ML18010B142

Proposed Tech Specs Associated W/Cycle 6 Fuel Transition

ML18010B142
Person / Time
Site:	Harris
Issue date:	07/16/1993
From:	CAROLINA POWER & LIGHT CO.
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ML18010B141	List: ML18010B140 ML18010B142
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NUDOCS 9307270190
Download: ML18010B142 (45)

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ENCLOSURE TO SERIAL HNP-93-826 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION TECHNICAL SPECIFICATION PAGES 9307270i90 9307kb PDR ADOCK 05000400 (2020HHP)

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3/4.2 POWER 3:STR!BUT!ON L:.".!;S

4. 2. 1 a'(.'AL FL"X 0!FFEREVCE L ..lTINC C NDl 0 t FOR OP 2>T:CV

3. 2. 1 The indicated AXIAL FLUX Dl. FERENCE ( AFD) sna ll be ma inca anted ~aching o- 4a.rid a.bow% %he. far e.+

e ac e a e o r i n c as specified in the CORE OPERATI VC LiMITS REPORT (COLR), plant procedure PLP-106O to R ax d aal Off ec nc ol op rac on, r

b. M'chi a b nd ouc che arg c 0 ri g ase oa op rac'on s pec fie in e C LR.

APPLICABILITY: MODE 1 above 50X of RATED THERMAL POWER"-.

ACTION! u);ah V

a. o C a <o ui che indicaced AFD oucside of che limics specified in the COLR, eicher'.

1. Restore che indicated AFD co Michin the limics specified in che COLR Mithin 15 minutes, or

2. Reduce THERMAL POWER co less chan 50X of RATED THERMAL POWER Michin 30 minutes and reduce che PoMer Range Neutron Flux-High Trip secpoincs co l,ess chan or equal co 55X of RATED THERMAL POWER Mithin che next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ND ~ Mich the 'ndic ed IA FLUX b For Base oad peraci n abov APL eich r:

~

D FERE E ou side o rhe b nd abo c che arge AFD,

l. escor the in icate AFD to Michin che argec band lim cs Michin 15 min ces, o 2 Redu e THER L PO'W R co 1 s than APL of TED ER L PO R and discon nue B e Load operac'n M'hin min tes THERMAI. POWER shall noc be increased above 50X of RATED THERMALin unless che indicated AFD is Michin che 1imics specified che

.POWER COLE o e o "See Special Test Exception 3.10.2 i th m'm al oMa e p Mer vel r Ba Loa ope acio an L 1 as pe ifi d i rh CO Amendmenc No.

SHEARON HARRIS - UNIT 1 3/4 2"1

'1 J

POMER 0

DISTRIBUTION LINITS SURVEILLANCE RE UIRWENTS 4 ~ 2.1.1 Thc indicated AFD shall bc determined co be vithin its limits during

?OWER OPERATION above SOZ of RATED THERMAL POMER bye

a. Nonitoz ing the indicated AFD for each OPERABLE excore channel at least once per 7 days vhen the AFD Honitor Alarm is OPERABLE, and

b. Nonitoring and Logging the indicated AFD for each OPERABLE cxcore channeL at Lease once per hour for the first, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, vhen the AFD Monitor ALarm is inoperabLe. The Logged values of the indicaced AFD shaLL bc assumed to exist during the intervaL preceding each Logging.

4.2'1.2 The indicated AFD shaLL be considered outside of its Limits vhen tvo or more OPERABLE excare channels arc indicating the AFD ta be outside the Llmlts ~

Whe. 5L 4.2.1.3 a zan t rcarget of each 5 AFD OPERABLE cxcore channeL shaLL be determined by measurement at least once per Effective FuLL Povcr Days The provisions of Specification 4,0.4 are nat appLicable.

c'x c.o c'

4. ~ 1.4 cn an a e oa oper xon, e t rget AFD s aLL e upd ted, t Leas o ce r 31 ffect, ve Ful Pave Day by c'er ete inin the argc AFD i onj etio vith he sur eiLLa ce rc uire nts f Sp cifi tian .2.1 3 abov or y Lin ar int rpolat on be veen he mo t re entL meas red v Lue d the c cuLa d valu at th end f cyc e Lif . pro isio s of pecif'tion .0.4 a e not appLi abLe.

c.onjuoc.+ o< a M tg +Q e requic'a meK4 cV 5Iaa,c.ig c.a.+lc ~ +.Z.P.P . e.cearly

%he +OrtIa+ A,FIO

~pd~4'p J logg~q~~ rnid.as~ I c& pA+

4~ a dd;nq ~he moa4 r value. nkvd +he. change. ~ 4hz.

VQILA~ ~ Clc.Q +k~

SHEARON HARRIS - UNIT 1 3/4 2-2 Aaeadseac No.& p5

AX IAL FLUX 0? FFERENC ': ..' iS A F" NC .:ON OF RATED THER@PL i O'WER 0 This c inure is deieced cr"m ".ecnni=a: S"eci::=ac,iors and is ooncrol;eJ oy c<e CORE OPERATING LlÃfTS REPORT, plant procedure PLP")0o.

