Text

6 to Core Operating Limits Report
	ML073450097
Person / Time
Site:	Oconee
Issue date:	12/04/2007
From:	Brandi Hamilton; Duke Energy Carolinas, Duke Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML073450097 (37)
	v • d • e

PDuke DEnergy December 4, 2007 U.

S.

Nuclear Regulatory Commission Document Control Desk Washington, D.

C.

20555 BRUCE H HAMILTON Vice President Oconee Nuclear Station Duke Energy Corporation ONO VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy. com

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Site Docket No.

50-287 Core Operating Limits Report (COLR)

Gentlemen:

Attached, pursuant to Oconee Technical Specifications 5.6.5, is an information copy of a revision to the Core Operating Limits Report for Oconee Unit 3, Cycle 24, Rev.

26.

Very truly yours, Bruce H. Hamilton Ite, Vice President Oconee Nuclear Site Attachment www. duke-energy. corn

NRC Document Control Desk December 4, 2007 Page 2 xc w/att:

Mr.

W. D.

Travers, Regional Administrator U.

S. Nuclear Regulatory Commission, Region II Mr.

L.

N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr.

Dan Rich Senior Resident Inspector Oconee Nuclear Site

NRC Document Control Desk December 4, 2007 Page 3 bxc wo/att:

NSRB -

EC05P bxc w/att:

ELL ONS Document Management

PRIORITY SuperRush DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW

1) 00620 DOC MGMT MICROFILM EC04T

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3) 01148 D L BROCK (ESE) ON01ES

4) 06358 ONS REGUL COMPLIANCE ONO3RC

5) 06700 ONS MANUAL MASTER FILE ON03DM

6) 06937 R R ST CLAIR EC08G Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION WORK ITEM: EXEMPTION M-5 RESP GROUP: NE RECORD RETENTION: 003587 CORE OPERATING LIMITS REPORT OCONEE 3 CYCLE 24 Page 1 of 1 Date:

11/29/07 Document Transmittal #:

DUK073330040 QA CONDITION Yes

- No OTHER ACKNOWLEDGEMENT REQUIRED 0 Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

Duke Energy P.O. Box 1006 Energy Center EC04T Charlotte, N.C.

INFORMATION ONLY 28201-1006 Rec'd By )3 0 fN4'.v.%

.Z)-mmn Date I

I DOCUMENT NO QA COND REV #/ DATE DISTR CODE I

2 13 4

5 6

7 8

9 10 11 12 13 14 115 TOTAL ONEI-0400-070 SEE REMARKS 1

026 11/29/07

/I

/-

I/

NOMD-27 V1 X

V1 V1 V1 V1 5

REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM PLEASE REFERENCE PAGE 3 FOR FILING INSTRUCTIONS THOMAS C GEER NUCLEAR STATION ENGR MANAGER GS-SVP NUCLEAR SUPPORT BY:

J W SIMMONS JWS/TER EC08H

ONEI-0400-70 Rev 26:

Page 1 of. 33.

Duke, Energy Oconee 3 Cycle 24 Core Operating Limits. Rep'-t QA Conditi0n 1 66'7 Prepare#dBy : DS. Or Date:;

Cecked:Byl: L.C. James !1 Date: 17 AIou ~

CDR.By: M.L. Cameiron Z*-"

6II,,

Approved By: R.R. St.Clair

"C&6 Date:: 11//.,/o7

.Date::

1AA

-7

'Documenrt No.] Rev.

ONEI-0400-7ORewv.26 Date November 26.12067-Page, No.

Page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:

Date:

(IfAZ6-O7 (Sponsor)

CATA*WBA W.aived SMCE (Mechanical &Civil) lE npýiected Ry/Date.

R S (lectricaltOnly)'

LI.I e

By/Pate:;0 SRES',(Reactor k[]

InspectedBy/Dte

.... _"___._:_:__[

MOD IInseted By/Iat:

Other.

[]

Inp ce.B / ae

ýOCONEEr inspection Waived

It,41.tiiny MOE (Mechani~cal. & Civil)

[]..

In.spected B.y..ate:.___.___._

ES! (Reactor) Oinec ted Byas*ie:f

'MOD M'.

Inspected By/Date:

Other ( _____________

Y

[]

~Inspected By/1ate;

-MQ GIIRE*

insphction 4OE- ý(Mechanicqal &rCivil)

[]insecd By/Dt;______________

RES (Electrical Only)

[:

Inspeted By/Date:....

RES (Reactor)

[-

Inpcted By/

.ate....

MOD El nspecte B~y/DaeM Other (

)

[]

Inspected By/D 9-te"

ONEi-0400-70 Rev :2i6 Page:3;of 33 Oconee 3CQyLe. 24 Core Operating Limits Report Irnsertion-S1ee~t4}6rReviSion :26 Removthies$

eRevision:25p Insertthese Revision* 26pages.

