ML17251A661
| ML17251A661 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/08/1986 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A662 | List: |
| References | |
| NUDOCS 8605150222 | |
| Download: ML17251A661 (7) | |
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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 POWER PLANT ANENDYIENT TO FACILITY OPERATING LICENSE Amendment No.
14 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 August 1, 1983 as modified October 26, 1983, 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 activiti.es 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.
8605150222 860508 PDR ADOCK 05000244 p
'PDR 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; (2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 10
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMYiISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
Hay 8, 1986 George E. Lear, Director
. Project Directorate ¹I Division of Ph~R Licensing-A
ATTACHMENT TO LICENSE AMENDMENT NO.
14 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 4.6-4 4.6-5 INSERT 4.6-4 4.6-5 4.6-5a
Co At each time data
.is recorded, new data shall be compared with old to detect signs of abuse or deterioration.
d.
Each battery shall be subjected to a load test within a twelve-month period from the last load test; however, to permit the load test to coincide with a scheduled refueling, the period may extend for an additional three months.
The battery voltage as a function of time shall be monitored to establish that the battery performs as expected during heavy discharge and that all electrical connections are tight.
e.
Each battery shall be subject to a discharge test at least once per 60 months.
The purpose of this test is to show that the battery capacity is at least 80% of the manufacturer's recommendations.
When performed, this discharge test may substitute for the load test.
II f.
The discharge test shall be performed annually for any battery that shows signs of degradation.
Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous discharge tests, or is below 90% of the manufacturer's rating.
Amendment No.
14 4.6-4
Basis The tests specified are designed to demonstrate that the diesel generators will provide power =for operation of 'equipment.
They also assure that the emergency generator system controls and the control systems for the safeguards equipment will function automatically in the event of a loss of all normal 480V AC station service power.
r The testing frequency specified will be often enough to identify and correct any mechanical or electrical deficiency before it can result in a system failure.
The fuel supply and starting circuits and controls are continuously monitored and any faults are indicated by alarm.
An abnormal condition in these systems would be signaled without having to place the diesel generators themselves
'on test.
Station batteries will deteriorate with time, but precipitous failure is extremely unlikely.
The surveillance specified is that which has been demonstrated over the years to provide an indication of a cell becoming unserviceable long before it fails, and to ensure that the battery capacity is acceptable.
The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capability of the battery.
As a check upon the effectiveness of the equalizing charge, the battery should be loaded rather heavily and the voltage monitored as a function of time. If a cell has deteriorated or if a connection is loose, the voltage under load will drop excessively indicating replacement or maintenance.
Amendment No.
14 4.6-5
The minimum permissjble on-'site fuel oil inventory, 10,000 gallons, is sufficient for operation under. loss-of-coolant accident conditions of two I
engineered safety features trains for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or for one train for 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />, or for operation under hot standby non-accident conditions for ill hours.
References (1)
FSAR, Section 8.2 (2)
FSAR, Section 8.2.3 Amendment No.
14
- 4. 6-5A