GO2-05-148, Cycle 18 Core Operating Limits Report Revision 1

Cycle 18 Core Operating Limits Report Revision 1

ML052510510
Person / Time
Site:	Columbia
Issue date:	08/30/2005
From:	Coleman D Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-05-148
Download: ML052510510 (61)

Text

E ENERGY NORTHWEST People. Vision- Solutions P.O. Box 968

• Richland, WA

• 99352-0968 August 30, 2005 G02-05-148 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397; CYCLE 18 CORE OPERATING LIMITS REPORT (COLR),

REVISION 1

Dear Sir or Madam:

Inaccordance with the Columbia Generating Station Technical Specifications (TS) 5.6.3.d, Energy Northwest herewith submits the Cycle 18 COLR, Revision 1. The operating limits in the COLR were developed in accordance with the requirements of TS 5.6.3.a, b,and c.

The changes to the COLR have been reviewed by the Columbia Generating Station Plant Operations Committee.

Should you have any questions or desire additional information regarding this matter, please contact me at (509) 377-4342.

Respectfully, DW Coleman Manager, Regulatory Programs Mail Drop PE20

Attachment:

Cycle 18 COLR, Rev. 1 cc: BS Mallett - NRC RIV BJ Benney - NRC NRR NRC Senior Resident Inspector - 988C JO Luce - EFSEC WA Horin - Winston & Strawn RN Sherman - BPA11399 Ax)

COLR 05-18 Revision I Columbia Generating Station Cycle 18 Core Operating Limits Report July 2005

Columbia Generating Station Cycle 18 Core Operating Limits Report List of Effective Pages PAGE REVISION I.............................................................................................................................................0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10 .0 11 .0 12 .0 13 .0 14 .. 0 15 .0 16 .0 17 .. 0 18 .0 19 .0 20 .0 21 .0 22 .0 23 .0 24 .0 25 .0 26 .. 0 Columbia Generating Station LEP-1 COLR 05-18 Revision 1

lUL 27 0 28 0 29 0 30 0 31 0 32.:.......0 33 .0 34 .0 35 .0 36 .0 37 .0 38.;;....

39 .0 40.;.....0 41 .0 42 .0 43 .0 44 .. 0 45 .0 46 .0 47 .0 48 .0 49 .0 50 .0 51 .0 52 .0 53 .0 54 .0 55 .0 56 .1 Columbia Generating Station LEP-2 COLR 05-18 Revision I

Columbia Generating Station Cycle 18 Core Operating Limits Report Table of Contents 1.0 Introduction and Summary .............................................. 1 2.0 Average Planar Linear Heat Generation Rate (APLHGR) Limits for Use in Technical Specification 3.2.1 .............................................. 4 3.0 Minimum Critical Power Ratio (MCPR) Limit for Use in Technical Specification 3.2.2 ............................................. 12 4.0 Linear Heat Generation Rate (LHGR) Limits for Use in Technical Specification 3.2.3 ................... 51 5.0 Oscillation Power Range Monitor (OPRM) Instrumentation Limits for Use in LCO 3.3.1.3 .............. 55 6.0 References .;.............. 56 Columbia Generating Station i COLR 05-1 8 Revision 0

1.0 Introduction and Summary This report provides the Average Planar Linear Heat Generation Rate (APLHGR) limits, the Minimum Critical Power Ratio (MCPR) limits, the Linear Heat Generation Rate (LHGR) limits and the Oscillation Power Range Monitor (OPRM)

Instrumentation limits for Columbia Generating Station Cycle 18 as required by Technical Specification 5.6.3. As required by Technical Specification 5.6.3, these limits were determined using NRC-approved methodology and are established so that all applicable limits of the plant safety analysis are met. References 6.1, 6.2, 6.3, and 6.4 describe the LOCA analyses for rated power. These analyses were performed with methodologies that result in Single Loop Operation (SLO) APLHGR limits as well as Two Loop Operation (TLO) APLHGR limits. The thermal limits for ATRIUM-1 0 fuel given in this report are documented in Reference 6.3. The MCPR limits for the SVEA-96 fuel are also documented in Reference 6.3. The APLHGR and LHGR limits for SVEA-96 fuel are documented in References 6.1 and 6.6. The basis for the OPRM Instrumentation limits is documented in References 6.3 and 6.5.

The MCPR limit is the maximum of (a) the applicable exposure dependent, full power and full flow MCPR limit, (b) the applicable exposure and power dependent MCPR limit, and (c) the applicable flow dependent MCPR limit specified in this report. This stipulation assures that the safety limit MCPR will not be violated during steady-state operation and anticipated operational occurrences throughout the Columbia Generating Station operating regime. Full power MCPR limits are specified to define operating limits at rated power and flow. Power dependent MCPR limits are specified to define operating limits at other than rated power conditions. A flow dependent MCPR is specified to define operating limits at other than rated flow conditions. The reduced flow MCPR limit, set by the limiting Recirculation Flow Increase event, provides bounding protection for all events at reduced flow.

