ML17254A253
| ML17254A253 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/08/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17254A255 | List: |
| References | |
| NUDOCS 8503140374 | |
| Download: ML17254A253 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R..E.
GINNA NUCLEAR P014ER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
2 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 January 25,
- 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;
+At B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
D.
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; I
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.
8503140374 850308 PDR ADOCK 05000244 P
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~'I 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 Vio. DPR-'I8 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
2
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specif icati ons.
3.
This license amendment is effective as of the date of its issuance.
FOR T NUCLEAR REGULATO Y COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 8, 1985 John A. Zwolinski, Chief Operating Reactors Branch F5 Division o< Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
2 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 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 marginal lines indicating the area of change.
REMOVE 3.8-1 3.8-5 INSERT 3.8-1 3.8-5
3.8 REFUELING Ap licabilit Applies,to..qperating limitations during refueling.-
operations.
To ensure that no.incident could occur during refueling 3.8.1 operations that would affect public health and safety.
During refueling operations the following conditions shall be satisfied.
a.
The equipment door> or a closure plate that restricts air flow from the containment, and at least one personnel door in the equipment door or closure plate and in the personnel air lock shall be properly closed.
In additionr all automatic containment isolation valves shall be operable or at least one valve in each line shall be locked closed.
b.
C ~
Radiation levels in the containment shall be monitored continuously.
Core subcritical neutron flux shall be con-tinuously monitored by at least two source range neutron monitors, each with continuous visual in-dication in the control room and one with audible indication in the containment and control room available whenever core geometry is being changed.
When core geometry is not being changed at 3.8-1 Amendment t)0.
2
provided on the lifting hoist to prevent movement of more than one fuel assembly at a time.
The spent fuel transfer mechanism can accommodate only one fuel assembly at a time.
In addition interlocks on the auxiliary building crane will prevent the trolley from being moved over stored racks containing spent fuel.
The operability requirements for residual heat removal loops will ensure adequate heat removal while in the refueling mode.
The requirement for 23 feet of water above the reactor vessel flange while handling fuel and fuel components in containment is consistent with the assumptions of the fuel handling accident 1
analysis.
(4)
The analysis for a fuel handling accident inside.containment 5
'stablishes acceptable offsite limiting doses following rupture of all rods of an assembly operated at peak power.
No credit is taken for containment isolation or effluent filtration prior to release.
Requiring closure of the containment openings and penetrations establishes additional margin for the fuel handling accident and establishes a seismic envelope to protect against seismic events during refueling.
References (1)
FSAR Section 9.5.2 (2)
Reload Transition Safety Report, Cycle 14 (3)
FSAR Section 9.3.1 (4)
Updated Final Safety Analysis Reporti Section 15.7 3.8-5 Amenrlment Ho.
2