ML20066G019

Amend 94 to License NPF-12,revising Tech Specs 3.4.2.1 & 3.4.2.2

ML20066G019
Person / Time
Site:	Summer
Issue date:	01/10/1991
From:	Adensam E, Lo R Office of Nuclear Reactor Regulation
To:	South Carolina Electric & Gas Co, South Carolina Public Service Authority
Shared Package
ML20066G022	List: ML20066G019 ML20066G026
References
NPF-12-A-094 NUDOCS 9101240325
Download: ML20066G019 (6)

Text

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UNITED STATES -

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NUCLEAR REGULATORY COMMISSION 4,

WASHINoToN;o C.206$5 0

t SOUTH CAROLINA ELECTRIC-& GAS COMPANY-

SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 1

AMENDMENT TO FACILITY-OPERATING-LICENSE

~ Amendment No. 94-License No. NPF-12

1.,

The Nuclear. Regulatory' Commission-(the Commission) has found that:

A.L

,The application _ for amendment by South Carolina Electric & Gas-4-

_ Company-(the licensee), dated May 16, 1990, as_ supplemented

August 13,-1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the F

Commission's' rules and regulations set forthiin 10 CFR Chapter I; c

B.

The facility will: operate in conformity with the application, the provisions-of the Act,-and the. rules and regulations of

.the Commission;

'C.

iThere is reasonable assurance (i) that the activities authorized by this-amendment can be conducted withouttendangering 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 to in accordance with 10 CFR Part 51 I

tof^the Commission's regulations and"all' applicable requirements have been satisfied.

U

2.

Accordingly, the license-is amended by changes to the-Technical-Specifications,-an indicated in the attachment to this license.

amendment;_ and paragraph 2.C.(2) of Facility Operating License

+

No.'NPF-121is.hereby amended to read as follows:

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9101240325 910110 PDR ADOCK 05000395 '

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-(2) Technical Specifications a_nd-Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 94

, and the Environmental Protection Plan contained _ in Appendix B, are hereby incorporated in_ the license.

South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ronnie Lo/for Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes-to the Technical Specifications -

Date of Issuance: January 10, 1991 n e s UFC : A:

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ATTACHNENT TO LICENSE AMENDMENT NO. 94 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with

-the enc'losed pages.

The revised pages are indicated by marginal lines.

Remove Pageal Insert Pages 3/4 4-7 3/4 4-7 3/4 4-B 3/4 4-8 B3/4 4 B3/4 4-2

REACTOR-COOLANT' SYSTEM l' 3/4. 4. 2 SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR OPERATION-3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485-PSIG i 3%.*

APPLICABILITY:

MODES 4 and 5.

' ACTION:

With no pressurizer code safety valve OPERAELE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE residual-heat removal-loop-into operation in the shutdown cooling moda.

' SURVEILLANCE REQUIREMENTS' 4.4.2.1-:The-Surveillance Requirements of Specification 4.0.5 shall be met. or;-

the pressurizer code safety valve shall have its lift set pressure verified under cold conditions.

a SUMMER - UNIT 1 3/4 4-7 Amendment No. 94

I REACTOR COOLANT SYSTEM OPERATING-i

' LIMITING CONDITION FOR OPERATION-

3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2485 PSIG i 3%.*

' APPLICABILITY:

MODES 1, 2 and 3 #

ACTION:-

With one pressurizer code safety valve-inoperable, either restore the-inoperable valve to OPERABLE status within 15 minutes or be in at least HOT

-STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.2.2 No additional Surveillance Requirements other than those required by Specification 4.0.5.

• The lift. setting pressure-shall correspond to ambient conditions of-the valve at nominal operating temperature and. pressure.

~# ode 3 applicability-is exempted under the following conditions:

M

-- 1.

There has:been-a least 5-days of operation in MODES 5 or 6 since the reactor was last critical, and 2.

All RCCAs.are fully inserted with all CRDMs de-energized.

SUtHER - UNIT 1-3/4 4-8 Amendment No. 94

REACTOR COOLANT SYSTEM BASES-3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at the valve set point plus 3% accumulation.

The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS over-pressurization.

In addition, the Overpressure Protection _ System provides a diverse means of protection against RCS overpressurization at low temperatures.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig, The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protective System trip set point is reached (i.e., no credit is taken for a_ direct reactor trip on the loss of load) and also assuming no_ operation of the power operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure

Code, 3/4.4.3 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal _ steady state envelope of operation assumed in the SAR.

The limit is consistent with the initial SAR assumptions.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter i

is restored to within its limit following expected transient operation.

The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system.

The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant l

to control Reactor Coolant System pressure and establish natural circulation.

l l

-3/4.4.4 RELIEF VALVES (PORV's)

The power operated relief-valves and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump.

Operation of the power operated relief valves minimizes the undesirable opening of the spring-loaded pressurizer code safety l

valves.

Each PORV has a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable.

SUMMER - UNIT 1 B 3/4 4-2 Amendment No. 94

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