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| | issue date = 12/07/1987 | | | issue date = 12/07/1987 |
| | title = LER 87-063-00:on 871108,plant Tripped Due to Loss of Main Feedwater.Caused by Mispositioned Condensate Recirculation Valve Due to Personnel Error.Operating Procedure Revised to Include Lessons from Event & Crews briefed.W/871207 Ltr | | | title = LER 87-063-00:on 871108,plant Tripped Due to Loss of Main Feedwater.Caused by Mispositioned Condensate Recirculation Valve Due to Personnel Error.Operating Procedure Revised to Include Lessons from Event & Crews briefed.W/871207 Ltr |
| | author name = SCHWABENBAUER, WATSON R A | | | author name = Schwabenbauer, Watson R |
| | author affiliation = CAROLINA POWER & LIGHT CO. | | | author affiliation = CAROLINA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:,,A~CELERY'J'ED | | {{#Wiki_filter:,,A~ CELERY'J'ED 'DI&'I'RIBUTION DEMONSTRATION SYSTEM 0 ~ |
| 'DI&'I'RIBUTION DEMONSTRATION SYSTEM 0~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8712090208 DOC.DATE: 87/12/07 NOTARIZED:'NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power&Light Co.WATSON,R.A. | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION | | ACCESSION NBR:8712090208 DOC.DATE: 87/12/07 NOTARIZED:'NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power & Light Co. |
| | WATSON,R.A. Carolina Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-063-00:on 871108,plant trip due to loss of main feedwater. | | LER 87-063-00:on 871108,plant feedwater. |
| W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL W SIZE-TITLE: 50.73 Licensees Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400 g RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY,B INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DE ST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PS B NRR/DEST/SGB NRR/DLPQ/QAB NRR/DREP/RAB PRR-S SIB G ILE 02 ORD,J RGN2 FILE 01 EXTERNAL: EG&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 5 5 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DE ST/CEB NRR/DEST/I CS B NRR/DEST/MTB NRR/DEST/RS B NRR/DLPQ/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/I LRB RES DEPY GI RES/DE/EIB FORD BLDG HOY i 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 1 2 2 1 1 l 1 1 1 1 1 1 1 1 1 1 A S j TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45 NRC Form 356 (94)3)LICENSEE EVENT REPORT (LER)U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.31604104 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER l2)PACiE 31 050004001'OF 03 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANT TRIP DUE TO THE LOSS OF MAIN FEEDWATER CAUSED BY A MISPOSITIONED CONDENSATE RECIRCULATION VALVE EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH OAY YEAR YEAR 5PÃ3 EEQUEIITIAL NUMBER N.NIIMSSR MONTH DAY YEAR FACILITY NAMES DOCK ET NUMB E R(S)0 5 0 0 0 11 08 8 7 8 7 6 3 001 20 7 87 0 5 0 0 0 OPERATINO MODE (9)POWER LEVEL y 20.405(~l(1)(I)20.405 (~)(1)(8)20.406(e l(l lliii)20AOS le)(I)(Iv)20.405 (e)l I I (vl X 60 73(s)l2)(iv) 50.73(el(2)(vl 20A06(e)EOM(c)(I)EOM(c)(2)50.73(e)(2)(I)50.73(a)(2)(rg)60.73(e)(2)(riii)(Al 50.73(a l(21(8)50.73(el(2)(iii) 50.73(e)(2)I viiil(8)S0.73(el(2)(al LICENSEE CONTACT FOR THIS LER (12)THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR (): (Check onr or morr of the foilovfingf ill)73.71(h)73.71(cl OTHER fSueclfy In Abstract hrrow coif In Test, NRC Ferns 366AJ NAME R.SCHWABENBAUER | | trip due to loss of main W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL TITLE: 50.73 Licensees Event Report (LER), Incident Rpt, etc. |
| -REGULATORY COMPLIANCE TECHNICIAN AREA CODE TELEPHONE NUMBER COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT l\3)CAUSE SYSTEM COMPONENT MANUFAC.TURER 9'''v c mr EPORTABLE",: CAUSE SYSTEM r COMPONENT MANUFAC.TURER EPORTABLE vtN'O NPRDS.r.5%&SUPPLEMENTAL REPORT EXPECTED (14)EXPECTED SU 8 M I SS ION DATE (15)MONTH DAY YEAR YES flf yer, complrte EXPECTED SVSMISSION OATH NO ABSTRACT fLImft to 1400 spaces, I 6, epproalmetrry fiftern alnrrerpecr typrwrfrten lined l16)The plant was operating in Mode 1, Power Operation, at 22 percent reactor power on November 8, 1987.The plant was in the start-up process following a scheduled outage and was preparing to increase power from 100 MWe to 150 MWe with only the'lA'eedwater train in service.1A Condensate Pump tripped on low discharge pressure which caused 1A Condensate Booster Pump and 1A Main Feedwater Pump to trip, which resulted in a total loss of Main Feedwater. | | W SIZE-NOTES:Application for permit renewal filed. 