SHEARON HARRIS " UNIT I 3/4 2-4 Amendment NO.M

I l

I

/ C

k POWER 9 I ST R.I BUT ION LIMITS SURVEILLANCE REQUfREMENTS 4 '.2a I ..".e prOViSiOnS Oi Spet::!tat'.On -'.O.4 are nOC appl:CaOle.

' 2.2. r iop( shall "e evaiuaced i:

o R 0 o FQ( Z) co decermi ne ii wichin ics Limit by:

a. Using che movable incore decectors co obcain a power oiscrsbucion map ac any THERMAL POWER greater chan 5X of RATED THERMAL POWER.

b. Increasing che measured FQ(Z) componenc of che power discribucion map by 3X to accounc 'for manufacturing colerances and further increasing che value by 5X co account for measurement uncertainties. Verify che requirements oE Specificacion 3.2.2 are sacisfied. a

c. Sacisfying che foil'owing relationship.'TP FQ (Z) < x K(Z) Eor P > 0.5 Px Z)

V RTP FQ (Z) < x K(Z) for P < 0.5 Z) x 0.5 M

where F (Z) is che measured F~(Z) increased by the allowances for Q

manufaccuring colerances and measurement uncertaincy, f RTP is che FQ L imic, K(Z) is che normalized F~(Z) as a Eunction of core heighc, P is che Ecaccion oi RATED TEERHAL POIIER, ane@Z) is chegyyljg e n e Eunccion chac accounts Eor power discribucion transients encountered during normal operation.', RTP K(Z), and Z) are specified in che COLR.

d ~ Measuring f~ (Z) according co che following scheduLe:

L. Upon achieving equilibrium condicions after exceeding by lOX or more of RATED THERMAL POWER, che THERMAL POWER ac which FQ(Z) was Lese decerminedP>> or

2. At Least once per 3 1 EEfeccive FuLL Power Days, whichever occurs ELrste

<<During power escalation at the beginning oE each cycLe, power level may be increased uncil a power LeveL for extended operation has been achieved and a power discribucion map obcained ~

SHEARON HARRIS - UNIT 3/4 2-6 Amendmenc No. ~

I C

OWER 9L ST% rrBU rON L:.". i: S SURVE.': y ANCE R"" ULRKbdEHTS (C .". Ln"ed)

H "ich measuremencs ind:acing I-<~

max um x<z) has increased since che previous determination oi FQ'Z) eicher of che following actions shall be taken'.

f Q (Z) shaLL be increased by 2Z ovec that specified in SpeciEicacion 4.2.2.2c, or a d o +a,~e.+ AF'G ree ~%~bi ~hW

2) F (Z) shall be measured ac Least onc e per 1 Effective full Q

Po~er Days until two successive maps indicace chac F<>

ma lmum Q() is not increasing.

E ~ With che relacionships specified in Specificacion 4.2.2.2c above noc being satisfied:

Calculace che percenr. FQ(Z) exceeds ics Limic by che toLLowing expression:

V maximum rr >

x L00 Eor P '.5 x K(Z)

P x QZ) vZ) maximum x L00 for P < 0.5 x K(Z) 0.5

2) One oE che following actions shalL be taken:

a) 'Within L5 minures, control the AFD co within new AFD limics which are determined by reducing the AFD Limics specified in che COLR by LZ AFD Eor each percenc FQ(Z) exceeds ics limits as determined in Specificacion 4.2.2.2f.l). Wichin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, resec che AFD alarm setpoints to these modified Limics, or b) CompLy with the requirements of Specif icacion 3.2.2 Eor P (2 ) eeceedrnd i'inie by cba pcrcenc calcclaced abccg.

~

SHEAROH HARRIS - UNIT L 3/4 2"7a Amendment Ho. ~

0 POWER OISTRIBUT'.ON LIMITS SURVEILLANCE REQUIREMENTS (Con".:.".ueo)

Veri cha cne requ remen s oi pecif.-act n 4.2.2.3 or Bas Load oper cion are s cisi t d an en e Base Load op caci:o

g. The limics specii'.ed in SpeciEicac ions 4 .2 .2 .2c, 4 .2 .2 .2e, and 4.2.2.2E above are noc applicable in che following core plane regions:

). Lower core region from 0 co 15K, inclusive.

2. Upper core region from 85 co 100X, inclusive.

4 .2. B se Lo oper ion i permit ed ac owers a ve APL iE the oil win condi tons e sat'ied:

P oz t enter g Base oad o ration, ainr,ain HERMAL P ER above L . nd le chan equal co chat llowed Spec'Eicac' 4.2. .2 Eor tease e previ s 24 hour . Maine tn Ba e Loa operac'on surv llance FD wich'he limi s speciEi d in e Co Opera ng Lim s Reporr, during is cime riod. B e Load perati is ch ~ermicc d )rovid g THERMAL OWER is ma cained ecween L and PL or ecween AP , and 10 hichev is mos limicin and fg rv[il.lant is maint tned pursua to Spe ficacio 4.2.2.4. APLB is fined as:

FRTP B K Z APL ~ mini m ( ) 100 F( x W(Z) wh e: M F~( is che mes ured F~(Z increased b the allo nces for nufactu tng toleran s and mea cement unce taincy, F P is che F~ lim' K(Z) is c e normaliz d F (Z) as a function core heig c, and )BL is the ycle depe ent $ unctio that acco ts Eor li ced po r distribute' cransien s encountere during Ba e Load eracion. F , K(Z), nd W(Z)BL ar specific in the CO b.. Durjgg Bas Load opera on, if the T RMAL POWE is decrea ed belo~

APL th che condic'ons oE 4.2.2 .a shall b sacisfied before rc-enc ing Base Lo operacion.