Eff~div PaesPaesPages ToaEfetv Revisin "Date Revised Added eeed PAges 1Ocon~eeý,Cy 3

'C.c24"2.v~isidn9 b~elow.o:071-3 3

N-OV

-Z

~1--33

-Oco3Ceya.e T

16..ý3Viio-hse bee

'Iw s23 MargŽ00 1 -4,6, 15-r 16, 21, 27,31f:,

22 Mar 20,06 1-5 33 21 s~Nov

-'*D-a'ei 1-vse

-.,3

.33'tdi:#g~~i' 19 F "004, 3

18 Nov2ý0031- ;-

17 Apr,2003ý 1-31323 5Oý.'~ C oy2002 1: 3-'

1, yNQ20,01 1-3'

. 4..

NOV2...:

1-31

ONEI-0400-70 Rev 26 Page 4 of 33 Oconee:3 Cycle24 1;0 Error:Adjusted CoreOperating lrmits The Gore; Operating Limits Report for O3.24,hasbeen prepared inaccordance.with the, requirements Of TS5*5...The core opqrating limits withinihis report, ave been dv using N C

appr'oyed,4,ethodology identified in-references 1 throu~gh, 11. The RPS prb.(.

eivmirits, anidmaximum allowable setpoints arei dbcumented in references 112 throughl'4. Thdeseilimits,.are validated-for useAi 03C24 :by refer.ences 15 through 17. The.O3C24.analyses-ass,.umea.:design fflowobf 107.5%,of 88,0009gpm periRCS:pump, radial lcal peaking (FAh) of 1.714i and axial'p.eaking*factor(Fz) of 1.5.

Theý_e.rrior djustpd :core:oteatinglimits included inmsectibn 1 of the repott incorporate all necessary uncertainties and.margins required for, peration

,of the, O324 reloadcore.

1.1 Refehi~es 1., Nuclear Deign Methodology UsingOASMO-3 I SIMU LATE-3P, DPCNE1'004*A, Reviii6n 0, SERd dted&No*vember_23. f9962.

2. coneexN`uclearStatiocn Reload. Deig-ethodloyIDCE-00-,Rv'in SER dated-a6tobe1r 1,~ 1985.

3., Oconee Nuclear Station Reload Design Methodology,- NFS-1 001 A-Revision5q, SER dated.Decembr ~;2004

4.

S**C*

eAleHydrauki od*h

.iol o......g...RE...

DPC.NE-.03-I.

Re....on..

S.Th'efte'iJunel* d 23,20A0*0,0.

5. The~al* Hyr46i-.li Sttistical. *ore-DesibnMyethodolog, DPCNE-2005.AR&,isiofr, S5ER dated'Seaptefber 1, -2002.

6.: Fuel'MechanicalReload Analysis Methodolb~g*Usirig TACO3, !DIPCNE-200O8-PA,.

7. UFSAR dhapter 15 T&ansient Ahnalysis MIethodology DPC;NE-3005-PA,Revision2i SER -ated Septeimber24 200-3.

Thermal Hydraulic Transienit Analyis: M.,ethodology', IDPC-NE6d-30PA Rev. -3 SER dated September 24, 2003.,

9. 8AW f0`2-PA, BW'NT LOCA-.BWNT Loss of *co6lant Accident. Evaluatiolno Md61l for.

Th ugh*S*eam G

.nerator Plants, Rev. 0,ER.F..1..

1,0. BA-06PA e.4 EA5MD-B&W - An.Advanced Computer orm for UihtWae R eacto r LO'CAýa n d No6n -LOCA Tranis ie nt A na.ysisI SER, date d AprHilf 9:,*2 002..

1:1. BAW1 0227-PA, Evaluaticon-ofAdvanced Cladding annd Structural Material- (M5)in PWR Reactor Fuel, Rev. 1,-.June. 2003,(SER:to.BAW-ý10186P-A daied June 18, 2003).

1'2. -RPS RC.SPres4urer& Te~iTperatJre T-ripFundtion-Uhcertainty ArAaýlyes dnd VaidabILLow Pressure Safety Limit.. SC-4048.Rev isioh -4,.Jury* 2001.

13..Po0wer Imbalance SafetyLimitsand Tech.Spec Setpoints Using Error Adjusted Flux-Flow Ratio0of, 1".094, OSC-5604, ReviSion'2, October2001.

14.*ATc and EQG Reduced Tavg. Operation, SC-7265, Rev. 1, Duke:Power rC.o. June 2002.

15. 03C24 Maneuvering Analysis, OSC-9099, Revision 2, November 2007.

16. :03C24, Specific DNB Analysis,,.OSC-91771, Revision 1, November 2007.

