ML20033G851

Proposed Tech Specs Adding Definition & Renumbering Spec 1.8 Re Core Operating Limits Rept & Deleting cycle-specific Parameter Limits

ML20033G851
Person / Time
Site:	Fermi
Issue date:	03/26/1990
From:	DETROIT EDISON CO.
To:
Shared Package
ML20033G850	List: ML20033G851 ML20033G869 NRC-89-0299, Application for Amend to License NPF-43,revising Tech Specs to Eliminate cycle-specific Parameter Limits & Describing Core Operating Limits Rept Which Will Contain Limits,Per Generic Ltr 88-16.Core Operating Limits Rept Encl
References
NUDOCS 9004120212
Download: ML20033G851 (54)

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SUMMARY

OF 79t0POSEO TECHNICAL SPECIFICATXON/ BASES CHANGES

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O FERMI 2 TECHNICAL SPECIFICATION / BASES CHANGES Specification No./

Revised Tables / Figure Specification Title Description of Change Page Spec 1.8 (Definition)

CORE OPERATING LIMITS Add definition and renumber 1.2 to (add to Index)

REPORT the remaining definitions.

1.8, (1),

(ii)

Spec 3/4.2.1 AVERAGE PLANAR LINEAR Change reference to cycle-3/4 2-1 HEAT GENERATION RATE specific Figures 3.2.1-1 through 3.2.1-4 in LCO to the Com.

Change terminology

" bundle type" to " fuel type" for consistency within the specification.

Figure 3.2.1-1 MAPLHGR VERSUS AVERAGE Delete cycle-specific bundle 3/4 2-2 (delete in Index)

PLANAR EXPOSURE (FUEL MAPLHGR curve and relocate (xxi)

TYPE 8CR183) in the COLR.

Exposure units changed from MWD /t to GWD/ST upon relocation to the COIR.

Figure 3.2.1-2 MAPLHGR VERSUS AVERAGE Delete cycle-specific bundle 3/4 2-3 (delete in Index)

PLANAR EXPOSURE (FTJEL MAPMGR curve and relocate (xxi)

TYPE 8CR233) in the COLR.

Exposure units changed from MWD /t to GWD/ST upon relocation to the CO M.

Figure 3.2.1-3 MAPLHGR VERSUS AVERAGE Delete cycle-specific bundle 3/4 2-4 (delete in Index)

PLANAR EXPOSURE (FUEL MAPLHGR curve and relocate (xxi)

TYPE BC318D) in the COLR.

Exposure units changed from MWD /t to GWD/ST upon relocation to the CO M.

ex FERMI 2 TECHNICAL SPECIFICATION / BASES CHANGES Revised Specification No./

Tables / Figure Specification Title Description of Change Page Figure 3.2.1-4 MAPLHGR VERSUS AVERAGE Delete cycle-specific bundle 3/4 2-4a (delete in Index)

PLANAR EXPOSURE (FUEL MAPIJiGR curve and relocate

{xxi)

TYPE BC318E) in the COLR.

Exposure units changed from MWD /t to GWD/ST upon relocation to the COLR.

Spec 3/4.2.3 MINIMUM CRITICAL POWER Delete the scram time 3/4 2-6 RATIO equations and relocate 3/4 2-6a in the COLR.

Rephrase the 3/4 2-7 ACTION statement to be non-cycle specific and consistent with the COLR.

Change the reference to the MCPR figures in the ACTION statement to the COLR.

Rephrase Surveillance Requirement 4.2.3.1 and 4.2.3.2 to be non-cycle specific and consistent with the COLR.

Figure 3.2.3-1, 1A, EXPOSURE DEPENDENT Delete cycle-specific 3/4 2-8 and 1B MINIMUM CRITICAL POWER MCPR versus Tau curves thru (delete in Index)

RATIO (MCPR) VERSUS TAU at rated flow and relocate 3/4 2-8b AT RATED FIDW in the COLR.

Figures in the (xxi)

COLR replace the term

" operational mede" to

" rod pattern" for clarity.

1

FERMI 2 TECHNICAL SPECIFICATION / BASES CHANGES Revised Specification No./

Tables / Figure Specification Title Description of Change Page Figure 3.2.3-2 FLOW CORRECTION (K )

Delete the cycle-specific 3/4 2-9 g

(delete in Index)

FACTOR K curve and relocate in (xxi) 7 the COLR.

Add equations for K in the COLR.

g Spec 3/4.2.4 LINEAR HEAT GENERATION Delete the cycle-specific 3/4 2-10 RATE IJIGR values and relocate the limiting LHGR values in the COLR.

Rephrase LCO and Surveillance Requirements for clarity and to correct grammatical errors.

Spec 6.9.3 CORE OPERATING LIMITS Add adminstrative controls 6-21 (add in Index)

REPORT for report preparation and (xx) submittal in accordance with NRC Generic Letter 88-16 guidance.

Bases 3/4.2.1 AVERAGE PLANAR LINEAR Change the cycle-specific B 3/4 2-1 HEAT GENERATION RATE references to the ALPHGR figures which have been relocated in the COLR.

Correct grammatical errors.

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o-FERMI 2 TECHNICAL SPECIFICATION / BASES CHANGES Revised Specification No./

Tables / Figure Specification Title Description of Change Page Bases Table B 3.2.1-1 SIGNIFICANT INPUT Delete entire table. Table B 3/4 2-3 (delete in Index)

PARAMETERS TO THE provides cycle-specific (xxv)

LOSS-OF-COOIANT information and is no longer ACCIDENT ANALYSIS referenced in the Bases.

Bases 3/4.2.3 MINIMUM CRITICAL Delete the explanation B 3/4 2-4 POWER RATIO of the cycle dependent thru MCPR curves.

Change B 3/4 2-5 reference to figures to reference to the COLR.

Change "MCPR" to *MCPR limit" for clarity.

Change

" thermal flow" to " core flow" to use correct terminology.

Bases 3/4.2.4 LINEAR HEAT GENERATION Expand definition of LHGR.

B 3/4 2-5 RATE Include reference to COIJt.

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ATTACHMENT 3 TEC)!NICAL SPECIFICATION AND BASES CHANGES

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6 Insert A CORE OPERATING LIMITS REPORT 1.8 The CORE OPERATING ~ LIMITS REPORT (COLR) -is a plant specific document that provides selected core operating limits for the current reload cycle.

These. cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.3.

Plant operation within these core operating limits is addressed in individual specifications.

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femmer_mmmy f,

p,,# D E c"hII"e" M "U E De'm'T Iffa'sb TeIE,fI' IDWTEFIS LEAMAE shall be:

i late eeliettien systems eush as pump sett er volse pesking I

filh a.

, that to, septered and een&seted to e oisp or cellesttag tenk, or Lestege $ste the sentalement etneophem fue seuroes that am 4eth 6.

specifiselly loseted and hasun either met to tolerfere with the re-tien of the leskape deteetten systems or met to he PERASE Y

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&8 ARA $t.

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{$0LAT10N SYSTM RtaPOME TIE

,)m8B The 191N Afl# SYSTM Elfell5E TDE shall be that ttee 'leterval fun when the een"tered parameter enesees its isoletten estuotten setpoint et the red posittens.

l'9 channel eenser until the toelation valves trevel to their I

Ylees shall include tiesel generator startise and ng solars where app 11seblo. The peepense ties any he tesoured esy sortes of pequential, everlapping er total steps such that the in toepense time f

to semured.

LDif71M IRNTEL eB pAfftp Jptf A LIMITINB CONTADL 000 PATTEM shall be a potten uhte t

e l'l0 value for APUSR, USA, or ICPA.

t plEAR BEAT EMRAT10N Raft W LIIEAR lEAT ENERAflu Raft (USR) shall be the host seneretten per unit length of fuel red. It is the fatogral of the heat flun over the heat

,, I R transfer em meestated wiu me unit sangu.

plRICSYSTMFWCT10nALftIT Jdt A LOGIC SYSTM FistTIONAL ftST shall be a test of all tests esepenents unita, sette state leste elements, r

/.h e.e., all m1ars and sentacta, all tet T

1 estudins tEs actuated tc. of a legle strovit free senser devic,e, te verify GPERABILITY. The LOSIC PWCT10NAL ftST any he I

4 performed asy series of esquential, everlapping er total systen steps l4 such that entire logic system is tested.

