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| | issue date = 03/18/1993 | | | issue date = 03/18/1993 |
| | title = LER 91-019-01:on 910716,determined That Failure to Rept Five Periods in Excess of 30 Days of Inoperability of Rv Seismic Monitor in Violation of Ts.Caused by Inadequate Procedures. Procedures revised.W/930318 Ltr | | | title = LER 91-019-01:on 910716,determined That Failure to Rept Five Periods in Excess of 30 Days of Inoperability of Rv Seismic Monitor in Violation of Ts.Caused by Inadequate Procedures. Procedures revised.W/930318 Ltr |
| | author name = BAKER J W, FIES C L | | | author name = Baker J, Fies C |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:ACCEI ERASED DOCUMENT DIST~KUTION SYSTEM REGULARLY INFORMATION DISTRIBUTI~ | | {{#Wiki_filter:ACCEI ERASED INFORMATION DOCUMENT DIST~KUTION SYSTEM REGULARLY DISTRIBUTI~SYSTEM (RIDS ) |
| SYSTEM (RIDS)-ACCESSION NBR:9303220230 DOC.DATE: 93/03/18 NOTARIZED: | | -ACCESSION NBR:9303220230 DOC.DATE: 93/03/18 NOTARIZED: NO DOCKET N FACIL;50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME - |
| NO DOCKET N FACIL;50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME-AUTHOR AFFILIATION FIES,C.L.Washington Public Power Supply System BAKER,J.W." Washington Public Power-Supply System'ECIP.NAME RECIPIENT AFFILIATION r SUBJECT LER 91-019-01:on 910716,determined that failure to rept five periods in excess of 30 days of inoperability of RV seismic in violation of TS.Caused by plant procedure.C/A includes revising Plant procedure when removing frame.W/930318 ltr.DISTRIBUTION CODE: IE22T'COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD5 LA CLIFFORD,J INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFBHE NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL: EG&G BRYCE,J.H ,NRC PDR NSIC POOREgW.COPIES LTTR ENCL 1 1 1 1 2 2 1'2 2 1 1 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD ACRS AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB RR~SSA/SPLB G FILE 02 RGN FILE 01 L ST LOBBY WARD NSIC MURPHYiG.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2"2 1 1 1.1 1 1 1, 1 1 1.1 1 1 1 1 1 1 1 1'1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | AUTHOR AFFILIATION FIES,C.L. Washington Public Power Supply System BAKER,J.W." Washington Public Power-Supply System RECIPIENT AFFILIATION 'ECIP.NAME r |
| PLEASE HELP US TO REDUCE WASTE!CONTACT TFIE DOCUMEN'I'ONTROL DI>V, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRI!3UTION LISTS FOR DOCUMENTS YOU DON'T NEED!~~~>allnsCj~ | | SUBJECT LER 91-019-01:on 910716,determined that failure to rept five periods in excess of 30 days of inoperability of RV seismic in violation of TS.Caused by plant procedure.C/A includes revising Plant procedure when removing frame.W/930318 ltr. |
| em m FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Bm 968~3000 George Wasbtngton Way~Richland, Wasbfngton 99352-0968 | | DISTRIBUTION CODE: IE22T 'COPIES RECEIVED:LTR ENCL SIZE: |
| ~(5093 372-5000 March 18, 1993 G02-93-063 Docket No.50-397 Document C'ontrol Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 CLIFFORD,J 1 1 INTERNAL: ACNW 2 2 ACRS 2 "2 AEOD/DOA 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/HHFBHE 1 1 NRR/DRCH/HICB 1, 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 RR~SSA/SPLB .1 1 NRR/DSSA/SRXB 1 1 G FILE 02 1 1 RES/DSIR/EIB 1 1 RGN FILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 2 2 L ST LOBBY WARD 1 1 |
| | ,NRC PDR 1 1 NSIC MURPHYiG.A 1 '1 NSIC POOREgW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT TFIE DOCUMEN'I'ONTROL DI>V, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRI!3UTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | ~~~>allnsCj~ em m FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 |
| | |
| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bm 968 ~ 3000 George Wasbtngton Way ~ Richland, Wasbfngton 99352-0968 ~ (5093 372-5000 March 18, 1993 G02-93-063 Docket No. 50-397 Document C'ontrol 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.91-019-01 | | NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO. 91-019-01 |
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| ==REFERENCE:== | | ==REFERENCE:== |
| | Letter G02-93-062, dated March 18, 1993, JW Baker (SS) to JB Martin (NRC), "Seismic Monitoring Instrumentation".- |
| | Transmitted herewith is Licensee Event Report No. 91-019-01 for the WNP-2 Plant. This revised 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. |
| | This revision removes a further corrective action to submit a Technical Specification change request to allow for relocation of the seismic monitor. |
| | Sincerely, |
| | . W, Baker WNP-2 Plant Manager (Mail Drop 927M) |
| | JWB/CLF/my Enclosure CC: Mr. J. B. Martin, 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) |
| | Mr. J. W. Clifford, NRC 9303220230 9303ie PDR ADOCK 050003'P7 8 PDR |
| | |
| | LICENSEE Evlk REPORT (LER) |
| | AGILITY NAHE (I) DOCKET HUHB R ( ) PAGE (3) |
| | Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I OF 4 ITLE (4) |
| | TECHNICAL SPECIFICATION VIOLATIONFOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR EVENT DATE 5 LER HUMBER 6 REPORT DATE 7) OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR SEQUENTIAL E VISION MOHTH DAY YEAR FACILITY NAMES CKE NUMB R (5) |
| | NUMBER UMBER 0 0 0 0 7 1 6 9 1 9 1 0 I 9 0 I 000 PERATIHG MIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or more of the following) (11) |
| | ODE (9) 4 ONER LEVEL 0.402(b) 20.405(C) 50. 73 (a) (2) ( I v) 77.71(b) |
| | (10) 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.73(c) 20.405(a)(l)(ii) 50.36(c)(2) 50.73(a)(2)(vii) THER (Specify in Abstract 20.405(a}(i)(iii} X 50.73(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) Form 366A) 20.405(a) (1) (v) 50.73(a)(2)(iii) M.73(a)(2)(x) |
| | LICENSEE CONTACT FOR THIS LER (12 TELEPHONE NUMBER CL Fies, Licensing Engineer REA CODE 5 0 9 7 7 - 4 1 4 7 COMPLETE OHE LINE FOR EACH COHPONEHT FAILURE DESCRIBED IH THIS REPORT (13) |
| | CAUSE SYSTEM COHPOHEHT MANUFACTURER EPORTABLE CAUSE SYSTEH COHPONEHT HAHUFACTURER EPORTABLE 0 NPRDS TO NPRDS SUPPLEHEHTAL REPORT EXPECTED (14) EXPECTED SUBHISSIDH HOHTH DAY YEAR ATE (15) |
| | YES (If yes, complete EXPECTED SUBHISSION DATE) HO TRACT (I OI On July 16, 1991 Plant Management determined that the failure to report five periods in excess of 30 days of inoperability of the Reactor Vessel Head Seismic Monitor was a violation of WNP-2 Plant Technical Specifications. During each of the past five annual Maintenance and Refueling Outages, beginning in 1986, the Monitor was inoperable due to the Space Frame, to which the Monitor is attached, being moved to a temporary location so that refueling and in-vessel outage work could be accomplished. |
| | There are two root causes for this event. The design which located the Seismic Monitor on the Space Frame did not meet the standard Technical Specification requirement for the instrument to be operable at all times. The Plant Procedure used to remove the Space Frame had no steps to inform the Shift Manager of the inoperability of the Monitor. |
| | Corrective action includes revising the Plant procedure to include a step to notify the Shift Manager when the Space Frame is moved. |
| | There is no safety significance associated with this event because the Monitor has no safety immediate function. |
| | |
| | LICENSEE EVENT REPOR ER) . |
| | TEXT CONTINUATION AGILITY NANE (1) DOCKET. NUMBER (2) LER NUNBER (B) AGE (3) |
| | Year umber ev. No. |
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 1 19 01 2 F 4 ITLE (4) |
| | TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC'ONITOR Pl n ndii n Power Level - 000% |
