ML20107C759
See also: IR 05000219/1972002
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UNITED STATES
O18's
ATOMIC ENERGY COMMISSION
omslON OF COWWANCE
201 6453944
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REGION I
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870 BROAD STREET
NEWARK. NEW JERSEY 07102
May 12, 1972
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R. T. Carlson, Sr. Reactor Inspector
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Regulatory Operations, HQ
RO INSPECTION REPORT NO. 50-219/72-02
JERSEY CENTRAL POWER & LIGIIT COMPANY
OYSTER CREEK - BWR
- If there is one thing I have learned from this inspection, it is that I
- am not going to permit seven months to pass again without a routine in-
spection. . There are too many items that can't get proper attention.
For
example, my inspection list included 35 items before I entered the plant and
started reading the log books. Something is lost in our 13 pection program
when this amount of time elapses between routine inspectiors or this number
of items is allowed to develop. Of course, there were four special inspec-
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tions, but these were problem oriented inspections of limited scope.
The requested action or information was obtained for the following HQ
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memos:
1.
Torus to Drywell Vacuum Breaker Check Valves for BWRs,1/6/72 -
Information forwarded by separate memo.
2.
Millstone Point C.apany Report to DRL Describing Failure Resulting
in Loss of Automatic Blowdown Function for a Relief Valve,1/12/72 -
Licensee was informed of the problem but does not have Target Rock
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relief valves.
3.
Monticello Unit 1 - CO Inspection Report No. 263/71-13, 1/17/72 -
A circuit review by the maintenance supervisor showed that the off
gas isolation system will not reset automatically.
4.
Monticello - Differential Pressure Switch Failure, 1/12/72 -
Informed the maintenance supervisor of the contamination problem
on the jewel bearing in the DP switch. No reported failures at
Oyster Creek.
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9604170527 960213
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DEKOK95-258
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5.
Niagara Mohawk Power Corporation - Report to DRL, December 13, 1971,
1/11/72 - Licensee plans to inspect the main steam flow venturi pressure
taps during the April 1972 outage.
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6.
Monticello - Licensee Report to DRL Describing Removal of Baffles
from Torus-and Modification to Relief Valve Discharge Piping, 1/12/72
The licensee was informed of the problem and plans to inspect the torus
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at least above the water line during the April 1972 refueling outage..
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Due to the chromate in the torus water, they do not plan to drain the
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torus unicos the above water inspection indicates problems.
' 7. ' Reactor Pressure Vessel Thermal Cycles,1/11/72 - All pressure and
temperature data has been accumulated in one log.
Usage data for some
of the more important parameters has been calculated. OC p1 mas to
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review and update this data at approximately six month intervals.
8.
Oyster Creek - Isolation Relay Failure, 9/27/71 - The inspector was
informed that the specific relay in question was a basic GECR120 relay
that was modified to make it a CR122A-09041AA time delay relay. These
relays have been replaced.
9.
Dnergency Service Water Pumps, 10/27/71 - Pumps are tested monthly,
but do not have any performance specifications. Will establish standard
test pressure but can not measure flow.
10.
Reporting Abnormal Occurrences, 8/17/71 - The subject has been discussed
several times, and the licensee is being cited for failure to promptly
report an abnormal occurrence.
I was disappointed in the report of the Loss of 4160 V Emergency Bus 1C
(Letter to DRL, March 10, 1972); however, in my tel2phoae discussion with
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Ivan Finfrock, I feel that I got a camnitment to expand the use of procedures
in performing safety related maintenance work. (Inquiry Report 219/72-06,
dated 4/12/72 gives another example of the problems that occur due to the
failure to use written procedures.) I expect a dramatic change in JCP&L's
attitude toward written procedures.
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As a result of the review of the loss of the 10 emergency bus, it appears
the TS permit both a startup transformer (supplying off site power) and
an Lemergency diesel generator to be out of service at the same time
- without any cross restriction on the availability of the other.
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-question whether this is the intent of the TS.
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I am planning to go back to Oyster Creek April 21, 1972 to witn:ss their
full load turbine trip test and observe reactor startup as par 6 of the
operator licensing examination. This inspection will be Ifnited to these two
items.
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F. S. Cantrell
Reactor Inspector
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