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| {{#Wiki_filter:R EGUL>TORY NFQRMATION DISTRIBUTŽ8 S TEM (R IDS>, ACCESSION NBR: 8706050170 DOC.DATh: 87/05/27 NOTARIZED: | | {{#Wiki_filter:R EGUL>TORY NFQRMATION DISTRIBUT '8 S TEM (R IDS> |
| NO DOCKET¹FACIL 50-397 WPPSS Nuclear Progecti UIiit 2i Washington Public Poue 05000397 AUTH.NAHE AUTHOR AFFILI AT I OH WASHINGTQNI S.L.Washing ton Public Pouer Supply SMstem POWERS>C.M.Washing ton Public Pouer Supply SystemREC IP.NAME RECIPIENT AFFILIATION | | , |
| | ACCESSION NBR: 8706050170 DOC. DATh: 87/05/27 NOTARIZED: NO DOCKET ¹ FACIL 50-397 WPPSS Nuclear Progecti UIiit 2i Washington Public Poue 05000397 AUTH. NAHE AUTHOR AFFILIAT I OH WASHINGTQNI S. L. Washing ton Public Pouer Supply SMstem POWERS> C. M. Washing ton Public Pouer Supply System REC IP. NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-007-00: | | LER 87-007-00: on 870427'ource range monitor Channel A inoperable during core altera+ions. Caused bM personnel error during coordination. Core alter ations immediately s+opped. |
| on 870427'ource range monitor Channel A inoperable during core altera+ions. | | Functional surveillance completed. W/870527 ltr. |
| Caused bM personnel error during coordination. | | DISTRIBUTION CODE: IE22D COPIES RFCEI VE!)'TR ENCL SIZE: |
| Core alter ations immediately s+opped.Functional surveillance completed. | | TITLE: 50. 73 Licensee Event Repor+ (LFN)I Incident Rpti etc. |
| W/870527 ltr.DISTRIBUTION CODE: IE22D COPIES RFCEI VE!)'TR ENCL SIZE: TITLE: 50.73 Licensee Event Repor+(LFN)I Incident Rpti etc.NOTES: REC IP I ENT ID CODE/NAME PD5 LA SAMWORTH, R INTERNAL: ACRS MI CHELSQN AEQD/DOA AEQD/DSP/TPAB NRR/DEST/ADE NRR/DEST/CEB NRR/DEST/ICSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/PTSB RES DEPY GI EXTERNAL: EGhG GROHi M LPDR NSIC HARRIS, J COPlES LTTR ENCL 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 2 2 1 1 1 5 5 1 1 RECIPIENT ID CODE/NAME PD5 PD ACRS MOELLER ALOD/DSP/ROAB DEDRO hRR/DEST/*DS NRR/DEST/ELB I"!RR/DEST/MEB I'!RR/DEST/PSB NHR/DEST/SGB t!RR/DLPG/GAB NRR/DREP/RAB PMAS/ILRB R FI 02 FILE Oj H ST LOBB Y WARD h!RC PDR i~!SIC MAYSI G COPIES LTTR ENCL 1 2 2 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1, 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL'40 | | NOTES: |
| ~~
| | REC IP I ENT COPlES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 PD5 PD 1 SAMWORTH, R 1 1 INTERNAL: ACRS MICHELSQN 1 1 ACRS MOELLER 2 2 AEQD/DOA 1 ALOD/DSP/ROAB 2 2 AEQD/DSP/TPAB 1 DEDRO 1 1 NRR/DEST/ADE 0 hRR/DEST/*DS 1 0 NRR/DEST/CEB NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 I"!RR/DEST/MEB 1 NRR/DEST/MTB 1 I'!RR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NHR/DEST/SGB 1 NRR/DLPG/HFB 1 1 t!RR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 PMAS/ ILRB 1 NRR/PMAS/PTSB 1 1 R FI 02 1 1, RES DEPY GI 1 FILE Oj 1 EXTERNAL: EGhG GROHi M 5 5 H ST LOBB Y WARD LPDR 1 h!RC PDR NSIC HARRIS, J 1 i~!SIC MAYSI G TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL '40 |
