ML20028G914

LER 90-018-00:on 900829,plant Outside Design Spec for Electrical Separation Criteria for Two Redundant Safety Sys. Caused by Inadequate Engineering Review During Leads installation.W/900928 Ltr

ML20028G914
Person / Time
Site:	Quad Cities
Issue date:	09/28/1990
From:	Bax R, Brohm K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-018-01, RLB-90-244, NUDOCS 9010030093
Download: ML20028G914 (5)

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, 7; 7 ' :- ~ Commonwealth Edison s_ -): ' ound Cites Nuctnr Power Station i' 22710 206 Avenue North -

Cordova, Ilkne's 61242 9740 +

p , Telephone 309/054-2241 - l L

RLB-90-244 ,

1 September 28, 1990 l I

U. S. Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555 *

Reference:

- Quad Cities Nuclear Power Station a Docket Number 50-254, DPR-29, Unit One  !

Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER)90-018, Revision 00, for Quad Cities i Nuclear Power Station. .

.This report is. submitted in accordance with the requirements!of the Code'of Federal Regulations, Title 10, Part 50.73(a)(2)(1)(B): The 11c6nsee-shall. .

report any event or condition that resulted in the nuclear power plant being_

in a condition that was outs _ide-the design basis of the plant.

Respectfully.

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-COMMONHEALTH EDISON COMPANY- '

Q D CITIES NUCLEAR POWER STATION I

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' R. L E 4I L6 l Station Manager

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. . Enclosure 9010030093 900928 PDR ADOCK 05000254 S PNV Lt. M. 3LUIh' T. Taylor INPO Records Center NRC Region III n q n n -- MI V

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3 LICENSEE EVENT REPORT (LER) , ,g 7g j Facility Name (1) Docket Number (2) _ Pace (3) j of El 01 of 01 21 El 4 I lof!O

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nuad Cities Unit one 4 N 0 h and two outside Their Design. Specification For. Electrical $eparation Criteria For Two Redundant $afety tyrtens Due To Inadeauate Enoineerino Review.

Event Date (E) LER Number (6) Reoort Date (7) Other Facilities Involved (B)

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Month . Day Year Year sequential Revision Month Day Year Facility Names Docket Number (s) l Number Number 01 El 01 01 of 21 61 5 Unit 2 I 01 B fl 9 91 0 91 0 0 l 1 lB 0l0 019 2 fB 91 0 01 El 01 01 of I l p THIS REPORT IS $L3MITTED PUR$UANT TO THE REQUIREMENTS OF 10CFR j (Check one or more of the followinoi (11) 4 20.402(b) _ 20.405(c) 50.73(a)(2)(iv) _ 73.71(b)

P0wtR ,,, 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL 20.405(a)(1)(11) 50.36(c)(2) 50.73(a)(2)(vii) Sther (specify

!0 !0 _ _

l flo) 1 20.405(a)(1)(ii,) 50.73(a)(2)(1) ,, 50.73(a)(2)(viii)(A) in Abstract i j' //////////////////////,//// _ 20.405(a)(1)(iv) X. 50.73(a)(2)(11) , 50.73(a)(2)(v111)(B) below and in

/////////////////////'///// j 20.405(a)(1)(v) , 50.73(a)(2)(111) 50.73(a)(2)(x) Text)

!!CENSEE CONTACT FDR THIS LER (12)

Name TELEPHONE NUMBER AREA CODE

_ Fevin R. Brohm. Technical Staff Encineer Ext. 2149 3 10 l9 6l El 41 -l 21 21 4 L ),

COMPLETE ONE LINE FOR EACH (21 N NT FAILURE DESCRIBED IN THIS REPORT f13)

CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAU$E SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER TO NPRDS .

I I i l i I I I I i I i l 1 1 I I I I l l / I I I I i l l SUPPLEMENTAL REPORT EXPECTED f14) Expected Month l Day l Year Submisston lyes fif ves. comnlete EXPECTED SUBMISS 10N DATE) X l ND l l ll A8sTRACT (Limit to 1400 spaces, i.e. approximately fifteen single-space typewritten lines) (16)

ABSTRACT:

On August.29, 1990, at 1736 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.60548e-4 months <br />, Units One and Two were both in the RUN mode at ,

100 percent of rated core thermal power. Engineering notified the station that both units were potentially outside the design basis of the plant's electrical divisional separation criteria. Test leads for the Emergency Core Cooling System (ECCS) Simulated Automatic Actuation and Diesel Generator (DG) Auto-Start Surveillance were wired such that two redundant safety-related divisions were. <

landed on one terminal block without an adequate fire barrier. An Emergency Notification System (ENS) telephone call was completed in accordance with i0 CFR50.72(b)(1)(11). Al1 test leads were removed prior to the expiration of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Limiting Condition for Operation (LCO).

The cause_of this event was lack of adequate engineering review when these leads were installed. Immediate corrective actions were to remove the test leads.

Further corrective actions are to change the test procedure to install temporary leads for the test and remove ttiem immediately afterward.

This report is submitted to comply with 10CFR50.73(a)(2)(ii)(B).

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LICEN$tt T/ENT REPORT (LER) T[XT CONTINUATION Form Rev Q .

FAc!LITY NAME (1) DOCKET NUMBER (2) LER NUMBER f6) Pane fil _ g Year. /,//

ff sequential /j/

/

ff Revision 1

/// Number /// Number _.

Quad Cities Unit one 015 10 1010 l 21 El 4 910 - 0 l 1 lB - 0l 0 01 2 0F 0 14 J

, TEXT. Energy Industry Identification System (Ells) cooes are identified in the text as IxXI-1 PLANT AND SYSTEM IDENTIFICATION: =

. General Electric - Bolling Water Reactor - 2511 MHt Rted core thermal power.

