ML17261A753

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LER 87-006-00:on 871130,standby Auxiliary Feedwater Pump 1D Deemed Inoperable Beyond Tech Spec Limit.Caused by Cooling Unit 1B Ac Electrical Breaker Found in Off Position Due to Unaware Operator.Breaker Turned to on position.W/871230 Ltr
ML17261A753
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/30/1987
From: Backus W, Kober R
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-006, LER-87-6, NUDOCS 8801060249
Download: ML17261A753 (9)


Text

REGULA'iuRY INFORMATION DISTRIBUTIOl SYSTEM (RIDS)

ACCESSION NBR: 88010b0249 DQC. DATE: 87/12/30 NOTARIZED: NQ DOCKET FACIL: 50-244 Robert Emmet Ginna Nuclear Plantz Unit 1I Rochester G AUTH. NAME AUTHOR AFFILIATION BACKUST W. H. Rochester Qas 5 Electric Corp.

KOBERz R. W. Rochester Gas 8. Electric Corp. 05000244='UBJECT:

REC IP. NAME 'ECIPIENT AFFILIATION LER 87-006-00: on 871130z standby aux iliarg Feedwater pump 1D inoperable For longer than tech specs allow. Caused bg cooling Unit 1B ac electrical breaker in oFF position.

BT eaker locked on 5 new modules to be designed. W/871230 ltr.

DISTRIBUTION CODE: IESSD COPIES RECEIVED: LTR j ENCL TITLE: 50. 73 Licensee Event Report. (LER)z Incident Rpt> etc.

Q SIZE:

NOTES: License Exp date in accordance with 10CFR2z 2. 109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 PDi-3 PD 1 1 STAHLEI C 1 1 INTERNAL: ACRS MI CHELSON 1 1 ACRS MQELLER 2 2 AEOD/DOA 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/*DS 1 0 NRR/DEBT/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ I CSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SQB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DQEA/E*B 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB NRRQDR-I S IB 1 1 NRR/PMAS/ ILRB 1 1 02 1 1 RES DEPY QI 1 1 RES TELFORD> J 1 RES/DE/EIB 1 RGN1 FILE 01 1 1 EXTERNAL: EG9rG GROHI M 5 5 FORD BLDG HOYLE A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRISI J 1 1 NSIC MAYSI G 1 1 TOT*L NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45

IALIRCMAR EEEVLATONY ClN~I NEIGH AIIYIOVEO OIN IOL $ 1~ Oe tteillEL UCENSEE EVENT REPORT {LHI)

III DOCKET INIEN OI FACILITYad%

R.E. Ginna Nuclear Power Inadvertent P~

Attendent Cooling Unit Inoperability Due 0 4 0 To Open Breaker Causes 1D 0 0 0 7 Standb Auxiliar Feedwater Pum To Be Deemed Ino erable Be ond The Tech S ec Limit W NQNEN Itl ASCNf OATE lll OTHEN eACILITIEE INVOLVED IEI tee IA4 OAY YEAII eACI UTY HAM% Doc@ET Nvietttltl IIONTH DAY YEAN YtAII tt vwe 1 0 4 0 0 0 1 130 878 7 0 0 6 0 0 1 2 30 87 lt ct1 f (ceeee lll 0 4 0 0 0 THN troat N aNNTTEO eVNEVANT TO THE AtovIENIENTE <<Nt eee et tttHY ee eie tseeeeet

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taeNWIIIINI NPSWOXE SMHIAlItel NPSNNIIN IIIIei 'NPSsHS INI LICNWEE CONTACT ION TH% LE% lltl AllEA CONE W.H. Backus, Technical Assistant To The Operations Manager 315 524 -44 46

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~November EXffCTtD EVEeettttOH DATEJ IA, ~ettetety tttNee ~ eeettteee tAteH 11N 30, 1987 at 1330 EST with the unit at 1004 Reactor

.Power the 1D Standby Auxiliary Feedwater Pump (SAFWP) was deemed IVEIIIEEHHI DATE lltl to have been inoperable for longer than the Technical Specifica-tions allowed. This was due to the Attendant SAFWP room cooling unit 1B AC electrical breaker being found in the off position.

