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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
[Table view] 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
[Table view] 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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- Chr.rtu W. J ckson va r, w t consoacwa Ecmn om./ d Wa Yp W heian Po ni %':or b'Cd'jhay #2 Ok J'k Py Ave Buchanan. NY 10511 Tetephone (914 73/ M116 May 6, 1982 Re: Indian Poi No. 2 Docket ' S- 'l '7'
'; 's /
Mr. Ronald C. Haynes - -
Regional Administrator 2 ' /p (g.Q, il O Region I 9-! /, -
U.S. Nuclear Regulatory Commission 1 AF f 9^f j 631 Park Avenue -
- O King of Prussia, PA 19406 T$( /
Dear Mr. Haynes:
4 W N
- 1. In accordance with the Technical Specifications of Facility Operating License No. DPR-26, the following confirms notification on May 5, 1982 to Mr. Walter Baunack and Mr. Ted Rebelowski of your office, by Mr. Kevin Burke of Consolidated Edison, of a
/ , ,, gpotential Reportable Occurrence, LER 8 2-17, of the type defined
+.
in Technical Specification, Section 6.9.1.7.le.
Indian Point Units 1 and 2 have a common central control room but have separate air conditioning systems. The design provided that the functional capability of the control room shall be maintained at all times inclusive of accident conditions.
Unit 1 and Unit 2 air intake ducts will isolate upon receipt of a manual, high control room radiation or safety injection signal from Unit 2. Concerns had developed about the ability of certain components in the Unit 1 and 2 air conditioning systems to function. These components included dampers and their associated activators for Units 1 and 2, the Unit 2 air conditioning fan motor, the two Unit 2 booster fans for filter operation, and the cooling water supply to the Unit 1 cooler.
While some of these components are not required to operate during accident conditions, the booster fans, one of which is assumed to be functional in the accident analyses contained in the FSAR, were declared inoperable due to motor failures.
On May 5, 1982, maintenance work was performed on these systems to assure that they would operate as specified in the FSAR. The Licensee Event Report will provide additional information concerning the ability of components of the Unit 1 and 2 air conditioning systems to operate and the corrective actions taken. We will continue to keep the NRC Resident Inspectors informed of our findings with respect to the air conditioning systems.
82 0 517 0 39e
-13
$90 t
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l Mr. Ronald C. Haynes May 6, 1982 Consolidated Edison believes that this' report also satisfies the requirement of 10CFR Part - 21.
Very truly yours, ivt - Y
.tCharles W. Jackson cc: Mr. William Mcdonald, Director (2 copies)
Office of Management Information and Program Control c/o Distribution Services Branch, DDC, ADM U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. T. Rebelowski, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 28 4
Buchanan, New York 10511
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