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| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 8907250172 DOC.DATE: 89/07/14 NOTARIZED: | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIL:50-335 St.Lucie Plant,'Unit 1, Florida Power&Light Co.AUTH NAME~AUTHOR AFFILIATION HOL1FIELD,C.D. | | ACCESSION NBR: 8907250172 DOC. DATE: 89/07/14 NOTARIZED: NO DOCKET N FACIL:50-335 St. Lucie Plant,'Unit 1, Florida Power & Light Co. 05000335 AUTH NAME ~ AUTHOR AFFILIATION HOL1FIELD,C.D. Florida Power & Light Co. L ~ 0" WOODY,C.O. Florida Power & Light R |
| Florida Power&Light Co.L~0" WOODY,C.O. | | = ~ RECIPIENT AFFILIATION Co.'ECIP.NAME I |
| Florida Power&Light Co.'ECIP.NAME | |
| =~RECIPIENT AFFILIATION
| |
|
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 89-002-00:on 890614,inoperability of 1B diesel fuel oil sys caused by misaligned valve due to personnel error.W/8 DISTRIBUTION.CODE: | | LER 89-002-00:on 890614,inoperability of 1B diesel fuel oil sys caused by misaligned valve due to personnel error. |
| IE22T COPIES RECEIVED:LTR | | W/8 DISTRIBUTION.CODE: IE22T COPIES RECEIVED:LTR ~ ENCL J SIZE:. |
| ~ENCL J SIZE:.TITLE:;50.73/50.'9 Licensee Event.Report (LER), Incident" Rpt, etc.NOTES DOCKET N 05000335 R I RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB | | TITLE:; 50.73/50.'9 Licensee Event. Report (LER), Incident" Rpt, etc. |
| 'H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSIR/EIB RGN2 FILE.01 EXTERNAL EG&G WILLIAMS P S L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A 1 1 1 1 1 1 1 1 1 , 1 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1.1 1'4 4 1 1 1 1 I 1 1 COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP IRM/DCTS/DAB ,NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 NRR/REPQRPB 10~02, S/DSR PRAB FORD BLDG HOY P A LPDR NSIC MAYS,G COPIES LTTR ENCL 1.1 2 2 1.1 2'~1 1-1 0 1.1 1 1 1 1 1 1 1 1 2 2~1.;1 1 1 1 1 1 1 1 1 D S D NOXK'IO ALL nRZDSn RZCZE'ZENXS PIZASE HELP US KO REDUCE%MTEL CONZACZ'IHE DOQlMEÃZ CCRZRDL DESK, RXN P1-37 (EZZ.20079)m ELXKBQXS YOUR MNE HKH DISTRIHVTIGN.
| | NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 .1 NORRIS,J 1 1 D INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 S ACRS WYLIE 1 1 AEOD/DOA 1 .1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 ' |
| IZSTS PDR DOCUMERHB YOU DGN~T NEZDf h D S FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL , 42 ox14000, Juno Beach, FL 33408.0420 JULY.1 4 19B9 L-89-242 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
| | DEDRO 1 1 IRM/DCTS/DAB ~ 1 1-NRR/DEST/ADE 8H 1 I |
| Re: St.Lucie Unit 1 Docket No.50-335 Reportable Event: 89-02 Date of Event: June 14, 1989 Misaligned Valve Caused Inoperability of the 1B Diesel Fuel Oil S stem Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.Very truly yours, O.Wood Acting S i r Vice President-Nuclear COW/JRH/cm Attachment cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St.Lucie Plant p9072lg0 f 72 P907 1 4 PDR PDOCK 0500033 PDC an FPL Group company RC Form 355 5'33)LICENSEE EVENT REPORT tLER U.S.NUCLEAR REQULATORY COMMISSION APPROVED OMS NO.3150410e EXPIRES: 5/31/SS FACILITY NAME (II St.Lucie Unit 1"'""'Nisaligned Valve Caused Inoperability of the lB D'l Fuel pil S stem Due to Personnel Error DOCKET NUMBER (2)0 5 0 0 0 3 PA E 5 1 OF 0 EVENT OATS ISI LKR NUMBER ISI REPORT DATE It)OTHER FACILITIES INVOLVED I~I MONTH OAY 0 614 YEAR YEAR 8 9 NNQUNNTIAI.