.2.2.4 Ouri g Base Load peration f~(Z shal.l be ev luaced co decermine ic is vithi ics limit b ~

a. Using the'ble incore ceccors ~o o ain a po er distribu ion map at any HERMAL POWE above APLN

b. Increas'ng the measu d FO(Z) compon c of th po~er distr bution map b 3X to accoun for manufaccur ng toier ces and fur her SHEARON HARRIS - UNIT 1 3I4 2-7b Amendmenc No. W

0

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1 POWER DI STRE BUT-.OH L v i, S SURVElLLANCE REQU? REAGENTS (" " ' -eo)

Ca ply M h the equire.ents a Speci: catia 3,'.': r F~(Z) ceedi .g i ts .mit a the pe ent ca culat Mitn t folio ing ex ession

((max. f F') x W

)gL

) -ll l00 t 'AP f I P p

x K(Z)

P

g. The ar

'mits not ap s ecified icabl.e 'he4.2.2.4 c, fol ouing 4 .2 co e

. .4 .e, an 4.2 plane egions'.

'. at ab e L er core egion 0 t l5 pere c, incl, ive.

2. Upper c e region to l00 ercent, elusive 4.2 ' @~ When F()(Z) is measured for reasons other than meeting the requirements of Specification 4.2.2.2 an o erall measured F~(Z) shall, be obcained from a pouer distribucion map and increased by 3X to account for manufaccuring tolerances and further increased by 5X to accounc for measurement uncertainty.

SHEAROM HARRIS " UNET l 3/4 2-7d Amendment Ho. ~

'. SPECIAL TEST EX . T'.ONS 3/a.10.2 GROUP HEIGHT INSERT:CN ANO POWER DISTRISUT ON LIMITS L MERITING CONDITION FOR OPERATION 3.10.2 The group height, insertion, and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3. 1.3.6, 3.2. 1, and 3.2.4 may be suspended during the performance of PHYSICS TFSTS provided:

a. The THERMAL POWER is maintained less than or equal to 85" of RATED THERMAL POWER, and

b. The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: MODE l.

ACTION:

With any of the limits of Specification 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1..3.6, 3.2.1, and either:

3.2.'re suspended,

a. Reduce THERMAl. POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or

b. Be in HOT STANDBY within 6 hours.

SURVEILLANCE RE UIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to he less than or eoual to 85K of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 The requirements of the below listed specifications shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during PHYSICS TESTS:

a. Specification 4.2.2.2 and 4., nd

b. Specification 4.2.3.2.

SHEARON HARRIS - UNIT 1 3/4 10 2 AAI~ndOIC& Alo.

,'C I l ~

J

3/4 ~ 2 POWER DISTR IBUT;ON Li..lTS BASES The spec iE icat ions oc this section provide assurance of c'ueL integrity during Condicion I (Hoc'mal Operacion) and II ( Incidents of moderate Frequency) events by: ( l) maintaining the minimum DHBR.in the core greater than oc'qual co che design OHBR value during nocmal opec'ac ion and in short-term transients, and (2) limiting the fission gas release, fuel pellet temperature, and cladding mechanical properties to within assumed design cciteria. In addition, limiting the peak linear power density during Condition I evencs provides assurance that the initial conditions assumed Eor the LOCA, analyses are met and the ECCS accepcance criteria limic of 2200'F is not exceeded, The definitions of certain hot channel and peaking factors as used in these specifications are as follows:

t Fq(Z) Heac flux Hot ChanneL Factor, is defined as the maximum local heat flux on che surface of a fueL rod at coce elevation Z divided by che average fuel rod heat flux, allotting foc manuEacturing toLecances on fuel peLlets and rods',

Nuclear Enthalpy Rise Hot Channel Factor, is defined as the catio of the incegral oE Linear powec aLong the cod wich che highest incegrated power to the average rod po~er; FaH Enthalpy Rise Hoc Channel Faccor, is defined as the ratio of the incegraL of linear power along the rod wich the highest incegrated power to the average rad power, with an allowance co accounc foc measurement uncec'tainty.