| N<tC Penn~($4$)UCENSEE EVENT REPORT{LER)US.NUCLEAR RKOULATOhY COe&llSSION APPROVKO OMS NO.$1gh410e EXPIRKS: SISIISS f ACIUTY NAME II I Washinqton Nuclear Plant-Unit 2 DOCXKT NUMSKh (2)0 6 0 0 0 39 710FO TITLE te)SRM Channel A Ino erable during Core Alterations caused by Personnel Error EVENT DATE (SI OAY YEAR YEAR LKR NUN%Eh (S)KN: SSQVSNTIAL NVMSSR REPORT DATE (7)MONTH OAY YEAR PACIUTY NAMCS DOCXKT NUMSER($)0 6 0 0 0 OTHEh fACIUTIKS INVOLVED (SI 2 7 8 8 7 0 0 0 0 0 2 7 7 0 6 0 0 0 OPKRATINO NOOK (9)~OIIEh LEYEL 0 0 rt'v<''''~op>e., 4p., 20AO2(1)SOAts)l1)(4 20AOS(s)Hl(I)20AOS4)(1)(Nl 20AOSle)(1)(I 20AOS4N)ltl 20AOS(el~OM(e)(I)SOM(e)(2)00.7$4)(2)(4$0.7$4)(2)(I)00.72 le)(2)(44 LICENSEE CONTACT f Oh THIS LKh l12)~0.7$4)(2)tlt)s0.7$4)(2)(t)O0.7$lsl(2)tsS)S0.7$4)(2)(t44 IAI 00.7$4)(2)t t(S)(S)S0.7$ts)(2)(s)THIS hEPORT IS S(I ITTEO PURSUANT T 0 THK RKOUIRKMKNTS Of 10 Cfh f: (Cence one or mere ol'le~l11 7$.71 (S)722f lel DTHER Jspectfy In AectnNt eeV>>remt In Tent, HIIC Form OSSA)NAME Steven L.Washington, Compliance Engineer TELEPHONE NUMSKR AREA COOK 50 3 7-08 COMPLETE ONE'LINE fOR EACH~NKNT fAILURK DESCRISEO IN THIS hEPORT (1$)CAUSE SYSTEM COMPONENT MANUP AC.TURER EPORTASLE TO NPRDS CAUSE SYSTEM COMPONENT MANUPAC.TUR Eh EPORTASL TO NPRDS????V'V?A?e..., SUPPLEMENTAL RKPOhT EXPECTED (Ie)YKS III tw, conV>>sts EXPECTED S(ISIJISSIDH DATE)NO ASSTRACT RJmlt te ICCI)s>>tet, I a, eppreseneteIT Ilhsen vnenrepece type>>rinse Irnest (I 0)EXPKCTKO SU OMISSION OATS (1$)MONTH OAY YEAR On April 27, 1987 at approximately 0345 hours Washington Nuclear Plant Unit-2'(WNP-2)was in Operational Condition 5, Refueling, and core alterations (fuel shuffle)were in progress.The Plant Shift Manager reviewed and approved performance of the weekly SRM Channel Functional Surveillance during the time periods when core alterations were not being perforated.
| | |
| Plant Operators and Plant Instrument and Control (I8C)Technicians were coordinating core alterations (fuel shuffle)and performance of the SRM Channel A Function'al Surveillance. | | ~ ~ |
| Due to an error in the coordination of the two activities, SRM Channel A was inoperable while a fuel bundle was being loaded into the reactor core quadrant monitored by that Channel.When Plant Operators recognized SRM Channel A,was inoperable, core alterations were suspended.
| | N< tC |
| All three remaining SRM channels were operable during the event.The cause of the event was personnel error during the coordination of SRM testing and core alterations.
