ML20137Z653

Amend 95 to License DPR-16,changing Tech Specs to Revise Channel Check for Low Reactor Water Level Instrumentation Channels from All Channels to Only Channels Having Indication in Control Room

ML20137Z653
Person / Time
Site:	Oyster Creek
Issue date:	11/30/1985
From:	NRC
To:
Shared Package
ML20137Z659	List: ML20137Z653 ML20137Z668
References
NUDOCS 8512110365
Download: ML20137Z653 (3)

Text

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o UNITED STATES -

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_g NUCLEAR REGULATORY COMMISSION b

h WASHINGTON, D. C. 20555 i

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f GPU NUCLEAR CORPORATION I

AND I

JERSEY CENTRAL POWER & LIGHT COMPANY f

f DOCKET NO. 50-219

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0YSTER CREEK NUCLEAR GENERATING STATION

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AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 95 License No. DPR-16 1.

The Nuclear Regulatory Commission (the Commission) has found tha't:

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A.

The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated September 30, 1985, as revised by letters dated November 7 and 16, 1985, and as supplemented by letters dated November 4, 8

,l; and 14, 1985, 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 thi>, amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be f

conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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.

8512110365 851130 PDR ADOCK 05000219 P

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l ATTACHMENT TO LICENSE AMENDMENT NO. 95 1.

t PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 I

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment' number and contain vertical lines indicating the 7

area of change.

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REMOVE INSERT l,

4.1-5 4.1-5 F

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I c

I e

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M e.1.1 4

Im MIX. CMTM am TEST m FIR m MTMATM I

l Imatrammat Chammel M

Calthrata Inst Ammeris fammiles ta fast and Callkrattant l

l 1.

High Beacter Pressure AA 1/3 me.

Este 1 By application of test pressure 2.

Nigh Drymell Pressure (Scram)

EA I/3 me.

IInte 1 ty appittatien of test pressure 3.

tow asector Meter Level IIste 3 1/3 as.

usta 1 By aspilcation of test pressure 4.

Law.tou Ideter tevel IIste 3 1/3 as.

IIste 1 By applicatten of test pressure 5.

migh IInter Level in Scram NA I/3 me.

mete 1 By varying level in switch colisms

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sischarge volesse 6.

tow-Low-tou Meter tevel NA t/3 me.

IInte 1 By appilcatien of test pressure i

7.

Nish Flow in semin Steemilne 1/d 1/3 me.

mete 1 By aspilcation of test pressure

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ter Pressure in IInin Steenline AA 1/3 me.

IIste 1 Ay aspilcation of test pressure 9.

Migh Dryuell Pressure 1/d IIste 1 By aspilcatten of test pressure f

(Core Coeling)

Is.

Iquin Steam 3selatten valve (Scram) eA mA 1/3 me.

By emercising valve 11.

MSI Level 5A 1/3 d EA thstput adjeestment usine operattenal type heat balance esring poner operatten ApeII Scram Trips Rete 2 1/Wr.

1/uk.

Using butit-in calibretten eemtpoent l

during semer operetten 12.

apWI and Blocks mete 2 1/3 me.

IAme.

Upscale and demoescale 13.a. Nigh Radiatten in 9tain Stesellne 1/s 1/3 me.

1/edt.

Usine built-in calibratten eeulement during gemer eseratten j

h. Sossers for 13(a)

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Each refuel IIA Usine external radiatten source j

ing autage i

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IS M TE 1: Initially once/me, thereafter acce% to Fig. 4.1.1 with an interval not less then one month nor more then

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Q Q-tierse months.

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IISTE 2: At leest daily durlas reacter peuer operation the reacter neutron flux peaking facter shall be estlemted and the j

flow-referenced arme scran and red black settings shall he adjusted, if necessary, as specified in Section 2.3.

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Specificattens (I) (a) and (2) (a).

IEITE 3: A delly chesnel rense will be performed using IE 21A and B to verify reacter esoter level instrissentation needer y

ew operability. 1915 is valid from Igovember 3.1985 to the restart frase the lit autase. Otherutse. a delly channel un check is reestred.

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