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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
[Table view] |
Text
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[R7gulat(Oh' File Cy~ 71,1 o
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. YANKEE ATOMIC ELECTRIC COMPANY
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ROWE, MASSACHUSETTS 01367 9 pt C- I yg' , .I; lj.
December, 14, 1972 .
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^U United h ates Atomic Energy Commission . .
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Attenti:n: Directorate of Licensing Referen:e: License No. DPR-3-(Docket No. 50-29)
Dear Sirs:
In accordance with ihe proposed Technical Specifications for the ' Ys:2ee Atomic Elcetric Compan;, , Section 5 7, C.a, we are reporting the felleving substantial variation from expected performance.
Following a routine inspection of shim rod S-18 on November 3, 1972, efforts to reinsert S-18 in core position JK-h5 vere unsuccessful.
Further periscope inspection of the shim rod revealed abnormal wear apIroxinstely nine inches below the normal guide block wear.
Following this evaluation of the problem, the decision was
!..ade to re.:ve the four fuel assemblies adjacent to JK-h5 to permit ins.recticn of the shim rod slot in the lower core support plate. An unde:Ja er television inspection revealed the following:
- 1. Aw screv vith locking cup intact was lying East ? ,
k'est in the cruciform formed by guide blocks fcr m lover core support plate at core position HJ-h5 Tnis bo3t and locking cup assembly was later proven to be a
. y- ~ , shroud tube mounting bolt. The bolt was not obstructing
(/7'C g N 2.,
x the shim rod hole. Subsequently, this bolt was retrieved from the lover core support plate.
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&L. g 2. Inspections through nozzle holes surrounding S-18 reveal-2 . -
%) ed crescent shapes through two nozzle holes to the East J.
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kj of the chim rod. Indications were that the shroud tube had shifted to the East.
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- 3. Inspections through shim rod slots of the lover core sup-port plcte revealed slots of North and South vanes nearly closed.
Upon discovery of the misaligned shroud tube and a shroud tube
- ( . bel-, the Ucision was made to remove all fuel from the reactor and inspect
-j the ;;rer reactor internals.
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" ' ' Unit $d States Atomic ". ergy Commission
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j, Attn: Directorateodricensing December 1h, 1972 (h[
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Durin6 the core unloading, control rod A-101 (rod #19) which
'had displayed erratic behavior during p] ant operation was_ removed from core position JK-67 for routine inspection. Later, an attempt to re-l~ insert control rod 19 was unsuccessful. The problem was believed to have
{ been caused by substantial boving of the control rod noted during the inspection. To substantiate this premise, a new control rod was inserted
- .into core position JK-67; it also failed to. insert.beyond the guide block j area of the lover core support plate. Subsequent te'levision inspection l'
of this core. position revealed.a second cap screv and locking cup vedged between the Guide blocks at the extreme southern end of the South vane.
During removal.of the core components a binocular inspection I' of the lover core support plate was performed. This inspection revealed a third cap screw and locking cup resting on the Northeast guide block i of nozzle G-h.
- ' Following removal of all fuel elements, shim rods and control rods on Hovember 13, 1972, a thorough television inspection was commenced of the lower core support plate to shroud tube bolting. The results were as follows
- 1. Core position JK-h , bolt missing, cup in place.
- 2. Core position J h5, bolt missing, cup in place.
- 3. Core position K-h5, bolt and locking cup missing.
- h. Core position JK-5, bolt missing, locking cup in place.
5 Core position GE-2, bolt and locking cup missins.
- 6. Core position G-23, bolt and locking cup missiac.
7 Core position H-23, bolt and locking cup missing.
A binocular inspection of the bottom of the reactor vessel re-vea]ed four shroud tube bolts, two with their locking cups.
On november 15, 1972, the reactor vendor representatives arrived on site and coimenced a television inspection of lower core internals.
Their findir.gs were consistent with those of Yankee with the exception of a possible loose shroud bolt at vore position G-12.
The vendor inspections resulted in the recommendation to remove the lower core support barrel to permit a more detailed inspection of the shroud tube structure. The barrel was removed on Hovember 16, 1972 and the follpving additional abnormalities were observed:
- 1. A sheared shroud tube tie bar between shroud tubes Ko, 24 and Ko. 25 Binocular inspection of shroud No. 25 on the Northwest side revealed a vertical '
scar one to two feet long on the outside lower quarter of the shroud tube.
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- 2. One bolt vaa founa missinc and one partially with- l drawn at the bottom tie plate on shroud tube Ho. 26.
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UnitedStatesAtomicf*ercyCommicsion ,
, Attn:
Directorate . of%, icensing
( December 114, 1972 The problem described in (1) aoove appears to be related to an occurrence early in plant life concerning dislodged specimen holders; no relationship has been developed relative to the currently observed shroud tube problem.
The reactor vendor is presently studying a repair which is ex-pected to result in a new unitized shroud structure. replacing the old bolted shroud structtu'e.
Very truly yours, YANKEE ATOMIC ELECTRIC CO. - ROWE F 0 Herbert A. Autio Plant Superintendent HAA:"vb cc: J. O'Reilly
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C 2 AEC DISg3UTION FOR PART' 50 000GT MATESP,,L
.(TEMPORARY FORM) CONTROL'No; 6381' 1
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FROP."j~ 5 DATE OF DOC: DATE REC'D LTR MEMO RPI OTHER
? 'Yad.ee Atc=ic Elcetric Co=pany Ro;e, Massachusetts 01367 .
. E* h * '"p n 12-1h-72 12-18-72 X
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ORIG CC WHER SENT AEC PD3 y SENT LOCAL PDR I nr m 3 siened i CIASS: INPUT NO CYS REC'D , DOCKET NO:
-, GJFROPINFO ,
40
- 50-29 i DESCRIP2 ION: ENCLOSURES: .
Ltr repertin6 an cbnormal occurrence on 11 Do Not itemove.
72, folleving a.rcutine inspection of shim d(j.., h
' rcd S-13, it vaa revealed that the shim rod hrh, p.p. 3 ruffered abncInal year approximately ninc inchen belev the no=al guide block vear. . . . . . ,
- NOTE *PLEASE CIRCULATE INSUFFICIE:E SJPIES RECEIVED ICR FULL DISTRIBWION PLA:Q NA:GS: Yankee ,
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FOR ACTION /INFORy.ATION 12-18-72 AB BWLER(L) SCIJENCER(L) # SCHEMEL(L) KNIGBTON(E)
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V/ Ccpics W/ Copies W/ Copies 'W/ Copies INTERNAL DISTRIBUTION M'R(FIII)
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