ML17318A551

Tech Specs 3.2.2,3.2.1,3.2.6 & 4.2.6 for ECCS

ML17318A551
Person / Time
Site:	Cook
Issue date:	01/09/1980
From:	INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17318A550	List: ML17318A549 ML17318A551
References
RTR-NUREG-0630, RTR-NUREG-630 NUDOCS 8001140463
Download: ML17318A551 (18)

Text

{{#Wiki_filter:IMPACT OF DATA <<PRESENTED IN DRAFT NUREG-0630 ON DONALD C.COOK UNIT 2 LOCA ANALYSIS A. Base Case The most limiting break for Donald C. Cook Unit 2 is a double ended cold leg guillotine break with a discharge coefficient of 0.8. Using the February 1978 evaluation model, the results for this break are:. 1. Fq =202 2. Hot Rod Peak Cladding Temperature (PCT) at Burst Node = 1905.5oF, Elevation = 6.05 feet. 3. Hot Rod PCT at non-ruptured Node = 2171.2oF, Elevation = 7. 5 feet Clad Strain During Blowdown At 7.5 feet = 1.154 Maximum Clad Strain at 7.5 feet = 9.05% 4. Average Hot Assembly Rod Burst Elevation = 9.0 feet Hot Assembly Blockage Calculated = 20.4Ã B. Burst Node The maximum potential impact on the ruptured clad node is expressed in letter NS-TMA-2174 in terms of the change in the peaking factor limit b,F required to maintain a PCT of 2200 F and in terms of a change in PCT ( h,.PCT) at,.a constant Fn. This procedure eliminates extrapolating data over a wile range above 2200oF since the increase in metal water reaction at these elevated temperatures may make such extrapolations inaccurate.

Using NS-TMA-2174: a. +0.01 6 F corresponds to +150oF 4PCT at the burst node, b. NRC burst m)del could require 5 F of -0.015, c. Minimum estimated impact of using NRC strain model is Fq of -0.030. Therefore, maximum penalty for hot burst mode is 6 PCT1 (0 015 + 0 030) (150 F/0.01) = 675 F Margin to 2200 F = 2200 - Burst Node PCT 2200 1905.5 = 294.5 F = h PCT2 Therefore, F penalty at burst node (a FqB) (675 - 294.5) F x (-0.01/150 F) = - 0.025 C. Non-Burst Node The maximum temperature calculated for a non-burst location typically occurs above the core midplane during reflood. The potential impact in this area in using the NRC fuel rods models can be.estimated by examining two aspects of the analysis. The first aspect is the change in gap conductance resulting from differences in cladding strain. Note that clad strain along the fuel rod stops after rupture and use of a different burst model can change the calculated burst time. Three sets of a LOCA analysis were studied to establish an acceptable sensitivity to apply generically to this evaluation. The maximum PCT increase resulting from a change in strain in the hot rod is 20 F per percent decrease in strain at the maximum clad temperature location. Since the clad strain during the RCS blowdown is unaffected by the new NRC data, the maximum decrease in clad strain that must be considered in the difference between the "maximum clad strain" (MCS) and clad strain at the end of blowdown (BCS) which are listed above in the, base case discussion. Therefore, 6 PCT3 = (20 F/1%) '(MCS - BCS) (20 F/1%) (9 05% - 1 15%o) = 158 F The second aspect of the analysis that can increase PCT is the cal-culated flow blockage. Using the methods detailed in NS-TMA-2174, the following change in PCT is calculated. A PCT4 = (1.25 F/X) (504 Hot Assembly Blockage) + (2.36 F//) (75K - 50Ã) 1.25 (50 20.4) + 59 F $ PCT5 96 F =5 PCT4 + Q PCT3 = 158 + 96 = 254 F A, PCT6 2200 F - Actual PCT = 2200 - 2171.2 = 28.8 F The F reduction required to maintain the 2200 F limit using the above values in conjunction with the results of NS-TMA-2174 F(N - 0.23. D. Benefit From Im roved Anal tical Modellin The effect on LOCA analysis of using improved analytical techniques which are currently approved for use in LOCA analysis of plants utilizing upper head injection in the blowdown (SATAN Code) calculation has been quantified via,an analysis recently submitted to the NRC. Since the review of this analysis is not yet

complete, the NRC has established a credit that is acceptable for this interim period. This credit for Donald C.