| | ,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 'H 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/PEB 10 1 1 NRR/DOEA/EAB 11 1 1. NRR/ REPQRPB 10 2 2 ~ |
| trUMNNR 0 0 2 MONTH SzrP,.NUMNNA-p p 07 OAY 1 4 YEAR 8 9 FACILITY HAM55 N/A DOCKET HUMBERIS)0 5 0 0 0 0 5 0 0 0 OPERATINO MOOt (Sl~OWER LEUEL 1 P P (10 I 20A02(bl 20AOB(elll l(0 20AOBIel(1)(Nl 20AOB(el(1 l(NO 20AOB(e)(1)(N) 20AOB (e)II)le)20AOB(el SOM(cl(II SOM(cl(2)X 50.73lel(2)III 50.73 Ie l(2)IN)50.73lel(2)
| | NUDOCS-ABSTRACT 1 1 1' |
| IN)LICKNSKE CONTACT FOR THIS LKR (12)50.734)12)
| | ~ |
| IN)50.734)(2 l(el 50.7341(211rNI 50,734)l2)I cNI)(Al 50.73(el(2((r BI(IS)50.73(e)l2 I I el THIS REPORT IS SUBMITTED PURSUANT T 0 THK REOUIREMENTS OF 10 CFR gr/Chectt one or more of the fo//orfinp/
| | 02, 1.; 1 RES/DSIR/EIB 1 S/DSR PRAB 1 1 RGN2 FILE. 01 1 EXTERNAL EG&G WILLIAMS S P 4 4 FORD BLDG HOY P A 1 1 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 D NSIC MURPHY,G.A I 1 1 h |
| 01 73.71(II)73.71(cl OTHER/Specify in Aettrect Oe/ory enr/in Tert, Hf)C Form 355l/NAME Charles D.Holifield, Shift Technical Advisor TELEPHONE NUMBER AREA CODE 40 74 65-355 0 COMPLETE OHK LINE SOll EACH COMPONENT FAILURE OKSCRISKD IH THIS REPORT 113)CAUSE SYSTKM COMPONENT MANUFAC.TURER TO NpROS Ajar y f CAUSE SYSTKM COMPONENT:@4%.,YQ,...Stol MANUFAC.TURER EPORTABL TO HPRDS NUMEN SUPPLEMENTAL REPORT EXPECTED (1el EXPECTED SUBMISSION DATE II BI%8~>$MONTH OAY YEAR YES/lf yer, complete EXPECTED$(/Sef/SS/OH DATE/NO ABBTRAcT/Limit to teo0 rptcer,/.e., epproe/merely f/freon r/noreopece typewr/(ton lintel (15)ABSTRACT On June 14, 1989, at 1740, with Unit 1 in Mode 1 at 1004 power, a routine weekly valve status check was performed in accordance with a plant procedure which recpxires a valve position check of various emergency diesel system valves.While performing this valve status check, the 1B diesel fuel oil transfer pump discharge valve was found in the locked closed position.Although the 1B diesel was capable of starting and supplying post-accident loads during the event, it was administratively rendered out of service due to the inoperability of the 1B diesel fuel oil transfer pump, per Technical Specification 3.8.1.1.b.3.
| | D NOXK 'IO ALL nRZDSn RZCZE'ZENXS S |
| The most probable root cause of the mispositioned valve was personnel error by a utility non-licensed operator, though the responsible individual has not been identified.
