ML20043H264

LER 90-011-00:on 900521,noted That Valve 1RN-69A Auxiliary Feedwater Assured Supply from Train a Nuclear Svc Water Repositioned to Open Position After Start of Pump.Cause Unknown.Pump Shut Down & Valve closed.W/900620 Ltr

ML20043H264
Person / Time
Site:	McGuire
Issue date:	06/20/1990
From:	Mcconnell T, Sipe A DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-011-01, LER-90-11-1, NUDOCS 9006220331
Download: ML20043H264 (7)

Text

- - -

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. DukeIbugr Company MEIS#

• McGuirrNuclearStation

.,_' 12700 flagers ferry Road, flunterwille, NC28078-8985 DUKE POWER June 20, 1990 I

-U.S. Nuclear. Regulatory Commission '

Document Control Desk Washington, D.C. 20555 '

Subject- McGuire Nuclear Station Unit 1 Docket No. 50-369 ,

Licensee Event Report . 369/90-11 '

y Gentlemen:

Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report'369/90-11 concerning a partial engineered safoty feature actuation which occurred because of unknown reasons. -This report is being submitted in accordance with 10 CFR'50.73(a)(2)(iv). This event is considered to be of no significance with respect to the health and safety of the public.

Very truly yours,

[T.L.

.2. n%,Q cConnell' DVE/ADJ/cbl Attachment l

^

xc: Mr. S.D. Ebneter American Nuclear Insureri Administrator, Region II c/o Dottie Sherman, ANI Library U.S. Nuclear Regulatory Commission The Exchange, Suit 245 i 101 Marietta St., NW, Suite 2900 270 Fr.rmington Avenue Atlanta, GA' 30323 l Farmington, CT 06032

-INPO' Records Center Mr. Darl Hood Suite 1500- U.S. Nuclear Regulatory Commission 1100_ Circle 75 Parkway l 0ff!ce of Nuclear Reactor Regulation 1

-Atlanta, GA 30339 Washington, D.C. 20555 l

M&M Nuclear Consultants Mr. P.K. Van Doorn i

.1221 Avenue of the Americas NRC Resident Inspector i New York, NY 10020' McGuire Nuclear Station 1

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i LER 369/90-11' l -: P:312 _ , .

I June,20, 1990 ibxc: B.W. Bline

-L.G.'Bost' J.S. Warren R.L. Gill C.L. Hartzell (CNS)

'R.S.:Matheson (ONS)

P.R. Herran-

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S.S. Kilborn (}{}

R.E. Lopez-Ibanez M.A.LMullen ~

R.O.'Sharpe (MNS)

G.B. Swindlehurst K.D. Thomas. '

M.S. Tuckman L.E. Weaver R.L.' Weber  !

'J.D. Wylie (PSD)

J.W. Willis ,

QA Tech. Services NRC Coordinator (EC 12/55)

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.e; . LICENSEE EVENT REPORT (LER) ' * a' * 8" PACILITY seatet til DOCKST NUM0th (2) PAGE (21 McGuire Nuclear Station, Unit 1 o is ;o lo lol 3l6 l 9 ijoFl l5 A Partial Engineered Safety Feature Actuation Occurred When A Valve Repositioned To The Open Position Because Of Unknown Reasons IVONT DAf t (S) LtR NUMBER ($1 - REPOsti DAf t 17) OTMER F ACILITill INVOLVED tel  ;

MONTM DAY YEAR YEAR k (A ' [y",[ MONTH DAY ylgR # Acatif v h Awls DOCKE T NUMetRts N/A ol5l0l0lo; i l Oj5 90 - -

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opt MTM THIS REPORY In SueMITit0 puR$UANT TO THE R40VIRtMENTS OF 10 CFR I ICheca eae e, seiere of the f n**'af f Illi g

M001 m 30 402(b) TO 406tel X to 73taH2 Hee 73 711tl

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Alan Sipe, Chairman, McGuire Safety Review Group 7;0l4 8; 7 i Si 4 l 8l3 i i i i COMPLETE ONE LINE FOR E ACM COMPONENT F AILUnt DESCRitt0 IN TMiB REPORT 113)

At ORTA Lt CAU$t SYST E M COMPONENT "(hC. p CAU68 $YSTEM COMPON E NT YNC- R{0m,Tagg hq d

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"} Yts u,,... <en.. exPucreo svowssion ca rri T NO l l l test R ACT m-, M e m ,,-., , . . .. *, a,. . . .,,,,,,. .. , o .i On May 21, 1990, Performance personnel were preparing to perform periodic test' PT/1/A/4252/14, Turbine Driven CA System Flow Balance. Operations personnel i

