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| | issue date = 04/22/1988 | | | issue date = 04/22/1988 |
| | title = LER 88-008-00:on 880318 & 24,plant Tech Spec Fire Penetration Seals Discovered Impaired/Unsealed During Ongoing 100% Insp.Cause Under Investigation.Penetrations Placed on Hourly Fire tour.W/880422 Ltr | | | title = LER 88-008-00:on 880318 & 24,plant Tech Spec Fire Penetration Seals Discovered Impaired/Unsealed During Ongoing 100% Insp.Cause Under Investigation.Penetrations Placed on Hourly Fire tour.W/880422 Ltr |
| | author name = ARBUCKLE J D, POWERS C M | | | author name = Arbuckle J, Powers 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:ee ,4C CEISRA7ZD DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8805030155 DOC.DATE: 88/04/22 NOTARIZED: | | {{#Wiki_filter:DISTRIBUTION ee DEMONSTRATION SYSTEM |
| NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION ARBUCKLE,J.D. | | ,4C CEISRA7ZD REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| Washington Public Power Supply System POWERS,C.M. | | ACCESSION NBR:8805030155 DOC.DATE: 88/04/22 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION ARBUCKLE,J.D. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000397 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 88-008-00:on 880318,plant Tech Spec fire penetration seals discovered impaired/unsealed during ongoing 1004 insp.W/8 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR A ENCL W SIZE: C TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD5 LA SAMWORTH, R INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10 NRR7DRQN/SIB 9A G~~02 RES7DE/EIB RGN5 FILE 01 EXTERNAL: EGS(G GROH,M H ST LOBBY WARD NRC PDR NSIC MAYS,G COPIES LTTR ENCL 1 1 1 1 1 1 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD ACRS MOELLER AEOD/DSP/NAS AEOD/DS P/T PAB DEDRO NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NRR/PMAS/ILRB12 RES TELFORD,J RES/DRPS DIR FORD BLDG HOY,A LPDR NSIC HARRIS,J COPIES LTTR ENCL 1 1 2 2 1.1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1.1 1 1 1 1 1 1 j A TOTAL'UMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 j A D P gpgg5P(~" D NRC Form 368 (8.83)LICENSEE EVENT REPORT ILER)V.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3160-0104 EXPIRES: 8/31/88 FACILITY NAME (11 Washin ton Nuclear Plant-Unit 2 DOCKET NUMBER (21 PAGE (3/0 5 0 0 03 9 7 1 OF 0/5 Plant Technical Specification Fire Penetration Seals Discovered Impaired/Unsealed Durin On oin 100%Ins ection-Cause Unknown EVENT DATE (5)LER NUMBER id)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY YE'AR YEAR SCOUCNT/AL NUMBER Rdvrd/ON yw7 NUMBER MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI 0 5 0 0 0 3 1 8 8 8 008 0 0 0 4 228 8 0 5 0 0 0 OPERATING MODE (8)1 POWE R LEVEL (101 NAME 20.402(6)20.406(~I (1 I ii)20.406(~)(11(ii)20.406(~)(I l(riil 20A05 I~l(1)(Iv)20.406(~)(1)(v)20.405(cl 50.35(cl(ll 50.3d (c)l2)59.73(~l(2)(i)60.73(~I I2)lit)60.73(el(2) liii)LICENSEE CONTACT FOR THIS LEA (121 50.73(~l(21(iv)50,73(~l(21(vl 50,73(e)l2)(xiii 50 73(~I(2)(vri/1(AI 50.73 (e I (2)(viii)I 81 60.73(~I(2)(e)AREA CODE THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR (): (Cnec/r one or more OI tne Iollowinp/(ll 73.71(o)73.71(cl OTHER ISpecily rn Aottrett oelow end in Text, NRC Po" 366A/TELFPHONE NUMBER D Ar 1 Com liance En ineer COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)0 9 3 7 7-1 CAUSE SYSTEM COMPONENT 6'IANUFAC TURER REPORTABLE TO NPADS Av%664~gv p/4>ghppklpN | | LER 88-008-00:on 880318,plant Tech Spec fire penetration seals discovered impaired/unsealed during ongoing 1004 insp. |
| >%3.";,P@$
| | W/8 ltr. |
| :$8~>cog': CAUSE SYSTEM COMPONENT MANUFAC TURER''r%%4+Ay"''
| | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR A ENCL W TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc. |
| po)tr~v.c..i/+6 SUPPLEMENTAL REPORT EXPECTED (14)YFS III ywcomplete EXPECTEO SUSMISSION OATEI ivO ABSTRACT ILimit to/400/peter, l,e., epproximetely IIINen rlnple rpsCe tyPewritNn linn/(181 EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR On March 23, 1988 and March 25, 1988 it was determined that problems documented (on March 18, 1988 and March 24, 1988)with regard to ll Plant Technical Specification fire penetrations were reportable under 10CFR50.73 (a)(2)(i).
| | SIZE: C NOTES: |
| The penetrations were impaired such that they would not qualify as a three-hour fire barrier.The penetrations are located in the Diesel Generator and Reactor Buildings.
