ML20050D999
| ML20050D999 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/02/1982 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RO-50-219-82-20, NUDOCS 8204120455 | |
| Download: ML20050D999 (3) | |
Text
.. '
- TO:
Ronald C. Haynes Administrator of Regulatory Operations Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 FROM:
G P U Nuclear Oyster Creek Nuclear Generating Station Docket No. 50-219 Forked River, New Jersey 08731
SUBJECT:
Reportable Occurrence Report No.50-219/82-20/01P The following is a preliminary report being submitted in compliance with the Technical Specifications, paragraph 6.9.2.a. (3).
REPORT DATE:
April 2, 1982 Preliminary Approval:
Peter B. Fiedler Vice-President - Director Oyster Creek Director (2)
Of fice of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.
20555 4
in NRC Resident Inspector (1)
O b
Oyster Creek Nuclear Generating Station Forked River, New Jersey 08731 NECEfygg
]
APR1g1982s.6 n
\\
Toc 0
6 1
020412Og58 9
0 DR ADO PDR g
S'i\\
y-OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/82-20/01P Report Date April 2, 1982 Occurrence Da te April 1, 1982 Identification of Occurrence It was identified that an abnormal degradation of the primary containment existed based on the results of leak rate testing performed on the Main Steam Isolation Va lves.
This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.a.3.
Conditions Prior to Occurrence The reactor was in the cold shutdown condition at the time the occurrence was identified.
De scription of Occurrence On February 8,
1982, while per f o rming local leak rate tests on Main Steam Isolation Valves, the leak rate for valve NS03A was found to be outside of the acceptable limit.
On March 28, 1982, the other Main Steam Isolation Valve in the "A" line, NSO4A, was leak tested and the results of this test were also unacceptable due to a packing leak in NSO4A.
In the "A"
line packing leak in the NSO4A and excessive leakage piping configuration, a
through NS03A provides an abnormal flow path from the reactor vessel to the secondary containment.
Ap pa re n t Cause of Occurrence The apparent cause of the occurrence is under investigation.
gC
p
-o Reportable Occurrence Page 2 Report No, 50-219/82-20/0lP Analysis of Occurrence At the present time it is not known if this abnormal leakage path existed during power operation.
A more complete analysis will be made as the investigation of this event continues.
Corrective Action Valve NS03A was disassembled and repaired, and it passed the subsequent leak rate test.
The valve packing on valve NSO4A was tightened and the valve was re-tested, and it subsequently passed.
l I
l 1
i t