ML18036A335

LER 91-010-01:on 910515,violation of Plant Tech Spec Occurred When LCO Expired.Caused by Inadequate Procedures. Sys Declared Inoperable,Personnel Trained & Procedures revised.W/910823 Ltr

ML18036A335
Person / Time
Site:	Browns Ferry
Issue date:	08/23/1991
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 9108300088
Download: ML18036A335 (14)

Text

'CCEL'ERATED DIRJBUTION DEMONS~TION SYSTEM I 4

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9108300088 DOC-DATE: 91/08/23 NOTARIZED: NO DOCKET FACIL':50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 AUTH. NAME AUTHOR AFFILIATION RIDGELL,E.M. Tennessee Valley 'Authority ZERINGUE,O.J. Tennessee Valley Authority RECIP NAME RECIPIENT AFFILIATION

SUBJECT:

LER 91-010-01:on 910515,violation of plant Tech Spec occurred when LCO expired. Caused by inadequate procedures.

Declare affected sys inoperable, training of personnel & rev D of plant procedures.W/910823 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D SANDERS',M. 1 1 HEBDON,F 1 1 ROSS,T. 1 1 D 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 1 1 NRR/DST/SPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG 1 1 RES/DSIR/EIB 1 1 RGN2 1 1 EXTERNAL EG&G BRYCE i J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYiG A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 D

D D

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

iI :0 Tennessee valley Authority. post office Box 2000. oecatur. Alabama 35609 IJ8 Q3 199t U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Dear Sir:

TVA BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 2 DOCKET NO. 50-260 FACILITY OPERATING LICENSE DPR-52 REPORTABLE OCCURRENCE REPORT BFRO-50-260/91010, Rev. 1 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, T SSEE V LLEY AUTHORITY Zeringue Enclosure cc: see page 2 9 i 0%~060SS 9'10S23 PDR ADOCK 05000260 PDR

0 ib U.S'. Nuclear Regulatory. Commission AUG 83 1991 cc (Enclosure):

INPO. Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339'RC 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

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(6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

FACILITY NAHE (1) fDOCKET NUHBER (2) w F TITLE (4) Plant Technical Specification Violation When 24-Hour Limiting Condition for Operation Expired Wi b f SE()UENTIAL f REVISION f f f f FACILITY NAHES fDOCKET NUHBER(S)

N D Y I I I I I I I I I I I OPERATING I ITHIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5:

HODE I I I20.402(b) I l20 405(c) f50.73(a)(2)(iv) f73.71(b)

POWER I I l20.405(a)( l)(i) f50.36(c)(1) f50.73(a)(2)(v) f73.7)(c)

LEVEL I f20.405(a)( l)(ii) f f50.36(c)(2) f50.73(a)(2)(vii) fOTHER (Specify in 1 f20.405(a)(1)(iii) f~f50.73(a)(2)(i) f50.73(a)(2)(viii)(A) f Abstract below and in f20.405(a)( l)(iv) f50.73(a)(2)(ii) f50.73(a)(2)(viii)(B) f Text, NRC Form 366A) 1 v NAHE I AREA CODE I I I IREPORTABLEI I I I IREPORTABLEI H N T N I I I I I I R P T EXPECTED DAY A f SUBHISSION f I l ABSTRACT (Limit to 1400 spaces, i.e., approximately fifteen single-space typewritten lines) (16)

On May 1'5, 1991't 1438 hours, 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. The procedure used in this event required that Operations be notified that TS related equipment would be removed from service prior to starting work on the equipment. The procedure also required Operations to be notified exceeded.

if it appeared that an LCO time limit would be However, the procedure did not require Operations to be notified of the exact time the equipment was removed from service, even though the time was documented in the procedure.

The immediate corrective action was to declare the affected systems inoperable.

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

NRC Form 366(6-89)

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LEAR R ULAT R MMI I N Approve MB No. 315 - 10 (6-B9) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) IDOCKET NUMBER (2)

I I I I SEQUENTIAL I IREVISIONI I I I I I I I I I r w F r TEXT (If more space is required, use additiona1 NRC Form 366A's) (17)

On Nay 15, 1991 at 1438 hours, 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 completed.

On May 14, 1991 at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br />, a 24-hour LCO was entered when a reactor vessel water level (RVWL)'ransmitter [JC] was removed from service for calibration.

On Hay 14, 1991 at 1828 hours0.0212 days <br />0.508 hours <br />0.00302 weeks <br />6.95554e-4 months <br />, Operations was notified that the RVWL transmi.tter 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, due to miscommunication, the time documented in the LCO tracking log was the time it was determined that the transmitter could not be calibrated within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allotted by TS (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).

E T 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 the calibration or repair 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 />, the systems affected by this transmitter 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)

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0rm Approve NB o ~ 15 - 1 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NANE (1) IOOCKET NUMBER (2) /REVISION/

I ) SEQUENTIAL / / (

I I I I I W

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 in this event required that Operations be notified that TS related equipment would be removed from service prior to starting work on the equipment. The procedure also required Operations to be notified if it appeared that an LCO time limit would be exceeded. However, the procedure did not require Operations to be notified of the exact time the equipment was removed from service, even though the time was documented in the procedure. This inadequacy in, the procedure resulted in a miscommunication between plant personnel. Specifically, the time entered into the LCO tracking log was the time it was determined the RVWL transmitter could not be calibrated instead of the time the transmitter was initially removed from 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 included the following:

Affected Maintenance personnel have been trained on the TS definition of "operable" and on how Operations uses the terms "inoperable" and "out of service."

Affected plant personnel will review the event investigation.

Affected surveillances and electrical maintenance instructions will be revised to require Operations be notified of the specific time when TS related instrumentation .is removed from service.

BFRO-50-259/84031 During normal operation the 'Dl'esidual 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 procedures and on the TSs.

BFRO-50-259/89-023 During the performance of a Surveillance Instruction (SI) the auto-start features of the emergency equipment cooling water system were disabled. This resulted in an unanalyzed condition. The corrective actions for this event included a revision to the BFN writers guide to require each revised or new SI to include a statement that clarifies the status of equipment operability when authorization is obtained to perform the SI.

NRC Form 366(6-89)

ik Il grP NRC Form 366A U. CLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) IDOCKET NUMBER (2)

I ( ( SE()UENTIAL ( ) REVISION( J I I I I I Brw F TEXT (If more space is required, use additional NRC Form 366A's) (17)

N Affected personnel will review the event investigation. This commitment was originally scheduled for completion by August 1, 1991. Affected plant personnel, with the exception of Operations, have completed the review of the event investigation. To ensure Operations awareness of this event an entry has been placed in the operations daily instruction which is reviewed during each shift turnover. Operations personnel will complete their review by September 9, 1991.

Affected surveillance and electrical maintenance instructions will be revised to require Operations to be notified of the specific 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

[zx].

NRC Form 366(6-89)

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