ML19345G662
| ML19345G662 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/20/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19345G661 | List: |
| References | |
| NUDOCS 8104090097 | |
| Download: ML19345G662 (4) | |
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D1IKE Powra COMPANY
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March 20, 1981 3, s:.3 svu a.: m.
Mr. James ?. O'Reilly, Director U.S. Nuclear Regulatory Cocanission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: RII:FJ 50-269/81-02 50-270/81-02 50-287/81-02
Dear Sir:
With regard to R. C. Lewis' letter.of February 24, 1981 which trans=itted the subject inspection report, Duke Power Cc=pany does not censider the infor=a-tien contained therein to be proprietary.
Please find attached a response to the cited items of ncncompliance.
I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge, executed on March 20, 1981.
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.truly.yours,
/
L). _ _ - j vmiam O. Parker, Jr.
JIJ:pw Attachment e
d 810 40900910 d
DUKE POWER COMPANY OCONEE NUCLEAR STATION Response to IE Inspection Report 50-269/81-02, -270/81-02, -287/81-02 i
i Violation A l
Technical Specification 6.4.le, requires adherence to procedures for maintenance i
on systems affecting nuclear safety.
Contrary to the above, on January 23, 1981, the Low Pressure Injection pump on i
Unit 3 was removed from service for maintenance without completing the double verification.
This resulted in an incorrect valve alignment, which in turn, permitted the water level in the reactor vessel to unintentionally drop to r
approximately 36 inches above the fuel assemblies.
3 This'is a Severity Level V Vialation (Supplement I.E.) applicable to Unit 3.
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Response
.This violation resulted ; rom personnel errors. The Removal and Restoration sheet for the'"3C" LPI pump was incorrectly filled out by a Reactor Operator, specifying valve 3LP-8 to be closed and tagged instead of 3LP-6.
The erroneous "R&R" sheet was then approved by the Unit Supervisor. The resulting incorrect-1 i -
valve line-up caused the water level'in the reactor vessel to drop.
AImmedfate corrective action included correcting the valve line-up, restoring the correct. vater level in the Reactor Vesseland restoring LPI _ flow for decay heat removal. 'As'further corrective action, the personnel involved in this incident have been counseled The incident' has been discussed in
.a meeting of'all Shift-Supervisors,.and the' requirement of a more thorough i
review of. '?R&R" sheets prior to use has been stressed. -The Removal and n
.Rasr. oration procedure is currently being reviewed for adequacy, and any appro-
.priate revisions'should be made by May 1, 1981.
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. Violation-E-Technical Specification 6.4.la requires adherence to procedures for startup operation and shutdown of th'e facility.
.'ContraryLto the above,.on January 5,-1981,.the~ turbine-building sump, which
-was being batch released due to an apparent steam generator tube leak,!was not
~ returned to local manual control as required by procedure OP/0/A/1106/31 Control
- of secondary Contamination. This'resulted in approximately 12000 gallons of 1-water-being release d..
~ This. is a ' Severity Level V. Violation (Supplement I.E.) applicable ' to Unit 1.
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- Violation B (Cont'd.)
Response
This violation resulted from personnel error.
The operator assigned to pump the Turbine Building sump failed to open the pump breaker after the sump level decreased enough to automaticany stop the pump. This was due to diver-sion of his attention to other dutiet. The sump level then increased enough for the pump to restart and. release more water. Upon discovery, the pump
. breaker was opened and the release terminated.
Sump samples revealed no Part 20 or Technical Specification limits were exceeded during the releases.
The operator involved has been counseled on his perfor=ance.
Each sump release now has an operator assigned full-time to monitor and control the release.
.d
Violation C Technical Specification 3.12.3 requires that during the period when the reactor vessel head is removed and ir adiated fuel is in the reactor b tilding, the polar crane shall not be operated over the transfer canal.
9 Contrary to the above, on January 6, 1981, Oconee Mechanical Maintenance personnel operated the Unit 3 polar crane iver the fuel transfer canal while the reactor fuel handling was in progress.
is a Severity Level V Violarion (Supplement I.E.) applicable to Unit 1.
Response
This violation was a result of inadequate training of the polar crane operator and flagman on the requirements of Technical Specification 3.12.3.
When other personnel observed the crane being operated over the transfer canal, the operator was immediately instructed to move the crane from over th. canal.
The operator and flagman were then instructed on the requirements of Technical Specification 3.12.
Further corrective action will include the following:
- 1) All polar crane operators will be trained on proper operation of the crane in compliance with Technical Specification 3.12.
- 2) This incident will be discussed in crew meetings with approp. m te personnel.
- 3) A list of qualified polar crane operators will be established.
I The above corrective actions will be completed by April 15, 1981.
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