The reload licensing analyses for this cycle provide operating limits for Extended Load Line Limit Analysis (ELLLA) operation which extends the power and flow operating regime for Columbia Generating Station up to the 108% rod line which at full power corresponds to 88% of rated flow. The MCPR limits defined in this report are applicable up to 100% of rated thermal power along and below the 108% rod line. The minimum flow for operation at rated power is 88% of rated flow; the maximum is 106%.

The specific topical report revisions and supplements which describe the methodology utilized in this cycle specific analysis are shown in Table 1.1.

Columbia Generating Station COLR 05-18 Revision 0

--- lWILL Table 1.1 Columbia Generating Station Reference Topical Reports

1. XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

2. XN-NF-85-67(P)(A) Revision 1, Generic MechanicalDesign for Exxon NuclearJet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.

3. EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-MechanicalEvaluation Model, Siemens Power Corporation, February 1998.

4. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic MechanicalDesign Chteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

5. XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

6. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

7. EMF-2158(P)(A) Revision 0, Siemens Power CorporationMethodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

8. XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

9. XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-HydraulicCore Analysis, Exxon Nuclear Company, February 1987.

10. ANF-524(P)(A) Revision 2 and Supplements I and 2, ANF CriticalPower Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

11. ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Programfor Boiling Water Reactor TransientAnalysis, Advanced Nuclear Fuels Corporation, August 1990.

12. ANF-1358(P)(A) Revision 1, The Loss of FeedwaterHeating Transientin Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.

13. EMF-2209(P)(A) Revision 2, SPCB CriticalPower Correlation,Siemens Power Corporation, September 2003.

Columbia Generating Station COLR 05-18 Revision 0

14. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.

15. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.

16. EMF-2292(P)(A) Revision 0, ATRIUM. -10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

17. EMF-CC-074(P)(A) Volume 4 Revision O, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

18. CENPD-300-P-A, Reference Safety Report for Boiling Water Reactor Reload Fuel, ABB Combustion Engineering Nuclear Operations, July 1996.

19. NEDO-32465-A, BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, August 1996.

Columbia Generating Station COLR 05-18 Revision 0

2.0 Average Planar Linear Heat Generation Rate (APLHGR) Limits for Use in Technical Specification 3.2.1 The APLHGRs for use in Technical Specification 3.2.1, as a function of Average Planar Exposure, shall not exceed the limits shown in the following figures. Note that the APLHGR limits for single loop operation for ATRIUM-10 fuel are obtained by applying a 0.9 multiplier to the two loop operation APLHGR limits.

a. Figure 2.1 - SA- and SB-Type SVEA-96 reload fuel - Two Loop Operation

b. Figure 2.2 - SA- and SB-Type SVEA-96 reload fuel - Single Loop Operation

c. Figure 2.3 - SC- and SD-Type SVEA-96 reload fuel - Two Loop Operation

d. Figure 2.4 - SC- and SD-Type SVEA-96 reload fuel - Single Loop Operation

e. Figure 2.5 - SE- and SF-Type SVEA-96 reload fuel - Two Loop Operation

f. Figure 2.6 - SE- and SF-Type SVEA-96 reload fuel - Single Loop Operation

9. Figure 2.7 - ATRIUM-10 reload fuel

., .,, s Columbia Generating Station COLR 05-18 Revision 0

in l 9.8 9.6 9.4 9.2 8E.8 3

a 8.6 8.4 8.2 8

7.8*

0 10000 20000 30000 40000 50000 60000 Average Planr Exposure (MWdUTU)

Average Planar Exposure MAPLHGR (MWd/MTU) (kW/ft) 0 9.6 5000 9.5 9000 9.3 12000 9.2 16000 8.9 20000 8.7 30000 8.6 42000 8.6 50000 8.5 59000 8.0 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure - Two Loop Operation SA- and SB-Type SVEA-96 Figure 2.1 Columbia Generating Station COLR 05-18 Revision 0

WILL 10 9.8 9.6 9.4 9.2 F9 o

(38.8 4 8.6 8.4 8.2 8

7.8 7.6 20000 30000 40 60000 Average Planar Exposure (MWdUTU)

Avefaige Planar 1 Exposure MAPLHGR (MWd/MTU) i

,kW/ft)

. 0 . 93 .

5000 . .9.2

- 9000 . 9.0 12000 .,. 8.9 16000 8.6 20000 - 8.3 30000 8.3 42000 8.3 50000 ,:-8.2 59000 -7.8 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure - Single Loop Operation SA- and SB-Type SVEA-96 Figure 2.2 Columbia Generating Station COLR 05-18 Revision o

10 .