IlhKDRM FRACTION OF LDEITIM POWER DEN 5ffY i

The IthXDEM FRACTION OF LDt!TEIS POWER 00t$ffY (IFLp0) shall be the Afghest

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value of the FLPO, which estats in the core,

%fGER($10FTHEPISLIC

$ SEftt4($) 0F TW PLSLIC shall include all persons who are met sesgattenelly l

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associated with the plant. This category eats met lastede esp 1syees of Also excluese from mis catetery

(* h the utt11ty, its contracters or venders.ero persons uhe enter the site l

i This category does incluso persons who use portfens of the s l

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4pti CRIT 90E 90ER 88T30 (IEpt) she11 he the eselleet OR ehleh g, 4 es 8ta a to spee.

to

' tee' dest es.ai,esqJr and 1"" lie.d te veduce

' 15AIIWff 18i vedPese*ttee e

off of vee ntee me m ui tee 1 5 I'tott,,% a a b w 1 3 *..

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grainsesumppaumann nem The OrtstTt sole Canaation swant t00can emoti coauta the estront I

l'E eseto Ml and persettees esed in the seheetation of offette doses eethode esettee and liquid effisents. $n the estestation of geoeous and it d off sent monitorino steenftelp ee teta,and in the esadat of the vedtele0 sal eartv6amental sont ne progres.

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GPit&RLt ? GPERABILITY train, esaponent er dettee she11 be OPERABLE er have l

%s06Aebtessubeystes,is le of performing its speciftad funetton(s)

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!LITYwhenit l'Jb and when 41) assessary at t instegeentation, sentrets, clostrical power,esalt er seal water, lubrication er other aust11avy equipment to perfees to funeston(s) ystes subsystas, trein. component er.devicee that see god for the s eupportfunetton(s).

OPtMTJORL 1D21T1011 10NDIIIM s,

l.a. COSIT10N shall be say one tesissive asf5 An CPERATICIEL COSITION,h pesItton and evetege veneter ecolant ecebinetton of sede swita l'A7 tamperetsee as specified in Table 1.2.

Bffftlti_11518 bd7 PHYSIC 818878 shall be these testa perfossed to speeste the fondamental i

emelear charseteristles of the resetor sees and related instrumentation I

l+38 and (1) esserited in Chapter 14 of the r$AR, (t) authottaed ender the provisions of 30 CFR 80.59, er (3) otherwtoe approved by, the Ceanission.

PRE 180RE RuiLBEARY LIARARE 298 PRESSURE 0001EARY LEARADE ehall be les tewough a menteolable favit l

, pipe wall, or eesse) well.

g,gy in a toaster cantant systes seaponent ptDERY CONTAll8ENT IWftRRITY

&ct9 ptDERY CONTAtleeff INTIBRITY aball estat when:

l.3e a.

All primary sentatement penetrations required ta he elesed during accident conditions are either:

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Capeble of being closed by en SPERABLE'priesey sentainment essaastic toelation systas, or

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or EtE:'22: ment::Tr.*I" - *"*" " '"

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suunnem amat.etatem p The P00Ctl8 Il0NftDL 90004M (PCP) shall sentein the siens to assure

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f 3l yi.et the 80Lut!FICATIM of wet tetteettive use a vos ts le a utste fers D

propertces thet meet me requipements of CFR Sh and of 1er level tediesttive utste di I sites.

PCP shall W ify j

as parameters inf1senet DIFICAT8 W such es out content, sentent, se11ds gentent eofseltsiflegtten.

to unste l

accesse additives Ier each type of antist and the utstellDe l

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greeptable sentittens for this scentified for uns teopfen 1e and feil seele

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j testine er e gertense.

ehe11 eise en ifteetion of genditlens that must be settsfled, tened on fv1 soste testi to assure t

onet eewetering of toed posins, peseted resins and ft1ter e a wH1 i

d etthetimeeldispose1,wt the fesult in op1gnes of free ester,lorlovel pediasettve easte steposal Itaits of le CFR Port $1 and of sites.

fimt2.Mlls aset MA0t er 9428!I8 is the sentrol s from l

t.n..en.nas.ent to est.iein tes (. led pros.ess of dische ress. h.

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gas is seg,uised to,sendi u en, nh..es.orthat,e,i,es,e.enteit.e er e ee e mun purify the eenflessent.

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G22 ttTED TItst4L pgWtt she11 h.e a tetel veester more heet transfer vote to l

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the teatter emelant of att Ittf.

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petemplet emesses N te(p selge et tLe ebennel eenser l' N eden the sent tien of the seres p11st estes solene es. De line entti by a v series of escuestial such 1

esy~ t the entire peepense ties is esasured., seerlapp as or tela the l

gg he ey ef these senditions specif$e6 le Section l

BIBbrY eheii.e. e.ee e, eenmi,ed.ei.e..serted as e i

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frettien of the total e of senteel ved estehes. All rods fv11y inserted I')b is sewivalent to 10 5 M D ITY.

SECDWARY CDMA1MWT IM8117Y l

W 8800GhtY 00 MAINE INfttt!TY ahe11 esist eden:

Ai1 secondary containment penettettens poesired to be sleseif during

" (.37 a.

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ettident tenditions are either:

slesed by on 9PitAtti secondary sentainment Sepableofbeigstensystem,or 1.#

evtomatic isel 3.

Closed by at least one annual selve, bited flenm, or l

sition estopt as provided in ab e 3.6.b8 in'its eleted1 of 8pe,sifoset deactivated evtomatic r set

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All setendary senteinsent hatches and blouset panels are s)esed and sealed.

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f The standby gas treatment systen is in esepliance with the c.

requirements of Speciftsation 3.6.8.3.

E d.

At least one deer in each attess to the secondary sentainment is 81esed (except as noted in iten g below).

The seeling mechaniss assetieted with eeth secondary containment 1

e.

penetration, e.g., welds, bellows er 9 rings, is OPE 448Lt..

f.

The eressure within the setendary sentainment is less than er equal I

to the value required by Specif tsation 4.6.6.1.a.

Seth ra11 reed bay attess dears are OPERABLE and closed except for i

g.

ingress and egress or testing as specified by $pecifisetten 3.6.8.1.

RGIN nhall be the enevnt of teettivity eMeh the teatter is l

i emberitical er would be subtritical assuming all sentrol gods are tv11y l

l' g inserted entopt for.the single control ted of highest voettevity softh l

which is assumed to be fully withdrawn and the teatter is in the shutdevn condition; cold, i.e., 60'F; and monen free.

I 9000ARY shall be that line which the land is seither l-4 ied,by = u n.ee.

l

,,3 ned, nor iessed..or.therwise sent FERMI WIT I 16 Amendatat No. H N

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uuuve es.es-nt e, e -e n..nnoi se is ed to a,edio u.e so.r..

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wi. n=== = wii ou.ansist er, i

. test uie for a.,.s. e

,s s trei. er.e r.e.si.n.tw i

g> e.

ses,enenu. uined., i.. g = e,eu h od test i

,esi 4 n

l equal seintervals.

6.

The testing of one systee, sesystes, trein er other.esignated l

sosponent et the beginning of each seinterval.

l 4

3 7 THElpEt, POWER shall be the tetel feester eere heat transfer rete to the g

g,q)

• 4 aster ene1 ant.

%MIM BYPAll SYSTM RESPONSE TIE l

MS 'The TUMINE BYPA&$ SYSTEM ESPON$t TIE shall be that time ' interva

(

I

.l d when the tertine bypass sentre) unit generates a tuttine typass valve flev signal until the tertine bypass valves trevel to their tegefre. posittens.