3/4.2 l AXIAL fLUX

~ DIFFERENCE The Limits on AXIAL fLUX DIFFERENCE (AfD) assure thac che f (Z) uppec bound envelope of the F() Limit specified in the CORE OPERATING LIMITS REPORT (COLR) times the normalized axiaL peaking Eactor is not exceeded during either normal operation oc'n che event of xenon redistribution followin ower changes. Th orma ted xca peakc g ac r is pecif ed <n the C Tar eW Target flux dif e ce ( AFD) is determined at equilibrium xenon condi-tions. The rods may ba posicioned wirhin the core in accordance wich their

~ cespeccive insarcion Limics and should be inserted near their normal position Eor steady-srate operation.ac high po~er levels. The value of the target Elux difference obtained under the e conditions divided by the fraction oE RATED gage.+ THERMAL POWER is che AFD ac RATED THERMAL POWER Eor the associated core burnup conditions. AFD foc other THERNAL POWER levels are obtained by mulciplying che RATED THERMAL POWER value by che appcopriate fcactional THERHAL POWER Level ~ The periodic t, oE the target flux dif ference vaLue is necessary to refLect core urnup considerations. The. targe.4 APL) ma.y 4e. tcpda~W 4aWAeC.A No-R~4rc'-m eeVS bcc.wad o< +Pa.

c ha~pe. in +he- prelic+ed Vcclue. wc& 4u.rnv-p.

cnco+ Q fcc.AA c.A4 SHEARON HARRIS - UNIT L B 3/4 2-l Amen dmen c Ho ~ P

I POWER DISTRIBUT:QH LI'Hl.S BASES go.rqe.+ 4a~d abo~+ 44e AXIAL FLUX DIFFBRENCK (Concinued) 'mr a.+ ggp

'The. targe) c we 0 op r i l el.s bel

~ T w A, c e l mic were on AFD calculated in ar a manner

<~

peciiied in che COLR+Q such chac expecced 4a~d p~gg operacional cransiencs, e.g ~, load Eol low operations, would noc result in che AFD deviacing outside of those limits. oweve, in ch evenc t a ev acion o urs, e shor period E time al owed ouc ide oE c limic ac reduc d wer l vels w l not r ult in si nifican xenon r iscrib ion such hat che envel e of p aking Ea ~rs woul change Eficien y to p venc ope acion in che icinic of che L powe level.

po~er evels eater ch APL,ND o modes f oper ion are rmissible

) RAO with fi d AFD li its as a unction E reac r power l el and 2) Base Load peratio which is defined che mai cenance of the AF wichin a and abou a car c value. Both the fixed AF limits or RAOC o eracion an che ba Eor 8 e Load eracion e speci ed in e COLR. OC operac's above L ar che sam as Eor o ration low APL H

. Howev, ic is po sible whe ollowi g excend d load E lowing neuvers ac the A l,imits resulc rescr tions i che maxi um allow d power AFD in o der co gua ancee oper cion wit F~(Z) l ss chan s limici g value. o allow o ration a che ma mum pe issible lue, ch Base Loa operacing rocedure escricts e i dicaced D co a el ac ivel small ca ec band a d power sw ngs. For ase oad ope ation, i is expe ed chac e plant wi l, operace ichin ch targec band. peracio outside E che car ec band Eo che short cime peri d allowed will ot resu in sign'icanc xe n redistr'tion such chac che nvelope '

pea ing fact rs would change suE ciencly t prohibit c ncinued eracion power gion de ned above. To assure there is no residual xenon edistri cion imp cc from pa operacio on the B~s Load op acion, a 24-hour waiting riod ac a ower level. above APLH and allo d by RAO is neces ary. Dur'ng this ti period, l ad changes nd rod m ion are res icted to hat allowe by the Ba Load proc dure. Af er the w cing p iod, exce ded Base L d operacio is permis ble.

The computer determines rhe one-minuce average of each oE the OPERABLE exoore detector outputs and provides an alarm messa e iamediacel if che AFD for cwo or more OPERABLE excore channels ar ' t ide che all ed I wer er ti pa e C op ra o r oucside c e accepcab e AFD cargec alarms are active wh ower i reacer band B e o er ci n . These than 5 o RAT D THFRMAL POtlE r RA ope a on , r ) AP ( or e o r o e a n mi u s or Ba e pe ac o a e oc o lcp sd nt eid E im drig hih praio ousia E cre bn i e SHEAROH HARRIS - UNIT l B 3/4 2-2 Amendmenc Ho. W

POWER D I ST R I BUT ION L I!II T 5 BASES HEAT FLUX HOT CHANNEL FACTOR, AND RCS FLOW RATE AND NUCLEAR ENTHALPy R ISE HOT CHANNEL FACTOR (Conc inued)

c. The control rod insertion limits of Specifications 3 .I .3.5 and 3.1.3.6 are ma incained; and

d. The axial power discribucion, expz'essed i'n cerms oz AXIAL FLUX DIFFERENCE, is maincained wichin che limir.s.

F<H will be maincained wichin its Limits provided Condicions a. chrough d.

above are maintained. The combinacions oE the RCS flow requirement and che measuremenc of F<H ensures chac the calculated ONBR wilL not be beLow che design DNBR value. The relaxacion of F<H as a funccion, of THERMAL pOWER allo~s changes in che cadial po~er shape Eoz'll pez'missible zod insertion 1 zml ts ~

When an F<< measurement is caken, anRy)lowance for measuremenc ezroz muse be applied prior co comparing to the F<< limic(s) specified in che CORE OPERATING LIMITS REPORT (COLR). An allowance of 4X is appropriace for a full-core map caken with the fncore Decectoz Flux Mapping Syscem.

Margin is maintained becween che safecy analysis Limit ONBR and che design limic DNBR. This mazgin is more chan sufficient co offset any rod bow penalty and cz ansicion coz'e penalcy.

