ML18012A345

LER 96-017-00:on 960805,failed to Perform Surveillance Testing.Cause Indeterminate & Investigation in Progress.W/ 960904 Ltr

ML18012A345
Person / Time
Site:	Harris
Issue date:	09/04/1996
From:	Donahue J, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-96-145, LER-96-017, LER-96-17, NUDOCS 9609110098
Download: ML18012A345 (4)

Text

CATEGORY 1 REGULALY INFORMATION DZSTRZBUTIOOSYSTEM (RIDE) 1 ACCESSION NBR:9609110098 DOC.DATE: 96/09/04 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power 6 Light Co.

DONAHUE,J.W. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 96-017-00:on 960805,failed to perform surveillance testing. Cause indeterminate 6 investigation in progress.W/

960904 ltr.

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 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 AEOD SPD RAB 2 2 AEOD/SPD/RRAB 1 1 C TER 1 1 NRR/DE/ECGB 1 1 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHYFG.A 1 1 NOAC POOREFW. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U

E N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK/

ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26

Carolina Power & Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 4 1996 U.S. Nuclear Regulatory Commission Serial: HNP-96-145 ATTN: NRC Document Control Desk 10CFR50.73 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 96-017-00 Sir or Madam:

In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report describes a failure to perform a surveillance test required by Technical Specifications.

Sincerely, J. W. Donahue Director of Site Operations Harris Plant MV Enclosure c: Mr. J. B. Brady (HNP Senior NRC Resident)

Mr. S. D. Ebneter (NRC Regional Administrator, Region II)

Mr. N. B. Le (NRC - NRR Project Manager) 9609ii0098 960904 PDR ADQCK 05000400 S PDR

.-,~050 State Road 1134 New Hill. NC

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150%104 FLBSI EXPIRES 04/30/9B ESTIMATED BURDEN PER RESPONSE TO COMPLY mTH THIS MANDATORY INFORMATION COllECTIOH REDDEST: 500 HRS. REPORTED LESSONS lEARHEO ARE LICENSEE EVENT REPORT (LER) INCORPORATED UITO THE UCEHSUIG PROCESS ANO FED BACK TO INDUSTRY.

FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MAHAGEMEHT BRANCH IT% F331 US. NUCLEAR REGUIATORY COMMSSION, (See reverse for required number of WASFINGTON. OC 20555000l. ANO TO THE PAPERWORK REDUCTION PROJECT ISI50.

digits/characters for each block) OIOtL OFFICE OF MAHAGEMEHT AND BUDGET, WASHDIGTOH OC 209KL FACIUTY NAME ill DOCKET NUMBER I3) PAGE I3I Harris Nuclear Plant Unit-1 50-400 1 OF 2 TITLE I4l Failure to perform surveillance testing required by Technical Specifications.

EVENT DATE {5) LER NUMBER {6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)

FACIUTY NAME OOCKETNVMBER SEOUENTUIL REVISION MONTH OAY YEAR MONTH OAY NUMBER NUMBER 05000 FACIUTY HAM E DOCKET NVM8ER 8 5 96 96 017 0 9 4 96 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR %: (Check one o r more) (11)

MODE (9) 20.2201(b) 20.2203(a) (2) (v) 50.73(a)(2)(i) 50.73(a) (2) (viii)

POWER 20.2203(a) {1) 20.2203(a) (3) (i) 50.73{a) (2) {ii) 50.73(a) (2) (x)

LEVEL (10) 100% 20.2203(a) (2) {i) 20.2203(a) (3)(ii) 50.73(a)(2)(IR) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a) (2) (iii) 50.36(c) (1) 50.73(a)(2) {v) Specify in Abstract below or m NRC Form 366A 20.2203(a) {2)(iv) 50.36{c) (2) 50.73(a) {2)(vii)

LICENSEE CONTACT FOR THIS LER {12)

NAME TELEPHONE NVM8ER ancrude Ares Code)

Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAiLURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED {14) EXPECTED MONTH OAY YEAR YES SUBMISSION

{It yes, complete EXPECTED SUBMISSION DATE).

