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| | issue date = 07/19/1993 | | | issue date = 07/19/1993 |
| | title = LER 93-026-00:on 930619,failed to Complete Weekly Battery Surveillance Requirements within Allowed TS Interval Due to Scheduling Oversight.Initiated & Completed PPM 7.4.8.2.1.20. W/930719 Ltr | | | title = LER 93-026-00:on 930619,failed to Complete Weekly Battery Surveillance Requirements within Allowed TS Interval Due to Scheduling Oversight.Initiated & Completed PPM 7.4.8.2.1.20. W/930719 Ltr |
| | author name = MACKAMAN C D, PARRISH J V | | | author name = Mackaman C, Parrish J |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:ACCELERATED DOCUMENT DISTRIBUTION SYSTEM U~REGULAT+INFORMATION DISTRIBUTZOtYSTEM (RIDE)IPCCESSZON NBR'9307280103 DOC'DATE'3/07/19 NOTARIZED'O DOCKET¹FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION MACKAMAN,C.D. | | {{#Wiki_filter:ACCELERATED DOCUMENT DISTRIBUTION SYSTEM U~ |
| Washington Public Power Supply System PARRISH,J.V. | | REGULAT+ INFORMATION DISTRIBUTZOtYSTEM (RIDE) |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION | | IPCCESSZON NBR'9307280103 DOC'DATE'3/07/19 NOTARIZED'O DOCKET ¹ FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION MACKAMAN,C.D. Washington Public Power Supply System PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 93-026-00:on 930619,failed to complete weekly battery surveillance requirements within allowed TS interval'due to scheduling oversight. | | LER 93-026-00:on 930619,failed to complete weekly battery surveillance requirements within allowed TS interval 'due to D scheduling oversight. Initiated & completed PPM 7.4.8.2.1.20. |
| Initiated&completed PPM 7.4.8.2.1.20. | | W/930719 ltr. |
| W/930719 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED'LTR (ENCL/SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: D A!RECIPIENT ID CODE/NAME PDV LA CLIFFORDFJ INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PDV PD ACRS AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB | | DISTRIBUTION CODE: IE22T COPIES RECEIVED'LTR ( ENCL / SIZE: |
| ~NR SSA/SPLB~E.~~5~h 0 2 RGN5 FILE 01 COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D~D EXTERNAL EG&G BRYCE F J~H NRC PDR NSIC POOREFW.2 2 L ST LOBBY WARD 1 1 NSIC MURPHYFG.A 1 1 NUDOCS FULL TXT 1'1 1 1 1 D D NOTE TO ALL"RIDS" RECIPIENTS:
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI D FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 July 19, 1993 G02-93-187 Docket No.50-397 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | NOTES: A! |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D~ |
| | PDV LA 1 1 PDV PD 1 1 CLIFFORDFJ 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 ~NR SSA/SPLB 1 1 NRR/DSSA/SRXB RES/DSIR/EIB 1 |
| | 1 1 |
| | 1 |
| | ~E.RGN5 |
| | ~~5~h FILE 02 01 1 |
| | 1 1 |
| | 1 EXTERNAL EG&G BRYCE F J ~ H 2 2 L ST LOBBY WARD 1 NRC PDR 1 1 NSIC MURPHYFG.A 1 1 NSIC POOREFW. 1 1 NUDOCS FULL TXT 1 1 D |
| | D D |
| | NOTE TO ALL"RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 July 19, 1993 G02-93-187 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO.93-026 Transmitted herewith is Licensee Event Report No.93-026 for the WNP-2 Plant.This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence. | | NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO. 93-026 Transmitted herewith is Licensee Event Report No. 93-026 for the WNP-2 Plant. This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence. |
| Sincerely, J.V.Parrish (Mail Drop 1023)Assistant Managing Director, Operations JVP/CDM/cgeh Enclosure CC: Mr.B.H.Faulkenberry, NRC-Region V Mr.R.Barr, NRC Resident Inspector (Mail Drop 901A, 2 Copies)INPO Records Center-Atlanta, GA Mr.D.L.Williams, BPA (Mail Drop 399)BOO 9307280103 930719 PDR ADOCK 05000397 PDR LICENSEE EVEIREPORT (LER)AGILITY NAHE (I)Washin ton Nuclear Plant-Unit 2 DOCKET NUHB R ()PAGE (3)0 5 0 0 0 3 9 7 I OF 5 ITLE (4)FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT EVENT DATE 5 YEAR YEAR DAY MONTH LER NUMBER 6)SEOUENTIAL NUHBER EVI SION UHBER REPORT DATE 7 HONTH DAY YEAR OTHER FACILITIES INVOLVED (6)FACILITY NAMES CKE 050 NUMB R (5)0 6 I 9 9 3 9 3 0 2 6 0 0 0 7 I 9 9 3 050 P ERAT ING ODE (9)HIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR E: (Check one or more of the following) | | Sincerely, J. V. Parrish (Mail Drop 1023) |