When an F~ measuremenc is taken, an allowance for both experimencal error and manufacturing rolerance must be made ~ An allowance oE 5X is appropriace foz- a fuLL"core map taken with che Incore Detector Flux Mapping System, and a 3X allowance is appropriace Eor manufacturing tolerance.

V The hoc cha eL Eactor F (Z) is measuzed pez iodicaLly and inczeased by a cycle and height ependenc power factor o r a e co e r o a e IZRSSRh to provide assurance that rhe Limit on the hot channeL factor, F~(Z, is mec. VZ) accounrs for rhe effeccs of normal operation transients and was decermined fzom expecced ower concroL maneuvers ovez the EuLL range of burnup conditions in the coze. W Z co n r th es z'1 tl 0 ez'l ml 5 1 w BseLod e cin hih e 1 es se er tr ns'en v ue . The Z) d funccion r specif ied in the COLE.

SHEARON HARRIS - UNIT 1 8 3/4 2-4 Amendmenc No. ~

ADMINISTRATIVE CO OLS 6 Co 0 G L TS REPOR'r 6.9.1.6.1 Core opeiating limits shall be established and documented in the CORE OPERATING LLMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a. Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,

b. Shutdown Bank Insertion Limits for Specification 3/4.1.3.5,

c. Control Bank Insertion Limits for Specification 3/4.1.3,6,

d. Axial Flux Difference Limits r t d a d for Specification 3/4.2.1, V

e. Heat Flux,Hot Channel Factor, Fo"~, K(Z), ( L and (Z) for Specification 3/4.2.2,

f. Enthalpy Rise Hot Channel Factor, F~a~, and Power Factor Multiplier, PF~ for Specification 3/4.2.3.

g. Boron Concentration for Specification 3/4.9.1.

6.9.1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

('in>at+ Stakema.wk g 4e.ra)

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (P Proprietary).

(Methodology for S ecification 3. .1. - de at T e a e e

Co t c en , 3. - hut wn ank ns ti n i , 3 1.3 6-B e io Lim , .2.1 - ial enc 3.2.2

.Heat Flux Hot Channel Facto 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor 0 0 ce t 0 ~

Cg A PORT G A RE NE ATIVE OL MOD TO TEMP CO CI TE CAL PECI CATION FOR S N NU PO P ", August 1988 Prop etary .

rov by C S ety E alua ion ed Ma 22, 1 89.

(Me odolo for Speci cati n 3.1 .3 - odera r Te eratur Co ficie t) .

-10 6-P-, " TIO OF C NSTANT AXIAL FFSET CONTRO Fq URVEI CE ECHNI SP IFIC ION", UNE 1 83 (W ropri ary).

(Met dolo for ecif atio 3.2.1 - Axia Flux iffer ce (Re ed ial Of set ntrol and 3. .2 - at Fl Hot Fac or (F Metho logy for W ) surv illanc req ement ).

SHEARON HARRIS - UNIT 1 6-24 Amendment No.

(Xnsme~ >e X Statement 1 Pace a 0 XN-75-27(A),. latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6 - Control Bank Insertion Limits, 3.2. 1. - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9. 1 - Boron Concentration).

b. ANF-89-151(A), latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 Shutdown Bank Insertion Limits, 3. 1.3.6 - Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference,,3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

gp , XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

XN-75-32(A), Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise.Hot Channel Factor).

XN-NF-84-93(A), latest Revision and Supplements, "Steamline Break, Methodology for PWRs," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1. 1;3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion. Limits, 3. 1.3.6 - Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EXEM PWR Large Break LOCA Evaluation Model as defined by:

XN-NF-82-20(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, Richland WA 99352.

XN-NF-82-07(A), latest Revision, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Richland WA 99352.

XN-NF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod Thermal Response Evaluation Model," Exxon Nuclear Company, Richland WA 99352.

XN-NF-85-16(A), Volume 1 and Supplements, Volume 2, latest Revision and Supplements, "PWR 17x17 Fuel Cooling Test Program," Exxon Nuclear Company, Richland WA 99352.

XN-NF-85-105(A), and Supplements, "Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

XN-NF-78-44(A), latest Revision, "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1.3.5 - Shutdown Bank Insertion Limits,

,3.1.3.6 Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).

ANF-88-054(A), latest Revision, "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, and 3.2.2-Heat Flux Hot Channel Factor).

ADMIHI STRATI V" CONTROLS UCAP l-0266-P-A. !!e .. ".:-.e !SSI Ve:e!oo o:ee "ES iNCHOUSE EVAI.UATIOH MODE'- USAHC THE BASH CODE", March 1987 ('>> ?ropr.ether/).

(Methodo)ogy ior Specii'.=at:on 3.2.2 - Heat Flux Hot Channel Faccor).

WCA -838 6

"? ER STRI UTIO CONT OL A LOA FOL OW IH PR EQU ES OPIC L RE RT", Sepc mber 974 Pro riec ry).