05000400 g RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 A BUCKLEY,B 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DE ST/ADS 1 0 NRR/DE ST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/I CS B 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PS B 1 1 NRR/DEST/RS B 1 1 NRR/DEST/SGB 1 1 NRR/DLPQ/HFB 1 1 NRR/DLPQ/QAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 PRR- S SIB 1 1 NRR/PMAS/I LRB 1 1 l G ILE 02 1 1 RES DEPY GI 1 1 ORD,J 1 1 RES/DE/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G GROH,M 5 5 FORD BLDG HOY i 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 S |
| The reactor and turbine were then manually tripp'ed at 1625 hours.The Hain Steam Isolation Valves were shut in order to limit pl.ant cool, down and the Auxiliary Feedwater System actuated to restore Steam Generator water levels.All plant systems responded as required.O OR OOR r'I o wO W(A COO co&OCJ C'2 O OR 0<<3: C'a mCZ Nu CO@CO NRC Form 366 ror.nv I The immediate cause of the event was the condensate recirculation valve was in the"OPEN" position rather than"MODULATE" position as required by normal plant operation. | | j TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45 |
| This caused the Condensate Pump and Condensate Booster Pump to be operating at near run~out condition and eventually tripped the Condensate Pump on low discharge pressure.The root cause of the event was personnel error as plant operators were not fully aware of all plant conditions.(i.e., the recirculation valve being in the open position.)
| | |
| Corrective actions are Operating Procedure (OP)-134, Condensate System, has been revised incorporating lessons of this event, and operating shifts were briefed on the causes and consequences of this event, and Post"Turnover briefings are being conducted to ensure understanding of plant conditions for the operating crew.This event is being reported in accordance with IOCFR50.73(ai(2)(ivl as an Engineered Sateguards System Feature and Reactor Protection System Actuation.
| | NRC Form 356 U.S. NUCLEAR REOULATORY COMMISSION (94)3) |
| /(
| | APPROVED OMB NO. 31604104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER l2) PACiE 31 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANT TRIP DUE TO THE LOSS OF MAIN FEEDWATER CAUSED BY A MISPOSITIONED CONDENSATE 050004001'OF 03 RECIRCULATION VALVE EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| NRC Form 348A (083 l LICENSEE EVENT REPORT ILERI TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMS NO.3(50&(04 EXPIRES: 8/31/88 FACILITY NAME III DOCKET NUMSER lll LER NUMSER (Sl IIAOE (3)SHEARON HARRIS~NUCLEAR POWER PLANT UNIT 1 TEXT/I/more 4/reoe 14 err/'rrrrf, voe NIN/orNI A/RC%%drre 38$AS/(171 DESCRIPTION o s o o o4 00 yEAR 58r$4QUENTIAL oI rrevrercN NUM44rr..8 NvM err 87-06 3-0 0 02>>0 3 The plant was operating in Mode 1, Power Operation, at 22 percent reactor power on November 8, 1987.The plant was in the start-up process following a scheduled outage.The Turbine Generator (EIIS:TA)output was to be increased from 100 MWe to 150 MWe at a rate of 3MW/min.Due to the power range at this time, only the'1A'ain Feedwater (EIIS:SJ)train was in service.As the load increase was started, the operator noted that the lA Condensate Booster Pump (CBP)(EIIS:SD)'Controller was in the maximum demand posit'.on.
| | EEQUEIITIAL MONTH OAY YEAR YEAR 5PÃ3 NUMBER N. NIIMSSR MONTH DAY YEAR FACILITYNAMES DOCK ET NUMB E R(S) 0 5 0 0 0 11 08 8 7 8 7 6 3 001 20 7 87 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR (): (Check onr or morr of the foilovfingf ill) |
| 1A Main Feedwater Pump (MFP)(EIIS:SJ) suction pressure and 1A CBP discharge pressure were approximately 430 psig'1A Condensate Pump (CP)(EIIS:SD) discharge pressure was approximately 200 psig.It was noted that the Condensate Recirculation Valve, 1CE-293, was in the"OPEN" position rather than the"MODULATE" (MODU)position as required by normal plant operation.
