|
---|
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
- -
h.), < CE CC
. T:;:.x, l
YAliliEE ATODiC El.ECTRIO domPAllY
% Rowe, Massachusetts 01367 yq, l
, $NKEj .
.Decaaber 12, 1975 ' 41 ,
9 [h* [t*/ 'l ' \
DEC 1? tp' u= .
i Lj- u.s. ,.w. .
'l I%n,; ^
Mr. J. P. O'Reilly, Director U.S. Nuclear Regulatcry Cammission
'T' u
Office of Inspection and Enforcement ,
- Region I
! 631 Park Avenue j King of Prussia, Pennsylvania 19406
Subject:
Reportable Occurrence 50-29/75-16 Excessive Leakage from Vapor Conta ner Trip Valve, TV-409
Dear Mr. O' Reilly:
In accordance with Technical Specifications, Section E.2.a. ,
the attached Licensee Event Report is hereby submitted.
Very truly yours ,
.Q[Cbry.f L bt' s Herbert A. Autio Plcnt Superintendent JLSjb Enclosure -
cc: (40) Director, Office of Ins,,ection and Enforcement U.S. Nuclear Regulatory Lrenission Washington, D. C. 20555 (3) Director, Office of Management Information & Program Control U.S. Nuclear Regulatory Commission
_f i THIS DOCUMENT C POOR QUAI.lTY PAG ee 8012 04 09yo 14013 7
e
'. . s pONTROL BLOCK:l
.( l(l I 8CENSEE EVENT REPORT l l l
( ( l (PLEASE PRINT ALL RET.UIRED INFORMATIO
, 1- 6 I 1 . 'E0l' oCENst NuueER -
'E!' ' '"'p"E TY
@ l rd AlY lK l'R l lj l O! 0l-l0 l0 l 0 l 0 l 0l-l 0l 0 l l4l1 l1 l1 l1 l l 0l 1l !
.). 89 *14 15 25 28 30 31 32 CATEGORY 00Cx(T NUMBER EVENT DATE REPORT DATE l'SpJ LL] I 01 s101-10 lo i2 I 9 I - I i l 112 Io 17 Is I i11211121:IsI
~
o i COmr I I 7 6 57 58 59 60 61 68- 63 74 75 80 EVENT DESCRIPTION o2 lDurina routine Tvne C Containment Isolatica Valvo Surveillance tnstinn nyeos :iva '
- l-7 89 80
.foTil lleakaae was detected from isolation valvo Tv-409. vanor containnr woatino system -~
I 7 -89 80
@ l Return Heador Isniatinn Trin Valvo- This constitutes a violation of Technical j-7 89 80
@ ISoecification, Section E.2.a. (3) abnormal dearadation discovered in the primary l 7 89 80
$ Icontainment and is therefore reported as Reportable Occurrence 50-29/75-16 l 7 89 peg 80 SYSTEM CAUSE COMPONENT COMPONENT COCf CODE COMPONENT CODE . SUPPUER MANUFACTURER VOL.ATON
@ lS l Dl [E_) lV l A lL l VI ElX l [A_j lM l1 l2 l0 l l yl 7r G 9 10 11 12 17 3 44 47 48 CAUSE DESCR!PTION ,
0 l The 4 inch. ASA150 Mason Neilan falve..siittina surfaco had dearaded ta A nnint tnMyj '
7 89 -
80
@ l excessive leakage. The val.a was refurbished and retested satisfactorily. l 7 09 80 8I I
'^'
StA S % POWER OTHER STATUS S OVERY DISCOVERY OF8sCRIPTON 1 [Hj l0l0l 0l l NA i l b.l l Type C, Containment Iso.lation Testl 7 8 9 10 12 13 44 45 48 80 ACTIVITY CONTENT RELEASEO AMOUNT OF ACTMTY LOCATON OF RELEASE 1
[Z.J OF lZlRELEASE NA l l l NA l 7 0 0 10 11 44 45 80 PERSONNEL EXPOSUnES M tveER TYPE DESCRIPTON 1 10101Ol lZl l NA _. l 7 89 11 12 13 80 PERSONNEL INJUdiES NUMBER DESCRIP TON N l010l0l l NA l 7 89 11 12 80 OFFSITE CONSEQUENCES 1
l NA l 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPT ON ,
H' l NA l ,
7 89 10 80 PUDLICiTY j 1 l NA l
l 7 89 ,
80 ADDITIONAL FACTORS E I l 7 i9 80 3I 7 89 .
00 I
NAME: J. L. Staub pgggg; O L E M
.. ., . __ _ _ _ " o a t 5 5 7_ _
l.
. ~ . c ~
( $;
+ . o .. _ . . . _ _ _ . _ . . . _ _ _ . _ _ - . . . , . . . . _.__t,. {.
7 . . .. . . . _ . . . . _ , . . . .
~
x l
E r
re f.i YAHilEE ATC5110 ELECTRIC C0fAPANY .
L,=
. # M -
[
- k. ..m5,,f
.L Rowe, Massachuse:1s 01367 lb Y ee<es
-e ' Decerrber 1,. 1975
[3 a 9i e U. S. Nuclear Regulatory Comission "i Office of Inspection & Enforcement .