NO DATE (15) 9 30 96 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On August 5, 1996, with the plant operating in mode 1 at 100% power, an internal Nuclear Assessment Section (NAS) assessment identified that test documentation for the October 5, 1995 performance of OS'I'-1052 (Reactor Auxiliary Building (RAB)

Emergency Exhaust System, 18-month Operations Surveillance Test) had not been transferred to the nuclear records storage vault and could not be located within the plant's document control program. Records and completed test documentation showed that OST-1052 had previously been performed on April 24, 1994 and the plant's surveillance test scheduling system indicated successful performance of OST-1052 on October 5, 1995 during refueling outage six. However, NAS personnel were unable to locate the October 5, 1995 OST-1052 test documentation. During the assessment, Engineering personnel informed NAS that they were also unable to locate the October 5, 1995 OST-1052 test documentation during RAB Emergency Exhaust System testing performed in May of 1996, but did not consider the possibility that the test had not been performed, which would result in a Technical Specification violation.

Additional searches were performed by personnel responsible for scheduling and tracking surveillance tests, and personnel involved in processing completed surveillance test documentation. These searches also failed to locate the October 5, 1995 OST-1052 test records. Investigation into the cause of this event is in-progress and the results, subsequent corrective actions and potential safety consequences will be provided in a supplement to this LER. If OST-1052 was not performed as scheduled in October 1995, the Technical Specification interval was exceeded on March 11, 1996. Based on the inability to verify that OST-1052 was performed within the Technical Specification required periodicity, a determination was made on August 23, 1996, that this condition constituted a missed Technical Specification surveillance test, which is reportable per IOCFR50.73 as a Technical Specification violation. Surveillance testing was completed on June 6, 1996, which verified the operability of the Reactor Auxiliary Building Emergency Exhaust System.

NRC FORM 3$ 5A US. NUClEAR REGUlA'TORT COMM)ss)ON

+S5)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACIUTT NAME ll) OOCXET lER NUMRER la) PAGE )3)

SEOUENnAt REV)S)ON NUMOER NUMRER Shearon Harris Nuclear Plant ~

Unit Nl 50400 2 OF 2 96 - 017 - 00 TEXT pl sssss spsssis sss)waf. sss sddtuul ssyia s/ iVRC Fane 3SQI ni)

EVENT DESCRIFFION:

On August 5, 1996, with the plant operating in mode 1 at 100% power, an internal Nuclear Assessment Section Assessment (H-OL-9641) identified that test documentation for the October 5, 1995 performance of OST-1052 (Reactor Auxiliary Building Emergency Exhaust System, 18-month Operations Surveillance Test) had not been transferred to the nuclear records storage vault and could not be located within the plant's document control program. Records and completed test documentation showed that OST-1052 had previously been successfully performed on April 24, 1994 and the plant's surveillance test scheduling system indicated successful performance of OST-1052 on October 5, 1995 during refueling outage six. However, assessment personnel ivere unable to locate the October 5, ! 995 OST-!05" test document..tion. During the assessment, Engineering personnel informed NAS that they were unable to locate the October 5, 1995 OST-1052 test documentation during RAB Emergency Exhaust System testing performed in May of 1996, but did not consider the possibility that the test had not been performed, which would result in a Technical Specification violation.

To resolve this condition, additional searches were performed by personnel responsible for scheduling and tracking surveillance tests, and personnel involved in processing completed surveillance test documentation. These searches also failed to locate the October 5, 1995 OST-1052 test records. Investigation into the cause of this event is in-progress and the results, subsequent corrective actions and potential safety consequences will be provided in a supplement to this LER. This investigation will also determine why the condition was not recognized as a potential Technical Specification violation when identified by Engineering personnel in May 1996. If OST-1052 was not performed as scheduled in October 1995, the Technical Specification interval was exceeded on March 11, 1996. Based on the inability to verify that OST-1052 had been performed within the Technical Specification required periodicity, a determination was made on August 23, 1996, that this condition constituted a missed Technical Specification surveillance test, which is reportable per 10CFR50.73 as a Technical Specification violation. Surveillance testing was completed on June 6, 1996, which verified the operability of the Reactor Auxiliary Building Emergency Exhaust System.

CAUSE:

The cause of this event is under investigation and will be provided in a supplement to this LER.

SAFETY SIGNIFICANCE:

The safety consequences associated with this event will be determined by the root cause investigation currently in progress and will also be provided in the supplement to this LER.

PREVIOUS SIMILAREVENTS:

A review for previous similar events associated with this event will be performed during the root cause investigation that is currently in progress and will also be provided in the supplement to this LER.

CORRECTIVE ACTIONS:

The corrective actions associated with this event will be determined by the root cause investigation that is currently in progress and will also be provided in the supplement to this LER.