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LER 89-009-01:on 890619,diaphragm Leak Discovered in RCIC Steam Line High Flow Isolation Switch.Caused by 1 & 1/2-inch Tear in Diaphragm.Pressure Differential Switch Replaced & Calibr.Reported Per NRC Bulletin 86-002.W/900214 Ltr
	ML20006E445
Person / Time
Site:	LaSalle
Issue date:	02/14/1990
From:	Diederich G, Tennyson M; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	IEB-86-002, LER-89-009-01, NUDOCS 9002230180
	Download: ML20006E445 (5)
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$ . Commonwealth Edison I LaSalle County Nucliar Station ;

Rural Route #1, Dox 220 L*' Marseilles, Illinois 61341 - I l._ Telephone 815/357,-6761 , ;

February 14, 1990 i

L Director of Nuclear Reactor Regulation l U.S. Nuclear Regulatory Commission

l. Mail Station PI-137 ,

l Washington, D.C. 20555 l 1 -t l'

Dear Sir:

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l Licensee tvent Report #89-009-01, Docket #050-374 is being !

l submitted to your office to supercede previously submitted i

Licensee Event Report 89-009-00 which was reported ,

pursuant to NRC I.E. Bulletin 86-02, " Static-o-Ring Differential Pressure Switches.". ,

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I Station

. J. Diederich Manager i i

LaSalle County Station l I~ GJD/79tT/kg -

Enclosure xc: Nuclear Licensing Administrator NRC Resident Inspector NRC Region III Administrator j- INPO - Records Center t'

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lA LICENSEE EVENT REPORT (LER) F LO 7 ,

00cket Nunber (2). Pace (3)

' ' Facility N me (1)

I lie County Station Unit 2 .

- 015101010131714 1!of!0l4 Title (4)

Reactor Core isolation Coolina Hi Ste m Flow Isolation Switch Failed Olaphra m Event Date (5) LER ikuher t (6? Report Date (7) Other Facilities involved (8)

Revision Month Day Year Facility Names Docket Huber(s)

Month Day Year Year /j// Sequential ///

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{// Naber /// Naber 01 51 01 01 01 1 1 el 9 el 9

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01 1 012 11 4 91 0 01 51 OI 01 ol' l I l-01 6 11 9 THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10CFR OPER611NG-(Check one or more of the followino) (11) 1 20.402(b) _

20.405(c) ,,__ 50.73(a)(2)(lv) _ 73.7)(b) 20.405(a)(1)(1) 50.36(c)(1) _ 50.73(a)(2)(v) _ 73.71(c)

POWER _

50.36(c)(2) 50.73(a)(2)(vil) ,,X_ Other (Specify LEVEL .

20.405(a)(1)(ll) ,,,_, ,_,_

in Abstract (10) 0 l. 7l5 ,. 20.405(a)(1)(lii) _

50.73(a)(2)(1) ,,_ 50.73(a)(2)(vill)(A) 50.73(a)(2)(vill)(B) below and in

/ /,///,/,////,/,/ /,/,/,/ /,/,/,/,/, 20.405(a)(1)(lv) 50.73(a)(2)(ll) ,_.

_,,,,_50.73(a)(2)(lii) 50.73(a)(2)(x) Text) Voluntary

////f '/j/ 20.405(a)(1)(v) f f///// ff '//'/j ff /f////,.

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ffff LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER Nee AREA CODE Michael Tennyson Technical Staff Enoineer, extension 2704 8 l 1 15 31 51 71 -l 61 71 61 1 COWLETE ONE LINE FOR EACH CO@0NENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC- REP 0dTABLE CAUSE SYSTEM COMPONENT MANUFAC. REPORTABLE TO NPRDS TURER- TO NPRDS TURER ~

X Rl 1 l l Fl S S1 31 81 2 Y l i i l l l I l i I I I I I I I I I I I l Expected Month i Day l Year SUPPLEMENTAL REPORT EXPECTED (14)

Submission lyes (If ves. - = lete EXPECTED SUBMISSION DATE) X l NO l ll l l

ABSTRACI (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16)

On June 19, 1989, at 0905 hours0.0105 days 0.251 hours 0.0015 weeks 3.443525e-4 months , while Unit 2 was in Operational Condition 1 (Run), Reactor Core isolation The Cooling (RCIC) Stem Line High Flow Isolation Switch POS-2E31-N013AA was found to have a diaphragn leak.

setpoint for this switch was found within the action limit and the Limiting Condition for Operation.