, started Turbine Driven. Auxiliary Feedwater Pump Number 1 using procedure OP/1/A/6250/02, Auxiliary Feedwater System, at approximately 0107. Operations and Performance personnel noted that valve IRN-69A, Auxiliary Feedwater Assured Supply from Train A Nuclear Service Water, repositioned to the open position 3

within seconds of the pump start. Operations personnel shutdown the pump and l closed valve IRN-69A. Performance verified that test equipment connections were

l. correct. Instrumentation and Electrical personnel troubleshot associated l instrumentation. No equipment and instrumentation problems were. identified. No low suction pressure conditions were identified by Operations personnel, Performance personnel, or asscciated instrumentation and alarms. Turbine Driven Auxiliary Feedwater Pump Lunber 1 was restarted with no unanticipated valve i movements. The Turbine Driven Auxiliary Feedwater flow balance test was successfully completed at 0416. This event is assigned a cause of unknown l because no definite or probable cause could be determined. Unit I was in Mode 1 I

(Power Operation) at 20 percent power. No Nuclear Service Water (raw lake water) was introduced into the Auxiliary Feedwater system or Steam Generators because no other valvec repositioned.

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EXPIRt$. S'31/5 F ACILITY =AMG tu oOCKET NUM0th (31 LER NUMSIR (Si Pant (3) i VEAR st i,a t a ,isy

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-l EVALUATION:

Background-The Auxiliary Feedwater (CA) system [EIIS:BA) assures a feedwater supply to the Steam Generators (S/G) [EIIS:SG) for decay heat removal if the Condensate (CM) system [EIIS:KA] and Feedwater (CF) system [EIIS:SJ) are not available through loss of power or other malfunctions. The CA system is provided with two 100 percent capacity motor (EIIS:MO) driven pumps [EIIS:P) and one 200 percent capacity turbine [EIIS:TRB) driven (TDCA)-pump. The TDCA pump supplies water to i all four S/Os. j The CA system suction supply has four sources. These sources are: Auxiliary l Feedwater Condensate Storage Tank [EIIS:TK), Upper Surge Tank (UST), Condenser

[EIIS: CON) Hotwell, and Nuclear Service Water (RN) system [EIIS:BI]. l l

The RN system provides the nuclear safety related assured CA system suction j source. This suction source is available to the Turbine Driven CA Pump by three j independent flow paths. Each flow path is isolated by an in-series CA valve and  ;

RN valve. Each of these isolation valves are associated with-a dedicated '

pressure switch (s) [EIIS:PS). See figure 1 page 5 of 5 for component one line  ;

diagram. The assured suction isolation valves are designed to open for automatic  !

suction swapover when CA pump suction pressure drops below 2 psig for 2 to 3 seconds.

Description of Event On May 21,1990, at 0100, Performance personnel. prepared to perform the Unit 1  :

TDCA' system flow balance test using periodic test procedure PT/1/A/4252/14, i Turbine Driven CA System Flow Balance.  !

Control Operator A started TDCA pump number 1 at 0107:24 using procedure OP/1/A/6250/02, Auxiliary Feedwater System. Control Operator A and Performance Engineer A noted that valve IRN-69A, CA Assured Supply From Train A RN, repositioned to the open position. Operator A shutdown TDCA pump number 1 at 0107:55 and then closed valve IRN-69A at 0108:18. Operator A then verified that no other assured CA pump suction supply valves repositioned to open positions. 3 Performance Engineer A contacted Performance personnel at the pump. Performance personnel at the pump ascertained that no actions were taken that would have' caused valve IRN-69A to reposition. Performance personnel reverified that all I test equipment was properly connected. No connection errors or problems were ,

identified.

, Operator A restarted TDCA pump number 1 at approximately 0146 to check for any unanticipated valve movements and subsequently shutdown the pump at approximately 0153. None of the assured CA suction supply valves repositioned.

I Operator A restarted TDCA pump number 1 at 0208:17 to perform the flow balance

! test. TDCA pump number 1 was shutdown at 0416:35 after successfully completing l

'U.S. GFOs 19 9 8 1N-S$1 < 000 4 NTC SQRM 306A 19 433'

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UCENSEE EVENT REPORT (LER) TEXT. CONTINUATION .. - - ..., - - + l maovio on =o mo.oio.

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1 the flow balance test using approved procedures. None of the assured-CA suction supply valves repositioned during this pump run.

