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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20199B4601998-01-20020 January 1998 Special Rept:On 980105,meteorological Monnitoring Instrumentation for Air Temp Delta T Inoperable for More than 7 Days.Caused by Breakdown in Wiring Between Junction Box at 199 Foot Level.Wiring Replaced ML20149K7781997-07-24024 July 1997 Special Rept:On 970520 & 0714,air Temp Delta T Channel Indicated Temp Difference Between Top & Bottom of Meteorological Tower.Caused by Reversed Input Wiring to Channel.Restored Air Temp Delta T Channel Operability ML20059C5011993-10-29029 October 1993 Special Rept:On 931019,meteorological Instrumentation Channel for Delta T Declared Inoperable.Caused by Ceased Aspirator Motor Located at Top of Tower.Motor Replaced ML20058H2841990-11-0303 November 1990 Special Rept:On 901101,control Rod 24 Found Disconnected from Drive Shaft.Drive Shaft Latching Will Be Initiated ML20058N6581990-08-13013 August 1990 Special Rept Re Diesel Fire Pump & Tank Inoperable for Greater than Seven Days for Draining,Cleaning & Insp.During Period Redundant Pumping Capacity Available Via Two Remaining Electric Driven Fire Pumps ML20056A1961990-08-0101 August 1990 Special Rept:Two Fire Pumps Inoperable at Same Time.Caused by Necessity to Accomplish Surveillance to Verify Capability to Start Pump on Emergency Diesel Generator 3 & Planned 18-month Insp of Diesel Per Tech Specs ML20245J8941989-08-11011 August 1989 Special Rept:On 890723,main Steam Line Area Radiation Monitor 2 Declared Inoperable Due to High Source Check Reading.Caused by Equipment Deterioration Resulting from Environ Conditions.Troubleshooting of Channel Initiated ML20247D9261989-07-21021 July 1989 Special Rept:On 890327,main Steam Line Monitors Inoperable for Greater than 7 Days.Caused by Normal Equipment Deterioration.Proposed Change 228 to Tech Specs 3.3.3.1, Addresses Actions to Be Taken If Monitors Become Inoperable ML20151Z0351988-08-19019 August 1988 Special Rept:On 880707,containment Fire Detection Instrumentation Left Out of Svc for Greater than 14 Days. Cause Can Not Be Determined Until Plant Shutdown & Reactor Missile Shield Removed to Access Detector Wire ML20133C4651985-09-0404 September 1985 Special Rept:On 850722,fire Detection Sys & Halon Automatic Suppression for Battery Rooms 1 & 2 Taken Out of Svc to Facilitate Const of New Battery Room Roof.Detection & Halon Sys Should Be Operable by 850913 ML20126C0141980-02-0101 February 1980 RO 50-29/80-8:during Surveillance Testing of Complete Circuit,Timers Failed to Operate.Caused by Timer Polarity Sensitivity.Installation Documentation Checked.Entire Circuit to Be Retested ML20136D0461979-09-11011 September 1979 RO 50-29/79-21:during Volumetric Examination of Steam Generator Feedwater Nozzle Areas,Unacceptable Welds Were Found.Welds Will Be Corrected Before Plant Startup ML20148K5311978-11-0909 November 1978 RO 50-29/78-30:on 781109,approx 100% Eddy Current Exam of Steam Generators 1 & 4 Revealed That 15 Tubes in Steam Generator 1 & 12 Tubes in Steam Generator 4 Have Degraded Tubes of More than 40% Wall Thickness ML20148K3901975-12-12012 December 1975 RO 50-29/75-16:on 751129,during Type C Containment Isolation Test,Leakage Detected from TV-409,vapor Container Sys Return Header Isolation Trip Valve.Caused by Valve Seating Surface Degradation.Valve Refurbished ML20148K3951975-12-12012 December 1975 RO 50-29/75-12:on 751114,calibr of Pressurizer Wide Range Level Instrument Found High Level Scram Bistable Setpoint Greater than Tech Specs Limit of 200 Inches.Caused by Instrument Setpoint Drift.Instrument Recalibr ML20148F2891974-12-11011 December 1974 Unusual Event:During ECCS Two Train Pump Flow Review, Accident Analysis Assumptions Not Supported by Data. Operation at or Below 11.6 Kw/Ft Will Maintain All Safety Margins.Westinghouse Investigating Problem ML20148J6091973-04-24024 