9.8 9.6 9.4.

9.2 I 9.1 0 8.8' z

8.6 8.4 8.2 8'

7.8 0 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWdIATU)

Average Plznar Exposure 'MAPLHGR (MWd/MTU) _.- '.'...(kW/ft) 09.8.

0' 5000. 9.9 -

-9000. 9.7 10000 9.6

'12000 . . 9.4

• 16000 . 9.1 1200000 8.9 30000 . 8.8 42000 . 8.8

'50000. . . 8.7 54000 8.5 59000. 8.1 r-.

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure - Two Loop Operation SC- and SD-Type SVEA-96 Figure 2.3 Columbia Generating Station COLR 05-18 Revision 0

'IIIIL 0 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWdMTU)

Average Planar -7

• Exposure )MAPLHGR (MWd/MTU) , . MEW/, )

.0 ° 9.4 5000 .9.6 9000 9.4 10000 .9.3

,12000 .9.1 16000 ... 8.7 20000 8.5 30000 . 8.4 42000 .8.4 50000 8.3 54000 8.2 59000 . 7.9 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure - Single Loop Operation

- SC- and SD-Type SVEA-96 Figure 2.4 Columbia Generating Station COLR 05-18 Revision 0

In -

9.8 9.6 9.4 92 w 8.8 z-I a.

> 8.6 8.4 8.2 7.8 0 10000 20000 300000 . 40000 50000 60000 Average Planar Exposure )MWd.IATU)

Average Planar  ; ;

Exposure MAPLHGR (MWd/MTU) (kW/ift) 0- 94 5000.. 9.5 9000 9.4 10000 - - 9;4 12000- 9.3 16000 - 9.0 20000 - 8.8 30000 8.8 42000.- . 8.7

'50000 .8.6

-54000 8.5 59000. 8.1 -

Maximum Average Planar Linear Heat'Generation Rate (MAPLHGR)

Versus Average Planar Exposure Two Loop Operation SE- and SF-Type SVEA-96 Figure '2.5 Columbia Generating Station . 9_ COLR 05-18 Revision 0

'IIIIU-10 9.8 9.6 9.4 9.2 q9 w 8.8 g 8.6 8.4 8.2 8

7.8 7.6 0 10000 20000 30000 40000 50000 60000 Average Planar Exposure Average Planar Exposure MAPLHGR (MWd/MTU) (kW/ft)

.0 9.2

. 5000 9.3*

--- 9000 - - 9.1 10000 9.1 12000 9.0 16000- -. -.-.8.7 20000 . . 8.5 30000 . . -8.4 ,

42000 8.4 50000 . .. 8.3 54000 8.1 59000 7.9 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure - Single Loop Operation SE- and SF-Type SVEA-96 Figure 2.6 Columbia Generating Station COLR 05-18 Revision 0

Cz

-J Lj 0 10000 20000 30000 40000 50000 60000 70000 80000 Average Planar Exposure (MWd,'MTU)

Average Planar TLO SLO Exposure MAPLHGR MAPLHGR (MWd/MTU) (kW/ft) (kW/ft) o .12.5 11.2 15000 12.5 11.2 67000 7.3 6.5 Maximum Average Planar Linear-Heat Generation Rate (MAPLHGR)

Versus-Average Planar Exposure

ATRIUM-10 Figure 2.7 -

Columbia Generating Station - II - COLR 05-18 Revision 0

_________________ ____________IiiL 3.0 Minimum Critical Power Ratio (MCPR) Limit for Use in Technical Specification 3.2.2 The MCPR limit for use in Technical Specification 3.2.2 shall be greater than or equal to the bounding limits determined from Table 3.1a, Table 3.1b, Table 3.2a, Table 3.2b, and Figures 3.1 through 3.33. For the purposes of cycle extension, the feedwater temperature entering the reactor vessel shall not be reduced to less than 355 0F.

The MCPR safety limit for Cycle 18 is 1.09 for two loop operation and 1.10 for single loop operation. The power dependent MCPR limits (MCPRp) for single loop operation (SLO) include a 0.01 adder to the two loop operation (TLO) MCPR limits due to the difference in the MCPR safety limit.

