ML17258B023
| ML17258B023 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 04/23/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17258B024 | List: |
| References | |
| NUDOCS 8105120478 | |
| Download: ML17258B023 (12) | |
Text
gp,S QE0yq Ip0 Cy I
gO
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 23, 1981 Docket No. 50-244 LS05-81-04-050 Mr. John E. Maier Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. Maier:
SUBJECT:
DIESEL GENERATOR SURVEILLANCE AND TESTING - R. E.
GINNA NUCLEAR POWER PLANT The ComIission has issued the enclosed Amendment No.
41 to Provisional Operating License No. DPR-18 for the R. E. Ginna Nuclear Power Plant.
This amendment responds to your application notarized November 16, 1977 (submitted by letter dated November 21, 1977).
The amendment modifies the Technical Specifications for the R. E. Ginna Nuclear Power Plant to remove an inconsistency regarding the electrical load to be added to the generator during testing.
The Technical Specifi-cations regarding diesel generator surveillance and testing have also been expanded in conformance with your suggested changes.
Changes have been made to your submittal as mutually agreed upon during telephone conversations with your staff.
Copies of our Safety Evaluation and Notice of Issuance are also enclosed.
Si cerely, Dennis M. Crutchfield, Ch f Operating Reactors Branch g5 Division of Licensing
Enclosures:
l.
Amendment No.
41 to DPR-18 2.
Safety Evaluation 3.
Notice cc w/enclosures:
See next page
Hr, John E. Maier April 23, 1981 cc w/enclosures:
Karry K. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and HacRae 1333 New Hampshire Avenue, N.
W.
Suite 1100 Washington, D. C.
20036 Hr. Michael Slade 12 Trai lwood Ci rcl e Rochester, New York 14618 Rochester Comnittee for Scientific Information Robert E. Lee, P h.D.
P. 0.
Box 5236 River Carpus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Techni ca 1 Development Programs State of New York Energy Office Agency Building 2 Emp i re State P 1 az a
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.
NRC 1503 Lake Road
- Ontario, New York 14519 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Washington, D. C.
20460 U. S. Environmental P rotecti on Agency Region II Office ATTN:
E I S COORD INATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chai.rman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Coanission Washington, D. C.
20555 Hr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N.
W.
Suite 600 Washington, D. C.
20006
~!
<~R AEo>
~o Cy 0
+>>*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 41 License No.
DPR-18 1 ~
The Nuclear Regulatory ComIIission (the Commission) has found that:
A.
The application for amendment by Rochester Gas and Electric Company (the licensee) notarized November 16, 1977 (transmitted by letter dated November 21, 1977),
complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the ComIIission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the filing, 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 Coranission'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 Technial Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional 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.
41, 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:
April 23, 1981 Denny s M. Crutchf iel d, Chi e Operating Reactors Branch Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 41 PROVISIONAL 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 contain the captioned amendment number and vertical lines which indicate the area of change.
Remove 4.6-1 4.6-2 Insert 4.6-1 4.6-1a 4.6-2
4.6 Emer enc Pow stem Periodic Tests A Iicabilit Applies to periodic testing and s'urveillance requirements of the emergency power system.
~Ob ective To verify that the emergency power system will respond promptly and properly when required.
The following tests and surveillance shall be performed as stated:
4.6.1 Diesel Generators Each diesel generator shall be demonstrated operable:
'a ~
Except during cold or refueling shutdown at least once per 31 days by:
1.
Verifying the fuel level in the day tank, 2.
Verifying a minimum oil storage of 10,000 gallons is at the
- station, 3.
Verifying the fuel transfer pump can be started and transfer fuel from the storage system to the day tank, 4.
Verifying the diesel starts from normal standby conditions, 5.
Verifying the generator is synchronized, loaded to at least 1950 kw but less than the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 2250 kw and operates for at least 60 minutes but less than 120 minutes, 6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.
b.
The tests in specification 4.6.la will be performed prior to C ~
exceeding 5% power if the time since the last test exceeds 31 days.
At least once per 92 days by verifying tha a sample of diesel fuel from the fuel storage tank is within the acceptable limits, specified in Table 1 of ASTN 0975-78 when checked for viscosity, water and sediment.
4.6-1 Amendment No. Q, 41
d.
At least once per 18 months during shutdown by:
l.
Inspecting the diesel in accordance with the manufacturer's recommendations for this class of standby service, 2.
Verifying the generator capability to reject a load 'of 295 Qi without tripping, 3.
Simulating a loss of offsite power in conjunction with a safety injection test signal and:
(a)
Verifying de-energization of the emergency buses and load shedding from the emergency buses.
(b)
Verifying the diesel starts from normal standby condition on the auto-start signal, energizes the emergency buses with permanently connected
- loads, energizes the automatically connected emergency loads with the following maximum breaker closure times after the initial starting signal for trains A and B not being exceeded A
Diesel plus Safety Injection Pump 20 sec B
22 sec plus RHR Pump All breakers 40 sec 42 sec and operates for > five minutes while its generator is loaded with emergency loads.
(c) Verifying that all diesel generator trips, except engine overspeed, low lube oil pressure,.
and overcrank, are automatically bypassed upon loss of voltage on the emergency bus and/or safety injection actuation signa) 4.6-1a Amendment No.
41
4.6.2 Station Batteries a.
Every month the voltage of each cell (to the nearest 0.01 volt),
the specific gravity and temperature of a pilot cell in each battery shall be measured and recorded.
b.
Every 3 months the specific gravity of each cell, the tempera-ture reading of every fifth cell, the height of electrolyte, and the amount of water added-shall be measured and recorded.
4.6-2 Amendment No. gg, 41
P
- ~,