30030 April 1989
Monthly Maint Category I Rept Pages from Monthly Operating Rept for Apr 1989 for Indian Point
ML20244C3311989-04-10010 April 1989
Safety Evaluation Supporting Amend 137 to License DPR-26
ML20248F4211989-03-31031 March 1989
NSSS Stretch Rating-3,083.4 Mwt Licensing Rept
ML20235V5931989-03-0202 March 1989
Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed
ML20248F3001988-12-31031 December 1988
10CFR50.59(b) Rept of Changes,Tests & Experiments Completed in 1988
ML20246E2711988-12-31031 December 1988
Con Edison 1988 Annual Rept
ML20196D3011988-10-31031 October 1988
Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V
ML20155H2541988-09-30030 September 1988
Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp Locations
ML20154M5661988-08-31031 August 1988
Monthly Operating Rept for Aug 1988 for Indian Point Station Unit 2
ML20154M5691988-07-31031 July 1988
Revised Page to Monthly Operating Rept for Jul 1988 for Indian Point Station Unit 2
ML20151N7881988-07-31031 July 1988
Rev 1 to Charpy Toughness & Brittle Transition Temp Characterization of HAZ High Hardness Zone of Indian Point Unit 2 Steam Generator Girth Weld by Gleeble Weld Thermal Cycle Simulation
ML20006B4741988-05-31031 May 1988
Nonproprietary Indian Point Unit 2 Evaluation for Tube Vibration Induced Fatigue.
ML20151N7821988-05-31031 May 1988
Fracture Sensitivity Study of Girth Weld 6 Repaired Configuration,Indian Point Unit 2
ML20153F9161988-04-28028 April 1988
Changes,Tests & Experiments - 1986
ML20151T4681988-01-31031 January 1988
Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness
1999-02-09
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- O 33 SusSEQUENT INVESTIGATION (CONCLUDED AT 2358 HOURS) INDICATED A g SitAM GENERATOR LEAK RATE OF APPROXIMATELY 1.8GPP aHICH IS IN EXCESS OF TML 0.3GPM LIMIT SET BY TECHNICAL SPECIFICATION 3.1.F.e AN UNUSUAL EVENT aAS DECLARE AT 358 H URS AN ALL NRC AN PU6LIC NCTIFICATIONS g 10 WEHE MADE AS PEH THE EMERGENCY PLAN HY 0147 HOURS ON MARCP 25 THE
- GENERATOW nAS HEMOVED FROM SERVICE BY 0225 HOURS ALL CONTROL RODS
!O WERE FULLY INSERTED AND THE UNIT nAS PROCEEDING TO TFE COLD SHUTDOWN g CONDITION IN ACCORDANCE aITH TECHNICAL SPECIFICATION REQUIREMENTS TOTAL RELEASE TO THE ATMOSPHERE aAS DETERMINED TO BE.LESS.THAN 5 O CURIES (CALCutATED .u2 Curies) F0s N0etE GAS CHErISTRY SAsptES ,
INDICAltD THAT NO IUDINE RELEASE OCCURHED THIS TELEGRAM SERVES AS A 24 POUR NOT IF IC ATION REQUIRED BY TECHNICAL SPECIFICATION 6.Q 1.7.C O JC oHONS RESIDENT MANAGER INDIAN POINT THREE NUCLEAR POWER PLANT PO NOA 215 g
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