ML20005A390

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Notifies That Util Is Participating in EPRI PWR Safety & Relief Valve Test Program Per NUREG-0737,Item II.D.1. Valves Representative of Facility Safety Valves Will Be Tested by End of Jul 1981
ML20005A390
Person / Time
Site: Farley  
Issue date: 06/25/1981
From: Clayton F
ALABAMA POWER CO.
To: Varga S, Youngblood B
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8106300274
Download: ML20005A390 (2)


Text

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Mailing Address d

Abb _ma Power Company c

vi 600 fjorth 18th Street Post Office, Don 2641 Birmingnam. Alsbama 35291

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Telephone 205 783-6081

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F. L Clayton, Jr.

Senior Vice President Alabama Power Flintridge Builtng June 25, 1981 Docket Nos. 50-348 M

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50-364 D

Director, ti/ clear Reactor Regulation f9 PF 1/s U. S. Nucicar Regulatory Commission g *{L g'

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Washington, D. C.

20555

e e-JU ' 2 91981 m Attention
Mr. S. A. Varga
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E ccmssa JOSEPH M. FARLEY NUCLEAR PLANT - UNITS 1 AND 2 o.

NUREG-0737, ITEM II.D.1 AND

' ' b l co NPF-8 LICENSE CONDITION 2.C(21)(d)

Gentlemen:

In accordance with the requirements of NUREG-0737, Item II.D.1 and the Farley Nuclear Plant - Unit 2 Operating License NPF-8 (Section F.C(21)(d)),

Alabama Power Company is participating in the EPRI PWR Safety and Relief Valve Test Program to demonstrate the operability of the Farley Nuclear c

Plant (FNP) - Units 1 and 2 Pressurizer Safety Valves (SV) and Power Operated ReliefValves(PORV).

Mr. R. C. Youngdahl of the Westinghouse Owners Group is scheduled to transmit the Interim Data Report for the SV/PORV test program on July 1, 1981. This report will summarize the test data collected to date on relief valves (safety valve data is not yet available) and provides justification for the selection of the particular valves for testing.

The FNP Units 1 and 2 have Copes-Vulcan Model D-100-160 3" (17-4 PH cage, 316 w/ stellite plug) relief valves and Crosby Model HB-BP-86 size 6M16 safety valves.

Preliminary results provided in Section 4.6 of the EPRI Interim Data Report are applicable to the FNP PORVs.

It is expected that testing will be completed on the FDP PORVs by mid-July 1981.

Evaluation of the preliminary data indicates that the FNP PORVs will perform their intended function. The present schedule indicates that valves representative of the FNP safety valves will be tested by the end o.' July 1981.

Alabama Power Company will supply additional information on the qualification of the PORVs and SVs when the applicable test data is available.

If there are any questions, please contact us.

Yours ver tru) a6 % y W.L.Clayton%,

, Jr.

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Mr. S. A. Varga Mr. B. J. Youngblood 2-June 25, 1981 cc: Mr. R. A. Thomas '

Mr. G. F. Trowbridge Mr. J. P. O'Reilly

~1 Mr. E. A. Reeves Mr. J. O. Thoma Mr. W.11. Bradford h

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