The response time any be esasured by og series of esquential, overlapping er total steps such that the entire response ties is esteered.

l l

IIIIMMIFl[p LEARAGE l

WIDENTIFIS LEARAGE shall be all lukage which is est IDENilFIED LEARAGE.

l l

STRICTED AREA j

MS An UNRESTRICTO AREA shall be og area et er beyond the $fft SOUIEARY l

cus u nich is not troned by the u

. f.e,.r,un.f

/'p =rotection of indivievels free esp $1TE BOLSEARY used for residential esure to radiation and radioactive pestarials, or any area within the guerters er for industrial, commertf al, instituttenal, and/or recreational purposes.

l fem! - WIT 2 17

_ _ _ _ _ _ _ 7 __ _.__.

i f~l 1mfr1Lafann magnust paginarr synal

$ A WWrflLAT80N E91458T TWmtNT M5fDI steit to em spetes destgenJ 4asteiled te vesnes M7 selete fore la er pesoles eastilettee or east echseet geoes tenoegh storeaal eenfor W PA filters fer the w eenwing to the teetnes or partlestates free the geeeeus eehaust etress telease to the eartreneent. Each a systee to est osas te have SW j

effect en sette gas effluente. Engineeres safety Festero

) stmespherfs TREATIIDtf i

. steene systems see set eensteered to to VWifILAT8til

)

i i

SYSTSIesepenents.

i IMUM afar wwr ss theit he see senteeises,,eesse of ete heroins air w oss e, e

eenfinement to estatsin temperature, pressure, eustetty, sensentratten er l'O ether operating eenditten, in ough a eenner that replesemect air er pas is met provided or reevived during VDfftels. West, used in systes names, does met leply a WWftless process.

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• UNIT 2 1-8 t

t

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S t S M a M ETRI M EI R L M rts

{

SALL1 NEttE MMht LIER EAT mispkTIm htft l

LIliff35 Mff15 FM WithTIM 8.8.3 All MttlE ptAll4R LIIEAR MAT WERRTION GRTES (APWbs) g$s11 est esseeds The Il4POWR limit ekteh has been approved for the vespeettve 1

s.

and Ettee tppe es e funstlen of tse p1 e

pf),

II detered med by the IOC approved estases ew or are the ses Stoitt lettg

6. g gilselett the j

the app 11 le

,,,, g,,,,, p ar

{.'-

gTD TIE 99WER '

M:

tatt

' earnett a tten within tMth an APUst eassedine the ebeve 1toitsAe 18 einstes and vestore APUBR to within t te"to

' n i hours or r

0 veduce TEDM 90 Wit to less then SIE of 4AT D E 70 Wit thin the esat 4 heers.

'O iig;;ratu r: armgarmwys i d.

[.-

i All APu1 Bas shall be verifted to be aquel to or less then the Itaits

).

4.2.}ved by Specifisetten 8.8.1t f.

requ e.

At least enee per N tours, j

M"E Worg'*4m'2,*u '"'" " "**** '"'

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the veneter is Inittelty and et 1 SERDLN0pATTERNforAPust.

operating with a S st s.

T!

d.

The provistens'of Speciftsatten 4.0.4 eee set appliesble.

t FEtt! - 15:17 2 S/4 8-1 Amendment Ilo. 42

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o POWit DISTRIBWfl0N LIMITS 8/4.1.3 MINillM CtlTICAL POWER RATIO

)

, LIMITINB CBS IT18N POR OPERAfl0N t

MC t

1. E44 T/4/e-3/M # r.)

% M;;= 3.2.0-0, #^2; $pa nTtec/ In fAc (og12 t,t PoK Y (WL K).

,I ], (Tave

• I )

B

'A*

DELGTED where:

ta = x. w 6 eetends, teatrei red ever o stem 3 section tien limit to notch 36 per $pecification 3

.3.3, I

)k.018 l

=0.813+t.65[

N 1

i i=1 n

I t,y,,

q,3 g

i=1 na er of surveillance tests perfe to date in cycle, th a number of active control rods measured the i surveillance test, tg = average stran time to notch 36 of all rods se red th in the i survet11ance test, and N = total number of active rods asasured in 6pecification g

4.1.3.2.a.

APPLICABILITY:

OPERATIONAL C MDITION 1, when THilMAL POWER is greater than er equal to 25% of RAtt0 THilMAL POWER.

"I ACTION

[

1 I in the Centrol Cell Core (CCC) operating mede* and MCPR s d t

le MCPR limit shown in Figures 3.2.3-1 thru 3.

• The CCC operating mode includes oper th on1 At reds. Al shallow rods less than er equal to notch 36,' a tal rods inserted in the core, and rods inse sition 46. Normal con rability checkse cou 11as c s, scram time testing, and friction tes non CCC Ern#pde's not require the utilisation of the more restrictive C

centre' e

enal mode MCPR limits. Arw other operation is a non-ccc -- ratina ____.

-_ l FERMI - UNIT 2 3/4 2 6.

Amendment No.

89.42 a

~

i l

gpER B1EfRInftIm1Mtf8 pt.La EtantetIRtfitu smEt hatte i.=nen r sea spreanse M (teistand) a w as.b.taittete (twve A) times the eself estve shown in 74 to a

ens someti%stion within

. an of in a news n,sene l

MM, A within the east 4 hows.

** fif.'"

.,*."=b.

• fe'tEll'A'rt.s::'i '!1

i.

initie<

e,,ue.,to. ten.n n u esamies.an t me.s sw.e tore 6wiwe ct.

hows e, os.e i to issa en e. e, eart

,ee..

GATO 90Wtt wieta tan aest 4 hows.

]

s.

Speratine in e etheCCCoreen9CC ine ests with either the esin tw6tne s avstas insperable 8pecifisetten 8.7.9 or the

)

esistwo tester inspere te spetetten ser sentinue and the provistens e tien 4.0.4 applise61e~provided that,the Itp etefeined he 1

ter then i

.ithin one how$ewn in igwes 8, e veheater aspetet e surve (y the esin 1 thre..

C) t IEPR limit es e sees the

)

tutine as er esis appliset K shoun in f

. >2.

g d.

Operati in either the CCC non CCC ratins este with heth the esin per ifisetten 3.7.9 and the esistere totine s systen i e

esperator eter inspor lel rot en may sentinue and 14e provisions i

e one how.

of Spostfisation 8.9.4 ne

< sele provided l

IICPR is deterenned to seuel to eter then the toit as shown esta tw hine st and esistwo theapp11gEshownin in Figutes 3.2.>1 th 8.f.>3 by g

reble swve t j

g y g eter i

1

)

l i

MhN h

neue, to.

me ac reu es. s e s ope,eti.n. m w = co.,$

or to seten position 36 all per 1 sees in the less tods inserted to position 44., Glweel sentrel seg ity este ches sow) shocks, eeres time sting, and friction i

CCC eent iteds a set voquite the et 11 stion of the more we n CCC ende.

l spe tiens) enee itPR limits, by other operation is e een tet operati

(

plien WNIT 2 3/4 t-64 doentent No. 42 56 )

O O e

Insert B l

t i

t ACTION l

a.

With McFR less than the applicable McPR limit in the COLR, l

initiate corrective action within 15 minutes and restore MCPR i

to within the required limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next j

t 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l b.

With the main turbine bypass nystem inoperable and/or the i

moisture separator reheater inoperable per specification 3.7.9, operation may continue and the provisions of Specification 3.0.4 are not applicable provided that, within one hour, McPR is determined to be equal to or greater than l

the applicable MCPR limit in the COLR.

l I

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=,

t I

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i h

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I Pat *R BitTR19UT10W LIMIT 5 i

SURVEILL*fE 'tt0UlisiNT$

4.2.3.1 MCPR, with:

t = 1.0 prior to performance of the initial scree stee sease s

I a.

for the cycle in accordance with Specification 4.1.3.2 as defined in Specification 3.t.3 used to determine e limit in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each scram ti Surveillance b.

w tes equired by Specification 4.1.3.2, shall be determine be equal to or greater than applicable MCPR limit determined from Figure

.t.3 1 througn 3.2.3 18 d 3.f.3.!:

a.