| | MODE (9) 20A06(e) X 60 73(s)l2)(iv) 73.71(h) |
| In effect, the 1A CBP and the 1A CP were operating at near pump"run out" condition.
| | POWER 20.405( ~ l(1) (I) EOM(c) (I) 50.73(el(2)(vl 73.71(cl LEVEL 20.405 ( ~ ) (1) (8) EOM(c)(2) 50.73(a) (2) (rg) OTHER fSueclfy In Abstract hrrow coif In Test, NRC Ferns 20.406(e l(llliii) 50.73(e) (2)(I) 60.73(e)(2)(riii) (Al 366AJ y 20AOS le) (I ) (Iv) 50.73(a l(21(8) 50.73(e) (2) I viiil(8) 20.405 (e) l I I (vl 50.73(el(2)(iii) S0.73(el(2)(al LICENSEE CONTACT FOR THIS LER (12) |
| The Shift Foreman determined that the safest way to avoid a flow disturbance', which would cause a CP or CBP trip, would be to slowly close the manual recirculation path isolation valve, 1CE-294.An operator was dispatched to do this;however, there was no attempt to halt the turbine power increase process.As turbine power approached 10S MWe, before any possible operator action on the manual recirculation path isolation valve could be made, 1A CP discharge pressure fell below the trip setpoint of 195 psig.After the S second trip delay, the 1A CP tiipped and initiated the trip of the 1A CBP and 1A MFP resulting in a total loss of Main Feedwater.
| | NAME TELEPHONE NUMBER R. SCHWABENBAUER REGULATORY COMPLIANCE TECHNICIAN AREA CODE CAUSE SYSTEM COMPONENT MANUFAC. |
| Since feedwater flow could not be immediately restored, the reactor and the turbine were manually tripped at 1625 hours.The Main Steam Isolation Valves (EIIS:SB)were shut in order to limit plant cooldown and Steam Generator (EIIS:TB)water levels were restored with the automatic actuation of the Auxiliary Feedwater System (AFW)(EIIS:BA).
| | TURER EPORTABLE |
| All plant systems responded as required and the plant was stabilized in Mode 3, Hot Standby.CAUSE: The immediate cause of the event was that Condensate Recirculation Valve 1CE-293, was in the open position rather than the moduLate position as required for normal plant operation.
| | '''v COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 9 c mr r |
| This resulted in the lA CP and 1A CBP to be operating at near run out condition and eventually tripping 1A CP on Low discharge pressure.The root cause of the event was personnel error as plant operators were not fully aware of all pl.ant conditions (i.e., the recirculation vaLve being in the open position).
| | CAUSE SYSTEM COMPONENT l\3) |
| Shift turnover notes did indicate that valve 1CE-293 was N/IC FD/IM 344*(043(e U.S.OPO:108~824 538/455 NRC Potm 264A (94L)I LlCENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.2150&104 EXPIRES: 8/21/88 PACILI'TY NAME ill SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 TEXT//I IINrp Spree/I Irovked, vrr 4/4/SAI/NRC Pr/m 6//$4'4/117)CAUSE: (continued)
| | MANUFAC. |
| OOCKET NUMBER 12)o s o o o4 00 YEAR 8.7-0 3 LER NUMBER 16)SEOVSNTIAL R>5 NVMSSII II 4 V IS IO N NVM SA PAGE IS)0 0 3 oF0 3 in an abnormal condition.