( etho olog ior peci icat n 3..1 - xial lux iife enc Const nc ial fisc Con. ol))

f<, Q HCAP-! !SIT-P-A, "EXTEllSION OF HETHOOOLOCY FOR CALCULATING TRANSITION CORE DHBR PENALTIES", January l990 (W Proprietary).

j'.Mc>hodo'Logy Rot <p<46<'tER~Sc!A 3-Z.'5-"~oc<~r Eath<(F')F 9,se. Ho4Chs6hQ plGE '+i 6.9.1.6.3 The core operacing limics shalL be determined so chat alL py,c+~y) 57~<~ applicable limits (e.geP fuel chermal-mechanical limics, core thermaL-hydraulic Limics, nuclear limics such as shutdown margin, and transi enc and accident analysis limics ) oi the safety analysis are mec.

6.9.1.6.4 The CORE OPERATINC LIMITS REPORT, including any mid-cycle revisions or supplemencs, shall be provided, upon issuance for each reload cycLe, to che NRC Documenc Control Desk, with copies co the Regional Administrator and Residenc Inspeccore SPECIAL REPORTS 6.9.2 SpeciaL reports shaLL be submitted co che HRC in accordance wich IOCFR50.4 within che time period specified for each report.

6.10 RECORD RETENTION 6.10 ~ 1 In addition co che applicable record retencion requiremenrs ot Title 10, Code of federal Regulations, the folLowing records shaLl be retained for ac Lease che minimum period indicaced.

6. 10 ' The foLlowing records shall be retained for at lease 5 years:

a. ,Records and Logs of unic operation covering time intervaL ac each power level1 bo Records and logs of principal maincenance activities, inspeccions, repair, and replacement of principal. items of equipment related co

'e nuclear safecy; C~ ALL REPORTABLE EVENTSP

d. Records of surveillance accivicies, inspections, and calibracions required by rhese TechnicaL Specificationsi SHEARON HARRIS - UNIT 1 6-24a Amendment Ho. 2

(xz<ev v'o PA6E Statement 2 5 -29~

k. EHF-92-081(P), "Statistical Setpoint/Transient Hethodology for Westinghouse Type Reactors," Siemens Power Corporation, Richland WA 99352.

(Hethodology for Specification 3. 1. 1.3 - Hoderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6 - Control Bank Insertion'imits, 3.2. 1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor ).

EHF-92-153(P), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Nuclear Power Corporati'on,Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

1, Supplement 1, XN-NF-82-49(A) Revision 1 and XN-NF-82-49(P), RevisionBreak Model," Exxon "Exxon Nuclear Company Evaluation Model EXEM PWR Small Nuclear Company, Richland WA 99352.

- Difference, 3.2.2 - Heat (Hethodology for Specification 3.2. 1 - Axial Flux Flux Hot Channel Factor, and 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor).

6 3 4'.2 POWER DISTRI ION LIMITS I'

4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION r

3.2. 1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a band about the target AFD as specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP- 106.

APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER*.

ACTION:

a ~ With the indicated AFD outside of the limits specified in the COLR, either:,

1. Restore the indicated AFD to within the limits specified in the COLR within 15 minutes, or

2. 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 less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.,

b. THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the limits specified in the COLR.

• See Special Test Exception 3. 10.2 SHEARON HARRIS - UNIT 1 3/4 2-1 Amendment No.

~ POWER DISTRIBUTION ITS, P

SURVEILLANCE RE(UIREMENTS 4.2. 1. 1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 50% of RATED THERMAL POWER by:

a ~ Monitoring the indicated AFD for each OPERABLE excore channel at least once per 7 days when the AFD Monitor Alarm is OPERABLE, and A

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2. 1.2 The indicated AFD shall be considered outside of its limits when two or more OPERABLE excore channels are indicating the AFD to be outside the limits.

4.2. 1.,3 The target AFD of each OPERABLE excore channel shall be determined by excore measurement at least once per 31 Effective Full Power Days in conjunction with the requirements of Specification 4.2.2.2. The target AFD may be updated between measurements by adding the most recently measured value and the change in the predicted value since the measurement. The provisions of Specification 4.0.4 are not applicable.

SHEARON HARRIS - UNIT 1 3/4 2-2 Amendment No.

FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER This figure is deleted from Technical Specifications and is controlled by the CORE OPERATING LIMITS REPORT, plant procedure PLP-106.

SHEARON HARRIS - UNIT 1 3/4 2-4 Amendment No.

i POWER DISTRIBUTION i MITS SURVEILLANCE REQUIREMENTS 4.2.2. 1 The provisions of Specification 4.0.4 are not applicable.

4,2.2.2 F,(Z) shall be evaluated to determine if it is within its limit by:

Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b. Increasing the measured F,(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2 are satisfied.

C. Satisfying the following relationship:

F," x K(Z)

M F,"(Z) z '

for P > 0.5 F,"(Z) a 'or P x V(Z)

F,"" x K(Z)

V(Z) x 0.5 P a 0.5 where F,"(Z) is the measured F,(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, F,"" is the F, limit, K(Z) is the normalized F,(Z) as a function of core height, P is the fraction of RATED THERMAL POWER, and V(Z) is the function that accounts for power distribution transients encountered during normal operation. F,~, K(Z), and V(Z) are specified in the COLR.

de Measuring F,"(Z) according to the following schedule:

1. Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which F,(Z) was last determined,* or

2. At least once per 31 Effective Full Power Days, whichever occurs first.

• During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and a power distribution map obtained.