| (11)2 OWER LEVEL (10)20.402(b)20.405(a)(1)(i) 20.405(a)(1)(ii) 0.405(a)(1)(iii) 20.405(a)(1)(iv) 0.405(a)(1)(v) 20.405(C)0.36(c)(1) 50.36(c)(2) 0.73(a)(2)(i) 50.73(a)(2)(ii) 0.73(a)(2)(iii) 50.73(a)(2)(iv) 0.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 0.73(a)(2)(x) 77.71(b)73.73(c)THER (Specify in Abstract elow and in Text, NRC orm 366A)LICENSEE CONTACT FOR THIS LER 12)C.D.Mackaman, Licensing Engineer TELEPHONE NUMBER REA CODE 5 0 9 7 7-4 4 5 1 COMPLETE OHE LIHE FOR EACH COMPONENT FAILURE DESCRIBED IH THIS REPORT (13)CAUSE STSTEH COMPONENT HAHUFACTURER EPORTABLE 0 NPRDS CAUSE STSTEH COMPOHEHT HAHUFACTURER REPORTABLE TO NPRDS 8";-'<SUPPLEMENTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SUBHISSIOH DATE)NO TRACT TleI EXPECTED SUBHISSIOH MONTH DAY TEAR ATE (15)On June 19, 1993, at 0611 hours, WNP-2 failed to comply with Technical Specification Surveillance Requirement 4.8.2.1.a for all safety-related batteries. | | Assistant Managing Director, Operations JVP/CDM/cgeh Enclosure CC: Mr. B. H. Faulkenberry, NRC - Region V Mr. R. Barr, NRC Resident Inspector (Mail Drop 901A, 2 Copies) |
| Surveillance Procedure PPM 7.4.8.2.1.20,"Weekly Battery Testing," satisfies the surveillance requirements for all plant safety-related batteries. | | INPO Records Center - Atlanta, GA Mr. D. L. Williams, BPA (Mail Drop 399) |
| The procedure was not completed within the required seven day interval plus 1.75 days (25%maximum allowable extension per Surveillance Requirement 4.0.2).The battery surveillance procedure was last completed on June 10, 1993, at 1211 hours, with the next completion due no later than 0611 hours on June 19, 1993.However, the surveillance procedure was not completed until June 19, 1993, at 1837 hours.This resulted in all plant safety-related batteries being technically inoperable from 0611 hours to 1837 hours on June 19, 1993, for failing to comply with Surveillance Requirement 4.0.2.The associated Technical Specification Action Statements were not entered as the battery surveillance procedure was in progress.Surveillance Requirement | | BOO 9307280103 930719 PDR ADOCK 05000397 PDR |
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| | LICENSEE EVEIREPORT (LER) |
| | AGILITY NAHE (I) DOCKET NUHB R ( ) PAGE (3) |
| | Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I OF 5 ITLE (4) |
| | FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVALDUE TO A SCHEDULING OVERSIGHT EVENT DATE 5 LER NUMBER 6) REPORT DATE 7 OTHER FACILITIES INVOLVED (6) |
| | MONTH DAY YEAR YEAR SEOUENTIAL EVI SION HONTH DAY YEAR FACILITY NAMES CKE NUMB R (5) |
| | NUHBER UHBER 050 0 6 I 9 9 3 9 3 0 2 6 0 0 0 7 I 9 9 3 050 P ERAT ING HIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR E: (Check one or more of the following) (11) |
| | ODE (9) 2 OWER LEVEL 20.402(b) 20.405(C) 50.73(a)(2)(iv) 77.71(b) |
| | (10) 20.405(a)(1)(i) 0.36(c)(1) 0.73(a)(2)(v) 73.73(c) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) THER (Specify in Abstract 0.405(a)(1)(iii) 0.73(a)(2)(i) 50.73(a)(2)(viii)(A) elow and in Text, NRC 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) orm 366A) 0.405(a)(1)(v) 0.73(a)(2)(iii) 0.73(a)(2)(x) |
| | LICENSEE CONTACT FOR THIS LER 12) |
| | TELEPHONE NUMBER C. D. Mackaman, Licensing Engineer REA CODE 5 0 9 7 7 - 4 4 5 1 COMPLETE OHE LIHE FOR EACH COMPONENT FAILURE DESCRIBED IH THIS REPORT (13) |
| | CAUSE STSTEH COMPONENT HAHUFACTURER EPORTABLE CAUSE STSTEH COMPOHEHT HAHUFACTURER REPORTABLE 0 NPRDS TO NPRDS 8";-'< |
| | SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED SUBHISSIOH MONTH DAY TEAR ATE (15) |
| | YES (If yes, complete EXPECTED SUBHISSIOH DATE) NO TRACT TleI On June 19, 1993, at 0611 hours, WNP-2 failed to comply with Technical Specification Surveillance Requirement 4.8.2.1.a for all safety-related batteries. Surveillance Procedure PPM 7.4.8.2.1.20, "Weekly Battery Testing," satisfies the surveillance requirements for all plant safety-related batteries. |
| | The procedure was not completed within the required seven day interval plus 1.75 days (25% maximum allowable extension per Surveillance Requirement 4.0.2). The battery surveillance procedure was last completed on June 10, 1993, at 1211 hours, with the next completion due no later than 0611 hours on June 19, 1993. However, the surveillance procedure was not completed until June 19, 1993, at 1837 hours. This resulted in all plant safety-related batteries being technically inoperable from 0611 hours to 1837 hours on June 19, 1993, for failing to comply with Surveillance Requirement 4.0.2. The associated Technical Specification Action Statements were not entered as the battery surveillance procedure was in progress. Surveillance Requirement 4.0.3 permits an action requirement delay of up to 24 hours to complete a delinquent surveillance. |
| | The immediate corrective action was the initiation and successful completion of PPM 7.4.8.2.1.20 on June 19, 1993, at 1837 hours. |
| | |
| | LICENSEE EVENT REPORTER) |
| | TEXT CONTINUATION ACILlTY NAME (1) OOCKET NUMBER (2) LER NUMBER (B) AGE (3) |
| | Year umber ev. No. |
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 026 00 2 OF 5 ITLE (4) |
| | FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT |
| | ~At~rac (Cont'd) |
