ML20244B604

Errata & Addenda Sheet 2 to LOCA Analysis for Edwin I Hatch Nuclear Plant 1

ML20244B604
Person / Time
Site:	Hatch
Issue date:	10/31/1981
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20032A846	List: ML20244B604
References
NEDO-24086-ERR, NEDO-24086-ERR-02, NEDO-24086-ERR-2, TAC-47092, NUDOCS 8111020467
Download: ML20244B604 (6)

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NUCLE An ENE MGY SV$lNISS GROVP e GENI A As GLLCTAlt COWAVY 1 saw soSE CAu708tMA 96125 -

j _- 1 G EN ER At $ ELECTRIC' l 1 APf'LICASLE 'TO: .

1 eu.i, car.o w o wroo-zto86 - IRRATA And ADDENDA-e 4 ll4-. '

.T.is m 77NED33_8 .

5HIET l

ygygx LOCA Analysis"for'Edwin 7__ ,,,_],.

uo ' _ - _ -

Hatch Nuclear Plant Unit 1 )

pyg October 1981 j

. .. s' p ' W Il! Caml##cccis h/ #sewyg ,

pukficetion et speejfjef peggy

' - ISSUE DATE December 1977 i

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• REFERENCES -

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-i:- fi t M - - (EECTSON. PAGC . ispan(ct:0**5 ANC A00fYeond)

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E'eplace with revised page .3-1/3-2.'

2. iPage 3-1/3-2 /

b 3. Pete'4.3 F.eplace with revised pag,e .4-3.

4. Page 4-11 Replace with revised par,e'4-11.

5. Page 4-12 Replace with' revised page' 4-12

6. Pago 4-13/4-14 Replace with revised pagel4-13/4-14.

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Tab'le 71 tie' M. .,

3-i i 3-1 Significant Input Parameters .to the Less-of-coolant' .' .j Accident. Analysis .3-1 'l

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Sumanary of.Resvits- , 4- 5 . -l lj '4-1~ ,

'4-27 - LOCA Analysts. Figure Sumiry .4-6

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4-3A - MAP G GR Versus. Average Planar Exposure MAPGGR Versus Average Planar Exposure t 4-8' <

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. MAPLHCR Versus' Average Planar Exposure

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. MAP GGR Versus Average Planar Exposure 4-10; .' 1

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. MAPLUGR Versus Average PlanarfExposure l4-11 4-3E'

'J 4-12 d 4-37 MAPLME Versus Average Planar Exposure.

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'S U '* . 3.- IKPt*T TO /M YSIS' l

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'A list of the significant' plant input parainers 'to the LOCA. analysis is.

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; tf. 1 presented in Table 13-1 ' 1 u,

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-- SIGNIFICANT INPL'I. PAR AMETERS 70 THE

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', . LOSS-OF-COOLANT Acc1 DEST. AKAI.YSIS

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I m Plant Parameters 1, ' '

' Core' Thermal Power. 2537 $ t, which corresponds to >

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11051'-of rated steam flow: . , ,

Vessel Steam Output: ' 10.50 x 10 lba/h;Lvhich corresponds.to .,e , . -

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L j 1031- of rated steam . flow - o L

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 ; Vessel Steam Dome Pressure 1055 paia q

Recirculation Line Break Area 1

, j p, h_ i .-M ;for Large Breaks - Discharge 2.4 ( +. /D'Ai1.9fty '(80% DW,)I .!

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Suction 4.0 ft (DBA) .

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'Wumber of Drilled Bundles All ,

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' Peak Technical .

, Initial- .i Specification Design Minimum Linear. Heat Axial Critical'

> Fuel Bundle Generation Race. Peaking Power 3 Fuel Type ' Geometry-_ (kV / f_t )_ __

Factor _ _ Ration IC Type 1 6 2..

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7 s -7 18.$ 1,5 1.2 d- A.  :

IC type 3 7 x 7, 18.5 1.5 1.2 .i

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f 1.4 1.2 .I

< i N,- C, 8D250 8x8 13.4 I

' I i0 8DR282 8x8 13.4 1.4 1.2

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8x8 13.4 1.4 1.2 it. ' 8D1233 i h 13 4 1.4 1.2 )

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+ ' F. 8DR183 8x8 <

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P8DRB284 8 y, 8 13.4 1.4 1.2 q h I C.

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' loaccountforthe2kuncertaintyinbundlepowerrequiredbyAppendizK,the t

RT cateulation'ds performed with an McPR of 1,18 (i.e.,1.2 divided by 1.02)

', . for a bundin with an initial ,MCPR of 1.20.

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' ' onelyt.e DBA. large breaks,l and s all breaks. Tor jet-pump reacters . these are defined-as followsi

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LAMB /$ CAT / SATE /DBA-RITLOOD/CKASTE. '. Break size:' <DBli.

