ML18004B944

LER 87-043-00:on 870820,discovered That Six Manual Isolation Valves Not Included in Operations Surveillance Test OST-1029.Caused by Personnel Error.Test Revised to Include Valves in Monthly Verification of position.W/870921 Ltr

ML18004B944
Person / Time
Site:	Harris
Issue date:	09/21/1987
From:	Schwabenbauer, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870498-(O), LER-87-043, LER-87-43, NUDOCS 8709280186
Download: ML18004B944 (7)

Text

REGULATO 'NFORMATION DISTRIBUTION STEM <BIDS)

ACCESSION NBR: 8709280186 DOC. DATE: 87/09/21 NOTARIZED: NO DOCKET

,.FACI~: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Poeer 5 Light Co.

WATSON'. A. Carolina Poeer ic Light Co.

REC IP. NAME REClPIENT AFFILIATION

SUBJECT:

LER 87-043-00: on 870820> discovered that six manual isolation valves not j,nc luded in Oper ations Surveillance Test OST-1029. Caused bg personnel error. Test r evised to include valves in monthly verification of position. W/870'F21 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ~ ENCL ~

SIZE:

TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpt etc.

NOTES: Application for permit reneeal Wi led. 05000400 REC IP IENT COP IES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BUCKLEYiB 1 INTERNAL: ACRS M ICHELSON 1 ACRS MOELLER 2 2 AEOD/DQA 1 AEOD/DSP/NAS AEOD/DSP/RQAB 2 2 AEOD/DSP/TPAB 1' DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEBT/ELB 1 NRR/DEST/ ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB NRR/DEST/PSB 1 NRR/DEBT/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 1 NRR/DQEA/E*B 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 NRR/ /SIB 1 1 NRR/PMAS/ ILRB 1 1 EG FIL 0& 1 1 RES DEPY GI 1 1 R ELFORDi J 1 RES/DE/EIB 1 RGN2 FILE 01 1 1 EXTERNAL: EG5G GROHi M 5 5 H ST LOBBY WARD LPDR 1 NRC PDR NSIC HARRIS' 1 NSIC MAYST G TOTAL NUMBER OF COP I ES REQUIRED: LTTR 44 ENCL 43

~ w NRC Fore 308 UA. NUCLEAR REGULATORY COMMISSION (943)

APPAOVED OMB NO. 31504104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITYNAME 0) DOCKKT NUMBER (2) PAQK 31 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 0 5 0 0 0 4 0 O 1.OFQ 4 SIX OUTSIDE CONTAINMENT. ISOLATION VALVES WERE OMITTED FROM MONTHLY POSITION C ECK DUE TO PERSONNEL ERROR IN PROCEDURE DEVELOPMENT.

KVKNT DATE (5) LEA NUMBFR (6) REPORT DATE (7) OTHER FACILITIES INVOI.VED (S) ~

MONTH DAY YEAR YEAR ggj SEQUENTIAL

'VMSKR 46 gYg'. REVISION NVMSKR MONTH OAY YEAR FACILITYNAMES DOCKtT NUMBEA(S) 0 5 0 0 0 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CF R g: (Check one or more of the follorflnFI (11)

OPEAATINO MODE (9) 20A02(b) 20A05(e) 50,73(e)(2) lirl 73.71(bl POWER 20A05( ~ ) (1)(il 5048(cl(1) 50.73(el(2) lrl 73.71(cl LEVEL (10) 20A05(e)(I)(ii) 50.38(c) l2) 50.73(e) (2) (rii) OTHKR (Specify In Ahttrect heforr end ln Text, IIRC Form

. 20A05( ~ )(1)(iii) 50.73(e) (2) li) 50.73(e) (2) (xiii)(A) 3ESAJ 20A05(c ) (I ) (Ir) 50.73(e) 121(ill 50,73(e)(2)(rid)(B) 20AOS(c)(I)(r) 50.73(el(2) Ail) 50.73(e) (2)(xl LICENSEE CONTACT FOR THIS LEA (12)

NAME TELEPHONE NUMBER AREa COOP.

