ML20050B591
| ML20050B591 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/02/1982 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8204060096 | |
| Download: ML20050B591 (3) | |
Text
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4 SourH CARollNA ELECTRIC a gas COMPANY L
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4pril 2, 1982 2
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Mr. liarold R. Denton, Director L5 ^ *
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Office of Nuc1 car Reactor Regulation 4
l U. S. Nuclear Regulatory Commission U 7r-d 4 7 Washington, D. C.
20555 J W
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 ESF Response Times
Dear Mr.Denton:
In our March 31, 1982 letter South Carolina Electric and Gas Company (SCE&G) provided infornation for the technical specifications regarding ESF response times. On April 1, 1982 the NRC staff requested additional information relating to the associated FSAR pages. Attached to this letter are marked up FSAR pages 7.3-41 and 7.3-42 which provide the I
information requested. These changes will be incorporated in the next FSAR amendment.
If you have any questions, please let us know.
Very truly yours, T. C. Nichols, Jr.
RBC:TCN:jes t
Attachment cc:
V. C. Summer (w/o attach.)
J. C. Ruoff G.11. Fischer (w/o attach.)
J. L. Skolds
- 11. N. Cyrus J. B. Knotts, Jr.
T. C. Nichols, Jr.
(w/o attach.)
B. A. Bursey M. B. Whitaker, Jr.
NPCF J. P. O'Reilly File
- 11. T. Babb 0l D. A. Nauman 0
C. L. Ligon (NSRC) y W. A. Williams, Jr.
j 1
R._B.
Clary
- 0. S. Bradham A. R. Koon M. N. Browne G. J. Braddick 8204060096 820402 PDR ADOCK 0500039]
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l0h 9-t95
- hh4 AMENDMENT Q +) 1 /I
' 0 02 TABLE 7.3-4
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SECONDARY SYSTEM ACCIDENTS AND REQUIRED INSTRUMENTATION, MINOR SECONDARY SYSTEM PIPE BREAK, MAJOR SECONDARY SYSTEM PIPE BREAK 1
Response
Channel Time Accuracy (1)
Range
.3 Reactor Building Pressure (2) 1.5 see i 1.75% of
-5 to 15 peig 29 full scale Steam Line Pressure 1.0 see 12.25% of 0 to 1300 span psig Steam Line Differential Pressure 1.0 see 13.0% of span 0 to 1200 psig I)
Steam Line Flow 2.0 see 14.5% of maximum 0 to 120% maximum guaranteed flow calculated flo-w over the pressure range of 700 to 1200 psig 2)
T,yg 6.0 see 12'F 530 to 630*F Pressurizer Pressure 1.0 see 11.75% of 1700 to 2500 span psig Notes:
1.
See Sestion 7.1 for definition / of ESFAS :::;:---
1 f accuracy.
/31 2.
Used for closing main steam line stop valves.
3.
RCS T as measured at the resistance temperature detector output
~.
'1 inclu81Elg 2 seconds for RTD bypass loop transport delay - assume other
,,, e s' m) [ro m h/ktn /Ac /non/ rCUnramder eXcd.r//.c E$
g setpinf <f fA' c4 noel.reasoe ',f-} the cAannel bhAM chanses sfale.
(*d 1 ~/ -BZ
/x/ f'h5 31.
f t#.ENDMENT 19 hd M TABLE 7.3-5 1982
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PRIMARY SYSTEM ACCIDENTS AND REQUIRED INSTRUMENTATION RUPTURES IN SMALL PIPES, CRACKS IN LARCE PIPES, RUPTURES OF LARGE PIPES, STEAM CENERNIt)R TUBE RUTURE i
Respo se Channel Time (27 Accuracy (1)
Range s.
Pressurizer 1.0 see 11.75% of 1700 to 2500 psig Pressure span Reactor Building 1.5 see 11.75% of
-5 to 15 psig 29 Pressure (2) span
[
t (1}SeeSection7.1fordefinitio/ofESFAS--;:nr:
'n.
' accuracy.
3/
Not required for steam generator tube rupture.
(3) Tlat timeinterval from When f4e moniforadparameter exceeds iis
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Eff.refpoint af the cAannel sensor un fil Ae clan nel birfiMc 3'
'4nfer.rfafe.
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7.3-42