ML17264A788
| ML17264A788 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/09/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264A789 | List: |
| References | |
| NUDOCS 9701160004 | |
| Download: ML17264A788 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No.
DPR-18 The Nuclear Re ulatory Commission (the Commission or the NRC) has found that:
A.
The appli ation for amendment filed by the Rochester Gas and Electric Porporation (the licensee) dated October 29,
- 1996, complies kith 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; 2.
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.
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-18 is hereby amended to read as follows:
9701160004 970i09 PDR ADOCK 05000244 P
3.
(2)
Techrii cal S eci ficati ons The Technical Specifications contained in Appendix A, as revised through Amendment No. 66
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
~a<>e~7 9
>99" I
S.
Singh Bajwa, Acting Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
.The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove 3.3-27 Insert 3 '
27
r ESFAS Instrumentat)on 3.3.2
'Table 3.3.2 1 (page 3 of 3)
Engineered Safety Feature Actwtfon Systee Instnaentatfon APPL ICASLE ICOES OR OTHEk SPECI F IED REINIRED QRVEILLANCE ALLOQLLE COOl TIONS CNANNELS COOI TIONS RECNIkE%NTS VAUK TRIP SETPOINT 5.
Feedwter Isolation
- a. Aut~tfc Actwtion Logfc
~nd Actuetfon Relays b.
SG Mater Level -Nfgh 1i2(c) 3(c) 2 tlafna Eig SR 3 3i2 7 1i2(c) 3(c) 3 per SC F,C SR 3.3.2.1 SR 3.3.2.2 Sk 3.3.2.5 s 94X s 85X c.
Safety Injection Refer to Fcsctfan 1 (Safety Injectfon) for all fnftfatfon
- fact fons and requirements.
6.
Auxflfary Feedwater (AFM) a.
Nanwl Inftiation Stenchy AFQ 1,2,3 1,2,3 1 per Pp-SR 3.3.2 4 SR 3.3.2.4 NA
- b. Aut~tIc Actustfon Logfc
~nd Actwtfon Relays 1,2,3 2 trafns E,C Sk 3.3.2.7 c.
SG Mater
. Level -Lou Lou 1,2,3 3 per SG F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 a 16X a 17X d.
Safety Injectfon (Notor driven pusps only) kefer to Fcsx:tfon 1 (Safety lnjectfon) for atl fnitiatfon fcsx:tfons and raquiraeents.
~.
Undervol tage <<gus 11A and 11g
, (Turbine. driven pucp only) 1,2,3 2 per bus D,C SR 3.3.2.3 SR 3+3+2,5 a 245D V ccfth s 3.6 sec tfee delay a 2579 V ufth s 3.6 sec tfae delay f.
Trip of goth lfafn Feechater Puapa (Notor driven pape only) 1,2 2 per
~
1IFM pucp S,C SR 3.3.2.4 (c)
Except uhen all Nein Fee%uter Regutatfng and assocfated bypass valves are closed and de-activated or isola'ted by a closed MclUll valve R.E. Glnna Nuclear Power Plant 303-27 Amendment No. g~ N66