ML20031C622

Forwards Description of Design of Modified Containment Vent & Purge Sys.Mod Scheduled to Be Installed Prior to Startup Following First Refueling

ML20031C622
Person / Time
Site:	Farley
Issue date:	09/30/1981
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8110070361
Download: ML20031C622 (4)

Text

Mailing Addr:ss Alabama Power Company 600 North 18th Street Post Office Box 2641 Berrningham, A!abarna 35291 Telephone 205 /83-6081 F. L. C'ay ton, Jr.

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Docket No. 50-364

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ll Direr. tor of Nuclear Reactor Regulation E-U. S. Nuclear Regulatory Commission 2 gOI

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%?s&rotu Q Attention: Mr. S. A. Varga 5y y

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Ref: Joseph M. Farley Nuclear Plant - Unit 2 NPF-8 License Condition 2.C.(17)

As required by the Joseph M. Farley Unit 2 Full Power Licence, NPF-8 [ paragraph 2.C.(17)], the design of a modified containment vent and purge system to reduce the use of the 18-inch purge valves during power operation is submitted (see attachment). This modification is scheduled to be installed prior to startup following the first refueling.

If you have any questions, please advise.

Yours very ru l

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L F. L. Clayton, Jr.

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FLCJr/ JAR:de Attachment cc: Mr. R. A. Thomas (w/ attachment)

Mr. G. F. Trowbridge (w/ attachment)

Mr. J. P. O'Reilly (w/ attachment)

Mr. E. A. Reeves (w/ attachment)

Mr. W. H. Bradford (w/ attachment) koN 8110070361 010930 (g \\

DR ADOCK 05000

ATTACHMENT Alabama Power Company is replacing the existing 18-inch Containment Mini-Purge Valves (valves 289, 290, 291, 292 on Figure 1) with 8-inch butterfly valves (valves 289, 290, 291, 292, 294, and 295 on Figure 2).

It should be noted that an additional 8-inch butterfly valve was a.dded in series inside containment on both the supply (valve 294 on Figure 2) and i

exhaust (valve 295 on Figure 2) lines. While these additional valves are not containment isolation valves, they will meet the fabrication requirements for containment isolation valves and are being purchased to the same specification as the containment isolation valves (valves 289, 290, and 292 on Figure 2).

The containment isolation valve arrangement remains as shown in FSAR Chapter 6.

The added valves (valves 294 and 295 on Figure 2) are designed to close upon receipt of a containment isolation signal. All of the new 8-inch valves are actuated by an air-operated Bettis actuator.

The actuator design is " air-to-open and spring-to-close" with the valve failing in the closed position.

Both the valves and actuators will be qualified siesmically and environmentally, have a design life of 40 years, and can withstand a cumulative radiation

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dose of 1x108 rads (gamma). The siesmic qualification will be accomplished by prototype testing prior to operation of the system.

The valycs will be capable uf opening or closing against DBA, LOCA and Steamline Break conditions. The valve is designed to function at a pressure 80 psig., a taperature of 387# F, a maximum differential

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pressure of 80 psi, 100% re,lati w humidity, cnd containment spray (Na0H and 10,000 PRM Boric acid). The closing time of the valve at design conditions will be less than or equal to 3.5 seconds. These valves will close upon receipt of a containment isolation signal (ger.erated as a resuit of safety injection, high containment pressure, or high containment radiation) and will remained closed on safety injection reset as required by IEB 80-06.

The valves will comply with the following standards:

ASME Boiler and Pressure Vessel Code, 1980 edition Sections II, III, V, VIII, IX ANSI B16.5 - 1977 i

ANSI N271 - 1976 ANSI N45.2.2 ANSI N45.2.6 MSS-SP-67, Butterfly Valves IEEE 323, 1974 IEEE 344, 1975 This design was discussed with the NRC staff in March and April of this year.

It complies with the requirements of Branch Technical Position CSB-6-4 and the Unit 2 SER, Supplement 5, Section 6.2.3.5.

The new valves and design meet or exceed all assumptions presently used in accident analysis. The proposed modifications have no adverse impact on safety or any analysis.

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