| | ID RECIPIENT PD5 LA CODE/NAME SAMWORTH, R COPIES LTTR ENCL 1 |
| The problems were identified during the performance of ongoing physical walkdowns of all accessible Technical Specification walls and penet'rations as further corrective action committed to in LER 87-030.As required by the Plant Technical Specifications, the penetrations were placed on an hourly fire tour.Further corrective actions include 1)preparing Maintenance Work Requests (MWRs)to repair/seal the penetrations, and 2)completing the 100K review of documentation and physical walkdowns of all accessible Technical Specification walls and penetrations.
| | 1 1 |
| At the completion of the review and walkdowns, a supplemental report describing any further deficiencies discovered will be submitted.
| | 1 ID RECIPIENT PD5 PD CODE/NAME COPIES LTTR ENCL 1 1 j |
| The cause of this event is currently under investigation.
| | A INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 . 1 AEOD/DS P/T PAB ' |
| It was determined that this event did not affect the health and safety of either the public or Plant personnel due to the fire protection design of the fire areas involved.8805030155 SS0422 PDR ADOCK 05000397 S DCD NRC Form 3dd (9 83)
| | AEOD/DSP/ROAB 2 2 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR7DRQN/SIB 9A 1 1 NRR/PMAS/ILRB12 1 1 G~~ |
| OO OO NRC Forro 358A ((S83 I LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150WI04 EXPIRES: 8/3(/88 FACILITY NAME ((I OOCKET NUMSER (2l LER NUMSER (SI PM 5EQVENTIAL
| | RES7DE/EIB 02 1 1 |
| ~ra?45VI5ION NVM554 I'2 NVM554 PAGE (3l Washington Nuclear Plant-Unit 2 TEXT///more spoce is/tr/Item.ose~/5'orre/HRC Form 3//SA'5/(ITI Pl ant Condi ti ons 0 S 0 O 0 0 0 0 0 02oF 0-5 a)Power Level-100%b)Plant Mode-1 (Power Operation) | | 1 1 |
| Event Descri tion On March 23, 1988 and March 25, 1988 the following problems which were documented with regard to Plant Technical Specification fire penetration seals were determined to be reportable under 10CFR50.73 (a)(2)(i).
| | RES TELFORD,J RES/DRPS DIR 1 |
| a)On March 18, 1988 it was documented on a Plant Nonconformance Report that: Fire seal penetrations D101-3002-and D101-3003 (Diesel Generator Building 441 Elevation) each had a non-approved fire configuration type~lug installed (holes had been drilled through the center and filled with'All Thread").b)NRC FORM 3554 (983 I~Fire seal penetrations D102-3002 and D102-3003 (Diesel Generator Building 441.Elevation) each had a non-approved fire configuration type (non-ferralloy) plug installed, and the penetrations were not'listed in'he Plant Seal Tracking'System (PSTS)data base.~Fire seal penetration D104-3063 (Diesel Generator Building,-441 Elevation) was impaired in that the seal depth was less than required.~Fire seal penetration D113-2012 (Diesel Generator Building-441 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed.
| | 1 . |
| On March 24, 1988 it was documented on a Plant Nonconformance Report that: Fire seal penetration R116-3003.9 (Reactor Building-422 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed.
| | 1 1 |
| t Fire seal penetration R116-3003.10 (Reactor Building-422.Elevation) was impaired in that the plug had a drilled hole through its center, and the penetration was not listed in the PSTS data base.Fire seal penetration R116-3011.4 (Reactor Building-444 Elevation) was impaired in that the seal depth was less than required.Fire seal penetration R116-3011.6 (Reactor Building-444 Elevation) was impaired in that the plug had a drilled hole through its center, and the penetration was'not listed in the PSTS data base.Fire seal penetration R410-4004.7 (Reactor Building-522 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed.
| | RGN5 FILE 01 1 1 EXTERNAL: EGS(G GROH,M 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 j |
| 4 U.S.GPO (98$0.824 538/455 NRC Form 358A IS'83 I LICENSEE EVENT REPORT ILERI TEXT CONTINUATION V.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150WIOO EXPIRES: 8/3I/88 FACILITY NAME III OOCKET NVMSER ITI LER NVMSER ISI YEAR~r'y SEOVENTIAL NUMOEII Vi IIEVISION Ri+i NUMef A PAGE I3I Washington Nuclear Plant-Unit 2 TEXT I//more epoo>>/I pppppnrL Pop o/8/Or'M//VRC forIII38SAS/(IT/
| | A D |
| o 5 o o o 39 788 0 0 8 00 03 OF 0 5 The problems were identified during the performance of ongoing activities associated with further corrective actions committed to in a previous LER (87-030,"Upgraded Plant Technical Specification Fire Wall not Constructed to gualify as a Three-Hour Fire Barrier and Wall Penetration not Sealed").Specifically, the Supply System committed to perform a 10(C review of documentation, and physical walkdowns of all accessible Technical Specification walls and penetrations, to determine the adequacy of PSTS.The problems noted in this LER (88-008)were discovered during the ongoing physical walkdowns. | | gpgg5P(~" D P |
| The cause of this LER is currently under investigation.
| | TOTAL'UMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 |
| Immediate Corrective Action As required by the Plant Technical Specifications, the penetrations were placed on an hourly fire tour.Further Discussion and Corrective Action a)Further Discussion
| | |
| ~Fire seal penetrations D101-3002, D101-3003, D102-3002 and D102-3003 are located in Fire Area DG-V (1B Diesel Oil Tank Pump Room).o Fire seal penetration D104-3063 is located in Fire Area DG-I (HPCS Diesel Generator). | | NRC Form 368 V.S. NUCLEAR REGULATORY COMMISSION (8.83) |
| ~Fire seal penetration D113-2012 is located in Fire Area DG-III (1B Diesel Generator).
