ML20107B029
| ML20107B029 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/11/1985 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20107B021 | List: |
| References | |
| NUDOCS 8502200208 | |
| Download: ML20107B029 (6) | |
Text
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OYSTER CREEK NUCLEAR GENERATING STATION a
PROVISIONAL OPERATING LICENSE NO. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 123, Rev. 1 DOCKET N0. 50-219 Applicant submits by this Technical Specification Change Request No.123, Rev. I to the Oyster Creek Nuclear Generating Station Technical Specifications, modified pages 4.3-1, 4.3-2, 4.3-3 and 4.3-4.
By YV Petet B. Fiedler l
Vice President and Director Oyster Creek Sworn and subscribed to before me this // ' day of hduz N
1985.
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Notary )ublic of Wew Jersey A No a bc fh u, c-o ie. u.,,,..,
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-8502200208 850211 PDR ADOCK 05000219 P
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF
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DOCKET N0. 50-219 GPU NUCLEAR CORPORATION )
CERTIFICATE OF SERVICE This-is to certify that a copy of Technical Specification Change Request No. 123, Rev. 1 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Commission on February 11
, 1985, has this day of February 11
,1985, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Henry A. Delo, Jr.
Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 4% d 8,
Peter B. Fiedler Vice President and Director Oyster Creek PBF: dam
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GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
February 11, 1985 The Honorable Henry A. Delo, Jr.
Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731
Dear Mayor Delo:
Enclosed herewith is one copy of the Technical Specification Change Request No.123, Rev.1 for the Oyster Creek Nuclear Generating Station Operating License.
This document was filed with the United States Nuclear Regulatory Comission on February 11, 1985.
Very truly yours, J
Peter B. Fiedler Vice President and Director l
Oyster Creek PBF: dam l
Enclosure
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i GPU Nuclear Corporation is a subsidiary of the General Public Ubi. ties Corporation
t OYSTER CREEK NUCLEAR GENERATING STATION (DOCKET N0. 50-219)
PROVISIONAL OPERATING LICENSE NO. DPR-16 Applicant hereby requests the Commission to reissue Appendix A to the above captioned ifcense:
1)
Section to be changed:
Administrative changes indicated below are applicable to Appendix A.
2)
Extent of change:
Remove detailed ISI and IST requirements of Section 4.3 and replace witn Commission's recommended wording.
3)
Changes requested:
As indicated a modified pages 4.3-1, 4.3-2, 4.3-3 and 4.3-4.
Delete existing table 4.3-1, renumber existing table 4.3.2, "4.3.1" and appropriately change / remove references to the two tables within the text.
4)
Discussion:
This Technical Specification Change Request modifies Section 4.3 by deleting detailed ISI and IST requirements and replacing them with general references-to 10 CFR 50.55a and ASME Boiler and Pressure Vessel Code,Section XI. This is in response to a Commission recommendation and will reduce the complexity of administering the programs.
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OYSTER CREEK NUCLEAR GENERATING STATION
- r PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 123 Pursuant to 10 CFR 50.91 an analysis concerning significant hazards considerations is provided below:
1)
Section to be changed:
Administrative changes indicated below are applicable to Section 4.3 of Appendix A.
2)
Extent of change:
Paragraphs 4.3.B and 4.3.C have been changed to reflect the Commission's recommended wording for the conduct of inservice inspection and inservice testing. Paragraph 4.3.D has been revised since the testing requirements for replacement and repaired safety valves are s;1ecified in Section XI of the ASME Boiler and Pressure Vessel Code, as stated in Paragraph 4.3.C.
The bases have also been changed accordingly.- Table 4.3.1 has
.been removed since it has been superceded by the Oyster Creek Inservice Inspection Program for the second 10-year interval.
The existing table 4.3.2 has been renumbered 4.3.1 along with the references to it.
3)
Discussion:
Examples of amendments that are considered not likely to involve significant hazards considerations were provided in the Federal Register on April 6,1983 (48FR 14870). Technical Specification Change Request No.123 meets the provisions of example (i) (as referenced above) in that it is an administrative change.
Copies of modified pages 4.3-1, 4.3-2, 4.3-3, and 4.3-4 are being provided for clarification purposes and the convenience of the Commission. The Comission has recommended the wording employed in modified paragraphs 4.3.B and 4.3.C and the elimination of program details elsewhere in the text. This change will make clearer the inservice testing and inspection requirements'as described in 10 CFR 50.55a and Section Xi of the ASME Boiler and Pressure Vessel Code, the details of which are implemented by the inservice inspection and testing programs for Oyster Creek. The proposed text will eliminate the need for frequent ~ changes to the Technical Specifications whenever program changes or requests for relief are made.
4)
Determination:
~ We have detemined that the subject change request involves no significant hazards in that operation of the Oyster Creek Nuclear Generating Station in accordance with Technical Specification Change Request No.123, Rev.1, would not:
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Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2)
Create the possibility of a new or different kind of accident frora any previously evaluated; or 3)
Involve a significant reduction in a margin of safety.
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