ML19350C403
| ML19350C403 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/24/1981 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 8104010436 | |
| Download: ML19350C403 (2) | |
Text
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UNITED S1 ATES NUCLEAR REGULATOHY COMMISSION f[c}t -
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Q Georgia Power Company ATTN:
J. H. Miller, Jr.
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V Executive Vice President
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270 Peachtree Street
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Atlanta, GA 30303 D
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k Gentlemen:
Subject:
Can'irmation of Action This refers to R. D. Martin's teiechone conversation o. Marcn 2t, 1931, witn Mr. W. A. Wicner, Vice President and General Manager-Nuclear Generation regard-ing operation of Hatch Unit 2 with the four channels of safety-relatec drywell pressure instrumentation inoperable.
With regard to the matters discussed, we understand that you will initiate the fellcwing actions:
1.
Investigate the event of March 23, 1931, involving operation of the reactor with the required safety-related crywell oressure systems inoperable cue to misalignment of instrumentation isolation valves.
As a minimum, your investigation will include the following items:
a.
Determine the cause of the incorrectly positioned valves.
b.
Determine why the mispositioned valves were not identified by the operating staff for over fourteen days.
2.
Initiate a special audit including representatives from the Georgia Power Company corporate quality assurance anc training staffs, of the facility management control systems and cersonnel, to determine tne ceficiencies which contributed to the event described above. As a minimum, this accit will include the following items:
a.
A review of the independent verification controls which assure precer safety-related system alignment.
b.
A review of the procedural controls which govern prcper safety-related system operation.
c.
A review of the verification controls that assure procer safety-related system restoratica following maintenance or testing.
d.
A review of the verification and documentation controls which assure that a'l operations personnel are cognizant of the current status of all safety-related equipment, and control bcard swittnes, parameters, and alarms on each shift.
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Identify critical system vaives whose mispositioning could defeat the designed safety functions of those systems.
Perform a verification of the valve positions to assure correct alignment. Subsequent manipulation of these critical system valves will have independent verification performed until the results of the investigation and audit have been discussed with Region II.
4.
Discuss the results of your investigation and corrective actions in a meeting to be conducted in the Region II office no later than April 3,1981.
The results of these activities will be documented in a special report following this meeting.
Please inform this office promptly if your understanding of this matter is different from that stated above.
Sincer James P. O'Reilly
/
Director cc W. E. Ehrensperger, Vice President Engineering / Construction W. A. Widner, Vice President and General Manager--Nuclear Generation M. Manry, Plant Manager
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