At least once per

ours, b.

Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after c n of a THERMAL POWER increase of at least lit of RAT [0 TN[

WER, and c.

Initially and at lesi once per 12 rs when the reactor is j

operating with a L T!hG CONTROL ROD (RN for MCPR.

l d.

The provision f $pecification 4.0.4 are no pplicable.

l 4.2.3.2 Prior te e use of Curve A and whenever Surveilla Requirement 4.2.3.2 is perfo d while using Curve A of Figures 3.2.3 1 th h 3.2.3 18, non.CCC control rods are fully withdrawn from the re.

verify that a el rods are all control rods excluding A2 rods, Al she rods d

i Non.CCC conss than or equal to notch position 36, all peripheral rods, inserted rted to position 46. Normal control rod operability checks, cou ing rods i, scram time testing, and friction testing of non..CCC control rods does I

checrequire the utilization of the more restrictive non-CCC operational acte

+c k R limits, f

/

~

l i

I i

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f i

FERM) - UNIT 2 3/42-7 Amendment No. fi,44 i

w-Q%

4 l

)

Insert C 4.2.3.1 MCPR shall be determined to be equal to or greater than the applicable MCPR limit specified in the CORE OPERATING '

LIMITS REPORT (COLR):

a.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at 1 cast 15% of RATED THERMAL POWER, and c.

Initially and at,least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL ROD PATTERN for MCPR.

d.

The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 Prior to the use of a MCPR limit which is based upon a specific control rod pattern,and whenever Surveillance Requirement 4.2.3.1 is performed while using a MCPR limit based upon a specific control rod pattern, the required control rod pattern shall be' verified.

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.ree uwem to is vee uwom i

MIN UM ORiv10AL POWER RATIO OPA WBASUS W8M RMEDPLOW MGURE SJ,3-1A

(

sm - mar a s/4 a m a

n

.. p),44

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1.08' genys A 1.98

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00.1 0.8 0 A 8.5 0.0 8. 0.0 0.0 1.0

%U ovava A. u a seest tot oss opetettoest sees ist sett 4 De typees eed seletese espetetet stot la estelee.

SWAVS 9 OPn tielt tot see. tee opetetiesel modo itt 6ett totDine typees est estelese eepetetet t le servies.

SURVE

= letPR Nelt tot.eth 900 eed 800 088 epe est

.eGee with either tettlee typtes et moettste espetetet estostet est et ettedet.

14...te.itto..et.

e,ete.

ope,et.ees,

.e.ee

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FP NAAT10 VER8U MU M !tKSpPL6W

(

FtSURE 3.2.3-18 353E -13127 3 3/4 3=8b meantaantth.49',44

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f 0-20 30 40 50 SO 70 80 0

100 i

00ftE FLOW (2) l PLOW CORRECTION (K') FACTOR \\

l FIGURE 8.2.3-2

(

l 95D5 -Ikut 2 3/4 3=9 Ananement tio.

44 i

i

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I j

phEt 315 TRIM 10N LMITS I

2/4.2.4 LIEAR lEAT MIERAften hAff f

n-iimii sammen paa apreaftau 4 kH64, hk',f spec'f J l

3.3.4 The L!st she11 set esseed 8

i

.x ce= = = -,o weeru m w,p w m l

grgp;, gT4,=,,=== i..n==t.0== to ter an er p sun:

v* eg With the LNBR of e$ fuel red esseeding thekteit i inte servestive action g

i within il einstes and testore the UElt to within h lef t within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or F

l vedese THERNAL P0dR to less then 355 of RATED M=L 90 Wit within the next j

i 4 heves, l

sutyrlLLANtt Rt001REMINTS I

LfR, AylA* k l

4.2.4 W shall be determined to be equal to or less than the feit:

6 s.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, I

Within 12 hopes after esopletten of a TNtlBIAL POWER insgesse of et 6.

least lit of RAff0 THERNAL POWER, and i

Initially and at least once per 12 hewes when the feetter is c.

sperating on a LIMITING CONTROL 800 PATTERN POR LNER.

i l

d.

The provisions of Specificetten 4.0.4 are est appliesble.

l l

l i

i FEMI-WIT 2 3/4 2 10 kneent No.y,44 s

o

i asetuttfaAftVE e T E R j

j O

8.9.2 Special reports shall be edettled to the begional Abteistreter of the togtensi t' flee of the IAC within the Stas perted,qpostflaLfer_aae report.

]

s.1a me2 m afTerrION

~] pl&vs.7 g

)

6.30.1 la edittien to the appilseble record retention vogulmments of Title 10 Code of Federal Regulattens icated.the felleslag resores shall te retaland for at I

least the state s period fat

)

6.10.2 The followtag vetores shall be retained for at least 5 years:

Records and legs of unit operetten severing time tolerval et each a.

power level.

b.

Records and legs of prfactpal estatenance activities, taspections, i

repair, and replassment of principal itans of egulpment related te nuclear safety.

s.

ALL REPORTABLE EVDffs.

Records of serveillance activities inspections, and enlibrations 1

' d.

required by these Technical spectfIcations.

6.. cords of changes made to the precedures required ty Specificatio Re

' g e.

.1.

f.

Records of redteactive shipments.

Records of sealed source *and fission detector leak tes and results.

g.

h.

Records of annual pitysical inventary of all sealed source estarial of record.

'J

. 6.10.3 The following records shall be retained for the duretten of the unit Sperating License:

l-Records and drawing changes ' reflecting unit design endifications sede a.

to systems and egetpoent described in the Final safety Analysts tapert.

b.

Records of new and irradiated fuel inventory, fuel transfers, and '

assembly bureup histeries.

Records of radiatten espesure for all individuals entering radiation c.

control areas.

d..

Socords of gaseous and 11guld radioactive esterial released to the i

environs.

Records of transtant er operational cycles for these unit osapenents e.

teentifled in Table 5.7.1-1.

i FEWII ~ UNIT 2 6-21 Amendment No.11

Insert D

?

i CORE OPERATING LIMITS REPORT 6.9.3 Selected cycle specific core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each re3?ad cycle or any remaining part of a reload

[

cycle.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC i

in GESTAR II (NEDE-24011-P-A). The core operating limits shall be determined so that all applicable limits (e.g.,

fuel thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The COLR, including any mid-cycle revisions or supplement thereto, shall be submitted upon issuance to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector prior to use.

I l

l i

k l

u

_ ~, -

O y

p/L2_f0Wtt IRSTRIBEIDE LpgTS

(

yes The flections of this egetten that the peak eleddle0 tempere-dure poetaleted desian Des s=of=esolent ecsteent will not outmed the Holt specified In 30 CPR

.46.

R/4.1.1 MERAGE MANAR LEEEM MEAT SDitR4710N MTE j

1he geek sleddin0 tempersture (pdfellowl lated less'ef=esolent l

d vote of all the essident to priestfly a functina of the esorege

l veds of a fuel assembly at egy estal locethon and at only esconder11y en the ved to red power distributten within en essemb y. The peak eled tempera-tore is salculated esseine a LNBR the the highest powered ved ehish is squel to j

er less then the design UER sortested for densiffsetien. This LNIR times 1.02

.ts esed in the hoste sede with the are dependent state gap and red to red peaki

r. The Tschat (fisetton l

APUBR) is this u sR f the highest fa(ctor. The limitino valog for APUSR l

PLANhR LINEAR RATION Fod divided I=M.4m E Cdc#cAMW MM e

i o

the "8 N4PUSR welve is the east Itaiting seaposite of the lt fuel eschenica design analysis II4PUSA and the 80C8 II4PUSR IRC approved methods (specified in Fuel IInchenical Design Analysis:

Reference 1) are use6 to demonstrate that all fuel fods in a lettice, speratino at the boundin0 pouer history, seet the feet design Itaits nU i

opecified in Referenge 1..This bounding pouer history is used as the basis for the fuel design analysis IIAPUIBR value.

i LOCA Analysis: A LOCA enelysis is eerformed in accordanci with 10 CFR 50 with the ICCS Appendia K to demonstrate that the II4PulBR values esep for the most lioits specified in 10 CFR 50.46. The snelysis is limiting break sise, break locatten, and sin 01e fat ure seabination for the plant.

sg l

m l~

On1 the most 11mitin0 II4 PUER values in the CDLA.

for su ice

. tihen hand sa es ations are II4PUSR4dgesceluesforthatfeel

,these j,

type are used for a lettises in e.