April 1973 Ro:On 730410,during Plant Startup,Difficulty Experienced w/13 of 27 Incore Thermocouples.Detailed Engineering Review Conducted.Present Plans Are to Install New Sys During Next Refueling Outage ML20148J6241972-12-14014 December 1972 Ro:On 721103,following Routine Insp of Shim Rod S-18,efforts to Reinsert Component in Core Unsuccessful.Insp Revealed Abnormal Wear.Vendor Insp Revealed Worn Shroud Tubes.Repair Procedure Being Studied ML20148J3861972-12-12012 December 1972 Ro:On 721103,following Routine Insp of s-18 Shim Rod,Efforts to Reinsert S-18 in JK-45 Core Position Unsuccessful.Insp of Shim Rod Revealed Abnormal Wear Nine Inches Below Normal Block Wear ML20148J0621972-10-0404 October 1972 AO:721004,during Routine Surveillance Test,Diesel Generator 3 Failed to Start.Investigation in Process ML20148G7981969-09-0303 September 1969 Ro:During Third Quarter of CY69,exposure of Jr Young to Radiation Exceeded 10CFR20.101(c) Specs.Caused by Supervisor Negligence.Supervisor Suspended W/O Pay.Exposure Dose Discrepancies Investigated 1998-01-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C1311999-10-0808 October 1999 Safety Evaluation Supporting Amend 153 to License DPR-3 ML20211J5111999-08-31031 August 1999 Rev 29 to Yankee Decommissioning QA Program ML20211J3361999-08-27027 August 1999 Safety Evaluation Supporting Amend 152 to License DPR-3 ML20209D5391999-06-22022 June 1999 Rev 29 to Yaec Decommissioning QA Program ML20207F9491999-03-0505 March 1999 Safety Evaluation Supporting Amend 151 to License DPR-3 ML20202H5871999-02-0303 February 1999 Safety Evaluation Supporting Amend 150 to License DPR-3 ML20154P9691998-10-16016 October 1998 Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program ML20249A7901998-06-17017 June 1998 Safety Evaluation Supporting Amend 149 to License DPR-3 ML20216C4581998-02-27027 February 1998 Response to NRC Demand for Info (NRC OI Rept 1-95-050) ML20203L1931998-02-25025 February 1998 Duke Energy Corp,Duke Engineering & Svcs,Inc,Yankee Atomic Small Break LOCA Technical Review Rept ML20203L2451998-02-23023 February 1998 Assessment Rept of Engineering & Technical Work Process Utilized at De&S Bolton Ofc ML20203L1621998-02-18018 February 1998 Rept of Root Cause Assessment Review ML20203L2691998-02-16016 February 1998 Duke Engineering & Svcs Assessment Process Review Rept ML20199B4601998-01-20020 January 1998 Special Rept:On 980105,meteorological Monnitoring Instrumentation for Air Temp Delta T Inoperable for More than 7 Days.Caused by Breakdown in Wiring Between Junction Box at 199 Foot Level.Wiring Replaced ML20203J3001997-12-31031 December 1997 Ynps 1997 Annual Rept ML20217N0981997-08-21021 August 1997 LER 97-S02-00:on 970725,discovered Uncontrolled Safeguards Documents.Caused by Personnel Error.Matls Retrieved & Stored in Safeguards Repositories ML20210H0991997-08-0707 August 1997 LER 97-S01-00:on 970709,potential Compromise of Safeguards Info Occurred.Caused by Human error.Stand-alone Personal Computer & Printer Not Connected to Network,Have Been Located within Text Graphics Svc Dept ML20149K7781997-07-24024 July 1997 Special Rept:On 970520 & 0714,air Temp Delta T Channel Indicated Temp Difference Between Top & Bottom of Meteorological Tower.Caused by Reversed Input Wiring to Channel.Restored Air Temp Delta T Channel Operability ML20141E4671997-05-30030 May 1997 Rev 28 to Operational QA Program ML20135C8461996-12-31031 December 1996 Yankee Nuclear Power Station 1996 Annual Rept ML20132G6771996-12-20020 December 1996 Rev 27 to YOQAP-I-A, Operational QA Program ML20058N4771993-12-20020 December 1993 Rev 0.0 to Yankee Nuclear Power Station Decommissioning Plan ML20059K8491993-12-15015 December 1993 Clarifications to Pages 2,41,43 & 44 of 44 in Section I, Organization of YOQAP-I-A,Rev 24, Operational QA Program ML20059C5011993-10-29029 October 1993 Special Rept:On 931019,meteorological Instrumentation Channel