't Region I M 631' Park Avenue King of Prussia Pennsylvania 19406 ;-
Attention: Mr. J. P. O'Reilly ,E :
P
Dear Mr. O'Reilly:
.j-Pursuant to the requirerents of the Technical Specificatio.ts .
L i* Section E.2.a.(3), abnormal degradation discovered in the primary i j
containr.cnt is reported as Reportable Occurrence 50-29/75-16,. ,
During routine Type C, Containment Isolation Valve Tests, -
excessive leakage was detected from isolation valve TV-409. Vapor Container Heating System Return Header Isolation Trip Valve.
A 14 day Licensee Event Report will #ollow.
.. Very truly yours, 4
H. A. Autio
- Plant Superintendent NNS/.ib cc: (2) Director, Office of MIPC
U.S. Nuclear Regulatory Comission Washington, D. C. 20555 i
l l
l 1
l
~ ..-~ w ,
j
5- .-
NRC, LMSTp!BUTION FOR PART 50 DOCK ERIAL d .'N - ** W'W (TEMPOR,ARY FORM)
Y ,- .- \
i,
. . .\
.y' CONTROL NO: 14013j
, ...- . R 3 . FILE: IncIDEttr REPOR9 l
l FROM: Yankee Atomic Elec.Co. DATE OF DOC DATE REC'D LTR TWX RPT OTHERl Rowe, Mass. .. . . !
h.A. Autio - ---
12-12-75 12-17-75 XXX TO: OR.lG CC OTHER SENT AEC PDR XYY J.P. 0:Reillv n an S NT LOCAL PDR XXX )
CLASS ' UNCLASS ~ PROPINFO INPUT NO'CYS REC'D DOCKET NO: ,
l yyy '
50-29 49 D FEC RIPTION'. . ENCLOSURES:
- EErter trans the following. . . . . . . ' .
Licensee Event Repott # 75--16,.on 1.1-29-75
'. Concerning : cessive Lea.ka'ge:;from Vapor
. Containeep frip Valve. . . . . . - ' - -
40 Cys. Received)" '
PLANT NAf4E: Yankee Rowe
~
FOR ACTION /lNFORt ATION 3AB '.2-18-75
! BUTLER (L) SCHWENCER (L) ZIEMANN (L) REG AN (E)
~
! W/ Copies W/ Copics W/ Copies W/ Copics CLARK (L) STOLZ (L) DICKER (E) LEAR (L)
! W/ Cocies W/ Cooics W/ Cocies W/ Copies I
i PARR (L) VASSALLO (L) KNIGHTON (E) SPELS ' '
W/ Copies W Copies W/ Copics W/ Copies -
KNIE L (L) RPLE (L) YOUNGBLOOD (E) REID J W/ Copics VMCopies W/ Copics W/ Copies INTERNAL DISTRIBUTION ffEG FILE)
N RC N ri TECH REV:EW LIC ASST A/T IND .
,,,, SCH R O E D E R y.DENTON GRIMES R. DIGGSM BRAITMAN j,OGC, ROOM P.50GA #MACCARY GAMMILL H. GEARIN (L) SALTZMAN GDSGICK/STAF F KNIGHT KASTNER E. GOULBOURNE (L) MELTZ f CASE PAWL ICKl BALLARD P. KREUTZER (E)
SHAO SPANG LER ,i. LE E (L) _ PLANS BOYD **p ST E L LO MCDONALD M. RUSHER 00K (L)
MOORE (L) ** HOUSTON _E NVI R O_ S. REED (E) CHAPMAN DEYOUNG (L) **,,.NOV AK MULLER M. ._RVICE (L) DUBE (Lirl SKOVHOLT (L) ,ROSS DICKER E. COUPE GOLLER (L) (Ltr) v . SHEPPARD (L) f '?PO LITO KNIGHTON M. SLATER (E) PETERSON P. CO L LINS /TEDESCO YOUNGBLOOD H. SMITH (L) HARTFIELD (2)
DENISE J. COLLINS ' REGAN - KLECKER S. TEETS (L) .
REG OPR L6!NAS PROJECT LDR EISENHUT G. WILLI AMS (E)
/ FIT 5 &76GION (2) BENAPOYA V. WIL50N (L) *WIGGINTON pa. M /?3' (3) VOLLMER HAR LESS STEELE R. INGRAM (L) - F. WILLI AMS M. DimCAN (El - HANAU M EXTERNAL DISTRIBUTION pl -- LOCAL PDR '
pl - TIC (ABERNATHY) Greenfield,) (1)(2 (W)- Mass. NATIONAL LABS 1 - PDR. SAN /LA/NY p1 - NSIC (BUCHANAN) 1 - W. PENNINGTON, Rm E 201 GT 1 - BROOKHAVEN NAT LAB 1 - AeLB 1 - CONSU LTANTS 1 - G. ULRIKSON, ORN L 1 .ewton Anderson NEWM AR K/B LUM E/AG B ABI AN 1 - AGMED (RUTH GUSSMAd
.; ACRS LE:Tr TO LIO i.SST S. Sheppard Rm B.127 GT ;
- SEND ONLY TEN DAY REFORTS , - 1 " J. D. RUNKLE'S, Rm E 22
,/4 GT - l
,,/ y
/ ,
_ ~ _
4 '
. , . . ~ , _ _ . _ _ _ . _ _ . . . _ . _