ML18004B809

LER 87-023-00:on 870420,alternate Miniflow Valves for Charging Safety Injection Pump Found Isolated.Verification of Correct Valve Lineup Unavailable.Caused by Personnel Error.Procedure OP-107 Being revised.W/870520 Ltr

ML18004B809
Person / Time
Site:	Harris
Issue date:	05/20/1987
From:	Schwabenbauer, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HLWR, HO-870433-(O), LER-87-023, LER-87-23, NUDOCS 8705280348
Download: ML18004B809 (7)

Text

REG TORY INFORMATION DISTRIB N SYSTEM (RIDS)

ACCESSION NBR: 8705280348 DQC. DATE: 87/05/20 NOTARIZED: NO DOCKET ¹ g'*CIL:50-400 Shearon Harris Nuclear Poser Plant> Unit 1> Carolina 05000400 AUTH. NAME. AUTHOR AFF I LIAT I QN SCHNABENBAUER Carolina Power 8r Ligh+ Co.

NATSQN> R. A. Carolina Power 5 Ligh+ Co.

REC IP. NAME RECIPIENT AFFILIATION SUB JECT: LER 87-023-00: on 870420> alternate mini flow valves f or charging safety inJection pump found isolated. Verif ication of correct valve lineup unavailable. Cause unknown. Procedure OP-107 will be revised. N/870520 ltr.

DISTRIBUTION CODE: IEEBD COPIES RECEIVED: LTR Q TITLE: 50. 73 Licensee Event Report (LFR) Incident Rpt> etc.

ENCL g SIIE:

NOTES: Ap pl 1 cation for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL p D2-1 LA 1 PD2-1 PD 1 1 BUCKLEY B 1 1 INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 2 AEQD/DOA 1 AEQD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 DEDRQ 1 1 NRR/DEBT/ADE 1 0 h!RR/DEST/ADS 1 0 NRR/DEBT/CEB 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 h!RR/DEST/MEB 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1' NRR/DEBT/RSB } 1 NRR/DEBT/SQB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 / ILRB 1 1 NRR/PMAS/PTSB 1 1 REG FI 02 1 1 RES DEPY GI 1 1 RGN2 FILE 01 1 1 EXTERNAL: EQM GROH M 5 5 H ST LOBBY NARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS> J 1 NSIC MAYS> G 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTl R 42 ENCL 40

x~

e

~

~ 'ls NRC Form 300 U3. NUCLEAR REOULATORY COMMISSION 1943) APPROVED OMB NO. 31500104 EXPIRES. 8/31/88 LICENSEE EVENT REPORT (LER)

FACILITY NAME (I) DOCKET NUMBER (2) PA E 3 SHEARON HARRIS PLANT TITLE ( ~ I UNIT 1 050004001OF03 ISOLATED MINIFLOW PATH FOR CSIP 1C-SAB EVENT DATE (6) LER NUMBER (6) REPORT DATE (7I OTHER FACILITIES INVOLVED LS)

MONTH OAY YEAR YEAR P~.'SEQUENTIAL MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S)

NUMBER 0 5 0 0 0 0 4 2 8 7 8 7 023 0 0 0 5 2 0 8 7 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR (I: (Check One or more of the foQovp'nPI l11)

OPE RATING MODE (8) ] 20.402(b) 20.405(c) 50.73(e) (2) (Ivl 73.71(Q)

POWER 20.405( ~ ) (1)BI 6030(cl(1) 50.73(e) (2)(v) 73.71(cl LEYEL 0 9 0 20.405(s) (I ) (Q I 50.30(c) l2) 60.73(e) l2)(vQ) OTHER ISpeclfy In Atrstrect helosv end In Text, NIIC Form 20.405( ~ I(1)(QII 50.73(e) (2)(I) 60.73(e)(2) ( vQI) (A) 38841 20.406(e)(1) (N) 50.73(sl(2) (QI 50.73(s) (2) (vIQ) (8 I 20.406(el(1) lv) 50.73(e)(2) (QI) 60.73(s) (2) I x)

LICENSEE CONTACT FOR THIS LER 02I NAME TELEPHONE NUMBER AREA CODE RICHARD SCHIJABENBAUER REGULATORY COMPLIANCE 919 362 -2 669 COMPLETE ONE LINF FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE 61.

SYSTEM COMPONENT MANUFAC. F PORTA 8 LE 5 TURER TO NPRDS TURER v

eel N..e?r.I'e2 +? PsrL I 6

tFAfÃ4 MONTH OAY xv YEAR SUPPLFMENTAL REPORT EXPECTED l14)

EXPECTED SUBMISSION DATE (ISI YES Ilfyes, complete EXPECTED SVShrISSION OA TSI X ABSTRACT ILlmlr ro f400 rpsces, I e., epproxlmetely fllreen slnple specs rypevrrltNn Ilnnl (16)

On April 20, 1987 the plant was operating at 90 percent reactor power. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> the alternate miniflow valves for 1C-SAB Charging Safety Injection Pump (CSIP) were found to be isolated. This flow path is required to be operable in accordance with FSAR table 6.3.2-8. 1C-SAB CSIP was placed in service on February 21, 1987 in place of 1B-SB CSIP. 1C-SAB CSIP was placed in service, at the time, in accordance with OP-107, Chemical and Volume Control System, which gives the required valve line up. However, it cannot be verified if the lineup was performed or if the valves were subsequently mispositioned.