| | TURER EPORTABLE NPRDS vtN'O |
| The position resulted from secondary plant chemistry operations conducted earlier in the week.The plant had been in a long path recirculation mode for the purpose of establishing secondary plant chemistry control prior to plant start-up.In this mode, Operation Procedure (OP)-134, Condensate System, permits placing valve 1CE-293, in the"OPEN" position in order to increase recirculation flow.The procedure did not specifically address returning the valve switch to the"MODULATE" position, which is the assumed position for normal pl.ant operation, when returning to the normal or short path recirculation moce.ANALYSIS: This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an Engineered Safeguards System Feature and Reactor Protection System Actuation. | | .r . |
| There were no safety consequences as a result of this event;although operation of a safety system was challenged (AFW).The AFW system started as required upon loss of Main Feedwater to maintain vater levels in the Steam'enerators. | | SUPPLEMENTAL REPORT EXPECTED (14) |
| | EXPECTED MONTH 5%& DAY YEAR SU 8 M I SS ION YES flfyer, complrte EXPECTED SVSMISSION OATH NO DATE (15) |
| | ABSTRACT fLImft to 1400 spaces, I 6, epproalmetrry fiftern alnrrerpecr typrwrfrten lined l16) |
| | The plant was operating in Mode 1, Power Operation, at 22 percent reactor power on November 8, 1987. The plant was in the start-up process following a scheduled outage and was preparing to increase power from 100 MWe to 150 MWe with only the 'lA'eedwater train in service. 1A Condensate Pump tripped on low discharge pressure which caused 1A Condensate Booster Pump and 1A Main Feedwater Pump to trip, which resulted in a total loss of Main Feedwater. The reactor and turbine were then manually tripp'ed at 1625 hours. The Hain Steam Isolation Valves were shut in order to limit pl.ant cool, down and the Auxiliary Feedwater System actuated to restore Steam Generator water levels. All plant systems responded as required. |
| | The immediate cause of the event was the condensate recirculation valve was in the "OPEN" position rather than "MODULATE" position as required by normal O plant operation. This caused the Condensate Pump and Condensate Booster Pump OR to be operating at near run out condition and eventually tripped the ~ |
| | OOR Condensate Pump on low discharge pressure. The root cause of the event was r'I o wO personnel error as plant operators were not fully aware of all plant W(A COO conditions. (i.e., the recirculation valve being in the open position.) |
| | co& Corrective actions are Operating Procedure (OP)-134, Condensate System, has OCJ been revised incorporating lessons of this event, and operating shifts were C'2 O OR briefed on the causes and consequences of this event, and Post"Turnover 0 <<3: |
| | briefings are being conducted to ensure understanding of plant conditions for C'a mCZ the operating crew. |
| | Nu CO@ CO This event is being reported in accordance with IOCFR50.73(ai(2)(ivl as an Engineered Sateguards System Feature and Reactor Protection System Actuation. /( |
| | NRC Form 366 ror.nv I |
| | |
| | NRC Form 348A U.S. NUCLEAR REOULATORY COMMISSION (083 l LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMS NO. 3(50&(04 EXPIRES: 8/31/88 FACILITYNAME III DOCKET NUMSER lll LER NUMSER (Sl IIAOE (3) yEAR 58r $ 4QUENTIAL oI rrevrercN NUM44rr ..8 NvM err SHEARON HARRIS NUCLEAR POWER PLANT ~ |
| | UNIT 1 TEXT /I/more 4/reoe 14 err/'rrrrf, voe NIN/orNIA/RC %%drre 38$ AS/ (171 o s o o o4 00 87 06 3 0 0 02>> 0 3 DESCRIPTION The plant was operating in Mode 1, Power Operation, at 22 percent reactor power on November 8, 1987. The plant was in the start-up process following a scheduled outage. The Turbine Generator (EIIS:TA) output was to be increased from 100 MWe to 150 MWe at a rate of 3MW/min. Due to the power range at this time, only the '1A'ain Feedwater (EIIS:SJ) train was in service. |
| | As the load increase was started, the operator noted that the lA Condensate Booster Pump (CBP)(EIIS:SD)'Controller was in the maximum demand posit'.on. 1A Main Feedwater Pump (MFP)(EIIS:SJ) suction pressure and 1A CBP discharge pressure were approximately 430 psig'1A Condensate Pump (CP)(EIIS:SD) discharge pressure was approximately 200 psig. It was noted that the Condensate Recirculation Valve, 1CE-293, was in the "OPEN" position rather than the "MODULATE" (MODU) position as required by normal plant operation. In effect, the 1A CBP and the 1A CP were operating at near pump "run out" condition. The Shift Foreman determined that the safest way to avoid a flow disturbance', which would cause a CP or CBP trip, would be to slowly close the manual recirculation path isolation valve, 1CE-294. An operator was dispatched to do this; however, there was no attempt to halt the turbine power increase process. |
| | As turbine power approached 10S MWe, before any possible operator action on the manual recirculation path isolation valve could be made, 1A CP discharge pressure fell below the trip setpoint of 195 psig. After the S second trip delay, the 1A CP tiipped and initiated the trip of the 1A CBP and 1A MFP resulting in a total loss of Main Feedwater. Since feedwater flow could not be immediately restored, the reactor and the turbine were manually tripped at 1625 hours. The Main Steam Isolation Valves (EIIS:SB) were shut in order to limit plant cooldown and Steam Generator (EIIS:TB) water levels were restored with the automatic actuation of the Auxiliary Feedwater System (AFW) |
| | (EIIS:BA). All plant systems responded as required and the plant was stabilized in Mode 3, Hot Standby. |
| | CAUSE: |
