05000374/LER-1993-005

LER 93-005-00:on 930802,2A DG Declared Inoperable.Caused by Equipment Failure of 2A DG Discharge Relief Valve.Work Request Written to Replace 2A DG Relief valve.W/930826 Ltr

ML20056G636
Person / Time
Site:	LaSalle
Issue date:	08/26/1993
From:	Kollross T, Schmeltz J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-005-06, LER-93-5-6, NUDOCS 9309030366
Download: ML20056G636 (5)

LER-2093-005,

Event date:
Report date:
3742093005R00 - NRC Website

text

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, Commonw::lth Edison LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseilles. !!!inois 61341 Telephone 815/357-6761 August 26, 1993 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Hashington, D.C. 20555 Licensee Event Report #93-005-00 Docket #050-374 is being submitted to your office in accordance with 10CFR50.73(a)(2)(v)(A).

J. V. Schmeltz Acting Station Manager LaSalle County Station JVS/CTK/gry Enclosure I xc: Nuclear Licensing Administrator NRC Resident Inspector i NRC Region III Administrator INP0 - Records Center IDNS Resident Inspector i

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9309030366 930826  ? l PDR ADDCK 05000374 -

S pon y ,

, , LICENSEE EVENT REPORT (LER)

Form Rev 2.0 bcility Name (1) Docket Number (2) Pace (3)  !

LaSa11e'Countv' Station Unit 2 0 15 10 10 10 13 17 14 1 l ef! 0 l 3 f Title (4) 2A Diesel Generator Air Sta-t System Below 200 PSIG Due to Ecuipment Failure

. Event Date (5) LER Number (6) Report Date (7) Other Facilities Involved (8)

Month Day Year Year Sequential Revision Year Facility Names

{

/// /// Month Day Docket Number (s) 2 fff fff

/// Number /// Number LaSalle Unit 1 0 15 10 10 10 13 17 13 *

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OIB 0 12 913 913 0 l 0 l5 Ol0 018 2 16 9I3 0 15 10 10 10 l i I f THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10CM  !

(Check one or more of the followino) (11) f 1 20.402(b) _ 20.405(c) _ 50.73(a)(2)(iv) _ 73.71(b)

P0tfER _ 20.405(a)(1)(1) _ 50.36(c)(1) _L 50.73(a)(2)(v) _ 73.71(c)

LEVEL 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) Other (Specify l0 l0_

(10) 1

_ 20.405(a)(1)(iii) _ 50.73(a)(2)(i) _ 50.73(a)(2)(viii)(A) in Abstract  !

/,/,/,/ / / / /, /,/,/,/ /, /,/,/,/,/,/,/,/,/, /, /, /, /, _ 20.405(a)(1)(iv) _ 50.73(a)(2)(ii) _ 50.73(a)(2)(viii)(B) below and in  !

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///////' ////' /' /' /' fff //fy' //' /'f, _ 20.405(a)(1)(v) >_ 50.73(a)(2)(iii) _ 50.73(a)(2)(x) Text)

LICENSEE CONTACT FOR THIS LER (12) '

Name TELEPHONE NUMBER j AREA CODE }

l Todd Ko11ress. System Enoineer Ert. 2704 8l1 I5 3 15 17 I -16 17 16 11 l COMPLETE ONE LINE FOR EACH COMPON NT FAILURE DESCRIBED IN THIS REPORT (13) l CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- '

REPORT /BLE TURER TO NPRDS TURER TO NPRDS 4 X L1C l IR IV R 13 14 14 Y l l l l l l l I X LIC II IS IV A 14 11 15 Y / l l 1 l I I i l SUPPLEMENTAL REPORT EXPECTED (14) Expected Month I Dav l Year Subm?ssion i j lyes (If ves. complete EXPECTED SUBMISSION DATE) X $ NO Date (15) l I I l f I I I >

l ABSTRACT (Limit to 1400 spaces, t.e. approximately fif teen single-space typewritten lines) (16) I l  !

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On August 2,1993 both Units 1 and 2 were in Operational Condition 1 (Run) at 100% power. At approximately {

, 1401 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.330805e-4 months <br /> the 2A Diesel Generator (DG)ILC] Air Receivers were reported to be at 192 psig, which is below the '

Technical Specification requirement of 200 psig. The 2A DG was declared inoperable. The 1A DG had already >

been declared inoperable at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br /> on July 31, 1993, when it was removed from service for a planned j i

bearing inspection of the DG Cooling Water Pump.  !

t Since the Limiting Condition for Operation (tro) for Techr;ical Specification 3.8.1.1.b could not be met, i i Technical Specification 3.0.3 was entered. ,

i An Equipment Operator (EO) was immediately dispatched to the 2A DG Room. At 1412 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.37266e-4 months <br />, the 2A DG Air

, Receivers were restored to a pressure greeter than 200 psig. The 2A DG was declared operable at 1412 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.37266e-4 months <br /> l on August 2, 1993. Technical Specification 3.0.3 was exited within one hour so no power reduction was i required.

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The cause of this event was equipment failure of the 2A DG Discharge Relief Valve, 2DG048B and the 2A DG Starting Air Isolation Check Valve, 2DG049A. The safety significance of the event was minimal.

This event is reportable to the Nuclear Regulatory Commission as a Licensee Event kepor*. in accordance with l l *DCFR50.73(a)(2)(v)(A) due to a decrease in safe shutdown capability.