Cook Unit 2, which is a four loop plant is Q F~ = + 0.20. E. M 1 1 11 1 Base Case (February '78 Model) 2.02 $ F~ penalty = max( ZLF~B,QF~N) = -0.23 Q F~ benefit = +0.20 1.99 Maximum Overall F~ = 1.99

ATTACHMENT B TO AEP'."NRC:00322B DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 DOCKET NO. 50-316 LICENSE NO. DPR-74

~hg I (Ch N 2 f AEP:N C:00297) Revisions to NLimitin'Condition'of'0'eration'CO '3;2;2 Fi ure 3.2-2 and Basis'Item'3/4 2.1 - Unit'No.' This change involves lowering the maximum allowable Fq (Z) limits. The maximum value is being reduced from 2.32 to 1.99. Until the 1.99 limit was established via the evaluation discussed in Attachment A of this letter, an administrative limit of 2.11 was employed in compliance with the NRC order which followed the d>hscovery of a 'logic inconsistency'n the metal-water reaction calculation of the Westinghouse ECCS Evaluation Models. The 2.11 administrative limit was established after a new Westinghouse ECCS analysis (using the October 1975 Model with the metal-water correction) was.performed. These analyses results were transmitted to the NRC on April 28, 1978. A reanalysis of Donald C. Cook 2 using the February 1978 Model resulted in a maximum Fq of 2.02. This base analysis was used to establish the new 1.99 limit..This change assures the continued protection of the public health and safety. ~CN ''N I 2 (Ch g N 4 f AEP'.NN:00297) 0'Revisions"to'L'CO'3;2;1:and:Fi ure'3;2-'1'-':Unit:No! 2 This change involves keeping the upper power limit for the'taking of action at 84/ Rated Thermal Power. The change requested in AEP:NRC:00297 was to raise the limit to 90% RTP. This technical basis for the change is the same as= that of Change No. 1 above. This change assures -the continued protection of the public health and'afety. ~00 'N': 0 (Ch g II 5 f A P:N 0:00297) 5 Revisions'to'L'CO:3;2 6:and:4!2;6'-:Unit'No.' This change involves keeping the APDMS turn-on point at 94% Rated Thermal Power. The change requested in AEP:NRC:00297 was to raise the turn-on point to"100/ RTP. This change is based on the revisions to LCO 3.2.1 and Figure,3.2-1 as discussed in Change No. 2 since"the APDMS turn-on point is defined as 10Ã above the upper limit of LCO 3.2.1. This change assures the continued protection of the public health and safety.

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~ ~ POWER Dl STR I BUT ION L IMITS HEAT FLUX HOT CHANNEL FACTOR-F" (Z) LIMITING CONDITIO.'l FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationships: F~(Z) < Q'.99) [K(Z)3 for P > 0.5 p F (Z) <<[(p,qg)] [Y.(Z)] for P <<0.5 THEPMAi POWER i and K(Z) is the function obtained from Figure 3.2-2 for a given core height location. APPLICABILITY: MODE 1 ACT!Oh: With F (Z) exceeding its limit: a. Comply with either o the following ACTIONS: 1. Reduce THERMAL POWER at least 1~~ for each 1;; F (Z) exceeds the limit within 15 minutes and similiarly reduce the Power Range Neutron Flux-High Trio Setpoints within the next 4 hours; POWER OPERA .ON may proceed for up to a total of ?2 hours; subsequenc POWER OPERATIOll may proceed provided the Overpower uT Trip Setpoints have been reduced at least 1.. for each 1" F~(Z) exceeds the limit. The Overpower aT Trip Setpoint reduc.ion shall be performed with the reactor in at least HOT STANDBY. 2. Reduce THERMAL POWER as necessary to meet the limits of Specification 3.2.6 using the APDMS with the latest incore map and updated R. b. Identify and correct the cause of the out of limit condiiton prior to increasing THERMAL POWER above the reduced limit re-quiredd by a, above; THERMAL POWER may then be increased provided F~(Z) is demonstrated through incore mapping to be within its limit. D. C. COOK - UNIT 2 3/4 2-5 I ~ <<<<<<

I 45 (' FIGURE K(Z}NORMALIZEDFQ(Z} ASUNCTIClN OF COt)E t/EIGI)T HEAT FLUX HOT, CHANNEL FACTOR NOPP~LIZ""0 OPER" TING ENYELOPE FOUR-LOOP OPERATION ~ Basis: F~(Z) x P ECCS limit of j.'fQ 1.0 ~"I"-:~:".I "~: t I ~ t: Z.:...I ".:.; i '::-:: <E'(} ~ G(}(}) j ":": (II.EV,O.SSS) t ~ I ~ } .8 } ~ ~ ~ ~ ~ ~ ~ ~ ' 'I ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I iM I I~ IE} iE l 1 ~ 4 I ~ ~ ~

