ML20084Q099
| ML20084Q099 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/08/1974 |
| From: | Stephenson B COMMONWEALTH EDISON CO. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| BBS-74-49, NUDOCS 8306130122 | |
| Download: ML20084Q099 (2) | |
Text
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Commohlth Edison h
A Outd-Citia ven:r: ting Station l
1 Post Office Box 216
.h5 Cordova, Illinois 61242 Telephone 309/654-2241
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John F.
O' Leary, Director 6
e Directorate of Licensing
"'l'N Regulation U. S. Atomic Energy Commission Washington, D.
C.
20545
Subject:
Quad-Citics Nuclear Power Station Docket No. 50-254 & 50-265 DPR-29 & 30, Appendix A, Section G.6.B.2.c
Dear Mr. O' Leary:
As reported to you in my letter of February 7, 1974 a problem was encountered recently while performing maintenance on a Re-sidual Heat Removal (RHR). service wa.ter. system valve.- In
' 'fifwirig. thisl event we havkconcitid'ect"thist'the'-as-bnili. co.f.re-nditi6n.-
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of this system should be reported as an unusual event as described in section 6.6.B.2.c of the Technical Specifications since a possible single failure could result in a failure of the con-tainment cooling system to perform its intended function.
The maintenance referred to above was the repair of a bent stem on the 2B RHR heat exchanger service water discharge valve, MO 2-1001-5B.
The 14" discharge from the 2B heat exchanger joins the discharge from the 2A heat exchanger downstream of the 5B valve.
This 18" header from the heat exchangers goes to a 30" header and,then to.the 48" service water.sys. tem river discharge headei.* It. appear.s. that if.a. piping: failure were postulated to-occur downstream of the SB valve in the reactor building, oper-
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ation of either containment cooling subsystem would be limited by the discharge of river water within the station.
SAFETY IMPLICATIONS The probability of such a failure occurring simultaneously with the analyzed loss of coolant accident is remote.
Any failure occurring during unit operation would be immediately obvious and necessitate a shutdown.
CORRECTIVE ACTION This problem is being referred to the Offsite Review and Investi-gation Function for review in accordance with section 6.1.G.l.a.
(3) of the Technical Speci'fications.
A reciues for a piping h
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Mr. J. F. O' Leary March 8, 1974 modification to alleviate this condition will also be initiated in accordance with Procedure 3-51 of the Commonwealth Edison Com-pany Quality Assurance Manual.
Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION i
D An B.
B.
St henson Station Superintendent BBS/lk cc:
Regional Director Directorate of Regulatory Operations-Region III
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