for Delta T Declared Inoperable.Caused by Ceased Aspirator Motor Located at Top of Tower.Motor Replaced ML20056H1741993-06-10010 June 1993 Preliminary Assessment of Potential Human Exposures to Routine Tritium Emissions from Yankee Atomic Electric Co Nuclear Power Facility Located Near Rowe,Ma ML20237F1671993-02-19019 February 1993 Safety Evaluation Supporting Amend 147 to License DPR-3 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 ML20198D2541992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Recertification Program ML20198D2481992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Initial Certification Program ML20062H1981990-11-30030 November 1990 Plant Specific Fast Neutron Exposure Evaluations for First 20 Operating Fuel Cycles of Yankee Rowe Reactor ML20058H2841990-11-0303 November 1990 Special Rept:On 901101,control Rod 24 Found Disconnected from Drive Shaft.Drive Shaft Latching Will Be Initiated ML20058F2201990-11-0202 November 1990 Safety Evaluation Accepting Util Response to Generic Ltr 83-28 Re post-trip Review - Data & Info Capability ML20062E8331990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Yankee Atomic Power Station ML20058G1471990-10-31031 October 1990 Vol 2 to Star Methodology Application for PWRs Control Rod Ejection Main Steam Line Break ML20058C4061990-10-22022 October 1990 Safety Evaluation Supporting Amend 137 to License DPR-3 ML20062B6751990-09-30030 September 1990 Monthly Operating Rept for Yankee Atomic Power Station for Sept 1990 ML20059G2411990-09-0606 September 1990 Safety Evaluation Supporting Amend 135 to License DPR-3 ML20059E3071990-08-31031 August 1990 Safety Assessment of Yaec 1735, Reactor Pressure Vessel Evaluation Rept for Yankee Nuclear Power Station. Detailed Plan of Action W/Listed Elements Requested within 60 Days After Restart to Demonstrate Ability to Operate Longer ML20059E8001990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Yankee Atomic Power Station ML20058P7841990-08-14014 August 1990 Part 21 Rept Re Misapplication of Fluorolube FS-5 Oil in Main Steam Line Pressure Gauges.All Four Indicators Replaced W/Spare Gauges Which Utilize High Temp Silicone Oil ML20058N6581990-08-13013 August 1990 Special Rept Re Diesel Fire Pump & Tank Inoperable for Greater than Seven Days for Draining,Cleaning & Insp.During Period Redundant Pumping Capacity Available Via Two Remaining Electric Driven Fire Pumps ML20058L0321990-08-0202 August 1990 Safety Evaluation Supporting Amend 133 to License DPR-3 ML20058L6651990-08-0202 August 1990 Safety Evaluation Supporting Amend 134 to License DPR-3 ML20056A1961990-08-0101 August 1990 Special Rept:Two Fire Pumps Inoperable at Same Time.Caused by Necessity to Accomplish Surveillance to Verify Capability to Start Pump on Emergency Diesel Generator 3 & Planned 18-month Insp of Diesel Per Tech Specs ML20055G6801990-07-31031 July 1990 Yankee Plant Small Break LOCA Analysis ML20055G7011990-07-31031 July 1990 Yankee Nuclear Power Station Core 21 Performance Analysis ML20055E1591990-07-31031 July 1990 Reactor Pressure Vessel Evaluation Rept ML20055J3221990-07-25025 July 1990 Decommissioning Funding Assurance Rept & Certification ML20055G7051990-07-19019 July 1990 Rev 0 to Yankee Cycle 21 Core Operating Limits Rept ML20055F6751990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Yankee Atomic Power Station 1999-08-31
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YAlllWE ATOMIC E!ECTWC 00DPAllY e ,. ,f Eh>
Rowe, Massachusetts 01367
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Mr. J. P. O' Reilly, Di rector U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue x'~x.~
King of Prussia, Pennsylvania 19406 ~-
Subject:
Reportable Occurrence 50 29/75-12 '
Pressurizer W.R. Level Sc' ram Instrument Setpoint Drift
Dear Mr. O'Reilly:
In accordance with Technical Specifications, Section E.2.b. ,
the attached Licensee Event Report is hereby subr.litted.