The RCIC System wu :naintained operable during the event. The High Pressure Core Spray System was inoperable-due to the replacem # the 28 Diesel Generator at the time of the event.

The pressure differential switch P05-2E31-N013AA was removed and replaced, tested and declared opr3ble on June 19, 1989 at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months . The failed pressure differential switch P05-2E31-N013AA was disassenbled and

, inspected at LaSalle Station. A one and a half inch tear was found in the diaphragn. The cause of the tear could not be detennined.

This event is reported to the Nuclear Regulatory Connission as a voluntary Licensee Event Report in accordance with the requirements of 1.E. Bulletin 86-02, " Static-0-Ring (50R) Differential Pressure Switches."

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' LICENSEE EVENT REPORT-(LER) TEXT CONTINURTION - Fort Rev 2.0 .

, . FACILITY.NRME (1): DOCKET NU SER (2) LER NUSER (6) Pace (3) -I Year' Sequential

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11e County Station Unit 2 0 1 5 1 0 1 0 1 0 l 31 71 4 8l9 -

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L TEXT.- Energy Industry identification System (Ells) codes are identified in the text as [XX] ;

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% , , PLANT AND SYSTEM IDENTIFICATION J

General Electric - Bolling Water Reactor ;

[' Energy'IndustryidentificationSystem(Ells)codesareidentifiedinthetextas[XX).

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= A. CON 01T10N PRIOR TO EVENT-1 Unit (s): '2 -Event Date: 6/19/89 Event Time: 0905 Hours 1

Reactor Mode (s): - 1 Mode (s) Name:. Run- Power Level (s): 75%

'B. DESCRIPTION OF EVENT-On June 19,~.198S, at 0905 hours0.0105 days 0.251 hours 0.0015 weeks 3.443525e-4 months . while Unit 2 wa3.In Operational Condition I (Run)r at 75% power, it was

, discoveredthattheReactorCoreIsolationCooling(RCIC)[BN]SteamLineHighFlowisolation'(PC)[JM]) i

'Swlich PDS-2E31-N013AA was-Inoperable. , :j During the perfonnance of LaSalle Special Test, LST 98-068,'" Unit 2 RCIC High Steam Flow lsolation .

Functional," the differe'ntial pressure switch PCS-2E31-N013AA was unable to maintain pressu e while the'

' Instrument Maintenance Technician (CST) was attempting to verify actuation at the proper setpoint. This ;

is nonnally'a symptom of a torn'diaphrajpn, therefore the differential pressure switch was. removed and J replaced.1

'Olfferential Pressure Switch 2E31 4 13AA is connected in reverse parallel to P05-2E31-N013AB. The !

design function of'2E31 4013AA is to initiate an automatic isolation of 2E51-F006, RCIC Steam Line

, Outboard Isolation valve, in the event of a steam Inne break. The purpose of 2E31-#013AB is to isolate-2E51-F008 in the event of RCIC High Steam Flow Instrument line break. .l I

-- The RCIC System was required to be operable in accordance with Technical Specification 3.5.1 during the. !

'perfonnance of the surveillance due to the High Pressure core Spray System (HP) [BG) being inoperable

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Y, .for repairs to the 28 Olesel Generator (DG).[EK).

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g , 'No other l'noperable-equipment / systems con'tributed to this event. No automatic or manual safety system L' ' actuations occurred and none were required. No Operator actions contributed to the severity of this.

event. ' Actions taken to correct the cause of this event were timely and appropriate. l

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.This event is reported to the Nuclear Regulatory Commission as a Voluntary Licensee Event Report in l accordance with the requirements of I.E. Bulletin 86-02, " Static-0-Ring (SOR) Olfferential Pressure R Switches."

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Fons Rev 2.0 i U . LtCENSEE EVENT REPORT (LER) TEXT CONTINUAll0N LER WIPSER (6) Pace (3) ]

FAcilliY NAME_(I) 00CKEl NU MER (2)

^ Year fj/j/

/ Sequential /j// Revision

/// Number f//j/ Ne$er_ I 1

A lle County Station Unit 2 0 l 5 1 0 1 0 1 0 l 31 71 4 8l9 - 010l9 - O l' 1 01 3 0F 01 4 l.f Energy Industry identification System (Ells) codes are identified in the text as [XX] l

' TEX 1 - 1 I

C. APPARENT CAUSE OF EVENT i

The failed pressure differential switch 2E31 W013AA was disassenbled and inspected at' LaSalle Etation, A one and a half inch tear was (cur

in the diaphrm. In inspection of the 0-rings and bearings revealed nothing abnonnal. 1he switch failure was due to the tear found in the diaphra p during the

