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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20044A9201990-07-10010 July 1990 LER 90-007-00:on 900611,feedwater Isolation & Auxiliary Feedwater Actuation Occurred & on 900612,four Bank B Rod Control Cluster Assemblies Dropped.Caused by Failed Input Buffer Card & Faulty Slave cycler,respectively.W/900710 Ltr ML20043C0181990-05-30030 May 1990 LER 90-005-00:on 900501,reactor Trip,Auxiliary Feedwater Actuation & Feedwater Isolation Occurred Due to Turbine Trip on Loss of Main Generator Stator Cooling Water.Caused by Blown Fuse.Fuse Replaced & Logic changed.W/900530 Ltr ML20012B5661990-03-0505 March 1990 LER 90-002-00:on 900202,control Rod Urgent Failure Alarm Received During Monthly Surveillance on Movable Control Rod Assemblies.Caused by Defective Chip on Circuit Card.Card replaced.W/900305 Ltr ML20011E3491990-02-0505 February 1990 LER 90-001-00:on 900108,discovered That 24-month Tech Spec Required Local Leak Rate Test Surveillance for Containment Electrical Penetration Had Not Been Performed Since 870917. Caused by Personnel Error.Test performed.W/900205 Ltr ML20005E4681989-12-29029 December 1989 LER 89-014-00:on 891209,two ESF Actuations Occurred.Caused by Spurious Signal on Fuel Bldg Radiation Monitor.Loose Terminal Block Connection on Radiation Monitor Skid Motor Controller Tightened & tested.W/891229 Ltr ML19332E8661989-12-0606 December 1989 LER 89-013-00:on 891109,ESF Containment Purge Isolation, Control Room Ventilation Isolation & Fuel Bldg Ventilation Isolation Actuation Occurred.Caused by Failed 15-volt Dc Power Supply.Thermography performed.W/891206 Ltr ML19332D1991989-11-20020 November 1989 LER 89-012-00:on 891019,determined That Leakage Past Liquid Radwaste Discharge Monitor Tank a Inlet Isolation Valve Invalidated Tech Spec Required Batch Sample Prior to Discharge.Caused by Corrosion.Valve replaced.W/891120 Ltr ML19325C4571989-10-0303 October 1989 LER 89-010-01:on 890905,ESF Containment Purge,Control Room Ventilation & Fuel Bldg Ventilation Isolation Actuations Received.Caused by Failure of 15-volt Dc Power Supply.Failed Power Supply Replaced & Event discussed.W/891003 Ltr 1990-07-10
[Table view] Category:RO)
MONTHYEARML20044A9201990-07-10010 July 1990 LER 90-007-00:on 900611,feedwater Isolation & Auxiliary Feedwater Actuation Occurred & on 900612,four Bank B Rod Control Cluster Assemblies Dropped.Caused by Failed Input Buffer Card & Faulty Slave cycler,respectively.W/900710 Ltr ML20043C0181990-05-30030 May 1990 LER 90-005-00:on 900501,reactor Trip,Auxiliary Feedwater Actuation & Feedwater Isolation Occurred Due to Turbine Trip on Loss of Main Generator Stator Cooling Water.Caused by Blown Fuse.Fuse Replaced & Logic changed.W/900530 Ltr ML20012B5661990-03-0505 March 1990 LER 90-002-00:on 900202,control Rod Urgent Failure Alarm Received During Monthly Surveillance on Movable Control Rod Assemblies.Caused by Defective Chip on Circuit Card.Card replaced.W/900305 Ltr ML20011E3491990-02-0505 February 1990 LER 90-001-00:on 900108,discovered That 24-month Tech Spec Required Local Leak Rate Test Surveillance for Containment Electrical Penetration Had Not Been Performed Since 870917. Caused by Personnel Error.Test performed.W/900205 Ltr ML20005E4681989-12-29029 December 1989 LER 89-014-00:on 891209,two ESF Actuations Occurred.Caused by Spurious Signal on Fuel Bldg Radiation Monitor.Loose Terminal Block Connection on Radiation Monitor Skid Motor Controller Tightened & tested.W/891229 Ltr ML19332E8661989-12-0606 December 1989 LER 89-013-00:on 891109,ESF Containment Purge Isolation, Control Room Ventilation Isolation & Fuel Bldg Ventilation Isolation Actuation Occurred.Caused by Failed 15-volt Dc Power Supply.Thermography performed.W/891206 Ltr ML19332D1991989-11-20020 November 1989 LER 89-012-00:on 891019,determined That Leakage Past Liquid Radwaste Discharge Monitor Tank a Inlet Isolation Valve Invalidated Tech Spec Required Batch Sample Prior to Discharge.Caused by Corrosion.Valve replaced.W/891120 Ltr ML19325C4571989-10-0303 October 1989 LER 89-010-01:on 890905,ESF Containment Purge,Control Room Ventilation & Fuel Bldg Ventilation Isolation Actuations Received.Caused by Failure of 15-volt Dc Power Supply.Failed Power Supply Replaced & Event discussed.W/891003 Ltr 1990-07-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E2691999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20212A3361999-09-14014 September 1999 1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20212A0201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210Q8331999-08-0505 August 1999 Rev 4 to Callaway Cycle 10 Colr ML20210T9481999-08-0303 August 1999 Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for