| | The immediate cause of the event was that Condensate Recirculation Valve 1CE-293, was in the open position rather than the moduLate position as required for normal plant operation. This resulted in the lA CP and 1A CBP to be operating at near run out condition and eventually tripping 1A CP on Low discharge pressure. |
| | The root cause of the event was personnel error as plant operators were not fully aware of all pl.ant conditions (i.e., the recirculation vaLve being in the open position). Shift turnover notes did indicate that valve 1CE-293 was N/IC FD/IM 344* |
| | (043( e U.S.OPO:108~824 538/455 |
| | |
| | NRC Potm 264A U.S. NUCLEAR REGULATORY COMMISSION (94L) I LlCENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 2150&104 EXPIRES: 8/21/88 PACILI'TY NAME ill OOCKET NUMBER 12) LER NUMBER 16) PAGE IS) |
| | YEAR SEOVSNTIAL R>5 II4 V IS IO N SHEARON HARRIS NUCLEAR POWER PLANT NVMSSII NVM SA UNIT 1 o s o o o4 00 8. 70 3 0 0 3 oF0 3 TEXT //I IINrp Spree /I Irovked, vrr 4/4/SAI/NRC Pr/m 6//$ 4'4/ 117) |
| | CAUSE: (continued) in an abnormal condition. The position resulted from secondary plant chemistry operations conducted earlier in the week. The plant had been in a long path recirculation mode for the purpose of establishing secondary plant chemistry control prior to plant start-up. In this mode, Operation Procedure (OP)-134, Condensate System, permits placing valve 1CE-293, in the "OPEN" position in order to increase recirculation flow. The procedure did not specifically address returning the valve switch to the "MODULATE" position, which is the assumed position for normal pl.ant operation, when returning to the normal or short path recirculation moce. |
| | ANALYSIS: |
| | This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an Engineered Safeguards System Feature and Reactor Protection System Actuation. |
| | There were no safety consequences as a result of this event; although operation of a safety system was challenged (AFW). The AFW system started as required upon loss of Main Feedwater to maintain vater levels in the Steam |
| | 'enerators. |
| Other events reported where the loss of Main Feedwater resulted, in a plant trip vere reported in LERs.'7-005-00, 87-008-00, 87-013-00, 87-017-00, 87-018"00, 87-019-00, 87-024-00, 87-025-00, 87-028-00, 87"031-00, 87-037-00. | | Other events reported where the loss of Main Feedwater resulted, in a plant trip vere reported in LERs.'7-005-00, 87-008-00, 87-013-00, 87-017-00, 87-018"00, 87-019-00, 87-024-00, 87-025-00, 87-028-00, 87"031-00, 87-037-00. |
| CORRECTIVE ACTIONS/ACTIONS TO PREVENT RECURRENCE: | | CORRECTIVE ACTIONS/ACTIONS TO PREVENT RECURRENCE: |
| 1.The Shift Turnover process has been enhanced.Previously, the turnover process included a briefing by the off going Shift Foreman and a one-on-one turnover of each position.Plant direction has been issued through a Night Order to require a Post-Turnover briefing by the Balance of Plant (BOP), Reactor Operator (RO), Senior Control.Operator (SCO), each Auxiliary Operator (AO), and the Shift Foreman (SF)to ensure the operating crew has a ful.l understanding of plant conditions. | | : 1. The Shift Turnover process has been enhanced. Previously, the turnover process included a briefing by the off going Shift Foreman and a one-on-one turnover of each position. Plant direction has been issued through a Night Order to require a Post-Turnover briefing by the Balance of Plant (BOP), Reactor Operator (RO), Senior Control. Operator (SCO), |
| Operations Management Manual (OMM)-001, Operations-Conduct of Operations, is being revised to incorporate this action.2.Operating Procedure (OP)-134, Condensate System, has been revised incorporating the lessons of this event.3.Following the event operating shifts were briefed on the causes and consequences of this event.I NRC SORM SSSA 19421*U.S.GPO:1986.0 624 558/455 Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 DEC 0 7~98'ile.Number'SHF/10-13510C Letter Number.'HO-870563 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 87-063-00 Gentlemen'. | | each Auxiliary Operator (AO), and the Shift Foreman (SF) to ensure the operating crew has a ful.l understanding of plant conditions. |
| In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. | | Operations Management Manual (OMM)-001, Operations-Conduct of Operations, is being revised to incorporate this action. |
| This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours, RAW'lkd Enclosure SF/W~~>R.A.Watson Vice President Harris Nuclear Project cc.'Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr: G.Maxwell (NRC-SHNPP)MEM/LER-87-063/1/OS1}} | | : 2. Operating Procedure (OP)-134, Condensate System, has been revised incorporating the lessons of this event. |
| | : 3. Following the event operating shifts were briefed on the causes and consequences of this Ievent. |
| | NRC SORM SSSA 19421 |
| | *U.S.GPO:1986.0 624 558/455 |
| | |
| | Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 DEC 0 7 |
| | ~98'ile |
| | .Number'SHF/10-13510C Letter Number.'HO-870563 (0) |
| | U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-063-00 Gentlemen'. |
| | In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983. |
| | Very truly yours, SF/W~~> |
| | R. A. Watson Vice President Harris Nuclear Project RAW'lkd Enclosure cc.'Dr. J. Nelson Grace (NRC RII) |
| | Mr. B. Buckley (NRR) |
| | Mr: G. Maxwell (NRC SHNPP) |
| | MEM/LER-87-063/1/OS1}} |
|
|---|
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LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A9151999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18017A8621999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18017A8361999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr
ML18016B0151999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9851999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr
ML18017A8981999-05-12012 May 1999
Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines.