| | Plant Mode Cold Shutdown Evn D cri ti n On July 16, 1991 Plant Management determined that the failure to report the inoperability of the Reactor Vessel Head Seismic Monitor during five previous Maintenance and Refueling Outages was a violation of WNP-2 Plant Technical Specifications. |
| | On May 16, 1991, during the R6 Maintenance and Refueling Outage a Plant System Engineer reported that the Reactor Vessel Head Seismic Monitor SEIS-TPA-1 had been inoperable for 30 days and that a Special Report to the NRC was required. Seismic Monitor SEIS-TPA-1 is attached to the Space Frame, a steel structure located between the Reactor Vessel'Head and the Containment Head Structures. The Monitor SEIS-TPA-1 was inoperable because the Space Frame is moved and stored in a temporary location for refueling and in-vessel work activities. The Special Report was sent to the Commission on May 24, 1991. |
| | (Reference Supply System Letter 602-91-107) During the time of report preparation it was realized by the Compliance Engineer preparing the report that this instrument would also have been inoperable during each of the five previous Maintenance and Refueling Outages. The Compliance Supervisor directed that this information be included in the May 24, 1991 Special Report. |
| | Just prior to July 16, 1991 a NRC Resident Inspector requested that the reportability of this event per 10CFR50.73 be reviewed. This review was concluded on July 16, 1991 when Plant Management directed that this LER be prepared. Table 1 below lists the estimated times when the Monitor SEIS-TPA-1 was inoperable. |
| | Estimated Times of Inoperability of SEIS-TPA-1 Maintenance and Estimated time of Inoperability Refueling Outage of SEIS-TPA-1 Rl April - May 1986 April - Jun'e 1987 R3 May - June 1988 R4 May - June 1989 May - June 1990 |
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| Letter G02-93-062, dated March 18, 1993, JW Baker (SS)to JB Martin (NRC),"Seismic Monitoring Instrumentation".-
| | LICENSEE EVENT REPORTER) |
| Transmitted herewith is Licensee Event Report No.91-019-01 for the WNP-2 Plant.This revised 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.
| | TEXT CONTINUATION AC1LITY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear '/umber ev. No. |
| This revision removes a further corrective action to submit a Technical Specification change request to allow for relocation of the seismic monitor.Sincerely,.W, Baker WNP-2 Plant Manager (Mail Drop 927M)JWB/CLF/my Enclosure CC: Mr.J.B.Martin, 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)Mr.J.W.Clifford, NRC 9303220230 9303ie PDR ADOCK 050003'P7 8 PDR LICENSEE Evlk REPORT (LER)AGILITY NAHE (I)Washin ton Nuclear Plant-Unit 2 DOCKET HUHB R ()PAGE (3)0 5 0 0 0 3 9 7 I OF 4 ITLE (4)TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR EVENT DATE 5 LER HUMBER 6 REPORT DATE 7)OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR SEQUENTIAL NUMBER E VISION UMBER MOHTH DAY YEAR FACILITY NAMES CKE NUMB R (5)0 7 1 6 9 1 9 1 0 I 9 0 I 0 0 0 000 PERATIHG ODE (9)ONER LEVEL (10)50.73 (a)(2)(I v)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B)
| | Washington Nuclear Plant - Unit 2 0 0 0 3 9 7 0 5 1 19 01 3 F 4 ITLE (4) |
| M.73(a)(2)(x) 20.405(C)50.36(c)(1) 50.36(c)(2)
| | TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR mm I e rrectiv A i n None F herEvl i nand rr iv A i n A. ' rther Evaluation |
| X 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 77.71(b)73.73(c)THER (Specify in Abstract elow and in Text, NRC Form 366A)0.402(b)20.405(a)(1)(i) 20.405(a)(l)(ii) 20.405(a}(i)(iii}
| | : 1. This event is reportable as a violation of WNP-2 Plant Technical Specification per 10CFR50,73(a)(2)(i)(B). |
| 20.405(a)(1)(iv) 20.405(a)(1)(v)LICENSEE CONTACT FOR THIS LER (12 TELEPHONE NUMBER MIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or more of the following)
