ML18011A719

LER 94-006-00:on 941116,surveillance Testing Revealed That inter-cell Float Voltage for Cell 50 of B-SB Safety Related Battery Outside Allowable TS Limits Due to Deficient Maint Surveillance Test Procedure.Procedure revised.W/941215 Ltr

ML18011A719
Person / Time
Site:	Harris
Issue date:	12/15/1994
From:	Donahue J, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-941060, LER-94-006-03, LER-94-6-3, NUDOCS 9412200181
Download: ML18011A719 (6)

Text

t PR.IC)RI EY (ACCELERATED RIDS PROCI'.SSli'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9'412200181 DOC.DATE: 94/12/15 NOTARIZED- NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina ,05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co.

DONAHUE,J.W. Carolina Power & Light Co. P RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 94-006-00:on 941116,inter-cell float voltage for cell 50 of B-SB safety related battery between 2.13 volt limit &

2.07 min allowable value of TS 4.8-2.Caused by deficient test procedure & poor work practices.W/941215 ltr.

0 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES:Application for permit renewal filed. 05000400 I

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS 1 1 AEO3)/S~Q ERB '2 2 AEOD/SPD/RRAB NRR/DE/ECGB 1

1 1

1 P IL~E" CENTERW02 NRR~DE/EE LB 1

1 1

1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DOPS/OECB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB I 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 D RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHY,G.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 C U

YO I'E TO ALL"RIDS" RECIPIL'4"I S:

PLEASE HELP I'S TO RF DL'CE 'O'ASTE! CONTACT'I I IE DOCL'ifEYTCONTROL DESK, ROOXf Pl-37(FX I: 504.2033 ) TO FLIXIIXATEYOL'R RAMIE FROXI DISTRIBL'TIOi LIS'I'S FOR DOCI'%II:i'I'S YOL'Oi "I'l;I:.0!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28

Carolina Power & Light Company Harris Nuclear Plant PO Box 1 65 New Hill NC 27562 DEc I 5 199tt Letter Number: HO-941060 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 94-006-00 Gentlemen:

In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September 1983.

Sincerely, 84 uQ J. W. Donahue General Manager Harris Plant MV Enclosure cc: Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRC - PM/NRR)

Mr. S. A. Elrod (NRC - SHNPP)

Mr. W. R. Robinson 9412200181 941215 PDR ADOi."!, 05000400 State Road ll34 New Hill NC S PDR .ZgQP >

NRC FORH (5-92) 366 t

LICENSEE EVENT REPORT (LER)

U.S.

r NUCLEAR REGULATORY COMHISSION t APPROVED BY OHB NO.

EXPIRES 3150-0104 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMHENTS REGARDIHG BURDEN ESTIHATE TO THE INFORMATION AND RECORDS HAHAGEMENT BRANCH (See reverse for required nunber of digits/characters for each block) (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION, WASHINGTON, DC 20555-000'I, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEHENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME (1) DOCKET NUHBER (2) PAGE (3)

Shearon Harris Nuclear Plant-Unit ¹1 05000/400 1OF3 TITLE (4) Cell voltage verification required by Technical Specifications was not performed when the safety related B-SB station batte individual cell volta e values fell outside the allowable limits.

EVENT DATE (5 LER NUHBER 6) REPORT DATE 7 OTHER FACILITIES INVOLVED 8)

SEQUENTIAL REVISION FACILITY HAHE DOCKET HUHBER HONTH DAY YEAR YEAR NUMBER NUHBER HONTH DAY YEAR 05000 FACILITY NAHE DOCKET NUMBER 16 94 94 006 00 12 15 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RE UIREHENTS OF 10 CFR 5: (Check one or more) (11)

HODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POWER 20.405(a)('l)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) 100K LEVEL (10) 20.405(a)('l)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a) (1) ( i i i ) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract beloM and in Text, 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A)

LICENSEE CONTACT FOR THIS LER (12)

HAHE TELEPHONE NUHBER (Include Area Code)

Michael Verrilli Sr. Specialist - Licensing (919) 362-2303 COHPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IH THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEH COHPONENT MANUFACTURER TO NPRDS TO HPRDS SUPPLEHENTAL REPORT EXPECTED 14) EXPECTED HONTH DAY YEAR YES SUB HISS ION (lf yes, cceplete EXPECTED SUBHISSION DATE). X HO DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typeHritten lines) (16)

On November 11, 1994, surveillance testing revealed that the inter-cell float voltage-(ICV) for cell ¹50 of the B-SB safety related battery was between the 2.13 volt "limit" and 2.07 volt "minimum allowable value" of Technical Specification (TS) Table 4.8-2. The battery is still considered operable with the voltage value in this range, provided that the voltage is restored to greater than the 2.13 volt "limit" within 7 days. Discussion related to this testing requirement resulted in a review of documentation from recently performed surveillance tests. This review identified that cell recharge verification had not been performed within 7 days as required following testing the previous month on October 19, 1994. Upon identification of this condition, the control room staff declared the B-SB battery inoperable and commenced a single cell charge on cell ¹50 to raise the voltage back to acceptable'levels. Subsequent investigation revealed nine additional instances where this verification had not been performed within 7 days as required. These occurrences constitute a violation of TS and are being reported per 10CFR50.73.