C#LA.

For some feel bundle desions II4PUIBR depends only on bundle toe and burnup.

Other feel bundles have 114PulBRs that very exially dependin0 upon the specific combination of enriched granium and gedeltate that semprises a fuel bundle cross l

eaction at a particular axial mode. Each Derticular combinetton of enriched for these fuel bundle types, is salled a lettice toe.

erente end gedolinia, bundle types have fl4PUBRs that very by lattice (an'lelly) rticular fuel These pas with fuel burnup.

as uel h

$""*'].'***"'*.!**$$.*"**"*"'*"*****"'***""'"~

(

FENU - UNIT 2 8 8/4 2-1 Amendment No A2 -

J

I t

f RAstl fable R 3.2.1 1 31R1FICAFT IDQ pts TD.1ME i

Lall.0F_.g10LMT ACCl$NT ANALYS!$

l Plant Parame as Core TE R............... 8430 Ittt* which a to 1988 of Peted ste law 6

vessel Steen est

.............. 14.06 a 10 1 which serresponds

$55 of reted steam flew Wessel Steam Dome Pressu

..... 1955 psi 1

i Design Basis Recirculation Li y

g [p i

Sreek Area fort f

\\

t a.

Large Breaks 4.1 ft t) 6.

San 11 treeks 0.1 f V

Fuel Parameters:

P8AKTECHN! CAL INITIAL SPECIFICATION

$18N It!NINUM l

t LINEAR NEAT CRITICAL FUt1 UNDLE SENERATION RATE PEA G

POWER FUEL TYPE f.0 METRY (W/ft)

FACTO RATIO Initial Core 8x8 13.4 1.4 1.18 First Reload 4a3 14.4 1.4 1.14 A more de led listing of input of each model and its source is Pres ted in Section of Reference 1 and subsection 4.3 of the PSAR.

• Thi e level meets the Appendix K vequirement of 1025. The core heatup calculation assumes a hundle power eensistent with operation of the l

highest powered ved at 1025 of its Technical Specifiestien LINEAR NEAT SERERATION RATE limit.

A i

=

......-. =

-' ~ --

l 1

s l

FRIDl! - IINIT 2 8 3/4 2 3 Amendment No.g,44.

l I

E

e

• DR ER DISTt! EfteN L11t!TS i

(

)

maeen l

S/4.t.3 II!E!IRBI CRITICAL poler RATIO Therequi ties 11mittag IICpts et e

.etsteopentiessenditions i

as specified la iftsatlen 3.3.3 are dortved es establishel feel stad.

ding inteerity sty Limit IICpt end as enslysis ebne m:1 eserational tmn-I sients. Per any ababenst operetIng transients ans isevaluatTenstunthe state operating "init it tattial senditten of the reteter betag at e s stes is required eat the resulting IICpt d6es act decrease belet the Safety Lislt j

llCpR st any time ductag the transiest assuming tastrument trip settleg given in Speciftsatlen2.t.

To assure Det the fuel cladding i rity Safe Limit is act exceeded 1

during a v saticipated abnormal operett transient the aest limiting tran-t sients have been anstra to determine which result in the 1ergest reduction in i

CRITICAL POWER RATIO (C

. The type of treasients evaluated were less of flow, increase in pressure en e)ener, positive reactivity insertion and seelant tem-perature decrease. The 11 siting transient ytoids D e largest When added to the Safety Limit flCPR the required ninte s operating limiting IICPR of cification).t.3 is obt4Ined and presented in 6 l

l

%, C.*af 0@4tW ci MMtT$ 4#8 44 (60 a.),

The flCPR surves illustl'bd in FA1 res 3.3.3-1 thru 3.3.31g were deriv C

es-ier ned a eve for *e e as

=ea e,eraune esadiuens I

separa reheater A

IICPR limit with turbine 'eNse system epistsI'en Cu

. stem n a rvice and C aiCitiCn.

i nde l

J

'At reds, Al shallows inserted 'ess than er equal notch posi.

s 36 all peripheral reds ed all rods i to positten I

46.T$eoperatinedoeninin,t$edesthe1

/ flew recien and ed lead line regten wie 1008 e and reduced flow.

,i l

l Curve g. IICPR itait the turbine bypass tea seisture esparster reheater sys in service and CCop,erationalsede(av men-CCC eenteel inserted thesere)'. The operating l

densin includes De r/fisw region and theJ atended k

lead line region with 1 e and redpeed flow.

Curve C - $1CpR limit for ei e CCC er eserstions) and a erith m

l either the mai e6ine typass sys inoperatise and the asis-ture espere reheater system avail er the asin turbine l

bypass available and the meisture ester reheater sys-I tem i rable. The operatine demain int 1 the 2005

/f sw resten and the estended lead line with 1005 r with reGused f1sw.

/

l

)

Cu

. IICPR limit for either CCC or men CCC sperational medes the asin turbine bypass system inestrative and the esisture e stor j

(

reheater systes inoperable. The operating demain includes th l

ptARI - Ull!T 2 8 3/4 t-4 Amendment lie. pp,#,44 l 4

,,,, - + -.,

..r.,

. - ~ -

~

-..-_,m,.. -, - - -., - -

,\\

f i

l WWWER 31STRIWf10N LMTS k

naars t

e, R/4.2.3 anuta-enf71 tat seura RATIS (Continued) m.

30 5 t/flev vesten and the estended lead lies vegion E

wtth power ens reduced fles, y

g terve A provides the Ept 19eit asseing operetten above SS RATED POWER with the tw6tne o ersten and meistwo taperator ter L

la co. The surve uns based the operettag E pt its for ten 3.4.3).for within 1 error trens ont UFSAR,fattne Tetp ylth Turt l

e ved tel ved patterns and Neta as Failure the CCC trenstant ShR Section 35.2.8S. 8CC eentrol veds are At shallow veds (fase less thee er aquel to esteh positten N) el pheral reds and all veds 1 to positten 46. The snelysis of a Tw tine Trip, 3

with fertine s Fellyre takes credit for the stese f to the oefsture esperator geheater.

Curve B provides Ept Itait assueing en ebeve the 35 percent GRTD MM POWit wf the tertine typass ers and esistwo separeter vehester system in servi and een CCC sentroT teserted in the sere. Wen-CCC eentrol rods are all excluttag At

.Alshellesveds(tasertedless all r

tal veds, and all rods faserted then er aquel to notch posit

36) loped een the operating Ept Itaits to positten 46. The curve uns ve (s

for e red withdrawal error trens at (UF

, Section 35.4.2) for egy operating withdrawal sequence.

Curve C provides the Ept Itait sein'0 speration ebeve the R$ percent RATB MMAL p0WER with the mois ester veheater opbroble and tutine typass ten inoperable or the store roter vehester taspetable and the turbine ss erstem operable.

he surve s developed based open the operat-ta0 epa sits for several inattens of ter Centre 11er Fellare.

l Operation with asin ine st er with a seistwo esperator.

gehester tasperable resol in a 1

flew s espebility of approxiestely le percent 36 percent tve. The of operation with the meisture e veheater i,

le tot typass operable and stilisatten of Cwve is senservettve the 86 bypass 111ty 4

to less Itaiting i ed to the entstfas ens) e to estehlish eC which ass ees en1 eercent typass espebf11 with the in turbine espass system tasperab1

. Therefore, the ration RATO MMAL p0WER with ei the seistwo sepa evehestertaspetable esin turbine i

typass ersten asperable is bounded by the suisttag Curve E.

