ML18153C976

LER 92-004-00:on 920326,B Chiller Became Inoperable Due to Hand Operated Rocker Switch Inadvertently Being Placed in Off Position.Chiller Returned to Svc.Upgrade to Sys Will Include Installation of Two chillers.W/920420 Ltr

ML18153C976
Person / Time
Site:	Surry
Issue date:	04/20/1992
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-263, LER-92-004-02, LER-92-4-2, NUDOCS 9204240105
Download: ML18153C976 (6)

Text

ACCELERPlTED D_J.RIBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9204240105 DOC.DATE: 92/04/20 NOTARIZED: NO DOCKET#

FACIL:50-281 Surry Power station, Unit 2, Virginia Electric & Powe 05000281 ATJTH.NAME AUTHOR AFFILIATION KA~SLER,M.R. Virginia Power (Virginia Electric & Power Co.)

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 92-004-00:on 920326,B chiller became inoperable due to hand operated rocker switch inadvertently being placed in I off position.Chiller returned to svc.Upgrade to sys will include installation of two chillers.W/920420 ltr.* D DISTRIBUTION CODE: IE22T COPIES RECE-IVED:LTR _j ENCL _j_ SIZE:_.> _ _ _ __ s TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

I NOTES:lcy NMSS/IMSB/PM. 05000281 A

RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 BUCKLEY,B 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 s AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFBlO 1 1 NRR/DLPQ/LPEBlO 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP /PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRR/ Q,$.,.T_d~~,?_Dl 1 1 NRR/DST/SRXB 8E 1 1

~~~~~~l~ 1 1 RES/DSIR/EIB 1 1 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST.LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 R

NOTES: 1 1 I

D s

• /

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

s PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PJ-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 33

• ~ '

- Virginia Electric and Power Company Surry Power Station P. 0. Box 315

• Surry, Virginia 23883

• April 20, 199~l

-*

U.S. Nuclea:r Regulatory Commission Serial No.: 92-263 Document Control Desk SPS:RJS Washington, :0. C. 20555 Docket No.: 50-281 License No.: DPR-37 Gentlemen:

Pursuant to- Surry Power Station Technical Specifications, Virginia Electric and Power Company hert~by submits the following Licensee Event Report for Unit 2.

REPQRTNUMBER 50-281/92-004-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by the Corporate Management Safety Review Committee.

Very truly yours, Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 9204240105 920420 PDR ADOCK 05000281 S PDR

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 16-89) ' APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (11 Surry Power Station, Unit 2 TITLE 141 Two Main Control Room/Emergency Switchgear Room Chillers Inop~rable Due to.Personnel Error EVENT DATE (51 LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (81 MONTH DAY YEAR 'JEAR 1

,:;:::;:;:SEQUENTIAL!::::::::: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI

NUMBER [

'.

'.

'.:'.: NUMBER o I 3 216 g 2 g j 2 - oj o j4 - o lo o14 ~ Io 9 I2 o Is Io Io Io 1 1 I THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Check one or more of the following) (11)

---

OPERATING MODE (9) N 20.402(b) 20.405(cl 60.73(ol(21(ivl

- 73.7.1(b)

---

1-20.406(o)(1)(i) 20.406(01(1 )(ii) 60.36(c) 111 .

60.381c)(21 50.73(oll21M 50.73(01(2) (vii)

- 73.71(cl OTHER (Specify in Abstract 20.405(6)(1 )(ill)

. "x' 50.73(o)(2llil 50.73(ol(2)(villl(AI t--- balow* and in Text, NRC Form 366/J,)

20.406(0)(1 llivl 20.406(0111 lM - 150.73(ol(2)(iil 60.73(ol(21(iii) -

LICENSEE CONTACT FOR THIS LER (121 50.73(o)(2)(viiil(BI 50.731oll2Hxl NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station Manager 8 10 I 4 3 1s I 7I- 13 1 1 18 14 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)

MANUFAC, MANUFAC*

CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TURER TURER I I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED n YES /If yes, complete EXPi;crED SUBMISSION DATE/

ABSTRACT (Limit to 1400 spac6.r, i.e., approximstBly fifteen single-spaco typowrittBn lines) (16)

SUBMISSION DATE !151 I I I On March 26, 1992, at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />, Unit 1 was at Cold Shutdown and Unit 2 was operating at 100% power. Main Control Room/Emergency Switchgear Room (MCR/ESGR) 1-VS-E-4A was out of service due to scheduled bus maintenance resulting in the loss of the normal and emergency power supply. The "B" chiller became inoperable due to the hand operated rocker switch inadvertently being placed in the "OFF" pos1t1on. The switch is located on the chiller mounted control panel and alllows local operation to turn on or off the chiller. Because two inoperable MCR/ESGR chillers is a condition not allowed by* Technical Specification (TS) 3.23.C.1.a, an action statement requiring Hot Shutdown within six hours was entered in accordance with TS 3.0.1. At 1202 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.57361e-4 months <br />, the "B" chiller was restarted and returned to service, terminating the .six hour action statement. No significant safety consequences resulted from this event. This event is being reported pursuant to 10 CFR 50.73 (a)(2)(i)(B).

NRC Form 366 (6-89)

• .

NRC FORM 366A (6-89).

e LICENSEE EVENT REPORT (LER)

• U.S. NUCLEAR REGULATORY COMMISSION e APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPlY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS.

TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555,.AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE

• ,. OF MANAGEMENT AND BUDGET, WASHING.TON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

Surry Power Station, Unit i 0 IS IO IO IO I 21 81 1 91 2 0I d4 - 01 0 0 12 OF O I4 TEXT /ff more S/JIICtl is n,quired, use_ additionatNRC Form 366A's/ (17)

1. O JDESCRIPTIQN QF THE EVENT On March 26, 1992, Unit 1 was at Cold Shutdown anp Unit 2 was at 100%

