ML17219A676

LER 87-012-00:on 870609,discovered That Component Cooling Water 1a & 1b HX Outlet cross-tie Valves Were in Open Position.Caused by Personnel Error.Valves closed.W/870709 Ltr

ML17219A676
Person / Time
Site:	Saint Lucie
Issue date:	07/09/1987
From:	Mendoza V, Woody C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-87-284, LER-87-012-01, LER-87-12-1, NUDOCS 8707150631
Download: ML17219A676 (6)

Text

REGULA INFORMATION DISTRIBUTIO YSTEM <RIDS)

ACCESSION NBR:8707150631 DOC. DATE: 87/07/09 NOTARIZED: NQ DOCKET FACIL 50 335 St. Lucie Planti Unit ii Florida Power 5 Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION MENDOZAi V. N. Flor ida Poeer ~~ Light Co.

WOODYi C. O. Florida Poeer 5 Light Co.

REC IP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-012-00: on 870609' i s c over e d that component cooling eater ia 8. ib HX outlet cross-tie valves mere in open position. Caused bg personnel error. Valves closed. W/870709 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE:

'ITLE: 50;73 Licensee Event Report <LER)i Incident Rpti etc.

NOTES RECIPIENT COPIES RECIPIENT COPIES

,ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD TOUR IGNYi E 1 1 INTERNAL: ACRS M I CHELSON 1 ACRS MQELLER 2 2 AEOD/DQA 1 1 AEOD/DSP/RQAB 2 2

• EOD/DSP/TPAB 1' DEDRO 1 1 NRR/DEST/ADE 0 NRR/DEBT/ADS 0 NRR/DEBT/CEB 1 NRR/DEBT/ELB NRR/DEST/ICSB 1 1 NRR/DEST/MEB 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 NRR/DEST/SGB 1 "NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 1' NRR/DOEA/EAB 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 - PM*S-/- RB 1 1 NRR/PMAS/PTSB 1 1 REG FI 02 1 RES DEPY GI 1 RES TELFORDi J RES/DE/EIB 1 1 RGN2 FILE 01 EXTERNAL: EG~~.G GRQHi M 5 5 H ST LOBBY WARD 1 LPDR NRC PDR 1 NSIC HARRIS' 1 NSIC MAYSz G 1 -1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 42

NRC Form 366 (9-8 3 I U.S. NUCLEAR RECULATORY COMMISSION APPROVED OMB NO. 3150-0101 LICENSEE EVENT REPORT (LER) EXPIRES; 8/31/88 FACILITY NAME (II DOCKET NUMBER )2) I'AOE St. Lucie Unit 5tl 0 3 35 10FO 3 LOSS OF COMPONENT COOLING WATER REDUNDANCY BECAUSE OF CROSSTIE VALVES BEING IN THE PEN POSITION DUE TO PERSONNEL ERROR.

EVENT DATE(5) LFR NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (BI MONTH OAY YEAR YEAR rrpr4'EOUENTIAL agan REY~~ MONT~ OAY FACILITY NAMES DOCKET NVMBERISI 6 NUMBER Sprn NUMBER YEAR 0 5 0 0 0 0 6 0 9 8 7 8 7 012 00 07 0 9 8 7 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT 7 0 THE REQUIREMENTS oF 10 cFR (Ir (cntcir ont or mort of rnt folfowfno) (Ill MODE (8) 20.802(b) 20.605(cl 60.73(v)(2((w) 73.7 I (III POWER 20.805 ( ~ l(1) I I) 50.36(c) III 60.73(s) (2)(vl 73.71(cl LEvEL 1 0 0 20.405 ( ~ ) (1) (ll) 50.38(c)(2) 50.734) (2l(villi(BI (2)(vill OTHER ISptCify in AOrrrtCI Otiow tnd In Tt>> NRC Form 20.406( ~ )ill(IIU 60.73( ~ l(2) ll) 60.73(s) (2 l(villi(A) 366A) 20 COS( ~ ) (1)(lv) 60,73(s)(2) (8) 50.73(s) 20.805( ~ I (1)(vl 50.73( ~ ) (2)(ill) 60.73( ~ ) (2) (c I LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE Victor N. Mendoza, Shift Technical Advisor COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOR'T (13) 305 465 -355 0 CAUSE SYSTEM COMPONENT MANUFAC. REPORTABLE MANUFAC.

TVRER TO NPRDS CAVSE SYSTEM COMPONENT TURER

QL '4 C.rsrn4pyn .b>n tfnolt.rptct ryptwrirrtn Iin>>I (16)

On June 19, 1987, St. Lucie Unit 81 was in Mode 1, 100% power, and at steady state conditions. All control stations were in normal operating mode. At 0124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br />, the Reactor Control Operator (RCO) was performing a monthly pump surveillance run for the 1B component cooling water (CCW) pump. During this surveillance run, it was discovered that the lA and 1B CCW'eat exchanger outlet cross-tie valves were in the open position. The normal position for these valves is closed. The operator immediately performed a valve alignment verification and closed the valves. The root, cause of the event was a cognitive personnel error by utility licensed operators who failed to have proper administrative control on these valves. The immediate corrective action was to close the valves. The event was terminated at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />.

No other system malfunction resulted from this event. Thi:s event is reportable under the Code of Federal Regulations 10 CFR 50.73 (a) (2) (i) (B), "Any event or condition prohibited by plant's Technical Specifications."