| | ($ 4$ ) |
| V There is no safety significance associated with this event because during core refueling operations the SRM System is only for indication while, Reactor protection is provided by the Intermdiate Range Monitoring (IRM)and the Average Power Range Monitor (APRM)Systems.870b050170 870527 PDR ADOCK 050003'7)7 NRC form Oeo (943)
| | Penn ~ US. NUCLEAR RKOULATOhY COe&llSSION APPROVKO OMS NO. $ 1gh410e EXPIRKS: SISIISS UCENSEE EVENT REPORT {LER) fACIUTY NAME III DOCXKT NUMSKh (2) |
| NRC Form SSEA, AHRI UCENSEE EVENT REPORT ILERI TEXT CONTINUATION UA.NUCLEAR REOULATORY COMMISSION APPROVED OMS NO.SIEOW104 EXPIRES: Sfll/85 FACILITY NAME III Washington Nuclear Plant-Unit 2 TEXT Igmao epoof Hrfqrnlaf, NM o4&onellVlIC Frfm JFII'el IITI Plant Conditions DOCKET NUMSER LT)o s o o o.9 LER NUMEER ISI'":x~55QVENTIAL NVM EII 0 0 7-IS ION NVM 002 PACE ISI oF 0 3 a)Power Level-OX b)Plant Mode-5 (Refueling)
| | Washinqton Nuclear Plant - Unit 2 0 6 0 0 0 39 710FO TITLE te) |
| Event On April 27, 1987 at approximately 0345 hours the plant was in Operational Condition 5 (Refueling), and Plant Operators were coordinating two activities; Core Alterations (fuel shuffle)and the weekly Source Range Monitor Channel Functional Surveillance.
| | SRM Channel A Ino erable during Core Alterations caused by Personnel Error EVENT DATE (SI LKR NUN%Eh (S) REPORT DATE (7) OTHEh fACIUTIKSINVOLVED (SI OAY YEAR YEAR KN: SSQVSNTIAL MONTH OAY YEAR PACIUTY NAMCS DOCXKT NUMSER($) |
| For a short period of time during this process, Source Range Monitor"A" was inoperable while a fuel bundle was being loaded in the reactor core quadrant monitored by SRM RA".However, neither SRM"BR or"0", which oonitor the ad,iacent quadrants, showed an.y increase in core reactivity. | | NVMSSR 0 6 0 0 0 OPKRATINO 2 |
| WNP-2 Plant Technical Specification 3/4.9.2 requires at least two SRM channels to be operable and located in the quadrant the core alteration is being made and in an adiacent quadrant.This ensures that any changes in core reactivity are readily detected.Prior to the event it was determined and approved by the Plant Shift Manager that the SRM Channel Functional Surveillance could be performed between core alterations w'ith proper communications between the Plant Operator and the Plant I8C Technicians performing the surveillance. | | NOOK (9) |
| The root cause of this event is insufficient coordination of the SRM testing and core alterations. | | ~ OIIEh 7 8 8 7 THIS hEPORT IS 20AO2(1) 0 0 SOAts) l1)(4 0 0 0 2 7 7 S(IITTEO PURSUANT T0 THK RKOUIRKMKNTSOf 10 Cfh f: (Cence one or mere ol'le 20AOS(el |
| Immediate Corrective Action Core alterations were immediately stopped.The four SRM Channel Functional Surveillances were completed later that day while core alterations were stopped.Further Corrective Action Each SRM Channel Functional Surveillance Procedure was deviated (revised)to require the Shift Manager to delay core alterations until the SRM Channel Functional Surveillances are completed. | | ~ OM(e) (I ) |
| An Operations Night Order describes the procedure deviation of the SRM Channel Functional Surveillances which prohibits these surveillances from being done between core alteration steps.Written feedback was provided to all licensed reactor operators describing the procedure dev iations.NRC fOIIM 555A IMQ I NRC Form ESSA~ISSS I.~0 UCENSEE EVENT REPORT (LER)TEXT CONTINUATION UA NUCLEAR REOULATORY COMMISSION APPROVEO OMS NO.SI SOMI04 EXPIRES: SISI/SS FACIUTY NAME 111 OOCKET NUMSER ISI YEAII LER NLSNER (Sl 5COVSHTIAL HVM ER.6P rl5VISIOH rrl HVM 5R PACE ISI Washington Nuclear Plant-Unit 2 TEXT 11t moro N>>oo 15 RRRr5or4 ooo~tt5toort tttlC Anrr SEAS I I ITI o s o o o 39 787 0 0 7 000 OF 0 3 Safety Si nificance There is no safety significance associated with this event.During core alterations the Source Range Monitoring System provides the operator indication of reactivity changes only and is not required to provide a protective RPS function.The IRM and APRM Systems which were operable at the time of the event provide reactor protection trip functions. | | ~ 0.7$ 4)(2) tlt) s0.7$ 4) (2)(t) |
