ML20155G984
| ML20155G984 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/05/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20155G986 | List: |
| References | |
| NUDOCS 9811090276 | |
| Download: ML20155G984 (4) | |
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4 UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION g
WASHINGTON, o.C. 20665-0001 o
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l GPU NUCLEAR. INC.
ANQ JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 l
l OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No.202 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear, Inc., et al., (the licensee), dated July 23,1998, as supplemented by a letter dated September 25,1998, 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 Commission; 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
9811090276 981105 PDR ADOCK 05000219 P
1,
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 4
Operating License No. DPR 16 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.202, are hereby incorporated in the license. GPU Nuclear, Inc. shall operate the facility in accordance with the Technical 4
Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Yh PT Cecil O. Thomas, Director Project Directorate 13 Division of Reactor Projects - l/II Office of Nuclear Reactor Regulation Attachment Changes to the Technical Specifications Date ofIssuance: Novemebr 5,1998
.n.
ATTACHMENT TO LICENSE AMENDMENT NO.202 FAClLITY 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 contains verticallic'.es indicating the areas of change.
Remove Insert 2.1-1 2.1 1
4 SECTION 2 S AFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1
. S AFETY LIMIT - FUEL CLADDING INTEGRITY Anoticability:
Applies to the interrelated variables associated with fuel thermal behavior.
Objective:
To establish linns on the important thermal hydraulic variables to assure the integrity of the fuel cladding.
Soecifications:
A.
When the reactor pressure is greater than or equal to 800 psia and the core flow is greater than or equal to 10% ofrated, the existence of a minimum CRITICAL 4
POWER RATIO (MCPR) less than 1.09' shall constitute violation of the fuel cladding integrity safety limit.
B.
When the reactor pressure is less than 800 psia or the core flow is less than 10%
of rated, the core thermal power shall not exceed 25% of rated thermal power.
C.
In the event that reactor parameters exceed the limiting safety system settings in Specification 2.3 and a reactor scram is not initiated by the associated protective instrumentation, the reactor shall be brought to, and remain in, the COLD SHUTDOWN CONDITION until an analysis is performed to determine whether i
the safety limit established in Specification 2.1.A and 2.1.B was exceeded.
D.
During all modes of reactor operation with irradiated fuel in the reactor vessel, the water level shall not be less than 4'8" above the TOP OF ACTIVE FUEL.
BAaca:
The fuel cladding integrity safety limit is set such that no fuel damage is calculated to occur if the limit is not violated. Since the parameters which result in fuel damage are not directly observable during reactor operation the thermal and hydraulic conditions resulting in a departure from nucleate boiling have been used to mark the beginning of the region where fuel damage could occur. Although it is recognized that a departure from nucleate boiling would not necessarily
' result in damage to BWR fuel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit. However, the uncertainties in monitoring the core operating state and in the procedure used to calculate the
- Applicable for cycle 17 only._
l OYSTER CREEK 2.1-1 Amendment No.: 75,125,1^2,202
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