Columbia Generating Station COLR 05-18 Revision o

Table 3.1a Columbia Generating Station MCPR Operating Limits Two-Loop Operation Core Average Exposures < 29898.6 MWd/MTU SLMCPR = 1 Q9(2)

Condition Limit ATRIUM^10 SVEA-96 Fuel Fuel Full power 1.31(3) 1.31(3)

NSS(') Flow dependent( 5 ) Figure 3.1 Figure 3.1 Power dependent( 4 ) Figure 3.2 Figure 3.3 Full power 1.34 1.33 TSSS(') Flow dependent(5 ) Figure 3.1 Figure 3.1 Power dependent(4) Figure 3.10 Figure 3.11 NSS(') Full power 1.33 1.31(3)

RPT Flow dependents Figure 3.1 Figure 3.1 Inoperable Power dependents) Figure 3.26 Figure 3.27 Columbia Generating Station COLR 05-18 Revision 0

IlllL Table 3.1b Columbia Generating Station MCPR Operating Limits Two-Loop Operation Core Average Exposures > 29898.6 MWd/MTU SLMCPR = 1.09(2)

SLMCPR= 1.09(2) FFTR/Coastdown Coio Core Average Exposures Extended Core Average Condition Limit < 32683.9 MWd/MTU Exposures s 35811.5 MWd/MTU ATRIUM-10 SVEA-96 ATRIUM 10 I SVEA-96 Fuel Fuel Fuel Fuel Full power 1.36 1.33 1.37 1.34 NSS(') Flow dependents Figure 3.1 Figure 3.1 Figure 3.1 Figure 3.1 Power dependent( 4 ) Figure 3.4 Figure 3.5 Figure 3.18 Figure 3.19 Full power 1.39 1.36 1.39 1.36 TSSS(') Flow dependent(5 ) Figure 3.1 Figure 3.1 Figure 3.1 Figure 3.1 Power dependent( 4 ) Figure 3.12 Figure 3.13 Figure 3.22 Figure 3.23 Full power 1.40 1.36 NSS(')

RPT Flow dependents5 Figure 3:1 - Figure 3.1 Not analyzed Inoperable Power dependent( 4 ) Figure 3.28 Figure 3.29 Columbia Generating Station COLR 05-1 8 Revision 0

Table 3.2a Columbia Generating Station MCPR Operating Limits Two-Loop Operation Turbine Bypass System Inoperable Core Average Exposures < 29898.6 MWd/MTU SLMCPR= 1.09(2)

Condition ATRIUM-10l SVEA-96 Fuel Fuel Full power 1.35 1.33 NSS(') Flow dependent(5) Figure 3.1 Figure 3.1 Power dependent(4) Figure 3.6 Figure 3.7 Full power 1.40 1.38 TSSS(') T. Fo e Flow dependent(5) F Figure 3.1 Figure 3.1 Power dependent(4 Figure 3.14 Figure 3.15 Full power 1.39 1.36 NSSMt1 . .. -.

RPT Flow dependent( 5 ) - Figure 3.1 Figure 3.1 Inoperable  :

Power dependent 4 Figure 3.30 Figure 3.31

. .. ......- . I... .

Columbia Generating Station . COLR 05-1 8 Revision 0

I1i14L Table 3.2b Columbia Generating Station MCPR Operating Limits Two-Loop Operation Turbine Bypass System Inoperable Core Average Exposures 2 29898.6 MWd/MTU SLMCPR- 1.09(2)

SLMCPR = 1.09(2) FFTR/Coastdown Core Average Exposures Extended Core Average Condition Limit < 32683.9 MWd/MTU Exposures s 35811.5 MWd/MTU ATRIUM-10 SVEA-96 ATRIUM-10 SVEA-96 Fuel Fuel Fuel Fuel Full power 1.40 1.37 1.41 1.38 NSSO) Flow dependents) Figure 3.1 Figure 3.1 Figure 3.1 Figure 3.1 Power dependent( 4 ) Figure 3.8 Figure 3.9 Figure 3.20 Figure 3.21 Full power 1.43 - 1.40 1.43 1.40 TSSS(') Flow dependent(5).. Figure 3.1. Figure 3.1 Figure 3.1 Figure 3.1 Powercdependent( 4 ) Figure 3.16 Figure 3.17 Figure 3.24 Figure 3.25 Full power .1.44

... ....-1..40.

NSSO)' ' ..

RPT Flow dependent(') Figure 3.1 Figure 3.1 Not analyzed Inoperable Power dependent(4 ) Figure 3.32 Figure 3.33 Columbia Generating Station COLR 05-18 Revision 0

Notes for Tables 3.1a, 3.1b, 3.2a, and 3.2b Note 1: The scram insertion times must meet the requirements of Technical Specification 3.1.4. The NSS MCPR values are based on Framatome ANP (FANP) transient analyses performed using control rod insertion times consistent with the following table. IfTechnical Specification 3.1.4 is met with the NSS insertion times shown below, the NSS MCPR limits in Tables 3.1 a, 3.1 b, 3.2a, and 3.2b are applicable. If the NSS insertion'times are exceeded, then the MCPR limits shall be determined using the appropriate TSSS limits. The NSS and TSSS MCPR limits are based on analyses that account for up to 8 declared "slow" rods, 1 stuck rod, and 1 rod assumed to fail to scram. I Control Rod NSS Position Time (notch) (sec) 45 0.43 39 0.72 25 , 1.60 5 2.95 Note 2: For Single Loop Operatioh (SLO), the SLMCPR increases by 0.01. This 0.01 increase must also be applied to the Two Loop Operation MCPRp 9perating Limit to obtainithe SLO operating limit. :'

Note 3: For the noted full power MCPR limitsjthe Rod Withdrawal Error (RWE) event is limiting. The RWE analysis was, performed with a nominal Rod Block Monitor (RBM) setpoint of 1.06.