| | APPROVED OMB NO. 3160-0104 LICENSEE EVENT REPORT ILER) EXPIRES: 8/31/88 FACILITY NAME (11 DOCKET NUMBER (21 PAGE (3/ |
| o Fire seal penetrations R116-3003.9, R116-3003.10, R116-3011.4 and R116-3011.6 are located in Fire Area R-IV (RHR Pump Room Rl, Pipe Chase and RHR Heat Exchanger"B" Equipment Room).~Fire seal penetration R410-4004.7 is located in Fire Area R-VIII (MCC Room Division 2).I b)Further Corrective Action~Maintenance Work Requests (MWRs)were written to repair/seal the penetrations.
| | Washin ton Nuclear Plant - Unit 2 0 5 0 0 03 9 7 1 OF 0/5 Plant Technical Specification Fire Penetration Seals Discovered Impaired/Unsealed Durin On oin 100% Ins ection - Cause Unknown EVENT DATE (5) LER NUMBER id) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| ~The penetrations which were not previously included in the PSTS data base were added to the data base.~At the completion of the 100%review-of documentation, and physical walkdowns of all accessible Technical Specification walls and penetrations, a supplemental report describing any further deficiencies discovered will be submitted.
| | MONTH YE'AR YEAR SCOUCNT/AL Rdvrd/ON DAY YEAR FACILITYNAMES DOCKET NUMBER(SI DAY NUMBER yw7 NUMBER MONTH 0 5 0 0 0 3 1 8 8 8 008 0 0 0 4 228 8 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR (): (Cnec/r one or more OI tne Iollowinp/ (ll MODE (8) 20.402(6) 73.71(o) 1 20.405(cl 50.73( ~ l(21(iv) |
| NRC FORM 3OOA I983)o U.S GPO:1988 0 824 538/455 OO~t NRC Form 388A$431 LICENSEE EVENT REPORT (LER)TEXT CONTINUATION US.NUCLEAR REGULATORY COMMISSION APPROVEO OM8 NO, 3150M(04 EXPIRES: 8/31188 FACILITY NAME (I)Washington Nuclear Plant-Unit 2 TExT RY naacp<<>>cp<<(ppund, 1>>p<<ApFp44(HRc Ann 388AYI (Ill DOCKET NUMSER (Tl 0 S 0 0 0 LER NUMSER Iel Y f AR a ff QVE NTIAL (3Q 4(V>>KI>NVMsf 4 i NVMsf 4 00 00 PAGE I31 4 OF Safety Si ni f i c ance Although there were no fires during the event period, the following is a description of the consequences had a Design Basis Fire had occurred in the areas described in this LER.a)Fire Areas DG-I, DG-III and DG-V Smoke from a fire would activate one or more smoke detectors, which would alarm in the Control Room.The fire brigade would be dispatched and take appropriate action in accordance with the pre-fire plans and emergency response procedures.
| | POWE R 20.406( ~ I ( 1 I ii) 50.35(cl(ll 50,73( ~ l(21(vl 73.71(cl LEVEL (101 20.406( ~ ) (11(ii) 50.3d (c) l2) 50,73(e) l2)(xiii OTHER ISpecily rn Aottrett oelow end in Text, NRC Po" 20.406( ~ ) (I l(riil 59.73( ~ l(2)(i) 50 73( ~ I(2)(vri/1(AI 366A/ |
| Manual hoses are available.
| | 20A05 I ~ l(1) (Iv) 60.73( ~ I I2) lit) 50.73 (e I (2)(viii)I 81 20.406( ~ ) (1)(v) 60.73(el(2) liii) 60.73( ~ I(2)(e) |
| The thermal detection system would sense a high heat condition and activate the pre-action sprinkler system.Automatic spray heads would fuse and control the fire.b)Fire Areas R-IV and R-VIII Smoke from a fire would activate an ionization detector, which would alarm in the Control Room.The fire brigade would be dispatched and take appropriate action in'ccordance with the pre-fire plans and emergency response procedures.
| | LICENSEE CONTACT FOR THIS LEA (121 NAME TELFPHONE NUMBER AREA CODE D Ar 1 Com liance En ineer 0 9 3 7 7 - 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 6'IANUFAC REPORTABLE MANUFAC CAUSE SYSTEM COMPONENT TURER TO NPADS CAUSE SYSTEM COMPONENT TURER Av%664 ~gv p/4>ghppklpN ''r%%4+Ay"'' |
| Manual hoses are available.
| | po)tr ~v.c..i/+6 |
| In addition, Fire Area R-IV has a low fire loading and, as a result, the probability of a fire spreading is considered remote.Accordingly, this event did not affect the health and safety of either the public or Plant personnel.
