ML20084S515
| ML20084S515 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/07/1976 |
| From: | Kalivianakis N, Swales J COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NJK-76-328, RO-50-254-76-28, NUDOCS 8306170080 | |
| Download: ML20084S515 (3) | |
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Co e:lth Edison
-Quad-Cities Nuclear Power Station E pgy C()PT Post Office Box 216 Corcova. Ithnois 61242 Telephone 30?!654-2241
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J. Keppler, Regional Director Office of Inspection and Enforcement Region ill U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Reference:
Quad-Cities Nuclear Power Station Docket No. 50-254, DPR-29, Unit 1 Appendix A, Sections 3.7.D.1, 6.6.B.2.b Enclosed please find Reportable Occurrence Report No. 50-254/76-28 for Quad-Cities Nuclear Power Station.
This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.2.
Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION f
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' 'WEff N. J. Kalivianakis Station Superintendent NJK/JAS/lk
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G. A. Abrell
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s'OPY SENT REGION, r
8306170080 760907 dj PDRADOCK05000g 9
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C,U LICENSEE EVENT MT CONTROL BLOCK:l l
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l (PLEASE PRINT ALL REQUIRED INFORMATioN) 1 8
NAME LCENSE NUMBER E
TYPE 01 li lt 10 l Al Dl 1l l0 l0 l-l 0 l 0 l 0 l 0 l 0l--l0 l0 l l4 l1 l1 l1 l1l l0 l3 l 7 89 14 15 25 26 30 31 32 f)
DOCKET NUMBER EVENT DATE REPORT OATE CATEGORY T
O CONT l l
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l015 lo l-10 l 2 l 5 l 4 l l 0l 8l Ol 91 7l 6 l lo 19 10 17 l7 l 6 l 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION gg l At 5:00 pm on August 9, 1976 position Indication was lost on Reactor Water Cleanup l
7 89 80 HE I System isolation valve MO l-1201-2. in-line valve MO 1-1201-5 was immediately closed l
7 89 80 Q l In accordanCe with Technical Specification 3.7.D.2. Upon Investigation it was found l
7 89 80 DE l that the control transformer for valve MO 1-1201-2 was burned out. Primary Containment l 7 89 80 Q l Isolation Relay 595-125 was.also burned out. Work Request 2902-76 was issued and the l 7 89 80 i
mg DE CODE COMPONENT CODE SUPPUER VIOLATON 35lClGl W lC l Kl Tl RlR lK l lNl lGl0l8l0l lN l 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION DE l (Proximate Cause-Equipment Failure) Inoperability of Reactor Water Cleanup System l
7 89 80
@ l Isolation Valve MO l-1201-2 was caused by relay 595-1.25 shorting out and then burning l 7 89 80 DE l uo the cnntrol transformer.
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% POWER OTHER STATUS OtSC VERY DISCOVERY DESCRIPTON (F_]
l0 l7 l5 l l NA l {
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1 7 8 9
10 12 13 44 45 46 80 R LE SEO OF E AMOUNT OF ACTMTV LOCATON OF RELEASE 35 tz_j Iz_]ASEl l
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NA 7 8 9
10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTON EE l 0l 0l 0 l l_Zj l
NA l
7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTON
(( l 0l 010 l l
NA l
7 89 11 12 80 OFFSITE CONSEOUENCES DE l NA l
7 89 80 LOSS OR OAMAGE TO FACIUTY TYPE DESCAIPTON
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7 89 10 80 PUBLICITY DE l NA l
l 7 89 80 ADOITIONAL FACTORS D@ l (Event Desc. cont) relay and transformer were replaced within 150 minutes. valves l
7 89 80 QE l MO l-1201-5 and Mc l-1201-80 were fully operable and would have Isolated the Cleanup l
7 89 80 James A. Swales NAME:
PHONE:
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ADDITIONA'L FACTORS System had a Group 111 Isolation condition been received.
Upon return to service, MO l-1201-2 was tested satisfactorily for operability. The corrective action taken is felt to be adequate to prevent recurrence. This is the first failure of this valve; however, MO 2-1201-2 experienced a torque switch failure in December 1974.
(R0 50-254/76-28) 8 um