' inspection. The cause of the tear in the diaphrap could not be detennined. ,

D. iAFETY ANALYSIS OF EVENT The differential pressure switch 2E31-N013AA ects a RCIC Stem Line break. The reverse connected 3 J

differential pressure switch 2E31-NOI3AB will octect an instrwnent line break on the "high" side of the instrument line. A leaking diaphrap of 2E31-N013AA would eventually allow equalization of pressure between the "high" and " low" instrument lines making the switch inoperable. Depending on the size of )

j the leak in the diaphrap P05-2E31 M)13AB would also be affected.

l There are two channels of RCIC High Stem Flow Sensing Instrwnentation which isolate the RCIC System in

' the event of a stem line break or an.instrwnent line break. Channel A would close the RCIC Stem Line

> ' Outboard' Isolation valve 2E51-F008,'and Channel B would close the RCIC Stem Line Inboard Isolation Valves 2E51-F063 and 2E51-F076. The Channel B RCIC Stem Line High Flow Sensing Instrumentation wps f l

fully operable at the time of the event and would have isolated the RCIC stem line by closing 2E51-f063 and 2E51-F076 in the event of a RCIC steam line break.

In addition, both the inboard and outboard isolation functions for Residual Heat Removal (RHR) [90]

stem line high flow woull have occurred as designed had a high flow condition existed in the RHR stem Inne downstrem of 2ESt-F064 and 2E51-F091, RHR Heat Exchanger Stem Line Outboard Isolation Valves.

The differential pressure switch 2E31-N013AA for Channel A was replaced within the I-hour timeclock as '(

required by Technical Specification 3.3.2 Limiting conditions for Operation. The outboard isolation l valve 2E51-F008 was never closed.

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The RCIC System was operable during the perfonnance of LST 89-068. The High Pressure Core Spray System l

was inoperable due to repair work to the 28 DG at the time of the event,

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1 E.- CORRECilVE ACT10NS 1

The corrective action for this event was perfonned as required by Technical Specifications 3.3.2. This i

resulted in the pressure differential switch P05-2E31-N013AA being removed and replaced within the time allowed for the limiting Condition of Operation.

I A new SOR differential pressure switch identical to the failed one was certified for use in the RCIC steam line high flow appilcation using LaSalle Instrwnent Procedure LIP-GM 952, " Static-0-Ring Differential Pressure Switch Operability Test," and LIP-GM-9%, Analysis of Static-0-Ring Olfferential ,

L Pressure Switch Data." This new switch was installed per LIP-GM-946, " Installation Procedure for S-0-R I i

l Model 103/102 Envirorsnentally Qualified Differential Pressure Switches" under LaSalle Work Request L90704 on June 19, 1989. The switch was calibrated per LIS-RI-201, " Unit 2 Steam Line High Flow RCIC isolation Calibration." Differential Pressure Switch 2E31-N013AA was restored to operability on June f 19, 1989, at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months .

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" Form Rev 2.0 '

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ga FACILITY NAME (1). DOCKET NUfeER (2) LER NUPSER (6) Pace (3) j Year /// Sequential / Revision ;

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ile County Station Unit 2 0'l 5 1 0 1 0 l C l 31 71 4 8l9 -

Ol0l9 - 0l 1 01 4 0F 01 ' A TEXT . Energy Industry identification System (Ells) codes are identified in the text as [XX] -]

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E. CORRECTIVE ACTIONS (Continued)

The failed Differential Pressure Switch, PDS-2E31-N013AA, was disassenbled and inspected at.LaSalle Station. ~ The findings of the inspection revealed that the switch failed due to the torn diaphram. '{

F. PREVIOUS EVENTS LER Nweer Title

.374/86-018-01 Failure of Reactor Core Isolation Cooling Steam Line Flow Isolation Switch Due to Torn Diaphra p 374/87-016 4 1 Defective Low Pressure Core Spray Minimum Flow Switch

~ 374/87419 Failure of Static-0-Ring Differential Pressure Switch Due to Leakage Across Ditphrap ;

373/88-009 4 1 High Pressure Core Spray Low Low Level Initiation Static-0-Ring Level Switch Diaphragm Rupture .

373/89 4 12-00, Div. II.RCIC Hi. Steam Flow Isol.. SOR Falled Diaphrap G. COMPONENT FAILURE DATA Manufacturer - Nomenclature Model Nunber MFG Part Nunber 50R;Inc. Differential Pressure 103AS-8203-CI A N/A Switch NX-JJTTX6 1

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ML20006E445

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Dear Sir:

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