| | PIZASE HELP US KO REDUCE %MTEL CONZACZ 'IHE DOQlMEÃZ CCRZRDL DESK, RXN P1-37 (EZZ. 20079) m ELXKBQXS YOUR MNE HKH DISTRIHVTIGN. |
| A contributing factor was the failure to record the mispositioned valve in the valve deviation log.Corrective actions included re-opening and locking open the valve, and counseling the operators on the importance of, and the use of, the valve deviation log.NRC Form 355 (5 03 I C Form 3SSA 8 831 LICENSEE+NT REPORT (LERI TEXT CONTINUON U.S.NUCLEAR REOUI.ATORY COMMISSION APPROVED OMB NO.3150WI04 EX PIR EB: 8/31/88 F CILITY NAME 111 DOCKET NUMBER I31 LER NUMBER (81 YEAR:~<'EQUENTIAI' | | IZSTS PDR DOCUMERHB YOU DGN~T NEZDf FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL , 42 |
| 'EViSION N UM S E A:.>1 rr U M S~A PACE l31 St.Lucie Unit 1 o s o o o 3 89-00 2-00 02oF 0 3 TEXT///rrroro Epoco it o//rr'rod.
| | |
| Irw odd/rrorro/H//C Forrrr 38//AS/l I 3)DESCR ION OF HE EVENT On June 14, 1989, at 1740, with Unit 1 in Mode 1 at 100%power, a routine weekly emergency diesel system valve status check was performed by a utility non-licensed operator in accordance with Administrative Procedure 1-0010125A.
| | ox14000, Juno Beach, FL 33408.0420 JULY. 1 4 19B9 L-89-242 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| While performing this valve status check, the 1B diesel fuel oil transfer pump discharge valve (EIIS:ISV) was found in the locked closed position.This administratively rendered the 1B diesel generator out of service, per Technical Specification 3.8.1.1.b.3.
| | Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 89-02 Date of Event: June 14, 1989 Misaligned Valve Caused Inoperability of the 1B Diesel Fuel Oil S stem Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event. |
| The valve was unlocked, re-opened, locked opened, and independently verified locked open, within 5 minutes of finding it closed.Prior to this event, the last time the pump dischaxge valve was operated was at 1015 on June 5, 1989, to place the 1B diesel fuel oil tank on recirculation.
| | Very truly yours, O. Wood Acting S i r Vice President Nuclear COW/JRH/cm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC 14 p9072lg0 f 72 P907 0500033 PDR PDOCK PDC an FPL Group company |
| This was required for a chemistry sample of the 1B diesel fuel oil tank.Although the valve was re-opened and locked open after the sample was completed, the closing and re-opening of the valve was not recorded in the Valve Deviation Log in accordance with Administrative Procedure 1-0010123.
| | |
| The valve's locked open position was verified independently on June 7 by a utility non-licensed operator, and on June 13 by a QC Inspector, when the valve status check of Administrative Procedure 1-0020235A was performed.
| | U.S. NUCLEAR REQULATORY COMMISSION RC Form 355 5'33) APPROVED OMS NO. 3150410e EXPIRES: 5/31/SS LICENSEE EVENT REPORT tLER DOCKET NUMBER (2) PA E FACILITY NAME (II 0 0 0 3 5 OF 0 St. Lucie Unit 0 5 1 |
| On June 14, 1989, the valve was found in the locked closed position.CAUSE OF TH EVENT No fuel oil samples wexe taken and no maintenance was performed on the diesel fuel oil system between 1600 on June 13, 1989 and 1740 on June 14, 1989.Only Operations Department personnel have access to the valve locking device key.Therefore, the most probable root cause of the event was personnel error by a utility non-licensed operator.After investigation, the responsible individual has not been identified.