D HW N REGULATORY COMPLIANCE COMPLETE ONE LINE FOR tACH COMPONENT FAILUAE DESCRIBEO IN THIS REPORT (13) 62 -2 rrscco CAUSE SYSTEM COMPONENT MANUFAC EPORTABLE '~ig+) ' 'O CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE A TURKR NPROS 16 r TURER TO NPRDS r>. r.

~ SUPPLEMENTAL REPORT KXPECTED (IC) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)

YEs Ilfyet, complete ExpEcTED sUshtlssloff DA TEI AdsTRAcT ILlmlt to Ie00 tpecet, I e., epproxlmeteiy fllteen tlnoleepece typewrinen llneel 118)

ABSTRACT The plant was operating at 100 percent reactor power in Mode 1, Power Operation, on August 20, 1987. During a review of containment isolation valves, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> that six manual isolation valves were not included in Operations it was discovered Surveillance Test (OST)-1029, Containment Penetration Outside Isolation Valve Verification, as required. OST-1029 ',satisfies. Technical Specifications item 4.6.l.l.a for a 31-day verification that the valves are closed and locked.

'll Upon'iscovery, six a check of the six isolation valves was made and valves were closed and locked as required. There is no indication that any of the valves have been opened since they were placed in their proper closed it was found that position prior to initial criticality of the plant.

The cause of the event was personnel error in omitting the six isolation valves from OST-1029 for verification of their locked closed position as required.

The immediate corrective action upon discovery was to verify that the six valves were in the closed and locked position as required, which they were.

Action to prevent recurrence is that OST-1029 has been revised to include these six valves in the monthly verification of position.

This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action item 4.6.1.1.a.

NRC Form Sdd 870'7)280 l 86 870%1 PDR ADOCK 0S000O00 rl

'r/

RC For)SISSSA U.S. NUCLEAR RECULATORY COMMISSION (94)3) 4 LICENSEE EV REPORT (LER) TEXT CONTINUATI APPROVEO OMS NO. 3(50M(04 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (3) PACE (3)

LER NUMBER (8)

YEAR SaavaNTIAL ASVISION

@g NUMaaR NVMSSR SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 "o s o o o 4 00 87 0 0 0 020F0 TEXT /1/'mora 4/>>cv /4 vr/Vtrad, v44 add/dor>>/NRC Form 35543/ (13)

The plant was operating in Mode 1, Power Operation, at 100 percent reactor power on August 20, 1987. 'lant personnel were implementing a program to identify and tag containment isolation valves [see LER-87-014-00 corrective action no. (1)j. This program involved a review of procedures, drawings, and a plant walkdown. During the review, it was discovered that the following six manual isolation valves were not included in Operations Surveillance Test (OST)"1029, Containment Penetration Outside Isolation Valve Verification, as required.

1FP-355: Fire Protection water supply to containment. (EIIS:KP) 1DW-63: Demineralized water supply to containment. (EIIS:KC) 1SI-302 and 1SI-304: Drain valves off of the safety injection recirculation sump valve chambers. (EIIS:BP) 1CT-103 and 1CT-106: Drain valves off of the containment spray recirculation sump valve chambers. (EIIS:BE)

OST-1029 satisfies Technical Specifications item 4.6.1.1.a for a 31-day verification that the valves are closed and locked.

Upon discovery that the six valves were missing from OST-1029's monthly position check, operations personnel immediately verified that the valves were in the closed and locked position as required. There is no indication that any of the valves have been opened since they were placed in their proper closed position prior to initial criticality of the plant.

Plant conditions during and following this event was 100 percent reactor power in Mode 1, Power Operation.

OST-1029 has been revised to include the six valves which were omitted from the procedure.

