ML17251A272
| ML17251A272 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/23/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A273 | List: |
| References | |
| NUDOCS 8809290129 | |
| Download: ML17251A272 (6) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION POCKET NO. 50-244 R.E.
GINNA NUCLEAR POMER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
30 License No.
DPR-18 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated September 24, 1987 as supplemented on May 3, 1988 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 Comlssion'..
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:
8809290i29 880923 PDR ADQCK 05000240 PNU (2)
Technical S ecifications The Technical Specifications contained in Appendix A as revised through Amendment No.
30
, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II Date of Issuance:
September 23, 1988 (2)
Technical S ecifications The Technical Specifications contained in Appendix A as revised through Amendment No.
, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 30, 1988
/s Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II k
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OFFICIAL RECORD COPY
ATTACHMENT TO LICENSE AMENDMENT N0.30 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A as follows:
REYiOVE page 3.5-16 page 4.1-7 INSERT page 3.5-16 page 4.1-7
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Accident Monitorin Instrumentation TOTAL REQUIRED NO.
OF CHANNELS (7)
MINIMUM CHANNELS OPERABLE (7) 1.
Pressurizer Water Level (1) 2.
Auxiliary Feedwater Flow Rate (2)(3) 3.
Steam Generator Water Level - Wide Range (3) 2/steam generator 1/steam generator 1/steam generator 1/steam generator 4.
Reactor Coolant System Subcooling Margin Monitor (4) 5.
Pressurizer PORV Position Indicator (5) 6.
PORV Block Valve Position Indicator (1) 7.
Pressurizer Safety Valve Position Indicator (5) 2/Valve 1/Valve 2/Valve 1/Valve 0/Valve 1/Valve 8.
Containment Pressure (8) 9.
Containment Water I,evel (Narrow Range, Sump A) 10.
Containment Water Level (Wide Range, Sump B) 1(6) 1(6) 11.
Core-Exit Thermocouples r
12.
Reactor Vessel I,evel Indication System 4/core quadrant 2/core quadrant Notes (1)
Emergency power for pressurizer equipment, NUREG-0737, item II.G.1.
(2)
Auxiliary feedwater system flow indication, NUREG-0737, item II.E.1.2.
(3)
Only 2 out of the 3 indications (two steam generator auxiliary feedwater flow and one wide-range steam generator level) are required to be
- operable, NUREG-0737, item II.E.1.2.
(4)
Instrumentation for detection of inadequate core cooling, NUREG-0737, item II.F.2.1.
(5)
Direct indication of relief and safety valve position, NUREG-0737, item II.D.3.
Two channels include a primary detector and RTD as the backup detector.
(6)
Operation may continue with less than the minimum channels operable provided that the requirements of Technical Specification 3.1.5.1 are met.
(7)
See Specification 3.5. 3 for required action.
(8)
Containment pressure
- monitor, NUREG-0737, item II.F.1.4.
Amendment Ho. P, gP, 3.5-16
O Channel TABLE 4.1-1 (CONTINUED)
Check Calibrate Test Remarks c
25.
Containment Pressure C) 26.
Steam Generator Pressure S
27.
Turbine First Stage Pressure S
M Narrow range containment pressure
(-3.0,
+3 psig) excluded 28.
Emergency Plan Radiation Instruments 29.
30.
I Environmental Monitors Loss of Voltage/Degraded Voltage 480 Volt Safeguards Bus NA NA NA 31.
Trip of Main Feedwater Pumps NA 32.
Steam Flow AVQ NA 34.
Chlorine Detector, Control NA Room Air Intake 35.
Ammonia Detector, Control Room Air Intake NA 36.
Radiation Detectors, Control NA Room Air Intake 37.
Reactor Vessel Level Indication System NA