%j s. DBA Methods.

' b. . Large' Break Methods _(LSM) . LAMB / S CAT / SAIE /non-DS A'. RL TLD0D / CHASTE.

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'1 Break sizes 1.0 ft 2 -A<JDBA.'

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SATE /non-DBA' RErLOOD. .. I Heat trafdf,er

c. ~ Staall Break Meth'ods (SSM).

-coefficients'. nucleate b'oiliac prior to core uncovery, 25 Btu /hr-ft *F.

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'4 . af terf racovery. ' core ' spray st.en' appropriate. - feak cladding 'te:nperature :

Break

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ad peik loen1' oxidation' are calculated in non-DBA-RETLOOD.'- '

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'4.5? RESULTS OF TRE C11ASTE ANA1.YSIS 1

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U ;3 hip' code is used, with'suitablefinputs free. the ethey~ codes, to calculate the '

j fuel claddi.og heatup rate, peak c1' aiding te .;:c;cture, feak 2cc4 cladding

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O oxidation,' .and core-wide netal-water reactict: f ee large Neaks. The detailed a l!:.

Ifuel mod =1 in CHASTE considers transient gap conductance, clad swelling and-

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rupture, and metal-water reaction. . The c.dirical core spray heat _ transfer and <

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~ . channel vetting correlations are built'into CHA5ft. which solves the transient. '

.' 'l heat transfer ~ equations f or the entire,1,0CA .trr.nitent at a single axial place - t in a mingle fuel assembly. , Iterativs applicatient,,of CH/iSTE detern.ine the.

I waximum permiso1ble planar power where required to satisfy the require:.ents o'i..

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10&R50.46 acceptance;criterf a. I d

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Ths' CESTE results presented are: -

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', Peak Cladding Temperature.versus time s Peak Cladding Temperature versus Break Area ll '

,; (f Peak Cladding Temperature and Peak 1.ocal 0xidaticu wrsos Planar i .e Average Exposure for the most 11*.niting break size pt 1

Maximus Average Flartar Heat Generation Rate (MAPEGR) versus Planar e -

4 Average T.xposure for the most . limiting break size J- l A owsmary of the analytical resulta is given in Table 4-1. Table 4-2 . lists the

figures-provided for this analysis. The MAPGGR values for each fuel type in the lis,tde 1 tore are presented in Tables 4-3A chrough 4-30, l.

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' (kV/ft)' ( F)',__.r Traction 1 .i (N.Wd

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it '. ..0.031- ,

200 ' .11,' $ 2162 , l u

.,-_r. 0,029:

11.5. 2151 t' f1000 ,

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.5000 11.9- '2187

.17.1 ' 2199 J0.034 i 2

{10000' x . , ,

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' 0.0'34 11.9' 2195 w.

20000 -

7 2138 0.028 25000 11.3-0.022 1 j 10.8' 2061 4, 30000 )

10.2 19B0 0.016: , i.-_

.35000 9.6- 1897 0.012 Q, .'40000; o a 1, Lf, e

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Toel Types: 8DR183 ,..

. Plants.-Hatch-1 s i ~

l ' Aversge Planar . , .

/0xidation- 1,' ,i Exposure MAPLER ' PCT' <

GeWd/c) (kV/ft) .('r) 4 traction' ,

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200 11.5' 2162 0.031 , .]

2156 'O.030- 1 1000 ;11,6 .j

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! 5000 2199. ,,

12.1- 2198 -

0.034 4 N- 10000 1

0. 034 -~

+, >i 15000 12.0 - 2200 n O.034 20000 12.0 2198 11.4- 2123 0.027 25000 i -0.17

' 30000 10.4 1985 35000' 9.B , 1911 0.013 )'$

40000 9.2 1836. 0.010 ' .)

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10.8 4 2000. 0.016 ..

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. ..i' 35000 10.4 1937 9.9 1867 .O.016 1 40000 9.4 1782 0.007 45000 t i

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ATTIONF_N1 2 1WC DO:XET M-321 , , '.O o

OPERATING LICENSE DDR-57 l .

EDWIN J. MT~H NJCLE/R PLANT. UNIT l'. .

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.-- PROPOSED C M N3ES TO TEC WICAL SPECIFICATIONS

+

Rg f Pursuant jto ' 10 CFR c170.12.;(c),' Georgia Power Company; hasL evaluated the i 4 l f attached proposed ' 'amendmnts ~ to ', Operating: License. :. DAR-57 f and has - .,.

l 4 = detemined that: i

.n I

H a) ' The. proposed amendtent' oats' not reaulre the evaluation. of a new,g y

~

Safety, Analysis. Report or rewrite .of, tne facility license;.

g A b) The proposed amen 3Tenti does not contain several, complex issues, ,

does 'not involve . ACRS review,; and' ~does : not require an , ,

'. environmental; inpact i ste t enent ; ,

^t- .