| | The root causes of this event were less than adequate Technical Specification surveillance tracking methods and personnel error. Further corrective actions include counseling of responsible Electrical Maintenance Shop personnel and Technical Specification Surveillance Program changes. |
| | This event posed no threat to the health and safety of either the public or plant personnel. |
| | P~ICh i Power Level - 1% |
| | Plant Mode - 2 (Startup) |
| | On June 19, 1993, at 0611 hours, WNP-2 failed to comply with Technical Specification Surveillance Requirements 4.8.2.1.a and 4.0.2 for all safety-related batteries. Surveillance Procedure PPM 7.4.8.2.1.20, "Weekly Battery Testing," satisfies the surveillance requirements for all plant safety-related batteries. The procedure was not completed within the required seven day interval plus 1.75 days (25% maximum allowable extension per Surveillance Requirement 4.0.2). |
| | Electrical Maintenance Shop personnel submitted the battery surveillance procedure to the Shift Manager for work authorization on June 19, 1993, shortly before 1700 hours. During the routine work authorization review, it was identified that the procedure should have been scheduled for June 16, 1993, with a work start "Late Date" of June 17, 1993. The Shift Manager subsequently initiated actions to perform PPM 7.4.8.2.1.20 immediately and determine the last successful completion of the procedure. The battery surveillance procedure was successfully completed on June 19, 1993, at 1837 hours with no discrepancies. |
| | Shortly thereafter, it was discovered that the previous successful completion was on June 10, 1993, at 1211 hours. Thus, the surveillance procedure should have been completed no later than 0611 hours on June 19, 1993, for Surveillance Requirement 4.0.2 compliance. This resulted in all plant safety-related batteries being technically inoperable from 0611 hours to 1837 hours on June 19, 1993, a period of 12 hours and 26 minutes. The associated Technical Specification Action Statements were not entered as the surveillance procedure was in progress. Surveillance Requirement 4.0.3 permits an action requirement delay of up to 24 hours to complete a delinquent surveillance. |
| | Imm i e rrecive A ti n The immediate corrective action was the initiation and successful completion of PPM 7.4.8.2.1.20 on June 19, 1993, at 1837 hours. |
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| | LICENSEE EVENT REPORT R) |
| | TEXT CONTINUATION AGILITY HAHE (I) DOCKET NUHBER (2) LER HUHBER (8) AGE (3) ear umber ev. Ho. |
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 026 00 3 F 5 ITLE (4) |
| | FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT F rtherEv luai n and orrecive A i A. ~hE |
| | : 1. This event is reportable pursuant to 10CFR50.73(a)(2)(i)(B) as "Any operation or condition prohibited by the plant's Technical Specifications...." |
| | : 2. At the time of this event, the Electrical Shop was working from a "Plant Restart Punchlist" following completion of the R-8 Maintenance and Refueling Outage. The punchlist was being used to list and coordinate all work for plant restart. Because the shop was concentrating on restart activities, battery surveillance procedure PPM 7.4.8.1.2.20 was not transferred from the normal "Daily Work List" to the "Plant Restart Punchlist" due to a shop administrative oversight. The Scheduled Maintenance S'stem (SMS) card for the battery surveillance was issued to the Electrical Shop in a timely manner and was added to the shop's "Surveillance Procedure Tracking Board." However, the surveillance procedure was again not transferred to the "Plant Restart Punchlist," due to another shop administrative oversight. Since Electrical Shop work activities were being scheduled solely from the punchlist, the surveillance was inadvertently left off the June 16, 1993, shop work schedule. |
| | : 3. Electrical Maintenance Shop personnel responsible for this event were counseled to prevent recurrence and to reemphasize the importance of Technical Specification compliance, |
| | : 4. The Plant Manager subsequently communicated his expectations to his staff regarding personnel accountability for completing surveillances within their normal intervals. |
| | B. ~R~~e The two root causes of this event were: |
| | : 1. Less than adequate Technical Specification surveillance tracking and statusing methods by Electrical Maintenance Shop supervision. |
| | : 2. The failure of Electrical Shop personnel to capture and transfer PPM 7.4.8.1.2.20 from the "Daily Work List" and "Surveillance Procedure Tracking Board" to the "Plant Restart Punchlist." |
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| ====4.0.3 permits====
| | LICENSEE EVENT REPORT 'QR) |
| an action requirement delay of up to 24 hours to complete a delinquent surveillance.