| | "'""'Nisaligned 1 Inoperability of the lB D'l EVENT OATS ISI Valve Fuel pil Caused S stem Due LKR NUMBER ISI to Personnel Error REPORT DATE It) OTHER FACILITIES INVOLVED I ~ I NNQUNNTIAI. OAY YEAR FACILITYHAM55 DOCKET HUMBERIS) |
| A contributing factor to the event was the failure to record the repositioning of the valve in the Valve Deviation Log.NAC FOAM SOFA IMSI C Form 3SSA JI LICENSEE NT REPORT (LER)TEXT CONTIN ON U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150M(04 EXPIRES: 8/31/88 I QCILITT NAME (ll St.Lucie Unit 1 DOCKET NVMSER (3)YEAR LER NVMSER (8)~$;SSOUSNTIAL
| | MONTH OAY YEAR YEAR trUMNNR SzrP,. NUMNNA MONTH N/A 0 5 0 0 0 0 614 8 9 0 0 2 p p 07 1 4 8 9 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T0 THK REOUIREMENTS OF 10 CFR gr /Chectt one or more of the fo//orfinp/ 01 OPERATINO MOOt (Sl 20A02(bl 20AOB(el 50.734)12) IN) 73.71(II) |
| .(N NUMSSR REVISION NUMSSII PACE (31 TEXT/I/moro tpoco it ror/u/rorL uto tr/I/I(/ooo///RC | | ~ OWER 20AOB(elll l(0 SOM(cl(II 50.734) (2 l(el 73.71(cl LEUEL (10 I 1 P P 20AOBIel(1) (Nl SOM(cl(2) 50.7341(211rNI OTHER /Specify in Aettrect Oe/ory enr/in Tert, Hf)C Form 20AOB(el(1 l(NO X 50.73lel(2)III 50,734) l2) I cNI) (Al 355l/ |
| %%dnrr 385l't/(171 o s o o o 33 589-0 0 2-0 0 0 3 oF 0 3 ANALYSIS OF THE EVENT This event has been deemed reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's Technical Specifications. | | 20AOB(e)(1)(N) 50.73 Ie l(2) IN) 50.73(el(2((r BI(IS) 20AOB (e) II ) le) 50.73lel(2) IN) 50.73(e) l2 I I el LICKNSKE CONTACT FOR THIS LKR (12) |
| Since the 1B Diesel was administratively out of service for as long as 25 hours, the surveillance requirements of Technical Specification 3.8.1.1., which requires that the operability of the other Diesel be tested within 1 hour and every 8 hours thereafter, should have been performed. | | NAME TELEPHONE NUMBER AREA CODE Charles D. Holifield, Shift Technical Advisor 40 74 65 -355 0 COMPLETE OHK LINE SOll EACH COMPONENT FAILURE OKSCRISKD IH THIS REPORT 113) |
| However, this surveillance was not done because the operators were not aware of the out of service diesel.Each emergency diesel is designed for full post-accident load operation for 75 minutes on the day tanks.The fuel oil transfer pump starts and the inlet valve to the day tanks opens at a day tank level of 23 inches.With the fuel oil transfer pump discharge valve shut, the diesel generator would start if required.However, automatic makeup to the day tank would be prevented, and the day tank level would decrease.Approximately 39 minutes later, at a level of 11 inches in the day tank, the low level annunciator would alert the operators of the problem locally and in the control room.This would leave approximately 36 minutes to dispatch an operator to the area to locate, unlock, and re-open the pump discharge valve.Since the emergency diesel was available to perform its safety function, the health and safety of the public were not affected by this event.CORRECTIVE ACTIONS 1)Operations personnel re-opened and locked open the valve.2)The Operations Supervisor counselled the operators on the importance of, and the use of, the valve deviation log.ADDITIONAL NFORMA ON 1.COMPONENT IDENTIFICATION 2~This event was not caused by component failure.PREVIOUS SIMILAR EVENTS For a similar event, see LER 5335-82-48, which pertains to the inoperability of the 1A diesel fuel oil pump due to valve mispositioning because of improper restoration from maintenance. | | MANUFAC. MANUFAC. EPORTABL CAUSE SYSTKM COMPONENT y f CAUSE SYSTKM COMPONENT TURER TO NpROS Ajar |
| | :@4%.,YQ, ... Stol TURER TO HPRDS NUMEN %8~>$ |
| | SUPPLEMENTAL REPORT EXPECTED (1el MONTH OAY YEAR EXPECTED SUBMISSION DATE II BI YES /lf yer, complete EXPECTED $ (/Sef/SS/OH DATE/ NO ABBTRAcT /Limit to teo0 rptcer, /.e., epproe/merely f/freon r/noreopece typewr/(ton lintel (15) |
