ML18033B727

LER 91-010-00:on 910515,24 H Limiting Condition for Operation Expired & Sys Affected by Reactor Vessel Water Level Transmitter Not Declared Inoperable.Caused by Inadequate Procedures.Personnel trained.W/910611 Ltr

ML18033B727
Person / Time
Site:	Browns Ferry
Issue date:	06/11/1991
From:	Ridgell E, Zeringue O TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-010-01, LER-91-10-1, NUDOCS 9106190009
Download: ML18033B727 (14)

Text

ACCELERATED DISTRIBUTION DEMONST1l'ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9106190009 DOC.DATE: 91/06/11 'NOTARIZED: NO DOCKET FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee '5000260 AUTH. NAME AUTHOR AFFILIATXON RZDGELL,E.M. Tennessee Valley Authority ZERINGUE,O.J. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 91-010-00:on 910515,24 h limiting condition for operation expired & sys affected by reactor vessel water level transmitter not declared inoperable. Caused by ltr.

inadequate procedures. Personnel trained.W/910611 DISTRIBUTION CODE IE22T COPIES RECEIVED:LTR / ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident J SIZE:

Rpt, etc.

NOTES:,1 Copy each to: S.Black,B.WILSON '05000260 RECXPIENT COPXES RECIPIENT COPIES ID 'CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL KREBS,M. 1 1 'HEBDON,F 1 1 ROSS,T. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1' NRR/DST/SICB8H3 NRR/DST/SRXB 1

1 1

1 EG FIL

/ LB8D1

'02 1 1

1 8E'ES/DSIR/EXB 1 1 RGN2 FXLE 01 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 NOTES: 5 5 NOTE TO ALL "RIDS" RECIPIENTS:

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

FULL TEXT 'CONVERSXON REQUIRED TOTAL NUMBER OF COPIES REQUXRED: LTTR 38 ENCL 38

0 Tennessee Vatfey Authority. Post Office Box 2000. Decatur.'Atabaina 35609 O. J. 'Ike'eringue Vice President. Browns Ferry Operations aux l1 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Dear Sir:

TVA BROWNS FERRY NUCLEAR 'PLANT (BPÃ) 'UNIT 2 DOCKET NO. 50-260 FACILITY OPERATING LICENSE DPR-52 REPORTABLE OCCURRENCE REPORT BFRO-50-260/91010 The enclosed report provides details concerning violation of the plant Technical Specification (TS) when a 24-hour Limiting Condition for Operation expired and the required actions described by the TS had not been completed. This report is submitted in accordance with 10 CFR 50.73(a)(2)(i).

Very truly yours, TENNESSEE VALLEY AUTHORITY Enclosure cc: see page 2

>10! 900 9 9 ~02~ 0 Ypv>~ i pop ADOCK 0500PD<

U.S., Nuclear Regulatory Commission Jug gi 19sl cc '(Enclosure):

INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 NRC Resident Inspector, BFN Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite '2900 Atlanta, Georgia 30323 Thierry M. Ross U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION Approved OHB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

. FACILITY NAME (1) lDOCKET NUMBER (2) l~gF~

TITLE (4) Plant Technical Specification Violation when 24-Hour Limiting Condition for Operation Expired V NT 0 t I I I lSEQUENTIAL l lREVISIONl l l l FACILITY NAMES lDOCKET NUMBER(S) 0 I I l I I I I l I I I ,I OPERATING I ITHIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5:

MODE I I 120 '02(b) I l20 405(c)

~ l50.73(a)(2)(iv) l73.71(b)

POWER'I l20.405(a)(1)(i) 'l l50.36(c)( 1) l50 ~ 73(a)(2)(v) l73 71(c)

~

LEVEL l20.405(a)(1)(ii) l l50.36(c)(2) l50.73(a)(2)(vii) lOTHER (Specify in l20.405{a){1)(iii) l~l50.73(a)(2)(i) l50.73(a)(2)(viii)(A) l Abstract below and in I l20.405(a)(1)(iv) l 150.73(a)(2)(ii) l50.73(a)(2)(viii)(B) l Text, 'NRC Form 366A) l AREA CODE l I I IREPORTABLEI I I I IREPORTABLEI D 4 l SUBMISSION l ABSTRACT (Limit to 1400 spaces, i.e., approximately fifteen single-space typewritten lines) (16)

On May 15, 1991, a violation of the plant Technical Specifications (TSs) occurred when a 24-hour Limiting Condition for Operation (LCO) expired and the systems affected by a reactor vessel water level transmitter were not declared inoperable.

The root cause, of this event was inadequate procedures. Operations is not required to be notified when equipment related to the TS is removed from service. Instead, procedures require Operations to be notified when time limit will expire.

it becomes apparent the the LCO The immediate corrective action was to declare the affected systems inoperable.

Additional'orrective actions will include training of the affected plant personnel and revision of plant .procedures.

