ML20041F147
| ML20041F147 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/12/1982 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-TM NUDOCS 8203160233 | |
| Download: ML20041F147 (2) | |
Text
l j
i SOUTH CAROLINA ELECTRIC & GAS COMPANY voss arrect mon res N
y CotuMe:A, Sourn CAnoWNA 29288 T C. NicHoLs,Ja.
s
?l.N,gg?
'( 3 vu p.na, m o.ou. c.umm
'lv [..
March 12, 1982
\\hN g['[
3 Mr. Harold R. Denton, Director
$$i Office of Nuclear Reactor Regulation x /
U. S. Nuclear Regulatory Comnission g _ x ',/
Washington, D.C.
20555
- M
/
Subject:
Virgil C. Sumner Nuclear Station Docket No. 50/395 NUREG 0737 Iten II.D.3
Dear Mr. Denton:
In a letter dated February 26, 1982, South Carolina Electric and Gas Cmpany (SCE&G) informed you of our decision to utilize limit switches to conply with NUREG 0737, Iten II.D.3 requirements for positive indication of pressurizer safety valve position at the Virgil C. Sumner Nuclear Station.
As discussed in the previous letter, SCE&G had initially proposed the use of a Westinghouse Acoustic Leak Detection System to perform this function. The Westinghouse systen is and will remain installed and operational, however future qualification testing of this equipnent will be suspended.
The limit switches are scheduled for installation by May 1, 1982. As we had indicated previously, the qualification testing on the switches is presently scheduled to be conplete in April, 1982. The qualification reports should be available in June, 1982.
SCE&G believes that this schedule is satisfactory for the following reasons:
1.
As indicated in our letter to you dated November 16, 1981, based on conpletion of part of the qualification program and results from the testing of similar equipment, the Westinghouse Acoustic Leak Detection System was expected to successfully conplete qualification as it is designed and installed in the Virgil C. Sumner Nuclear Station. Therefore, we have a high degree of confidence that this system will perform its design function.
2.
As statal in Section 5.5.10.2.2.4 of the FSAR, monitoring the status of the pressurizer safety valves can be acconplished using the following methods.
a) Tenperature detectors in the piping downstream of the valves b) Acoustic Leak Monitoring Systen O I s
iD 8203160233 820312 PDR ADOCK 05000395 A
f
- f' s
Mr. Harold R. Denton
. March 12, 1982 Page 2 c) Pressure, tenperature and level in the pressurizer relief tank These instrunents along with the safety valve limit switches provide indications and/or alarm on the main control board.
It is our position that, the above reasons are sufficient to justify fuel load and operation up to full power.
Should installation and/or qualification of the limit switches not be couplete prior to fuel load, we hereby request relief on the TMI Item II.D.3 fuel load requirement based on the above reasons.
If you have additional questions, please let us know.
Very truly yours,
/g A
t-T. C. Nichols, Jr.
NEC:'ICN:lkb cc:
V. C. Sunmer 4
G. H. Fischer H. N. Cyrus T. C. Nichols, Jr.
M. B. Whitaker, Jr.
J. P. O'Reilly H. T. Babb D. A. Nauman C. L. Ligon (NSRC)
W. A. Williams, Jr.
R. B. Clary O. S. Bradham A. R. Koon M. N. Browne G. J. Braddick J. C. Ruoff J. L. Skolds l
J. B. Knotts B. A. Bursey NPCF File
.-