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BASES The s"ecifica i"ns o his section provide assurance cf -ue'. 'nta"- rity d. ri,.c C~rditic. I {Normal Operation) and II (Inciden.s cf,'= r=-te Frequency) even.s by: (a) maintaining the calculated O'GR in.he cora at or a"cve design dur;ng normal operation and in short t rm '.ra.".S.en-.s, and (b) l'-it ng he.ission gas release, fuel pellet tempera.ure and cladd',. g;..e hanical "rcperties to witnin assure design cr'i-er ia. in addition, li;.;iting-the-oeak linear powe. density during Condi,c-a .'ven:s r"v..ces assuranc tha the initial conditions assumed =or -he LOCA analyses are "..e-ar. the ECCS accep.ance cri ter',a l iraqi t of 2200'; is not excee'ed. The def'.niticns of c rtain ho channel and peaking factors as use in these spec;f;cat;cns are as follows: Fq(Z) Hea= Flux.'-.'ot Channel

Factor, fs defired as the

."..ax:.-..u.".. loc:-; heat flux cn the surface of a fuel rod at core elevati".n Z. diivided by the averace fuel rcd heat flux, al 1cwing for man-u;acturing tol =rances on fue'1 pellets and rods. 3/4.2. 1 nuclear En hairy Rise Hot.Channel Fac.or, is deAn d as .he 'ratio of t.".e integral of linear pc" er along the rod wi:h th hiches in-.aerated power to the ave. ace rcd pcwer. Radial Peaking Fa"-.or, is defined as .he rat o c, peak power dens ' 0 avel age pcwer dens i ty ' the "Gr i" n plane a.t c".o eievaticn Z. FLUX OIFFER'.<CE ('FO) The limits on AXIAL FLUX OIFFEREi<CE assure hat the F~(Z, uper bound a,",v .ope o-, ~.qg times the normal i= d axial pe king ac:on is no excee"'e" durin" either normal operation or in the event of xenon redis-tribution f"liowing pcwe. changes. Tarcet, flux d',f=eren e is determined at equilibrium xeron conditions. The fully lenc-.h rc"'s aa.ay be posi:ioned wi.hin the core in acc"rcance with heir ros"ective irrserticn 1imits and should be inserted ne=r their nor;a'. -c~ :; n fc. =- e=-dy state cperation at hich power levels. The value of "'"

arce-flu" difierence obtained uncer these conc;tiors divided bv

-;.e,rac icn of RATED THER'".AL POX";."; is the targe" flux diffe. e..e a-RAT:-D ;H=R.'!AL POWER for the associated core ur.".u" con-ditic;,s. ar"et f.ux d;-.ferences -,or other THER,'iAL POWER ieve:s =.. e obtained bv.-..ul ticl".nc.the ?ATED THER.".AL POWER vaiue by -.he ac=roar'.ate a, fractional TH=K.'".AL PG'r'=.=. level. The periodic updating GT he flux diffe. nce value is necessary o reflect core burnup consic ra-.,-.ns. 0oCo CQQK Jl'll I a B 3/4 2-1 Ar,end-,. n No. 10