| In addition the two SRM channels in adjacent quadrants were also operable during the event.This event results in consequences no different than if an SRM channel were to fail during core alterations. | | ~ l11 0 6 0 7$ .71 (S) 722f lel 0 0 LEYEL 0 0 20AOS(s) Hl(I) SOM(e) (2) O0.7$ lsl(2) tsS) DTHER Jspectfy In AectnNt eeV>>remt In Tent, HIIC Form rt ' v< ''''~op 20AOS4)(1) (Nl 00.7$ 4)(2)(4 S0.7$ 4) (2)(t44 IAI OSSA) |
| All required Technical Specification actions were successfully completed once it was recognized that the SRM was inoperable. | | >e. |
| | 20AOSle) (1)( I $ 0.7$ 4) (2) (I) 00.7$ 4) (2) t t(S) (S) |
| | , 4p., 20AOS4N)ltl 00.72 le)(2) (44 S0.7$ ts) (2)(s) f LICENSEE CONTACT Oh THIS LKh l12) |
| | NAME TELEPHONE NUMSKR AREA COOK Steven L. Washington, Compliance Engineer 50 3 7- 08 COMPLETE ONE'LINE fOR EACH ~NKNT fAILURKDESCRISEO IN THIS hEPORT (1$ ) |
| | MANUPAC. EPORTASLE MANUPAC. EPORTASL CAUSE SYSTEM COMPONENT TO NPRDS CAUSE SYSTEM COMPONENT TURER TUR Eh TO NPRDS |
| | ???? |
| | V 'V |
| | ?A?e..., |
| | SUPPLEMENTAL RKPOhT EXPECTED (Ie) MONTH OAY YEAR EXPKCTKO SU OMISSION OATS (1$ ) |
| | YKS IIItw, conV>>sts EXPECTED S(ISIJISSIDH DATE) NO ASSTRACT RJmlt te ICCI) s>>tet, I a, eppreseneteIT Ilhsen vnenrepece type>>rinse Irnest (I 0) |
| | On April 27, 1987 at approximately 0345 hours Washington Nuclear Plant Unit-2 |
| | '(WNP-2) was in Operational Condition 5, Refueling, and core alterations (fuel shuffle) were in progress. The Plant Shift Manager reviewed and approved performance of the weekly SRM Channel Functional Surveillance during the time periods when core alterations were not being perforated. Plant Operators and Plant Instrument and Control (I8C) Technicians were coordinating core alterations (fuel shuffle) and performance of the SRM Channel A Function'al Surveillance. Due to an error in the coordination of the two activities, SRM Channel A was inoperable while a fuel bundle was being loaded into the reactor core quadrant monitored by that Channel. When Plant Operators recognized SRM Channel A,was inoperable, core alterations were suspended. All three remaining SRM channels were operable during the event. |
| | The cause of the event was personnel error during the coordination of SRM testing and core alterations. |
| | V There is no safety significance associated with this event because during core refueling operations the SRM System is only for indication while, Reactor protection is provided by the Intermdiate Range Monitoring (IRM) and the Average Power Range Monitor (APRM) Systems. |
| | 870b050170 870527 050003'7)7 PDR ADOCK NRC form Oeo (943) |
| | |
| | NRC Form SSEA, UA. NUCLEAR REOULATORY COMMISSION AHRI UCENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMS NO. SIEOW104 EXPIRES: Sfll/85 FACILITY NAME III DOCKET NUMSER LT) LER NUMEER ISI PACE ISI |
| | '":x~ 55QVENTIAL IS ION NVM EII NVM Washington Nuclear Plant - Unit 2 o s o o o . 9 0 0 7 002 oF 0 3 TEXT Igmao epoof Hrfqrnlaf, NM o4&onellVlICFrfm JFII'el IITI Plant Conditions a) Power Level - OX b) Plant Mode - 5 (Refueling) |
| | Event On April 27, 1987 at approximately 0345 hours the plant was in Operational Condition 5 (Refueling), and Plant Operators were coordinating two activities; Core Alterations (fuel shuffle) and the weekly Source Range Monitor Channel Functional Surveillance. For a short period of time during this process, Source Range Monitor "A" was inoperable while a fuel bundle was being loaded in the reactor core quadrant monitored by SRM RA". However, neither SRM "BR or "0", which oonitor the ad,iacent quadrants, showed an.y increase in core reactivity. |
| | WNP-2 Plant Technical Specification 3/4.9.2 requires at least two SRM channels to be operable and located in the quadrant the core alteration is being made and in an adiacent quadrant. This ensures that any changes in core reactivity are readily detected. Prior to the event it was determined and approved by the Plant Shift Manager that the SRM Channel Functional Surveillance could be performed between core alterations w'ith proper communications between the Plant Operator and the Plant I8C Technicians performing the surveillance. |
| | The root cause of this event is insufficient coordination of the SRM testing and core alterations. |
| | Immediate Corrective Action Core alterations were immediately stopped. The four SRM Channel Functional Surveillances were completed later that day while core alterations were stopped. |
