ML19320A155
| ML19320A155 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/07/1977 |
| From: | Mardis D ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19320A146 | List: |
| References | |
| NUDOCS 8004140748 | |
| Download: ML19320A155 (4) | |
Text
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1.
Reportable Occurrence Report No.
50-313/77-S 2.
Report Date: 3/7/77 3.
Occurrence Date: 1/28/77 4.
Facility: Arkansas Nuclear One-Unit 1 Russellville, Arkansas S.
Identification of Occurrence.- A pinhole leak on the upstream pipe-to-valve weld of Valve RBV-77B. This valve serves as a means of venting the "B" Reactor Coolant Pump seals during initial fill of the RCS.
6.
Conditions Prior to Occurrence:
Steady-State Power ____
Reactor Power 0
MWth Hot Standby Net Output 0
MWe Cold Shutdown Percent of Full Power 0
Refueling Shutdown Load Changes During Routine Power Operation Routine Startup Operation
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Routine Shutdown Operation Other (specify)
Hot Shutdown l
7.
Description of Occurrence:
At approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on January 28, 1977, during a routine walk-through inspection by Operations Personnel prior to cooldown for refueling, a pinhole leak was observed on the upstream pipe-to-valve weld of Valve RBV-77B.
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_e Peportable Occurrence Report No. 50-313/77-5 8.
Designation of Apparent Cause of Occurrence:
Deign Procedure Manufacture Unusual Service Condition Including Environmental Installation /
Construction Component Failure (See Failure Data)
Operator Other (specify): Unknown 9.
Analysis of Occurrence:
Since the Reactor Coolant System leak rate prior to shutdown was only approximately 0.5 GPM, there was no hazard t. the health and safety of the public.
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- I Reportable Occurrence Report No.
50-313/77-5 i
10.
Corrective Action:
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Re repair of the weld is scheduled during the current refueling outage.
A followup report will be submitted after the repair is completed.
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Failure Data:
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D is is the second failure in this area. See Abnormal Occurrence Report 74-14.
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