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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 ML20198D2481992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Initial Certification Program ML20198D2541992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Recertification 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 ML20058L6651990-08-0202 August 1990 Safety Evaluation Supporting Amend 134 to License DPR-3 ML20058L0321990-08-0202 August 1990 Safety Evaluation Supporting Amend 133 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 ML20055E1591990-07-31031 July 1990 Reactor Pressure Vessel Evaluation Rept ML20055G7011990-07-31031 July 1990 Yankee Nuclear Power Station Core 21 Performance Analysis 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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,,,. , n . s , n YAN/WE MOMiG ELECLIC COMPANY h
WYT. 74-52 r__7__'*
20 Turnpske Road Wessborough, Mossochusetts 01581
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Deceinber 11, 1974 E,_- . U '"
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Unitod States Ator.ic Ir. orgy Consnission ~
Directorate of P.egulatory Cperations .
Region I G31 Park Avenue k
King of' Prussia, Pennsylvania 19406
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Attention. James P. o'neilly, Director THIS DOCUMENT CONTAINS neference, ueense so. DPR-3 (Docket No. 50-29)
D*ar Sir: ~
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In accordance with Section E.2.b, Appendix "A" Technical Speelfications of the Reference License the following Unusual Event is reported. k I
A review of ECCS two train pump flow indicated that the data did not support the assumptions used in the accident analysis. In fact, the flow ((
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for two of the three trains as determined from s;hield tank cavity level change followst and the average flow as measured by the flow instrumentation is as . .
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cavity Level change Ins trurwnta tion I
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Tratna 1 ard 2 2290 vpm 2100 gpm 1-Trains 2 and 3 2278 gpm i Trains 1 and 3 2220 gra -
2271 gpa 2320 gpn hse VCues are consistent with the initial design criteria .
energency core cooling system. However, for the
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Westinghouce in the Eccs analysis was 2400 gpm.theThis two was trainanpump input flow used by error. }
The taxh allovable peak linear heat generation rate calculated for the Yankee Rove core using this erroneous value was 13.06 kv/ft.
When this error was veri.fied, the plant was administratively derated to 90 % o f f ull powe r (a resultant power level of $40 MVt) as a conservative (
wacure pending further investigation. This investigation by Yankee Atomic Eloctric Corpany has concluded that operation at er below 11.6 kv/f t will conservatively r.aintain all safety margins previously indicated in the Et"TS cnalyses.
In-core teeasurnments at the plant verity that the 11.6 kw/f t linear heat generation rate lini,t will not be exceeded by operation at 1004 plant output (600 MWt). Plant output was accordingly increased to icos on December 9,1974.
h Directorate of Licensing was inforr.ed of the i
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United States Atonic Energy Cersnission Deceanber 11, 1974 Attns James P. O'Reilly, Director page Two probica and Yankee Atoetic Electric coespany inmediately began preparation of a cupplerent to our Proposed Change No.117 to account f'or the error.
A review of Core M' operating data confirms that the peak linear heat generation rate did not exceed 11.6 kw/f t durin7 that cycle. During the i period. between Septear.ber 9,1974, and Decociser 6, 1974, the conservative
- I limit of 11.6 kw/f t was exceeded at some points. -It should be recognized E that until the results of a revised ECCS analysis are available, it cannot i be concluded that the operating conditions during that period were such l that the applicable ICCS criteria were, in fact, not met. , l We are currently discussing the problem with Westinghouse and desire to have a revised analysis perforr.ed as soon as possible. The resulta vill be submitted to the Directorate of Licensing as soon as they are -
availcble and we shall keep the Dire ctorate of Licensing inforned as to r.chedule . .
.Very truly yours, .
~
YAMKEE ATONIC ELECTRIC ANY -
L. H. Raider Asst. Vice President.
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' ** EC DIST, UTIDN FOR ? ART 50 DOCKET .1kRI AL, (T E T.;F O R A R Y. F O R T.;) l CONTROL NO: 127h3 FILE: m !
DATE OF COC D ATE R EC'D LTR T'.'lX RPT OTHER FRO?.1: Yankee Atomic Elec. Co.
Westborough, Mass. 01581 X !
12 11-7h 19-18 7h u n,, y ,, .
CC OTHER SENT AEC PDR XX ORIG To. '
1 SENT LOCAL PDR E DRO PROPINFO INPUT NO CYS REC'D DOCKET NO: .
CLAS$ U ! CLASS 1 50-29 XXX Ltr reporting an Unueual Event ENCLOSURES:
DESCRI?TiO:::
involving ECCS two train pump flow indicated in that the data did not support the assumptions ased in the accident analysis..... n- n ,
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