ML18009A794

LER 90-001-00:on 910103,operations Personnel Identified Procedural Deficiency That Resulted in Check Valves Not Being Tested as Required.Caused by Procedural Deficiency. Procedure Revised to Incorporate testing.W/910204 Ltr

ML18009A794
Person / Time
Site:	Harris
Issue date:	02/04/1991
From:	Richey R, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-910016-(O), LER-91-001, LER-91-1, NUDOCS 9102080132
Download: ML18009A794 (6)

Text

ACCELERATED Dg RIBUTION DEMONSTXTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9102080132 DOC.DATE: 91/02/04 NOTARIZED: NO DOCKET g FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co'.

RICHEY,R.B. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

'ER 90-001-00:on 910103,operations personnel identified procedural deficiency that resulted in check valves not D being tested as required.Caused by procedural deficiency.

Procedure revised to incorporate testing.W/910204 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR L TITLE: 50.73/50.9 Licensee Event Report (LER), IncidentJ Rpt, etc.

ENCL SIZE:

NOTES:Application for permit renewal filed. =05000400 COPIES RECIPIENT COPIES D'ECIPIENT ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-1 LA 1 1 PD2-1 PD 1 1 BECKER,D 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/LHFB11 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/SICB 7E 1 1 NRR T/.S.PLB8 D- 1 1 NRR/DST/SRXB 8E 1 1 REG' E 02 1 1 RES/DSIR/EIB 1 1 RG~N2

' - 1'LE=- 02 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1' NSIC MURPHYPG A 1 1 NUDOCS FULL TXT 1 1 D.

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! 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

0 Fl

Caroljna Power 8 Light Company P. O. Box 165 ~ New Hill, N. C. 27562 HARRIS NUCLEAR PROJECT R. B. RICHEY P. 0. Box 165 Vice President New Hill, NC 27562 Harris Nuclear Project FEB 0 419S1 Letter Number.'HO-910016 (0)

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 91-001-00 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.

Very truly yours, R. B. Richey Vice President Harris Nuclear Project RBR:gcm Enclosure cc: Mr. R. A. Becker (NRR)

Mr. S. D. Ebneter (NRC RII)

Mr. J. E. Tedrow (NRC SHNPP)

MEM/HO-9100160/1/OS1 9i02080i32 9i0204 PDR ADOCK 05000400 S &eh W

NRC FOAM 366 U.S. NUCLEAR AEGULATOAYCOMMISSION (64)9) APPROVED OMB NO. 31504)(04 EXPIAESI 4(30IS2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEOUESTI 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE AECORDS AND REPOATS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PRO3ECT (31500104). OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON. DC 20503.

FACILITYNAME (1) DOCKET NUMBER (2) PA E 3 Shearon Harris Nuclear Plant Unit I1 0 5 0 0 0 4 Q Q 1 OF P TITLE Ie)

Technical Specification violation due ta missed surveillance testing for Control Room EVENT DATE (SI LE R NUMBER (6) REPOR'r DATE (7) OTHER FACILITIES INVOLVED IS)

MONTH OAY YEAR YEAR SEDUENTIAL REVISION OAY FACILITYNAMES DOCKET NUMBERIS)

)sm NUMBER NUMBER MONTH YEAR 0 5 0 0 0 0 1 3 91 91 0 0 1 0 0 0 2 0 4 9 1 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REQUIREMENTS OF 10 CFR ()I ICnrck onr oi more ol tne Iollowingl (11 OPERATING MODE (6) 20A02(BI 20AOS(cl 50.73(ew2) (ivl 73.71(III POWER 20.405(e) (1)(il 60.36(c)(ll 50.73(IHEHvl 73.7((c)

LFvEL (10 I 1 P 20.406(e HI)(4) 60.35(c)(2 I 50.73(ew2)(v4) DTHER Isnrclty En Aostirct Below rsvd In Test, HRc Form 20.405( ~ HIHml 50.73(e) (2) (I) 50,73(r)(2HvBI)(AI 35(IAI E RIE EPPES. ~

20AOS(el(IH(vl 50.73(e)(2)(4) 50.73(el(2HvBI)ml

)IE 20.405 (e I (I H v) 50.734II2)(BI) 50.73(e) (2 H xl LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER Michael Verrilli, Specialist Reg. Compliance AREA CODE 9 19 362- 23 03 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRISEO IN THIS REPORT (13)

$~4)(y CAUSE SYSTEM COMPONENT MANUFAC. EPEETEEEE MANUFAC. EPORTABLE TURER E VEE SYSTEM COMPONENT TURER TO NPRDS SKM~S%. k%5%%

SUPPLEMENTAL REPORT EXPECTFD (14) MONTH DAY YEAR EXPECTED SUBMISSION YES IIIyrA coinPlrtr EXPECTED SVSEIISSIOH DA TEI DATE (15)

NO ABsTRAcT ILlmlt to 1400 sprees, I r., eppioslmrtrly Iiftern single sneer typewritten llnNI (16)

On I/3/91 the plant was operating in Mode-1 at 100 percent, power. During a procedure review of OST-1131 (Control Room Area HVAC System Inservice Test - punrterly Interval), Operations personnel identified a procedural deficiency that resulted in two check valves not being tested as required.