NRC Form 366(6-89)

4 NRC Form 366A U.S. -NUCLEAR REGULATORY COHHISSION Approved OHB No. 3150-0104 (6-09) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAHE (1) IOOCKET NUHBER (2)

I /SEQUENTIAL i iREVISIONI I / I (

I I Y A I

I I.I I TEXT (If more space is required, use additional NRC Form 366A's) (17)

On May 15, 1991 at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br />, a Technical Specification (TS) violation occurred when a 24-hour Limiting, Condition for Operation (LCO) expired and the required actions described by the TS had not been coropleted.

On May 14, 1991 at 1438 hours, a 24-hour LCO was entered when a reactor vessel water level (RVWL) transmitter [JCI was removed from service for calibration.

On May 14, 1991 at 1828 hours, Operations was notified that the RVWL transmitter could not be calibrated and was therefore inoperable.. At this time, a log entry was made in the Operations LCO tracking log to document the time of entry into the LCO. However, the .time documented in the LCO tracking log was the time the RVWL transmitter was determined to be inoperable (1828 hours0.0212 days <br />0.508 hours <br />0.00302 weeks <br />6.95554e-4 months <br />) not the time the transmitter was removed from service (1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br />). As a result of the incorrect log entry,, Operations personnel did not declare the systems affected by the RVWL transmitter inoperable within the allotted 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by the TS.

'At the time of this event, Unit 2 was in cold shutdown and Units 1 and 3 defueled. In addition, no fuel handling or other operations over spent fuel were in .progress. This event resulted in a violation of the plant TS and is reportable in accordance with 10 CFR 50.73(a)(2)(i).

The RVWL transmitter provides input to. the reactor low water level instrument channel. This instrumentation is required for the operability of the following systems: Residual Heat Removal, Core Spray, Diesel Generators, Automatic Depressurization, .High Pressure Coolant Injection, and Reactor Core Isolation Cooling.

The TS allows the RVWL transmitter to be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for calibration or repair. In the event that'he calibration or'epair of this transmitter cannot be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> then the affected systems must be declared inoperable There were .no safety consequences or .implications resulting from this event. If Unit 2 had been operating at .power when this event occurred, the plant TS would have required the unit to be in hot standby within six hours and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. However, Unit 2 was already in cold shutdown during this event. Therefore, this event had no safety significance.

NRC Form 366(6-89)'

l5 NRC Form 366A U.S. NUCLEAR REGULATORY COMNISSION Approved ONB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NANE (1) iOOCKET NUNBER (2)

I I I I SEQUENTIAL I I REVISIONI I I I I I I I. I I TEXT (If more space is required, use additional NRC Form 366A's) (17)

The root cause of this event was an inadequate procedure. The procedure used to perform this calibration documented the time the RVWL transmitter was removed from service. However, it did not require Operations to be notified of the time the instrument was removed from service. Instead, the procedure only required Operations to be notified if it appeared the work would exceed the LCO time limit.

In addition, a .contributing factor to this event was inadequate communication.

Plant personnel did not ensure the time entered in the Operations LCO tracking log was the actual time the RVWL transmitter was taken out-of-service.

The immediate corrective action was to declare the systems affected by the RVWL transmitter inoperable. This action was completed on May 15, 1991 at 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br />.

Additional corrective actions will include the, following:

First, affected plant personnel will review the. event investigation.

Second, affected Maintenance personnel will be trained on the TS definition of "operable" and on how Operations interprets the terms "inoperable" and "out of service."

Finally, affected surveillances and electrical maintenance .instructions will be revised to require operations to be notified of the time when TS related instrumentation is removed from service.

BFRO-50-259/84031-During normal operation the 'Dl'es'idual Heat Removal Service Water (RHRSW) pump was removed from service. Contrary to the TS, the 'D2'HRSW pump was not immediately verified to be operable. Plant personnel were trained on the associated'rocedures and on the TSs.

NRC Form 366(6-89)

i4 NRC Form 366A U.S. NUCLEAR REGULATORY CONNISSIOH Approved ONB Ho. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CONT IHUATIOH.

FACILITY HANE (1) )OOCKET NUNBER (2)

I I I SEQUENTIAL ) ) REVISION [

I I I,I I TEXT (If more space is required, use additional NRC Form 366A's) (17)

First, affected personnel will review the event investigation. This will be completed by August 1, 1991.

Second, affected Maintenance personnel will be trained on the TS definition of "operable" and on how Operations interprets the terms "inoperabl'e" and "out of service". This will be completed by August 1, 1991.

Finally, affected surveillance and electrical maintenance instructions will be revised to require Operations to be notified of the time when TS related instrumentation is removed from service. This will be, completed by December 31, 1991.

Energy Industry Identification System (EIIS) codes are identified in the text .as t'zz].

'NRC Form 366(6-89)