117. O3C24 Reload SafetyEvaluation, 0S0-9222, Revision 1, November20-07.

ONEI*-400-70 -Rev 26 Page 5 of 33 oconee 3 Cycle 24 Miscellaneous Setp.ints§ BWST boron concentration shall be geater han 2220 ppm and less, than 3000ppm.

Referred to by3TS 3.5.4.

Spent fuel pool boron. concentration shall be greater than 2220 ppm.

IReferred to by TS 3.7.12.

The-equiValent of at.least 110 O'Cubic feet of 1,000 ppm boronshallbe maintained in the CBAST; Referred to by TS SLC 16.5;1:3.

cFT b6oern concentration :sha~llbe.bgieaterd than 1835 :ppm. The average boron cbncentration in the CF(7sshball be. less than.4000:pprn.'m Referred to by TS 3'.5.A.

.RGS.Tanid Refueling canal:boon:'b6nceritratibti shall be. gteater than 2221pprnm

,RBeferred to by TS.319.1.

ý$huotdown Margin (1DM) shall be greater-than 1% Ak/k.

Referedtoy TS 3.1.1.

Moderator Temperature C(7oefficiýent (:MTC) shall beAlessth~a~n:

R jfere to byTS

.1.3.

ApI PFZ 1 +0.70 0..;525*

Q.o00 0.00

.!0 20; 80:

1005 420 D.epartutrefrom Nucleate BOitling (ON B) parameter fdo RCS leoop pressurd. shallbe Rlefer,red toby TS&3.4.1 4 RCP:

measured hibtqleg ptressure > 2125 psig 3 O:measured. hot'leg,pressure., 2125 psig

.DNB parameter for RCS loopiayerage temperature shall be:

1R6f erred toby TS-3.4.1.

S-Tv

`br

'i"ess thyi COLR limw its mionus instr, u-ment uncertainty. A-Tc i's-the setpo'irt value sel~eted b~y the6 oerators. Values are expanded by' hr ear interpolation on page 33ýof this document *ithoutinstrment unertainty.

Max Loo Ip Tavg ý(IncI 20F unc A~h, 0F R4 RO OQp 3'RPO 0D 58.1.0 51.

.2 518 581A.4 3

582.1 581.7

4 582.5, 58,1 9 5

582.9 582.

This limit is apliedljto fhe loop with :the lowest Ioop.average temperature consistent With the NOTE in :SR..1.:.. All other temperatre limits apply to fhe maximum loop Tavg.

DNB parameter for RCS loop,total*f flw shall be:

Referred to by TS 3.4.1.

-4 RCP:

Measured :107.5 %df 3 RcP:..

ýMeasuried >_74.7 %.of 4 ROP'mihn flow Regulating rod groups shall be Withdrawn in sequence starting with group.5,gqroup 6, and finally group 7.

,Referred to by TS 3.2. 1.

Regulating rod group overlap.shall be 25*% 5% between two sequentialgroups.

Referred to by TS 3.2A..

Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculations when determining if overap requir6ements are met as these situations are expli"itl*yaddressed by TS 3:1.4, (Control RodGroup Alignment Limits)" TS 3.1.5 (Safety Rod.Position Limits), and TS-3'23:

(Quadrant Power Tilt).

ONEI-0400-70 R.ev 26.

Page.6 Wf 33 O0

-nee 3Cycle 24 EFPD 0 to.,446.

446,t0 EOC Core Pawer Level, %FP

Bukof Ciore

,Bacdkup moorea Steady State Operating rBand Ro,d Index APSR %WD Min.

Max, Min Max.

2922,+/- 5 300.

30 40 292 5 300 100 100.,

Quadrant Power ýTilt.S.etpoints,:

3,50 7.61-T.11 t9.0 2.25.

387 3.63,,

4v81-Referred to-jbyl TSjs3.2:31 Maximum 100 14.22 10.07 CorrelationoSlope *(OS)

Referred to by S3.3-1.1ý (SR 83318.3)...

ONEI-04O0-0o Rev 26 Page 7 of 33; Ocp-nee 3 Cycle 24 Variable Low RWDS Pressure RPS Setpoints ReferTreadtoby TS 3,3.1 2400 P=

.2355: pS ig T=6!8 T =61,89F

230: 0

,2200-Operationi CO:

_-,9

-P'=11I.-14&* TOUt.-.,470 0

11,00 180p-18 000 T =58.4 OF 1700 540 560 580 600 620 640-Reactor-Coolant Outlet Temperature, *F

ONEI-040070 Rev 26 Page.8 of 33 Oconee.3 Cycle 24 RPS Power Imbalance Setpoints 4.Pumps

'% FP 0.0 87-.5 1 07.9

107.9 0..0

% Imbalance

-33.0

-33.0 14.*

33o.0

33.0*

-33.0 14.4 33.0

.330:

.3Pumhps 0.0

'60.2ý 80.6

'63.1

'0.0.