Upon discovery of the misaligned valves, a new valve lineup was immediately initiated and was successfully completed at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> in accordance with OP-107 and PLP-702, "Independent Verification". OP-107 is being revised to include attachments which will be completed, signed, and verified when placing a CSIP in service to ensure valve line up is correct.

870528 0348 870520 ADO ( ~ 05000400 PDR PDR S

NRC Form 300 (9 83)

US. NUCLEAR REGULATORY COMMISSION (94)3)

LIC EE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3)50M)04 EXPIRES'I 8/31/88 f ~ FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

SEOVENTIAL REVSION YEAR mp

'...4 Shearon Harris Plant Unit 1 NUMBER NUMBER 0 5 0 0 0 OF TEXT //ma/e <<>>I>> /4/EEMEEd, I>>4 /I/&b/I/>>/ A'RC F//ml 3/)//4'4/ (IT)

DESCRIPTION:

On April 20, 1987 the plant was operating at 90 percent reactor power. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> the alternate miniflow valves for 1C-SAB Charging Safety Injection Pump (CSIP) were found to be isolated. The as found positions of the valves were 1CS-749-shut, 1CS-750-partially open, and 1CS-751-open. The correct valve positions are 1CS-749-open, 1CS-750-open, and 1CS-751-closed, when 1C-SAB CSIP is in use in place of 1B-SB CSIP. The flow path is required to be operable in accordance with FSAR table 6.3.2-8. 1C-SAB CSIP was declared operable on February 21, 1987 in place of 1B-SB CSIP.

The incorrect lineup isolated the pump discharge from the miniflow path to the RWST. (The 1A-.SA pump was not affected by this lineup error.)

1C-SAB CSIP was placed in service in accordance with OP-107, Chemical and Volume Control System, Section 8.17, which states the required valve positioning. However, a PLP-702, Independent Verification, form cannot be located to verify the proper valve positioning at the time 1C-SAB CSIP was placed in service. OP-107 does not contain a signoff list for this evolution',

the forms and instructions of PLP-702 are used to obtain this documentation.

Upon discovery of the mispositioned valves, a new valve lineup was initiated and successfully completed at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> in accordance with OP-107 and PLP-702.

CAUSE'he event was caused by personnel error. Either the valves were not properly positioned when the pump was placed into service or were mispositioned later by persons unknown. Procedural requirements were not met when the 1C-SAB CSIP was placed in service in that the valve lineup verification sheet was not completed and filed or was later lost.

ANALYSIS:

1A-SA CSIP was operable and properly aligned throughout the entire period.

The 1C-SAB CSIP was capable of normal operation and capable of starting on a Safety Injection Signal throughout the time frame the alternate miniflow valves were improperly positioned.

NRC FORM SEEA ~ *U.S.GPO:1986 D624 538/455 (94)31

U.S. NUCLEAR REGULATORY COMMISSION RC FEEm 358A (94)31 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150-0)04 EXPIRES: 8/31/88 FACILITY NAME Ill DOCKET NUMBER (2) LE R NUMBE R (5) PACE (3)

YEAR SEOUENTIAL REVISION NUMSER NUMBER Shearon Harris Plant Unit 1 00 S7 023 0 0 0 OF TEXT 9'm4/E Ep404 /4 nq/m/f, IIw ~HRC Ann 3554'4) (17)

ANALYSIS (continued)

The motor operated alternate miniflow isolation valves open on a SI Signal and place two relief valves in service (refer to FSAR Figure 9.3.4-2 and -3). The relief valves lift at 2500 psia to provide recirculation flow for the CSIP.

The alternate miniflow system provides protection only during certain steam line or feedwater line breaks. It was determined by Westinghouse that for these breaks, the potential exists to have the RCS pressure increase to the point where the CSIP would be dead headed prior to Safety Injection termination. Prior to SI termination, the CSIP's normal miniflow path would be isolated and the alternate miniflow system was designed to prevent pump damage during this scenario. The design basis for the alternate miniflow assumes that the Pressurizer PORV's do not function because they are not safety related.

CORRECTIVE ACTION:

Procedure OP-107 is being revised to include a valve line-up for the alternate mini-flow which will have to be completed, signed, and verified when placing a CSIP into service.

>NRC EORM 3O)A *U,S.OPO;1 988 0 524.538/455 194)3)

CÃC L Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 NAY 2 0 1987 File Number'. SHF/10-13510C Letter Number.'O-870433 (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 87-023-00 Gentlemen.'n 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 with thirty (30) days of a reportable occurrence and is in accordance the format set forth in NUREG-1022, September, 1983.

Very truly yours, rz~~-

R. A. Watson Vice President Harris Nuclear Project RAW:bjb Enclosure cc: Dr. J. Nelson Grace (NRC RII)

Mr. B. Buckley (NRR)

Mr. G. Maxwell (NRC SHNPP)

MEM/HO-8704330/Page 1/OSl

l