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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
[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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60 61 DOCKET NUMBER 68 69 EVF,NT DATE 14 75 REPORT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l While at cold shutdown for a refueling outage, performance of sur- I g
veillance Test 3PC-R4 (Pressurizer pressure calibration) indicated that l g , l pressure transmitters PT-456, PT-457 and PT-474 were out of specifica- l g 3 g tion on the non-conservative side at a test pressure of 1800 PSIG. Worst l g 3 l case analysis determined that under these conditions, the low pressure l y o l,; ; reactor trip signal would occur at a system pressure of 1797 PSIG, which l
,gg; is below the 1800 PSIG limit set by Technical Specification 2.3.1.B.3. I DE CODE S BC E COMPONENT CODE SUBC dE S E
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, , l necessary under the Technical Specifications. Transmitters PT-456, i PT-457 and PT-474 (Foxboro E11CM-SAEI) were calibrated to within l g
acceptable limits. Similar events occurred on November 11, 1980(LER- l
, g 80-015/03L-0) and August 1, 1978(LER 78-021/03L-0). l 7 8 3 80 STA S % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION l1 15l W @ l0l0l0l@ L NA l (A_jh! ENGINEERING REVTFW l ACTivlTY Co TENT RFLE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l l NA l li lo !8 Lz_J 7 9
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FLOYD W. CDtBLE 914-739-8200,X217 E, NAME OF PREPAHER PHONE:
8 ATTACHMENT 1
.LER 82-003/01T-0 Power Authority of the Docket No. 50-286 State of New York The plant was in the cold shutdown condition during a refueling outage.
On April 15, 1982, performance of Surveillance Test 3PC-R4 (Pressurizer Pressure Calibration) indicated that Pressure Transmitters PT-456, PT-457 and PT-474 were out of specification in the non-conservative direction at a test pressure of 1800 psig.
As the plant was in the cold shutdown condition, no immediate action was required under the Technical Specifications. Transmitters PT-456, PT-457 and PT-474 (Foxboro Ell GM-SAE1) were calibrated to within acceptable limits and returned to service. Preliminary engineering analysis determined' that all three transmitters were set conservatively with respect to Safety Injection Initiation setpoints, but were non-conservative with respect to Low Pressurizer Pressure reactor trip setpoints by 12, 3 and 4.3 psi, respectively. This is a worst case condition, in that the derivative rate action circuitry associated with the pressurizer pressure logic would anticipate the trip and normally. respond sooner.
The Low Pressurizer Pressure setpoint is 1800 psig according to Technical Speci-fication 2.3.1.B.(3). Examination of plant operation records confirmed that at no time during the period since the last performance of this surveillance test did pressurizer pressure approach 1800 ps!g with the reactor critical.
The effect on the overtemperature delta-T trip setpoint, which also utilizes the pressurizer pressure signals, was as follows: pressure transmitters PT-455 and PT-456 were found to be set non-conservatively, thereby lowering the redundancy designated by Technical Specification Table 3.5.2., Item 3, from 2 to 0.
Two out of the four channels required for reactor trip remained _ operable at all times.
The cause of this incident was determined to be instrument drif t. Similar events, involving the failure of only a single transmitter occurred on November 1,1980 (LER 80-015/03L-0) and August 1,1978 (LER 78-021/03L-0).