Although i";5 in.ended that the plant will be operated with the AX ~L Fl UX D F"""?:"liC."" within the~:5~ tal ge'and abou the target flux diff=rence, during rapid p'iant:.'-.'=,=.Y~L PC'~'-"R reducticns, control r..d mot'.on ui il cause tke %F0 -." dev-.ate outside of the target band a. re-du-ed T'."'=.".l"~L PG'n=R 1 evel s. This dev ia icn wi1 l Aot a=feet the xenon r "is . ibu-icn suff',ciently o ch Age the envelope of peaking,ac:ors >:hick i-..av be reached on a subseq'ent return to P~T""0 Ti =".='QL PCW~R (with the AFD ui "hin the target band) provided the tirie duration of the devi-ation i 5 1 lmlted ~ r'cc01 Ci Agl v, a 1 hour penal ty dev. ation 1 imit cumu-ia ive Cur Ac the previcus 2< hours is provided ol oper tion outside of the tar"et band bu w-thin the 1'.mits of Figure'.2-1 while a 7',-::-.=.i"~ PC'r'-R 1 vet5 be;ween 0" and FQ/ of RATED'IiERiQL poI;Ep P. ror IH..=';.L PC<'cR 1 evel 5 be uee!l 1 ~'nd 50lo oi K&I "0 IHh.."ARL ! v'r R, deviations o 0 ou 5-'de ~i the ta rect band are 1 ess 5 i Qnl i c:-At T le pena ty of 2 A'urs ac:uai t,.-.;e reflects this reduced significarce. Provisions fol moni or-t,".g the AFO on ari automat'c basis are derived f"ot. "'-e plan proc ss corn.ut r krough the AFD Honitor Alarm. Tne cc..."uter deter,ines he one minu-e average of each o-the OPt.RABL= ~ ~ 1 'C Jg excore d=-ec"or outp ts anc prov"es an a!arm...essace lr.edlately lf'he 0 0 .areas 2 of 4 or 2 0" 3 OP" ~wBL excoro channe! s are outsi de ~ ~ ~ ~ -:;e tar"e Land and the Tn""."".'QL P"'ri"-8 is greater -.',",an gqy, oi ~i=J in-.. A PCn' Our ng operation at T."'.:-."-..".-'.L PO'4"=3 1 eve! s be. ueen "G~ arid s'p t-and b 'een 1 ":~ and =Os RRl D l H . 'L . Q'n". tiie cc.. uter o 'uts aA 1 al ii m ssag when the penal y devla .OA ace umiul ates beyond tAQ 1 lmi "5 of 1 h"ur ard 2 hours, respectively. Fioure B 3/4 2-1 shows a ypical monthly target band. O.C. COOK - Vali 2 8 3/4 2-2

Cs \\

CMANGE NO. 2

3/4.2 POWER:,. STR IBJTION L IMITS f AXIAL FLUX DIFFERENCE (AFD) LIMITING COleDITIOte FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a +5. target band (flux difference units) about the target flux difference. I APPLICABILITY:.ai>ODE 1 AuO'll E 50'e RATED THERMAL POWER ACTION: a. With tho indicated AXIAL FLUX DIFFERENCE outside of the +5 ~ target bard about the target flux difference and with THERMAL POWER: Above 5')5 of RATED THERMAL PO!!ER, within 15 minutes: a) Either restore the indicated AFD to within the target band limits, or 2. b) Reduce THERMAL POWER to less than gpss of RATED THERMAL POWER. Between 50:. and f8/.of RATEO THERMAL PO!E'ER: a) POWER OPERATION may continue provided: 1) The indicated AFD has not been outside of the +5% target band for more than 1 hour penalty deviation cumulative during the previous 24

hours, and 2)

The indicated AFD is within the limits shown on Figure 3.2-1. Otherwise, reduce THERMAL POWER to less than 50., of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip Setpoints to < 55". of RATED THERMAL POWER within the next 4 hours. b) Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1. A total of 16 hours operation may be accumulated with the AFD out-side of the target band during this testing without penal ty deviation. E 3.1 .2 D. C. COOK - UNIT 2 . 3/4 2-1

ONER DISTR'BUT~9'! L',"~ S CTIOt(: (Continued) c) Surveillance testing of the APDMS may be performed pursuant to Specification 4.3.3.7.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1. A total (of 6 hours of operation may be accumulated with the AFD outside of the target band during this testing without ponalty deviation. b. THERMAL PO'<<ER shall not be increased aboie gpss, of RATED THERl1AL POMER unless the irdicated AFD is within the +5:> target band and ACTION 2.a) 1), above has been satisfied. c. THERMAL PO'<<ER shall rot be increased above 50'! of RATED TH RMAL POWER unless the indicated AFD has not been outside of the +5 target band for more than 1 hour penalty deviation cumulative during the previous 24 hours. SUiVlEILLAl(CE REnU'lR'EM:iTS 4.2.1.1 The indicated AXIAL FLUX DIFF"RECCE shall be determined to be within its limits during POWER OPERATIO,") above 15".l of RATED THERMAL POAER by: a. Monitoring the indicated AFD for each OPEPABLE excore channel: - 1. At least once per 7 days when the AFD Monitor Alarm is OPERABLF, and 2. At least once per hour for the first 24 hours after restoring the AFD Monitor Alarm to OPERABLE status. b. Monitoring and logging the indicated AXIAL FLUX DIFFERED'iCE for each OPERABLE excore channel at least once per hour for the first 24 hours and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERED!CE Monitor Alarm is inoperable. The logged values of the indicated AXIAL.FLUX DIFFEREHCE shall be assumed to exist during the interval preceding each logging. D. C. COOV, - Ur~rT 2 3/4 2-2.