Immediate corrective action taken was to return the affected breaker to the- on position.

The intermediate cause of the event was indeterminate as no reason or action was found for the breaker to be in the off.

position. The root cause of the event was determined to be the level of awareness concerning operator and maintenance actions as they relate to the relatively new operability .Technical Specifica-tions'.

Corrective action to prevent recurrence was to lock the affected breaker in the on position and to request training to design and implement modules focusing on the relatively new operability Technical Specifications.

88010b0249 871230 PDR ADOCK 05000244 8

V.S. NUCLEAR REOVLATORY COMMISSION I~

NRC PenA SSEA I

LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVEO OMS NO. SI SOWIOl EXPIRES- 8ISI ITS OOCKET NUMRER ISI LER NVMSER IISI ~ AOE IS>

PACILITY NANt 111

)~', 55OVtNTIAL 5 V It IO II g I +NUM YEAR ~ IVM l1 TA 006 TEXT IN MNP MPPP Il ~

R.E. Ginna Nuclear Power Plant IMP OANOnel HJIC lOIIII~IIIITI 0 5 0 0 0 2 4 8 7 00 02 OF 0 7 PRE-EVENT PLANT CONDITIONS The unit was at 100% Reactor Power and the Instrument and Control (I&C) and Electrical Departments were trouble shooting, per Maintenance Work Request 87-6070, The Standby Auxiliary Feedwater Pump (SAFWP) Room Cooling unit 1B for a problem with an inoperable green light (OFF) bulb.

The bulb had been replaced but there was still no indica-tion.

DESCRIPTION OF EVENT A. EVENT:

On November 30, 1987 at 1330 EST, the electrician trouble shooting the SAFWP Room 1B Cooling Unit green light (OFF) indication problem found the AC electrical breaker for the above cooling unit in the OFF posi-tion. The SAFWP Room 1B Cooling Unit AC Electrical Breaker in the OFF position rendered the 1B Cooling unit inoperable and based upon the Technic;:cl Specifi-cation (TS) definition of operable - operability, also rendered the 1D SAFWP inoperable as this was the pump that the cooling unit served.

A review of plant records indicates that the SAFWP Room Cooling Unit 1B was verified operable per operating procedure S-30.5 on November 18, 1987.

Because the date tha- the 1B Cooling Unit AC Electrical Breaker was inadvertently turned off could not be established, Rochester Gas and Electric Corporation (RG6E) conservatively assumed that the last date that it was confirmed ON. TS 3.4.1(e) it was off since requires two Standby Auxiliary Feedwater Pumps arid associated flow paths operable when Reactor Coolant System (RCS) temperature is at or above 350 F.

NRC PORM SSSA (94ll

U,S. NUCLEAR REOULATORY COMMISSION NRC eww 888A IS<<5 I LICENSEE EVENT REPORT {LER) TEXT CONTINUATION AOOROVEO OM8 NO. 5150&IOI EXOIRES: 8/51/85 SACILITY NAME III LER NUMSER (SI ~ AOE IS)

SEOVCNTIAL P:; OIVI5ION NVM IO NVM fe R.E. Ginna Nuclear Power Plant 0 5 0 0 0 2 4 4 8 7 006 0 0 03oF07 TEXT /Swore <<moo << teyslerL eoe o<<<<a<<pro//YRC /orw ~'o/ I ITI TS 3. 4. 2 (d) allows one Standby Auxiliary Feedwater Pump or flow path to be inoperable as long as the inoperable pump or flow path is restored to operable status within 7 'days or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at an RCS temperature below 350 F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. RG&E has conservatively assumed that the SAFWP Room Cooling Unit 1B was inoperable from November 18, 1987 .(date that it was last verified operable), to November 30, 1987 (date that it was returned to operable status), a total of 12 days. Due to the operable - operability TS the 1D SAFWP was also deemed inoperable for the 12 days thus not satisfying TS 3 .4 .2(d) .

