ML17261A484

LER 87-004-00:on 870424,during Full Power,Train B Containment Isolation Occurred.Caused by Personnel Accidentally Bumping Relay in Safeguards Cabinet During Electrical Wire Checkout.Personnel counseled.W/870522 Ltr

ML17261A484
Person / Time
Site:	Ginna
Issue date:	05/22/1987
From:	Backus W, Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-004, LER-87-4, NUDOCS 8705290244
Download: ML17261A484 (10)

Text

REGULATORY IhRMATION DISTRIBUTION SYST (R IDS)

>g ACCESSION NBR: 8705290244 DOC. DATE: 87/05/22 NOTARIZED: NO DOCKET FAC IL: 50-244 Robert Emmet Qinna Nuc lear P lant> Unit 1> Roc h e ster '0 05000244 AUTH. NAME AUTHOR AFFILIATION BACKUS W. H. Rochester Gas 8c Electric Corp.

KOBER> R. W. Rochester Gas 8c Electric Corp.

RECIP. NAME RECIPIENT AFFILIATION SUB JECT: LER 87-004-00: on 870424> during iul 1 power> Train B containment isolation occur r ed. Caused by personnel accidental 1!) bumping relay in saieguards cabinet during electrical !!!ire checkout. Personnel counseled. W/870522 itr.

DISTRIBUTION CODE: IE22D COPIES RECEIVEl): LTR ENCL SIZE:

TlTLE: 50. 73 Licensee Event Repor t (LF'R) Incident Rpt> etc.

NOTES: License Exp date in accordance i ith 10CFR2> 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 STAHLE> C 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 DEXTRO 1 NRR/DEST/ADE 0 NHR/DEST/ADS 1 0 NRR/DEST/CEB NRR/DEST/ELO 1 NRR/DEST/ICSB 1 1 NRR/DEST/MEO 1 1 NRR/DEST/MTB 1 VHR/DEST/PSB 1 1 NRR/DEBT/RSB 1 1 ted% R /DEST/ SGB 1 a

NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 C

NRR/DOEA/EAB 1 NRP/DREP/RAB 1 NRR/DREP/RPB 2 2 /ILRB 1 NRR/PMAS/PTSB 1 RED FILE 02 RES DgPV GI 1 RGi I LE 01 1 ai EXTERNAL: EGaG GROH,M 5 5 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSI,C HARRIS, J 1 1 N IC MAYS, G 1 TOTAL NUMBER OF COP lES REQUIRED: LT I R 42 ENCL 40

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AOTNOVSD OSN NO. 0) CLOlOS tXOINEL SO I M UCENSEE EVENT REPORT LER)

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On April 24, 1987 at 1130 EDST with the unit at 100't reactor power, a Train B Containment Isolation occurred due to personnel inadvertently bumping a relay in the safeguards cabinets while performing a field walkdown for the electrical drawing upgrade program.

All Containment Isolation valves required to close, operated as designed.

Immediate correction action taken was: after the cause of the Containment Isolation was determined, Operations restored all systems affected to their pre-event status.

The root cause of the event was personnel error Electrical Engineer who bumped the relay. in the performance byof the work in these cabinets.

Corrective action taken to prevent with all personnel who have to work recurrence was to reinforce, in safeguards cabinets, the precautions that must be taken and to minimize access to these cabinets during power operation. All access will be supervised by trained plant personnel.

8705290244 870522 PDR ADOCK 05000244 8 PDR NNC Osroe (04$ )

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V.S, NUCLEAR RECULATORY COMM(SSION NRC FOUR 366A (9.83(

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ACCROV EO OMB NO 3150-0(04 EXPIRES 8(3(F85 FACILITY NAME (I) OOCKET NUMBER (2( LER NUMBER (6) ~ AOE (31 YEAR SEOUENTIAL NUMBER i, REViSION

'UMBER OF R.E. Ginna Nuclear Power Plant 0 5 0 0 0 2 4 4 7 0 0 4 TEXT lllmom SPoco ie coqoired, v(o oddemol Nl(C %%dnn 36(SA'cl 021 PRE-EVENT PLANT CONDITIONS The unit was at 100% reactor power and two Electrical Engineers were performing field walkdowns of electrical systems as part of the on-going electrical drawing upgrade program. They had started this work on April 22, 1987 and their intentions were to review the field conditions in nine electrical cabinets in the Relay Room: Ml, M2, RAl, RA2, RA3, SIA1, SIA2, SIBl, and SIB2.

Prior to starting the work the two Electrical Engineers reviewed the proposed work scope with the Instrument and Control Supervisor and the Shift Supervisor and were given permission to proceed with the following restrictions:

Only one cabinet be open at at time and that no tie wraps or wires be touched.

Prior to the event work had successfully been completed on seven of the nine electrical cabinets.

DESCRIPTION OF EVENT A. EVENT:

On April 24, 1987 at 1130 EDST, while the two Electri-cal Engineers were performing their inspection of electrical cabinet SIB1, a Train B Containment Isolation (CI) occurred. All Containment Isolation valves not required to be'pen during accident conditions closed as designed.

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

None.