ML18016A9581999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8941999-04-0505 April 1999
Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760
ML18016A9101999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr
ML18016A8661999-03-31031 March 1999
Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept.
ML18017A8931999-02-28028 February 1999
Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A8551999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8531999-02-18018 February 1999
Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18022B0631999-02-0404 February 1999
Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings
ML20202J1161999-02-0101 February 1999
SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program
ML18016A8041999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7801998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr
ML18016A7671998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr
ML18016A9731998-11-28028 November 1998
Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A8351998-11-28028 November 1998
ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1.
ML18016A7411998-11-25025 November 1998
Rev 1 to Shnpp Cycle 9 Colr.
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A7071998-11-0303 November 1998
Rev 0 to Harris Unit 1 Cycle 9 Colr.
ML18016A7201998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr
ML20154F8701998-10-0606 October 1998
Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves
ML18016A6201998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr
ML18016A5971998-09-21021 September 1998
Rev 1 to Harris Unit 1 Cycle 8 Colr.
ML18016A5881998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr
ML18016A5071998-07-31031 July 1998
Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr
ML18016A9431998-07-0707 July 1998
Rev 1 to QAP Manual.
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A9371998-06-30030 June 1998
Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp.
ML18016A4861998-06-30030 June 1998
Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18016A4521998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr
ML18016A7711998-05-26026 May 1998
Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
1999-09-30
[Table view] |
Text
,,A~ CELERY'J'ED 'DI&'I'RIBUTION DEMONSTRATION SYSTEM 0 ~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8712090208 DOC.DATE: 87/12/07 NOTARIZED:'NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power & Light Co.
WATSON,R.A. Carolina Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 87-063-00:on 871108,plant feedwater.
trip due to loss of main W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL TITLE: 50.73 Licensees Event Report (LER), Incident Rpt, etc.
W SIZE-NOTES:Application for permit renewal filed. 05000400 g RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 A BUCKLEY,B 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DE ST/ADS 1 0 NRR/DE ST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/I CS B 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PS B 1 1 NRR/DEST/RS B 1 1 NRR/DEST/SGB 1 1 NRR/DLPQ/HFB 1 1 NRR/DLPQ/QAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 PRR- S SIB 1 1 NRR/PMAS/I LRB 1 1 l G ILE 02 1 1 RES DEPY GI 1 1 ORD,J 1 1 RES/DE/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G GROH,M 5 5 FORD BLDG HOY i 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 S
j TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45
NRC Form 356 U.S. NUCLEAR REOULATORY COMMISSION (94)3)
APPROVED OMB NO. 31604104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER l2) PACiE 31 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANT TRIP DUE TO THE LOSS OF MAIN FEEDWATER CAUSED BY A MISPOSITIONED CONDENSATE 050004001'OF 03 RECIRCULATION VALVE EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
EEQUEIITIAL MONTH OAY YEAR YEAR 5PÃ3 NUMBER N. NIIMSSR MONTH DAY YEAR FACILITYNAMES DOCK ET NUMB E R(S) 0 5 0 0 0 11 08 8 7 8 7 6 3 001 20 7 87 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR (): (Check onr or morr of the foilovfingf ill)
MODE (9) 20A06(e) X 60 73(s)l2)(iv) 73.71(h)
POWER 20.405( ~ l(1) (I) EOM(c) (I) 50.73(el(2)(vl 73.71(cl LEVEL 20.405 ( ~ ) (1) (8) EOM(c)(2) 50.73(a) (2) (rg) OTHER fSueclfy In Abstract hrrow coif In Test, NRC Ferns 20.406(e l(llliii) 50.73(e) (2)(I) 60.73(e)(2)(riii) (Al 366AJ y 20AOS le) (I ) (Iv) 50.73(a l(21(8) 50.73(e) (2) I viiil(8) 20.405 (e) l I I (vl 50.73(el(2)(iii) S0.73(el(2)(al LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER R. SCHWABENBAUER REGULATORY COMPLIANCE TECHNICIAN AREA CODE CAUSE SYSTEM COMPONENT MANUFAC.
