ML17341A845

Forwards Addl Clarification Re 811210 Proposed License Amend Re Moderator Temp Coefficient,In Response to NRC 820125 Request

ML17341A845
Person / Time
Site:	Turkey Point
Issue date:	01/28/1982
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-82-35, NUDOCS 8202030124
Download: ML17341A845 (18)

Text

REGULATORY FORMATION DISTRIBUTION "SY M 0RIDS)

AOGESSION NBR;8202030124l DOC AGATE: 82/01/28 NOTARI'ZED0 NO FAOIL:50"250 Tur key 'Point iPlanti,'Uni't 3i Florida tPower.and Li'ght IC

,'50-251 Turkey 'Poi.nt Pl anti ',Uni;t 4c Florida IPower and Li'ght iC

'AUTH BYNAME AUTHOR AFF ILIATIOM UHRIG e'R ~ E ~

F l or i de IPower 5 '.,Light:Co,

<RECIP ~ NAHE RECIPIENT AFFIL'IATION EISENHUTE.D.G, Di.v.ision of Licensi.ng DOCKET 05000250 05000251

SUBJECT:

Forwards addi clarification re 811'210 iproposed license

.amend re moderator, temp coefficient<in Anesponse ito NRC 820 1'25 r e qu es t.

DISTRISOTION iCODEs AOOI0 iCORIES lRECEI YES:LTR J.

ENCL I SIIE:. -------.--

TITLE; General Distribution* for af ter Issuance of.Operating, License

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FLORIDAPOWER & LIGHT COMPANY January 28, 1982 L-82-35 Office of Nuclear Reactor Regulation Attention:

Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Eisenhut:

Re:

Turkey Point Unit 3 E

4 Docket Nos.

50-250 and 50-251 Proposed License Amendment Moderator Tem erature Coefficient

+9 gal@

gQ%~gb% ebb bb Cv On December 10, 1981 we sent you the subject propose amendment with an attached safety evaluation (FPL letter L-81-517).

Mr. Ron Frahm requested clarification concern-ing this submittal which was discussed by telephone on January 18, 1982.

Additional clarification was requested on January 25,

1982, a formal response to which is submit-ted with this letter.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 6 Technology REU/SKM:jc cc:

Mr. J.

P. O'Reilly, Region II Harold F. Reis, Esquire Attachment 8202030124 820128 W l PDR *DOCK 05000250 i -P.

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QSEMQ TITAN ~>P'Q~)IQ fan%~

The'bank ~fthdrawal fro:-. subcrftfcal fs a Condftfcn.'I evan and there ore, the

%BR roast reeafn above the lirA value durfng the transient.

En the Turkey Point FSAR, this )fr;.ft fs net by de~onstratfng

='hat th core average heat:lux relefns below the full po+r no. fnal vaTue.

This riethod of denanstratfng that the GNSR lfmft is net constftutcs the licensing basis.or.hfs accid nt for Turkey Point. ever thouah the D.'lBR.is not explfcf.lv canicula ed.

thre recent analvses (e,g.

5!iUPPS, Seabrook, Byron/858

~ dnooo and later plants) use a dffferent rethodolcgy whfch includes the calculation of.he,D'iBR.

co garison of resuits for these plants xfth those of FPSL using consistent input assmptions (such as reactfvi~~v insertion rate) can b

rode to further daooostrate that the

%BR lfvftfs met for FPKL.

This fs done by sho~ina that transient results obtained for FPKL are conservat've fifth r spec to equfvalent tesults frae: the recent analysfs.

The bank Qthdraial fro.- subcritfcal accfde.it fs analyzed for Turkey point using

'ET-6 (MCAP-I980), a standard neutron-point, kinetics core """de to calcuiate nuclear polar, and FAC~i

('ICECAP-7908) a th rral tranisien riedel

-.or the uel rod, to calculate the heat flux, fuel arid clad te-.;peratures.

These calculatfons are done for the average channel.

The conservatist'nherent fn the point kfnetfcs fidel fs su ffcfent to ensure that the 0!iBR resins above the lfr:ft value fn the hot spot.

as sfll be demonstrated fn this co~iarfson.

TlM. Seabrook.

