ML17258A150

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Amend 45 to License DPR-18,authorizing Tech Specs Re Operability of Dc Electrical Sys & Availability of Addl Battery Chargers
ML17258A150
Person / Time
Site: Ginna 
Issue date: 08/27/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17258A151 List:
References
NUDOCS 8109140010
Download: ML17258A150 (8)


Text

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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 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 45 License No.

DPR-18 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Rochester'as

'and Electric Company (the licensee) notarized October 10, 1978 (transmitted by letter dated October 12, 1978) as supplemented by submittals dated April 18, 1979 and August 10, 1979, complies with the standards and requi rements 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.

8109140010 810827 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 by changing paragraph 2.C(2) of Provisional Operating License No.

DPR-18 to read as follows:

(2)

Technical S ecifications The Technical Specifications, contained in Appendix A, as revised through Amendment 'No.

45, 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 issuance.

4 FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 27, 1981 Dennis M. Yrutc fiel, ief Operating Reactors Bran h 85 Division of Licensing

ATTACHMENT TO LICENSE AMENDMENT NO. 45 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 marginal lines which indicate the area of changes PAGES 3.7-1 3.7-2

3. 7-3*
3. 7-4.
  • This page is included for pagination purposes only.

3.7 AUXELXARY ELECTRICAL SYSTEMS

~b Applies to the availability of electrical power for the operation of plant auxiliaries.

~b'o define those conditions of electrical power availability necessary (1) to provide for safe reactor operation, and (2) to provide for the continuing availability of engineered safeguards.

3.7.1 The reactor shall not be maintained'ritical without:

a The 34.5 KV-4160 Volt station service transformer in service.

b.

480-volt buses 14, 16, 17 and 18 energized.

c.

4160-volt buses 12A and 12B energized.

d.

Two diesel generators operable with onsite supply of 10,000 gallons of fuel available.

e.

Both batteries and both d.c.

systems

operable, and at least one 150 amp battery charger or two 75 amp 3-.7-2 battery chargers in service for each

/

During reactor operation the requirements modified as follows:

battery.

of 3.7.1 may be 3.7-1 Amendment t<0.

-".5

a.

Power operation may. continue with 'the station service transformer out of service provided (a) the failure shall be reported to NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with an outline of the plans for prompt restoration of offsite power and the.

additional precautions to be taken while the transformer is out of service and.

(b) both diesel. generators are operable.

Under conditions of fulfillment of (b) and non-fulfillment of (a), continued power operation shall not extend beyond 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Non-fulfillment of>(b) shall be

. deemed sufficient cause for immediate reactor shutdown..

b.

Power operation may continue if one diesel generator is out of service provided.(a) the remaining diesel generator is run continuously, and (b) the station service trans-former is in service and (c) such'peration is not in excess of 7 days(total for both diesels) during any month.

c.

Power operation may continue if less than 150 amp': of battery charging capacity is available to one d. c. system, as long as at least 150 amp'f battery charger.capacity is available'to each

d. c.

system within two hours.

If not available, the reactor shall. be placed in the hot shutdown condition within the next P

six hours and in the cold shutdown condition within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Basis':

The electrical system equipment is arranged so that no single contingency can inactivate enough safeguards equipment to jeopardize the plant safety.

The 480-volt equipment is arranged 3 ~ 7 2

Amendment No.

>.5

1 on 6 buses.

The 4160-volt equipment, also is supplied from 4 buses.

Two separate outside sources supply station service power to the plant.

The plant auxiliary equipment is arranged electrically so that mul-tiple items receive their power from the two different sources.

The charging pumps are supplied from the 480-volt buses No.

14 and 16.

The four containment fans are divided between 480-volt buses No.

14 and 16.

The two residual heat pumps are on separate 480-volt buses.

Valves are supplied from motor control centers.

One outside source of power is required to give sufficient power to run normal operating equipment.

One transmission line can supply all the plant auxiliary power.

The 115-34.5 kv station service transformer can supply all the auxiliary loads.

The bus arrangements specified for operation ensure that power is available to an adequate number of safeguards auxiliaries.

With additional switching, more equipment could be out of service without infringing on safety.

C Two diesel generators have sufficient capacity to start and run at design load all the engineered safeguards equipment.

The safeguards operated from one diesel generator can'adequately cool the core for. any loss-of-coolant incident, and they also 3 ~ 7 3

maintain the containment pressure within the design value.

The minimum diesel fuel oil inventory at all times is maintained to assure the operation of both diesels carrying design load of all the engineered safeguards ec(uipment for at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

Commercial oil supplies and trucking facilities exist to assure deliveries within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

The plant design includes two 150 amp battery chargers and two 75 amp battery.chargers.

The 75 amp battery chargers are capable of manual transfer from one

d. c.

system to the other.

At least one 150 amp battery charger or two 75 amp battery chargers shall be in service for each battery so that the batteries wi11 always be at full charge.

This ensures that adequate dc power will be avai'lable.

The plant can be safely shutdown without the use of offsite power since all vital loads (safety systems, instruments etc.)

\\

can be supplied from, the emergency diesel generators.

The two diesel generators, each capable of supplying safeguards

loads, and the station auxiliary transformer provide three separate sources of power immediately available for operation of these E

loads.

Thus the power supply system meets the single failure criteria r'equired of safety systems. (2)

References:

- (l)

CESAR Section',.2.l (2)

CESAR Appendix 8A 3.7-4 Amendment No.

45