| | Further Corrective Action Each SRM Channel Functional Surveillance Procedure was deviated (revised) to require the Shift Manager to delay core alterations until the SRM Channel Functional Surveillances are completed. |
| | An Operations Night Order describes the procedure deviation of the SRM Channel Functional Surveillances which prohibits these surveillances from being done between core alteration steps. |
| | Written feedback was provided to all licensed reactor operators describing the procedure dev iations. |
| | NRC fOIIM 555A IMQI |
| | |
| | NRC Form ESSA ~ |
| | . ~ 0 UA NUCLEAR REOULATORY COMMISSION ISSS I UCENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. SI SOMI04 EXPIRES: SISI/SS FACIUTY NAME 111 OOCKET NUMSER ISI LER NLSNER (Sl PACE ISI YEAII 5COVSHTIAL .6P rl5VISIOH HVM ER rrl HVM 5R Washington Nuclear Plant - Unit 2 o s o o o 39 787 0 0 7 000 OF 0 3 TEXT 11t moro N>>oo 15 RRRr5or4 ooo ~ tt5toort tttlC Anrr SEAS I IITI Safety Si nificance There is no safety significance associated with this event. During core alterations the Source Range Monitoring System provides the operator indication of reactivity changes only and is not required to provide a protective RPS function. The IRM and APRM Systems which were operable at the time of the event provide reactor protection trip functions. In addition the two SRM channels in adjacent quadrants were also operable during the event. This event results in consequences no different than if an SRM channel were to fail during core alterations. All required Technical Specification actions were successfully completed once it was recognized that the SRM was inoperable. |
| This event caused no threat to the safety of the public or plant personnel. | | This event caused no threat to the safety of the public or plant personnel. |
| HIIC FORM 555A tO F91 0~ | | HIIC FORM 555A tO F91 |
| ~e gw~~~WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 Hay 27, 1987 Document Control Desk U.ST Nuclear.Regulatory Commission Washington, D.C.20555 | | |
| | 0 ~ |
| | ~ e gw~ ~ ~ |
| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 Hay 27, 1987 Document Control Desk U.ST Nuclear .Regulatory Commission Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.87-007 | | NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO. 87-007 |
| | |
| | ==Dear Sir:== |
|
| |
|
| ==Dear Sir:==
| | Transmitted herewith is Licensee Event Report No. 87-007 for WNP-2 Plant. |
| Transmitted herewith is Licensee Event Report No.87-007 for WNP-2 Plant.This report is submitted in response to the report requirements of 10CFR50.73 and discusses the item of reportability, corrective action taken, and action taken to preclude recurrence. | | This report is submitted in response to the report requirements of 10CFR50.73 and discusses the item of reportability, corrective action taken, and action taken to preclude recurrence. |
| Very truly yours, uM~C.M.owers (M/D 927M)WNP-Plant Manager CHP:db | | Very truly yours, C.M. |
| | uM~ |
| | owers (M/D 927M) |
| | WNP- Plant Manager CHP:db |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
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| |
|
| Licensee Event Report No.87-007 cc: Mr.John B.Martin, NRC-Region V Hr.R.T.Dodds, NRC-Site (M/D 901A)Mr.W.E.Hilbrot, BPA (M/D 399)INPO Records Center-Atlanta, GA Ms.Dottie Sherman, ANI Mr.C.E.Revell, BPA (H/D 399)g1/}} | | Licensee Event Report No. 87-007 cc: Mr. John B. Martin, NRC - Region V Hr. R. T. Dodds, NRC - Site (M/D 901A) |
| | Mr. W. E. Hilbrot, BPA (M/D 399) |
| | INPO Records Center - Atlanta, GA Ms. Dottie Sherman, ANI Mr. C. E. Revell, BPA (H/D 399) g1/}} |
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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
R EGUL>TORY NFQRMATION DISTRIBUT '8 S TEM (R IDS>
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ACCESSION NBR: 8706050170 DOC. DATh: 87/05/27 NOTARIZED: NO DOCKET ¹ FACIL 50-397 WPPSS Nuclear Progecti UIiit 2i Washington Public Poue 05000397 AUTH. NAHE AUTHOR AFFILIAT I OH WASHINGTQNI S. L. Washing ton Public Pouer Supply SMstem POWERS> C. M. Washing ton Public Pouer Supply System REC IP. NAME RECIPIENT AFFILIATION
SUBJECT:
LER 87-007-00: on 870427'ource range monitor Channel A inoperable during core altera+ions. Caused bM personnel error during coordination. Core alter ations immediately s+opped.