Note 4: Power dependent MCPR'limits are'provided for core therrmal powers greater than or equal to 25% of rated pooe'r&at all core flows. The power dependent MCPR limits for core thermal powers less than or equal to 30% of rated power are subdivided by core flow. Limits are provided for core flows greater than 50% of rated flow and less than or equal to 50% of rated flow. A step change in the power dependent MCPR limits occurs at 30% of rated power because direct scram on turbine throttle valve closure is automatically bypassed below 30% of rated power and not applicable per Technical Specification 3.3.1.1.

Note 5: Flow dependent MCPR limits are applicable to both TLO and SLO.

Columbia Generating Station COLR 05-18 Revision 0 '

WILL 0.

I 50 60 110 Flow (% rated)

. . 4 l Flow. MCPRI Il MCPR,

(% of rated) ATRIUM-10 SVEA:-96

..0 1;76 1.76 20 1,76 1.76 30 1.58 1.58 100 1.16 1.16 108.5 1.16 1.16 Reduced Flow MCPR Operating Limit Versus Total Core Flow ATRIUM-10 and SVEA-96 Figure 3.1 Columbia Generating Station COLR 05-18 Revision 0.

2.80 I Two Loop Operation 2.60 2.40 2.20 2.00 0.

4.

1.80 1.60 1.40 1.20 1.00 20 30 40 50 60 70 9D 100 110 Power e%rated)

Power, TLOMCPRFI SLO MCPRp

(%

N -- ...- #-chrit ':Lmit' U

100 - -AM.31 132 65 - 1.46 -1.47-30 -.1.58 1.59 30 at 550% flow - 2.28 2.29 25 at s 50% flow -2.43 -. 2.44 --

30 at > 50% flow 2.36 2.37 25 at > 50% fl' ' 2.47 2.48 MCPRp Limits Versus Percent of Rated Power NSS, ATRIUM-10 Core Average Exposures < 29898.6 MWd/MTU Figure 3.2 Columbia Generating Station - 9 COLR 05-18 Revision 0

IhuIL 2.80 I Two Loop Operation 2.60 240 -

2.20 200 C.)

2 1.80 1.60 1.40 1.20 1.00 . . .

20 30 40 so 60 70 80 90 100 110 Power (%rated) hI Power. 1TLOMCPRp l SLO MCPRp (O/o) Limit 'Limit 100>, 1.31 1.32 65 -1.44 1.45 30 1.55 1.56 30 at 5 50% flow 2.29 2.30 25 at 5 50% flow 2.38 . 2.39 30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 2.54 MCPRP Limits Versus Percent of Rated Power NSS, SVEA-96 Core Average Exposures <c29898.6 MWd/MTU Figure 3.3 Columbia Generating Station COLR 05-18 Revision 0

I2.80 -

s.uw I Two Loop Operation 2.60 2.40 2.20 2.00 U

1.80 1.60 1.40 1.20 1.LUI 20 30 40 50 60 70 60 90 100 110

' mow pirated)

Power I.TLO MCPRl SLOMCPRp

(%) -- Limlit . Limit 100 . .1.36 1.37 65 <'1.46. 1.47 30 . 1.58 1.59 30 at s 50% flow. 2.28 2.29 25 at 5 50% flow 2.43 2.44 30 at > 50% flow . 2.36 2.37 25 at> 50% flow ,. I 2.47 2.48 MCPRp Limits VersLisPreiint of Rated Power NSS,ATRIUM-7 0 29898.6 MWd/MTU S Core Average" Exposures S 32683.9 MWd!MTU Figure 3.4 Columbia Generating Station COLR 05-18 Revision 0

WIILL i-2.8 An I Two Loop Operation 2.60 2.40 2.20 2.00 a.

EC 1.80 1.60 1.40 1.20 1.00 20 30 40 50 60 70 80 90 100 110 Powef ( %raled)

. .I ..