/ c):. The proposed amen 3nent: does not . involve a. complex issue, en.

l.  !

anvirorrental' issue or more than one safety issue;; a, d) The proposed amenonent consists ofJ two changes, ~ each involving, .

a single aafety issue namely; addition of @%KR operating, '

limits for. two new fuel types,, and an increase in the : Rod Block-mnitor setpoint ans K:PR-limit as a result of nem analyses.

e)

The proposed change is therefore two Class III smendents. , . -t 9

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' IRC' D3*XET 50-321 ' /,. '

OPERA 11NO LICEt6E DPR-57 7 d EDWIN I. :t%TCH N. CLEAR PLMT UNIT:li .

, ,g i I

?. PROPOSED CHANGE 5' TO TEC+1 CAL SPECIFICAT10NS ' o l

't + ~ The ' proposed change to Technical Specifications ( Appendix A to. Operating : ,41, .<.n , 4 s - ' License DPR-57) would be' incorporated at followst 1 1

~

g aa ~ Remove Page Insert Page: j m .j

, 3.2 '3.2-16~

. 3.11-1.. .3.11-1

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- Fjgure 3.11-l'.(Sheet 3) rigste 3.11-1 (Sheet 3) - f -

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F1 pre 3,11.A- 'rigare 3.11.4- ,

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?' :l 4.11 T3L iCF 3 11 TI7t 20?$

" _ Applicability

'. .l , Ape 12enJ11tv The Surveillance Requiretrents apply'-

'The Limit.ing Conditions for Operation tr the parase: era which nontter the. #

associated with the f uel t'ods apply to

,~

those parararers which :t.onitor the fuel rod operating condi: tons. {*

fuel rod operating conditions. i I Objec tive Obleetive l the objective of the 'initing Condi- The Objec t;ve of the Surveillance Requirement s is to specify the type s

' tiens f or, Operaticn is to assure the ar.d f requency of sua veG;ance to y

' perforsanct of the fuel rods. be Applied to'the fuel rods. l s

I. -Speci!fcatlens J

.' Verifications l

., f A. Averap e_ ?;anter linear Mer.t . Cenera- 0 AJ . Av eT a r e pl a qa r 1.f r.c ar Fe s t Ce nt r a.- 1 t f on Ra t e ( AP'JiGR) t tion Rate (AP 3 CR) .

A The APL.HCR for each type of fuel as .!

During power operation, the AP*.HCR' a function of average planar,.

~

.i for each. type of fue as a functien exposure;shal; be deterr.ined, daily 1 of average planar expesure shall. ,

not exceed the ';1r.itir.g va* ue isbo.m during reactor Spera: en at .r~ 2$1 toted thernal power.

-i, l .in .Tigure 3.114, r, beet s ", 2 and 3 '/

i= 11 'at any tine during operation it

.I is determined by r.ctr.a1 surveillance l '- .

.thet the limiting value for API.HCR .]

. I' *. ( .. 'is being-exceeded, action shall be .i initiated within'i$ einutes to re-store operation to within the pre-

}

scribed li=2ts. If the APGOR is not returned to v;thtn the pre-scribed liraits vithin two (2) hours, j

F j then reduce reactor power to less -)

' than 2$" of rated therr:a1 power with- j in the f. ext four (4L hours. If the  !

. limiting conditten for operation is restored prior to expiration of the specified time interval, then further

' I progression to '.ess than 25; of rated 3

thermal power is not required. )

1 t

h Linetr Heat Generation Rate (LH0y ,

3. 't.inear Neat Generatiem Rata (GGRJ J

)

During power operation, the LHOR as The LHCR as f unction of core

,,~ ' a function of core heighc shall not height shall be checked daily dur- '

l ing reactor operation at 1 2$5l l enceed'the limiting value shown in rated there.a1 pover.

~

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Tigure 3.11-2 f or . 7 x' 7 f uel or the  !

f limiting value.cf 13.4 kw/ft for 8 x 8/ )

j 8 x SR fuel. If at any time durir.g l operation it is deternined by norr.a1 l; surveillance thJt the liniting value f or LHCR is' being exceeded, action shall f

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[' ' f\ be ' initiated withio 15 nihutes to j

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i restore operation in within

>! the prescribed limits. If the )'

L Amendment No. y, (6 FI, #f, 69 L 11- 1

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l.i Director of hbclet,I Reactor Regplation ,

- U. S. Mr. lear Reqplatory Commission Wasitinf.on, D, C. 2DM3 <

l b

l tRC DOCKET 50-321 OPERATING LICuiSE OP457 f

i EDWIN 1. HATCH N ELEAR P M UNIT 1 REQUEST F09 CHAN3E5 TO TEC+lICAL SPECIFICATI0t@

l i  !