NRC CORM SBBA (9.83(

NRC FOIIR 366A U 5, NUCLEAR REGULATORV COMMISSION (9831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO 3150&104 EKPIRE5 8/31I85 FACILITY NAME lll DOCKET NUMBER 13l LER NUMBER l6I PACE 13)

VEAA SLOUENTIAL REVISION NUMaSR NUMBFR R.E. Ginna Nuclear Power Plant o s o o o2 44 0 0 4 0 003 0 6 TEXT (Ifmoso apso is IoqoiRRL o>> pffOORof fffIC Ferns 8R'A'll 1171 C. DATES AND APPROXIMATE TIMES FOR MAJOR OCCURRENCES:

o April 24, 1987, 1130 EDST: Event date and time.

o April 24, 1987, 1130 EDST: Discovery date and time.

o April 24, 1987, 1137 EDST: All Train B CI relays reset and normal position.

all CI valves returned to D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

With the Train B CI, the following major systems lines were isolated:

o Instrument Air to the Containment Vessel (CV) o Reactor Coolant System (RCS) Letdown Line o Reactor Coolant Pumps (RCP) gl Seal Return Line o Containment Ventilation o Steam Generator Blowdown E. METHOD OF DISCOVERY:

The event was immediately apparent due to a control board annunciator, Train B CI relay indication, CI valve positions indication in the Control Room. and F~ OPERATOR ACTION:

Operations and an Instrument and Control (1&C)

Technician immediately checked out the reason for the CI. After finding all relays in their normal Operations restored all systems affected bystatus, the B Train CI to their pre-event status.

NSIC FOAM 366A 19 83 I

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U.S. NUCLEAR REGULATORY COMMISSION NRC Fosm 366A I9 83I

'LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROYED OM8 NO 3I50 DIOS EXPIRES 8/3Ii85 DOCKET NUMSER I?I LER NUMSER ISI PAGE I3)

FACILITY NAME III SEQUENTIAL REVISION YEAss NUMSSR NUMSSA R.E. Ginna Nuclear Power Plant TEXT Illmore spesoie seoosod, we ~ HAC Form 3SSA'sl (17) 0 5 0 0 0 2 4 4 8 7 0 0 4 0 0 0 4 OF 0 6 CAUSE OF EVENT A. IMMEDIATE CAUSE:

B Train CI relay C-2 actuated due, to being inadver-tently bumped by Engineering personnel inspecting electrical cabinet SIB1.

B. ROOT CAUSE:

The root cause was determined to be personnel error by the Electrical Engineer by not being more careful when working in the electrical cabinets.

IV. ANALYSIS OF EVENT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires reporting of "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)" in that Containment Isolation is a ESF sub-system.

An assessment was performed of 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 inadvertent CI because; 0 The CI system operated as designed.

0 The systems affected were restored to normal status very quickly (within approximately 7 minutes).

0 The systems affected were capable of withstanding the isolation for a short period of time.

NAC CORM 366A I883I

U.S. NUCLEAR REGULATORY COMMISSION NRC Form 3ddA 19431 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROUEO OM8 NO 3150M(Cd EXPIRES 8131'85 OOCKET NUMSER (2( LE R NUM8 E R (dl PAGE (31 FACILITY NAME (11 EEOUENTrAL rl E v I 5 ro N YEAR NUMEER NUM ER R.E. Ginna Nuclear Power Plant TEXT illmore Trrooo lr eoerr'eoo, rroo ~ HRC Form 3684'Fl (LT(

0 6 0 0 0 2 4 4 004 0 0 05 oF 0 6 V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

o Operations, after finding that the cause for the CI was inadvertent, restored all systems affected by the event to their pre-event status.

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

I' The Operations Manager has sent a letter to all Sections Managers affected, that states to the extent practical, work in all electrical safe-guards and protection cabinets will be minimized while the plant is at power..

Both of the Electrical Engineers involved with the event have had their awareness reinforced as to the precautions which must be taken while working in electrical safeguards and protection cabinets.

0 All Engineering personnel requiring access to electrical safeguards and protection cabinets have been made aware of this event by their managers.

0 Placards will be'ade and attached to all electrical safeguard cabinets that read: During power operations access will be supervised by Operations, I&C personnel, or Test and Results'ersonnel.

NRC FORM 3ddA (9 831

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NRC Farm 36SA V.S. NUCLEAR REGULATORY COMMISSION (943 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. 3(50&(04 EXPIRES 8(3( r85 FACILITY NAME (II OOCKET NVMSER (2( LER NUMBER (SI ~ AGE (3l YEAR SSQUSNTrAL .'svrsro4 a88r. 4UMes/I 4UMes4 R.E. Ginna Nuclear Power Plant TEXT Illmore sirese is eyvr(erS vse ~ rYRC %%dmr 3554'sl (It(

p g p p p 24 487 0 0 4 0 0 06 oFo 6 VI. ADDITIONAL INFORMATION A. FAILED COMPONENTS:

There were no component failures that contributed to this event.

r 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.

4 R C s 0 8 M 36 (IA Ia 831

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aA May 22, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 87-004, Inadvertent Containment Isolation Due to Personnel Error During Electrical Wire Checkout of Safety Injection Relay Cabinet.

R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv) which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 87-004 is hereby submitted.

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

V ry truly yours,

d. /c Rog r W. Kober xc U.S, Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Ginna USNRC Resident Inspector