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CDCUMENT ID 93 i

LICENSEE EVENT REPORT (LER) TEXT CONTINUATTON Form Rev 2.0 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) Pace (3)_

Year // Sequential Revision j/,j/

// Number j/////jj/ Number t tasalle Countv Station Unit 2 0 1 5 l 0 1 0 1 0 13 17 14 9l3 -

010l5 -

0 I0 0 12 0F 0 13 TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [XX)

PLANT AND SYSTEM IDENTIFICATION: ,

General Electric - Boiling Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as [XX). ,

A. CONDITION PRIOR TO EVENT Unit (s): 2 Event Date: B/02/93 Event Time: 1401 Hours Reactor Mode (s): 1 Power Level (s): 1Ry%

Mode (s) Name: RUN B. DESCRIPTION OF EVENT On August 2,1993 both Units 1 and 2 were in Operational Condition 1 (Run) Mode at 100% power. At approximately 1401 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.330805e-4 months <br /> the 2A Diesel Generator (DG)[LC) Air Receivers were reported to be at 192 psig, which is below the Technical Specification 4.8.1.1.2.7 requirement of 200 psig. The 2A DG was declared  !

inoperabl e. The 1A DG had already been declared inoperable at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br /> on July 31, 1993, when it was removed f rom service for a planned bearing inspection of the DG Cooling Water Pump. Since the Limiting l Condition for Operation (LCO) for Technical Specification 3.8.1.1.b could not be met, Technical l Specification 3.0.3 was entered.

Technical Specification 3.0.3 requires action to be initiated within one hour to place the Unit in an operational condition in which the specification does not apply (Shutdowri). An Equipment Operator (EO) was immediately dispatched to the 2A DG Room. At 1412 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.37266e-4 months <br />, the 2A DG Air Receivers were restored to a pressure greater than 200 psig. Work Request L23239 replaced the relief valve that lifted prematurely causing the depressurization. Work Request L21695 was written to disassemble and repair the 2A DG Starting Air Isolation Check Valve, 2DG049A. The ZA DG was declared operable at 1412 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.37266e-4 months <br /> on August 2 I 1993. Technical Specification 3.0.3 was exited before the one hour time limit expired. {

This event is reportable to the Nuclear Regulatory Commission as a Licensee Event Report in accordance with 10CFR50.73(a)(2)(v)(A) due to a decrease in safe shutdown capability.

C. APPARENT CAUSE OF EVENT The cause of this event was equipment failure. The Discharge Relief Valve, 2DG04BA, has been installed since original plant start up. Work Request L23239 was written July 2,1993 to repair a minor leak around the valve seat. The work was originally scheduled to be completed during the Unit 2 Divisional 2 work week beginning on July 26, 1993. During the week beginning on July 19,1993, _ the 2A DG 'B' Air Compressor was taken out of service to be overhauled. This decision to replace the 'B' compressor was

., based on vibrational,and oil analyses. The 'B' compressor job took precedence,over the 'A' compressor work, thus the 'A' compressor work was rescheduled for the week beginning August 23, 1993.

DCCUMENT ID 93

LICENSEE EVENT REPORT {t ER) TEXT CONTINUATION Form Rev 2.0 FACILITY NAME (1) DOCKET N21BER (2) __ LED NUMBER (6) pace (3)

Year /

,//p, Sequential /jj/

/ Revision f

/// Number /// Number LaSalle County Station Unit 2 0 1 5 1 0 l 0 l 0 13 17 14 913 -

0IOI5 -

0 IO O 13 0F 0 13 TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [XX]

C. APPARENT CAUSE OF EVENT CONTINUED The 2A DG Starting Air Compressor Isolation Check Valve, 2DG049A, failed due to corrosion caused by moisture in the air lines. This problem had been identified in 1992. The moisture was allowed to form within the lines because of a clogged moisture separator, air dryer drain trap, and non-functioning air l d rye r. These problems had been identified in the past and were documented per work requests. Due to I the engineering being completed to install the dryers and the delay on parts from the manufacturer, the dryer could not be scheduled for completion until July 26, 1993. Because of the above mentioned 'B' compressor work, the 'A' Staring Air System could not be worked on and was rescheduled to be completed during the month of August,1993.

- D. SAFETY ANALYSIS OF EVENT The safety consequences of this event were minimal. Division 1 and Division 2 Emergency Core Cooling

, Systems (ECCS) were fully operable throughout this event. Automatic Depressurization System (ADS)[SB) was available to reduce reactor pressure to allow the Low Pressure Core Spray (LPCS)(LP)[BMJ System and Low Pressure Core Injection (LPCI) system to operate if necessary. Although the 2A DG was administratively inoperable, the 2A DG was fully functional as long as the Starting Air Pressure for the

2A DG did not depressurire below 165 psig, as is specified in section 9.5.6.1.1 of the Updated Final Safety Analysis Report (UFSAR).

E. CORRECTIVE ACTIONS i

Work Request L23239 was written to replace the 2A DG 'A' Starting Air Compressor Discharge Relief Valve, 2DC04BA. Work Request L21695 was written to disassemble and repair the 2A DG Starting Air Isolation Check Valve, 20G049A. The valve was cleaned, reassembled and tested satisfactorily. The moisture trap, air dryer, and air dryer drain ball trap have outstanding work requests against them to repair and replace f aulty parts as needed. As of August 23, 1993, the moisture trap and air dryer drain ball trap have been cleaned and repaired. The air dryer is presently being installed. This work should be completed by September 4,1993.

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F. PREVIOUS EVENTS

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1 There are no similar events of this type documented at LaSalle.

1 G. COMPONENT FAILURE DATA MANUFACTURER NOMENCLATURE M3 DEL NUMBER MFG PART NUMBER Rockwell-Edward 1-1/2 Check Valve N/A (Figure Number 2610010

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838YT3)

Anderson, Greedwood l" Relief Valve 83M5RR-4L and Co.

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