ML20100Q397
| ML20100Q397 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/04/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20100Q401 | List: |
| References | |
| DPR-16-A-183 NUDOCS 9603110621 | |
| Download: ML20100Q397 (4) | |
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
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GPU NUCLEAR CORPORATION 8NQ JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.183 License No. DPR-16 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated December 5, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9603110621 960304 PDR ADOCK 05000219 P
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, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby j
amended to read as follows:
(2)
Technical Snecifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 183, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULA RY COMMISSION 1
M J
F. Stolz, Director Pro ct Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 4, 1996
ATTACHMENT TO LICENSE AMENDMENT NO. 183 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following page of the Appendix A, Technical Specifications, with the attached page as indicated.
The revised page is identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 6-13 6-13
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6.9 REPOR'HNG REOUIREMENTS i
la addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted to the Administrator of the NRC Region I office unless otherwise noted.
6.9.1 ROUTINE REPORTS a.
Startuo Report. A summary report of plant startup and power escalation testing shall be submitted following (1) mceipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. 'Ibe report i
shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test
' program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specified details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commanca-mar of commercial power operation, i
or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
b.
Annual Exposure Data Report Routine exposure data reports covering the operation of the facility during the previous calendar year shall be submitted prior to April 30 of each year.
Reports shall contain a tabulation on an annual basis of the number of station, utility, and other' personnel (including contractors) receiving exposures greater than 100 mrem / year and their associated man rem exposure according to work and job functions (this tabulation supplements l
the requirements of 10 CFR 20.407), e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimated based on pocket dosimeter. TLD, or film badge measurements. Small exposures totalling less than 20%
of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
c.
MontMy Onerada Renort. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis which will include a narrative of operating experience, to the Director, Office of Management and Program Control, U.S. Nuclear Regulatory Commission, with a copy to the Regional Office, no later than the 15th of each month following the calendar month covered by the report.
OYSTER CREEK 6-13 Amendment No.: 166, 183