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Amends 183 to Licenses DPR-32 & DPR-37,respectively, Permitting Operation W/Three Degree Increase in Svc Water Temp Limit for Containment Air Partial Pressures of 9.1,9.2 & 9.35 Psia & Correcting Typos
	ML20056H407
Person / Time
Site:	Surry
Issue date:	09/07/1993
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20056H408	List: ML20056H407; ML20056H414;
References
	NUDOCS 9309090277
	Download: ML20056H407 (8)
	v • d • e

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t NUCLEAR REGULATORY COMMISSION k'...

wassmcTon. o.c. 20sssam VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 License No. DPR-32 i

1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated July 16, 1993, 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 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; 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

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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.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. OPR-32 is hereby l

amended to read as follows:

(B)

Technical Specifications The Technical Specifications contained in Appendix A, as revised i

through Amendmen' No. 183, 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 its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION l

rbert N. Berkow, Director i

Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 7,1993

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NUCLEAR REGULATORY COMMISSION (tq/

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wassincrow, o.c. rosss-oooi VIRGINIA ELECTRIC ANC POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 License No. DPR-37 1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated July 16, 1993, 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 optrate 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 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; D.

The issuance of this amendment will not be inimical to the commor.

defense and security or to the health and safety of the public; and E.

The issuar.ce of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfiad.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 1

l and paragraph 3.B of facility Operating License No. DPR-37 is hereby amended to read as follows:

l (B)

Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

183, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

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

FOR THE NUCLEAR REGULATORY COMMISSION l

Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 7, 1993 i

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

183 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.

183 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Paaes Insert Paaes TS 3.8-3 TS 3.8-3 TS 3.8-4 TS 3.8-4 TS Figure 3.8-1 TS Figure 3.8-1

1 TS 3.8-3 c.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or i

d.

Otherwise, place the unit in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D.

Intemal Pressure 1.

Containment air partial pressure shall be maintained within the acceptable operation range as identified in Figure 3.8-1 whenever the Reactor Coolant System temperature and pressure exceed 350*F and 450 psig, respectively.

r a.

With the containment air partial pressure outside the acceptable operation range, restore the air partial pressure to within acceptable limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SHUTDO"3! within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Basis CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment will be restricted to those leakage paths and associated leak rates assumed in the accident analysis. These restrictions, in conjunction with the allowed leakage, will limit the site boundary radiation dose to within the limits of 10 CFR 100 during accident conditions.

The operability of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

The opening of manual or deactivated automatic containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing an operator who is in constant communication with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and 1

Amendment Nos. 183

TS 3.8-4 (3) assuring that environmental conditions will not preclude access to close the valves and 4) that this administrative or manual action will prevent the release of radioactivity outside the containment.

The Reactor Coolant System temperature and pressure being below 350*F and 450 psig, respectively, ensures that no significant amount of flashing steam will be formed and hence that there would be no significant pressure buildup in the containment if there is a loss-of-coolant accident. Therefore, the containment intemal pressure is not required to be subatmospheric prior to exceeding 350 F I

and 450 psig.

The allowable value for the containment air partial pressure is presented in TS Figure 3.8-1 for service water temperatures from 25 to 95*F. The allowable value l varies as shown in TS Figure 3.8-1 for a given containment average temperature.

The RWST water shall have a maximum temperature of 45'F.

The horizontal limit lines in TS Figure 3.8-1 are based on LOCA peak calculated pressure criteria, and the sloped line is based on LOCA subatmospheric peak pressure criteria.

The curve shall be interpreted as follows:

The horizontal limit line designates the allowable air partial pressure value for the given average containment temperature. The horizontallimit line applies for service water temperatures from 25*F to the sloped line intersection value (maximum service water temperature).

From TS Figure 3.8-1, if the containment average temperature is 112*F and the service water temperature is less than or equal to 83*F, the allowable air partial pressure value shall be less than or equal to 9.65 psia.

If the average containment temperature is 116*F and the service water temperature is less than or equal to 91*F, the allowable air partial pressure value shall be less than or j equal to 9.35 psia. These horizontal limit lines are a result of the higher allowable initial containment average temperatures and the analysis of the pump suction break.

Amendment Nos.183

TS Figure 3.8-1 ALLOWABLE AIR PARTIAL PRESSURE SURRY POWER STATION UNITS 1 AND 2 TC MINIMUM = 100 'F iII i i

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25 35 45 55 65 75 85 95 SERVICE WATER TEMPERATURE (*F)

FIGURE NOTATION TC - Containment average temperature FIGURE NOTES

1. Refueling Water Storage Tank temperature s 45*F.

2. Allowable operating air partial pressure in the containment is a function of service water temperature.

3. Horizontallines designate a!!owable air partial pressure per given containment average temperature.

4. Each containment temperature line is a maximum for the given air partial pressure.

Amendment Nos.183

ML20056H407

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