Power: . TLO MCPRp SLO MCPRP

(%) Limit Limit 100 1.33 - 1.34 65 .1.44 1.45 30 _ 1.55 1.56 30 at S 50% flow 2.29 2.30 25 at S 50% flow . 2.38 2.39 30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 2.54 MCPRp Limits Versus Percent of Rated Power NSS, SVEA-96 29898.6 MWd/MTU S Core Average Exposures S 32683.9 MWd(MTU Figure 3.5 Columbia Generating Station COLR 05-18 Revision 0

I Two Loop Operation 3.60 3.4D 3.20 3.00 2.80 2.60 2.40 2.20 2.O0 1.80 1.60 1.40 1.20 i IY0 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power* l TLO-MCPRp SLO MCPRp

(%) - Lirhit l Lirmit 100 -- 1;35 1.36 65 - 1.51 1.52 30 -1.68- 1.69 30 at S 50% flow 2.90 2.91 25 at S 50% flow - "3.23 3.24 30 at > 50% flow -3.03 3.04 25 at > 50% flow -3;33 .. 3.34 MCPRp Limits Velrsus Percent of Rated Power NSS, Turbine Bypass Inoperable, ATRIUM-10 Core Average Exposures < 29898.6 MWd/MTU Figure 3.6 Columbia Generating Station COLR 05-18 Revision 0

u1L 3.80 l Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 0.

Ma

0. 2.40 I0 2.20 2.00 1.80 1.60 1.40 1.20

i. . n1 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power

(%)

j'TLO MCPRp l Limit '

rSLOLimit MCPRp

-100 .1.33 1.34

.65 1.49 1.50 30 1.63 1.64 30 at s 50% flow 2.98 2.99 25 at S50% flow 3.28 3.29 30 at > 50% flow 3.14 3.15 25 at > 50% flow 3.41 3.42-MCPRp Limits Versus Percent of Rated Power.

NSS, Turbine Bypass Inoperable, SVEA-96 Core Average Exposures < 29898.6 MWd/MTU Figure 3.7 Columbia Generating Station COLR 05-18 Revision 0

3.8 -

.n I Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 a.m U

2.40 2

2.20 2.00 1.80 1.60 1.40 1.20 IM +

20 30 40 50o ' 60 70 80 90 100 110

• Powr ( rated)

P6wer TLC MCPRI3 SLO'MCPR

(-) -. '-Limit . Limit 100 ' .40 1.41 65 -1.52 1.53 30 1.68 1.69 30 at S 50% flow  : 2.90 '2.91 25 at 5 50% flow -. 3.23 -3.24 30 at > 50% flow 3.03 3.04 25 at > 50%/6 flow _. '..3.33. 3.34 MCPRp Limits VersiisPeicent of Rated Power NSS, Turbine Bypass lnoperable,'ATRIUM-10, 29898.6 MWd/MTU S Core Average'Exposures '<32683.9 MWd/MTU Figure 3.8 Columbia Generating Station - 25 - COLR 05-18 Revision 0

_IILIU nD -

I Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 a.

a. 2.40.

U 2.20.

2.00 1.80 1.60 1.40 1.20 1.00 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power l TLO MCPRp 1 SLO MCPRp

(%) . Limit Limit 100 1.37 1.38 65 . 1.49 1.50

30. -1.63 1.64 30 at *50% flow 2.98 2.99 25 at s 50% flow 3.28 3.29 30 at> 50% flow 3.14 3.15 25 at > 50% flow 3.41 3.42 MCPRP Limits Versus Percent of Rated Power NSS, Turbine Bypass Inoperable, SVEA-96 29898.6 MWd/MTU < Core Average Exposures < 32683.9 MWd/MTU Figure 3.9 Columbia Generating Station COLR 05-18 Revision 0

I Two Loop Operation 2.60 2.40 2.20 2.00 0.

0.

0.

L) 1.80 1.60 1.40 1.20 1.au+ .

20 30 40 50 60 70 0o 90 100 Ito

.A *Power (ated)

• Power ' TL6 MCPRp SLO MCPRp

(%) l Limit Limit 100 -1.34 1.35 65 1.47 1.48 30 -'1.61 1.62 30 at s50% flow '2.28 '2.29 25 at 5 50% flow 2.43 2.44 30 at> 50% flow 2236 2.37 25 at> 50% flow :2.47 ' 2.48 MCPRp Limits Versus Percent of Rated Poweir

- TSSS,'ATRIUM-10 Core Average Exposures < 29898.6 MWd/MTU Figure 3.10 Columbia Generating Station COLR 05-18 Revision 0

HIM' 2.80 I Two Loop Operation 2.60 2.40 2.20 2.00 -

C.

1.80 1.60 1.40 1.20 1.00 +

20 30 40 50 60 . 70 80 90 100 110

, Power(% rated)

Power . l TLO MPRp SLO MCPRp (iO) Limit Limit 10i.1.34 65 -1.46 1.47 30 .1.57 1.58 30 at s 50% flow 2.29 . 2.30 25 at s 50% flow 2.38 2.39 30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 2.54 MCPRp Limits Versus Percent of Rated Power TSSS, SVEA-96 Core Average Exposures < 29898.6.MWd/MTU Figure 3.11 Columbia Generating Station COLR 05-18 Revision 0

2.80 Two Loop Operatio n 2.60 2.40 -

2.20 2.00 0.