Functional surveillance completed. W/870527 ltr.
DISTRIBUTION CODE: IE22D COPIES RFCEI VE!)'TR ENCL SIZE:
TITLE: 50. 73 Licensee Event Repor+ (LFN)I Incident Rpti etc.
NOTES:
REC IP I ENT COPlES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 PD5 PD 1 SAMWORTH, R 1 1 INTERNAL: ACRS MICHELSQN 1 1 ACRS MOELLER 2 2 AEQD/DOA 1 ALOD/DSP/ROAB 2 2 AEQD/DSP/TPAB 1 DEDRO 1 1 NRR/DEST/ADE 0 hRR/DEST/*DS 1 0 NRR/DEST/CEB NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 I"!RR/DEST/MEB 1 NRR/DEST/MTB 1 I'!RR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NHR/DEST/SGB 1 NRR/DLPG/HFB 1 1 t!RR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 PMAS/ ILRB 1 NRR/PMAS/PTSB 1 1 R FI 02 1 1, RES DEPY GI 1 FILE Oj 1 EXTERNAL: EGhG GROHi M 5 5 H ST LOBB Y WARD LPDR 1 h!RC PDR NSIC HARRIS, J 1 i~!SIC MAYSI G TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL '40
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Washinqton Nuclear Plant - Unit 2 0 6 0 0 0 39 710FO TITLE te)
SRM Channel A Ino erable during Core Alterations caused by Personnel Error EVENT DATE (SI LKR NUN%Eh (S) REPORT DATE (7) OTHEh fACIUTIKSINVOLVED (SI OAY YEAR YEAR KN: SSQVSNTIAL MONTH OAY YEAR PACIUTY NAMCS DOCXKT NUMSER($)
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NAME TELEPHONE NUMSKR AREA COOK Steven L. Washington, Compliance Engineer 50 3 7- 08 COMPLETE ONE'LINE fOR EACH ~NKNT fAILURKDESCRISEO IN THIS hEPORT (1$ )
MANUPAC. EPORTASLE MANUPAC. EPORTASL CAUSE SYSTEM COMPONENT TO NPRDS CAUSE SYSTEM COMPONENT TURER TUR Eh TO NPRDS
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On April 27, 1987 at approximately 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> Washington Nuclear Plant Unit-2
'(WNP-2) was in Operational Condition 5, Refueling, and core alterations (fuel shuffle) were in progress. The Plant Shift Manager reviewed and approved performance of the weekly SRM Channel Functional Surveillance during the time periods when core alterations were not being perforated. Plant Operators and Plant Instrument and Control (I8C) Technicians were coordinating core alterations (fuel shuffle) and performance of the SRM Channel A Function'al Surveillance. Due to an error in the coordination of the two activities, SRM Channel A was inoperable while a fuel bundle was being loaded into the reactor core quadrant monitored by that Channel. When Plant Operators recognized SRM Channel A,was inoperable, core alterations were suspended. All three remaining SRM channels were operable during the event.
The cause of the event was personnel error during the coordination of SRM testing and core alterations.
V There is no safety significance associated with this event because during core refueling operations the SRM System is only for indication while, Reactor protection is provided by the Intermdiate Range Monitoring (IRM) and the Average Power Range Monitor (APRM) Systems.
