ML17339A638

Forwards Attachment 1 to Submitting Info Re Potential Effect of New Fuel Clad Research Data on ECCS Analysis.Page Omitted from Original Submittal

ML17339A638
Person / Time
Site:	Turkey Point
Issue date:	02/28/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-80-64, NUDOCS 8003040494
Download: ML17339A638 (8)

Text

REGULATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR;8003040494

,DOC ~ DATE: 80/02/28 NOTARIZED:

NO FACIL!50

-50 urkey Point Plant< Unit 3i Florida Power and Light C

5'0 251 urkey Point Plantp Unit 4p Florida Power and Light C

4 U

~ N'A'M AUTHOR AFFILIATION UHR sR ~ Ko Flo~ida Power 8 Light Co ~

RKC IP ~ NAMF RECIPIENT AFFILIATION KISKNHUT~O~ G ~

Division of Operating Reactors

SUBJECT:

Forwards Attachment 1 to 800123 1 tr submitting info-r e potential effect of new fuel clad research data on ECCS analysis

~ Page omitted from or iginal submittal

~

DOCKET ¹ 05000250 05000251 DISTRIBUTION COOK!

A001S COPIES RECEIVED:LTR g

ENCL*

~

SIZE!

TITLE: General Distribution for after Issuance of Oper ating Lic NOTES:

RECIPIKNT 10 CODE/NAME" ACTION; 05 BC DgB INTERNAL: )0 REG FILE

~2.-

17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS OELO EXTERNAL: 03 LPDR 23 ACRS COPIES LTTR ENCL 7

7 1

1 2

2 1

1 1

1 1

0 1 '.1 16 16 RECIPIENT ID CODE/NAME 02 NRC POR 15 CORE PERF BR 18 REAC SFTY BR 20 EEB KPB DOR STS GROUP LEAOR 04 NSIC COPIES LTTR ENCL NAg

)ggg TOTAL NUMBER OF COPIES REQUIRED!

LTTR 38 ENCL 37 I

O. BOX 529100, MIAMI,FL 33152

>lr, FLORIOA POWER 4 LIGHT COMPANY February 28, 1980 L-80-64 Office of Nuclear Reactor Regulation Attention:

Hr. Darrell G. Eisenhut Acting Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Hr. Eisenhut:

Re:

Turkey Point Units 3 & 4 Docket Nos.

50-250

& 50-251 On January 23, 1980 (L-80-34), Florida Power 8 Light Company submitted information concerning the potential effect of new fuel clad research data on th'e ECCS analysis for Turkey Point Units.3 and 4.

A page was

.omitted from Attachment 1 to that letter.

Attachment 1 is forwarded in its'ntirety with this letter. 'e apologize for any inconvenience this oversight may have caused you.

Very truly yours, Pa%~

Robert E. Uhrig Vice President Advanced Systems

& Technology REU/GDW/ah cc:

J.

P. O'Reilly, Region II Harold F. Reis, Esquire

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but a si neous change in FQ &1ch cau-he PCT to remain'n the n ig.

orhood of 2200.oF justifies u~of this evalua-tion procedure.

- From HS-IN-2174:

For the Burst Bode of the clad:

0.01 hFq ~ 4'50 F BURST N)OE hPCT Use of the HRC burst redel could require an Fg reduction of 0.015 The v2xirn~ estinated impact of using the HRC strain model is a required Fg reduction of 0.03.

Therefore, the maxim~a penalty for.the Hot Rod burst node is:

hPCT1

{.015 +.03) {150oF/.01)

~ 675oF Margin to the 2200oF limit is:

bPCTZ 2200.oF - PCS

"-~<F The Fg reduction required to maintain the 22MoF clad tempera-ture limit is:

~Fq' (a cT - ~cT ) (~o~, ~

)

8 1

2 H00F

(~l-~> (jm) 1 i

C h",,

~

. ~'ion~

(but not less than zero).

~a NOH-BURST HOQE Tee max$ mua teryerature calculatod for a non-burst section of clad typica)ly occurs at an eleva'ion above the core mid-plane during the core reflood phase of the LOCA transient.

Tne poten--

tial impa t. on that maxirL;ca clad 4eryerature of using the ]BC'.=:

.--'";,,-'=;.,-.'. '=:.

fuel rod models can be estimated by examining t>~o asp cts of the".:""."::: '."";.'-':.,

analyses.