| | ABSTRACT On June 14, 1989, at 1740, with Unit 1 in Mode 1 at 1004 power, a routine weekly valve status check was performed in accordance with a plant procedure which recpxires a valve position check of various emergency diesel system valves. While performing this valve status check, the 1B diesel fuel oil transfer pump discharge valve was found in the locked closed position. Although the 1B diesel was capable of starting and supplying post-accident loads during the event, it was administratively rendered out of service due to the inoperability of the 1B diesel fuel oil transfer pump, per Technical Specification 3.8.1.1.b.3. The most probable root cause of the mispositioned valve was personnel error by a utility non-licensed operator, though the responsible individual has not been identified. A contributing factor was the failure to record the mispositioned valve in the valve deviation log. |
| | Corrective actions included re-opening and locking open the valve, and counseling the operators on the importance of, and the use of, the valve deviation log. |
| | NRC Form 355 (5 03 I |
| | |
| | C Form 3SSA U.S. NUCLEAR REOUI.ATORY COMMISSION 8 831 LICENSEE+NT REPORT (LERI TEXT CONTINUON APPROVED OMB NO. 3150WI04 EX PIR EB: 8/31/88 F CILITY NAME 111 DOCKET NUMBER I31 LER NUMBER (81 PACE l31 YEAR:~<'EQUENTIAI' N UMS E A:. 'EViSION |
| | >1 rr U M S ~ A St. Lucie Unit 1 o s o o o 3 |
| | 89 00 2 00 02oF 0 3 TEXT ///rrroro Epoco it o//rr'rod. Irw odd/rrorro/H//C Forrrr 38//AS / lI 3) |
| | DESCR ION OF HE EVENT On June 14, 1989, at 1740, with Unit 1 in Mode 1 at 100% power, a routine weekly emergency diesel system valve status check was performed by a utility non-licensed operator in accordance with Administrative Procedure 1-0010125A. While performing this valve status check, the 1B diesel fuel oil transfer pump discharge valve (EIIS:ISV) was found in the locked closed position. This administratively rendered the 1B diesel generator out of service, per Technical Specification 3.8.1.1.b.3. The valve was unlocked, re-opened, locked opened, and independently verified locked open, within 5 minutes of finding it closed. |
| | Prior to this event, the last time the pump dischaxge valve was operated was at 1015 on June 5, 1989, to place the 1B diesel fuel oil tank on recirculation. This was required for a chemistry sample of the 1B diesel fuel oil tank. Although the valve was re-opened and locked open after the sample was completed, the closing and re-opening of the valve was not recorded in the Valve Deviation Log in accordance with Administrative Procedure 1-0010123. |
| | The valve's locked open position was verified independently on June 7 by a utility non-licensed operator, and on June 13 by a QC Inspector, when the valve status check of Administrative Procedure 1-0020235A was performed. |
| | On June 14, 1989, the valve was found in the locked closed position. |
| | CAUSE OF TH EVENT No fuel oil samples wexe taken and no maintenance was performed on the diesel fuel oil system between 1600 on June 13, 1989 and 1740 on June 14, 1989. Only Operations Department personnel have access to the valve locking device key. Therefore, the most probable root cause of the event was personnel error by a utility non-licensed operator. After investigation, the responsible individual has not been identified. A contributing factor to the event was the failure to record the repositioning of the valve in the Valve Deviation Log. |
| | NAC FOAM SOFA IMSI |
| | |
| | U.S. NUCLEAR REGULATORY COMMISSION C Form 3SSA JI LICENSEE NT REPORT (LER) TEXT CONTIN ON APPROVED OMS NO. 3150M(04 EXPIRES: 8/31/88 DOCKET NVMSER (3) PACE (31 I QCILITT NAME (ll LER NVMSER (8) |
| | YEAR ~$ |
| | .(N |
| | ; SSOUSNTIAL NUMSSR REVISION NUMSSII St. Lucie Unit 1 33 589 0 0 2 0 0 0 3 oF 0 3 o s o o o TEXT /I/ moro tpoco it ror/u/rorL uto tr/I/I(/ooo///RC %%dnrr 385l't/ (171 ANALYSIS OF THE EVENT This event has been deemed reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's Technical Specifications. Since the 1B Diesel was administratively out of service for as long as 25 hours, the surveillance requirements of Technical Specification 3.8.1.1., |
| | which requires that the operability of the other Diesel be tested within 1 hour and every 8 hours thereafter, should have been performed. However, this surveillance was not done because the operators were not aware of the out of service diesel. |