Cwwe provides the'EpR Itait assuming operetten above nt GATED p0WER with both the seisture separeter veheater le end I

the ne bypass system taspetable. The swve uns developed the j

spero ng EpR limits from the Feeenster Centro 11er pe11ere.

I There is ao sede thenge vostreint should the sein turbine typass or

(

stwo separator veheater be taspetable. Neuever, eheeld the esin tuttine

(

e l

4 i

FEMI - tst!T 2 3 3/4 2 4e Ameneent No. 39. 4f r,

d POutR_MafRIMf10R LIMITS

, k.

an m 314.f.3 Intetsmet CRitteAL POWtt RAfte (Contissed)

/

typees erster or the soisture seperator vehester be 1eoperable as Sl'agereent BTED filtlBihL S0WER is saceeded, the flCPR sheek sust be completed attain onej bove.

The evaluation of a given transiset begins with the system initial strometers shown in UPSAR Table 18.0.1 that are tapet to a 88. core tyneate behavior transtant casou progree. The codes seed go evaluate transients 1

are described in SBSTAR Thi princips1 result of this evalsation is the l

reduction in 310PR saused the transient fAaMast &T,

4 d. Gef aftter>% %% idboT(tM The purmse of the L 1'astor is to esting

.a d

Itaits at et e *-- -*d s.i, flow

itions, i

%I rated flow up41gfRsis the product of the

. The IL factors es

. we safety Limit IICPR will a violate during a flow theresse transient rosulting fece a seter generater meed conteel failure. The 8 fatters may be applied to both annual and autoasti : fles sentrol sedes.

9 e,a

/

The factor values seradeveloped rica11y l

o all

, and SWR /4 res stors. N festors end are op 'lisable t

' ' ' ' ' * ' a **"'"'"''

n ** **'"" ' ' "5 "

C

• a*t rated sore flow', although they are app 11eebl "or uhe eatended operating ef region.

For the annual Plow centeel sede, the ly fasters were seleulated such that for the naminum flou rate as Itaited ty the pump act op tube setpoint and the corres nding THtlBU L PCedR along the rated flow cont rol line the limiting bundle a relative pc werwasad,1esteduntiltheIICPRI hangeswlthdifferentsore flows. h ratis 01 the IICPR solculated at a gives p sint of core flow, divided ty the operating lis it flCPR. determines the 1(9

) $M.ifL Ited Passet att i a 3/4 a-46 Amendment Ile. 88.48+"

1

,.,M,....

1 1

fBER R15ft1RKION pHITS i

ama l

3/4.2.3 MIhDRM CRITICAL FINER RATIO (Continued)

For operetten in the estaastic flou sentrel mode the same precedure uns esplayed oncept the initial gewer distribution was esh11shed such that the WPt ens aquel to the aperating Itait Ept at BATS flEm 90ER and voted l

M Cett ektefd. Ms AchtT (c,64)

The K,facters en eeneervatin for tem General 6 are greater then the original 1.prettas limit EPts6 AMe. (et.4 Electricplant en because a

se operating limit EPR used for the I

1 generic derivation of A.

g At flEm 90ER levels less then er aquel to 35 percent of BATB TERMAL Ii FOER, the reacter will to eMeeting et einfam recirculatten speed and the

'4 enderster void sentent will he very eas11. For all dest sentrol red pet-

)

teens which egy be employed at this point, operating p1 t tence indicates 1,

that the resulting E SR value is in excess of toevirements e eensiderable

,I mergin. During initial starte testino of the plant, e ICP evaluetten will be

}*

ande et 25 percent of RATS TWWIAL POSER 1evel with etnism recirculation pop 2

speed. The ICPR sergin will thus te demonstrated such that future IEPR evalue-i tien below this power level will be shown to be annocessary. The daily require-O esat et Rata view 1ItpA when TIEttAL POWER is greater then er aquel to 2 eent for calculati

'0wER is.vericient since so or distrihetica shifts are very slew when there have not been significant power er sentrol ved changes.

The requirement for calculatine EPR when a limiting eentrol ved pattern is ep-preached ensures that IEPR will be known follow!ag a change in'IIEWlAL POWER or gehepe, regardless of magnitude, that seuld piece aparatisin et a thermal I

3.4.R.4 LINEAR lEAT SENERATION RATE Y

en (LHBR) in eh s

a liet l

a postulated.

h:

1.

Seneral Electric Company Analytical Itodel for Less-of-Coelant l

Analysis in Accordence with 10 CFR 50, Appendix K. IEDE-20666,

\\

l Ilevesber 1975.

7(

i 2

" General Electric Standard Application for Gescter Feel,"

IE0E-34011-p A. tTt ;;nzf n;tL...

J

(

pEDU - IBGT 2 8 3/4 2-5 Amendment No. 42

a l

i 1

i Insert E i

The thermal. expansion. rates of U02 pellets and Zircalloy cladding are different in that,'during heatup, the fuel pellet could come into contact with the cladding and create stress.

If the stress i

exceeds'the yield stress of the cladding material, the' cladding-I will crack.

The IJIGR limit assures that at any. exposure, 1%

plastic strain on the clad is not exceeded.

This limit is a function of fuel type and is presented in the COLR.

i

?

i i

e s

t 4

f

'I

)

I f

i 1

I I

i e

ATTACHMENT 4 Changes.to Single Recirculation Loop Operation Technical Specifications (Reference 6)

?

i s

i t

k

s-0 u

.r i

F4.R.1 NERAM pLMAR LIEAR EAT MEMTION MTE G mia a EM BfftM 933 g ematt0N 3.2.1 All MERAGE PLAMR LIMAR MAT MERATIM MTgs (APUSRs) shall set l

eassed:

a.

The MPUSR limit which has been for the respective fuel and lettles type as e function of pionerqges as detereised by the MC approved methode SW thed la EST II),

J er 6.

tRien hand selsulations are red, the most tietting lettice two

~

espesare eteen in N4PUSA 11 14 as e for the l

the Coat 8%fala MS M*AT N"'d ll.

epp11 le er aquei se sau of BATED TEM 4L POWER., when MM4L PO PL1 TAR 1LITY: OPE COSITION 1 jf

-[

s'

i M:

J W th an APUER exceedi the above limit inittete secrective action within 1

15 einstes and restore UER to within limits within 2 hoves er h

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. reduce THERMAL POWER to less than 2 5 of RATE MAL POWER within the next j

y l

SURVEliter REQUlumms he 4.2.1 All APuGRs shall be verified to be equel to er less than the limits F.

required by Speciffsation 3.2.1:

~

c.-

At least once per 24 6'ours, e.

.j 6.

Wthin 12 hoves after sempletten of a TEMAL POWER increase of at l

t least 15 of RATO TERMAL POWER, and Initially and at least once per 12 hoves when the teacter is I

s.

j sperating with a LIMITIM 00NTROL MO PATTERN for APUER.

l d.

The provisions of specificetten 4.0.4 are est applicable.

l

}

Th e Nf Afl.ti & R liel/

.s. h a ll b e.

r'eclu e rd b y a fa c to r-f m ide/

a l

I.1 tke Col R h r19.sl9 s

/voy ep e a tien I

I FEMI - WIT 2 3/4 2-1 Amendment No. 42 i

1

i 34aimma muf mpu pn.a.1 autanames eram j

'( N gpm aanma ma esseman s2 AL?w==we !=!=t aptes =1-!aj mgp een ne a apr,tfm.

e

. acu x

=r.. m om.r = a m c m =,,..,_

M c MILITY: W Eh473 W 4L M M f e d 28 i

amas recte,e w.w

/a

,+ 7 me one reenter seeint erstes =teesiatten us, est n e,e=tt i

tenediately tattiste setten te veduce TIENt4L 90WER to less e

i 1 to the Itait apostfied in Figwe 3.4.1.1-1 within 8 and i.-

4 inte esaswes to pla.ce the entt in et least IST within gg

~~

i b.

M th no ter ecolant system recirculatten leaps t

retten, I

tunediate) eittste action to reduce TIEM4L ess than er equal to it specified in Figure 3.4.1.1-ithin i hours and initiate esas to place the unit in at 1 STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in NOT thin the east 6 c.