| | TEXT CONTINUATION |
| The immediate corrective action was the initiation and successful completion of PPM 7.4.8.2.1.20 on June 19, 1993, at 1837 hours.
| | . ~ |
| LICENSEE EVENT REPORTER)TEXT CONTINUATION ACILlTY NAME (1)Washington Nuclear Plant-Unit 2 OOCKET NUMBER (2)0 5 0 0 0 3 9 7 LER NUMBER (B)Year umber ev.No.3 026 00 AGE (3)2 OF 5 ITLE (4)FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT~At~rac (Cont'd)The root causes of this event were less than adequate Technical Specification surveillance tracking methods and personnel error.Further corrective actions include counseling of responsible Electrical Maintenance Shop personnel and Technical Specification Surveillance Program changes.This event posed no threat to the health and safety of either the public or plant personnel. | | ACILITT NAHE (1) OOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No. |
| P~ICh i Power Level-1%Plant Mode-2 (Startup)On June 19, 1993, at 0611 hours, WNP-2 failed to comply with Technical Specification Surveillance Requirements 4.8.2.1.a and 4.0.2 for all safety-related batteries.
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 026 0 4 F 5 ITLE (4) |
| Surveillance Procedure PPM 7.4.8.2.1.20,"Weekly Battery Testing," satisfies the surveillance requirements for all plant safety-related batteries.
| | FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT her rrec ive Action |
| The procedure was not completed within the required seven day interval plus 1.75 days (25%maximum allowable extension per Surveillance Requirement 4.0.2).Electrical Maintenance Shop personnel submitted the battery surveillance procedure to the Shift Manager for work authorization on June 19, 1993, shortly before 1700 hours.During the routine work authorization review, it was identified that the procedure should have been scheduled for June 16, 1993, with a work start"Late Date" of June 17, 1993.The Shift Manager subsequently initiated actions to perform PPM 7.4.8.2.1.20 immediately and determine the last successful completion of the procedure.
| | : 1. Administrative Procedure PPM 1.5.1, "Technical Specification Surveillance Program," will be revised by September 1, 1993, to further strengthen the surveillance program. In the interim, daily reports detailing those surveillances approaching their due date will be generated and provided to the Shift Managers and plant management. |
| The battery surveillance procedure was successfully completed on June 19, 1993, at 1837 hours with no discrepancies.
| | ~fi l1 The battery surveillance procedure PPM 7.4.8.2.1.20 was successfully completed on June 19, 1993, at 1837 hours with no discrepancies. The allowed surveillance interval of 8.75 days was exceeded by only 12 hours and 26 minutes as the procedure had previously been completed on June 10, 1993, at 1211 hours. |
| Shortly thereafter, it was discovered that the previous successful completion was on June 10, 1993, at 1211 hours.Thus, the surveillance procedure should have been completed no later than 0611 hours on June 19, 1993, for Surveillance Requirement 4.0.2 compliance.
| | Since all of the batteries met the surveillance procedure acceptance criteria, they were capable of performing their design safety functions during the interval between surveillances. This includes the delinquent period. Thus, there was no safety significance associated with this event and it posed no threat to the health and safety of either the public or plant personnel. |
| This resulted in all plant safety-related batteries being technically inoperable from 0611 hours to 1837 hours on June 19, 1993, a period of 12 hours and 26 minutes.The associated Technical Specification Action Statements were not entered as the surveillance procedure was in progress.Surveillance Requirement
| | imil r Even Other events reported since 1988 that are considered similar to this event are listed below. These events involved conditions where Technical Specification surveillances were not performed within the required interval due to the lack of procedural and programmatic controls, or due to personnel errors. Those events that resulted from procedural and programmatic deficiencies are being addressed in LER 93-010 through implementation of the Technical Specification Surveillance Improvement Project. The remaining events were the result of personnel errors. Plant management is concerned about the recurrence of personnel errors resulting in missed surveillances. As a result, the Plant Manager has sponsored cultural, accountability and additional programmatic changes to address this issue. |
| | LER 88-009 LER 91-013 (seven events) |
| | LER 88-020 LER 91-027 LER 88-033 LER 91-028 LER 88-035 LER 91-036 LER 88-036 LER 92-023 LER 89-003 LER 92-038 LER 92-046 LER 91-005 LER 93-010 |
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| ====4.0.3 permits====
| | LICENSEE EVENT REPORT R) |
| an action requirement delay of up to 24 hours to complete a delinquent surveillance.
| | TEXT CONTINUATION AGILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear umber ev. No. |
| Imm i e rrecive A ti n The immediate corrective action was the initiation and successful completion of PPM 7.4.8.2.1.20 on June 19, 1993, at 1837 hours.
