ML19320A107
| ML19320A107 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/08/1975 |
| From: | Cavanaugh W, Phillips J, Reuter D ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19320A102 | List: |
| References | |
| NUDOCS 8004140711 | |
| Download: ML19320A107 (3) | |
Text
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1.
Abnormal Occurrence Report No. 50-313/74-14 2.
Report Date:
1/6/75 3.
Occurrence Date:
12/28/74 6
4.
Facility:
Arkansas Nuclear One-Unit 1 i
Russellville, Arkansas 6
5.
Identification of Occurrence: -Pinhole leak on the upstream pipe to va weld on valve RBV-77B. This valve serves as a means of venting the re coolant pukp seals during initial. fill of the reactor coolant system.
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particular valve vents the seal on "B" reactor coolant pump.
6.
Conditions Prior to Occurrence:
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Steady-State Power Reactor Power 0
MWth Hot Standby Net. Output 0
MWe Cold Shutdown X
Percent of Full Power 0
Refueliag Shutdown i
i Routine Startup Operation Routine Shutdown Operation Load Changes During Routine Power Operation Other (Specify) l 7.
Descriotion of Occurrence:
At approximately 12:30 p.m. on December 28, 1974, during a routine wal through inspection by operations ' personnel, a pinhole leak was observe on the upstream pipe to valve weld on RBV-77B.
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- 800414o74 July S, 1974 NSP-10, Rev. O Page 1 of 3 -
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LJ Abnormal Occurrence Report No. 50-313/74-14 Sheet 8.
Designation of Apparent Cause of Occurrence:
Design Procedure
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Manufacture Unusual Service Condition. Including Installation /
X Environmentai Construction Component Failure Operator Other (Specify)
This pinhole leak is considered an isolated incident of non-generic consequences. Particularly sensitive variables such as temperature, amount of weld material, etc. may have affected the situation.
9.
Analysis of Occurrence:
Prior to or at the time of the discovery of this occurrence, there.t no safety implications or har.ard to the health and safety of plant personnel or the public. This is due to the fact that the reactor coolant system leak rate was less than 1 gpm prior to shutdown and 1' the plant was at cold shutdown at the time of discovery.
10.
Corrective Action:
This weld h'as been ground out and rewelded. A dye penetrant check.
been completed with no defects noted.
E s
d July 5, 1974 NSP 10-, Rev. O Page 2 of.
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Abnormal Occurrence Report No.
50-313/74-14 Sheet 3 I
11.
Failure Data:
There were no equipment failures as a result of this. occurrence.
There is no previous record of this type occurrence in this particular i
area.
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12.
Revious and Approvals:
Reviewed and Approved by:
Plant Safety Committee Yes (X)
No ( )
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Plant Superintendent Yes (X)
No ( )
Reference:
JWA-760 Date:_1/2/75
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Reviewed by:
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Date:
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Licensing Supervisor Approved by:,
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Date:
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Safety Review Committee
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Approved by:(,)
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_/A Date:
"~ Manager of Nuclear Servic M Appreved by:
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[hr4 Date: /-2-7
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Director of Power Production Approved by:
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/f Date: /.I 7 '
9 Senior Vice President
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July S, 1974 NSP-10, Rev. O Pue 3 of 3