| | : 2. Technical Specification 3.3.7.2 requires the Reactor Head Vessel Head Seismic Monitor to be operable at all times. The specification also requires that: "With one or more of the seismic monitoring instruments inoperable for more than 30 days, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instruments to operable status." This LER documents the failure to submit a Special Report for each of the previous Maintenance and Refueling Outages. |
| (11)4 CL Fies, Licensing Engineer REA CODE 5 0 9 7 7-4 1 4 7 COMPLETE OHE LINE FOR EACH COHPONEHT FAILURE DESCRIBED IH THIS REPORT (13)CAUSE SYSTEM COHPOHEHT MANUFACTURER EPORTABLE 0 NPRDS CAUSE SYSTEH COHPONEHT HAHUFACTURER EPORTABLE TO NPRDS SUPPLEHEHTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SUBHISSION DATE)HO TRACT (I OI EXPECTED SUBHISSIDH HOHTH DAY YEAR ATE (15)On July 16, 1991 Plant Management determined that the failure to report five periods in excess of 30 days of inoperability of the Reactor Vessel Head Seismic Monitor was a violation of WNP-2 Plant Technical Specifications.
| | : 3. The cause of, the delay in submitting an LER when this event was first discovered in May 1991 is Personnel Error. The Compliance Supervisor erroneously made an independent determination that reporting the information on previously missed and required Special Reports in the May 24, 1991 Special Report was sufficient and that an LER was not required. |
| During each of the past five annual Maintenance and Refueling Outages, beginning in 1986, the Monitor was inoperable due to the Space Frame, to which the Monitor is attached, being moved to a temporary location so that refueling and in-vessel outage work could be accomplished.
| | : 4. There are two root causes for this event. First, the design which located the Monitor on the Space Frame did not meet standard technical specification requirements which required the instrument to be operable, at all times. The second root cause is procedural inadequacy. The Plant procedure which moved the Space Frame had no step to notify the Shift Manager of the inoperability of the Monitor. The Shift Manager is responsible for tracking compliance with Technical Specification Action Statements. |
| There are two root causes for this event.The design which located the Seismic Monitor on the Space Frame did not meet the standard Technical Specification requirement for the instrument to be operable at all times.The Plant Procedure used to remove the Space Frame had no steps to inform the Shift Manager of the inoperability of the Monitor.Corrective action includes revising the Plant procedure to include a step to notify the Shift Manager when the Space Frame is moved.There is no safety significance associated with this event because the Monitor has no safety immediate function.
| | : 5. There were no structures, systems, or components inoperable at the beginning of this event that contributed to this event. |
| LICENSEE EVENT REPOR ER).TEXT CONTINUATION AGILITY NANE (1)Washington Nuclear Plant-Unit 2 DOCKET.NUMBER (2)0 5 0 0 0 3 9 7 Year LER NUNBER (B)umber ev.No.AGE (3)1 19 01 2 F 4 ITLE (4)TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC'ONITOR Pl n ndii n Power Level-000%Plant Mode-4-Cold Shutdown Evn D cri ti n On July 16, 1991 Plant Management determined that the failure to report the inoperability of the Reactor Vessel Head Seismic Monitor during five previous Maintenance and Refueling Outages was a violation of WNP-2 Plant Technical Specifications.
| | B, F rther orrective Ac i n The Maintenance Procedure for moving the Space Frame was revised to include a requirement to notify the Shift Manager when SEIS-TPA-1 becomes inoperable. |
| On May 16, 1991, during the R6 Maintenance and Refueling Outage a Plant System Engineer reported that the Reactor Vessel Head Seismic Monitor SEIS-TPA-1 had been inoperable for 30 days and that a Special Report to the NRC was required.Seismic Monitor SEIS-TPA-1 is attached to the Space Frame, a steel structure located between the Reactor Vessel'Head and the Containment Head Structures.