TURER EPORTABLE
v COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 9 c mr r
CAUSE SYSTEM COMPONENT l\3)
MANUFAC.
TURER EPORTABLE NPRDS vtN'O
.r .
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH 5%& DAY YEAR SU 8 M I SS ION YES flfyer, complrte EXPECTED SVSMISSION OATH NO DATE (15)
ABSTRACT fLImft to 1400 spaces, I 6, epproalmetrry fiftern alnrrerpecr typrwrfrten lined l16)
The plant was operating in Mode 1, Power Operation, at 22 percent reactor power on November 8, 1987. The plant was in the start-up process following a scheduled outage and was preparing to increase power from 100 MWe to 150 MWe with only the 'lA'eedwater train in service. 1A Condensate Pump tripped on low discharge pressure which caused 1A Condensate Booster Pump and 1A Main Feedwater Pump to trip, which resulted in a total loss of Main Feedwater. The reactor and turbine were then manually tripp'ed at 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br />. The Hain Steam Isolation Valves were shut in order to limit pl.ant cool, down and the Auxiliary Feedwater System actuated to restore Steam Generator water levels. All plant systems responded as required.
The immediate cause of the event was the condensate recirculation valve was in the "OPEN" position rather than "MODULATE" position as required by normal O plant operation. This caused the Condensate Pump and Condensate Booster Pump OR to be operating at near run out condition and eventually tripped the ~
OOR Condensate Pump on low discharge pressure. The root cause of the event was r'I o wO personnel error as plant operators were not fully aware of all plant W(A COO conditions. (i.e., the recirculation valve being in the open position.)
co& Corrective actions are Operating Procedure (OP)-134, Condensate System, has OCJ been revised incorporating lessons of this event, and operating shifts were C'2 O OR briefed on the causes and consequences of this event, and Post"Turnover 0 <<3:
briefings are being conducted to ensure understanding of plant conditions for C'a mCZ the operating crew.
Nu CO@ CO This event is being reported in accordance with IOCFR50.73(ai(2)(ivl as an Engineered Sateguards System Feature and Reactor Protection System Actuation. /(
NRC Form 366 ror.nv I
NRC Form 348A U.S. NUCLEAR REOULATORY COMMISSION (083 l LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMS NO. 3(50&(04 EXPIRES: 8/31/88 FACILITYNAME III DOCKET NUMSER lll LER NUMSER (Sl IIAOE (3) yEAR 58r $ 4QUENTIAL oI rrevrercN NUM44rr ..8 NvM err SHEARON HARRIS NUCLEAR POWER PLANT ~
UNIT 1 TEXT /I/more 4/reoe 14 err/'rrrrf, voe NIN/orNIA/RC %%drre 38$ AS/ (171 o s o o o4 00 87 06 3 0 0 02>> 0 3 DESCRIPTION The plant was operating in Mode 1, Power Operation, at 22 percent reactor power on November 8, 1987. The plant was in the start-up process following a scheduled outage. The Turbine Generator (EIIS:TA) output was to be increased from 100 MWe to 150 MWe at a rate of 3MW/min. Due to the power range at this time, only the '1A'ain Feedwater (EIIS:SJ) train was in service.
As the load increase was started, the operator noted that the lA Condensate Booster Pump (CBP)(EIIS:SD)'Controller was in the maximum demand posit'.on. 1A Main Feedwater Pump (MFP)(EIIS:SJ) suction pressure and 1A CBP discharge pressure were approximately 430 psig'1A Condensate Pump (CP)(EIIS:SD) discharge pressure was approximately 200 psig. It was noted that the Condensate Recirculation Valve, 1CE-293, was in the "OPEN" position rather than the "MODULATE" (MODU) position as required by normal plant operation. In effect, the 1A CBP and the 1A CP were operating at near pump "run out" condition. The Shift Foreman determined that the safest way to avoid a flow disturbance', which would cause a CP or CBP trip, would be to slowly close the manual recirculation path isolation valve, 1CE-294. An operator was dispatched to do this; however, there was no attempt to halt the turbine power increase process.
