IR 05000269/1972003
| ML19316A073 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/10/1972 |
| From: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19316A070 | List: |
| References | |
| 50-269-72-03, 50-269-72-3, NUDOCS 7911210744 | |
| Download: ML19316A073 (2) | |
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U. S. ATOMIC E'IERGY COMMISSION
REGION II
I DIVISION OF COMPLIANCE t
C0 Inquiry Report No. 50-269/72-3 Subject: Duke Power Company Seneca, South Carolina License No.: CPPR-33 Facility: Oconee Nuclear Station Unit 1
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Descriptive Title: Accidental Trip c^ ECCS Systems Prepared By: _
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g G.~E. Murphy, Reactor Inspector Date A.
Date and Manner AEC Was Informed:
Mr. J. E. Smith, Superintendent, Oconee Nuclear Station, advised the inspector of the problem by telecon on March 9, 1972.
B.
Description of Particular Event or Circumstances:
Mr. Smith advised the inspector that the event occurred as an instru-ment technician was adjusting a reactor building pressure switch.
The pressure switches for the ECCS trip had been replaced. The technician calibr ted one switch and had started calibrating the second switch. He lost sight of the fact that the logic channel locked in the trip position. When the second channel was tripped, the ECCS
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system trip signal was initiated. The HP and LP injecticn pumps started automatically as they should. The reactor building spray
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system and the Keovee hydro units were locked out at the time and did not start. The reactor coolant loop was at 535 F and 2155 psig for hot functional testing at the time of the occurrence. The high pres-sure injection system pumped sufficient water into the system to raise the pressurizer level 100 inches. Because of the high system pressure, the low pressure system did not inject any water into the reactor coolant system. Operator response to the incident was correct according to Smith.
C.
Actica by Licensee:
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Personnel vill be cautioned to nore closely review their actions to preclude such occurrences.
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2-CO Inquiry Rpt. No.-
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50-269/72-3 Smith stated that the licensee does not plan to report the incident since B&W has advised them previously that a single occurrence of pumping cold water into the system would n.t cause a failure to the systua components. A test of the HP system at 1500 psig had been scheduled.
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