| |
| The Monitor SEIS-TPA-1 was inoperable because the Space Frame is moved and stored in a temporary location for refueling and in-vessel work activities.
| |
| The Special Report was sent to the Commission on May 24, 1991.(Reference Supply System Letter 602-91-107)
| |
| During the time of report preparation it was realized by the Compliance Engineer preparing the report that this instrument would also have been inoperable during each of the five previous Maintenance and Refueling Outages.The Compliance Supervisor directed that this information be included in the May 24, 1991 Special Report.Just prior to July 16, 1991 a NRC Resident Inspector requested that the reportability of this event per 10CFR50.73 be reviewed.This review was concluded on July 16, 1991 when Plant Management directed that this LER be prepared.Table 1 below lists the estimated times when the Monitor SEIS-TPA-1 was inoperable.
| |
| Estimated Times of Inoperability of SEIS-TPA-1 Maintenance and Refueling Outage Rl R3 R4 Estimated time of Inoperability of SEIS-TPA-1 April-May 1986 April-Jun'e 1987 May-June 1988 May-June 1989 May-June 1990 LICENSEE EVENT REPORTER)TEXT CONTINUATION AC1LITY NAME (1)Washington Nuclear Plant-Unit 2 DOCKET NUMBER (2)0 5 0 0 0 3 9 7 LER NUMBER (8)ear'/umber ev.No.1 19 01 AGE (3)3 F 4 ITLE (4)TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR mm I e rrectiv A i n None F herEvl i nand rr iv A i n A.'rther Evaluation 1.This event is reportable as a violation of WNP-2 Plant Technical Specification per 10CFR50,73(a)(2)(i)(B).
| |
| 2.Technical Specification 3.3.7.2 requires the Reactor Head Vessel Head Seismic Monitor to be operable at all times.The specification also requires that: "With one or more of the seismic monitoring instruments inoperable for more than 30 days, in lieu of any other report-required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification | |
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| ====6.9.2 within====
| | LICENSEE EVENT REPORTER) |
| the next 10 days outlining the cause of the malfunction and the plans for restoring the instruments to operable status." This LER documents the failure to submit a Special Report for each of the previous Maintenance and Refueling Outages.3.The cause of, the delay in submitting an LER when this event was first discovered in May 1991 is Personnel Error.The Compliance Supervisor erroneously made an independent determination that reporting the information on previously missed and required Special Reports in the May 24, 1991 Special Report was sufficient and that an LER was not required.4.There are two root causes for this event.First, the design which located the Monitor on the Space Frame did not meet standard technical specification requirements which required the instrument to be operable, at all times.The second root cause is procedural inadequacy.
| | TEXT CONTINUATION AGILITY NAME (1) OOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear '(umber ev. No. |
| The Plant procedure which moved the Space Frame had no step to notify the Shift Manager of the inoperability of the Monitor.The Shift Manager is responsible for tracking compliance with Technical Specification Action Statements.
| | Washington Nuclear Plant - Unit 2 0 0 0 3 9 7 0 5 1 19 01 4 F 4 ITLE (4) |
| 5.There were no structures, systems, or components inoperable at the beginning of this event that contributed to this event.B, F rther orrective Ac i n The Maintenance Procedure for moving the Space Frame was revised to include a requirement to notify the Shift Manager when SEIS-TPA-1 becomes inoperable.
| | TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR afet i nifi n There is no safety significance associated with this event. The triaxial peak accelerograph SEIS-TPA-I is a sensitive wide band, low frequency, acceleration recording instrument. Permanent records are scribed by diamond styli on replaceable metal plates. The peak acceleration is computed by multiplying the maximum excursion of the trace by the acceleration sensitivity of the recorder. This passive instrument is used to capture the response of the space frame, a steel structure located between the reactor vessel head and containment head structures. The data collected is for subsequent engineering analysis and does not play a role in the immediate determination of Plant operability following a seismic event, Any loss of data can best be characterized as a lost opportunity to aid in the analysis to support a decision to restart should a significant seismic event have been experienced. |
| LICENSEE EVENT REPORTER)TEXT CONTINUATION AGILITY NAME (1)Washington Nuclear Plant-Unit 2 OOCKET NUMBER (2)0 5 0 0 0 3 9 7 LER NUMBER (8)ear'(umber ev.No.1 19 01 AGE (3)4 F 4 ITLE (4)TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR afet i nifi n There is no safety significance associated with this event.The triaxial peak accelerograph SEIS-TPA-I is a sensitive wide band, low frequency, acceleration recording instrument. | |
| Permanent records are scribed by diamond styli on replaceable metal plates.The peak acceleration is computed by multiplying the maximum excursion of the trace by the acceleration sensitivity of the recorder.This passive instrument is used to capture the response of the space frame, a steel structure located between the reactor vessel head and containment head structures. | |
| The data collected is for subsequent engineering analysis and does not play a role in the immediate determination of Plant operability following a seismic event, Any loss of data can best be characterized as a lost opportunity to aid in the analysis to support a decision to restart should a significant seismic event have been experienced. | |
| imilar Even There are no similar events pertaining to the failure to submit a Special Report when required by Plant Technical Specifications. | | imilar Even There are no similar events pertaining to the failure to submit a Special Report when required by Plant Technical Specifications. |
| II Inf rm i Te R fern f system~om m~nen Reactor Vessel Head Seismic Monitor (SEIS-TPA-I) | | II Inf rm i Te R fern f system ~om m~nen Reactor Vessel Head Seismic Monitor IN (SEIS-TPA-I) |
| Space Frame Reactor Vessel Head Containment Head Structures IN FRM RPV}} | | Space Frame FRM Reactor Vessel Head RPV Containment Head Structures}} |
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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
ACCEI ERASED INFORMATION DOCUMENT DIST~KUTION SYSTEM REGULARLY DISTRIBUTI~SYSTEM (RIDS )
-ACCESSION NBR:9303220230 DOC.DATE: 93/03/18 NOTARIZED: NO DOCKET N FACIL;50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME -
AUTHOR AFFILIATION FIES,C.L. Washington Public Power Supply System BAKER,J.W." Washington Public Power-Supply System RECIPIENT AFFILIATION 'ECIP.NAME r
SUBJECT LER 91-019-01:on 910716,determined that failure to rept five periods in excess of 30 days of inoperability of RV seismic in violation of TS.Caused by plant procedure.C/A includes revising Plant procedure when removing frame.W/930318 ltr.
DISTRIBUTION CODE: IE22T 'COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 CLIFFORD,J 1 1 INTERNAL: ACNW 2 2 ACRS 2 "2 AEOD/DOA 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/HHFBHE 1 1 NRR/DRCH/HICB 1, 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 RR~SSA/SPLB .1 1 NRR/DSSA/SRXB 1 1 G FILE 02 1 1 RES/DSIR/EIB 1 1 RGN FILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 2 2 L ST LOBBY WARD 1 1
,NRC PDR 1 1 NSIC MURPHYiG.A 1 '1 NSIC POOREgW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT TFIE DOCUMEN'I'ONTROL DI>V, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRI!3UTION LISTS FOR DOCUMENTS YOU DON'T NEED!
~~~>allnsCj~ em m FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bm 968 ~ 3000 George Wasbtngton Way ~ Richland, Wasbfngton 99352-0968 ~ (5093 372-5000 March 18, 1993 G02-93-063 Docket No. 50-397 Document C'ontrol Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO. 91-019-01
REFERENCE:
Letter G02-93-062, dated March 18, 1993, JW Baker (SS) to JB Martin (NRC), "Seismic Monitoring Instrumentation".-
Transmitted herewith is Licensee Event Report No. 91-019-01 for the WNP-2 Plant. This revised 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.
This revision removes a further corrective action to submit a Technical Specification change request to allow for relocation of the seismic monitor.