The first aspect is the change in pellet-clad gap conductance resulting from a difference in clad strain at &e. ',

non-burst maximm clad temperature node ~levat'.on.

tfote that clad strain all along the fuel red stops aft r clad burst occurs:.:--'.-:::.-:.:.'.

and use 'of a different clad burst model can change the time ae '-;=".-'::-'.:,;,"..:.

A<ich hearst is calculated.

Three sets of LGCA analysis results"';,.".~":::~'>.,:;=,:.-'. '"

mre studied to establish an acceptable sensitivity to apply" generically in this esaluation. 'he possible PCT increase resulting from a change in strain {in the ifot Rod) is +20.oF:.--'..':=i-.".;.;:.-:.

per percen decrease in strain at the maxia:um clad tmperaturi':--':-'. ".-::.'

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locations.

Sfnce the clad strafn c 1

inc uaed u fng th qa p

the accfdent fs nof: cha qM by r

ue

~o mode>s, the oexfmcw decrease fn clad strafn that ())est te covsiAred here fs the dfA'eren the "max>mum el% strw'n" and the "clad st n

an e

c zd s rafn d ~<rg

... 'herefore:

APcT~

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,3 (HAx sTRALN - BLOMVQNl sTRAIH) 2Q

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~c(

oq

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I n Increase PCT fs the'est valve of blockage

percent, the nroxf)))um

.that the current leva)

'ye)

cate@

by the 1',C blimp,age eodel.'s 75 PCT iocreass can be est.ieate4 by assU4(n9 of blockage fn the analysis (fndfcated.ob percent ezcf then agp/yfog en oppropl fate:

show fn NG-7M-PPC.

l The e fore

~PCTq. 1.25oF (SS -.)FRVVr Cuffed

= < 2.3P'F (75-60}

~ 1.2~ (50' 2.8,.t.).

< 2.N 0

~:.:.1'tOCXAM}

(?S-So} '

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ester.thon f.,t3"

~,>9>!';"'.i'::. ",'

PCT Increase

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0P clgld'e@+'.'

~)' '('~'."IPjr.'

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I,f POTE oeei.r>> rheo Ue co."e

@@flood rat'e'fs y.

)noh per seciind bPCTq

~ 0.

'Ne total poten~<fal far the ace-horst r~octe L> t,hen.

Marplot to-the 22'>F l.fait h.

6K' 2200oF - KTg

=

.>>'8.~~

The. Fg seduction required to vaunt,a4 this 2200 peretuve. l fa:A. fs. (,free HS-'PN-23?4}

6P+

(6PCT6 - 6PCT6)

('~)

l0"F hPCT I

hFgq

~

C~@

but cat less; thaA zero;.

'<he paak<ng factor reduction reouirect to tra3nta$ n the 2200 'F Had temperature 1)mit is therefore the yreater of dFO> ond8'gli, '

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g y

6 FgPPHAl yg

+

0 e

h,'

~

~gag W

5 4

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.lb'edi'(DQ fact%

1 )ftft dd fusb.ant regular

, opeY'atfce 'fo)'th55 )ntt r"sm periNt

$ s date

..A,Eg c're@'t Men(U(cd in se~ticn (8) above calcu)atcd in section (A) above (but not 9

e

~

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ed tv"3vst$fy p3.ant'.

amer'ed a

the.ppvopr<ate" w'nus. the&,FQ veeeee ttiee zeal>'I'.'"'~~

Fg ANUS'tHEKI ~ ~0.

e

- 'o,oV

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The effect on LKA a~alys.hs results of us)n9 imp~oved analytical and model)ng techniques (Mh<ch are cvrzently approved for"use 3n the.

lJpper hedd lndwthv plan".LOCA are>uses) ln the reactor coolant system b'lo~dum calculation (SATRAP ccmpv4ir code) has br.en qvont3" fied via an analys]s i~h<ch has recently been sulmitfed to the HRC for rev>ee.

Re:cgn(r$ ny that veviw o. that anal'.fs

)s not yet complete and that th bencf)ts assoc1ated vs.an frcrexsc:

<n the LOCA pedJ:>ng factor Ihit of 0,)2, 0,>S end 0.20 respectively, e

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