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~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ I ~ I I ~ ~ ~ ~ ~ ~ f ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ IJJ ~ ~ ~ ~ ~ ~ A ~ ~ ~ ~ l - t 100 ...,~... ~ ~ ~ ~ I ~ ~ ~ t i ~ ~ ~ II ~ ~ 0 f r f ~ ~ ~ ~ ~ ) w ~ l f -UNACCEP t A-< "" '( Ig, yq) OPER 'C"' I '((~ ~p) U<iACCEPTABLE-- '== C? = RATIO'i 80 3=j. f I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I f ~ ~ ~ ~ I ~ ~ ~ r ~ ~ 60 ~ ~ ~ ~ ~ ~ I ~ ~ \\ ~ ~ ~ ~ ~ ~CCEPTA" L = ~ ~ I

OPERA

( IG;i-r ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ - ~ (a>a~3 40 ~ ~ ~ ~ f ~ ~ ~ ~ ~ g+ SO) j ~ ~ ~ ~ \\ ~ ~ ~ ~ ~ 20 !..-'I: ~ ~ ~ ~ r I ~ ~ ~ ~ I ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t I ~ J ~ ~I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 'C ~ ~ ~ ~ ~ -50 -40 -30 -20 "10 0 10 20 30 40 50 FLUX DIFFERENCE.QI) 'ro FIGURE 3.2-1 AXIALFLUX DIFt REiMC-LIMITSAS A FUi4CTION QF RATF0 THE Rh1 AL POiV E R O. C. COOK - UH? T 2 3/4 2-4

3 PO's'lER DISTRIBJTICls Lab. TS AXIAL PO'r'ER DISTRIBUTIO LIMITING CO.'iDITIO.'l FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following relationship: [F-{Z)]S = f~ 9~1'. r(z) (R.)(PL)(1 O3)(1 + -)(1 O7) Mhere: r J a. F.(Z) is the normalized axial power distribution from.himble jj at core el eva tion Z. b. C. PL is the fraction of RATED THER~'lAL POWER. K(Z) is the function obtained from Figure 3.2-2 for a given core heigt t locatior,; R., for thimble j, is determined rom at least n=6 in-core flux maps covering the full configuration of permissible rod patterns above 0+/ of RATED THERt1AL POWER in accordance with: n R- =-. ~ R- ~ n =1 Mhere: Peas 1 ij Max and [F . (Z)]< is the maximum value of the normalized ij Max axial distribution at elevation Z from thimble j in map i which had a measured peaking factor without uncertainties Deas. or densification allowance of v~. 0. C. COOK - UNIT 2 3/4 2-17

POWER DISTRIBUTION LIP!.TS LINITIN" CONDITIO.'( FOR OPERATION (Con inued) o is the standard deviation associated with thimble j, expressed as a fraction or percentage of R., and is derived from n flux maps J from the relationship below, or 0.02, (2:.) whichever is greater. n 1

2 1/2 [ 1,. 1(R. -.Ri ) ] R-The factor 1.07 is comprised of 1.02 and 1.05 to account 'or the axial power distribution instrumentation accuracy and the measure-ment uncertainty associated with F. using th!e movable detectol sys em respectively. The factor 1.03 is the eng neering uncertainty factor.'PPLICABILITY: NODE 1 above f'tf.'F RA ED THERIAL POWER=. ACTION: )C a. With a-F (Z) factor exceeding [F.(Z)]S by 4 percent, reduce J J THER!AL POWER one percent for every percent by which the F.(Z) factor exceeds its limit 'within 15 minutes and within the next two hours ei.her reduce the F,-(Z) fac or to within its limit or reduce THER,",AL POWEP. to qqy'. orless of RATED THER'>AL POWER. b. With a F.(Z) factor exceeding [F.(Z)]S by 4 percent, reduce J J S THEfNAL POWER to 9'j% or less of RATED THER'!Al POWER within 15 minutes. 0 The APQNS may be out of service when surveillance for determining power distribution maps is being performed. D. C. COOK - UNIT 2 3/4 2-18 c!

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