Sincerely,
. W, Baker WNP-2 Plant Manager (Mail Drop 927M)
JWB/CLF/my Enclosure CC: Mr. J. B. Martin, 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)
Mr. J. W. Clifford, NRC 9303220230 9303ie PDR ADOCK 050003'P7 8 PDR
LICENSEE Evlk REPORT (LER)
AGILITY NAHE (I) DOCKET HUHB R ( ) PAGE (3)
Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I OF 4 ITLE (4)
TECHNICAL SPECIFICATION VIOLATIONFOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR EVENT DATE 5 LER HUMBER 6 REPORT DATE 7) OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR SEQUENTIAL E VISION MOHTH DAY YEAR FACILITY NAMES CKE NUMB R (5)
NUMBER UMBER 0 0 0 0 7 1 6 9 1 9 1 0 I 9 0 I 000 PERATIHG MIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or more of the following) (11)
ODE (9) 4 ONER LEVEL 0.402(b) 20.405(C) 50. 73 (a) (2) ( I v) 77.71(b)
(10) 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.73(c) 20.405(a)(l)(ii) 50.36(c)(2) 50.73(a)(2)(vii) THER (Specify in Abstract 20.405(a}(i)(iii} X 50.73(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) Form 366A) 20.405(a) (1) (v) 50.73(a)(2)(iii) M.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12 TELEPHONE NUMBER CL Fies, Licensing Engineer REA CODE 5 0 9 7 7 - 4 1 4 7 COMPLETE OHE LINE FOR EACH COHPONEHT FAILURE DESCRIBED IH THIS REPORT (13)
CAUSE SYSTEM COHPOHEHT MANUFACTURER EPORTABLE CAUSE SYSTEH COHPONEHT HAHUFACTURER EPORTABLE 0 NPRDS TO NPRDS SUPPLEHEHTAL REPORT EXPECTED (14) EXPECTED SUBHISSIDH HOHTH DAY YEAR ATE (15)
YES (If yes, complete EXPECTED SUBHISSION DATE) HO TRACT (I OI On July 16, 1991 Plant Management determined that the failure to report five periods in excess of 30 days of inoperability of the Reactor Vessel Head Seismic Monitor was a violation of WNP-2 Plant Technical Specifications. During each of the past five annual Maintenance and Refueling Outages, beginning in 1986, the Monitor was inoperable due to the Space Frame, to which the Monitor is attached, being moved to a temporary location so that refueling and in-vessel outage work could be accomplished.
There are two root causes for this event. The design which located the Seismic Monitor on the Space Frame did not meet the standard Technical Specification requirement for the instrument to be operable at all times. The Plant Procedure used to remove the Space Frame had no steps to inform the Shift Manager of the inoperability of the Monitor.
Corrective action includes revising the Plant procedure to include a step to notify the Shift Manager when the Space Frame is moved.
There is no safety significance associated with this event because the Monitor has no safety immediate function.
LICENSEE EVENT REPOR ER) .
TEXT CONTINUATION AGILITY NANE (1) DOCKET. NUMBER (2) LER NUNBER (B) AGE (3)
Year umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 1 19 01 2 F 4 ITLE (4)
TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC'ONITOR Pl n ndii n Power Level - 000%
Plant Mode Cold Shutdown Evn D cri ti n On July 16, 1991 Plant Management determined that the failure to report the inoperability of the Reactor Vessel Head Seismic Monitor during five previous Maintenance and Refueling Outages was a violation of WNP-2 Plant Technical Specifications.
On May 16, 1991, during the R6 Maintenance and Refueling Outage a Plant System Engineer reported that the Reactor Vessel Head Seismic Monitor SEIS-TPA-1 had been inoperable for 30 days and that a Special Report to the NRC was required. Seismic Monitor SEIS-TPA-1 is attached to the Space Frame, a steel structure located between the Reactor Vessel'Head and the Containment Head Structures. The Monitor SEIS-TPA-1 was inoperable because the Space Frame is moved and stored in a temporary location for refueling and in-vessel work activities. The Special Report was sent to the Commission on May 24, 1991.