Maiu AllowAble RP PowerIblneLmt 4 Pumps 6 FIP'

'87.1 1:09.4; 109.4-90.0 0.0 Smalanm-

-35.0

-35.G0

-11.4 14.4

- 35.0 35.0 3 Pumps

'0.0 59.4 8,1.7 81.7 0.0

ONEI-04007O Re,vy 26 Page:9 of 33 Qcbonee,:3 Cycle 24 Operatibnail !Power Imbalance.Setp6ints Full Backup

'Out of

%FP Incore Incore Core 4 Pumps Ao0

-28&0

-28.0

-28.0 8.>0

-28.0o

-28.80

-28.0

.90.0 25,4 25.44 100.10

-114.7

4.

14.7.

102,.

-12.6 6 6126 102.0 15.7 15.7 1i5.7 100 17.8, 1 7.ý

.17.8

~~9O.0 28-0 280280 80~0 8.0 2.0 2.0 0.0 28.0 28:0 28.0M 3 Pumps 0.0

-28.0

-28.0 6*0i.2.

-28:0:

'.28i.0 60.2 28;0 7!.0o

-10.2-

-10._2, 0

TO:

1:34.2, 132 13.2 63.1 28.0 631:

28.0 28.0 0.0 28.0 28..0 28.0

ONEI-0400.70 Rev 26 Page 10 of 33 Oconee.3 Cycle 24 Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOCto.EOC

%:FP:

RPS Trip Full lhcore Alarm

Out of Core Alatm 1.07.9 1i07.0 1!06.0 105.0 104.0:.

103.0 102.0*.

1101.*:

100.0,

99.0

,98:0:

971.0 96.0 954:0 93.0.

92.0:

87;5

87.'0

86.0J 8.04

8,3 ;,0 0830 81.0 8020 0.0 12.3

-13.4[

.14.4.

-1164

-17.S

-1:8.7 A19'.7

-20.8

ý!32..5

-33.10 233-01

-37:2

-310

-33 '0:

-3320

-33.0 14..4:

15.4, 16.4.

17.5 18.5 19.6

.20.7

,2'1.7:-

,22.8

?:93,1' 24,9.

26.0-27*.0 29.2

.30:2

.31.3 32.3 33.0

33. 0 33&O 33.0 33.0 33.0 33.0 333.0 33.0 3.3.0.

33.0

33.0 33.0

-'12:6:'

-,13.7*

ý-14.7-

-15,:8*

-16.9

--A7:9'ý

-20.1

-*21.1

-22.2'

-23.*2

-24.3 w-25'04

-25;6

-25.9

-26.0

-26.2

-26.4.

-26.7

-.,26.9

-27.2

-27.7

-28.0

-28.0 1"5.7 16.7 1738 1*8.8 1 98 2ý2.9 23.9 2:6.0Q 27.0' 27;.6 28.0 28.0 28.0 28'.0 28.0 28.0 28.10 28.0 218.0' 28.0.

28.0 28.0:

28.0

-12.6

-14. 7 4,13:5.8

-16:9

-A9.0

.,22.2:-

-23.2

-2,4.

-25.0

-25.4

-25!9

ý2&0

-26.2

-:26.4

-26.7

-26.9

-27.2

-27.5

-27.7

-28.0

'*15.7" 1.7:82 20.9

,24.9',

26.0 27.0

'28.0 28.0 p28.0..

28.0:

.:,2*;

28.0

% FP RPS:Tdp Full Incore Alarm Out'of Core:Alarhm

ONEI-0400-70 Rev 26 Page 11 of 33 Oconee 3 Cycle 24 Operational Power Imbala.n0ce Setpoihts Operation with-3 ROS Pumps. BC toEOC

% FP RPS Trip Full* Incore Alarm

._ut.:f_

_CoteAlam 80.6!

1:.4 14.4 800 1'2.0D 15.0 79*O.

-!3*0 16.1 78.0:

"-l4i 17.1

77.

-52 18.2

-10.-2' 1,3.2

-1.50.2 13.12.

6 76.0

-.:2 19.3

-11.21 14.3.

-112 14.3 "75*0

-17.3 20.3

-12.3 5.3

-Z..3

&'45 -1'8.3 21.4

-13.3 16.4

-13:3 1.4 73.0

-19.4

22.

-14.4 1.74

.14."4.

17:4, 7*1,.0

-2;-5 24.6

-616.5.

19.6

-16.5 1.9.6 7_0.0

-22.6 25.6

-t17&6 20.6

-7.056:

69.0i

-23.7 26;7

-18.71

,21.-7

-18.7 21.7

`68.0

-ý24.7 27.8 19.7

2.

-19.

22.8ý'

67.0

-2..8,28.8 20..8

.223.8

,65.0:

-27.9 30.9

-22.9 25.9

.64.0 29.0 32.0

-24ý0.

27.0

.-24.0 27.0.

