ML20078S836
| ML20078S836 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/21/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078S840 | List: |
| References | |
| NUDOCS 9502270279 | |
| Download: ML20078S836 (4) | |
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UNITED STATES'
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,j NUCLEAR REGULATORY COMMISSION l
wAsmwomu, o.c. -m GPU NUCLEAR CORPORATION ggl-l i
JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION l
AMENDMENT TO FACILITY OPERATING LICENSE i
I Amendment No.177 License No. DPR-16~
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
I (the licensee), dated June 15, 1994, as supplemented i
September 23, 1994, and November 3, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as l
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; 1
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 i
defense and security or to the health and safety of the public; and khe issuance of this amendment is in' accordance with 10 CFR Par E.
51 of the Commission's regulations and all applicable l
requirements have been satisfied.
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i 9502270279 950221 3
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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 amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No.177, 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, to be implemented within 60 days of issuance.
TOR THE NUCLEAR REGULATORY COMMISSION l
0 Phillip F. McKee, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
February _21, 1995 f
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1 ATTACHMENT TO LICENSE AMENDMENT NO.177 FACILITY OPERATING LICENSE NO. DPR-16 I
DOCKET NO. 50-219 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment l
number and contains vertical lines indicating the areas of change.
Remove Insert 2.3-2 2.3-2 i
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I FUNCTION LIMITING SAFETY SYSTEM SETTINGS B.
Neutron Flux, Control Rod Block The Rod Block setting shall be
_f.BP_
S 1 ((0.90 x 10) W + 53.1] '(MFLPD]
with a maximum setpoint of,'108% for core flow equal to 61 x 10 lb/hr and greater.
The definitions of S. W. FRP and MFLPD used above for the APRM scram trip apply.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0, in which case the actual operating value will be used.
i This adjustment may be accomplished by increasing the APRM gain and thus reducing the flow referenced APRM rod block curve by the reciprocal of the APRM gain change.
C.
Reactor High, 11060 psig Pressure, Scram D.
Reactor High Pressure, 2 9 s 1085 psig Relief Valves Initiation 3 9 s 1105 psig E.
Reactor High Pressure, 11060 psig with time delay Isolation Condenser 13 seconds Initiation F.
Reactor High Pressure, 4 9 1212 psig 12 psi Safety Valve Initiation 5 9 1221 psig 12 psi G.
Low Pressure Main Steam 1825 psig (initiated in IRM Line, MSIV Closure range 10)
H.
Main Steam Line Isolation 110% Valve Closure from Valve Closure, Scram full open I.
Reactor Low Water Level, 211'5" above the top of the Scram active fuel as indicated under normal operating conditions J.
Reactor low-Low Water 27'2" above the top of the Level, Main Steam Line active fuel as indicated under Isolation Valve Closure normal operating conditions OYSTER CREEK 2.3-2 Amendment No. 164, 177
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