The cause of this condition was a combination of a deficient test procedure and poor work practices on the part of those involved in performing and reviewing the tests. Immediate corrective actions included restoring"the cell voltage to an acceptable value, reviewing other battery testing procedures and revising the deficient maintenance surveillance test procedure. Additional actions will include training for maintenance personnel to enhance their understanding of procedural and TS requirements. There were no safety consequences as a result of this

~

condition. Even though testing was not performed as required by TS, the battery ICV values were always above the "allowable level", therefore the battery was capable of performing it's safety function. There have been no previous reports submitted related to the failure to perform TS battery testing.

NRC FORM 366A (5-92)

0 P,

NRC FORH (5-92) 366A LjCENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COHHISSION t APPROVED BY OHB NO.

EXPIRES 3150-0104 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHAT ION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORHATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION ,PROJECT (3180-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

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

YEAR SEQUEHT IAL REVISION Shearon Harris Nuclear Plant - Unit ¹1 05000/400 20F3 94 TEXT (If more space fs required. use additional copies of NRC Form 36&i) (17)

EVENT DESCRIPTION:

On November 16, 1994, with the plant operating in mode-1 at 100% power, maintenance surveillance testing (MST-E0011) on the B-SB safety related battery revealed that the inter-cell float voltage (ICV) for cell ¹50 was between the 2.13 volt "limit" and 2.07 volt "minimum allowable value" of Technical Specification (TS) Table 4.8-2. Per the notations of TS Table 4.8-2, any time the ICV falls into this range, the battery can still be considered operable provided that the voltage is restored to greater than the 2.13.volt "limit" within 7 days. Discussion related to these requirements resulted in a review of documentation from the previous month's surveillance test. This review identified that cell ¹50 was below 2.13 volts on October 19, 1994 and had not been restored as required, following testing. Upon identification of this condition, the control room staff declared the B-SB battery inoperable and commenced a single cell charge on cell ¹50 to raise the voltage back to acceptable levels. During the root cause investigation of this condition, a review was performed of completed MST-E0011 documentation packages, which exposed nine additional instances where this verification had not been performed within 7 days as required. These nine occurrences constitute a violation of TS and are being reported per 10CFR50.73.

CAUSE:

The cause of this event was a combination of a deficient maintenance surveillance test procedure and personnel error during the performarice and review of surveillance testing. MST-E0011, the Safety Related Battery Quarterly Surveillance Test, includes a table and table notations that are very ambiguous. They have led to an unclear understanding of test acceptance criteria and of what actions are needed if values are obtained between the acceptance limits and minimum allowable values. Poor work practices on the part of personnel performing this testing were also noted. These work practices involved routinely working to the procedure data sheets instead of the contained step-by-step guidance. Personnel performing the tests also exhibited insufficient awareness of the impact of their actions. The rev'iew of completed test documentation, which is performed by electrical maintenance supervisory personnel, did not consistently identify that TS actions were required.

SAFETY SIGNIFICANCE:

There were no safety consequences as a result of this event. In all cases the obtained ICV values were above the minimum allowable value of TS table 4.8-2. Thus the battery was always capable of performing it's intended design and safety function.

NRC FORM 366A (5-92)

NRC FORM (5-92) 366A LICENSEE EVENT REPORT (LER) t APPROVED BY OHB NO.

EXPIRES 3150-0104 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS ~

FORWARD COMMENTS REGARDIHG BURDEN ESTIHATE TO THE INFORHATION AHD RECORDS HANAGEHENT BRANCH (MNBB 7714)i U ST NUCLEAR REGULATORY COMMISSIONi WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET NUHBER (2) LER NUMBER (6 PAGE '(3)

YEAR SEQUENTIAL REVISION Shearon Harris Nuclear Plant - Unit ¹1 05000/400 3 OF 3 94 006 TEXT (If more space fs required, use addftfonal copfes of NRC Form 866A) (17)

CORRECTIVE ACTIONS:

1. Battery operability was restored on November 17, 1994 by performing a single cell charge that raised the ICV value of Cell ¹50 above 2.13 volts.

2. MST-E0011 has been revised to clarify the acceptance criteria and the a tions needed when parameters fall between the TS "acceptance limit" and the "minimum allowable value".

3. Training will be provided for maintenance personnel that perform and review MST-E0011 to enhance their understanding of procedural and TS requirements.

EIIS INFORMATION:

N/A NRC FORM 366A (5-92)