As turbine power approached 10S MWe, before any possible operator action on the manual recirculation path isolation valve could be made, 1A CP discharge pressure fell below the trip setpoint of 195 psig. After the S second trip delay, the 1A CP tiipped and initiated the trip of the 1A CBP and 1A MFP resulting in a total loss of Main Feedwater. Since feedwater flow could not be immediately restored, the reactor and the turbine were manually tripped at 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br />. The Main Steam Isolation Valves (EIIS:SB) were shut in order to limit plant cooldown and Steam Generator (EIIS:TB) water levels were restored with the automatic actuation of the Auxiliary Feedwater System (AFW)
(EIIS:BA). All plant systems responded as required and the plant was stabilized in Mode 3, Hot Standby.
CAUSE:
The immediate cause of the event was that Condensate Recirculation Valve 1CE-293, was in the open position rather than the moduLate position as required for normal plant operation. This resulted in the lA CP and 1A CBP to be operating at near run out condition and eventually tripping 1A CP on Low discharge pressure.
The root cause of the event was personnel error as plant operators were not fully aware of all pl.ant conditions (i.e., the recirculation vaLve being in the open position). Shift turnover notes did indicate that valve 1CE-293 was N/IC FD/IM 344*
(043( e U.S.OPO:108~824 538/455
NRC Potm 264A U.S. NUCLEAR REGULATORY COMMISSION (94L) I LlCENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 2150&104 EXPIRES: 8/21/88 PACILI'TY NAME ill OOCKET NUMBER 12) LER NUMBER 16) PAGE IS)
YEAR SEOVSNTIAL R>5 II4 V IS IO N SHEARON HARRIS NUCLEAR POWER PLANT NVMSSII NVM SA UNIT 1 o s o o o4 00 8. 70 3 0 0 3 oF0 3 TEXT //I IINrp Spree /I Irovked, vrr 4/4/SAI/NRC Pr/m 6//$ 4'4/ 117)
CAUSE: (continued) in an abnormal condition. The position resulted from secondary plant chemistry operations conducted earlier in the week. The plant had been in a long path recirculation mode for the purpose of establishing secondary plant chemistry control prior to plant start-up. In this mode, Operation Procedure (OP)-134, Condensate System, permits placing valve 1CE-293, in the "OPEN" position in order to increase recirculation flow. The procedure did not specifically address returning the valve switch to the "MODULATE" position, which is the assumed position for normal pl.ant operation, when returning to the normal or short path recirculation moce.
ANALYSIS:
This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an Engineered Safeguards System Feature and Reactor Protection System Actuation.
There were no safety consequences as a result of this event; although operation of a safety system was challenged (AFW). The AFW system started as required upon loss of Main Feedwater to maintain vater levels in the Steam
'enerators.
Other events reported where the loss of Main Feedwater resulted, in a plant trip vere reported in LERs.'7-005-00, 87-008-00, 87-013-00, 87-017-00,87-018"00, 87-019-00, 87-024-00, 87-025-00, 87-028-00, 87"031-00, 87-037-00.
CORRECTIVE ACTIONS/ACTIONS TO PREVENT RECURRENCE:
- 1. The Shift Turnover process has been enhanced. Previously, the turnover process included a briefing by the off going Shift Foreman and a one-on-one turnover of each position. Plant direction has been issued through a Night Order to require a Post-Turnover briefing by the Balance of Plant (BOP), Reactor Operator (RO), Senior Control. Operator (SCO),
each Auxiliary Operator (AO), and the Shift Foreman (SF) to ensure the operating crew has a ful.l understanding of plant conditions.
Operations Management Manual (OMM)-001, Operations-Conduct of Operations, is being revised to incorporate this action.
- 2. Operating Procedure (OP)-134, Condensate System, has been revised incorporating the lessons of this event.
- 3. Following the event operating shifts were briefed on the causes and consequences of this Ievent.
NRC SORM SSSA 19421
- U.S.GPO:1986.0 624 558/455
Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 DEC 0 7
~98'ile
.Number'SHF/10-13510C Letter Number.'HO-870563 (0)
U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-063-00 Gentlemen'.
In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.
Very truly yours, SF/W~~>
R. A. Watson Vice President Harris Nuclear Project RAW'lkd Enclosure cc.'Dr. J. Nelson Grace (NRC RII)
Mr. B. Buckley (NRR)
Mr: G. Maxwell (NRC SHNPP)
MEM/LER-87-063/1/OS1