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PDR ADOCg 3i 87p7p9 S PgPPP3 PDp NRC Form 366 (9831

NRC Form 388A U.S. NUCLEAR REOULATORY COMMISSION (943)

LICENSEE EVENT REPORT HLER) TEXT CONTINUATION APPROVED OMB NO. 3)9)WIOE EXPIRES: 8/31/88 FACILITY NAME u) DOCKET NUMBER Il) LER NUMBER (8) PACE (3)

YEAR . /8 SEOUENTIAL REVISION

M'UMBER ~WI~S NUMSEII St. Lucie Unit 8'1 3 3 5 8 7 0 1 2 0 0 02 OF 0 3 TEXT ///moro e/Nce /e rer/vired, ore eddr)/orre/iVRC Form 36549) (17)

DESCRIPTION Op EVENT On state June conditions. 't 19, 1987, St. Lucie Unit 81 was 0124 hours, in Mode 1, 100% power, and at steady the Reactor Control Operator (RCO) was performing a monthly pump surveillance run for the 1B component cooling water (CCW) (EIIS:CC) pump. The 1B CCW pump discharge valve was throttled to obtain 4000 CPM flow on the "B" header, as required by the procedure. As the valve was throttled, the RCO noticed that the "A" header flow was also decreasing concurrent with the "B" header. The RCO notified the Assistant Nuclear Plant Supervisor (ANPS) and the ANPS immediately instructed the Nuclear Operator to perform a valve alignment verification. During this verification, it was discovered that the lA and 1B CCW heat exchanger outlet cross"tie valves V-14169 (which is a normally locked closed valve) and V-14439 (which is a normally closed valve) were in the open position. Both valves were then immediately closed and independently verified to be closed. The normal CCW valve alignment was restored to its normal operations line-up. The pump surveillance run was then resumed and noted as satisfactory. No 'other abnormalities in the system were noted after the restoration of the CCW system valve alignment. The event was terminated at 0130 on June 19, 1987. No other system malfunctions were observed during the entire event.

CAUSE OP EVENT On June 8, 1987, the 1B CCW heat exchanger was scheduled, for repairs. A clearance was issued for all valves and related equipment required to isolate the 1B CCW heat exchanger. The cross-tie valves V-14169 (which is normally locked closed) and V-14439 (which is normally closed) were opened to allow both the "A" and "B" trains of the CCW system (EIIS:CC) to be in service while the 1B CCW heat exchanger was being repaired. Neither of the cross-tie valves were li'sted on the clearance. The utility licensed operator in charge of reviewing the clearance prior to issuance decided not to include these valves in the clearance as these valves were not required for maintenance boundary isolation. He opted to administratively control valve V-14169 by listing this valve in the locked valve deviation log as being in the open position. However, the locked valve deviation log was not reviewed by operations personnel. Thus, V"14169 and V"14439 were not in their normal closed positions.

it was not noted in the clearance that valves After the repairs to the heat exchanger were completed on June 9, 1987, all the valves and related equipment on the clearance were released and independently verified as being restored to the required operating positions.. Since valves V-14169 and V-14439 were not listed on the clearance, they were not restored to their normal position as part of the clearance release process, nor was independent verification called for.

NRC FORM seeA (943)

NRC Ftrrm 3BBA U.S. NUCLEAR REOULATORY COMMISSION (943)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS NO. 3(50-0104 EXPIRES: 9/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) PACE (3)

YEAR ~ SEOUENTIAL +ZAN REVISION NUMBER ':Rd NUMBER St. Lucie Unit fP1 o so oo335 87 0 12 0 0 03 OF 0 3 TEXT ///mote t/>>toit rer/u/red, ute eddie'or>>///RC Form 3SS/I'/(17)

The root cause of the event was cognitive personnel error by utility licensed operators who failed to have proper administrative control on valves that were positioned in other than their normal operating positions. There were no procedure deficiencies 'or unusual characteristics of the work location that directly contributed to this event.

ANALYSIS OP EVENT The event is reportable under 10 CFR 50.73 (a) (2) (i) (B), "Any event or condition prohibited by the plant's Technical Specifications." Technical Specification 3.7'.3.1 requires "at least two independent component cooling water loops, shall be operable."

This event resulted in a loss of component cooling system (EIIS:CC) redundance.

However, the loss of redundancy was discovered within 10 days during performance of a routine monthly surveillance. Redundancy was completely restored within six (6) minutes of discovery. There were no other abnormalities in the system during the event. All plant safety functions were met throughout this event. At no time during this event was the health and safety of the public endangered.

CORRECTIVE ACTIONS

1. Valve V-14169 was restored to its locked closed position and valve V-14439 was closed. Independent verification of valve proper position was performed.

2. The plant training group will evaluate this item to determine appropriate training requirements and methods.

3. The responsible supervisor has been instructed to include these valves in future clearances to ensure restoration. 1 ADDITIONAL-INFORMATION Failed component identifications There were no failed components during this event.

PREVIOUS SIMILAR EVENT See LER 8335-85-02 for a previous valve mispositioning event.

NRC FORM 3BBA (M3)

P. O. B ~ 14000, JUNO BEACH, FL 3340B 0420 JULY u ISUI L-87-284 U.S. Nuclear Regulatory Commission Attn:. Document Control Desk Washington, D.C. 20555 Gent I emen:

Re: St. Lucie Unit No. I Docket No. 50-335 Reportable Event: 87-12 Date of Event: June 9, 1987 Loss of Com onent Coolin Water S stem Redundanc The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.

Very truly yours, Nuclear Energy COW/GRM/cn cc:. Dr. J. Nelson Grace, Regional Administrator, Region ll, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant p$

PEOPLE... SERVING PEOPLE GR M5/061/ I

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