ML20107B315

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Discusses & Forwards RO Insp Rept 50-219/72-05
ML20107B315
Person / Time
Site: Oyster Creek
Issue date: 03/09/1973
From: Caphton D
US ATOMIC ENERGY COMMISSION (AEC)
To: James Keppler
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 NUDOCS 9604160216
Download: ML20107B315 (2)


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'y, J. G. Keppler, Chief, Reactor Testing & Operations Branch Directorate of Regulatory Operations, HQ RO INSPECTION REPORT NO. 50-219/72-05 JERSEY CENTRAL POWER & LIGHT O(3tPANT

, OYSTER CREEK - BWR The subject inspection report is forwarded for your information.

Six violations were identified in this report and a letter has been sent to the licensee regarding these matters. Based upon the concerns in the radiological area identified by this report I

and a subsequent inspection (R0 Report 50-219/73-02) of this l

subject area, a corporate level management meeting was held on March 1, 1973. The licensee appears to be responding to the issues; we are following these matters closely.

It is my opinion that one of the underlying problems at this facility is the lack of capacity of the plant to process liquid radioactive wasta.- Ity concerns in this area are further highlighted when I see long times between regeneration of domineralisers, i.e., up to 125 d gs. This facility also g.g has experienced main condenser tee leaks as referenced in this report.

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.j A flaking condition was observed on irradiated fuel channels.

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Sanples are to be shipped to GE for metalographic studies.

We will inform you of the findings when available.

I A number of mainten=ce type items are covered in the report with apparent causes ranging from past to current QC problems.

-We are currently pursuing the QA for operations issue with 4

this licensee and are making progress.

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SURNAME >

w, 3/9/73

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Form AEC-HS (Rev. 9-M) AECM 0240 a

9604160216 960213' i

PDR FOIA DEKOK95-258 PDR

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This report discusses design changes made to the circuitry l

of the liquid poison system and the stan6y gas treatment systen.

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2his report contains information regarding the following S$f i

"Hamo Route Slips" as follows:

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hrs. 3/14/72 - Bia Rohk - siphon Breaker - A PORC evaluation l

j indicated that this is not a problem at hyster Creek, even j

though the check valves in the fill lira eennot be tested.

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HRS. 6/19/72 - Paddle Type Flow aritches - Oyster Creek plans to inspect these switches during the spring of 1973 refueltag outage and evaluate the results of this inspection.

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HRS. 9/21/72 - TWJe=1 speci$catico Surynillance ameutrements -

Oyster Creek continues surveil:,ance testing progran during the j

outage.

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l hrs. 6/28/72 - Fuel sandlina Activities - oyster Creek uses een l

people.

hrs. 10/27/72 a d hrs. 11/s/72 - Delta F ca11s - oystar Creek does not have Barton Hodel 368, 344 or 386 suitdies (has 224, i

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295, 296 and 278).

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HRS. 8/9/72 - Safety Valve Aetuation C n _.__n - DW inspected for tape over pressure tape.

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D. L. Caphton i

man 4ar Reentor Inspector l

Facility Operations Branch Enclosure Subject Inspection Report l

cca RO Chief, Reactor Testing & Operations Branch, M i

20 M (5) i DR Centrel riles i

Regulatory Standards (3)

Directorate of Licensing,(13)

R0 Regional Directors l

PDR, report only j

Local FDR, report only NSIC, report only i

DTIE, report only State of New Jersey, report only l

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