ML20202F822
| ML20202F822 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/03/1986 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 0163A, 163A, NUDOCS 8604140228 | |
| Download: ML20202F822 (3) | |
Text
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c-GPU Nuclear Corporation Nuclear
- n
- ;388 Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
April 3, 1986 Mr. Harry B. Kister, Chief Division of Project and Resident Programs U.S. Nuclear Regulatory Coranission Region I 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Kister:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Inspection Report 86-02 Attachment I to this letter provides GPU Nuclear's response to the violation identified in Appendix A of your letter dated February 28, 1986.
In the event that any comments or questions arise, please contact Mr.
John Rogers of ray staff at (609)971-4893.
Very truly yours,
)
m et iedler Vice President and Director Oyster Creek PBF/JJR/ dam (0163A)
Attachment cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.
%04t4o228e60jg9,
Bethesda, MD 20014 ApocW 05 PDR Mail Stop No. 314 g
G NRC Resident Inspector Oyster Creek Nuclear Generating Station i
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation g
g t-
ATTACHMENT I Violation:
l Technical Specification 3.5. A.8.a requires that all hydraulic snubbers listed in Table 3.5.1 shall be operable during all modes of operation except cold shutdown and refuel.
l Contrary to the above, on January 2t,1986, during full power l
operations, an operable snubber listed in Table 3.5.1 (NQ-2-S7) was made inoperable to remove a part for use on a nonsafety-related snubber.
1
(
Response
f-GPUN concurs in the violation.
l The violation occurred as a result of corrective maintenance which was L
performed while the reactor plant was at power. On January 6,1986, a damaged snubber was identified on a non-safety related system. A spare for the damaged part, the front paddle, was obtained from tne warehouse.
It was determined that the new paddle was shorter in length than the old paddle (original equipment) and could not be used to replace the damaged paddle. A search was conducted to locate a snuDoer l
whose front paddle could be replaced by the shorter paddle from the l
warehouse. Snubber NQ-2-S7 (Containment Spray System) was chosen as it was easily accessible and did not involve contamination concerns.
A maintenance short form was written to swap the front paddle on NQ-2-S7 with the spare paddle. The work was authorized by the Group Shift Supervisor (GSS) who misunderstood the requested maintenance. The GSS thought the damaged paddle was on NQ-2-S7. Subsequently, NQ-2-S7 was disconnected and the paddles were swapped. The safety related snubber was inoperable for approximately 10 minutes. The swapped paddle was placed on the non-safety system restoring both systems to operability.
A Licensee Event Report (LER 86-002) was issued on February 21,1986 to document the occurrence in accordance with 10CFR50.73.
The LER identified the root cause as personnel error in that the GSS approved a maintenance task which placed the plant in a Limiting Condition for Operation.
Immediate corrective action was taken to ha'it all maintenance on safety related snubbers unless the snubber had been determined to be inoperable. Additionally, personnel initiating maintenance short forms were instructed to be more clear and concise in their descriptions of work to be performed. These actions have been effective in that tnis event has not recurred.
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. Corrective action has also been initiated to distribute LER 86-02 as required reading to all GSS's and maintenance planners. This required reading will be completed by May 15, 1986. Additionally, the plant procedure relating to the removal and replacement of snubbers, 775.1.004, will be revised to clarify and define those precautions and limitations applicable to safety related snubbers. This revision is presently scheduled to be issued by April 15, 1986.
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