M0.

c Q

1.80 1.60 1.40 1.20 1.00 .

20 30 40 50 60 70 60 90 100 110

"'_ PWir(%rated)

Power' TLO MCPRp SLO MCPRp

(%) imit Limit 10o0 - 1.39 1.40 65 11.47 1.48 30 '1.61 1.62 30 at S 50% flow - 2.28 2.29 25 at s 50% flow 2.43 2.44 30 at > 50% flow . .2.36 2.37 25 at > 50% flow ..2.47,., 2.48 MCPRp'Limits'Versus Pericent of Rated Power" '

TSSS,-ATRlUM-1 0 29898.6 MWdIMTU < Cbre Average Exposures< 32683.9 MWd/MTU Figure 3.12:'

Columbia Generating Station COLR 05-18 Revision 0

_ _ _Un-L 2.80 Two Loop Operation 2.60 2.40 2.20-2.00-O.

¢ 5.

0 1.80-1.60 1.40 1.20 1.00 20 30 40 50 60 70 80 90 . 100 110 Power (%rated)

Power TLO MCPR'-l-SLO MCPRp

(%) . Limit Limit 100 1.36 1.37 65 1.46 1.47 30 1.57 1.58 30 at s 50% flow 2.29 . 2.30 25 at s 50% flow 2.38 2.39.

30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 2.54 MCPRp Limits Versus Percent of Rated Power TSSS, SVEA-96 29898.6 MWd/MTU S Core Average Exposures 532683.9 MWdIMTU Figure 3.13 Columbia Generating Station COLR 05-18 Revision 0

I Two Loop Operation 3.60 3.40.

3.20 3.00 2.80 2.60 C.

0.

0 2.40 2.20 1.80 1.60 1.40 1.20 20 30 40 50 60 70 80 90 100 110 Power (#rated)

Power 1TLOMCPRp SLO MCPRp

- (  % - Limit L ILimit 1 1o o -- .40 1.41 65 -1.54 1.55 30 -1.i2 1.73 30 at 5 50% flow 2.90 2.91 25 at S 50% flow '3.23 3.24 30 at i 50% flow - -. 03 3 04 25 at> 50% flow -. '3.33 3.34 -

MCPRp Linits Versus ercent of Rated Power TSSS, Turbine Bypass Inoperable, ATRIUM-10 .

Core Average Expo'sures< 29898.6 MWd/MTU Figure 3.14 Columbia Generating Station COLR 05-18 Revision 0

I ELI 3.80 l Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 20 30 40 50 60 70 80 90 100 110 Power (%rated)

PoWer TLO MKPR! 1 SLO MCPRp

(%) Limrit Limit 100 1.38 1.39 -

65 1.52 1.53 30 1.68 1.69 30 at S 50% flow 2.98 2.99 25 at s 50% flow 3.28 3.29 30 at> 50%flow 3.14 3.15 25 at > 50% flow 3.41 3.42 MCPRp Limits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, SVEA-96 Core Average Exposures < 29898.6 MWd/MTU Figure 3.15 Columbia Generating Station COLR 05-18 Revision 0

3.80 ITwo Loop Operation 3.60 -

3.40-3.20 -

3.00 -

2.80 -

2.60-C.

U 2.40-2.20.

1.80 -

1.60-1.40.

1.20-1.00 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power l TLO MCPRp SLO MCPRp

'(%)l - .'_ __ Limit Limit 100 - 1:43 1.44 65 -1.54 - 1.55 30 1.72 1.73 30 at5s50% flow 2.90 2.91 25 at s 50% flow -3.23 3.24 30 at > 50% flow -3.03 3.'04' 25 at > 50% flow .3.33 -- 3.34 :

MCPRp Limrits Versus Per'cent of Rated Power' TSSS,'Turbine Bypass Inoperable, ATRIUM-10 29898.6 MWd/MTU < Coie Averag6 Exposures < 32683.9 MWd/MTU Figure 3.16 Columbia Generating Station COLR 05-1 8 Revision 0

________ 'LU-I

i.jU ITwo Loop Operation 3.60 3.40 3.20 3.00 2.80 2.601 0.

0. 2.40 C.

220 2.00 1.80 1.60 1.40 1.20 1.00 I 20 30 40 50 60 70 so 90 100 110 Power (%rated)

Power l .TLO MCPR sLo MCPRp

(/) j Limit Limit 1001.40 41

.65 1.52 1.53 30 1.68 1.69 30 at s 50% flow 2.98 2.99 25 at s 50% flow 3.28 3.29 30 at > 50% flow 3.14 3.15 25 at > 50% flow 3.41 3.42 MCPRp Limits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, SVEA-96 29898.6 MWd/MTU 5 Core Average Exposures 5 32683.9 MWd/MTU Figure 3.17 Columbia Generating Station COLR 05-18 Revision 0

2.80 ITwo Loop Operation 2.60 -

2.40 -

2.20 -

2.00 -

C.