| | >%3.";,P@$ :$ 8~>cog': |
| Similar Events LERs 85-028, 87-004-00, 87-004-01 and 87-030.EIIS Information NRC FORM 3584 (883 I Text Reference Fire Penetration Seals D101-3002 D101-3003 D102-3002 D102-3003 D104-3063 D113-2012 R116-3003.9 R116-3003.10 EIIS Reference System Component KP Pen*U.s opo:lose o 83f essMss NAC form 344A IS4)3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPAOVEO OMS NO.3)50&)04 EXPIRES: 8/31/88 PACILITY NAME)1)OOCKET NUMSEA l2)LEA NUMSER (4)PAGE 13)Washington Nuclear Plant-Unit 2 TEXT//f more Secre ir reerr)wS eee rr/R/Or'on/I HRC for//I 3//fASI Ill)o s o o o YEAR 8 8 my&.440USNTIAL m'iEr NUM 4 O YeWA 0 0 II 4 VISION NVMSSII 0 0 0 5 OF 0 5 R116-3011.4 R116-3011.6 R410-4004.7 Diesel Generator Bldg Reactor Bldg 1B Diesel Oil Tank Pump Room HPCS Diesel Generator 1B Diesel Generator RHR Pump Room Rl RHR Meat Exchanger NBN Equipment Room IRCC Room, Division 2 NB NG ME EK NB nIE I1E I1E Bldg Bl dg Room Room Room Room Room Room NIIC PO/IM 344A 1883)oU 8GPO;ISSS-O
| | SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15) |
| $24$38/4$$
| | YFS III ywcomplete EXPECTEO SUSMISSION OATEI ivO ABSTRACT ILimit to /400 /peter, l,e., epproximetely IIINen rlnple rpsCe tyPewritNn linn/ (181 On March 23, 1988 and March 25, 1988 it was determined that problems documented (on March 18, 1988 and March 24, 1988) with regard to ll Plant Technical Specification fire penetrations were reportable under 10CFR50.73 (a)(2)(i). The penetrations were impaired such that they would not qualify as a three-hour fire barrier. The penetrations are located in the Diesel Generator and Reactor Buildings. |
| ai WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 April 22, 1988 Document Control Desk UPS.Nuclear Regulatory Commission Washington, D,C.20555 | | The problems were identified during the performance of ongoing physical walkdowns of all accessible Technical Specification walls and penet'rations as further corrective action committed to in LER 87-030. |
| | As required by the Plant Technical Specifications, the penetrations were placed on an hourly fire tour. Further corrective actions include 1) preparing Maintenance Work Requests (MWRs) to repair/seal the penetrations, and 2) completing the 100K review of documentation and physical walkdowns of all accessible Technical Specification walls and penetrations. At the completion of the review and walkdowns, a supplemental report describing any further deficiencies discovered will be submitted. |
| | The cause of this event is currently under investigation. |
| | It was determined that this event did not affect the health and safety of either the public or Plant personnel due to the fire protection design of the fire areas involved. |
| | 8805030155 SS0422 PDR ADOCK 05000397 S DCD NRC Form 3dd (9 83) |
| | |
| | NRC Forro 358A OO OO U.S. NUCLEAR REGULATORY COMMISSION |
| | ((S83 I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMS NO. 3150WI04 EXPIRES: 8/3(/88 FACILITY NAME ((I OOCKET NUMSER (2l LER NUMSER (SI PAGE (3l PM 5EQVENTIAL ~ra? 45VI5ION I'2 NVM554 NVM554 Washington Nuclear Plant - Unit 2 0 S 0 O 0 0 0 0 0 02oF 0- 5 TEXT ///more spoce is /tr/Item. ose ~ /5 'orre/HRC Form 3//SA'5/(ITI Pl ant Condi ti ons a) Power Level - 100% |
| | b) Plant Mode - 1 (Power Operation) |
| | Event Descri tion On March 23, 1988 and March 25, 1988 the following problems which were documented with regard to Plant Technical Specification fire penetration seals were determined to be reportable under 10CFR50.73 (a)(2)(i). |
| | a) On March 18, 1988 it was documented on a Plant Nonconformance Report that: |
| | Fire seal penetrations D101-3002- and D101-3003 (Diesel Generator Building 441 Elevation) each had a non-approved fire configuration type ~lug installed (holes had been drilled through the center and filled with 'All Thread" ). |
| | ~ Fire seal penetrations D102-3002 and D102-3003 (Diesel Generator Building 441 .Elevation) each had a non-approved fire configuration type (non-ferralloy) plug installed, and the penetrations were not 'listed in Plant Seal Tracking'System (PSTS) data base. 'he |
| | ~ Fire seal penetration D104-3063 (Diesel Generator Building, - 441 Elevation) was impaired in that the seal depth was less than required. |
| | ~ Fire seal penetration D113-2012 (Diesel Generator Building - 441 Elevation) was impaired in that through and the penetration not re-sealed. |
| | it appears that a cable had been pulled b) On March 24, 1988 it was documented on a Plant Nonconformance Report that: |
| | Fire seal penetration R116-3003.9 (Reactor Building - 422 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed. |
| | t Fire seal penetration R116-3003.10 (Reactor Building - 422. Elevation) was impaired in that the plug had a drilled hole through its center, and the penetration was not listed in the PSTS data base. |
| | Fire seal penetration R116-3011.4 (Reactor Building - 444 Elevation) was impaired in that the seal depth was less than required. |