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 2 6 0 5 F 5 ITLE (4) |
| LICENSEE EVENT REPORT R)TEXT CONTINUATION AGILITY HAHE (I)Washington Nuclear Plant-Unit 2 DOCKET NUHBER (2)0 5 0 0 0 3 9 7 LER HUHBER (8)ear umber ev.Ho.3 026 00 AGE (3)3 F 5 ITLE (4)FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT F rtherEv luai n and orrecive A i A.~hE 1.This event is reportable pursuant to 10CFR50.73(a)(2)(i)(B) as"Any operation or condition prohibited by the plant's Technical Specifications...." 2.At the time of this event, the Electrical Shop was working from a"Plant Restart Punchlist" following completion of the R-8 Maintenance and Refueling Outage.The punchlist was being used to list and coordinate all work for plant restart.Because the shop was concentrating on restart activities, battery surveillance procedure PPM 7.4.8.1.2.20 was not transferred from the normal"Daily Work List" to the"Plant Restart Punchlist" due to a shop administrative oversight. | | FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT EII Inf rmai n Tex Reference HIIS R f |
| The Scheduled Maintenance S'stem (SMS)card for the battery surveillance was issued to the Electrical Shop in a timely manner and was added to the shop's"Surveillance Procedure Tracking Board." However, the surveillance procedure was again not transferred to the"Plant Restart Punchlist," due to another shop administrative oversight.
| | $gggm /~moyen DC Power System - Class 1E Safety-Related Batteries BTRY}} |
| Since Electrical Shop work activities were being scheduled solely from the punchlist, the surveillance was inadvertently left off the June 16, 1993, shop work schedule.3.Electrical Maintenance Shop personnel responsible for this event were counseled to prevent recurrence and to reemphasize the importance of Technical Specification compliance, 4.The Plant Manager subsequently communicated his expectations to his staff regarding personnel accountability for completing surveillances within their normal intervals.
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| B.~R~~e The two root causes of this event were: 1.Less than adequate Technical Specification surveillance tracking and statusing methods by Electrical Maintenance Shop supervision.
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| 2.The failure of Electrical Shop personnel to capture and transfer PPM 7.4.8.1.2.20 from the"Daily Work List" and"Surveillance Procedure Tracking Board" to the"Plant Restart Punchlist."
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| LICENSEE EVENT REPORT'QR)TEXT CONTINUATION
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| .~ACILITT NAHE (1)Washington Nuclear Plant-Unit 2 OOCKET NUHBER (2)0 5 0 0 0 3 9 7 LER NUHBER (8)ear umber ev.No.3 026 0 AGE (3)4 F 5 ITLE (4)FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT her rrec ive Action 1.Administrative Procedure PPM 1.5.1,"Technical Specification Surveillance Program," will be revised by September 1, 1993, to further strengthen the surveillance program.In the interim, daily reports detailing those surveillances approaching their due date will be generated and provided to the Shift Managers and plant management.
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| ~fi l1 The battery surveillance procedure PPM 7.4.8.2.1.20 was successfully completed on June 19, 1993, at 1837 hours with no discrepancies.
| |
| The allowed surveillance interval of 8.75 days was exceeded by only 12 hours and 26 minutes as the procedure had previously been completed on June 10, 1993, at 1211 hours.Since all of the batteries met the surveillance procedure acceptance criteria, they were capable of performing their design safety functions during the interval between surveillances.
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| This includes the delinquent period.Thus, there was no safety significance associated with this event and it posed no threat to the health and safety of either the public or plant personnel.
| |
| imil r Even Other events reported since 1988 that are considered similar to this event are listed below.These events involved conditions where Technical Specification surveillances were not performed within the required interval due to the lack of procedural and programmatic controls, or due to personnel errors.Those events that resulted from procedural and programmatic deficiencies are being addressed in LER 93-010 through implementation of the Technical Specification Surveillance Improvement Project.The remaining events were the result of personnel errors.Plant management is concerned about the recurrence of personnel errors resulting in missed surveillances.