SHEARON, HARRIS - UNIT 1 3/4 2-6 Amendment No ~

I POWER DISTRIBUTION HITS SURVEILLANCE REQUIREMENTS (Continued)

e. With measurements indicating F " has increased since the previous determination of F,"(Z) either of the following actions shall be taken:

1) F,"(Z) shall be increased by 2% over that specified in Specification 4.2,2.2c, or

2) F,"(Z) shall be measured and a target AFD reestablished at least once per 7 Effective Full Power Days until two successive maps indicate that F " is not increasing.

With the relationships specified in Specification 4.2.2.2c above not being satisfied:

1) Calculate the percent F,(Z) exceeds its limit by the following expression:

F "(Z) x V(Z) maximum RTP

-1 x 100 for P a 0.5 F

x K(Z) p FM(Z) x V(Z) maximum RTP x 100 for P < 0.5 F

x K(Z) 0.5

2) One of the following actions shall be taken:

a) Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits specified in the COLR by 1% AFD for each percent F,(Z) exceeds its limits as determined in Specification 4.2.2.2f. 1). Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits, or b) Comply with the requirements of Specification 3.2.2 for F,(2) exceeding its limit by the percent calculated above.

SHEARON HARRIS - UNIT 1 3/4 2-7a Amendment No.

POWER DISTRIBUTION ITS SURVEILLANCE RE(UIREMENTS (Continued) g, The limits specified in Specifications 4.2.2.2c, 4.2.2.2e, and 4.2.2.2f above are not applicable in the following core plane regions:

1. Lower core region from 0 to 15%, inclusive.

2. Upper core region from 85 to 100%, inclusive.

4.2.2.3 'hen F,(Z) is measured for reasons other than meeting the of Specification 4.2.2.2 an overall measured F,(Z) shall be

'equirements obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncer'tainty.

(Pages 3/4 2-7c and 3/4 2-7d have been deleted)

SHEARON HARRIS - UNIT 1 3/4 2-7b Amendment No.

l ~ 1 SPECIAL TEST EXCEPT NS

~ <I (P 3 4.10.2 GROUP HEIGHT INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION

3. 10.2 The group height, insertion, and power distribution limits of Specifications

3. 1 of

'. 1, 3. 1.3.5, 3. 1.3.6, 3.2. 1, and 3.2.4 may be suspended PHYSICS TESTS provided:

during the performance

a. The THERMAL POWER is maintained less than or equal to 85% of RATED THERMAL POWER, and

b. The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4. 10.2.2 below.

APPLICABILITY: MODE 1.

ACTION:

With any of the limits of Specification 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3. 1.3. 1, 3. 1.3.5, 3. 1.3.6, 3.2. 1, and 3.2.4 are suspended, either:

a. Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or

b. Be in HOT STANDBY within 6 hours.

SURVEILLANCE RE(UIREMENTS

4. 10.2. 1 The THERMAL POWER shall be determined to be less than or equal to 85% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4. 10.2.2 The requirements of the below listed specifications shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during PHYSICS TESTS:

a. Specification 4.2.2.2 and

b. Specification 4.2.3.2.

SHEARON HARRIS - UNIT 1 3/4 10-2 Amendment No.

2

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.I sa ~

i 3 4. 2 POWER DISTRI ION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (1) maintaining the minimum DNBR in the core greater than or equal to the design DNBR value during normal operation and in short-term transients, and (2) limiting the fission gas release, fuel pellet temperature, and cladding mechanical properties to within assumed design criteria. In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200'F is not exceeded.

The definitions of certain hot channel and peaking factors as used in these specifications are as follows:

F,(Z) Heat Flux Hot Channel Factor, is defined as the maximum local heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing For manufacturing tolerances on fuel pellets and rods; F~ Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power; F~ Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power, with an allowance to account for measurement uncertainty.

3 4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F,(Z) upper bound envelope of the F, limit specified in the CORE OPERATING LIMITS REPORT (COLR) times the normalized axial peaking factor is not exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference (target AFD) is determined at equilibrium xenon conditions. The rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target AFD at RATED THERMAL POWER for the associated core burnup conditions. Target AFD for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic measurement of the target flux difference value is necessary to reflect core burnup considerations. The target AFD may be updated between measurements based on the change in the predicted value with burnup.

.SHEARON HARRIS - UNIT 1 B 3/4 2-1 Amendment No.

,s

~ ~

y l

I e I'

\ ~ ~

L POWER DISTRIBUTION ITS

~ iv 7 BASES AXIAL FLUX DIFFERENCE Continued The target band about the target AFD is specified in the COLR. The target band limits were calculated in a manner such that expected operational transients, e.g., load follow operations, would not result in the AFD deviating outside of those limits.

The computer determines the one-minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the acceptable AFD target band.

These alarms are active when power is greater than 50% of RATED THERHAL POWER.

SHEARON HARRIS - UNIT I 8 3/4 2-2 Amendment No.

POWER DISTRIBUTION ITS BASES'EAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued

c. The control rod insertion limits of Specifications 3. 1.3.5 and 3; 1.3.6 are maintained; and

d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE,'is maintained within the limits.