EVENT IDENTIFICATION: Unit'One and Two Outside Their Design Specification for Electrical Separation Criteria for Two Redundant Safety Systems Due To Inadequate Engineering Review.

A. CONDITIONS PRIOR TO EVENT: ,

l Unit: One Event Date: August 29, 1990 Event Time: 1736 l Reactor Mode: 4 Mode Name: RUN Fower Level: 100%  ;

This report was initiated by Deviation Report D-4-1-90-085 -

RUN Mode (4) - In this position the reactor system pressure is at or above 825 psig, and the reactor protection system is energized, with APRM protection and RBM interlocks in= service (excluding the 15% high flux scram).

B. DESCRIPTION OF EVENT:

On August 29, 1990, at 1736 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.60548e-4 months <br />, Units One and Two were both in the RUN mode at J 100 per enc of rated core thermal power. The Engineering and Construction (ENC) department notified _the station that both units were potentially outside their design basis for electrical divisional separation of the Emergency Core Cooling Systems (ECCS) [JE). This determination resulted from an engineering review of a Drawing Change Request (DCR) which had been submitted to correct wiring discrepancies identified during the performance of Work Request 082395. This work

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request was being performed as a corrective action for an event previously reported

-in LER 265/90-004. Specifically,-test leads [CBLl] connected to-the logic circuitry of 01visten I and Division II equipment were landed on the same terminal strip [BLK] in the 901(2)-5 panel. These test leads provided a method of attaching ,

a six-pen recorder [AR) during the performance of-QTS 110-1(3), Unit One(Two)

Emergency Core Cocling System (ECCS) Simulated Automatic Actuation and Diesel Generators Auto-Start Surveillance. The installation of this wiring had been performed on April 28, 1978 under Work Requests 1232-78 for Unit One and 1233-78 for Unit Two.

Both units, at this time entered a voluntary 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Limiting Condition for Operation (LCO) as statea in Technical Specification 3.5.A.6 and 3.5.B.5. The 1/2 diesel generator (DG) [DG], lA and 2A Ccre Spray [BM) Pumps [P], and the IA, 18, 2A and 2B Low Pressure Coolant Injection (LPCI) [B0] pumps were de:lared inoperable, administratively.

The test leads were removed by 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> on August 30, 1990 and all affected systems were declared operable.

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LIC[NS[E EVENT RfPORT fLER) TEXT CONTINUATION Form Rev 2.0 l  ; FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER f6) Pace _f3)

Year /j/j/p sequential / Revision

/// Number //,j/

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/ Number Duad Cities Unit One 0l5 10 l010 l 21 El 4 9i 0 - 0~l1 l B - 0l 0 01 3 0F 0 14 Tcxi Energy Industry Icenttrication system (EIIs) codes are identified in the text as [XX)

C.- APPARENT CAUSE OF EVENT:

This report is being submitted in accordance with 10CFR50.73(a)(2)(11)(B); The licensee shall report any event or condition that resulted in the nuclear power

. plant being in a condition that was outside the design basis of the plant.

The cause of this event is inadequate engineering review for the installation of these test leads. The installation of these test leads was performed in 1978 under nonsafety related work requests and did not receive engineering review for design basis compliance. This is not in accordance with General Electric's Design Specification 22A?501, Separation Requirements For Reactor Safety and Engineered Safeguards Systems.

D. SAFETY ANALYSIS OF EVENT:

The divisional separation criteria for electrical systems in the control room is designed to prevent failure of ECCS equipment in both divisions due to damage from a fire or missiles from rotating equipment. Since there is no rotating equipment in'the control room this failure is not of concern. Damage due to a fire has

'previously been evaluated under the Appendix R Fire Protection Program. The control room was evaluated as a single fire area, and therefore all equipment located in the control room was assumed to be rendered inoperable. Modifications have been installed as a result of this review which provide the capability to shutdown the reactors to a cold shutdown condition independent of the equipment located in the control room. Based on this, the safety consequences of this event are minimal.

E; CORRECTIVE ACTIONS:

The immediate corrective action was to remove all the test leads between centrol room panels [PL]- 901(2)-3, 90l W -5 and 901(2)-8 and lift the leads that ran ,

between both units for the 1/2 DG running indication. This met the design specification and single failure criterion.

Present modification and minor design change programs involve several design and installation walkdowns along with several engineering reviews which were not performed when the test leads were installed. Therefore, an event similar to-this would not occur with these programs.

Further. corrective actions will be to enhance procedures QTS 110-1 and 3 so that they instruct the test director to temporarily install the test leads,-perform the

-test, and remove the leads one division at a time so that the station stays within

.their design specification (NTS 2542009008501). No further corrective actions are deemed necessary.

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LICENSEE EVENT REPORT.(LER) TEXT CDNTINUATION Form Rev 2.0 LER NUMBEk f6) Pane f3) 7.-l # ' FACILITY NAME (1)- DOCKET NUMBER (2)  ;

_ Year // sequential Revision i

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pj/, f/jf//

/// Number /// Number

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' Quad Citiet Unit One 015 101010 l 2l'El 4 910 -

-Ol1 lB - 0l 0 01 4 f# 014

,, TEXT. Energy Industry Identification systeen (E!!!) codes are idontified in.the text as [XX]

F. PREVIOUS EVENTS:

No previous Licensee Event-Reports were identified'which were similar to this event.

G. COMPONENT FAILURE DATA:

There were no component failures associated with this event.

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