ML18227B313
| ML18227B313 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/19/1975 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18227B313 (6) | |
Text
CONTROL NO:
FILE:
NRC D INTR I BUT ION FOR PART 50 DOCKET MATER IAL
{TEIvlPORARY FORiM) 4 FROM:
plorida-Power.& Light Co Miami, Fla.
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.'DATE OF DOC.
5-19-75 DATE R EC'D 5-22-75 LTR TWX RPT OTHER TO:
Mr Rusche
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ORIG one signed CC OTHER SENT AEC PDR SENT I.OCAL P 0 R CLASS UNCLASS PROPINFO INPUT r
- PLANT NAhlE:
Turkey Point 3 & 4 DESCRIPTION:
Ltr re our request....furnishing info with.regard to EGGS analysis for two.
loop operation'.....'O CYS REC'0 ENCLOSURES:
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FLORIDA POWER & UGHT COMPANY May 19, 19.753-,~;-
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~ptmd%~ D Mr. Benard C.
Rusche Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commissi'on washington, D.
C.
20555
Dear Mr. Rusche:
Re:
Turkey Point Units, 3- & 4 Docket Nos.
50-250
& 50-251 ECCSAnal s'isfor Two L'oo '
erat'i'on This is in response to a reques't'y your Staff,that we supply information on the capability of the Turkey Point Emergency Core Cooling System (ECCS).to provide adequate cooling in case of a Loss of Coolant Accident (LOCA) when oper'ating the,plant with one idle loop.
On March 11, 1975 we submitted to you the ECCS analysis for. 3 loop operation at design power.
The, consequences'f a LOCA when operating this plant, which 'has no isolation valves', with 'one idle reactor coolant
.pump at a maximum of 60% of full power will not be as severe "as those of a LOCA occurring with 3 loop operation at full power.
Reasons.for this.become clear by considering the comparison of the various phases of the accident transient for three 'loop and two'oop operating conditions.-
l.
Blowdown:
In comparing three loop and two loop LOCA's 'the predominant factor influencing the blowdown transient is the effect of reduced core power required'uring two loop operation.
For any given break size, including the "limiting"break, the core mass flow,transient wi;11 remain essentially the same 'for the cases because the energy and driving forces in the reactor coolant system, i.e. pressuxe and temperature,,are similar.
The idle reactor coolant pump may cause a slight time shift in the "cox'e 'flow,'.chaxact'existics,; but the trends will x'emain the same."
Ther'efore, because 'of.the reduced, core powex,,'coolant quality in the'oxe during bl'owdown'ill be significantly lower for two. loop opeiation and,the clad and pellet temperatures will be 'lowex,at, the end of blowdown.
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~ HELPING BUILD FLORIDA
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Mr. Pexiard C, Rusche May, 19, 1975 2.
Refi,ll:
Since the.'blowdown hy'draulic transients are simil'ar and emergency. core cooling system.performance for the 'two cases is the
- same, lowe'r plenum refill and bott'om of core recovery will not be altered si'gnificantly.
3.
Reflood:
One important factor,that influences 'the "reflood transient ia,the containment, pressure.'heconservatively calculated ECCS,,containment pres'sure 'transient wi;ll be 'only slightly affected because
.the ECCS'ass, RCS, energy and'ate 'of explusion of.the pr'imary coolant to 'containment'i.'ll be about the 'same for the two cases'..
Anothe'r'actor in the 'reflood calculation that must be considexed is, again, core power'.
Sensitivity studies per'formed with;the Westinghouse.'Appendix K ECCS, evaluati'on model show.that decreasing.
core power'nd core 'heat release in the '.reflood calculation res'ult in a more effective 'core 'reflood transient with 'respect to core cooling.. The 'dec'xease 'in core '.powe'r for two'oop oper'ation will, therefoxe,'improve 'the '.xeflood transient.
Xn summary, since 'the 'core ',conditions at the 'en'd of blowdown will be "improved for,the two loop operation analysis and the '.refill/reflood transient ia, at worst, the same, for three 'loop and two.loop operation, a LOCA postulated to 'occur during two. loop opexati'on will result in lover calculated
.peak 'clad,t'emperatures'.'than for 100% powei.
For additional conservatism it is,proposed that.the 'present Technical Sp,ecifications be 'amended so that for two loop operation the 'permissible
'maximum peaki'ng factor, Fq, be reduced to 80% of the. value per'mitted by. Section 3.2.,6a of the Turkey Point Technical Specifiations.
This would lower the'eak linear heat. rate 'during two loop operation to 109 kw/gt, compared to the 13.62,kw/ft value used in the '3 loop ECCS analysis, According to sensitivity studies. des'cribed in WCAP-8340, thepeak clad t'emperature following a LOCA would be lower'ed another. 360oF as
'a result of this reduction in heat rate, bringing.the',',clad temperature
'wel'1 below 1840<F.
.Vexy truly yours,'obert E. Uhr g Vice Pres'ident REU:nch
c:
Mr.~
Noxman Mosel'ey'ack
'R'.
Newman, Esquire
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