SRUPPS, and Byron/Braidmod analyses use TMENYL'E (NCAP-7979}, a snolU-dfeensfonal neutron kinetics code instead of VET-6 to ca',cu'iate nucliear powr.

A l-9 axfal riedel fs used, thus re-ioving a large arount of conservatfsa.

caused by pofnt kfnetfcs. (Furth r conservatfsr-could be re~ved by 3-D calculattons, but this fs not necessary).

FACTRN fs. used to calcu'ate heat Aux, and the THiNC code (MCAP-7015) uses the FACTPJc4 calcu',ated heat flux to calculate

%BR.

The average channel heat flux fs used fn this calcu>ation because the peaked axfal and radfal pomr dis rfbutfons which could occur during this transient are incorporated into TAENC via separate input.

Conservatively'

Ol'

~

peaked dfstrfbvtfons are used to ensue tna= the resu;~s are.=-u-;:.o tfres in the planY. cycle.

For purposes of co~arfng the relative conservatfsr:

bet~zen

.he '..c r~d 's,

.he transient valu s of nuclear poser and heat flux shou'.d be vsed since 't fs these (especially the latter) ~hfch ~old vary due to red 1 changes as fnput into the NBR calculation.

Note that although the r odel differences ~fil also affect the fuel and clad te~era-ures, these changes do, not af ect the

%BR calcu)atfons since THINC does not use these values.

".:he te-.'"eratures can be used to co~are the rela+fve avaunt

o. subcoolfng in the core, which

=

Cs related to NiBR.

In Table ), the results

o. the Turkey Point Unit 4 Cycle 6 analysis

o. the bank withdrawal fror. svbcritfcal are co..~ared fifth those of S abrook, S!lUPPS.

and Byron/Brafbeood.

{8yron/Brafd~ood resu1ts are presented as fnforretfon only.

Mrect corgarfson with Turkey Paint is inapproprfate since th reactivity fnsertfon rate is dffferent.

fddftfonally, Byron/Brafd~ood hh op~ir'.fzed fuel

, ehfch has dffferent core physics para~ters.)

>ax'.rru-valves -. core average heat flux and fuel and clad te~era+ur s are presented for al'lan-.s.

hot spot fluxes are presented for the three p:ants using the l-D neu-'.rnrfcs riedel.

The,transfent values for Turkey Point and Seabrook are sr sen-.ed in Figures, 1

and 2, respectively.

Note that the hot spot vaiues are presented in the FSAR eely as upper calculated lfrrfts of flux and te;.oeratvre (see Figure' or Seabraok) and are not used in the PlBR ca'iculatfon.

Direct co~arfson fifth respect to tho two mdels, and hence the conservatfsr.. of the Turkey Point eedel fn eeetfn9 the DNBR lfmit, is based on the ca1culated values of nuclear pomr and average channel heat flux.

The conservatfsa inherent fnthe point kfnetfcs riedel is easily seen by co;parfng the values fn Table 1 and the transients in Ffgures 1 and 2.

For th same reactivity insertion rate of 75 per/sec, the raxfr."m nuclear pomr as calculated by NIT-6 fs approximately six tires the va;u calculated bv Tii'NKLE.

Th maxfsvn average heat f'lux is rare than brice the value ca'culated for S abrook

(,Rl Ys.339).

The predicted fuel and clad te".peratures are also higher fn the TVAey Point analysis than fn the other three calculations, indicatfng

0 s

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a conserva'.$ ve'3'ow KG~un 0

sub 3

4'nc.

Tnus h: Jr!'-'9

'palsos bounds the 1-9 analysis

~or he,average channel.

Tne Hn'.".u-.

l;HR's for aU three plants Presented rerein above the lirft values, for Seabi"ok, he

n4nimcv, DNSR is 7.59.

This is mll above th lirÃt valu of 1.30.

fn conclusion, the able and Agures sho~'ha+

he Point kinetics riedel is highly conservative s!nce a co~arab]e l-0 rode'nalysis o

the bank withdrawal frv.-.

subcrit$ cal analysis yields acceptable results. 4.e.,

0'iBP. ab ve the ".'vi va'Iue.

Tnarefore, it can be conclud d that the licensing basis o

Turkey Poin+

4s sufficient to'hm that th

~intr,m DNBR is greater han

%he 'fir.'alue of 1.3D.

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