| | Fire seal penetration R116-3011.6 (Reactor Building - 444 Elevation) was impaired in that the plug had a drilled hole through its center, and the penetration was'not listed in the PSTS data base. |
| | Fire seal penetration R410-4004.7 (Reactor Building - 522 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed. |
| | NRC FORM 3554 4 U.S.GPO (98$ 0.824 538/455 (983 I |
| | |
| | NRC Form 358A V.S. NUCLEAR REGULATORY COMMISSION IS'83 I LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVEO OMS NO. 3150WIOO EXPIRES: 8/3I/88 FACILITY NAME III OOCKET NVMSER ITI LER NVMSER ISI PAGE I3I YEAR NUMOEII Vi IIEVISION |
| | ~r'y SEOVENTIAL Ri+i NUMef A Washington Nuclear Plant - Unit 2 o 5 o o o 39 788 0 0 8 00 03 OF 0 5 TEXT I//more epoo>>/I pppppnrL Pop o/8/Or'M/ /VRC forIII38SAS/(IT/ |
| | The problems were identified during the performance of ongoing activities associated with further corrective actions committed to in a previous LER (87-030, "Upgraded Plant Technical Specification Fire Wall not Constructed to gualify as a Three-Hour Fire Barrier and Wall Penetration not Sealed" ). Specifically, the Supply System committed to perform a 10(C review of documentation, and physical walkdowns of all accessible Technical Specification walls and penetrations, to determine the adequacy of PSTS. The problems noted in this LER (88-008) were discovered during the ongoing physical walkdowns. |
| | The cause of this LER is currently under investigation. |
| | Immediate Corrective Action As required by the Plant Technical Specifications, the penetrations were placed on an hourly fire tour. |
| | Further Discussion and Corrective Action a) Further Discussion |
| | ~ Fire seal penetrations D101-3002, D101-3003, D102-3002 and D102-3003 are located in Fire Area DG-V (1B Diesel Oil Tank Pump Room). |
| | o Fire seal penetration D104-3063 is located in Fire Area DG-I (HPCS Diesel Generator). |
| | ~ Fire seal penetration D113-2012 is located in Fire Area DG-III ( 1B Diesel Generator). |
| | o Fire seal penetrations R116-3003.9, R116-3003.10, R116-3011.4 and R116-3011.6 are located in Fire Area R-IV (RHR Pump Room Rl, Pipe Chase and RHR Heat Exchanger "B" Equipment Room). |
| | ~ Fire seal penetration R410-4004.7 is located in Fire Area R-VIII (MCC Room Division 2). I b) Further Corrective Action |
| | ~ Maintenance Work Requests (MWRs) were written to repair/seal the penetrations. |
| | ~ The penetrations which were not previously included in the PSTS data base were added to the data base. |
| | ~ At the completion of the 100% review - of documentation, and physical walkdowns of all accessible Technical Specification walls and penetrations, a supplemental report describing any further deficiencies discovered will be submitted. |
| | NRC FORM 3OOA o U.S GPO:1988 0 824 538/455 I983) |
| | |
| | NRC Form 388A |
| | $ 431 OO LICENSEE EVENT REPORT (LER) TEXT CONTINUATION |
| | ~ t US. NUCLEAR REGULATORY COMMISSION APPROVEO OM8 NO, 3150M(04 EXPIRES: 8/31188 FACILITY NAME (I) DOCKET NUMSER (Tl LER NUMSER Iel PAGE I31 f |
| | Y AR a ffQVE NTIAL (3Q NVMsf4 i 4(V>>KI> |
| | NVMsf 4 Washington Nuclear Plant Unit 2 0 S 0 0 0 00 00 4 OF TExT RY naacp <<>>cp <<(ppund, 1>>p <<ApFp44(HRc Ann 388AYI (Ill Safety Si ni fi c ance Although there were no fires during the event period, the following is a description of the consequences had a Design Basis Fire had occurred in the areas described in this LER. |
| | a) Fire Areas DG-I, DG-III and DG-V Smoke from a fire would activate one or more smoke detectors, which would alarm in the Control Room. The fire brigade would be dispatched and take appropriate action in accordance with the pre-fire plans and emergency response procedures. Manual hoses are available. |
| | The thermal detection system would sense a high heat condition and activate the pre-action sprinkler system. Automatic spray heads would fuse and control the fire. |
| | b) Fire Areas R-IV and R-VIII Smoke from a fire would activate an ionization detector, which would alarm in the Control Room. The fire brigade would be dispatched and take appropriate action in 'ccordance with the pre-fire plans and emergency response procedures. Manual hoses are available. |
| | In addition, Fire Area R-IV has a low fire loading and, as a result, the probability of a fire spreading is considered remote. |
| | Accordingly, this event did not affect the health and safety of either the public or Plant personnel. |
| | Similar Events LERs 85-028, 87-004-00, 87-004-01 and 87-030. |
| | EIIS Information Text Reference EIIS Reference System Component Fire Penetration Seals KP Pen D101-3002 D101-3003 D102-3002 D102-3003 D104-3063 D113-2012 R116-3003.9 R116-3003.10 NRC FORM 3584 *U.s opo:lose o 83f essMss (883 I |
| | |
| | NAC form 344A U.S. NUCLEAR REGULATORY COMMISSION IS4)3) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVEO OMS NO. 3)50&)04 EXPIRES: 8/31/88 PACILITY NAME )1) OOCKET NUMSEA l2) LEA NUMSER (4) PAGE 13) |