Very truly yours, ,
h gir) 0 lb Herbert A. Autio -
Plant Superintendent JLS/jb Enclosure cc: (40) Director, Office of Inspection crid Enforcement U.S. iluclear Regulatory Commission .
Washington, D. C. 20555 (3) Director, Office of Management Information & Program Control 0.S. fluclear Regulatory Commission
--. Washington, D. C. 20555 ,
THIS DOCUMENT CONTAINS P00R QUALITY PAGES t
l 801204'O k W p 14012 i
[
s y LICENSEE EVENT REPORT. <
i CONTROL B'.0CK:l p* l l l l l [{I.EACE PRINT All. RE
. ; 1 6 s NA E LICENSE NUMDER YE TYPE
? 01 lM l A lY l K l Rl'll l0 l0 l-l0 l 0 l 0 l Ol 0l-l0 l0 l l 4 l1 l1 l1 l1l l Ol1 l j 7 89 ,14 - 15 25 26 30 31 32
. CATEGORY TY P S E D CKET NUMDER EVENT DATE REPORT OATE-lll2111217l5l l Ol Sl0 l-101012 l 91 11 l1 11 14 l7 151 01 CorrT l l l [LJ lLl 7 8 57 58 59 EO G1 68 09 74 75 60
, EVENT DESCR:PTION
@ l During noral refueling operations a calibration of the pressurizer wide range level 'l 7 89 80 '
35 l instrument found the hich level scram histable setooint areater thar the Technical I 7 89 80 3E l Snacification lir,i t of 900 inchot This enns ti tutos a violation of Technical l
[ 7 89 80 f @ l Specification Section E.2.b.(1) and is reported as Reportable Occurrence 50-29/75-12.l 7 89 80 l
o I I 7 89 payg 80 DE C E COMPONENT CCOE MANU CU R VIOLATON
, M LI I B l [E_) li lN ISITl RI Ul lN I lWlll2l01 l Yl 7 89 10 11 iP 17 43 44 47 48 CAuSE DESCR:PTION DE lThe Westinghouse 957D633, Gr.1, Standard Bistable Assembly used for thS Pressurizer i 7 89 80 '
EUE IUide Rance Level Scram tricoed at 203 inches vice the Technical Specification limit of}
7 89 80 3 19nn in This '.'es attributed to instrument setnoint drift. The instrument was l FA0tuTY METHOO OF STATUS % P /.'ER OTHEA STATUS 0:$00VERY DISCOVERY DESORPTON IIE lHl lol01Ol l UA I Lbj l NA l, 7 8 9 10 12 13 44 45 48
- EO FCRM OF ILE CED C AMOUNT OF ACTMTY LOCATON OF RELEASE 7 8 12 9
(Z_l LZ.]b 10 11 I 31NAl l 44 45 l NA l-80 PERSONNEL EXPCE:ES f NUMCER Tf;I CISOR PTION 1 1010l 0] lZl l NA Jl 7 89 11 12 13 80 l PERSONNEL INJUA ES Nut /eER CEs;::T :N ,
1 7 89 l 010l Ol 11 12 l ':A ll 60 i OFFSITE CONSECUENCES gg l NA ll 7 89 80 !
LOSS 04 DAMAGE TO FAC:LITY '
TYFE CESO A D l'
i3 7 89 hl 10 UA 80 PUBLICITY 1 l NA lt 7 89 80 l i
ADDiTICNAL FACTC: 6 1c l Cause Descriptic1 (cont'd): recalibrated and tested satisfactorily. ll 7 89 80 ml
? 89 W1i; NAYE. 0' h ,y A M 10NE413-625-61 @ ' i r.P 0 881.tG7 I
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' ~ NRC D(.CfRIBUTION FOR PART 50 DOCKET"rcATE * '
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. CONTROL NO: '14012 i a :
FILE:
I FROM: Yankee Atomic Elec. Co. DATE OF DOC DATE REC'D LTR TWX RPT OTHER Rowe, Mass;. - ~
H.A. Autio 12-12-75 12-17-75 XXX -
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ORIG CC OTHER SENTNRC POR XXX I
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XXX 40 50-29 .
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DESCRIPTION: ENCLOSUREC:
Letter trans the following. . . . . . . -
s Licensee Event Report # 75-12, on 11-14-72
.Concerning.a calibration of.the pressurizs
' wide range.leve,1 f.nstrument exceeding:the!
Tech. Specs....... ,, ,
(40.Cys. Received)- '
t PLANT NAME: Yankee Rowe -
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