ML17252B554

LER 80-008/03L-0 for Dresden, Unit 2 Re Equipment Operator Discovered Level in the 2/3 Diesel Generator Coolant Water Expansion Head Tank Overflowing Thru the Vent Line

ML17252B554
Person / Time
Site:	Dresden
Issue date:	02/22/1980
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR 80-147 LER 80-008/03L-0
Download: ML17252B554 (2)

Text

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e CommonwealAdison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 February 22, 1980 BBS LTR /180-147 James *c. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report":/180-8/03L~O,. Docket 11050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(b), conditio~s leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

f:\uP B. B.

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'lX.019' Station Superintenden*t Dresden Nuclear Power.Station

• ms: leg Enclosure cc: Director of Inspection & Enforcement

. Director of Management Information & Program Control File/NRC

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• LICENSEE EVENT REPORT

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ID I 1 I L I D I R I s I 2 l@_Io_____ I o. . . .l_-_l_o_l_o_._Io__._Io__._lo_.._l-__._lo_....__Io__.I G)I 4 I 1; I 1 I 1 I 1 101 I I 0 S 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE

JO 57 CAT 58 PN'T UD ~;~~~~ L!J© I o 1s I o I o I o I 2 I 3 17 101 o 11 12 i 6 I B I o I© I o I 2 I 2 I s I B I o IG) 8 . 60 61 DOCKET NUMBER 68 69 EVEN! DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

!IIJ I During routine surveillance, Equipment Operator discovered level in the 2/ 3 diesel generator coolant water exp.ansion head tank overflowing thru the vent 1 line. 2/3 till tITJ I D/G w:as declared inoperable. Both Unit 2 and Unit 3 D/G's, low pressure core cooling

~ and containment cooling subsystems were proven operable, therefore this event was of J...J2_J fJ:§J .1 minimal safety significance. First event of this type at Dresden.

till mJ8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE tm I El El@ ~@ l.!:J@) I H ,, T I E x Ic I H I@ ~@) ~@

8 9 10 11 12 13 18 19 20 REVISION

(."::;\ LE R/RO CV18 ENT YEAR I0 I SEQUENTIAL REPORT NO.

OCCURRENCE CODE RE?ORT TYPE NO.

\:..:,J REPORT NUMBER Io 10 18 I I /I Io I 3 I L!J L2.J 21 22 23 24 26 27 . 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATIACHMENT NPRD-4 i'RIME COMP. COMPONENT TAKEN ACTIO"J ON PLANT METHOD . HOURS SUBMITTED FORM ::;UB. SUPPLI E:i-1 MANL'FACTURER

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. CAUSE DESCRl?TION AND CORRECTIVE ACTIONS @

tI2J I Upon investigation it was determined that the D/G cooling water heat exchanger had tIIJ I some tube leaks causing service water to enter the coolant system. Tube leaks will tIIJ I occur in heat .exchangers due to normal environmental wear The heat ex-

!J1] Ir.hanger was pressure tested and-seven tubes were plugged. Following repairs the 2/3

}:ID I D/G was run satisfactoI.'ily .. No further action is required.

8 9 . BO FACILITY STATUS °'o POWER OTHER STATUS IJQ\

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METHOD OF DISCOVERY DISCOVERY DESCRIPTION r.:;:;-.

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9 I 0 I 9 I 7 l@I Unit 10 12 11 3 in refuel

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~@)l __Da_i_*1_y_D_i_e__s_e_l_C_h_e_c_k_ _ _ _ _ _ _ _ _. ,_.,I 45 46 80 ACTIVITY CONTENT r::;;-.

>--r,;"iRELEASED OF RELEASE AMOUNT OF ACTIVITY l(V LOCATION OF RELEASE@

~ ~@) ~@l NA . NA B 9 10 11 44 45 so PERSONNEL EXPOSURES Q, NUMBER r:;:;-. TYPE DESCRIPTION

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8 9 11 12 13 so PERSONNEL INJURIES (';"';\

NUMBER OESCRIPTION6

TIJ B 10 9

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11 12 80 LOSS OF OR DAMAGE TO FACILITY f'43\

TYPE DESCP.li>TIQN '\:..::.)

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. NA so PUBLICITY (.;;\ A SE ISSUE De:;\ IJESCR1PT10N ~ N C U ON l. *i "'

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PHONE: ____x_s_2_9________________

0 NAME CF ?REPARER M. Korchynsky o.