ML20236T461
| ML20236T461 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/21/1998 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20236T463 | List: |
| References | |
| 1940-98-20386, NUDOCS 9807280200 | |
| Download: ML20236T461 (3) | |
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NUCLEAR Post Office Box 388 Forked River, NJ 087310388 Tel 609-9714000 July 21,1998 1940-98-20386 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 257 Changes to Administrative Controls in Oyster Creek Technical Specifications In accordance with 10 CFR 50.4(b)(1), enclosed is Oyster Creek Technical Specification Change Request (TSCR) No. 257. The purpose of this TSCR is to make several changes to Section 6 of the Oyster Creek Technical Specifications and make other changes of an administrative nature.
Specifically, Specification 6.2.2.2 (a) has been modified to provide some flexibility to accommodate unexpected absence of on-duty shift crew members. Specification 6.2.2.2 (j) refers to the Manager, Plant Operations and that position has been eliminated. The maximum time in which to forward audit reports to the responsible management positions has been reduced i
from 60 days to 30 days. In several places in Section 6 the term "Vice President" has been replaced with the tenn " Corporate Officer". In addition, several typographical errors have been corrected.'
Using the standards in 10 CFR 50.92, GPU Nuclear, Inc. has concluded that these proposed changes do not constitute a significant hazards consideration, as described in the enclosed analysis performed in accordance with 10 CFR 50.91(a)(1).
Attached to the TSCR are three unrelated changes to the Bases of Specifications 2.3,3.3, and 3.8. These changes have been reviewed in accordance with 10 CFR 50.59 and determined to
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contain no unreviewed safety questions. The change to the Basis of Specification 2.3 clarifies the applicability of the definition of top of active fuel (TAF). The change to the Basis of 9807280200 900721
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1940-98-20386 Page 2 Specification 3.3 updates and clarifies the analyzed number of thermal cycles (i.e., heatup /
cooldown) used to confirm that the original allowable fatigue usage limit is maintained. The change to the Basis of Specification 3.8 makes the Basis statement consistent with a change to the Specification approved by an earlier Amendment.
Also enclosed is a Certificate of Service for this request, certifying service to the chief executives of the township and county in which the facility is located, as well as the designated official of the state of New Jersey, Bureau of Nuclear Engineering.
If you require any further information please contact Mr. Dennis P. Kelly, Oyster Creek Technical Analyst, at 609-971-4246.
Sincerely, Michael B. Roche Vice President and Director Oyster Creek 1
MBR/DPK Enclosure j
cc: NRC Administrator, Region I NRC Project Manager NRC Senior Resident Inspector l
UNITED STATES OF AMERICA l
NUCLEAR REGULATORY COMMISSION l
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IN THE MATTER OF
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DOCKET NO. 50-219 GPU NUCLEAR, INC.
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CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 257 for the Oyster Creek
' Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission on July 21,1998 has this day of July 21 -1998 been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in thE U.S. mail, addressed as follows:
The Honorable Louis A. Amato Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By:
Michael B. Roche Vice President & Director Oyster Creek l
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