| | Each emergency diesel is designed for full post-accident load operation for 75 minutes on the day tanks. The fuel oil transfer pump starts and the inlet valve to the day tanks opens at a day tank level of 23 inches. With the fuel oil transfer pump discharge valve shut, the diesel generator would start automatic makeup to the day tank would be prevented, and the day if required. However, tank level would decrease. Approximately 39 minutes later, at a level of 11 inches in the day tank, the low level annunciator would alert the operators of the problem locally and in the control room. |
| | This would leave approximately 36 minutes to dispatch an operator to the area to locate, unlock, and re-open the pump discharge valve. |
| | Since the emergency diesel was available to perform its safety function, the health and safety of the public were not affected by this event. |
| | CORRECTIVE ACTIONS |
| | : 1) Operations personnel re-opened and locked open the valve. |
| | : 2) The Operations Supervisor counselled the operators on the importance of, and the use of, the valve deviation log. |
| | ADDITIONAL NFORMA ON |
| | : 1. COMPONENT IDENTIFICATION This event was not caused by component failure. |
| | 2 ~ PREVIOUS SIMILAR EVENTS For a similar event, see LER 5335-82-48, which pertains to the inoperability of the 1A diesel fuel oil pump due to valve mispositioning because of improper restoration from maintenance. |
| NRC SORM SSSA (WA1}} | | NRC SORM SSSA (WA1}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:RO)
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr
ML17241A4741999-08-31031 August 1999
Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr.
ML17241A4591999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr
ML17241A4301999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A4091999-06-30030 June 1999
Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17355A3681999-06-30030 June 1999
Revised Update to Topical QA Rept, Dtd June 1999
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3631999-05-31031 May 1999
Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17241A3331999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0841999-04-0707 April 1999
Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines.
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0961999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229B0461999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr
ML17229B0051999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9961999-01-14014 January 1999
SG Tube Inservice Insp Special Rept.
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9831998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17241A3581998-12-0909 December 1998
Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209.
ML17229A9421998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17241A4931998-11-0101 November 1998
Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project).
ML17229A9051998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr
ML17229A8871998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length
ML17229A8781998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8721998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8611998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17229A8481998-08-0707 August 1998
Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr.
ML17229A9461998-08-0707 August 1998
Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr.
ML17229A8301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7981998-06-30030 June 1998
Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr
ML17229A7701998-05-31031 May 1998
Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
1999-09-30
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 8907250172 DOC. DATE: 89/07/14 NOTARIZED: NO DOCKET N FACIL:50-335 St. Lucie Plant,'Unit 1, Florida Power & Light Co. 05000335 AUTH NAME ~ AUTHOR AFFILIATION HOL1FIELD,C.D. Florida Power & Light Co. L ~ 0" WOODY,C.O. Florida Power & Light R
= ~ RECIPIENT AFFILIATION Co.'ECIP.NAME I
SUBJECT:
LER 89-002-00:on 890614,inoperability of 1B diesel fuel oil sys caused by misaligned valve due to personnel error.
W/8 DISTRIBUTION.CODE: IE22T COPIES RECEIVED:LTR ~ ENCL J SIZE:.
TITLE:; 50.73/50.'9 Licensee Event. Report (LER), Incident" Rpt, etc.
NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 .1 NORRIS,J 1 1 D INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 S ACRS WYLIE 1 1 AEOD/DOA 1 .1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 '
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ox14000, Juno Beach, FL 33408.0420 JULY. 1 4 19B9 L-89-242 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 89-02 Date of Event: June 14, 1989 Misaligned Valve Caused Inoperability of the 1B Diesel Fuel Oil S stem Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Very truly yours, O. Wood Acting S i r Vice President Nuclear COW/JRH/cm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC 14 p9072lg0 f 72 P907 0500033 PDR PDOCK PDC an FPL Group company
U.S. NUCLEAR REQULATORY COMMISSION RC Form 355 5'33) APPROVED OMS NO. 3150410e EXPIRES: 5/31/SS LICENSEE EVENT REPORT tLER DOCKET NUMBER (2) PA E FACILITY NAME (II 0 0 0 3 5 OF 0 St. Lucie Unit 0 5 1
"'""'Nisaligned 1 Inoperability of the lB D'l EVENT OATS ISI Valve Fuel pil Caused S stem Due LKR NUMBER ISI to Personnel Error REPORT DATE It) OTHER FACILITIES INVOLVED I ~ I NNQUNNTIAI. OAY YEAR FACILITYHAM55 DOCKET HUMBERIS)
MONTH OAY YEAR YEAR trUMNNR SzrP,. NUMNNA MONTH N/A 0 5 0 0 0 0 614 8 9 0 0 2 p p 07 1 4 8 9 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T0 THK REOUIREMENTS OF 10 CFR gr /Chectt one or more of the fo//orfinp/ 01 OPERATINO MOOt (Sl 20A02(bl 20AOB(el 50.734)12) IN) 73.71(II)
~ OWER 20AOB(elll l(0 SOM(cl(II 50.734) (2 l(el 73.71(cl LEUEL (10 I 1 P P 20AOBIel(1) (Nl SOM(cl(2) 50.7341(211rNI OTHER /Specify in Aettrect Oe/ory enr/in Tert, Hf)C Form 20AOB(el(1 l(NO X 50.73lel(2)III 50,734) l2) I cNI) (Al 355l/
20AOB(e)(1)(N) 50.73 Ie l(2) IN) 50.73(el(2((r BI(IS) 20AOB (e) II ) le) 50.73lel(2) IN) 50.73(e) l2 I I el LICKNSKE CONTACT FOR THIS LKR (12)
NAME TELEPHONE NUMBER AREA CODE Charles D. Holifield, Shift Technical Advisor 40 74 65 -355 0 COMPLETE OHK LINE SOll EACH COMPONENT FAILURE OKSCRISKD IH THIS REPORT 113)
MANUFAC. MANUFAC. EPORTABL CAUSE SYSTKM COMPONENT y f CAUSE SYSTKM COMPONENT TURER TO NpROS Ajar
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SUPPLEMENTAL REPORT EXPECTED (1el MONTH OAY YEAR EXPECTED SUBMISSION DATE II BI YES /lf yer, complete EXPECTED $ (/Sef/SS/OH DATE/ NO ABBTRAcT /Limit to teo0 rptcer, /.e., epproe/merely f/freon r/noreopece typewr/(ton lintel (15)
ABSTRACT On June 14, 1989, at 1740, with Unit 1 in Mode 1 at 1004 power, a routine weekly valve status check was performed in accordance with a plant procedure which recpxires a valve position check of various emergency diesel system valves. While performing this valve status check, the 1B diesel fuel oil transfer pump discharge valve was found in the locked closed position. Although the 1B diesel was capable of starting and supplying post-accident loads during the event, it was administratively rendered out of service due to the inoperability of the 1B diesel fuel oil transfer pump, per Technical Specification 3.8.1.1.b.3. The most probable root cause of the mispositioned valve was personnel error by a utility non-licensed operator, though the responsible individual has not been identified. A contributing factor was the failure to record the mispositioned valve in the valve deviation log.
Corrective actions included re-opening and locking open the valve, and counseling the operators on the importance of, and the use of, the valve deviation log.
