ML20149J328
| ML20149J328 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/16/1988 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Hayes J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.097 GL-82-33, NUDOCS 8802220361 | |
| Download: ML20149J328 (2) | |
Text
s So th Ca na Electric & Gas Company n A. N um n lumbia 29218 Nuclear Operations SCE&G
= =, -
February 16, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention: Mr. John J. Hayes
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Generic Letter 82-33 Regulatory Guide 1.97 Gentlemen:
In a letter dated November 13, 1987, South Carolina Electric & Gas Company (SCE&G) received a request for information from the NRC concerning the SCE&G previous responsas on Regulatory luide 1.97, Revision 3.
The letter stated that the SCE&G actions to meet t' a requirements found in the regulatory guide were acceptable with the exception of three items. Additional information is hereby being provided to address the concerns dealing with these items.
Regulatory Guide 1.97 recommends instrumentation with a range of 40 F to 400 F to monitor the containment atmosphere temperature during post accident conditions. The SCE&G instrumentation range for monitoring containmert atmospheric temperature is 50 F to 350 F.
The peak calculated Reactor Building temperature for the Virgil C. Summer Nuclear Station is the result of the postulated 0.645 ft2 double ended rupture of a main steam line at 102%
power assuming emergency feedwater fails to isolate and the diesel generator fails to start.
The peak temperature in this case is calculated to be 321.5 F, 83 seconds af ter the break.
(Seesection 6.2.1.3.1.2 of the Virgil C. Summer Nuclear Station Final Safety Analysis Report (VCSNS FSAR).)
Computer program CONTEMPT LT/26 was used to analyze this FSAR steam line break and obtain the containment temperature values. This computer code is discussed in detail in section 6.2.1.3.3.1 of the FSAR. Based on this information the installed instrumentation would remain on scale during and after accident conditions and is considered to meet the intent of Regulatory Guide 1.97.
Therefore, SCE&G considers the present instrumentation acceptable.
8802220361 880216 PDR ADOCK 05000395 d
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b Gentlemen February 16, 1988 Page 2 Regulatory Guide 1.97 recommends Category 2 instrumentation be provided to monitor a release from the steam generator safety relief valves or atmospheric dump valves. The steamline monitors utilized at the Virgil C.
Summer Nuclear Station conform to the criteria for Type E, Category 2 variables with the exception of environmental qualification. This exception is justifiable since the monitors are located in areas of mild environment during accident conditions for which the monitors are required to supply indications. These monitors are located in Reactor Building Penetration Access Areas and are not required to provide information during main steamline break conditicns at their respective locations.
During design basis steam generator tube rupture events, during which the monitors are required, they will be exposed to the following maximum conditions:
Temperature 104 F Pressure Atmospheric Relative Humidity 90%
Radiation
< 1 x 103 Rad TIO 6 months Chemicals None Therefore, SCE&G considers the qualification of the steamline radiation monitors to be acceptable and meets the intent of the requirements of Regulatory Guide 1.97.
As discussed in the NRC November 13, 1987 letter, the issue of the environmental qualification of Category 2 instrumentation, and thus the acceptability of the current SCE&G accumulator tank level and pressure instrumentation, is a generic issue still under review by the NRC staff. Any additional information required by the NRC from SCE&G at the conclusion of the generic review will be provided upon request. Until that time, the acceptability of the accumulator tank level and pressure instrumentation will remain an open issue.
If you should require any additional information, please advise.
Very.tr ly yours, Nauman r
AMM/ DAN: led c:
- 0. W. Dixon, Jr./T. C. Nichols, Jr.
T. L. Matlosz E. C. Roberts R. M. Campbell, Jr.
O. S. Bradham K. E. Nodland W. A. Williams, Jr.
J. C. Snelson J. N. Grace G. O. Percival General Managers R. L. Prevatte C. A. Price J. B. Knotts, Jr.
G. G. Soult NSRC J. R. Proper RTS l
R. B. Clary NPCF W. R. Higgins File
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