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| As a result, the Plant Manager has sponsored cultural, accountability and additional programmatic changes to address this issue.LER 88-009 LER 88-020 LER 88-033 LER 88-035 LER 88-036 LER 89-003 LER 92-046 LER 93-010 LER 91-013 (seven events)LER 91-027 LER 91-028 LER 91-036 LER 92-023 LER 92-038 LER 91-005 LICENSEE EVENT REPORT R)TEXT CONTINUATION AGILITY NAME (I)Washington Nuclear Plant-Unit 2 DOCKET NUMBER (2)0 5 0 0 0 3 9 7 LER NUMBER (8)ear umber ev.No.3 2 6 0 AGE (3)5 F 5 ITLE (4)FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT EII Inf rmai n Tex Reference DC Power System-Class 1E Safety-Related Batteries HIIS R f$gggm/~moyen BTRY}}
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B1111997-11-10010 November 1997 LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr ML17292B1151997-11-0707 November 1997 LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established ML17292B0641997-09-24024 September 1997 LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr ML17292B0241997-08-18018 August 1997 LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr ML17292B0291997-08-15015 August 1997 LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr ML17292B0201997-08-15015 August 1997 LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr ML17292A9481997-07-23023 July 1997 LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr ML17292A9201997-06-26026 June 1997 LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr ML17292A8331997-04-28028 April 1997 LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr ML17292A8311997-04-28028 April 1997 LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr ML17292A8251997-04-21021 April 1997 LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr ML17292A7431997-03-20020 March 1997 LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr ML17292A7401997-03-13013 March 1997 LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr ML17292A6641997-01-22022 January 1997 LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr ML17292A6461997-01-0606 January 1997 LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr ML17292A6371996-12-19019 December 1996 LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr ML17292A4121996-08-0808 August 1996 LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr ML17292A3801996-07-24024 July 1996 LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr ML17292A3771996-07-24024 July 1996 LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr ML17292A3641996-07-12012 July 1996 LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr ML17292A3361996-06-20020 June 1996 LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr ML17292A2861996-05-24024 May 1996 LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr ML17291B0891995-10-19019 October 1995 LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr ML17291A9021995-07-0707 July 1995 LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr ML17291A9031995-07-0707 July 1995 LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr ML17291A8501995-06-0808 June 1995 LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup ML17291A8101995-05-12012 May 1995 LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr ML17291A7841995-05-0505 May 1995 LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid ML17291A7801995-05-0404 May 1995 LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr ML17291A7851995-05-0303 May 1995 LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr ML17291A7071995-03-25025 March 1995 LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr ML17291A7011995-03-20020 March 1995 LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr 1999-07-20
[Table view] Category:RO)
MONTHYEARML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B1111997-11-10010 November 1997 LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr ML17292B1151997-11-0707 November 1997 LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established ML17292B0641997-09-24024 September 1997 LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr ML17292B0241997-08-18018 August 1997 LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr ML17292B0291997-08-15015 August 1997 LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr ML17292B0201997-08-15015 August 1997 LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr ML17292A9481997-07-23023 July 1997 LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr ML17292A9201997-06-26026 June 1997 LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr ML17292A8331997-04-28028 April 1997 LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr ML17292A8311997-04-28028 April 1997 LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr ML17292A8251997-04-21021 April 1997 LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr ML17292A7431997-03-20020 March 1997 LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr ML17292A7401997-03-13013 March 1997 LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr ML17292A6641997-01-22022 January 1997 LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr ML17292A6461997-01-0606 January 1997 LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr ML17292A6371996-12-19019 December 1996 LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr ML17292A4121996-08-0808 August 1996 LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr ML17292A3801996-07-24024 July 1996 LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr ML17292A3771996-07-24024 July 1996 LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr ML17292A3641996-07-12012 July 1996 LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr ML17292A3361996-06-20020 June 1996 LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr ML17292A2861996-05-24024 May 1996 LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr ML17291B0891995-10-19019 October 1995 LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr ML17291A9021995-07-0707 July 1995 LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr ML17291A9031995-07-0707 July 1995 LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr ML17291A8501995-06-0808 June 1995 LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup ML17291A8101995-05-12012 May 1995 LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr ML17291A7841995-05-0505 May 1995 LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid ML17291A7801995-05-0404 May 1995 LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr ML17291A7851995-05-0303 May 1995 LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr ML17291A7071995-03-25025 March 1995 LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr ML17291A7011995-03-20020 March 1995 LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr 1999-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
[Table view] |
Text
ACCELERATED DOCUMENT DISTRIBUTION SYSTEM U~
REGULAT+ INFORMATION DISTRIBUTZOtYSTEM (RIDE)
IPCCESSZON NBR'9307280103 DOC'DATE'3/07/19 NOTARIZED'O DOCKET ¹ FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION MACKAMAN,C.D. Washington Public Power Supply System PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 93-026-00:on 930619,failed to complete weekly battery surveillance requirements within allowed TS interval 'due to D scheduling oversight. Initiated & completed PPM 7.4.8.2.1.20.
W/930719 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED'LTR ( ENCL / SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES: A!
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D~
PDV LA 1 1 PDV PD 1 1 CLIFFORDFJ 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 ~NR SSA/SPLB 1 1 NRR/DSSA/SRXB RES/DSIR/EIB 1
1 1
1
~E.RGN5
~~5~h FILE 02 01 1
1 1
1 EXTERNAL EG&G BRYCE F J ~ H 2 2 L ST LOBBY WARD 1 NRC PDR 1 1 NSIC MURPHYFG.A 1 1 NSIC POOREFW. 1 1 NUDOCS FULL TXT 1 1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 July 19, 1993 G02-93-187 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO.93-026 Transmitted herewith is Licensee Event Report No.93-026 for the WNP-2 Plant. This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.