NRC FORM 348A *U.S.OPO: I 988.0.834 538/455

NRC FosiyrXSA s U.S. NUCLEAR REQULATORY COMMISSION (94)3) a LICENSEE EYIO REPORT ILER) TEXT CONTINUATI APPROVEO OMS NO. 3150&)04 EXPIRES: 8/31/88 FACIUTY NAME (1) COCKET NUMBER (3) LER NUMBER (6) PACE (3)

YEAR I': SEOVENTIAL "g>>

NVMSER REVISION NUMSER SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1.

oo s7 043 0 0 0 30F 0 4 TEXT ///mead 4Pddd 1I /sdv)dd, I/w a/s//I/dsas////I C hmi 3584'4/ (IT)

Cause:

The reason for the errors in the procedure was investigated. The results of that investigation are as follows'.-

1) 1FP-355 " In the original design, this valve had an air operator and was closed by a phase A isolation signal. The actuator was deleted by a subsequent change that was not reflected in the flow drawings until the spring of 19S7. Thus, the valve was not included in the early drafts of the procedure.

2) 1DW-63 " In the initial draft of the procedure, this valve was included but with the incorrect "noun name". It was listed as "Primary Water Supply" vice the real title of "Demineralized Water Makeup". Since Primary Water Supply is not a containment isolation valve, 1DW-63 was deleted from the procedure.

3) 1SI-302, 1SI-304, 1CT-103, 1CT"106 The initial draft of the procedure did not include these valve chamber drain valves. The investigation concluded that these valves were omitted because they do not connect directly to containment.

In each case listed, the system valve lineup checklist which is separate from OST-1029 put the valves in the required locked closed position.

The root cause of the event is personnel error in omitting the valves in the monthly surveillance test to check their position.

~anal sis:

Operation of plant components and systems and the health of the general public were unaffected by this event as the valves were in their proper position when checked'.

In the case of 1FP-355 and 1DW-63 additional check valves are in series to provide redundant containment isolation capability. Had the valves 'been open during accident 'conditions, the potential for additional containment releases to the Reactor Auxiliary Building is minimized.

In the case of the valve chamber drain valves, a chamber does not communicate directly with the containment. The valve chamber serves to collect and isolate potential leakage from the containment sump isolation valves and from the pipe penetration to the containment sump. If these valves were left open the leakage would be released into the Reactor Auxiliary Building drains or leak-off holdup tanks.

Releases into the Reactor Auxiliary Building would either be monitored by area radiation monitors andlor the Plant Vent Stack radiation monitors.

This event is reportable in accordance with 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action Item 4.6.1.1.a.

There have not been any similar events reported of this nature.

NRC FORM SOdA *U.S.QPO:1988 0 834 538/455

RC For)drSSBA U.S. NUCLEAR REGULATORY COMMISSION (34)3)

'ICENSEE'EVIO REPORT (LER) TEXT CONTINUATI APPROVEO OMS NO. 3150-0104 EXPIRES: 8/31/88 FACIUTY NAME (1) DOCKET NUMSER l21 LER NUMBER (6) PAOE (3)

YEAR SEOUENTIAL REVISION SHEARON HARRIS NUCLEAR POWER PLANT NUMSER '.Ir r NUMSER UNIT 1 TEXT /((more 4/reoe /4 /lr/rer/ Iree ////oee/HRC Ferrrr 3//543/ (17) 0 5 0 0 0 4 0 0 8 7 043 0 0 0 4 OF 0 4 Corrective Action:

The valves were checked and verified to be in their proper position upon discovery that they were omitted from OST-1029.

Action to Prevent Recurrence:

l. OST-1029 has been revised to include the six valves in the monthly surveillance test to check their position, and has been performed.

2. A review of drawings for all systems with fluid* penetrations into the containment building was done to verify that OST-1029 is complete and has no additional errors.

'NRC FORM SSSA *U.S.GPO:1988 0-824 538/45S

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Carolina Power 5 Light Company (ggse~> ~

HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 SEP2 I lg87 File Number,'HF/10-13510C Letter Number: HO-870498 (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 87-043-00 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. A. Watson Vice President Harris Nuclear Project RAW:acm Enclosure cc'. Dr. J. Nelson Grace (NRC RII)

Mr. B. Buckley (NRR)

Mr. G. Maxwell (NRC SHNPP)

MEM/LER-87-043/1/OS1