The SAFWP Room Cooling Unit 1B AC Electrical Breaker was turned ON, immediately after the discovery that it was OFF, on November 30, 1987.

B. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

The SAFWP Room Cooling Unit 1B was inoperable due to its AC Electrical Breaker being .in the OFF position.

C. DATES AND APPROXIMATE TIMES FOR MAJOR OCCURRENCES:

o November 18, 1987, 2004 EST: assumed event date and time o November 30, 1987, 1330 EST: discovery date and time o November 30, 1987, 1330 EST: SAFWP Room Cooling Unit 1B AC Electrical Breaker returned to the ON position D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

o The Control Power for the SAFWP Room Cooling Unit was also rendered inoperable due to the AC electrical Breaker being in the OFF position.

This affected both the remote control of the breaker and the remote indication (i.e. Red and

'Green indicating lights).

NRC OORM 888*

I84$ l

NRC ferrrr ESSA U.S. NUCLEAR REOULATORY COMMISSION l045I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS PrO., 3150WI04 "1 EXPIRES'ISI/$ 5 fACILITYNAME III DOCKET NUMSER l1) LER NUMSER 141 ~ AOE IS) 55OVENTrAL 1LYISION

~ rVM 51 !rVM 51 0 S 0 0 0 0 6 0 0 oa'F 07 TEXt AYrrrfrfMfrrf4 PffrrPPC INP oAWanV HRC %%drrrr ~'PI (ITI E. METHOD OF DISCOVERY:

The SAFWP Room Cooling Unit 1B AC Electrical Breaker was discovered in the OFF position by an electrician during trouble shooting of the above units green light OFF indication problem.

F. OPERATOR ACTION:

The electrician that found the breaker in the OFF position notified the Shift Supervisor of this fact.

The Shift Supervisor instructed the electrician to turn the breaker on and check the Room Cooling Unit for operability. With the SAFWP breaker on, the Cooling Unit tested satisfactorily.

G. SAFETY SYSTEM RESPONSES:

None.

IIZ. CAUSE OF A. IMMEDIATE CAUSE:

SAFWP Room 1B Cooling Unit AC Breaker in OFF position rendering the 1D SAFWP inadvertently inoperable per TS for more than 7 days.

B. INTERMEDIATE CAUSE:

Indeterminate because. no reason or action was found for the SAFWP Room 1B Cooling Unit AC Breaker to be in the OFF position.

C. ROOT CAUSE:

The root cause of the event was determined to be the level of awareness concerning operator and maintenance actions as they relate to the relatively new operability Technical Specifications.

NRC PORM ESSA IS 43 I

U.S. IIVCLEAIIIIEOULATOIIYCOMMI55IOII MAC SWM EEEA 10451 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION ASSAovEooME!Io,3150MI05

! EXSIIIES 8/SI!55 SACILITY IIAME 111 OOCIIET IIUMIEIIIEI LEII IIVMSE!1 III ~ AOE IEI y~

55OVENTIAL fHUM CVISION 5A NIZAM 5A R.E. Ginna Nuclear Power Plant 0 5 0 0 0 244 87 006 000 5 0 7

~ IroffMSff H toy/e4 ffe oASArW HHC form ~'5l 1171 IV. ANALYS S OF NT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B) which requires reporting of, "any operation prohibited by the Plant's Technical Specifications" in that the 1D SAFWP was deemed inoperable per TS operable - operability definition for longer than the allowed time limit.

An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:

There were no operational or safety consequences or implications attributed to the SAFWP Room 1B Cooling Unit inoperability because:

0 The 1D SAFWP, itself, was fully operable and capable of performing its intended function throughout the event.

The 1C SAFWP was fully operable and capable of performing its intended function throughout the event even though it was deemed inoperable twice for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 50 minutes per A-52.4 (Control of Limiting Conditions for Operating Equip-ment) for calibration of fl'ow and pressure instrumenta-tion. During these times the operational personnel were not aware of the inoperability of the SAFWP Room 1B Cooling Unit.