Ue Callaway Plant,Unit 1 ML20216D8791999-07-31031 July 1999 Rev 3 to Callaway Cycle 10 Colr ML20210T4451999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20209H0881999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With ML20195H4831999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With ML20206R7111999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp ML20205S5791999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Callaway Plant Unit 1.With ML20207A7401999-03-30030 March 1999 Draft, Evaluation of Risk of Induced Steam Generator Tube Rupture, for Callaway Plant ML20205G4071999-03-25025 March 1999 Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325 ML20204B6741999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Callaway Plant,Unit 1.With ML20199E7011998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Callaway Plant.With ULNRC-03990, 1998 Annual Rept for Ameren Corp/Union Electric Co. with1998-12-31031 December 1998 1998 Annual Rept for Ameren Corp/Union Electric Co. with ML20198D9811998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Callaway Plant,Unit 1.With ML20195C8341998-11-10010 November 1998 Rev 20 to Operating QA Manual ML20195C8181998-11-0909 November 1998 Rev 19 marked-up Changes to Operating QA Manual ML20195D6931998-10-31031 October 1998 Non-proprietary Rev 3 to Electrosleeving Qualification for PWR Recirculating SG Tube Repair ML20195D3581998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Callaway Plant,Unit 1.With ML20154L4931998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Callaway Plant Unit 1.With ML20151Y5151998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Callaway Plant,Unit 1.With ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20237B8421998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Callaway Plant,Unit 1 ML20155H7381998-06-30030 June 1998 10CFR50.59 Summary Rept for Jan-June 1998. with ML20236Q9991998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Callaway Plant,Unit 1 ML20249C5851998-06-30030 June 1998 Rev 1 to Callaway Cycle 10,COLR ML20248M0501998-06-0808 June 1998 Special Rept 98-02:on 980502,Channel 3 of loose-part Detection Sys Was Declared to Be Inoperable.Caused by Failure of Component Inaccessible at Power.Addl Troubleshooting Will Be Performed ML20249A7681998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Callaway Plant,Unit 1 ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247G0811998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Callaway Plant Unit 1 ML20217R2031998-04-27027 April 1998 Cycle 10 Colr ML20216H0651998-04-15015 April 1998 SER Approving Licensee Proposed Alternative to Use Code Case N-508-1 for Rotation of Serviced Snubbers & Prvs for Purpose of Testing in Lieu of ASME B&PV Code,Section Xi,Article IWA-7000 Requirements ML20216K0531998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Callaway Plant,Unit 1 ML20217F3181998-03-24024 March 1998 SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program ML20216G3551998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Callaway Plant, Unit 1 ML20203M0101998-02-25025 February 1998 Rev 11 to Callaway Cycle 9 Colr ML20203A7951998-02-0909 February 1998 Rev 10 to Callaway Cycle 9 Colr ML20202D4821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Callaway Plant ML20198S6361998-01-22022 January 1998 Ro:On 980121,determined That Plant Shutdown Would Be Required IAW TS 3.8.1.1,Action D.Caused by 'B' Train EES Charcoal Absorber Being Determined Inoperable.Requested 24 Hour Extension to Allow Restoration of EDG & ESW Train ULNRC-03775, 1997 Annual Rept for Union Electric1997-12-31031 December 1997 1997 Annual Rept for Union Electric ML20198Q0631997-12-31031 December 1997 Rev 9 to Callaway Cycle 9 Colr ML20198J6791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Callaway Plant,Unit 1 1999-09-30
[Table view] |
Text
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Cassway Plant : February 5, 1990 k
U. S. Nuclear Regulatory Commission j Document Control Desk
= Washington, DC 20555 ULNRC-2150 -i
' Gentlemen:-
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 1 FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REFORT 90-001-00
, TEST ON ELECTRICAL PENETRATION WAS NOT PERFORMED WITHIN ITS REOUIRED FREQUENCY DUE TO A HUMAN PERFORMANCE ERROR The~ enclosed Licensee Event Report is submitted pursuant to- -
10 CFR 50.73(a)(2)(1)(B) concerning operation of the Callaway Plant with a condition prohibited by the plant's Technical Specifications. The condition resulted from the failure to perform a local leak rate test on ,
an electrical penetration within its Technical Specification required 24 month frequency due to a human performance error. .