| | YEAR 440USNTIAL m'iEr II4 VISION my&. NUM 4O YeWA NVMSSII Washington Nuclear Plant - Unit 2 o s o o o 8 8 0 0 0 0 0 5 OF 0 5 TEXT //f more Secre ir reerr)wS eee rr/R/Or'on/I HRC for//I 3//fASI Ill) |
| | R116-3011.4 R116-3011.6 R410-4004.7 Diesel Generator Bldg NB Bldg Reactor Bldg NG Bl dg 1B Diesel Oil Tank Pump Room ME Room HPCS Diesel Generator EK Room 1B Diesel Generator NB Room RHR Pump Room Rl nIE Room Meat Exchanger NBN RHR Equipment Room I1E Room IRCC Room, Division 2 I1E Room NIIC PO/IM 344A oU 8GPO;ISSS-O $ 24 $ 38/4$ $ |
| | 1883) |
| | |
| | ai WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 April 22, 1988 Document Control Desk UPS. Nuclear Regulatory Commission Washington, D,C. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.88-008 | | NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO. 88-008 |
| | |
| | ==Dear Sir:== |
|
| |
|
| ==Dear Sir:==
| | Transmitted herewith is Licensee Event Report No. 88-008 for the WNP-2 Plant. |
| Transmitted herewith is Licensee Event Report No.88-008 for the WNP-2 Plant.This report is s'ubmitted 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 report is s'ubmitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence. |
| Very truly yours,'..Powers (M/D 927M)WNP-2 Plant Manager CMP: lg | | Very truly yours, WNP-2 Powers (M/D 927M) |
| | Plant Manager CMP: lg |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| -Licensee Event Report No.88-008 cc: Mr.John B.Martin, NRC-Region V Mr.C.J.Bosted, NRC Site (M/D 901A)INPO Records Center-Atlanta, GA Ms.Dottie Sherman, ANI Mr.D.L.Williams, BPA (M/D 399)p 7g 5 05'r'f}} | | |
| | -Licensee Event Report No. 88-008 cc: Mr. John B. Martin, NRC Region V Mr. C.J. Bosted, NRC Site (M/D 901A) |
| | INPO Records Center Atlanta, GA Ms. Dottie Sherman, ANI Mr. D.L. Williams, BPA (M/D 399) p 7g 5 05'r'f}} |
|
|---|
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
DISTRIBUTION ee DEMONSTRATION SYSTEM
,4C CEISRA7ZD REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8805030155 DOC.DATE: 88/04/22 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION ARBUCKLE,J.D. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 88-008-00:on 880318,plant Tech Spec fire penetration seals discovered impaired/unsealed during ongoing 1004 insp.
W/8 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR A ENCL W TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
SIZE: C NOTES:
ID RECIPIENT PD5 LA CODE/NAME SAMWORTH, R COPIES LTTR ENCL 1
1 1
1 ID RECIPIENT PD5 PD CODE/NAME COPIES LTTR ENCL 1 1 j
A INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 . 1 AEOD/DS P/T PAB '
AEOD/DSP/ROAB 2 2 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR7DRQN/SIB 9A 1 1 NRR/PMAS/ILRB12 1 1 G~~
RES7DE/EIB 02 1 1
1 1
RES TELFORD,J RES/DRPS DIR 1
1 .
1 1
RGN5 FILE 01 1 1 EXTERNAL: EGS(G GROH,M 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 j
A D
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TOTAL'UMBER OF COPIES REQUIRED: LTTR 45 ENCL 44
NRC Form 368 V.S. NUCLEAR REGULATORY COMMISSION (8.83)
APPROVED OMB NO. 3160-0104 LICENSEE EVENT REPORT ILER) EXPIRES: 8/31/88 FACILITY NAME (11 DOCKET NUMBER (21 PAGE (3/
Washin ton Nuclear Plant - Unit 2 0 5 0 0 03 9 7 1 OF 0/5 Plant Technical Specification Fire Penetration Seals Discovered Impaired/Unsealed Durin On oin 100% Ins ection - Cause Unknown EVENT DATE (5) LER NUMBER id) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH YE'AR YEAR SCOUCNT/AL Rdvrd/ON DAY YEAR FACILITYNAMES DOCKET NUMBER(SI DAY NUMBER yw7 NUMBER MONTH 0 5 0 0 0 3 1 8 8 8 008 0 0 0 4 228 8 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR (): (Cnec/r one or more OI tne Iollowinp/ (ll MODE (8) 20.402(6) 73.71(o) 1 20.405(cl 50.73( ~ l(21(iv)
POWE R 20.406( ~ I ( 1 I ii) 50.35(cl(ll 50,73( ~ l(21(vl 73.71(cl LEVEL (101 20.406( ~ ) (11(ii) 50.3d (c) l2) 50,73(e) l2)(xiii OTHER ISpecily rn Aottrett oelow end in Text, NRC Po" 20.406( ~ ) (I l(riil 59.73( ~ l(2)(i) 50 73( ~ I(2)(vri/1(AI 366A/
20A05 I ~ l(1) (Iv) 60.73( ~ I I2) lit) 50.73 (e I (2)(viii)I 81 20.406( ~ ) (1)(v) 60.73(el(2) liii) 60.73( ~ I(2)(e)
LICENSEE CONTACT FOR THIS LEA (121 NAME TELFPHONE NUMBER AREA CODE D Ar 1 Com liance En ineer 0 9 3 7 7 - 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 6'IANUFAC REPORTABLE MANUFAC CAUSE SYSTEM COMPONENT TURER TO NPADS CAUSE SYSTEM COMPONENT TURER Av%664 ~gv p/4>ghppklpN r%%4+Ay"
po)tr ~v.c..i/+6
>%3.";,P@$ :$ 8~>cog':
SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)
YFS III ywcomplete EXPECTEO SUSMISSION OATEI ivO ABSTRACT ILimit to /400 /peter, l,e., epproximetely IIINen rlnple rpsCe tyPewritNn linn/ (181 On March 23, 1988 and March 25, 1988 it was determined that problems documented (on March 18, 1988 and March 24, 1988) with regard to ll Plant Technical Specification fire penetrations were reportable under 10CFR50.73 (a)(2)(i). The penetrations were impaired such that they would not qualify as a three-hour fire barrier. The penetrations are located in the Diesel Generator and Reactor Buildings.
