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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:== | |||
l l , | |||
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.". , | |||
4 R> / | |||
O ! | |||
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' | |||
I; . | |||
s' I ic 0' C n' V | |||
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 /// | |||
ff fff | |||
{// Naber /// Naber 01 51 01 01 01 1 1 el 9 el 9 | |||
~ | |||
01019 | |||
~ | |||
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////,. | |||
/ _ | |||
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 hours, 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 hours. 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." | |||
- - = - - _ - - - - _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ | |||
..~ . . . - - . -- .. . | |||
I | |||
)- | |||
? | |||
, o | |||
; ' 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 | |||
// | |||
/f . Revision | |||
/ | |||
. .[ | |||
ff | |||
/// Number f | |||
/// thaber j | |||
- ' | |||
* 11e County Station Unit 2 0 1 5 1 0 1 0 1 0 l 31 71 4 8l9 - | |||
'Ol0l9 - -0l'I 01 2 0F' 01 4 [![ | |||
L TEXT.- Energy Industry identification System (Ells) codes are identified in the text as [XX] ; | |||
1 x , .; | |||
% , , PLANT AND SYSTEM IDENTIFICATION J | |||
: General Electric - Bolling Water Reactor ; | |||
[' Energy'IndustryidentificationSystem(Ells)codesareidentifiedinthetextas[XX). | |||
l | |||
+ | |||
1 | |||
= 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 hours. 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 | |||
~ | |||
) | |||
Y, .for repairs to the 28 Olesel Generator (DG).[EK). | |||
] | |||
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 | |||
,x l? . | |||
l I | |||
! 4 - | |||
.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." | |||
d L , | |||
I s | |||
l l | |||
1 j | |||
J j_.- | |||
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. | |||
I J- | |||
~ | |||
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, | |||
) , | |||
) | |||
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 hours. | |||
l-l t | |||
l i | |||
. & j | |||
" 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 ; | |||
fff | |||
/// Nunber //j/ | |||
ff | |||
// Neeer ; | |||
s L | |||
* 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] -] | |||
i | |||
: 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 | |||
~ | |||
i | |||
.:. .. . =}} |
Latest revision as of 15:04, 17 February 2020
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) | |
Text
. - - . . . . . . . - . . .
$ . 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:
l l ,
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.". ,
4 R> /
O !
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'
I; .
s' I ic 0' C n' V
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 ///
ff fff
{// Naber /// Naber 01 51 01 01 01 1 1 el 9 el 9
~
01019
~
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////,.
/ _
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 <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />, 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 <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />. 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."
- - = - - _ - - - - _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _
..~ . . . - - . -- .. .
I
)-
?
, o
- ' 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
//
/f . Revision
/
. .[
ff
/// Number f
/// thaber j
- '
- 11e County Station Unit 2 0 1 5 1 0 1 0 1 0 l 31 71 4 8l9 -
'Ol0l9 - -0l'I 01 2 0F' 01 4 [![
L TEXT.- Energy Industry identification System (Ells) codes are identified in the text as [XX] ;
1 x , .;
% , , PLANT AND SYSTEM IDENTIFICATION J
- General Electric - Bolling Water Reactor ;
[' Energy'IndustryidentificationSystem(Ells)codesareidentifiedinthetextas[XX).
l
+
1
= 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 <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />. 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
~
)
Y, .for repairs to the 28 Olesel Generator (DG).[EK).
]
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
,x l? .
l I
! 4 -
.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."
d L ,
I s
l l
1 j
J j_.-
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.
I J-
~
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,
) ,
)
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 <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />.
l-l t
l i
. & j
" 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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/// Nunber //j/
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// Neeer ;
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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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