ML19351F462

Forwards Revised Data for Tech Spec Table 3.4-1 & Discusses Leak Tight Integrity of Primary Coolant Sys Pressure Isolation Valves

ML19351F462
Person / Time
Site:	Summer
Issue date:	01/06/1981
From:	Nichols T SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8101130126
Download: ML19351F462 (3)

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south CAROLINA ELECTRIC & GAS COMPANY 9; '

PO%T O F FIC E. 80 8 7#4

COLUMBIA. SOUTH CAROLINA 29218 { '

T. C. Nicwots, J n. Janulry 6, 1981 j wcir o m....oc.o.r.m.m.  ;

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u, Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20535 i

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 i Leak Tight Integrity of Primary Coolant System Pressure Isolation J,

Valves

Dear Mr. Denton:

Subsequent to discussions with Mr. A. Cappucci by telephone on January 5 and 6, 1981, concerning information addressed in a November 20, 1980 letter to Mr. Denton, South Carolina Electric and Gas Company, acting for itself and as agent for South Carolina Public Service Authority, herewith provides forty-five (45) copics of the requested additional information. Technical Specification Table 3.4-1 is revised as shown on the attachment.

There exists three casts where there are systems rated at less than 50% of RCS design pressure. These three cases and a discussion of testing required each time the associated valves are actuated due to automatic or manual action or flow through the valve are as follows:

Case 1: RHR Suction Valves From Hot Legs (Valves 8701 A,B and 8702 A,B)

As shown on the attachment, these valves are not tested fol-l lowing valve actuation due to automatic or manual action or flow through the valve. Justification for not performing this

- testing is: (1) These valves have pressure interlocks that insure that they are closed at reactor coolant system pressures greater than 425 psig, (2) These valves have position indica-tion available in the nain control reon and, (3) There are relief valves located downstream of these valves that would protect the low pressure piping in the event of a leak. These re? ief valves discharge to the Pressurizer Relief Tank which can be used for identifying leaks associated with these valves.

Case 2: SI Low Head to Cold Legs (Valves 8974 A,B; 8973 A,B,C; and 8998 A,B,C)

As shown on the attachment, these valves are not tested fol-lowing valve, actuation due to automatic or manual action or flow t: rough the valve. As discussed with :Ir. Cappucci, with the adoition of valves 8974 A,B to the table, this testing is not required.

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Mr. Harold R. Denton January 6, 1981 Page Two Case 3: Accumulators to Cold Legs (Valves 8448 A,B,C and 8956 A,B,C)

As shown on the attachment, these valves are tested following valve actuation due to automatic or manual action or flow through the valve.

The remainder of the valves shown on the attachment are part of systems which are rated at greater than 50% of RCS pressure.

If you have further questions, please let us know.

Very truly yours,

", r#. f.lc T. C. Nichols, Jr.

RBC:TCN:glb

Enclosures:

cc: V. C. Summer w/o enclosures G. H. Fischer w/o enclosures T. C. Nichols, Jr. w/o enclosures E. H. Crews, Jr.

O. W. Dixon, Jr.

D. A. Nauman O. S. Bradham W. A. Williams, Jr.

A. A. Smith A. R. Koon R. B. Clary J. B. Knotts, Jr.

J. L. Skolds B. A. Bursey NPCF/Whitaker File e

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REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NO. DFSCRIPTION REF. DWG.

8993 A,B,C SI to Hot Legs 1143075 Sh. 1 8992 A,B,C SI High Head to Hot Legs 114E075 Sh. 1 8990 A,B,C SI High Head to Hot Legs ll4E075 Sh. 1 8988 A,B SI Low Head to Hot Legs 114E075 Sh. 1 8997 A,B,C Primary SI High Head to Cold Legs ll4E075 Sh. 1 8995 A,B,C Alternate SI High Head to Cold Legs ll4E075 Sh. 1 8998 A,B,C SI to Cold Legs ll4E075 Sh. 1 8973 A,B,C RHR Low Head to Cold Legs 114E075 Sh. 3

• 8948 A,B,C Accumulators to Cold Legs ll4E075 Sh. 2

• 8956 A,B,C Accumulators to Cold Legs 114E075 Sh. 2 8701 A,B RHR Suction from Hot Legs ll4E074 8702 A,B RHR Suction from Hot Legs ll4E074 8974 A,B RHR Low Head to Cold Legs 114E073 Sh. 3 I

• Valves Leak Tested prior to entering Mode 2 following valve actuation due to automatic or manual action or flow through the valve.

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