'63;-1

,-.30.Q0 33.0

-25.0 280

-25.0 28.0

63.

-30.0:

33.0 25.0 28a.0

-25.0 2.0o 62.0.

31.1 33.0

-26.1 28.0

-26.1 28.0, 61.i"0

-32.20 33.0 0

-27.2 428.0 602

-3.0.

33.0

-28.0 28.0

-0 28.0:

.60I0

-'33.0 33.0

-28.0 28.0

-28.0 28.0 0.0

-33.0 33.0

-28.0 28.0:

-28;.0

-28.0

%FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-70 Rev 26 Page 12 of 33 Obonee 3 Cycle 24 RPS. Power Imbalance Setp0ints.

Referred to by TS 3.3.1 Thermal Power Level, *0iFP 120.0

(-1.4,1 Ml = 0.942 i(,- i 33.i:!,0,87. 5)

(-1.;0 6) 7T9).

(14.4,1.07.9)

.100.0

-M2 =-0942.

Acceptablea4.Pump.Oieration (14.04,Y.6

(-33.0#60.2).

60"0 -

240:0 -

(33;O,63.1) l I

I l

I I

r I

0

-40.0

-30.0

-20.0

-10.0 0.0 10.0 20.0 30.0 40.0 Percent Power imbalance

ONEI-*-70 Rev 26 P -age 1.3:of 33; Oconee -:Cyce i24 Imba~an ý.Setp i n ts f or 4 Pum Oertlon, BOt EO-C 110.0 100.0 90.0 80;0-70.0 a-ýWo2.

40.0ý 30.0 20.0 10.0 0o.

RPSTrip':Setpoint RPS Trip Setpoint In~ore & Outcore Alarm;.

z_ Lc-4~+..4 ~

-40,

-3 5..

.3 0

-25

-20:

1,;5,- -10i

.5 0

5.

10..

1.5 20 25:

Percen't AxfAl Imbalance.

30 i35 40

(

O ONEI-0400-70 Rev 26

.Page-14 of 33 Oconee.3 Cycle 24 IMbalNihe" Setpilht, Pump Operaftion, BOO" toSEOC U) 0 0~

LL

'I, 0

U)a-t1T0 100 90 80 701 60 50

.40

30

20 10b

.0' IIII 11 A4-7~1 ~

s

r.

i iSe.point RPS Trip Setpoint -

In:o.e.& Out.,r Alarm IIIII 4-i i

-4.0

-35.

-30

-r25

ý

-20

5

-10 iB j

.5 0

5 10 15 20 25 Percent 11 Axba

'Iiban 30 3,5-40

ONEI-0400-70 Rev26 Page 15 of 33 Oconee 3 Cy.cle.24 4 Pumps 3 Pump O:perational Rod Index Setpoints RI Insertion Setp8i4 t

%FP No Inop Rod, 1 hop Rod 102.0 263.5-

.283.4 1.000 261..5-

281.5i

.90:0

.251.5:

271.9

!8.0 251.5

262.3:

50.0, 201.5 23.

48.0f 1952.2 231.5-130 76.5:

161.15 3.101.78 2.8

.0 74.81

.i0; 0

0.0:S

!351.

RI Withdrawal Setpoint 300 300

.300 300.ý

.300ýýo 300

3 0 300

ý300 300

.,3-00

-300 8.00

-300 300 300 3000 300

.300 300'-

770 75.0

50.0:

480A 15,0 5.0 3.0 2.8 0.0 246.5.1 243.2:

201.5 195.2 76.5 16.5 1.5 0.0 0.0 2,35.2 165.5 93.5 76S5 74.8 51.0

ONEI-0400-70 Rev 26 Page 16 of 33 Qconee ix3 Cyc e

ti24

'Shutdown MarginýRod ýInd~ex-Se6tpoints 4 Pumps

%FP 102.0 100.0 48.0 13&0 3.0 0.00 77.0 75.0 48.0 13.0 2.i8 0.o RI Insertion Setpoint No-lhop Rod-1.1i6p Rod

.224.6 283.4

22145 281.5 141*!:5 i2,31.;5.

76.5&

161.5 1.5' 76.5 OZO 74.8 0.0:

51.0k RI Withdrawal Setpointý 300 300

-300.

300 300

30Q

'300 300

,3001

300)

300:

`227.4 221.5 141.5

-76 0.0 0.*,0

285.2

231.1: 5 5-15 51 o

Oconee.3 Cycle:24

Rod Index::Seitpoints 4-Pump Operation. No Inoperable Rods, BOC to EOC ONEI-0400-70 Rev 26 Page 17.of.33

'Shbtdown Margin Setpoint

.OPeratibnaAlarm Setpoint.

%FFP CR`.GP:5:

CRGP.6 CRGP7

.CGP5

'CRGP6 CRGPR 7 102 100 99.8' 24.8 1.00 100 63.5" 101 100 99.0 24.0 100 1.00 62z.