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. D. Blosser Manager, Callaway Plant VS tam TPS/ LAM:jlh o Enclosure cc: Distribution attached r ym
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Mr. Merlin Williams' J Manager,-Electric Department Supt. of Regulatory Quality & '
Missouri Public~-Service: Commission' Administrative Services.
P. 0 Box.360' Wolf Creek Nuclear Operating Corp. i' Jefferson City, MO 65102' P. O. Box 411-_.
Burlington, KS -66839 .
Records Center Mr. R. L. Hague :
. Institute of: Nuclear-Power Operations -Chief Project Section.3C Suite 1500 .
'U.S. Nuclear Regulatory _ Commission 1100 circle 75 Parkway Region III
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eACiufv NAME ol DoCn 1 NUw R iil ' Ant s p
F 5" Teat on Electrical Penetration was not Performed Within Its Required p Frequency Due to a Human Performance Error IVENT DAf f (Si Lt R NUMBt f. ISI REPORT DAf t {7) . OTHER 7 ActLifitS INVOLVED tel
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TH18 REPORT IS $USMITTED PUR$UANT TO THE REQUIREMENf8 0810 CFR { (CWe og er me . of fas fewe-opi '10 l
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1 20 406teH1Hol 6013mH2 Heat) 50 734.H2Hal LICIN5ti CONT ACT FOR THL% LER (12) a NAME TE L EPHONE NUMEsER ARL A CODt G. J. Czeschin, Superintendent of Planning & Scheduling 3 14 6 76- 84 30 l i I i i 1 1 1 !
COMPLtil ONE LING FOR E ACH COMPONENT f ALLURE DE5CR44ED IN THl4 REPORT (131 AtPONTA LE * ^C' CAUSE sv5f tv COMPONENT **7g AC. CAvst sv$7tM CovPONENT "' TO P0nNPRT AN t
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~} No l l l Aosf R ACT a,, .e to oa a o . ..-. , o.n , ,,,, -, ,m.., m. a. a o s, On-1/8/90, the utility surveillance scheduling engineer discovered that the 24 month Technical Specification (T/S) required Local Leak Rate Test (LLRT) surveillance for containment electrical penetration.ZSE250 had not been performed since 9/17/87. The plant was in Mode 1 - Power Operation, 100 percent reactor power at the time of discovery.
On 9/17/87 a retest LLRT was performed satisfactorily on ZSE250 per a work request. A surveillance scheduling engineer took credit for the retest as a T/S 4.6.1.2.d surveillance and manually changed the next periodic due date and late finish date incorrectly in the computerized surveillance scheduling system.
On 1/8/90, containment integrity was declared inoperable and T/S 3.6.1.1 was entered. The surveillance was immediately performed satisfactorily and T/S 3.6.1.1 was exited.
The root cause of this event is a cognitive human performance error by a surveillance scheduling engineer in September 1987.
All currently scheduled Type B and C LLRT surveillance tasks were reviewed and no other problems were identified with future due dates or late finish dates. Based upon this review, this event is considered an isolated case.