power. Main Control Room/Emergency Switchgear Room (MCR/ESGR)

Chillers (EIIS-VI-CHU) 1-VS-E-4B and 1-VS-E-4C were in operation. The "A" chiller, 1-VS-E-4A was out of service due to scheduled electrical bus maintenance resulting in the loss of the normal and emergency power supply. At 1_150 hours, the Unit's Senior Reactor Operator noticed that the "B" chiller was off. An operator was immediately dispatched to investigate. At 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br />, the operator reported the rocker switch (EIIS-VI-HS) on the chiller mounted control panel was in .the "OFF" position. With the switch off, the "B" chiller would not operate. With the "B" chiller inoperable and the "A chiller previously inoperable, a condition not ~Bowed by Technical Specification (TS) 3.23 existed.

TS 3.23.C.1.a requires that MCR/ESGR Chillers "A", "B" and "C" be operable when eitlier unit is above Cold Shutdown. TS 3.23.C.1.b. permits. '*

one chH}er to be inoperable for a maximum of seven days. With the "A" chiller previously inoperable for bus maintenance, a seven day action statement .in accordance with TS 3.23.C.1.b was in effect. When the "B" chiller became inoperable due to the manual rocker switch being in the "OFF" position, two of the three MCR/ESGR chillers were inoperable'.

This condition is not allowed by TS 3.23.C.1.a and at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> on March 26, 1992, a six hour action statement to Hot Shutdown was entered in accordance with TS 3.0.1 due to two of three MCR/ESGR chillers* being inoperable, a condition not addressed by TS 3.23.

• Tlh.is report is required by 10 CFR 50.73(a)(2)(i)(B) as the station was operated . in a condition not allowed by Technical Specifications.

2. 0 SJGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS Chillers "A", "B" and "C" are part of the MCR/ESGR Air Conditioning System. This is a shared system designed to maintain the Unit 1 and Unit 2 MCR and ESGR areas at or* below ambient design temperatures during normal operation and design basis accident conditions. Two chillers are required to operate m order to remove post-accident design heat loads, as_suming worst case ambient air temperature and service water temperature.

With the "A" chiller inoperable for bus maintenance and the "B"

• chiller

• im>perable due to the inadvertent placement of the rocker switch in the.

"OFF" position, the "C" chiller would have continued running under accident conditions. Based on design calculations, this created the NRC Form 366A (6-89)

NRC Form 368A U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88

\. FACILITY NAME (11 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 VEAR ;:;:::;:;: SEQUENTIAL ;:;:;:;:;:: REVISION

NUMBER

::;::: NUMBER Surry Power Station, Unit 2 o Is I o I o I o 12 I 8 11 9I2 - o IO I 4 - o Io o I3 OF o 14 possibility that ambient design temperature could have been

• exceeded illl the MCR and ESGR areas in an accident situation. However, this condition existed only for a brief period of time . (12 minutes).

Temperature rise in the MCR and ESGR areas would have been limited in an accident situation since service water temperature was below that a:ssumed in design calculations.

• The rate of temperature rise would also

. have been limited since one chiller remained operable throughout the

.event. In addition, past experience with a complete loss of MCR and ESGR air conditioning has shown that temperatures have not increased as rapidly as indicated by the design calculations. Therefore, it

• is concluded that no safety consequences resulted from this event.

• .CAUSE OF THE EVENT The cause of this event was the inadvertent repositioning of the manual rocker switch on the "B" chiller panel in the "OFF" position due to cognizant personnel error. Scaffolding was being erected around the "A" and "B" chillers by contract personnel. The scaffolding is being used to protect the equipment

• in the area against , damage from falling objects such as tools while work is being performed overhead.

The switch being in the "OFF" position was . due to contract personnel inadvertently bumping the rocker

• switch which placed it in the "OFF" po:sition and rendered the "B" chiller inoperable. . A pre-job brief had been conducted for the personnel erecting the scaffolding. The. safety significance of the chillers and the dose. proximity of the scaffolding being erected to the control .panel switches had been d~scussed.

4. 0, IMMEDIATE CORRECTIVE ACTION{S)

At 1202 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.57361e-4 months <br />, the "B" chiller was restarted and returned* to service. The six hour action statement to Hot Shutdown was exited.

5. O AUDITION AL CORRECTIVE ACTION{S}

On March 27, 1992 at 0906 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.44733e-4 months <br />, l-VS-E-4A was returned to service and the seven day action statement was exited.

6. O AC:flONS TO PREVENT RECURRENCE An upgrade of the MCR/ESGR Air conditioning System is in progress.

The upgrade will include the installation of two additional 50% capacity chillers. These* additionai

• chillers will increase operational flexibility and improve the capacity to withstand single failures.

NRC FORM 366.A

NRC FORM 366A (6-89) e LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COMMISSION e APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPCJI\ISE TO* COMPLY WTH THIS INFORMATION COLLECTION REGUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR

. REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2)

• LEA NUMBER (6) PAGE (3)

Surry Power Stat fon, . Unit 2 0 1s I O I O I O I 21 8 , _1 .9 I 2 - 0 IO I 4 - 0 I O OI 4 0F OI 4 TEXT (ff mom space is mquired, U/JIJ ad,fftiom,/ NRC Form 3S6A '$/ (17)

7. O SIMILAR EVENTS None.

8. O .1,DDITIONAL INFORMATION None.

NRC Form 366A 16-891