(Reference Supply System Letter 602-91-107) During the time of report preparation it was realized by the Compliance Engineer preparing the report that this instrument would also have been inoperable during each of the five previous Maintenance and Refueling Outages. The Compliance Supervisor directed that this information be included in the May 24, 1991 Special Report.
Just prior to July 16, 1991 a NRC Resident Inspector requested that the reportability of this event per 10CFR50.73 be reviewed. This review was concluded on July 16, 1991 when Plant Management directed that this LER be prepared. Table 1 below lists the estimated times when the Monitor SEIS-TPA-1 was inoperable.
Estimated Times of Inoperability of SEIS-TPA-1 Maintenance and Estimated time of Inoperability Refueling Outage of SEIS-TPA-1 Rl April - May 1986 April - Jun'e 1987 R3 May - June 1988 R4 May - June 1989 May - June 1990
LICENSEE EVENT REPORTER)
TEXT CONTINUATION AC1LITY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear '/umber ev. No.
Washington Nuclear Plant - Unit 2 0 0 0 3 9 7 0 5 1 19 01 3 F 4 ITLE (4)
TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR mm I e rrectiv A i n None F herEvl i nand rr iv A i n A. ' rther Evaluation
- 1. This event is reportable as a violation of WNP-2 Plant Technical Specification per 10CFR50,73(a)(2)(i)(B).
- 2. Technical Specification 3.3.7.2 requires the Reactor Head Vessel Head Seismic Monitor to be operable at all times. The specification also requires that: "With one or more of the seismic monitoring instruments inoperable for more than 30 days, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instruments to operable status." This LER documents the failure to submit a Special Report for each of the previous Maintenance and Refueling Outages.
- 3. The cause of, the delay in submitting an LER when this event was first discovered in May 1991 is Personnel Error. The Compliance Supervisor erroneously made an independent determination that reporting the information on previously missed and required Special Reports in the May 24, 1991 Special Report was sufficient and that an LER was not required.
- 4. There are two root causes for this event. First, the design which located the Monitor on the Space Frame did not meet standard technical specification requirements which required the instrument to be operable, at all times. The second root cause is procedural inadequacy. The Plant procedure which moved the Space Frame had no step to notify the Shift Manager of the inoperability of the Monitor. The Shift Manager is responsible for tracking compliance with Technical Specification Action Statements.
- 5. There were no structures, systems, or components inoperable at the beginning of this event that contributed to this event.
B, F rther orrective Ac i n The Maintenance Procedure for moving the Space Frame was revised to include a requirement to notify the Shift Manager when SEIS-TPA-1 becomes inoperable.
LICENSEE EVENT REPORTER)
TEXT CONTINUATION AGILITY NAME (1) OOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear '(umber ev. No.
Washington Nuclear Plant - Unit 2 0 0 0 3 9 7 0 5 1 19 01 4 F 4 ITLE (4)
TECHNICAL SPECIFICATION VIOLATION FOR FAILURE TO REPORT OUT OF SERVICE TIME OF SEISMIC MONITOR afet i nifi n There is no safety significance associated with this event. The triaxial peak accelerograph SEIS-TPA-I is a sensitive wide band, low frequency, acceleration recording instrument. Permanent records are scribed by diamond styli on replaceable metal plates. The peak acceleration is computed by multiplying the maximum excursion of the trace by the acceleration sensitivity of the recorder. This passive instrument is used to capture the response of the space frame, a steel structure located between the reactor vessel head and containment head structures. The data collected is for subsequent engineering analysis and does not play a role in the immediate determination of Plant operability following a seismic event, Any loss of data can best be characterized as a lost opportunity to aid in the analysis to support a decision to restart should a significant seismic event have been experienced.
imilar Even There are no similar events pertaining to the failure to submit a Special Report when required by Plant Technical Specifications.
II Inf rm i Te R fern f system ~om m~nen Reactor Vessel Head Seismic Monitor IN (SEIS-TPA-I)
Space Frame FRM Reactor Vessel Head RPV Containment Head Structures
