ML17244A702

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Amend 27 to License DPR-18 Proposing Mods to Safety Injection Actuation Sys Logics
ML17244A702
Person / Time
Site: Ginna 
Issue date: 06/15/1979
From: Ziemann D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17244A703 List:
References
TASK-07-02, TASK-7-2, TASK-RR NUDOCS 7907250312
Download: ML17244A702 (4)


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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.

E.

GINNA'NUCLEAR POWER PLANT AMENDMENT TO PROVISIONAL OPERATING'LICENSE Amendment No. 27 License No.

DPR-18 1."

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated June ll, 1979, 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.

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ATTACHMENT TO LICENSE AMENDMENT NO.

PROVISIONAL OPERATING LICENSE NO.

DPR-18

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r DOCKET NO: 50-'244 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.

The revised page is identified by the captioned amendment number and contain a vertical I ine indica ting the area of change.

REMOVE 3.5-5 INSERT 3.5-5

TABLE 3.5-2 I".lERGE,NCY CNLIRG NO, FNiCTIONAL VKI'f RO. of MIN.

HD.

PERHIGSIBLE NO. of CHAHKELS OPERABLE DEGKE OF BYPASS CHANNELS

?0 TRIP~+

CI ANÃKLS REDUNDANCY CONDETEON 6

OPERATOR ACTIOh IF CoeITIONS OF COLUHH 3 OR 5 CANNOT BE HET 1.

SAFETl'NJECTION a.

Nanual

h. High Containment Pressure
c. Steas Generator Low St,eae Pressure/Loop d, Pressuriser Los Pressure 2.

CONTAINlSNT SPRAY

a. manual
b. Hi.Hi Contaieeent Pressure 2 sets 2 of 3 (Containaent Spray) of 3 in ea.

set Bust actuate 2 switches siiaultaneously.

2 per 1(set set primary pressure less Het Shutdeveeae than 200Q paig Hot Shutdown~

Hot Shutdown~

Hot Shutdown~~

Hot Shutdova~

Hot Shutdown~

IE sining conditions are not Net vithn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the unit in cold shutdown conditions.

If a functional unit is operating-with the shrine operable channels the number of channels to trip the reactor vi1.1 be colm 3-less column 4.

3.5-5 Amendment No. 27