ML20062A656
| ML20062A656 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/16/1978 |
| From: | Crews E SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810170105 | |
| Download: ML20062A656 (6) | |
Text
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SOUTH CAROLINA EttcTRic a gas COMPANY
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i COLUMelA, SOUTH CAROUNA 29210
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c, October 16, 1978 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 4
Subj ect: Virgil C. Sunumer Nuclear Station Docket No. 50-395 Evaluation of Safety Related Equipment Temperature Transients During the Limiting Main Steam Line Break in Containment Revision 1 Dacr Mr. Denton:
South Carolina Electric & Gas Company, acting for itself and as agent for d
South Carolina Public Service Authority, herewith files forty-three (43) copies of Revision 1 of Report No.1987 entitled " Evaluation of Safety Related Equipment Temperature Transients During the Limiting Main Steam Line Break in Containment" which was originally submitted to NR n July 5, 1978. The material submitted l
contains three (3) signed original t sa:3ttal letters and forty (40) conformed copies thereof.
V ry t
- yours,
. H. C
, Jr.
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RBW:EHCJr:msd CC: Messrs.
H. T. Babb G. H. Fischer i
W. C. Mescher 2 -
W. A. Williams, Jr.
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W. S. Murphy NPCF/Dixon f.~__
T. B. Conner, Jr.
i File B. A. Bursey l
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For containment peak temperature analysis, the single failures considered are listed in Table 1.
Only three failures are considered for ruptures with dry cteam blowdowns. These failures maximize the mass and energy release prior to containment sprays actuation.
The peak calculated reactor building temperature of 324 F occurs 73 seconds following a.681 square foot split of a main steam line at 70 percent power.
This break will be used for the purpose of qualification of safety related equipment. Mass and energy release for this break is presented in Reference 5. l Figures 1 and 2 show the reactor building vapor temperature as a function of time for the four split rupture main steam line breaks considered in this analysis.
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The modifications made to CONTEMPT LT/26 are:
As originally programmed, CONTEMPT LT/26 uses the Uchida heat transfer coefficient even if the heat structure is superheated; a heat transfer 2
(
coefficient of 2.0 BTU /hr-ft - F (11.4 w/m - K) should be used. The following equations are now employed:
qt = h A (T,-T,)
q2 = h,A (T -T,)
y i-
.(,
where:
q,q2 = heat transfer rate (h )
g Btu h = Uchida heat transfer coefficient (
)
2 h~ ft oF h, = superheated heat transfer coefficient 2
= 2.0 BTU /hr-ft - F (11.4 w/m - K)
T, = containment vapor saturation temperature ( F) l
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camt-l Rev. 1 10-16-78 l
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REFERENCES 1.
- Uchida, H., Oyama, A. and Toyo Y. " Evaluation of Post-Incident Cooling Systems of Light-Water Power Reactors," Proceeding of the Third International Conference on the Peaceful Uses of Atomic Energy, Geneva, August 31 to September 9, 1964, Vol. 13, New York, United Nations, 1965, pp.93-104, (A/ CONF. 28/P/436).
2.
Westinghouse Electric Corporation, Environmental Qualification
-Instrument Transmitter Temperature Transient Analysis" (NSSS-Non-proprietary), WCAP-8937.
3.
Wheat, L. L., et al, CONTENTT LT - A Computer Program for Predicting
(,
Containment Pressure Temperature Response to a Loss of Coolant Accident Appendix E, ANCR-1219, June 1975.
4.
Kreith, Frank. Principles of Heat Transfer, Scranton, Pennsylvania:
(
International Textbook Company, 1965.
5.
Westinghouse Safety Analysis Standard No. 12.2, " Mass-Energy Release to Containment Following a Steam Line Rupture For Series 51 and D Steam Generators," Revision 1 dated 12/11/75.
AQl s
Geert/Canmonuesta Rev. 1 10-16-78
a TABLE 6 (DELETED) f 1
1 e
i Rev. 1 10-16-78
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