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0l0 0l2 OF) 0l3 stxs tu me. wm m. no .ww nc wm sesaw nn Basic for Reportabildtv Technical Specifiestion (T/S)'4.6.1.2.d requires that Type B and C Local Leak Rate Testo (LLRT) be conducted with gas at a pressure less than T , 48.1 psig, at intervals no greater than 24 months. On 1/8/90 the utility surveillanceschedulingengineerdiscoveredthatthe24monthTgrequired LLRT surveillance for containment electrical penetration ZSE250 had not been performed since 9/17/87.
This Licensee Event Report is submitted pursuant to 10CFR50.73(a)(2)(1)(B) to report a condition prohibited by the plant's T/S. !
Condition at Time of Event Mode 1 - Power Operations, Reactor Power 100%.
Description of Event-On 9/17/87 a retent LLRT was performed satisfactorily on electrical penetra-tion ZSE250 per a work request. The surveillane.e scheduling engineer took-credit for the retest as a T/S 4.6.1.2.d surveillance and manually changed the next periodic due date in the computerized surveillance scheduling system as allowed by procedure.
1 On 1/8/90 it was discovered through periodic review of upcoming scheduled
~
surveillances by the current utility surveillance scheduling engineer that the-scheduled performance date for the LLRT for ZSE250 showed 2/9/90 while ,
the Inte finish date for the surveillance was 2/3/90. He then discovered '
that the 24 month T/S ri:[uired LLRT surveillance for ZSE250 had not been performed since 9/17/87.
Steps to perform the surveillance were immediately initiated by the Planning !
and Scheduling department. The Engineering and Instrument and Control departments and the licensed operators were notified. ;
At 1235 the licensed operators declared containment integrity inoperabic and the one hour action statement for T/S 3.6.1.1, Containment Integrity,.was ;
entered. The-action statement was entered because T/S 3.6.1.2 action statement for Containment Leakage does not specify the actions to be taken when the plant is greater than 200'F. The LLRT surveillance for the penetration was completed satisfactorily at 1304 therefore exiting the action statement and satisfying both Liriting Conditions for Operation for T/S 3.6.1.I and 3.6.~1.2.
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' LICENSEE EVENT REPORT (LER) TEXT C;NTINUATION Amovto ove No. sue-om i
(XPmtS. 8/3DOB (1q P AC6LITY NAAet O) DOCkti NUMDt m (2) Lta NunettR (ei PA04 (31 ma i I"M!'.'. ' 00J.9 Callaway Plant' Unit 1-015 l01010 l41813 910 Ol0 ll -
010 013 OF 0 l3 hKT s.* awe gnpor e .,qrumt, par seweenaf 44C #enn Jed W dh Root Cause-- l i
The root cause of this event is a cognitive human performance error by a i previous surveillance scheduling engineer in September 1987. On 9/17/87, following a successful LLRT retest on electrical penetration 2SE250, the
-computer generated due date and late finish date were manually changed to I 9/21/89 and 2/3/90.
He apparently read the frequency of 24 months in T/S 4.6.1.2.d and set the due date 24 moaths from 9/17/87, or 9/21/89. He did not observe the surveillance task sheet note that T/S 4.0.2, which allows a 25 percent extension to the late finish date, was not applicable. He then incorrectly added a 25 percent extension for the late finish date (based on a 18 month frequency). It was set at 2/3/90 which is 4.5 months from 9/21/89.
Surveillance credit taken for LLRT retests and the subsequent manual adjustment of the computerized scheduled due dates is infrequently done.
1 Corrective Actions
- 1. .The surveillance scheduling engineer and the LLRT engineer conducted a l review of all currently scheduled Type B and C LLRT surveillance tasks L to ensure there were no other problems and to check to enstree future due dates and' late finish dates were within the proper time interval. The 'i review, completed on 1/15/90, did not identify any additional problems
~
with' future due dates or late finish dates, i
'2. Methods for adding the independent verification of manually initiated .!
changes to the surveillance scheduling program will be evaluated, i
Safety Significance ;
Tha LLRT surveillance for the electrical penetration ZSE250 was performed satisfactorily on 1/8/90. All equipment functioned as required by plant design and therefore this event posed no threat to the health or safety of the public.
Previous Occurrences None.
Footnotes ;
The system and component code below is from IEEE Standards 805 and 803A, respectively..
1)- System - JM, Component - PEN N%C FO%M 366A . 'U.5. CPGs 1988 4N- 589 ' 000 'O