100 100 98.2

232, 100 100.561 99 100 "

97.5, 22o5 100 100 60.5, 98 1006--

_ 96.7 21.7 1"00:

100 59.5 97 100.

95.9 20.9 100 100 5&.5 96 100 95.2 20.2 100 100 57.5 95 100 94.4 19.4 100 10,0 56.5:

94 1 *0 93.6 118.16 0

100 55.5--

93 100 92.9 17,9 1

100.

54.5 92 O0 92.1 17.1 1100 535.

91 100 J

91.3 16.3

'100

10. 0

52.5 90, 100.

.90,.6*

15.56

100, 100 51.5 89

'100...

89;8:

1,4."18

. 100 100 51.5 88

.10 o89.0

.0 100 100 51.5 87 100 8.*

8.2..

13.20

1500, 51.5 86 100 87.5 125 100 10 5..

.5

85 100 86.7 11.7 100,.

100

.5.5 84 100 85.9 10o.9 10o 100 1.5 83 100 s85.2 102...

100 10

.51.5

82.

100 84 9.,4 100 1,00

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CRGP7,

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Shutdown Margin Setpoint.opkerational Alarm S.etpoint RI = 300is.withdrawal limit at all power levels.

Continued on next.page..

Oconee:3 Cycle.24 Rod Index Setpoints 4 Pump Operation, No Inop*rablle Rods, BOC to EOC ONEI-0400-70 Rev. 26 Page 18 of 133 Shutdown MdijSe*t OpeationalAlarms etpoit.

%./FP CRGP 5 CRGP.6 GRGP7

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_ Shutdown Margin Setpoint Operati*nal Alarm Seto int RI = 300 is withdrawal limit at all power levels.

Ooenee 3 Cycle 24 Rod. ln.dex.Setpoints.

3 Pump Operation; No Inoperable Rods,. BOC to EOC

.ONEI-0400-70 Rev. 26 Page. 19 of 33 Shutdown :Margin-S tpoiht OPe0ationaI Alarm Setppint

%FP CRGP;5 CRGP6_8.

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Shutdown Mafrgin.. Setpoint Opepratonal.Alarm"Setpoint, RI = 300 is.withdrawal limit at all power levels C6ontinuedl on next page.

'Oconee.3 Cycle 24 Rod Index, Setpoints 3 Pump Operation, No Inoperable Rods, BOG to EQO ONE0400-70 Rev 26 Page 20 of33 Shutdown Mairgi-n Setpoint:

.Operatioal Aoarm*Seoint.

%FP CRGP5 CRGP6 CRGP77 CRGP5

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Soint Operational. Alarim Seztpobint Rt= 300 is withdrawal limit at all power levels.

Oconee 3 Cycle 24 Rod in,dex Setpo.ints 4 Pump Operation, 1 Inoperable Rod, B.OC to EOp ONEI-0400-70 Re*v26 Page21 of 33.

Shutdown MarnSetpoint

_OperationaI Alarm setpoint

% FP ORGP5 CRGP'6.

CRGP7 CRGP 5:

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_Shutdown Margin Setpoint.

Operational Alarm Setpoint RI.= 300 is withdrawal'limit at all powerlevels:

COnti.nMad-onnext.page; -

Oconee 3 Cycle 24.

Rod Index Setpoints 4.Pump.Operaltion, 1 InopeTrable. od,- BOC. to EOC ONEi040'0-70 Rev 26:

Page 22 of 33 ShutdoQ Margin Set~~

t QpeOAti6nal Alarm S0tpint.

%FP CRGP5 CRGPB6 CGP.7.

CRGP 5

.CRGP.6 CRGP7 47

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%DFP CRGP5 CRGP 6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Op0eratibnal Alarm Setpoint RI = 300 is withdrawal limit at all power levels.

Oc6nee 3 Cycle 24 Rod Index Setpoints 3 PumprOperation, 1 Inoperable. Rod, BOC to EOC ONEI-040p-70' Rey 26' Page23bf o33 Shutdo*n Margin Setpoint QOppratin.al Alarm Setpoint.

%.FP GRGP5 CRGP:6.

GRGP7

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C

'Continued on next.page.

Oconee 3ý Cycle 24 Rod Index Setpoints

.3 Pump Operation,,.1 Inoperable. Rod, BOC to EOC ONEI-0400:70 Rev 26.

Page 24 of 33 Shutdo W6Margj'Sqetpint O.eratioinal-Al~ar.SAe*0tt

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CRP 7 Shutdow Mar~qin:Setpoint Operational Alarm Setpo~int -

RI = 300 is-withdrawal limit at all power levels.

0 0

ONE-02400-70 Rev 26 Page 25 of 33 d

coe 3," YCyce- ~4

~1!

105.

