ML19354D459

Submits Addl Info Re Performance Testing of Relief & Safety Valves.Attachment I Reproduces Operating Mode Data in Util 820512 Ltr.Porv Flow Rates Used in Thermal Hydraulic Analysis Instead of Flow Test Results from EPRI Testing

ML19354D459
Person / Time
Site:	Catawba
Issue date:	10/27/1989
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8911090192
Download: ML19354D459 (3)

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HAL H. TUCKEN '

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F October 27, 1989.

U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, D.C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Performance Testing'of Relief and Safety Valves Ge'ntlement

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My April 29, 1988 letter to the NRC transmitted a response to Dr. K. N.

Jabbour's July 31, 1987 request for additional information regarding the

'- performance testing of relief and safety valves'(Item II.D.I of NUREG-0737).

The response to Question No. 9(D), Initial Conditions and Flow Rates, referenced a May 12, 1982 internal Duke Power letter No. CN-5A-82-0926.

- This letter can no longer be found in our files. The May 12, 1982 letter contained the operating mode data for the extended HPI transient.

Attachment I reproduces the operating mode data in the May 12, 1982 letter.

The' PORV flow rates provided in Attactunent I were used in the Catawba thermal hydraulic analysis instead of the flow test results from EPRI spcnsored PORV testing. The EPRI tests show the PORVs capable of passing flow rates up to 900,000 lbm per hour. These tests are described in EPRI 1 Special Report NP-2628, EPRI PWR Safety and Relief Valve Test Program dated December 1982.

-The EPRI-sponsored tests of Pressurizer PORVs and safety valves bound a variety of conditions which may or may not occur during actual transients and'FSAR accidents. The 900,000 lb/hr flow rate at 440* F (Test No.

38-CC-5W, EPRI, Special Report NP-2628, Table 4.4.1-2a) was an "as-tested" result during Phase III PORV testing at Wylie Labs. This flow rate is not

, representative of the expected response to transients. The 900,000 lbm por hour flow rate only demonstrates that the valve internals and valve operator ,

can tolerate flows which bound expected conditions without failure to open l and close on demand. i Westinghouse performed transient analyses concurrently with the EPRI tasts to determine the expected inlet conditions at which PORVs and safety valves would be challenged in response to FSAR accidents, extended HPI transients, l and cold overpressure transients. Results of these analyses are presented a.

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. ' October 27, 1989 L

f' in'EPRI Final Report'NP-2296, Valve Inlet Fluid Conditions for Pressurizer ,

Safety and Relief Valves in Westinghouse-Designed plants. This report was used to generate the parameters specified in EPRI Special Report NP-2628.:  ;

The fluid conditions at the inlet to the PORVs during the extended HPI transients in Westinghouse 4-loop plants range from 565'F to 569'F at 2350 psia. These fluid conditions result in an expected flow rate from 113.1 to 1104.1 gpm (40.788 lbm/hr to 398,181 lbm/hr) considering maximum pressurizer "

surge line flow. These values are slightly different from those in Attachment I because of conversions and-interpolations.- The actual flow . -

trate achieved in the analysis is 414,000 lb/hr.

Very truly yours,

/ 9emos F

H. B. Tucker JGTill/lcs xc: Mr. S. D. Ebneter Regional Administrator, RII U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Dr. K. Jabbour Office of Nuclear Reactur Regulations U. S. Nuclear Regulatory Commission One White Flint' North Mail Stop 14H25 Washington, D.C. 20555 hr. W. T. Orders NRC Resident Inspector Catawba Nuclear Station ,

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. OPERATING MODE DATA POR THE EXTENDED- ,

HPI TRANSIENT' 1 .: ,

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, T(*F) P(PSIG) Flow (1b/hr) j Extended HPI; 572-576 '2507 SRV~

.No PORV operating Extended HPI' .

565-569 2353 PORV '

, PORV operating ' 40,646'to 396,792' i

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Notes' ' Flow Rates Are At The 12' Inch Common Header >

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