ML17264A493
| ML17264A493 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/20/1996 |
| From: | Jeffrey Mitchell NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264A494 | List: |
| References | |
| NUDOCS 9605230196 | |
| Download: ML17264A493 (4) | |
Text
~g R500 e
Cy 0O IVl C
0 Op r+
gO
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 OC TER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AM NDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated February 9, 1996, 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.
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-18 is hereby amended to read as follows:
9605230i96 960520 PDR ADOCK 05000244 P
(S)
T c c
ic tions The Technical Specifications contained in Appendix A, as revised through Amendment No.
6~
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
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:
May 20, 1996 Jocelyn A. Mitchell, Acting Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
T TO C
NS AMENDMENT NO.
63 ITY OPERATING LIC NSE 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 3.3-27
1 ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)
Engineered Safety Feature Actuation System Instrunentation FUNCTION APPLICABLE HMES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE ALLONABLE CONDITIONS REOUIREHENTS VALUE TRIP SETPOINT 5.
Feeduater Isolation a.
Automatic Actuation Logic and Actuation Relays 1,2 3
2 trains E,G
, SR 3.3.2.7'A KA b.
SG llater Level -High 1,2") 3(')
3 p r SG F,G SR 3.3.2.1 S 94K s 85K SR 3.3.2.2 SR 3.3.2.5 c.
Safety Injection Refer to F~tlon 1 (Safety Injection) for all initiation ftnctions and requirements.
6.
Auxiliary Feechater (AFN) a.
Hanual Initiation AFN Standby AFil 1,2,3 1,2,3 1 per IMP 1 per pump SR 3.3.2.4 SR 3.3.2.4 NA NA b.
Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains E,G SR 3.3.2.7 NA
'NA c:
SG lister Level -Lou Lou 1,2,3 3 per SG D',G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 i 16X a 17X d.
Safety Injection (Hotor driven lxmps only)
Refer to Fmction 1 (Safety Injection) for all initiation ftnctions and requirements.
e.
Undervoltage -Bus 11A and 118 (Turbine driven pm'nly) 1,2,3 2 per bus D,G SR 3.3.2.3 SR 3.3.2.5 a 2450 V arith s 3.6 sec time delay a 2579 V Mith s 3.6 sec time delay f.
Trip of Both Hain Feeduater Pcs (Hotor driven pumps only) 1,2 2 per HFll pwca B,C SR 3.3.2.4 NA (c)
Except shen all Hain Feeduater Regulating and associated bypass valves are closed and de-activated or isolated by a closed manual valve.
R.E.
Ginna Nuclear Power Plant 3.3-27 Amendment No, Pg 6~