Sincerely, J. V. Parrish (Mail Drop 1023)
Assistant Managing Director, Operations JVP/CDM/cgeh Enclosure CC: Mr. B. H. Faulkenberry, NRC - Region V Mr. R. Barr, NRC Resident Inspector (Mail Drop 901A, 2 Copies)
INPO Records Center - Atlanta, GA Mr. D. L. Williams, BPA (Mail Drop 399)
BOO 9307280103 930719 PDR ADOCK 05000397 PDR
LICENSEE EVEIREPORT (LER)
AGILITY NAHE (I) DOCKET NUHB R ( ) PAGE (3)
Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I OF 5 ITLE (4)
FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVALDUE TO A SCHEDULING OVERSIGHT EVENT DATE 5 LER NUMBER 6) REPORT DATE 7 OTHER FACILITIES INVOLVED (6)
MONTH DAY YEAR YEAR SEOUENTIAL EVI SION HONTH DAY YEAR FACILITY NAMES CKE NUMB R (5)
NUHBER UHBER 050 0 6 I 9 9 3 9 3 0 2 6 0 0 0 7 I 9 9 3 050 P ERAT ING HIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR E: (Check one or more of the following) (11)
ODE (9) 2 OWER LEVEL 20.402(b) 20.405(C) 50.73(a)(2)(iv) 77.71(b)
(10) 20.405(a)(1)(i) 0.36(c)(1) 0.73(a)(2)(v) 73.73(c) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) THER (Specify in Abstract 0.405(a)(1)(iii) 0.73(a)(2)(i) 50.73(a)(2)(viii)(A) elow and in Text, NRC 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) orm 366A) 0.405(a)(1)(v) 0.73(a)(2)(iii) 0.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER 12)
TELEPHONE NUMBER C. D. Mackaman, Licensing Engineer REA CODE 5 0 9 7 7 - 4 4 5 1 COMPLETE OHE LIHE FOR EACH COMPONENT FAILURE DESCRIBED IH THIS REPORT (13)
CAUSE STSTEH COMPONENT HAHUFACTURER EPORTABLE CAUSE STSTEH COMPOHEHT HAHUFACTURER REPORTABLE 0 NPRDS TO NPRDS 8";-'<
SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED SUBHISSIOH MONTH DAY TEAR ATE (15)
YES (If yes, complete EXPECTED SUBHISSIOH DATE) NO TRACT TleI On June 19, 1993, at 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br />, WNP-2 failed to comply with Technical Specification Surveillance Requirement 4.8.2.1.a for all safety-related batteries. Surveillance Procedure PPM 7.4.8.2.1.20, "Weekly Battery Testing," satisfies the surveillance requirements for all plant safety-related batteries.
The procedure was not completed within the required seven day interval plus 1.75 days (25% maximum allowable extension per Surveillance Requirement 4.0.2). The battery surveillance procedure was last completed on June 10, 1993, at 1211 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.607855e-4 months <br />, with the next completion due no later than 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br /> on June 19, 1993. However, the surveillance procedure was not completed until June 19, 1993, at 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br />. This resulted in all plant safety-related batteries being technically inoperable from 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br /> to 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> on June 19, 1993, for failing to comply with Surveillance Requirement 4.0.2. The associated Technical Specification Action Statements were not entered as the battery surveillance procedure was in progress. Surveillance Requirement 4.0.3 permits an action requirement delay of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete a delinquent surveillance.
The immediate corrective action was the initiation and successful completion of PPM 7.4.8.2.1.20 on June 19, 1993, at 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br />.
LICENSEE EVENT REPORTER)
TEXT CONTINUATION ACILlTY NAME (1) OOCKET NUMBER (2) LER NUMBER (B) AGE (3)
Year umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 026 00 2 OF 5 ITLE (4)
FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT
~At~rac (Cont'd)
The root causes of this event were less than adequate Technical Specification surveillance tracking methods and personnel error. Further corrective actions include counseling of responsible Electrical Maintenance Shop personnel and Technical Specification Surveillance Program changes.
This event posed no threat to the health and safety of either the public or plant personnel.
P~ICh i Power Level - 1%
Plant Mode - 2 (Startup)
On June 19, 1993, at 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br />, WNP-2 failed to comply with Technical Specification Surveillance Requirements 4.8.2.1.a and 4.0.2 for all safety-related batteries. Surveillance Procedure PPM 7.4.8.2.1.20, "Weekly Battery Testing," satisfies the surveillance requirements for all plant safety-related batteries. The procedure was not completed within the required seven day interval plus 1.75 days (25% maximum allowable extension per Surveillance Requirement 4.0.2).
Electrical Maintenance Shop personnel submitted the battery surveillance procedure to the Shift Manager for work authorization on June 19, 1993, shortly before 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />. During the routine work authorization review, it was identified that the procedure should have been scheduled for June 16, 1993, with a work start "Late Date" of June 17, 1993. The Shift Manager subsequently initiated actions to perform PPM 7.4.8.2.1.20 immediately and determine the last successful completion of the procedure. The battery surveillance procedure was successfully completed on June 19, 1993, at 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> with no discrepancies.