-iinn t 9 50.1 14111 L

~Th~i1T

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Control Rod Posthion Setpdjnts N nperable R~o ds, 4Pump lo Restricted Op~eration 90

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tt1.1 NTNr EF:

H"7 H

1.05 100 95 90 85 80 75 7.0.

65.

60 55:

50.

45.

40 35 44~1 4i=

,U-0.r) 0."5 0'

Ii 1Ir Accepts Operatic

35 25 20 15 10 5

0 I

14 T!

4I~

1-4 Hr

[V 730 25

~1 10+/-1 i"*I+/-44

~W H

.42~ 0 Group.6

5 15 25 35 45 55 65' 75, R8i IS 25

35, 45-56' 05

&5 05 I-IT Ii

,4a 1o jO 20

,3o 4050

.o 70 80 90, 100, I l 10.20 30 40 50 60, 70; 80 50 I~roup 80

,90 100 I I

Conitrol Roid Position, % W

Ocone.e 3 C yce24 1*

ONEI-O4O. Rev 26 Page 26 of 33 m

n I, an..

L

'1

.a LL 0a-0,3 105 100 95'

.90 85 80 70 65 60 55 50 45:

40,

.35:

.30 25 120 "10 5

if, Control Rod Position Setpolntsi I

No-Inoperable Rods, 3.Pump Flow I

it.

L*J*r 144 Unacceptable Operation i¸,i i

it I Alt +3; in

-ý'

ý11 4

]:.r, 1*00 95 90 85 80 75 70 65 60 55 50 45 40.

35 30

.25:

20.

10.

4 Rest~lcted Operatl6n Acceptab!e OperatiOn S4.

im*

1 11 i 10"

+41 I

it 5

5 1..

..l5 :

25 35:

=

RR; Q.*;

0 L!+/-U 15 25 45':

75 85 95 I'Ii 1.0 10 20

.30 401ý 50:

UZ4 0 I

60.

70 80 90 100

1 0

10T 20 30 40

,5 6,0 7080

90 100 I I Gýroup:*051

.1 50 100 1 I

I Grouqp I Co ntrol-Rod Poition !,

% WD

io~e3 Cycl k24 ONE170400-70. Rev. 26 Page 27 of 33 105 100 95 90 85.

80 75:

70 65 0~

CL 460 55 30

25.

.04 35 30

'25.

.20" 15!

10o 5

0 I

control Rod Positfion Setpnt F F

F: :t "I

. p o in's' a 1 Inoperable: Rod, 4 Pump Flow 4444.

Y j Tr+r

Unac~ceptablie 7Oper1tto S cceptab=le otlOperation

44 147 i -i *.....i-ri c t

F

=

F 5 :;151 i :253 :5 45

!55:i i~65 75 85..

,95:....

'ILI I!

-PI 105 100 95 90 85 80 75 70 65 60 55 50 45 35*

30 25' 15 5

0 i'..

k

. :.,,I; T

10 110.

20 30

....0..

60

O7 80 6

9 0o

1OO, 10 10.

2 3.0 40:

`50 60, 70 890

ý90. 1:00 I GroupS Group7 Contro IRo~d:Positon % WD

0

-INEI-04,0070 Rev 26 Pag~e 28. of 33 I

ii iiii I I I I 1[ 1 1 1 06 Ocnlee Ci~e 24 I.

105:

1900 95.

80

75 70:

65a Control Rod Position Se.tpp"is 1 Inoperable, Rod, 3 Pum~p.FIO.w W-

- `V+!HHH

H 14 4t

+44 --

4H*h*

Uriacceptable Operation 1.05 100 95 90 85 80, 75 70 65 60 55 50.

45S 0*

.0 a.

0 ca-

[}*!

60 55

.50

ý45.

-40; 35.

.30 25.:

11 i

Acceptable

':,Oper~ati~on ALU-~i+/-II.

I I 4' 0

!+/-

35, 30 25 ItI IM

!20.

10. i Lý LL I-444I 4111 ""

iiI i Uroup S 45ý 55,6 i

I I 20.

15

.5 0.

00.

ýz i;p ill`;;ý25

".. 1. -, I -11

- ý..........

jj ý.'Wjj--

14 1.- +1.11.11---4" Z!jk--

'--ý I

ýL 10 10 2Q 3040 50 60 708*0 90 IGroup-S 1 :

20.,

30 40 50 60 70

80:

.90

.1.

IGroup,77 bConttol Rod PWoDtion,,% WO

ONEI-0400-70 Rev 26 Page 29 of 33 Oconee 3 Cycle 24 2.0. Core Operating Limits Not Error Adjusted The data provided: on the following pages satisfiesýa Iidensing commitment toidentifyspecific parameters beforedinstrumentation uncertainties arehirpjorated.

References provided in section 1 of this COLR ied.ntify thesources for the datawhich follows.