0 The SAFWP Room 1A Cooling Unit was operable and capable of'erforming its intended function.

All three main Auxiliary Feedwater Pumps were fully operable and capable of performing their intended function.

0 A security evaluation of the event revealed no obvious malicious intent to sabotage TS related equipment.

MIIC SOIIM 555A 10451

U.S, NUCLEAR 4ECULATOR Y COMMISSION NRC fern ESSA 10031 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AtfROYEO OMS NO. 3150WI04 EXfIRES'ISI/8$

fACILITYNAME Ill OOCRET NUMSER liI LER NUMSER I ~ I ~ AOE 1$ 1

$ C 0 U S N YI A \. ~vf ASVOION HUM 4 NUM fa R.E. Ginna Nuclear Power Plant TEXT O'IINff~ N teevteC fffo4SAeal HRC %%drm ~'fl(1Tl 0500024487 0 0 6 6oFO 7 V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

o The SAFWP Room Cooling Unit 1B AC Electrical Breaker was turned ON and the Cooling Unit satisfactorily tested.

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

0 With the breakers in the ON position, locks were placed on the AC electrical breakers for the SAFWP Room Cooling Units "A" and "B".

0 Procedure changes were submitted, for all procedures involved, to reflect the new locked breaker status o f the above AC electrical breakers.

Operations Department will review the generic implications to other safety related equipment.

0 Nuclear Assurance Department will review current methodology for assuring that the operability of the redundant, component of a system, sub-system, train, component or device is effective.

0 Operations will develop guidelines for and request training, focusing on the relatively new oper-ability Technical Specifications.

0 Training will design and implement new training modules based on the above request; NRC fORM SSSA IS441

U.S, NUCLEAII AEOULATOIIYCOMMISSION NIIC Perre ESSA ISIS)

LICENSEE EVENT REPORT {LER) TEXT CONTINUATION APPAOVEO OMS NO. SI SOWI04 ESPIIIKS 8/SIrs5 PACILITY NAME III OOCIIST NUMSSII ITI LEII NUMSEII ISI ~ AOS ISI YSAII g~$ 5 5 0 V 5 HT I A L n KVIe lO rr

~ rvMeen ~ rvM en R.E. Ginna Nuclear Power Plant 0 S 0 0 0 2 4 4 8 70 0 6 000 7 OF 0 7 TEXt Idmore epeee N reeeeerE vee eMWarMI NOMIC form ~IIIIITI VI. ADDITIONAL INFORMATION A. FAILED COMPONENTS:

None.

B. PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: No documentation of similar LER events could be identified.

C~ SPECIAL COMMENTS:

0 The Standby Auxiliary Feedwater System was installed to provide an independent system capability following a high energy line break event which could render the three main Auxiliary Feedwater Pumps inoperable. The Standby Auxiliary Feedwater System is manually started and con-trolled from the Control Room in the event that all other means of feedwater are lost. The system pumps lake water from the service water system to the Steam Generators and would only be used after all other feedwater addition alterna-tives had been exhausted.

0 The corrective action planned will be tracked by Corrective Action Report (CAR) g 1836.

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ROGER iV, KOBER VICE, PRCSIOCt'T CLCCTRtC PAODVCTIOtt t ttt.i CGCt ' 5 C Z '(t~)

December 30, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 87-006, Inadvertent Attendant Cooling Unit Inoperability Due To Open Breaker Causes 1D Standby Auxiliary Feedwater Pump To Be Deemed Inoperable Beyond The Technical Specification Limit.

R.F. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i):(B) which requires a report of, "any operation prohibited by the Plant's Technical Specification", the attached Licensee Event Report LER 87-006 is hereby submitted.

This event has in no way affected the public's health and safety.

/~~(

Roger W. Kober XC>> U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Ginna USNRC Resident Inspector gag,2 CE@7iFteD 00 - PSST 87( Q,g