ML20039G847
| ML20039G847 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/15/1982 |
| From: | Clary R SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Virgilio M Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8201190216 | |
| Download: ML20039G847 (1) | |
Text
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.o SOUTH CAROLINA ELECTRIC & GAS COMPANY Post orries sox 7s4 COLUMBI A. S. C. 29218 January 15, 1982
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Mr. Martin Virgilio 9
Office of Nuclear Peactor Pegulation
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U. S. Nuclear Pegulatory Ccumission Washington, D. C.
20555
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Dear Mr. Furtin:
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In regards to our discussion regarding the leak tight integrity of primary coolant systen pressure isolation valves, I am enclosing a copy of our letter to fir. Denton dated January 6,1981. In this letter, we explain wtty we only have to test the accumulation after each actuation due to autanatic l
or manual action or flow through the value.
Very truly yours, k4 Ronald B. Clary, Manager Nuclear Licensing ikb cc:
D. A. Nauman W. A. Williams, Jr.
R. B. Clary w/ attach.
O. S. Bradham A. R. Koon w/ attach.
W. R. Kane L. D. Shealy w/ attach.
f M. B. Whitaker, Jr.
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W. R. Baehr w/ attach.
g NPCF File
!I 8201190216 820115 PDR ADOCK 05000395 PDR A
Sci 1TH CAROLINA ELECTRIC a gas COMPANY
.,or,,e CotunsiA. SouTM CAnouuA asate T. C. Nicuots. Ja.
January 6, 1981 MCE Pegaatsat.ase Geowe EstCynog
. e,mae Mr. Harold R. Denton, Director Office of Nuclear Reactcr Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Leak Tight Integrity of Primary Coolant System Presrure Isolation' 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 I
(45) copies of the requested additional infccmation. Technical Specification Table 3.4-1 is revised as shown on the attachment.
There exists three cases 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-loving 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 main control room and, (3) There are
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relief valves located downstream of these valves that would protect the low pressure piping in the event of a leak. These relief 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,3; 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 through the valve. As discussed with Mr. Cappucci, with the addition of valves 8974 A,B to the table, this testing is not required.
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Mr. Harold R. Denton
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January 6,1981 Page Two i
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, I.
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T. C. Nichols, Jr.
RBC:TCN:glb
Enclosures:
I V. C. Su=mer w/o enclosures cc:
C. 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 0
lo me REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NO.
DESCRIPTION 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 114E075 Sh. 1 8988 A,3 SI Low Head to Hot Legs ll4E075 Sh. 1 8997 A,B,C Primary SI High Head to Cold Legs 114E075 Sh. 1 8995 A,B,C Alternate SI High Head to Cold Legs 114E075 Sh. 1 8998 A,B,C SI to Cold Legs ll4E075 Sh. 1 l
8973 A,B,C RHR Low Head to Cold Legs 114E075 Sh. 3
- 8948 A,B,C Accumulators to Cold Legs 1
114E075 Sh. 2
- 8956 A,B,C Accumulators to Cold Legs 114E075 Sh. 2 8701 A,B RER Suction from Hot Legs ll4E074 8702 A,B RHR Suction from Hot Legs ll4E074 8974 A,B RHR Low Head to Cold Legs ll4E073 Sh. 3
- 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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