M th two resetor esel tem retire ion leaps in aperation and total core flow less the W of core flew and flEttAL POWER greater then the Itait spec ed f igure 3.4.1.1-1:

1.

Itsnitor the APM and 1se levels (Surveillense 4.4.1.1.3):

3 a)

..i n. -.f te, e this een m en a at i.ast ence per 24 thereafte 11e in this sendition end.

l b) m thin 30 s after the a tien of a TEMAL POWER i

increase at least W of RATED MAL POWER in an hour by to 1 red esvesent.

2.

With PM or lpm ** neutron flua noise le Is greater than l

tare fees their established baseline noise le e, tamediately in ato corrective action to restore the noise le is to within required limits within 2 hopes by increasing to low to 1

i.

gmater than 4R of Peted sore flow or by reducing THE POWER to less than er equal to the limit specified in Ffgure 3..

11.

C8ee Special Test Enception 3.10.4.

l eegetacar levels A and C of one LPM string per core octant pies g&nstemet-

)

and C e' e

the center of the n'tored when eperating with a nonsymmete en. Only the center of the core LPAM stri na C and tme o tectors A and l

tored for operations with a apuestric centeel FEMI - UNIT 2 3/4 4-1 1

i i

1 a

ea e

i 6

Insert P e.

With one reactor coolant system recirculation loop not in operations i

1.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1

i a) Place the individual recirculation pump flow contro11er f or the operating recirculation pump in the Manual mode.

j i

b) Reduce THERMAL POWER to toss than or equal to 70% of RATED THERMAL POWER.

c) Limit the speed of the operating recirculation pump to less than or equal to 75% of rated pump speed.

B d) Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit b/

0.01 to 1.08 por Specification 2.1.2.

e) Reduce the Maximum Average Planar Linear Heat Generation Rats (MAPLHOR) limit per Specification 3.2.1.

f) Reduce the Average Power Range Monitor (APRM) Scram and Rod Block and Rod Block Monitor Trip Setpointa and Allowable Vatues to those applicable for single recirculation loop operation

• per Specifications 2. 2.1, 3. 2. 2. and 3. 3. 6.

g) Perform Surveillance Requirement 4.4.1.1.4 if THERMAL POWER is less than or equal to 30% of RATED THERMAL POWER or the recirculation loop flow in the operating loop is less than or equal to 50% of rated loop flow.

2.

The provisions of Specification 3.0.4 are not applicable.

3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l b.

With no reactor coolant system recirculation 1 cops in operation, whilo in l

OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the t

SHUTDOWN position.

c.

With no reactor coolant system recirculation loops in operation, while in OPERATIONAL CONDITION 2, initiate measures to place the unit in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, l

E APRM gain adjustments may be made in lieu of adju; ting the APRM and RBM l

Flow Blased Setpoints to comply with the single loop values for a period of up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

t 1

1

7 5

.m l

i

'n4=vina - m sysfum amr=e i

i 1

maaes

?

mes pastremm

.1.m.

mefmeertATION atTpettffs (gentinued)-

Secause the flux distribution associated with unifem l

Genera 11y the ty a significant amount. the rete of power rise is very slow.In en essmed uniform I

heat flum is in near equilibrim with the fission rete.

red withdraws 1 approach to the trip level, the rete of peuer rise is not aore i

thein N of RAffD TEML POWER.per minute end the ApM system would be m l

" than adequate,te assure shutdown before the power sou1d escoed the S f

The 185 neutron flum trip reesins active until the ende suitch is placed in 1

i

• the Run position.

i tem is salibrated using host balance data taken during

' The ApM trip 's Fission chambers provide the basic input to the due

s. aystes and therefore the sentters respond directly and qu Ctaa $. state conditions.

il) be less than that

.. i.e. for a power increase, the THEWL POWER of the fuel w indicated by the neutron flux due to the Stee constants'ef the heat f

casociated with the fuel. time constant of 4 a 1 seconds is introduced into the I

A more conservative to steulate the fuel thema1 transient characteristics.

eaxious value is used for the flow biased setpoint as shown in Table 2.2.1-1.

l The Apm setpoints were selected to provide adequate margin for the $sfety Licits and yet allow operating margin that reduces the possibility of.unneces*

(

)

The flew referenced trip setpeint must be adjusted by the specified femula in Specificatten 3.2.2 in order to enintain these margins sary shutdown.

l when NFLpD is greater than er equal to FATP. Adat he#f.

\\

Reactor Vessel St=== Dese pressvee Ninh 3.

Migh pressure in the nuclear system could cause a rupture to the nuclear A pressure system process barrier resulting in the release of fission products.

incrosse while operating will sise tend to increase the power of the reactor by The trip will quickly reduce the sempressing poids thus adding reactivity.

The trip setting is slightly moutron flux, counteracting the pressure increase.

higher than the operating pressure to po sit normal operation without spur p

The setting prov' des for a wide mergin to the maxteue allowable design i

pressure end takes into account the location of the pressure measurem trips.

This trip to the highest pressure that occurs in the system during a transient.

l setpoint is effective at low power / flew conditions when the tuttine stop val

)

For a turbine trip under these condittens, the transient analysis indicated an adequate margin to the thermal (qrdraulic limit closure trip is bypassed.

l l

fr l

8 2*7 l

FEMI - UNIT 2 L

....an i

a i

l INSERT PAGE B 2-7 j

l I

For single recirculation loop operation, the reduced APRM setpoints are based on a A W value of 85. The A W value corrects for the difference in indicated drive flow (in percentage of drive flow which produces rated core flow) between two loop and single loop operation of the same core flow. The decrease in setpoint is derived by multiplying the slope of the setpoint curve l

by 85. The High Flow Clamped Flow Biased Neutron Flux-High setpoint is not.

applicable to single loop operation as core power levels which would require this limit are not achievable in a single. loop configuration.

i f

• I T

e f

i i

e i

i e

i 4

a i

i a

4

w ps. u ma m m in e m tapts

(

==a E ed s Ne ha F(.$.1 AVERARE MANAR LIMAR MAT Mutt 4 TIM RATE Thepeak

$11evi postulated less*efasselant escident to a

en of fetten vote of all the veds of a f as ly at est antal and only seconderfly en the vette red power distribution vi a

semb y.

k stad tempera-ehlsh is squel to tute is calculated essee as e L M R for the U SR times 3.02 or less then the des USR servested for 9s used in the sede with the ute dependent state gap and ved-poeti f

r. The Techst ifiestion ptAll4R 1,1NEAR RATION APUSR1is this USA the hi p st ved div'ded k1 The 1ssiti lugg<aruSRa ersumum p

n il4 PURR velse is the gest Itaiting gesposite of the The' i

fuel eschanica design entlysis $14PUSA and the ICCS 814 PUER ISC appfeved methods (specified in Fel lischenical Desien Analysis:

Reference 1) are use8 to demonstrate that a11 fm1 veds in a lettice, operatina et the bounding power history, seet the fuel design limits O

specif tet in Referenge 1..This bounding power history is med as the l

basis for the fuel design analysis finfulGR value.

LOCA Analysis: A LDCA entlysis is perfereed in accordsaci with 10 CFR 50 d

Appendix E to demonstrate that the 114PUSR vales with the ICCS for the sost limits specified in 10 CFR 50.46. The analysis is Itaiting break size, break location, and single fat ure sembination for the e.

plant.

l t.en hand DfilECEA.

in the i

en1 the most Itaiting II4 PUER value

.re t

for.iti

.ttice fue

,these 114PUERQ oelues for llet fuel type 6fe med for a lattises in e.

For esos fuel bundle dosi II4 PUER enly on hundle and burnup.

that very exially de~pending egen specific Other fuel bundles have 184 PUS i

seabinetten of enriched urania and gedellnia that sceptises a fuel hundle cross section at a particular antal sede. Each Derticular esebinetten of enriched for these fuel bundle types, is ea11ed a 1sttise type.

grenim and gedelinia,hundle types have Il4PUSRs that very by lattice (amia11y) eticular fuel Thesepaswithfuelburnup.

es wel Aofcl Zyg 3/t' 2-/

pneral Electric StandeNI Application for Seacter Fuel,* Mst.M011-P A -

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3.

