ML19322B669
| ML19322B669 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/19/1977 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19322B666 | List: |
| References | |
| NUDOCS 7912040689 | |
| Download: ML19322B669 (2) | |
Text
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DUKE POWER COMPANY Powzn Burtnzws 422 Socra CacBen STwzzT. CaABLOTTr. N. C. asa4a WIL LI A M O. PAmmER.JR.
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37 3-4C e 3 October 19, 1977 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Suite 1217 230 Peachtree Street, Northwest Atlanta, Georgia 30303 Re:
RII: JE0 50-269/77-19 50-270/77-19 50-287/77-19
Dear Mr. O'Reilly:
With regard to Mr. F. J. Long's letter dated September 26, 1977 which transmitted OIE Inspection Report 50-269, -270, -287/77-19, Duke Power Company does not consider this information to be proprietary.
Please find attached a response to the apparent items of noncompliance identified in the subject inspection report.
Very truly yours,
/
w.'. lj.
~f William O. Parker, Jr(]
MST:vr Attachment ec:
Director, Office of Management Information and Program Control 19120 @
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.,g RESPONSE TO OIE INSPECTION REPORT 50-269, -270, -287/77-19 Item A Specification 6.4.1 for this facility requires in part that the station be operated and maintained in accordance with approved procedures.
Contrary to this requirement procedure PT/0/A/120/1 was not followed in the rotation of the fuel assembly damaged on August 23, 1977, in the line scan tester.
RESPONSE
The referenced procedure PT/0/A/120/1, "Oconee PIE Program - FA Rotation in LST," specifically addressed only the use of the handwheel or crank which drives the lower turntable in the line scan tester.
Personnel per-forming the fuel examination procedures were familiar with the content of the procedure, however, and at that time did not consider that the procedure prohibited the use of a tool to manually rotate the upper floating turntable.
Operation in this manner was considered technically correct and a properly reviewed and approved revision to the procedure would have been processed had it been recognized as necessary.
It is also considered that this action did not contribute to the damage to fuel assembly 1D40.
'In order to provide assurance that instances such as this do not occur in the future, formal communications have occurred with the vendor emphasizing the need for strict compliance with procedures.
Also, a meeting will be held with site personnel responsible for the conduct of fuel examinations prior to any additional examinations.
Item B Facility Technical Specification 6.1.2.1 requires in part that temporary changes to procedures be approved by two members of the station staff at least one of whom holds a senior reactor operator's license on the unit affected, and that such procedure changes be reviewed within seven days by the station manager or his designee.'
Contrary to the Technical Specification, changes were made in the conduct of Enclosures 9.4 and 9.6 in preparation for the August, 1977 refueling of Unit 1 to the procedure OP/0/A/1503/1 without the required approvals and review.
RESPONSE
Personnel involved in this incident have been reprimanded.
In order to assure dissemination of the cause of this incident, it was discussed at the
.ober 13, 1977 shift Supervisors' meeting.
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