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05000286/LER-1982-001, Forwards LER 82-001/01T-0 | Forwards LER 82-001/01T-0 | | 05000286/LER-1982-002, Forwards LER 82-002/01T-0 | Forwards LER 82-002/01T-0 | | 05000286/LER-1982-003, Forwards LER 82-003/01T-0 | Forwards LER 82-003/01T-0 | | 05000286/LER-1982-004, Forwards LER 82-004/01T-0 | Forwards LER 82-004/01T-0 | | 05000247/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | 05000247/LER-1982-012, Forwards LER 82-012/03L-0 | Forwards LER 82-012/03L-0 | | 05000247/LER-1982-015, Forwards LER 82-015/03L-0 | Forwards LER 82-015/03L-0 | | 05000247/LER-1982-016, Forwards LER 82-016/03L-0 | Forwards LER 82-016/03L-0 | | 05000247/LER-1982-018, Forwards LER 82-018/03L-0 | Forwards LER 82-018/03L-0 | | 05000247/LER-1982-019, Forwards LER 82-019/03L-0 | Forwards LER 82-019/03L-0 | | 05000247/LER-1982-020, Forwards LER 82-020/03L-0 | Forwards LER 82-020/03L-0 | | 05000247/LER-1982-021, Forwards LER 82-021/03L-0 | Forwards LER 82-021/03L-0 | | 05000247/LER-1982-022, Forwards LER 82-022/03L-0 | Forwards LER 82-022/03L-0 | | 05000247/LER-1982-023, Forwards LER 82-023/03L-0 | Forwards LER 82-023/03L-0 | | 05000247/LER-1982-024, Forwards LER 82-024/03L-0 | Forwards LER 82-024/03L-0 | | 05000247/LER-1982-025, Forwards LER 82-025/03L-0 | Forwards LER 82-025/03L-0 | | 05000247/LER-1982-026, Forwards LER 82-026/03L-0 | Forwards LER 82-026/03L-0 | | 05000247/LER-1982-027, Forwards LER 82-027/03L-0 | Forwards LER 82-027/03L-0 | | 05000247/LER-1982-028, Forwards LER 82-028/03L-0 | Forwards LER 82-028/03L-0 | | 05000247/LER-1982-029, Forwards LER 82-029/03L-0 | Forwards LER 82-029/03L-0 | | 05000247/LER-1982-030, Forwards LER 82-030/03L-0 | Forwards LER 82-030/03L-0 | | 05000247/LER-1982-031, Forwards LER 82-031/99X-0 | Forwards LER 82-031/99X-0 | | 05000247/LER-1982-032, Forwards LER 82-032/01T-0 | Forwards LER 82-032/01T-0 | | 05000247/LER-1982-033, Forwards LER 82-033/99X-0 | Forwards LER 82-033/99X-0 | | 05000247/LER-1982-034, Forwards LER 82-034/03L-0 | Forwards LER 82-034/03L-0 | | 05000247/LER-1982-035, Forwards LER 82-035/03L-0 | Forwards LER 82-035/03L-0 | | 05000247/LER-1982-036, Forwards LER 82-036/03L-0 | Forwards LER 82-036/03L-0 | | 05000247/LER-1982-038, Forwards LER 82-038/03L-0 | Forwards LER 82-038/03L-0 | | 05000247/LER-1982-039, Forwards LER 82-039/03L-0 | Forwards LER 82-039/03L-0 | | 05000247/LER-1982-040, Forwards LER 82-040/03L-0 | Forwards LER 82-040/03L-0 | | 05000247/LER-1982-041, Forwards LER 82-041/03L-0 | Forwards LER 82-041/03L-0 | | 05000247/LER-1982-042, Forwards LER 82-042/03L-0 | Forwards LER 82-042/03L-0 | | 05000247/LER-1982-043, Forwards LER 82-043/03L-0 | Forwards LER 82-043/03L-0 | | 05000247/LER-1982-044, Forwards LER 82-044/03L-0 | Forwards LER 82-044/03L-0 | | 05000247/LER-1982-045, Corrected LER 82-045/01T-0:on 821108,insp Revealed That Upper End Plug from Fuel Rod within Assembly Separated from Fuel Tube.Cause Not Stated.Assembly Replaced | Corrected LER 82-045/01T-0:on 821108,insp Revealed That Upper End Plug from Fuel Rod within Assembly Separated from Fuel Tube.Cause Not Stated.Assembly Replaced | | 05000247/LER-1982-046, Forwards LER 82-046/03L-0 | Forwards LER 82-046/03L-0 | | 05000247/LER-1982-047, Forwards LER 82-047/03L-0 | Forwards LER 82-047/03L-0 | | 05000247/LER-1982-048, Forwards Updated LER 82-048/03X-1 | Forwards Updated LER 82-048/03X-1 | | 05000247/LER-1982-049, Forwards LER 82-049/99X-0 | Forwards LER 82-049/99X-0 | | 05000247/LER-1982-050, Forwards LER 82-050/03L-0 | Forwards LER 82-050/03L-0 | |
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