870b050170 870527 050003'7)7 PDR ADOCK NRC form Oeo (943)
NRC Form SSEA, UA. NUCLEAR REOULATORY COMMISSION AHRI UCENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMS NO. SIEOW104 EXPIRES: Sfll/85 FACILITY NAME III DOCKET NUMSER LT) LER NUMEER ISI PACE ISI
'":x~ 55QVENTIAL IS ION NVM EII NVM Washington Nuclear Plant - Unit 2 o s o o o . 9 0 0 7 002 oF 0 3 TEXT Igmao epoof Hrfqrnlaf, NM o4&onellVlICFrfm JFII'el IITI Plant Conditions a) Power Level - OX b) Plant Mode - 5 (Refueling)
Event On April 27, 1987 at approximately 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> the plant was in Operational Condition 5 (Refueling), and Plant Operators were coordinating two activities; Core Alterations (fuel shuffle) and the weekly Source Range Monitor Channel Functional Surveillance. For a short period of time during this process, Source Range Monitor "A" was inoperable while a fuel bundle was being loaded in the reactor core quadrant monitored by SRM RA". However, neither SRM "BR or "0", which oonitor the ad,iacent quadrants, showed an.y increase in core reactivity.
WNP-2 Plant Technical Specification 3/4.9.2 requires at least two SRM channels to be operable and located in the quadrant the core alteration is being made and in an adiacent quadrant. This ensures that any changes in core reactivity are readily detected. Prior to the event it was determined and approved by the Plant Shift Manager that the SRM Channel Functional Surveillance could be performed between core alterations w'ith proper communications between the Plant Operator and the Plant I8C Technicians performing the surveillance.
The root cause of this event is insufficient coordination of the SRM testing and core alterations.
Immediate Corrective Action Core alterations were immediately stopped. The four SRM Channel Functional Surveillances were completed later that day while core alterations were stopped.
Further Corrective Action Each SRM Channel Functional Surveillance Procedure was deviated (revised) to require the Shift Manager to delay core alterations until the SRM Channel Functional Surveillances are completed.
An Operations Night Order describes the procedure deviation of the SRM Channel Functional Surveillances which prohibits these surveillances from being done between core alteration steps.
Written feedback was provided to all licensed reactor operators describing the procedure dev iations.
NRC fOIIM 555A IMQI
NRC Form ESSA ~
. ~ 0 UA NUCLEAR REOULATORY COMMISSION ISSS I UCENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. SI SOMI04 EXPIRES: SISI/SS FACIUTY NAME 111 OOCKET NUMSER ISI LER NLSNER (Sl PACE ISI YEAII 5COVSHTIAL .6P rl5VISIOH HVM ER rrl HVM 5R Washington Nuclear Plant - Unit 2 o s o o o 39 787 0 0 7 000 OF 0 3 TEXT 11t moro N>>oo 15 RRRr5or4 ooo ~ tt5toort tttlC Anrr SEAS I IITI Safety Si nificance There is no safety significance associated with this event. During core alterations the Source Range Monitoring System provides the operator indication of reactivity changes only and is not required to provide a protective RPS function. The IRM and APRM Systems which were operable at the time of the event provide reactor protection trip functions. In addition the two SRM channels in adjacent quadrants were also operable during the event. This event results in consequences no different than if an SRM channel were to fail during core alterations. All required Technical Specification actions were successfully completed once it was recognized that the SRM was inoperable.
This event caused no threat to the safety of the public or plant personnel.
HIIC FORM 555A tO F91
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 Hay 27, 1987 Document Control Desk U.ST Nuclear .Regulatory Commission Washington, D.C. 20555
Subject:
NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.87-007
Dear Sir:
Transmitted herewith is Licensee Event Report No.87-007 for WNP-2 Plant.
This report is submitted in response to the report requirements of 10CFR50.73 and discusses the item of reportability, corrective action taken, and action taken to preclude recurrence.
Very truly yours, C.M.
uM~
owers (M/D 927M)
WNP- Plant Manager CHP:db
Enclosure:
Licensee Event Report No.87-007 cc: Mr. John B. Martin, NRC - Region V Hr. R. T. Dodds, NRC - Site (M/D 901A)
Mr. W. E. Hilbrot, BPA (M/D 399)
INPO Records Center - Atlanta, GA Ms. Dottie Sherman, ANI Mr. C. E. Revell, BPA (H/D 399) g1/