Inservice Inspection Test (ISI-203) implements the requirements of Technical Specification (TS)

Section 4,0,5, which in turn implements ASME Section XI testing. Check valves SICZ-15 and ICZ-16 are required to be full forward flow tested, per ISI-203, on a quarterly basis'uring the aforementioned review of OST-1131, it was revealed that the acceptance criteria of the procedure erraneously took credit for testing these check valves, but in actuality, did not conduct or document, an independent I rs forward flow test for these check valves.

The cause of this event was procedural deficiency. OST-1131 has never included steps to properly test these two check valves. This procedure was immediately revised to incorporate the required testing and was successfully performed on I/18/91 were no significant safety cansequences as a result of this procedural deficiency. This is

'here based on the following evidence that validates the functional status of these valves nnd the fact that the systems safety function hns never been challenged by radiological conditions. Forward flaw is tested through at least one of these check valves once per 18 months by the performance of OST-1231 (Control Room Emergency Filtration Operability Test) ~ This test hns consistently verified forward flow and wns last performed satisfactorily on 10/I/90. This provides n high degree of confidence that the valves would have functioned as designed if needed'his is being reported in accordance with IOCFR50.73 (a) (2) .(i) (8) as a TS violation.

NRC Fosin 366 (664)

NRC FOR)51 368A UN. NUCLEAR REGULATORY COMMISSION (84)9) APPROVED OMB NO. 31500104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT ILERI ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 600 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP4301. U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(500(04). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503, FACILITYNAME (ll DOCKET NUMBER 12)

LER NUMBER (6) PAGE (3)

Sg SEOVENTIAL REVISION Shearon Harris Nuclear Plant YEAR NUMSE R NUMSE R Unit I/1 o so o 04 00 9 1 0 0 1 00 02 OF 0 2 TEXT ///mfm fpff8 lf /88 uied. 848 ~/VRC lomI 3MAB/ ((2)

EVENI DESCR I PT I ON:

On I/3/91 the plant was operating in Mode-1 at 100 percent power. During a procedure review of OST-1131, Operations personnel identified a procedural deficiency that resulted in two check valves not being tested as required, Inservice Inspection Test (ISI-203) implements the requirements of TS Section 4.0.5, which in turn implements ASME Section XI testing. Check valves llCZ-15 and ICZ-16 are required to be full forward flow tested, per ISI-203, on a quarterly basis. During the aforementioned review of OST-1131, it was revealed that the acceptance criteria of the procedure did in fact take credit for testing these check valves, but i'n actuality, did not conduct or document an independent forward flow test for these check valves.

There has been one previous similar event, in regards to IST program/procedure deficiencies. This was submitted on LER 90-011, CAUSE:

The cause of this event is procedural deficiency, OST-1131 has never included steps to properly test these two check valves.

SAFETY S I GN IF I CANCE:

There were no significant safety consequences as a result of this procedural deficiency. This is based on the following evidence that validates the functional status of these valves and the fact that the systems safety function has never been challenged by radiological conditions. Forward flow is tested through at least one of these check valves once per 18 months by the performance of OST-1231 (Control Room Emergency f iltration Operability Test). This test has consistently verified forward flow and was last performed satisfactorily on 10/I/90. This provides a high degree of confidence that the valves would have functioned as designed if needed, CORRECT I VE ACTIONS:

1. EPT-I72 was specifically developed to perform a forward flow test for check valves ICZ-15 and ICZ-16 'his test was successfully completed on I/16/91 to verify system operability.

2. OST-1131 was revised to incorporate this testing and was performed satisfactorily on I/18/91 '

~ Operations procedure group will review this event to enhance their awareness of potential problems related to ISI program requirements contained in OST procedures.

4~ ISI personnel will perform a comprehensive procedure review to identify similar IST program problems, related to the testing of parallel flow through check valves E I SS CODE I tFORMATION:

N/A NRC Form 388A (889)