Shortly thereafter, it was discovered that the previous successful completion was on June 10, 1993, at 1211 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.607855e-4 months <br />. Thus, the surveillance procedure should have been completed no later than 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br /> on June 19, 1993, for Surveillance Requirement 4.0.2 compliance. This resulted in all plant safety-related batteries being technically inoperable from 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br /> to 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> on June 19, 1993, a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 26 minutes. The associated Technical Specification Action Statements were not entered as the surveillance procedure was in progress. Surveillance Requirement 4.0.3 permits an action requirement delay of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete a delinquent surveillance.
Imm i e rrecive A ti n The immediate corrective action was the initiation and successful completion of PPM 7.4.8.2.1.20 on June 19, 1993, at 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br />.
LICENSEE EVENT REPORT R)
TEXT CONTINUATION AGILITY HAHE (I) DOCKET NUHBER (2) LER HUHBER (8) AGE (3) ear umber ev. Ho.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 026 00 3 F 5 ITLE (4)
FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT F rtherEv luai n and orrecive A i A. ~hE
- 1. This event is reportable pursuant to 10CFR50.73(a)(2)(i)(B) as "Any operation or condition prohibited by the plant's Technical Specifications...."
- 2. At the time of this event, the Electrical Shop was working from a "Plant Restart Punchlist" following completion of the R-8 Maintenance and Refueling Outage. The punchlist was being used to list and coordinate all work for plant restart. Because the shop was concentrating on restart activities, battery surveillance procedure PPM 7.4.8.1.2.20 was not transferred from the normal "Daily Work List" to the "Plant Restart Punchlist" due to a shop administrative oversight. The Scheduled Maintenance S'stem (SMS) card for the battery surveillance was issued to the Electrical Shop in a timely manner and was added to the shop's "Surveillance Procedure Tracking Board." However, the surveillance procedure was again not transferred to the "Plant Restart Punchlist," due to another shop administrative oversight. Since Electrical Shop work activities were being scheduled solely from the punchlist, the surveillance was inadvertently left off the June 16, 1993, shop work schedule.
- 3. Electrical Maintenance Shop personnel responsible for this event were counseled to prevent recurrence and to reemphasize the importance of Technical Specification compliance,
- 4. The Plant Manager subsequently communicated his expectations to his staff regarding personnel accountability for completing surveillances within their normal intervals.
B. ~R~~e The two root causes of this event were:
- 1. Less than adequate Technical Specification surveillance tracking and statusing methods by Electrical Maintenance Shop supervision.
- 2. The failure of Electrical Shop personnel to capture and transfer PPM 7.4.8.1.2.20 from the "Daily Work List" and "Surveillance Procedure Tracking Board" to the "Plant Restart Punchlist."
LICENSEE EVENT REPORT 'QR)
TEXT CONTINUATION
. ~
ACILITT NAHE (1) OOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 026 0 4 F 5 ITLE (4)
FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT her rrec ive Action
- 1. Administrative Procedure PPM 1.5.1, "Technical Specification Surveillance Program," will be revised by September 1, 1993, to further strengthen the surveillance program. In the interim, daily reports detailing those surveillances approaching their due date will be generated and provided to the Shift Managers and plant management.
~fi l1 The battery surveillance procedure PPM 7.4.8.2.1.20 was successfully completed on June 19, 1993, at 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> with no discrepancies. The allowed surveillance interval of 8.75 days was exceeded by only 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 26 minutes as the procedure had previously been completed on June 10, 1993, at 1211 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.607855e-4 months <br />.
Since all of the batteries met the surveillance procedure acceptance criteria, they were capable of performing their design safety functions during the interval between surveillances. This includes the delinquent period. Thus, there was no safety significance associated with this event and it posed no threat to the health and safety of either the public or plant personnel.
imil r Even Other events reported since 1988 that are considered similar to this event are listed below. These events involved conditions where Technical Specification surveillances were not performed within the required interval due to the lack of procedural and programmatic controls, or due to personnel errors. Those events that resulted from procedural and programmatic deficiencies are being addressed in LER 93-010 through implementation of the Technical Specification Surveillance Improvement Project. The remaining events were the result of personnel errors. Plant management is concerned about the recurrence of personnel errors resulting in missed surveillances. As a result, the Plant Manager has sponsored cultural, accountability and additional programmatic changes to address this issue.
LER 88-009 LER 91-013 (seven events)
LER 88-020 LER 91-027 LER 88-033 LER 91-028 LER 88-035 LER 91-036 LER 88-036 LER 92-023 LER 89-003 LER 92-038 LER 92-046 LER 91-005 LER 93-010
LICENSEE EVENT REPORT R)
TEXT CONTINUATION AGILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 3 2 6 0 5 F 5 ITLE (4)
FAILURE TO COMPLETE WEEKLY BATTERY SURVEILLANCE REQUIREMENTS WITHIN THE ALLOWED TECHNICAL SPECIFICATION INTERVAL DUE TO A SCHEDULING OVERSIGHT EII Inf rmai n Tex Reference HIIS R f
$gggm /~moyen DC Power System - Class 1E Safety-Related Batteries BTRY