ML20011F492

LER 89-013-01:on 890907,Group I Isolation Received During Performance of Instrument Surveillance LIS-MS-401.Caused by Depressurization of Main Steam Line Low Pressure Switch. Surveillance Revised to Split Into Two parts.W/900216 Ltr

ML20011F492
Person / Time
Site:	LaSalle
Issue date:	02/16/1990
From:	Crowl D, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-013, LER-89-13, NUDOCS 9003060114
Download: ML20011F492 (7)

Text

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D3 .4  ! LaSalle County Nuclear Station h . Rural Route #1, Box 220.' -!

Marseilles, Ulinois 61341 l

_ Telephone 815/357 6761 t

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February 16, 1990 Director of Nuclear Reactor Regulation -

U.S. Nuclear Regulatory Commission  :

Mail Statton P1-13'1 Washington, D.C. 20555 l ,,

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Dear Sir:

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l Licensee Event Report #89-013-01, Docket #050 M is being l submitted to your office to supercede previously submitted p -Licensee Event Report 89-013-00.

iOkO G. J. Diederich

[ Station Manager LaSalle' County Station

,i GJD/DAC/kg Enclosure xc: Nuclear Licensing Administrator NRC Resident Inspector NRC Region III Administrator I

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LICENSEE EVENT REPORT (LER) F L0 Docket Nunber (2) Pace (3)

Facility N ee (1)

W ile County Station Unit 2 015101010131714 Ilof!0l6 l Title (4) frireri Containment Isolation Durine Instr.a.ent S;.rwillame Testine Due to PrWural Deficiency ,

LER Number (6) Report Date (7) Other Facilities involved (8) l Event Date (5) Facility Names I

Revision Month Day Year Docket Neber(s)

Month Day Year Year g/fSequential/j/j/ f

/// thaber /// Naber 01 51 01 01 01 I I 01 9 017 81 9 81 9 01113 0l 1 012 11 6 91 0 01 51 01 01 of I 1 l.

THis REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR

^ (Chsek one or more of the followine) (11) 20.405(c) _]L 50.73(a)(2)(iv) 73.71(b) 4 20.402(b) _

50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

POWER _ 20.405(a)(1)(l) ,___ _ _

Other (Specify LEVEL- 20.405(a)(1)(ll) _ 50.36(c)(2) _ 50.73(a)(2)(vil)- _ a In Abstract (10) 0l 0l 0 _ 20.405(a)(1)(lit) _ 50.73(a)(2)(1) 50.73(a)(2)(ll) 50.73(a)(2)(vill)(A) 50.73(:)(2)(vill)(8) below and in

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TELEPHONE NUSER Nee AREA CODE Don Crow 1. h latory Assurance, extension 2860 8 l 1 15 315171-l6171611 i wrFi.ETE ONE LINE FOR EACH wrruniiNT FAILLE 5 DESCRIBED IN THIS REPORT (13)

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lyes (if ves. ==lete EXPECTED SUBMISSION DATE) Yl NO ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16) l On September 7,1989 with Unit 2 in Cold shutdown (Operational Condition 4) a Group 1 Isolation (closes Main f' Stem isolation and stem Inne drain valves) was received during the perfonnance of LaSalle Instrument j

Surveillance LIS-MS-401, " Unit 2 Main Stem Line Low Pressure MSIV isolation Functional Test."

The Group 1 Isolation occurred when the Instrisment Maintenance personnel depressurized one of the Main Stem line low pressure switches (PS-2B21-N015C). Pressure switch 2821-N015C was tested without resetting the half isolation which existed after testing isolation logic channel Bl.

The unit was in Cold Shutdown with all Main Stem line isolation valves closed. No v41ve motion or tra was caused due to this event.

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The surveillance had been recently revised to spilt it into two separate parts, one if the unit is in the Run

! Mode and the other if the unit is in the Shutdown Mode. The review failed to identify the requirement for f

resetting the half isolation when one part of the surveillance was coupleted prior to testing the other half of the logic.

The Group 1 isolation was reset and the survelliance was conpleted without further problems.

l This report is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(lv) due to the actuation of l' an Engineered Safety Feature System.