Cetlemem f

l Pursuant to 10 CFR 50,90, Georgia Power Coepany hereby requests two j ,

changes to the Technical Specifications (Appendix A to Operating License 1

DF4 57).

The first proposed chang adds two fuel types to Specification 3.11. A, which sets M4PLHQR operating limits. The justification for these two additional HAPLKR curves .is provided in enclosure 1, Errata and Addenda Sheet for NEDO-24006, LOCA A% lysis for Edwin I. Hatch H> clear Plant thit l*

ditch we also sutxnit at this time. We have evaluated the results given in this (pdate to the Hatch 1 ECCS document and believe these HV'LHGR limits to j be conservative for operation of these fuel types in Hatch 1.

Tin secured proposed change increases the Rod Block ntnitor setpoint to The KFR.

107E limit and increases ircrease the KPR la based limit for Electric's on General all fuel typ(es CE)to new 1.29. generic md

' withdrawal error (RWE) analysis procedure as sitaitted from E to the IRC by letter of May 18, 1981.

The new method' for HWE analysis sets the transient change in critical power ratio ( CPR) for the potential worst rod withdrowal error etpal to the 95/95 statistical value of limiting CPR's from 40 arAlyses with the previous nethod. The new nethod provides CPR/1CPR es a function of Ibd Block Monitor (ROM) setpoint. The CPR/ICPR can bei algebraically manipulated to provide the MCPR operating limits necessary to maintain the MCfR above the safety limit in the event of rod withdrawal error. An advantage of the new wcthod is that the operating limits are independent of the fbel cycle, which will elitninate the uncertainty of future RWE analysis results and will facilitate 10 CFR $0.59 reload submittals. Tre 95/95 value of maxinum linear heat generation rate (kW/Ft) was shown to be consistently I

less than the current transient limits (1% plastic strain), and therefore, will not be reported onder the new procedJres.

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, Director of ttselaar. Reactor aegulation

• U.'5. tesclear Gegulatory Commission a

s l;

• 'theshington,;D. C.1 20535> ,

j # 1( .Octaber.27,'1981 , .> .j r'W ,'

Page Two-3-

4 ' ,,.

'1 y

i i JJ'

. ? We believe Ithat; the Generic KPit limit ' of 1.29, conservatively bounds '

> J > that tAich would. be obtained from the rod' withdrawal: error analysis of thei ,

Hutch licore, c , ,

.. . , s.. .

i

'F

. The 1.29 McHt- litnit nis based on the' assumption that- rod withdrawal' erior1, i

.will be the limiting event when GE. completes its transient' analysis.. In the':

1

'g [ " ,

?i ,

o - unlikely event that another transient As determined to be sore, limiting','new '

Technical Specification changes,will be sutnitted.- '. .

.e i!F ' The ' proposed ' changes . to the Technical : Specifications tevise i certain < -

• operatinD limits ' based on analysis using General Electric Compwiy . standard:

sa . methodology and. therefore' maintain exist.ing' margins of safety. . Beesuss' .

Df margins of sefety = are ciaintaloed and: ns . change in' operating modes sis.  !

dL %, . proposed,7 4 there e is H no ' increase in. ' the l probability . or. consequences of-w - " < accidents; cr malfunctions of letpipment . hnportant. - to o safety . previously ' .

y amlyzed, nor is ' the 'possibl31ty createc for a new. eccident 'or malfunction ; y' '

inot previously considered.' 1The: Plant - Review Board ; has'. therefore , reviewed  :

1! and; approved. thel proposedc chaq0es and has' ? concluded: that they . do not , j

,' , M, constitute anlunreviewed safety ' question. ' ,

u heOhave !detertained this rehuest to :be 'two Classi III' amen $aents. . < ,

,*. Ehclosure .2 iconsists- of a

• detertnination of amendment class, = Enclosure 4 '

- contains ! instructions for : incorporation of tha proposed changes 'and copies a of effected pages,t '

. i; Ahls request Lis being stbunitted in support of the Unit 1~.outoge to - 1 I

) '.

a..

letter.replaceLleaking We. therefore. request feel assentnics your expediticosas discussed review 'andinapproval our

October- of the' 7j 1981,

,4 d.: pruposed changes'to the Unit 1 Technical Specifications.

4 .p 3" ' W.JA. Widnar states that he is Vloe President of Georgia Power Conpany and ,  ;

=is authorized to execute this oath on behalf of Georgia Power Company, a:td I

that to the best of his knowledge and belief the facts $et forth in this.  !

x. letter are true.

b.

' < (10RGIA POWER COWANY

>h

, t-I By: YI k.).[ A. Widner gp i

~l

M t

> rn and subscribed before ne this 27th day of Octrber,1981.

\' AA_a '

D My . e WL

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, __ ;. , ' ~ 'teta'ry Public u

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