LD-84-049, Forwards Response to Mechanical Engineering Branch 840424 Request for Addl Info Re Operability of Shutdown Cooling Sys Relief Valves Used on Sys 80 Std Plant.Valves in Question Will Function Under Anticipated Design Conditions

Forwards Response to Mechanical Engineering Branch 840424 Request for Addl Info Re Operability of Shutdown Cooling Sys Relief Valves Used on Sys 80 Std Plant.Valves in Question Will Function Under Anticipated Design Conditions

ML20097A563
Person / Time
Site:	Palo Verde, Waterford, 05000000, 05000470, Satsop
Issue date:	09/07/1984
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
LD-84-049, LD-84-49, NUDOCS 8409130307
Download: ML20097A563 (4)

Text

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C-E Power Systems Tel. 203/688-1911 g) Combustion Engineering. Inc.

1000 Prospect Hill Road Telex: 99297 Windsor, Connecticut 06095 POWER M SYSTEMS Docket No: STN 50-470 September 7, 1984 LD-84-049 Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

SCS Relief Valve Operability

Reference:

NRC letter, C. O. Thomas (NRC) to A. E. Scherer (C-E),

dated April 24, 1984

Dear Mr. Eisenhut:

This letter provides information requested in the reference letter regarding the operability of the Shutdown Cooling System (SCS) relief valves used on C-E's System 80' Standard Plant.

The enclosure provides a discussion of data which leads C-E to believe that the valves in question v:111 ft.nction properly under their anticipated design conditions, since the installed valves are'similar to those tested in both design and operating principal.

If you have any questions on this subject please do not hesitate to contact me or Mr. T. J. Collier of my staff at (203)285-8215.

Very t ruly you rs ,

COMBUSTION ENGINEERING, INC.

h R-A. E. Scherer Director Nuclear Licensing )

I AES:jld l Enclosure l cc: K. T. Eccleston (U.S. NRC Project Manager) 09 t

8409130307 840907 PDR ADOCK 05000382 A PDR

. . r' Enclosure

-.- LD 049 Response to the NRC Mechanical Engineering Branch Request for Additional Information The following information is provided in response to the NRC request for information which would substantiate operability of the Shutdown Cooling System

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(SCS) relief valves which are specified for.Waterford Unit 3, Palo Verde Units L 1-3, Washington Nuclear Project 3 and C-E System 80". Significant data is recorded which demonstrates that these valves will open and close under their

! anticipated fluid conditions.

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L Test reports of relief valve testing by the Crosby Valve and Gage Company (Crosby) and Dresser Industries, Inc. (Dresser) provide the requestad evidence of- operability of ~ the SCS relief valves specified for the identified units.

Crosby valves are installed at Waterford 3 and Palo Verde 1-3. Dresser valves i

are installed at WNP 3. Table 1 presents specific data on these installed and i . tested valves. ,

Relief valve operability testing was conducted by Crosby for seismic qualification of two models of relief valves purchased by C-E. The results of these tests demonstrated that the relief. valves would operate properly before,

, during and after application of static loads simulating maximum seismic l

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deflection and maximum pipe loads. The tests were conducted with both steam and water. A Crosby 6R10 JB-56-TD steam service valve was tested with steam with seismic loads applied. This valve is similar to the Crosby 6R10 J0-55 liquid service valve supplied for the three Palo Verde units. The major difference between these two velves is that the test valve was equipped with a bellows. This is not considered significant because no appreciable back pressure was present during testing. A Crosby 4P6 J0-45 liquid service valve was tested with water with both seismic and pipe loads applied. This valve was supplied to TVA for the Yellow Creek units for use in the shutdown cooling

, system.

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r The steam tests (Crosby 6R10 JB-56-TD) were conducted at full pressure (490 psig) and demonstrated proper valve operation with stable and consistent valve performance. _Tha water tests (Crosby 4P6 J0-45) were conducted at a reduced pressure of 66 psig with a prorated spring in order to achieve high flow rates through the valve. (The test facility's centrifugal pump had insufficient capacity at the full set pressure of 435 psig.) The valve was tested with subcooled water at a flowrate approximately 96 percent of the full pressure rated relief capacity. This valve also showed stable and consistent valve performance and proper valve operation. Both Crosby tests demonstrated the valves ability to successfully open, achieve full lift, and reseat.

The Dresser valves for WNP Unit 3 were tested at the factory. These tests were Dresser's standard production tests on each valve it manufactures that is specified for SCS service, which consists of a full flow test using steam.

Test data was recorded for the WNP 3 valves which have been specified at 1333 gpm and 435 psig set pressure. The test which was performed at the actual set pressure, successfully demonstrated that the valve will open, achieve full l'.ft and reseat.

Table 1 lists the shutdown cooling system relief valves specified for WNP 3, Waterford 3 and Palo Verde 1, 2, and 3. Included for comparison is the valve model intended for TVA's Yellow Cree.k units because of the seismic operability tests which had been performed on that valve. These steam and water tests envelope the subcooled water fluid conditions expected in the plants.

The valves which were tested for operability adequately span the size and capacity ranges for the installed valves. Also, since the installed valves are of similar design and operating principle to those tested, C-E considers these operability tests to be applicable.

Based upon these successful valve tests C-E expects the valves to operate correctly providing the required pressure relief capacity and subsequently

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reclosing under actual service conditions.

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TABLE 1

. .. Shutdown Cooling System Relief Valves Orifice Set Rated Inlet Outlet Area Press. Flow Vendg _~Model (h. ) (M. ) (M.2) (gsia) (Spm) Plant

.Specified Valves:

Dresser 1910-30/P/P1 4 6 7.417 43:s 1333 WNP 3 Crosby. JB-55-w 6 8 11.045 415 3505 Waterford 3

Crosby J0-55 6 10 16.0 467 4000 Palo Verde 1, 2, 3 Test Test Tested Valves: Press. Test Flow (psig) Medium (gpm)

Dresser 1910-30/P/P1 4 6 7.417 435 Steam (1)

Crosby J0-45 4 6 6.379 66 Water 1923 Crosby' JB-56 6 10 16.0 490 Steam (1)

(1) Tested with steam, flow not recorded

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