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/I - L1"" EVENT ::"J:21 (LER) TEXT CONTilalATION DOCKET tlUISER (2). LER IRauti (6)  ?= 0)

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01113 0l 1 Ol' 2 ' 0F 01 6 l Alle County Station unit 2' 0 1 5 1 0 1 0 1 0 1 31 11 4 819

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, TEXT- Ener1g industry identification System (Ells) codes are ider.tified in the text as (XXJ

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' General Ele:tric - Bolling Mater Reactor

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Energy Industry identification System (EIIS) codes are identified in the text as [XX).-

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A. Coll 0! TION PRIOR TO EVENT Event Date: 9/7/09- Event ilme:- 0100 Hours' j Unit (s):: 2 Reactor Mode (s): 4 Mode (s) N ee: Cold Shutdown Power Level (s): __3_

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8. DESCRIPT10ll 0F EVENT L[

On September 7,1909 at 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> with Unit 2 in CCd Shutdown (0perational Condition 4), a full Group' t 1 Primary Contalmuent isolation (closes Main Stem (MS) (58] lsolation (MSIV) and Main Stem Ilne drain-y valves) was received during the perforinance of LaSalle Instrument Survel11ance LIS 4tS 401, " Unit 2 Main . 3 Ste m Line Low Pressure MSIV isolation functional Test." The LaSalle Instrument Surveillance LIS-MS 40 was revised in llovember 1908 in order to spilt the procedure into two separate' parts, one'part to be .l t used if the unit is in the Run Mode'and the other part to be used if the unit is in the Shutdown Mode.- Q

>i This was done to simpilfy the procedure and to prevent errors which could lead to inadvertent:

-isolation. This was the first time the functional test was being perfomed with the unit in Cold Shutdown since its revision.

The Group'1 isolation logic (PCIS) (JM] is "one-out-of-two-taken-twice." - The Main Stem line low pressure (854 psig) isolation signal is bypassed when the reactor mode switch is not in the Run position. (Refer to attached slapilfled. schematic of one subchannel.)

.Below is a chronological description of the events which lead up to the Group 1 isolation: ,j The fleid side leads were lifted off teminal FF-39 In Control Room panel 2H13-P609.. This removes the '

reactor mode switch " toot in Run" bypass of the low pressure isolation signal for pressure switch PS-2821-41015A (reactor low pressure 854 psig) and creates a channel Al isolation signal, s

PS-2821-N0158 was pressurized to approximately 1000 psig which t clears the Division 1 (81) Main Stem t Line pressure low alam.

.PS-2821-N015A was pressurized to approximately 1000 psig which clears the Division 1 (A1) Main Ste m k., line pressure low alam. Both the Al and the 81 alarins must be clear to reset the alam window "Div 1 +

Main Steam Line Press Lo" (B301) on Control Room panel 2H13-P603.

The leuclear Station Operator (NSO, licensed Reactor operator) reset the valve isolation logic by momentarily depressing the reset pushbuttons for inboard and outboard isolation logic on Control Room panel 2H13-P601. At this time the PS-2821-N01SA (AI) and the PS-2821-N0158 (BI) are pressurized (i.e.,

not tripped) and the PS-2821-#015A (A1) is also not bypassed due to the lifted lead.

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Fem Rev 2.0 M LME'E' VENT REPORT (LER) TENT CONTlinthT10M Pose Cl) i

> FACILITY Mafgi (1). 00CKET tou SER (2) LER IRDSER (6) r

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A lel C b Av Station unit 2 0 1 5 1 0 1 0 1 0 1 31 71 4 819 - 0l113 ~

- 0l 1 01 3 0F 01 6 l TEXTt Energy Industry identification System (Ells) codes are identified in the text as [KX).

i S. DESCRIPTION OF EVENT (Continued)

~ PS-2821-4015A is slowly depressurized until alam window "Olv 1 Main Stem Line Press is" on the Control Room panel 2H13-P603 has annunciated. Dep*essurizing PS-2821-40015A creates a subchannel Al isolation signal.

l PS.-2821-N015A test pressure was increased to approximately 1000 psig.

The NSO reset the valve isolation logic by momentarily depressing Reset pushbuttons for the inboard and ,

outboard isolation logic, on control Room panel 2H13-P601. ' All isolations were reset; no isolation s signals present.  !

Fleid side leads removed previously from teminal FF-39 on Control Room panel 2H13-P609 were landed.

This reinstates the mode switch "Not in Run" bypass logic for PS-2B2141015A (A1). ,

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' Fleid side lead was lifted off of teminal FF-39 on Control Room panel 2H13-P611. This removes the bypass for PS-2821480158 (81).

