ML19322A896
| ML19322A896 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/26/1974 |
| From: | Thies A DUKE POWER CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7911270651 | |
| Download: ML19322A896 (3) | |
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CONTROL NO:
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F ROTJ: Duke Power Co:::pany DATE OF COC D ATE R EC'D LTR T'.*!X RPT OTHER Cnarlotte, N.C.
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ORIG CC OTHER SENT AEC POR XY SENT LOCAL PDR XX Mr. A. Giambusso 1 simed CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
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A 50-270 50-287 ENCLOSURES:
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DUKE POWER COMPANY
- 3 Powra Bertorwo 422 SouTu Cnuncu STnzzT, CuARLOTTz, N. C. 28201 A. C. Ttir es 56.,0. wcc p.e s.egn, P.O. Box 2ns PnODUCTH3*e AND Taassgeesssion December 26, 1974 Ok
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Mr. Angelo Giambusso y
Deputy Director for Reactor Projects
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.f Directorate of Licensing iv, J a; ~g r -
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Office of Regulation U. F. Acou c Energy Commission Qf h giCs C
Washington, D. C.
20545 Re: Oconee Nuclear Station Docket Nos @ -270, -287
Dear Mr. Giambusso:
Oconee Nuclear Station Technical Specification 6.1.2 requires that, in matters of nuclear safety and radiation exposure, review and audit of station operation, maintenance and ::chnical matters be provided l
by two committees - the Station Review Committee (SRC) and the Nuclear Safety Review Committee (NSRC).
With regard to the on-site committee, the SRC, Technical Specification 6.1.2.1.d requires that the cocmittee have the responsibility to " review all new procedures or changes to existing procedures determined by the station Manager or his designate to affect operational safety."
In order to adequately implement this Technical Specification, the Duke Power Company, Steam Production Department, " Administrative Policy Manual for Nuclear Stations" establishes a detailed program for the review and approval of station procedures and revisions thereto.
Concerning procedure revisions, the program specifies that prior to final approval of a procedure revision the Techr.ical Services Superin-tendent, the Operating Superintendent or the Maintenance Superintendent review the revision for its safety significance.
Such an individual may approve the revision or may transmit it to the station Manager for further review.
Upon review by the station Manager, the revision may be approved, or depending on the station Manager's determination of the safety significance of the revision, the revision may be transmitted to the SRC for review.
In this manner, full compliance with the Technical Specification requirement is achieved in that those procedure revisions which are determined by the station Manager, or his designate (i.e., the group Superintendents), to affect operational safety are reviewed by the SRC prior to final approval for use.
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.Mr. Angelo Giambusso Page 2
}ecember 26, 1974 With regard to implementation of the Technical Specification requirement, examples of procedure revisions which would not require SRC review are as follows:
1.
Revisions resulting from changes to the Technical Specifications.
(Such changes are reviewed by the SRC prior to submistal to the AEC and are reviewed, approver' and issued by the AEC.)
2.
Revisions resulting from a properly reviewed and approved station modification.
(Prior SRC review of modifications to safety-related structures, systems and components is performed.)
3.
Revisions resulting from corrective actions necessitated by station incidents.
4.
Procedure revisions which the station Manager, or his designate, determine (a) do not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report, (b) do not create a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report, and (c) do not reduce the margin of safety as defined in the basis for any Technical Specification.
It is Duke Power Company's position that the above-described program fully complies with Oconee Nuclear Station Technical Specification 6.1.2.1.d.l.
The purpose of this letter is to describe our program for meeting the requirements of Technical Specification 6.1.2.1.d.l.
If it is your determination that the program does not fully comply with the requirements of t"e cited Technical Specification, please advise.
Very truly yours,
-Q.
(Y A. C. Thies ACT:vr cc:
Mr. Norman C. Moseley j
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