ML20031C296
| ML20031C296 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/25/1974 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| AO-74-20, NUDOCS 8110070035 | |
| Download: ML20031C296 (4) | |
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Mr. J. F. O' Leary, Director Re: Docket 50-155
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Directorate of Licensing License DPR-6 US Atomic Energy Coz=nission Big Rock Point i
Washington, DC 20545 A0-20-74
Dear Mr. O' Leary:
Attached is our report of Abnormal Occurrence No A0-20-Th.
This report covers a procedural deficiency in a system checkoff.
I Yours very truly,
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I Ralph B. Sewell (Signed) 4 i
Riti/mel Ralph B. Sevell I
Nuclear Licensing Adninistrator 1
CC: JGKeppler, U3AEC i
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ABNORMAL OCCURRENCE R2 PORT 1.j Big Rock Point Plant 1.
Report No: AO-20-74, Docket 50-155
' 2.
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Report Date: July 26, 1974 b.
Occurrence Date: July 15, 1974 3.
Facility: Big Rock Point Plant i
4.
Identification: Refueling operation with Post-Incident system.
valve out of service.
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5 Conditions Prior to Occurrence: Refueling shutdown.
i 6.
Description of Occurrence: As required by Technical Specifications, during each refueling outage and prior to loading fuel, the operability 2
of the automatic valves within the Post-Incident system has to be j
tested. The system was tagged out of service and the test completed on July 13, 1974. On July 14, 1974, the valve checkoff sheet of tbc q
system was run prior to commencement of fuel reloading. However, the j
supply root valves were still closed and tagged out. Fuel loading j
ccamenced on the "A" shift at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> and twelve fuel elements -
j were loaded with the Post-Incident system unavailable. Discovery was j
at 0800 on July 15, 1974, at which time the fuel loading procedure i
was suspended.
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Designation of Apparent Cause: Procedural deficiency.
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8.- Analysis of Occurrence: 'Ihe supply root valves of the Post-Incident f
sestem have always been considered as a part of the fire system and c
checked off as such. Analysis shows that these valves can really be a
considered common to both systems which enhanced the procedural de-ficiency. It was assumed that the system was available for service when so specifying 1:. the initial conditions of the procedure to com-j t
mence the refueling operation. If the system had been called on for 1
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sedice, ita deficiency would have been detected through instrumenta-
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tion indicating " loss of flow." However, it is felt that during re-
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fueling, the situation would have been readily detected through other means and there would have been more than ample time to take ccrrective
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action to return the system to service.
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This is because, in order to refuel and acccmmodate the transfer cask.
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approximately 10,000 gallons of additional water are flooded above the
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reactor flange. Normal experience has shown in the past that it takes 1
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/osas' approxinetely four hours to drain this water through a 2-inch line.
For a 3-inch line break, the operator would haire at least two hours to take corrective action before the water level would drop to the reactor flange level and, at this point, there are still approxi-mately 2,000 gallons of water to drain before starting to unwater any fuel assemblies.
9 Corrective Action: Changes will be made to the Post-Incident system valve check sheet to include the root valves which are located in the fire system. In addition, outstanding r. witching orders are to be reviewed by the shift supervisor and documented as such on the master start-up check sheet.
- 10. Failure Data: Not Applicable
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