PS-2821-N0158 test pressure was decreased until alam window "Div 1 Main Stem Line Pressure LO" (8301), '

on control Room panel 2Hl3-P603 annunciated. Depressurizing PS-2821-400158 creates a subchannel B1 Isolation signal. .

Fleid side ' lead of teminal FF--39 on Control Room panel 2H13-P611 is landed. This reinstates the mode f switch "Not in Run" bypass for PS-2B21-N0158, however the isolation logic is not yet reset. The 81 isolation signal is still present because no reset pushbuttons have'been depressed at this point.

PS-2821-N015A pressure is reduced to zero. This depressurizes the PS-2B21-40015A (A1), but this is bypassed so no new isolation signal is present.

No reset pushbuttons have been depressed yet.

Field side lead was lifted from teminal AA-39 of Control Room panel 2H13-P609. This removed the mode switch "Not in Run" bypass of switch PS-2821-40015C (A2). This action generated a subchannel A2 Isolation signal with the B1 signal still present creating a full Group 1 isolation. All Group 1 isolation valves were closed prior to this event, therefore no valve movement took place.

C.. -APPARENT CAUSE OF EVENT The procedure did not provide steps for resetting the isolation signal prior to completing the surveillance on subchannel BI in order to allow additional low pressure switches to be tested without causing an actual isolation.

The procedure revision review process failed to identify this deficiency when the revision was in progress.

4 Fore Rev 2.0 LW^~ EVENT REPORT (LER) ' TEXT CONTINUATION DOCKET NupWER (2) LER C

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FACILITY limpE (1) '

Year /4/ Sequential / Revision W/ tiumber

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01113 0I 1 01 4 01 6 w ile County Station unit 2 0 1 5 1 0 1 0 1 0 1 31 71 4 019 .

- 0F TEXT = Energy industry identification System (Ells) codes are identified in the text as (KK) i C. APPARENT CAUSE OF EVENT (Continued)

No warning was provided to the Unit NSO prior to creating the isolation signal on subchannel A2.- The NSO may have stopped the test knowing that an isolation signal was going to be created with one already' active.' j m

! s ti D. SAFETY ANALYSIS OF EVENT. f l The safety consequences of this event is minimal. All the isolation valves associated with the Group 1 L' isolation logic were closed prior to this event. The unit was in Cold Shutdown and no transient a l resulted from the initiation of the Group I isolation signal. This particular portion of the surveillance is only perfonned when the unit is shutdown.

If this event would have occurred when the unit was at full power a reactor scram would be init!ated

- from the closure of the MSIV's due to the initiation of the PC15 Group 1 Isolation.

L L E. CORRECTIVE ACTIONS L The Group 1 Primary Containment 1sciation System (PCIS) signal was reset and the survelliance completed-without any further event.

'LIS-MS-301 and LIS-MS-401 procedures will be revised to provide instruction to reset and verify isolation logic' has been reset when required,'in order to prevent isolations from occurring when trying:

' to coglete this surveillance. Also a requirement to notify the NSO prior to any 1/2 scram or 1/2 3 '

isolation signal will became a nonnel maintenance practice per a new Maintenance Memo. Action item Report neber (AIR) 374-200-89-04901 will track this procedure revision.

The individuals involved in the preparation and approval of L15.NS-401 (Revision neber 3) have been l

tailgated about this event.with emphasis placed on the leportance of attention to detall.- The review of LaSalle Administrative Procedure LAP-820-2, " Station Procedure Preparation and Revision," has been ,

i' incorporated into annual required reading for all On Site Review participants and personnel who develop and revise procedures. AIR 374-200-8944902 to track this corrective action has been completed.  ;

The Instrument Maintenance Department has completed a review cf other surveillance procedures which has .

been revised or created since 1987 for proper resetting of logic during testing. One.survelliance, s LIS-RP-07, "APRM Flow Blased Neutron Flux High-High Scram Response Time Test," was identified as also needing a revision. AIR 374-200-89-04903 has been submitted to track the coupletion of this revision.

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Form Rev F.0 f (i LICNESEE EVENT REPORT (12R) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (6) Page (3)

FACLTY NAME (1)

Year FZSequential V//)Rension FA Number y// Number laSalle County Station Unit 2 0l5l0l0l0l3l7l4 8l9 - 0l_1l3 - 0l1 0l6 0F 0l6 l

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