The problems were identified during the performance of ongoing physical walkdowns of all accessible Technical Specification walls and penet'rations as further corrective action committed to in LER 87-030.
As required by the Plant Technical Specifications, the penetrations were placed on an hourly fire tour. Further corrective actions include 1) preparing Maintenance Work Requests (MWRs) to repair/seal the penetrations, and 2) completing the 100K review of documentation and physical walkdowns of all accessible Technical Specification walls and penetrations. At the completion of the review and walkdowns, a supplemental report describing any further deficiencies discovered will be submitted.
The cause of this event is currently under investigation.
It was determined that this event did not affect the health and safety of either the public or Plant personnel due to the fire protection design of the fire areas involved.
8805030155 SS0422 PDR ADOCK 05000397 S DCD NRC Form 3dd (9 83)
NRC Forro 358A OO OO U.S. NUCLEAR REGULATORY COMMISSION
((S83 I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMS NO. 3150WI04 EXPIRES: 8/3(/88 FACILITY NAME ((I OOCKET NUMSER (2l LER NUMSER (SI PAGE (3l PM 5EQVENTIAL ~ra? 45VI5ION I'2 NVM554 NVM554 Washington Nuclear Plant - Unit 2 0 S 0 O 0 0 0 0 0 02oF 0- 5 TEXT ///more spoce is /tr/Item. ose ~ /5 'orre/HRC Form 3//SA'5/(ITI Pl ant Condi ti ons a) Power Level - 100%
b) Plant Mode - 1 (Power Operation)
Event Descri tion On March 23, 1988 and March 25, 1988 the following problems which were documented with regard to Plant Technical Specification fire penetration seals were determined to be reportable under 10CFR50.73 (a)(2)(i).
a) On March 18, 1988 it was documented on a Plant Nonconformance Report that:
Fire seal penetrations D101-3002- and D101-3003 (Diesel Generator Building 441 Elevation) each had a non-approved fire configuration type ~lug installed (holes had been drilled through the center and filled with 'All Thread" ).
~ Fire seal penetrations D102-3002 and D102-3003 (Diesel Generator Building 441 .Elevation) each had a non-approved fire configuration type (non-ferralloy) plug installed, and the penetrations were not 'listed in Plant Seal Tracking'System (PSTS) data base. 'he
~ Fire seal penetration D104-3063 (Diesel Generator Building, - 441 Elevation) was impaired in that the seal depth was less than required.
~ Fire seal penetration D113-2012 (Diesel Generator Building - 441 Elevation) was impaired in that through and the penetration not re-sealed.
it appears that a cable had been pulled b) On March 24, 1988 it was documented on a Plant Nonconformance Report that:
Fire seal penetration R116-3003.9 (Reactor Building - 422 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed.
t Fire seal penetration R116-3003.10 (Reactor Building - 422. Elevation) was impaired in that the plug had a drilled hole through its center, and the penetration was not listed in the PSTS data base.
Fire seal penetration R116-3011.4 (Reactor Building - 444 Elevation) was impaired in that the seal depth was less than required.
Fire seal penetration R116-3011.6 (Reactor Building - 444 Elevation) was impaired in that the plug had a drilled hole through its center, and the penetration was'not listed in the PSTS data base.
Fire seal penetration R410-4004.7 (Reactor Building - 522 Elevation) was impaired in that it appears that a cable had been pulled through and the penetration not re-sealed.
NRC FORM 3554 4 U.S.GPO (98$ 0.824 538/455 (983 I
NRC Form 358A V.S. NUCLEAR REGULATORY COMMISSION IS'83 I LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVEO OMS NO. 3150WIOO EXPIRES: 8/3I/88 FACILITY NAME III OOCKET NVMSER ITI LER NVMSER ISI PAGE I3I YEAR NUMOEII Vi IIEVISION
~r'y SEOVENTIAL Ri+i NUMef A Washington Nuclear Plant - Unit 2 o 5 o o o 39 788 0 0 8 00 03 OF 0 5 TEXT I//more epoo>>/I pppppnrL Pop o/8/Or'M/ /VRC forIII38SAS/(IT/
The problems were identified during the performance of ongoing activities associated with further corrective actions committed to in a previous LER (87-030, "Upgraded Plant Technical Specification Fire Wall not Constructed to gualify as a Three-Hour Fire Barrier and Wall Penetration not Sealed" ). Specifically, the Supply System committed to perform a 10(C review of documentation, and physical walkdowns of all accessible Technical Specification walls and penetrations, to determine the adequacy of PSTS. The problems noted in this LER (88-008) were discovered during the ongoing physical walkdowns.