NRC Form 355 (5 03 I
C Form 3SSA U.S. NUCLEAR REOUI.ATORY COMMISSION 8 831 LICENSEE+NT REPORT (LERI TEXT CONTINUON APPROVED OMB NO. 3150WI04 EX PIR EB: 8/31/88 F CILITY NAME 111 DOCKET NUMBER I31 LER NUMBER (81 PACE l31 YEAR:~<'EQUENTIAI' N UMS E A:. 'EViSION
>1 rr U M S ~ A St. Lucie Unit 1 o s o o o 3
89 00 2 00 02oF 0 3 TEXT ///rrroro Epoco it o//rr'rod. Irw odd/rrorro/H//C Forrrr 38//AS / lI 3)
DESCR ION OF HE EVENT On June 14, 1989, at 1740, with Unit 1 in Mode 1 at 100% power, a routine weekly emergency diesel system valve status check was performed by a utility non-licensed operator in accordance with Administrative Procedure 1-0010125A. While performing this valve status check, the 1B diesel fuel oil transfer pump discharge valve (EIIS:ISV) was found in the locked closed position. This administratively rendered the 1B diesel generator out of service, per Technical Specification 3.8.1.1.b.3. The valve was unlocked, re-opened, locked opened, and independently verified locked open, within 5 minutes of finding it closed.
Prior to this event, the last time the pump dischaxge valve was operated was at 1015 on June 5, 1989, to place the 1B diesel fuel oil tank on recirculation. This was required for a chemistry sample of the 1B diesel fuel oil tank. Although the valve was re-opened and locked open after the sample was completed, the closing and re-opening of the valve was not recorded in the Valve Deviation Log in accordance with Administrative Procedure 1-0010123.
The valve's locked open position was verified independently on June 7 by a utility non-licensed operator, and on June 13 by a QC Inspector, when the valve status check of Administrative Procedure 1-0020235A was performed.
On June 14, 1989, the valve was found in the locked closed position.
CAUSE OF TH EVENT No fuel oil samples wexe taken and no maintenance was performed on the diesel fuel oil system between 1600 on June 13, 1989 and 1740 on June 14, 1989. Only Operations Department personnel have access to the valve locking device key. Therefore, the most probable root cause of the event was personnel error by a utility non-licensed operator. After investigation, the responsible individual has not been identified. A contributing factor to the event was the failure to record the repositioning of the valve in the Valve Deviation Log.
NAC FOAM SOFA IMSI
U.S. NUCLEAR REGULATORY COMMISSION C Form 3SSA JI LICENSEE NT REPORT (LER) TEXT CONTIN ON APPROVED OMS NO. 3150M(04 EXPIRES: 8/31/88 DOCKET NVMSER (3) PACE (31 I QCILITT NAME (ll LER NVMSER (8)
YEAR ~$
.(N
- SSOUSNTIAL NUMSSR REVISION NUMSSII St. Lucie Unit 1 33 589 0 0 2 0 0 0 3 oF 0 3 o s o o o TEXT /I/ moro tpoco it ror/u/rorL uto tr/I/I(/ooo///RC %%dnrr 385l't/ (171 ANALYSIS OF THE EVENT This event has been deemed reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's Technical Specifications. Since the 1B Diesel was administratively out of service for as long as 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, the surveillance requirements of Technical Specification 3.8.1.1.,
which requires that the operability of the other Diesel be tested within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, should have been performed. However, this surveillance was not done because the operators were not aware of the out of service diesel.
Each emergency diesel is designed for full post-accident load operation for 75 minutes on the day tanks. The fuel oil transfer pump starts and the inlet valve to the day tanks opens at a day tank level of 23 inches. With the fuel oil transfer pump discharge valve shut, the diesel generator would start automatic makeup to the day tank would be prevented, and the day if required. However, tank level would decrease. Approximately 39 minutes later, at a level of 11 inches in the day tank, the low level annunciator would alert the operators of the problem locally and in the control room.
This would leave approximately 36 minutes to dispatch an operator to the area to locate, unlock, and re-open the pump discharge valve.
Since the emergency diesel was available to perform its safety function, the health and safety of the public were not affected by this event.
CORRECTIVE ACTIONS
- 1) Operations personnel re-opened and locked open the valve.
- 2) The Operations Supervisor counselled the operators on the importance of, and the use of, the valve deviation log.
ADDITIONAL NFORMA ON
- 1. COMPONENT IDENTIFICATION This event was not caused by component failure.
2 ~ PREVIOUS SIMILAR EVENTS For a similar event, see LER 5335-82-48, which pertains to the inoperability of the 1A diesel fuel oil pump due to valve mispositioning because of improper restoration from maintenance.
NRC SORM SSSA (WA1
