ML19322A907
| ML19322A907 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/03/1973 |
| From: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | James Keppler US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19322A898 | List: |
| References | |
| NUDOCS 7911270664 | |
| Download: ML19322A907 (3) | |
See also: IR 05000269/1973001
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UNITED STATES
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ATOMIC ENE7GY COMMISSION ~
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January 3, 1973
J. G. Keppler, Chief, Reactor Test and Operations Branch, Directorate of
Regulatory Operations, Headquarters
ADVANCE INSPECTION INFORMATION - DUKE POWER COMPANY (OCONEE 1), REPORT
No. 50-269/73-1
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The Oconee Nuclear Plant Superintendent, J. E. Smith, telephoned the
- Region II inspector, R. F. Warnick, at approximately 8:45 a.m. on
December 30, 1972, and infor ed him of an oil fire experienced in the
Unit I reactor building on and in the ic=ediate area of the 1B2 reactor
coolant pump (RCP-1B2).
The inspector arrived at the reactor site at 3:15 p.m. to personally
observe the area where the fire occurred.
According to entries in the shift supervisors' logbook, the " FIRE"
stat alarm was received in the Unit 1 control room at 0725 on
December 30, 1972. A checx of the alarm panel indicated the alarm
originated in the reactor building. Operators visually confirmed
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there was a fire on RCP-132 and on the 132 steam generator outlet "J"
leg. The fire was extinguished with CO2 from portable bottles.
When the fire alarm was received, the reactor coolant system was at
5250F and 2155 psig for hot functional tests; however, no tests were
in progress. RCP's 1A2 and 132 were operating.
The 1B2 AC and DC oil lift pu=ps were started at 0722 in preparation
for stopping RCP-132. At 0724 RCP-182 was stopped,'and at 0726 the
1B2 oil lift pu=ps were stopped. The shift supervisors' logbook stated
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that these actions were routine and were not taken sa a result of the
fire.
The fire was caused by oil from the oil lift pump system falling on
the hot reactor coolant system piping. The oil escaped from a flanged
joint near the oil system pressure relief valve, drained to the
25 gallon capacity lower bearing housing reservoir, overflowed and
fell onto the pump, piping, and floor below.
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TRANSMITTED VIA FACSIMII.E
1/3/73 - re - 3:30 p.m.
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J. G. Keppler
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January 3, 1973
7:
The inspector was informed that the oil was Texaco Regal B rust and
oxygan inhibited (R and 0) oil and that the flash point was approximately
4250F.
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During the original notifying phone conversation, the inspector was told
the oil leaked from a " blown" flange gasket. On January 2, 1972, the
inspector was informed that the failed gasket was a "Velomoid" oil
resistant material. While at' the site, the inspector was told that this
was the third gasket failure oil leak to occur on the oil lift system,
but the first leak with the reactor coolant system hot.
On January 2,1972, the plant superintendent informed the inspector that
the following corrective actions have been taken:
1.
The reactor coolant system was cooled down to reduce the system
temperature below the oil flash point, and to permit re= oval of the
'1dirror" insulation for examination and cleanup.
2.
The "Mi_ror" insulation was removed, inspected by a factory
representative, and determined to be undar. aged.
3.
The piping and surfaces beneath the insulation were cleaned.
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4.
All Velomoid gaskets on the oil 11ft system were replaced with
asbestos saskets.
5.
The RCP cil leakage collection drain lines have been temporarily
rerouted to drain into oil barrels.
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6.
Westinghouse has been contacted to aid in determining a per=anent
solution-to the problem.
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The spilled oil has been cleaned up.
The inspector was informed on January 2, 1972, that the reactor coolant
system was at 400 psig, that hot functional testing conditions were being -
re-established, approximately 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> at hot conditions are needed to
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complete the hot functional tests, and that approximately three and a
half days have been lost because of the fire.
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)<*G. Keppler
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January 3, 1973
While at the site the inspector observed small areas of charring on
the " Mirror" insulation of the reactor coolant pump and the
"J" leg
of the steam generator, some charring on an empty cable tray and small
diameter piping, and oil on both horizontal and vertical surfaces below
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the oil lift system. No smoke was visible in the reactor building and
only minor fire odors remained eight hours after the fire.
From the information available at the present time, it is possible that
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this incident has generic significance. This possibility will be
reviewed during the next inspection. DPC has not determined at this
time whether this is a reportable incident as defined in 10 CFR 50.55(e).
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C. E. Mur h , Act ng Chief
Facilities Test and Startup
RO:II:CD!
Branch
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