F E M I - IINI T 2 B S/4 2-1 Amendeent tioA2 -

i e,

i Insert p. B 3/4 2-1 For plant operation with a single recirculation loop, the above MAPLHOR tim 2ts are multiplied by a factor specified in the CORE OPERATING LIMITS REPORT (COLR). The COLR f actor is derived f rom LOCA analysis initiated f rom s' ingle loop operation to account f or earlier boiling transition at the limiting fust nodo compared to the standard LOCA analysis.

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p e.a.1 MtittRRAfth STATEN L.

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le jet gnep to est fa flee 1f e esfffstent poseen to destem

1. asret is*sesteent.

o vestmoletten leap toepereHe, tot it ages. Se sees of a An taspe 18e sereh tarvesse the Massown eres ses seemse the espsM19ty of 4

with a peup taspetehle.

resent for sluplesun of the festl en e tauis,the een to estatted ty senttert pump

.' det peup fatpreserthed seheavle fler afgetf"teent degredetten.

eespitanee via %BCC$ra,es 'u i

totiteelet. ten,.hspes.e elseets% 14mits are n,.w

.,e,ser.

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enei, sis s

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In ereer to prevent endue steess en the sessel essales eng bettes lead veston, the restesetetten leap temperstwee shell to witMe gr'F of esen ot l

The leap tempotetsre must slee te within e m = =i e mi u s teepw t m se,^m ent te i

E *ter to etertup of an idle leep.

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r of e. emee w r

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""m 5 1 1:=i j

i O.. F;..._d-F 5 0 = ~:==:r = " S,2 E

. 1 44FtTV/stL1tF VALVES 2/4,4.2 The oefety valve function of the esfety/roitef volves operate to prevent i

sortsed ebeve the lef Limit of the reacter eselant system fees he A total of 11 esfety/

natt psig in accordance with thetelief volves is retutred to limit reacter presswee III alleueble values for the eerst ease apset transtant.

during shutdown and will be perfereed in essereente w Specifisetten 4.0.5.

The 1sw leu set system ensures that a potentially high thrust lead (desig-ested as lead.sese C.S.8) en the SRV efeaterge Itaes to elleinsted during sub I

TMs is erhieved by autenettee11y lowerfag the closing set

• pint of two velves and lowerlag the opening setpoint of two valves seguent estustions.

$UffiClent fededenty is previed for the jew law set system suci. that fe11ere of egy one selve to open er elese et its reduced setpoint do Initist spaning.

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not violate the ensign tests.

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pggpu - gel!T 2

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Insert 0:

the igact of single recirculation locp operatism won plant madety is r levels assessed and shows that single-loop operation is permitted at ty Amit is,

up to 7M of IE'it 15BlN04,70fER if the MCPR fuel claddingAMM actam ano cents 01 rod inereased as noted by Specificetion 2.1.2.

f block setpoints (or AMM gains) are adjusted as noted in Sttdes 2.2.

r 3 3.6-2, respectively.A time pe11od of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed to make these gecification 3.2.1.

adjustaunts follwing the estatdiahment of single Aoop operation since the 8CFR operating j

need for single loop operation often cannot be anticipata5.

l limits ad3ustments in Specifioation 3.2.3 for difforent plant operating

. situations are applicatdo to both single and two recirculation loop operatiorb l

Tb prevent potential control system oscillations from coeurring in the recirculation Alew ocntrol system, the operating made of the recirculation f

21w control syste must be restricted to the manual control made for l

l single-loop operation.

Additionally, surveillance on the pump speed of operating recirculation i

loop is Agosed to esclude the possibility of esoessive core internaisSh j

vibration.

POiER or 5M rated recirculation Aoop flow is to prevent undue thermal stress on vessel nozzles, recirculation puup and vassat bottom head during l

,O a power or flow increase intlowing extended operation in the single I

recirculation loop mode.

Insert 11:

I The limits will ensure an adequate cote flow coastdown from either recirculation loop followmg a LOCA.

In the case where the mismatch limits cannot be mamtaanpd durmg two loop f

operation, continued operation is permitted in a smgle recirculation loop 1

mode.

Insert I:

Radden equalization of a temperature difference >145 F between the 1

reactor vessel bottom head coolant and the coolant in the upper region of i

l the reactor vessel by increasing core flow rate would cause undue stress in j

the reactor vessel bottom head.

Requirements are inposed to pronabat idle loop startup above the 80t rod 1

line to minimize the potential for initiating core thermal-hydraulic instaba.11ty.

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SCTOR000LANTSISTW maass t

l 1/4.4.10 "! TIBIBl&L NTDRAULIC STABILITY BWR oores typtoally operate with the presence of global neutron fluu noise l

As the in a stable mode which is due to randos boiling and flow noise.

power / flow conditions are changed, along with other systes parameters (pressure, suboooling, power distribution, etc.) the thornal hydraulic /

)

reactor kinetto feedback anchantas can be enhanced such that random perturbations any result in sustained limit cycle or divergent oscillations l

in power and flow.

The first mode Two major *.1sodes of oscillations have been observed in BWRs.

is the fundamental or core-wide oscillation mode in which the entire core The second mode involves oscillates in phase in a given axial plane.

regional oscillation in which one half of the core oscille.tas ISO degrees out of phase with the other half. Studies have indicated that adequate margin to the Safety Limit Minimum Crittoal Power Ratio (SLMCPR) any not j

exist during regional oscillations.

l Regions A and B of Figure 3 4.10-1 represent the least stable conditions of the plant (high power / low flow). Region A and B are usually entered as the Ih result of a plant transient (for example, recirculation pump trips) and 1

therefore are generally not considered part of the normal operating 1

Since all stability events (including test experience) have domain.

occurred in either Region A or 8, these regions are avoided to minimize the possibility of encountering oscillations and potentially challenging the Therefore, intentional operation in Regions A or 8 is not SLMCPR.

allowed. It is recognized that during certain abnormal conditions within l

the plant, it any become necessary to enter Region A or 8 for'the purpose of protecting equipment which, were it to fail, could impact plant safety In or for the purpose of protecting a safety or fuel operating limit.

these cases, the appropriate actions for the region entered would be i

l performed as required.

Nost oscillations that have occurred during testing and operation have occurred at or above the 100% rod line with core flow near natural l

This behavior is consistent with analysis which predict circulation.

As core reduced stability margin with increasing power or decreasing flow.

flow is increased or power decreased, the probability of oscillations l

Region A of Figure 3 4.10-1 bounds the majority occurring will decrease.

of the stability events and tests observed in GE BWRs. Since Region A l

1 represents the least stable region of the power / flow operating domain, the potential to rapidly encounter large magnitude core thermal hydraulic

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p.

esoillations la ineressed. Ruring transtants, the operater any not have suffiotent time to annually insert eentrol rods to a141 Rate the

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esoillations before they reach an annoceptable empitude. Therefore, the prompt action of annually seremains the plant edien Regies A is entered is required to ensure protection of the SACPR.

Based on test and aparet esperianos, the frequency of eere therbal i

hydraulio oscillations is in Region 3 than in Region A; Decay ratios j

i, are espooted and predicted to be louer in this regica staes Region 5 oovers a lower power and higher flev range than Region A.

Also, the margin to the EJCPR will typtoally be larger in Angton 3 than in Region 4.

With more margin to RJCPR and a lower probability of socillations, eatting Region 3 by control rod insertion is, justified. Rouever, if socillations are observed while emiting Region 8, the reactor will be manually seressed.

j The potential for oore thermal hydrau11e oscillations to occur outside of Regions A and 3 is very small and therefore special requirements are not necessary outside of theos regions.

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4 9 8

e ENCLOSURE 1 FERMI 2 CYCLE 2 CORE OPERATING LIMITS REPORT REVISION O I

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