F~ will be maintained within its limits provided Conditions a. through d.

above are maintained. The combination of the RCS flow requirement'nd the measurement of F<< ensures that the calculated DNBR will not be below the design DNBR value. The relaxation of F~ as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.

When an F~ measurement is taken, an allowance for measurement error must be applied prior to comparing to the F~R~ limit(s) specified in the CORE OPERATING LIMITS REPORT (COLR). An allowance of 4% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System.

Margin is maintained between the safety analysis limit DNBR and the design limit DNBR. The margin is more than sufficient to, offset any rod bow penalty and transition core penalty.

When an F, measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System, and a 3%

allowance is appropriate for manufacturing tolerance.

The hot channel factor F,"(Z) is measured periodically and increased by a cycle and height dependent power factor V(Z) to provide assurance that the limit on the hot channel factor,= F,(Z), is met. V(Z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. The V(Z) function is specified in the COLR.

SHEARON HARRIS - UNIT 1 8 3/4 2-4 Amendment No.

r . ~ 4.

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ADMINISTRATIVE CONT S 6.9.1.6 CORE OPERATING LIMITS REPORT 6.9. 1.6. 1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a. Moderator Temperature Coefficient Positive and Negative Limits ahd 300 ppm surveillance limit for Specification 3/4. 1. 1.3,

b. Shutdown Bank Insertion Limits for Specification 3/4. 1.3.5,

c. Control Bank Insertion Limits for Specification 3/4. 1.3.6,

d. Axial Flux Difference Limits for Specification 3/4.2. 1,

e. Heat Flux Hot Channel Factor, F,"", K(Z), and V(Z) for Specification 3/4.2.2, Enthalpy Rise Hot Channel Factor, F~R~, and Power Factor Multiplier, PF<< for Specification 3/4.2.3.

g. Boron Concentration for Specification'/4.9. 1.

6.9. 1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

a. XN-75-27(A), latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2 Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9. 1 - Boron Concentration).

b. ANF-89-151(A), latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank- Insertion Limits, 3. 1.3.6-Control .Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2 Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

C. XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24 Amendment No.

J',

e,

' ADHINISTRAT IVE CON S 4 4 ~

6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

d. XN-75-32(A), Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Richland MA 99352.

(Methodology for Specification 3.2.2 - Heat Flux Hot .Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

e. XN-NF-84-93(A), latest Revision and Supplements, "Steamline Break Methodology for PWRs," Exxon Nuclear Company, Richland WA 99352.

(methodology for Specification 3. 1. 1.3 - Hoderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

f, EXEH PMR Large Break LOCA Evaluation Model as defined by:

XN-NF-82-20(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEH/PWR ECCS Model Updates," Exxon Nuclear Company, Richland WA 99352.

XN-NF-82-07(A), latest Revision, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company,. Richland WA 99352.

XN-NF-81-58(A), latest Revision and Supplements, "RODEX2 Fuel Rod

=Thermal Response Evaluation Hodel," Exxon Nuclear Company, Richland WA 99352.

XN-NF-85-16(A), Volume 1 and Supplements, Volume 2, latest Revision and Supplements, "PWR 17x17 Fuel Cooling Test Program," Exxon Nuclear Company, Richland WA 99352.

XN-NF-85-105(A), and Supplements, "Scaling of FCTF Based Reflood Heat, Transfer Correlation for Other Bundle Designs," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

g. XN-NF-78-44(A), latest Revision, "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Mater Reactors," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6 - Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24a Amendment No.

(1 j

ADMINISTRATIVE CONT 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

h. ANF-88-054(A), latest Revision, "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear

'Fuels Corporation, Richland WA, 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).,

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (W Proprietary).

A (Hethodology for Specification 3.2.2 - Heat Flux Hot Channel Factor and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

WCAP-10266-P-A, Rev. 2, "The 1981.Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

(Hethodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

k. WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).

(Hethodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EHF-92-081(P), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," Siemens Power Corporation, Richland WA 99352.

(Hethodology for Specification 3. 1. 1.3 - Hoderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2 Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

m. ENF-92-153(P), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland WA 99352.

(Hethodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

n. XN-NF-82-49(A) Revision 1 and XN-NF-82-49(P), Revision 1, Supplement 1, "Exxon Nuclear Company Evaluation Model EXEH PWR Small Break Model," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24b Amendment No ~

ADMINISTRATIVE CONT 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued) 6.9. 1.6.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9. 1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator'and Resident Inspector.

REPORTS 'PECIAL 6.9.2 Special reports shall be submitted to the NRC in accordance with 10CFR50.4 within the time period specified for each report.

6. 10 RECORD RETENTION

6. 10. 1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

• 6. 10.2 The following records shall be retained for at least 5 years:

'a ~ Records and logs of unit operation covering time interval at each power level;

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; C. All REPORTABLE EVENTS;

d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications;

e. Records of changes made to the procedures required by Specification 6.8. I;

f. Records of radioactive shipments; g, Records of sealed source and fission detector leak tests and results; and SHEARON HARRIS - UNIT 1 6-24c Amendment No.

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