The cause of this LER is currently under investigation.
Immediate Corrective Action As required by the Plant Technical Specifications, the penetrations were placed on an hourly fire tour.
Further Discussion and Corrective Action a) Further Discussion
~ Fire seal penetrations D101-3002, D101-3003, D102-3002 and D102-3003 are located in Fire Area DG-V (1B Diesel Oil Tank Pump Room).
o Fire seal penetration D104-3063 is located in Fire Area DG-I (HPCS Diesel Generator).
~ Fire seal penetration D113-2012 is located in Fire Area DG-III ( 1B Diesel Generator).
o Fire seal penetrations R116-3003.9, R116-3003.10, R116-3011.4 and R116-3011.6 are located in Fire Area R-IV (RHR Pump Room Rl, Pipe Chase and RHR Heat Exchanger "B" Equipment Room).
~ Fire seal penetration R410-4004.7 is located in Fire Area R-VIII (MCC Room Division 2). I b) Further Corrective Action
~ Maintenance Work Requests (MWRs) were written to repair/seal the penetrations.
~ The penetrations which were not previously included in the PSTS data base were added to the data base.
~ At the completion of the 100% review - of documentation, and physical walkdowns of all accessible Technical Specification walls and penetrations, a supplemental report describing any further deficiencies discovered will be submitted.
NRC FORM 3OOA o U.S GPO:1988 0 824 538/455 I983)
NRC Form 388A
$ 431 OO LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
~ t US. NUCLEAR REGULATORY COMMISSION APPROVEO OM8 NO, 3150M(04 EXPIRES: 8/31188 FACILITY NAME (I) DOCKET NUMSER (Tl LER NUMSER Iel PAGE I31 f
Y AR a ffQVE NTIAL (3Q NVMsf4 i 4(V>>KI>
NVMsf 4 Washington Nuclear Plant Unit 2 0 S 0 0 0 00 00 4 OF TExT RY naacp <<>>cp <<(ppund, 1>>p <<ApFp44(HRc Ann 388AYI (Ill Safety Si ni fi c ance Although there were no fires during the event period, the following is a description of the consequences had a Design Basis Fire had occurred in the areas described in this LER.
a) Fire Areas DG-I, DG-III and DG-V Smoke from a fire would activate one or more smoke detectors, which would alarm in the Control Room. The fire brigade would be dispatched and take appropriate action in accordance with the pre-fire plans and emergency response procedures. Manual hoses are available.
The thermal detection system would sense a high heat condition and activate the pre-action sprinkler system. Automatic spray heads would fuse and control the fire.
b) Fire Areas R-IV and R-VIII Smoke from a fire would activate an ionization detector, which would alarm in the Control Room. The fire brigade would be dispatched and take appropriate action in 'ccordance with the pre-fire plans and emergency response procedures. Manual hoses are available.
In addition, Fire Area R-IV has a low fire loading and, as a result, the probability of a fire spreading is considered remote.
Accordingly, this event did not affect the health and safety of either the public or Plant personnel.
Similar Events LERs85-028, 87-004-00, 87-004-01 and 87-030.
EIIS Information Text Reference EIIS Reference System Component Fire Penetration Seals KP Pen D101-3002 D101-3003 D102-3002 D102-3003 D104-3063 D113-2012 R116-3003.9 R116-3003.10 NRC FORM 3584 *U.s opo:lose o 83f essMss (883 I
NAC form 344A U.S. NUCLEAR REGULATORY COMMISSION IS4)3)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVEO OMS NO. 3)50&)04 EXPIRES: 8/31/88 PACILITY NAME )1) OOCKET NUMSEA l2) LEA NUMSER (4) PAGE 13)
YEAR 440USNTIAL m'iEr II4 VISION my&. NUM 4O YeWA NVMSSII Washington Nuclear Plant - Unit 2 o s o o o 8 8 0 0 0 0 0 5 OF 0 5 TEXT //f more Secre ir reerr)wS eee rr/R/Or'on/I HRC for//I 3//fASI Ill)
R116-3011.4 R116-3011.6 R410-4004.7 Diesel Generator Bldg NB Bldg Reactor Bldg NG Bl dg 1B Diesel Oil Tank Pump Room ME Room HPCS Diesel Generator EK Room 1B Diesel Generator NB Room RHR Pump Room Rl nIE Room Meat Exchanger NBN RHR Equipment Room I1E Room IRCC Room, Division 2 I1E Room NIIC PO/IM 344A oU 8GPO;ISSS-O $ 24 $ 38/4$ $
1883)
ai WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 April 22, 1988 Document Control Desk UPS. Nuclear Regulatory Commission Washington, D,C. 20555
Subject:
NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.88-008
Dear Sir:
Transmitted herewith is Licensee Event Report No.88-008 for the WNP-2 Plant.
This report is s'ubmitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.
Very truly yours, WNP-2 Powers (M/D 927M)
Plant Manager CMP: lg
Enclosure:
-Licensee Event Report No.88-008 cc: Mr. John B. Martin, NRC Region V Mr. C.J. Bosted, NRC Site (M/D 901A)
INPO Records Center Atlanta, GA Ms. Dottie Sherman, ANI Mr. D.L. Williams, BPA (M/D 399) p 7g 5 05'r'f