The NRC was notified of this event at 0430 as directed by RP/0/A/5700/10,-NRC

-Immediate Notification Requirements. -

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1 Conclusion i This event is assigned a cause of Unknown. because no definite or probable cause could be determined. No procedure problems were identified. The procedures  !

, involved have been successfully used several times in the past. These same- ]

procedures.were used to successfully start and test the TDCA system after this ,

event occurred on May 21, 1990. No inappropriate actions were identified.

Operations and Performance personnel involved in this event stated they acted in i accordance with appropriate approved procedureni. No actions were identified that '

would have resulted in the repositioning of valve IRN-69A. No equipment failure

, or malfunction was identified. Emergency work request number 141198 was. issued r on May 21, 1990, at 0400 to investigate and repair the cause for valve IRN-69A opening when the TDCA pump started. The time delay relay [EIIS:62] setpoint and

o pressure switches, ICAPS 5350 and ICAPS 5370, (either pressure switch could independently actuate valve IRN-69A) setpoints were checked. These setpoints- ,

i~ ' were verified within required calibration tolerances. The time delay relay was found set at 3 seconds. Pressure switches ICAPS 5350 and ICAPS 5370 were respectively found set at 2.33 and 1.97 psig. Pressure, switch ICAPS 5350 was near the high tolerance (+/ .35 psig). This pressure switch setpoint was adjusted

_ back to the nominal of 2 psig decreasing and verified to actuate at 2.04 psig.

No electrical problems were identified with the valve actuator. No low CA suction pressure was identified. Operations and Performance personnel noted

, -static ~CA suction pressure at 26 to 31 psig before the TDCA pump was started. CA

suction pressure was documented-at 19.5 to 20.9 psig during the subsequent successful TDCA system flow balance test. None of the other eight. pressure  ;

switches' set at 2 psig decreasing picked up since none of the associated assured 3 CA system supply valves repositioned open. Also, none of the three pressure ,

switches set at 4 psig decreasing associated with alarm [EIIS: ALM} pointt, picked /

up since no low CA suction pressure alarms were recorded on the Alarm Typer. No other activities were in progress that would have resulted in valve IRN-69A repositioning to the open position. It is unlikely.that air was entrained in the CA suction lines because the three CA pumps had been started and run at least '

three times each for various tests between April 23 and May 17, 1990.

( Additic4 tally, CA Pumps 1A and IB were run for flow balance testing on the evening of May 20, 1990, just prior to starting TDCA pump number 1. No anomalies-

,. were identified by Operations, Performance, or Instrumentation and Electrical ,

personnel that would explain this event.  !

A review of the Operating Experience Program Data Base for the previous twenty-four months revealed one event, LER 370/89-01 that involved an Engineered  !

y Safety Feature actuation that was attributed to unknown causes. LER 370/89.-01

involved different equipment, administrative control, and personnel actions.

'Therefore, this event is not considered recurring.

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McGuire Nuclear Station, Unit.i o l5 j o j o j o l 3 l -6[ 9 9j0 _ Oj1l1 0l0 l4 or -l5 text in . v. wimw mac e- amaw nn

-This event is:not Nuclear Plant Reliability data System (NPRDS) reportable.-

There were no personnel injuries, radiation overexposures, or uncontrolled.

releases of radioactive material as a result of this event.

CORRECTIVE ACTIONS:

-Immediate: 1) Operations personnel shutdown TDCA pump number 1.

2) Operations personnel closed valve IRN-69A.

' Subsequen't: 1) Performance personnel verified that test connections were Correct.

2)~ ' Operations personnel verified CA-system conditions.

3) _ Operations personnel initiated work request number 141198 to

-investigate and repair the reason for valve IRN-69A opening on the pump start.

'4) Instrumentation and Electrical personnel performed troubleshooting and calibration verifications. No equipment problems were identified.

Planned: None

= SAFETY ANALYSIS:

This event resulted in one valve, 1RN-69A, repositioning to the open position.

The open position for_this valve is the most conservative position because it provides the emergency' nuclear safety related water supply to the Turbine driven

.CA' Pump suction when the in-series CA valve also opens. The suction supply to the Turbine driven CA Pump remained unchanged since only one of the:in-series

' isolation valves opened. A manual or automatic start of the Turbine Driven CA

-Pump with only one in-series isolation valve,open would result in a suction supply from normal non-safety related sources, y This inadvertent repositioning of valve IRN-69A did not affect any other equipment or systems. Operations personnel made the proper notification to the NRC.

The health and safety of the public were not affected by this event.

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