Core Power LeveLA Qu :rntPwer Tie Core Out!

p 1:

,2.

2-2":

%FP 3(

It, %

hudat PoWer.Tilt Limitsb Referred ~to. by:T.S,3.2.3 1:00, 0"30 30 1'

'5.40 10.00 9.44 ransient:

0 D-.30 i2.00 20..11,00 eVariablierLow F1S Pres.ure P Limits Rleferred t yT etePressurea FRectorCoolant Outlet eemperature, :-F sia 3R.CS P*mp 4

'.RCS Pumps 80&

581.0 578.3:

900.

590'0 587-.3:

200.

598.9; 596.3 1i00 607.69 6,05.2 200 616.9 614.2 300 625.9 6232.

ONEI-0400-70 Rev 26 Page 30 of 33 Oconee 3 Cycle 24 Axial Power Imbalance Protective Limits Referred to by TS 2.. 1.

4 Pumps

%FP 80.0 87--.1 4O0 1,09.-

109.4 100.,0 90'.0 80.0 0.0.-Q 5%9.4 77.0 77.0

'0.0-RP$ Op~pal.na :0

-35.0

-31.4 35.0

35:01

-39.5 78:

39.5 39.5*

39.5

-39.5.

-39.5 39.5 39.5

ON EI-0400-70. Rev 26 Page 31 of 33 Oconee 3 Cycle 24 Rod Inde'xLimits$,:

ReferredtO by TS 3;2.1

Oerational RI ShutdMowniMargini RI.Insertionimit

%FP ný Inse'in Limit 'No ko Ro hopý Rod

-4 Pumps 3 Pumps 90;

-80' 50, i5-5 77 50 15 5-

ý26-2 260-

.250 0ý 245 06

22,0

-i40:

.2209 75

0 230 280 160.

75

.RI Withdrawal limit 3WQ 300.*

300:

,3001

300*

ONEi-0400-704 Rev 26 Page 32 of 33 Oconee 3 Cycle,24 OAA Limiits CdrerElbvation Feet LQCA LhIR kw/ft Lmit Versus Burnip Mk-8B11 Fuel*

0-.000" O.O0;6

77791, 9.536ý 12.00:

17716 0 GWd/rritU 14.9, 145i 40 GWd/mtU; 17.5 17t6 17.7 17.6' 17.5 40.GW-d/mtU 14.9

'11 5 `8 151.7'

,14.9 62ýGW/MtU 12.2 12.2

-~/-

"11 *0 12.2 1:1.0*

WH-177 Fuel 0.0001 2.506 4.264 6.021 7.'679

N6tef&or,03C24ý7>The four B1oIting~ncy' 2.0 wt% Mk-B1'1 feed assemblies-used in this ccehv nlidLOAiit.The: penalties ar.eaccounted for in the appl6icationgof the abov limits to the-contingency assemblies,as described in the MA.*

ONE.I-0400-70 Rev 26 Page 33 of ý3

Ocoriee 3 Iycle 24

" I.

4 RCi p.--.a.

PAoop Ve..ge-T*P..

.1F 3-CP pe.....

ibtio ege'Temp "..f 0-

-<5:8JQ....

.. o

!11.*

.0.2.

8.<

1.0-<5810

0.

.8...

.158. T, 0.4

~~<581.2

8.

.0.*5

<58 1.2 8..

.1*

. 1..

o6.

.081,2

,.581

7 8..3

<8.,<58112 A9.83,13 5..

0.

<581Y3

<581a.

1.9

.414 5i 1 :"

81,i...... :"

,,581:2

.2.2

.:!.5 581 S *1.3 583,5"...

,.~581*3:

1.4'

<581.5...

,5.3 15

<581.6

<581_3 71.6

<5

'¢81.6"....

581,4'

..."1h7.

"8L6

<:581*.4.

...5.177.58.4 Z8.9.81.7

<5818.4 120

<581.8 *"..

32.2

-<5818

<5815.

25

<:5820 J..5816 26,

<820 58A 2.8

,68241

'<58.!

2.9 0582:

dg<5816 3.02<8.

<581.7

.3.1 582.W<8.7.

.9.

424.

<5,82.2r

<582.)

339

<82.3

<582:.0 3.4

-.6 582:

3:5

<582,8:

<-5812..

3:6

<5*82.4..

<81:

4.9,

<582.9<581.

45.

<5 82-:6

-<5821j 4.2

<582.6'

<58,!L9..

4.3

'582.,6"

<58,1.9:

' 4:4

.<582.7 "582:0:

4.5

<582.7.

<5*82.0:

4.6

<,*582.7l:

<582.0 4.7

< 582.*8.

r

<582 0 4.8

..<582.8

"<-582.1" 4..9

<'582.9"

<582'.1 5.0.

<582.9:

<582.1

ML073450097

Text

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