U 1.80-1.60 -

1.40 1.20 1.00_

30 40 50 60 70 80 90 100 110 Power (%tated)

Power- TLb MCOR, SLO MCPRp

.(%) .. .Limit -_. Limit 100 -1.37 1:38 60 -':l48 1.49 30  : 1.58 1.59 30 at s 50% flow 2.28 2.29 25 at s 50% flow 2.43 - 2.44 30 at > 50% flow 2.36 2.37 25 at> 50% flow ... 2.47 2.48 MCPR' Limits Versus Peeicent of Rated Power NSS,-ATRIUM '10 .

FFTR/Coastdowi Operation Figure 3.18 Columbia Generating Station COLR 05-18 Revision 0

ITwo Loop Operation 2.60 2.40 2.20 2.00 a.

0.

¢ 1.80 1.60 1.40 1.20 20 30 40 50 60 70 80 90 100 110 Power (%rated)

I .

'PoWeY TLO MCPRp 1 SLO MCPR.

(°!°) Limit' Limit 100 f.34 1.35

60. 1.46 1.47 30 1.55 1.56 30 at S 50% flow 2.29 2.30 25 at S 50% flow 2.38 . 2.39 30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 . 2.54 MCPRP Limits Versus Percent of Rated Power NSS, SVEA-96 FFTR/Coastdown Operation Figure 3.19 Columbia Generating Station COLR 05-18 Revision 0

3.80 I Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 a.

a. 2.40 a-C.

2.00 1.80 1.60 1.40 1.20 1 no 4 20 30 4G 50 60 70 80 90 100 110 Power (%rated)

Power ItLo MCPRp SLO MCPRP (io.) - .Limit .. Limit.

100 . 1:41 1.42 60 '1 .54 - 1;55 30 '1.68 1.69 30 at s 50% flow 2.90 2.91 25 ats 50% flow 3.23 3.24 30 at > 50% flow 3.03 3.04 25 at > 50% flow .. 3.33 3.34 MCPRp Limits Versus, ercent.of Rated Power NSS, Turbine Bypass Inoperable, ATRIUM-10 FFTRiCoastdown Operation Figure 3.20 Columbia Generating Station COLR 05-18 Revision 0

3.80 -

Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 C.

2.40 U

2.20 ZOO 1.80 1.60 1.40 1.20 1.00 D 20 30 40 50 60 70 80 90 100 110 Power (%rated)

. Power TLO MCPRp SLO MCPRp

(%) Limit Limit 100 .1.38 1.39 60 1.51 1.52 30 1.63 1.64 30 at s 50% flow 2.98 2.99 25 at s 50% flow 3.28 3.29 30 at > 50% flow 3.14 3.15 25 at> 50% flow 3.41 3.42 MCPRp Limits Versus Percent of Rated Power NSS, Turbine Bypass Inoperable, SVEA-96 FFTR/Coastdown Operation Figure 3.21 Columbia Generating Station COLR 05-1 8 Revision 0

2. .vv

.80 -

ITwo Loop Operation 2.60 2.40 2.20 2.00 0.

0.

U 1.80 1.60 1.40 1.20 1.UU +

20 30 40 50 60 70 60 90 100 110

' Powervrated)

Power TLO MCPRp SLO MCPRp

(%)  :'Limit . Limit 100 1.39 1.4o 60 '1.49 1.50 30 i.61 1.62 30 at s50% flow 2.28 2.29 25 at s 50% flow 2.43 2.44 30 at > 50% flow 2.36 2.37 25 at > 50% flow 2.47 2.48' MCPRp Limits Versus P~erent of Rated Power TSSS; ATRIUM-10  : "

FFTR/Cob'stdown'Operation Figure 3.22 Columbia Generating Station COLR 05-18 Revision 0

IIWL 2.80 l Two Loop Operation 2.60 2.40 2.20 2.00 2L a.

1.80 1.60 1.40 1.20 1.00 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power - TLO MCPR' SLO MCPRp

(%/0) Limit Limit 100 1.36 1.37

.60 1.48 1.49 30 1.57 1.58 30 at 5 50% flow 2.29 . 2.30 25 at 5 50% flow 2.38 2.39 30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 2.54 MCPRp Limits Versus Percent of Rated Power TSSS, SVEA-96 FFTR/Coastdown Operation Figure 3.23 Columbia Generating Station COLR 05-18 Revision 0

ITwo Loop Operation 3.60 3.40 3.20 3.00 2.80.

2.60 a.

a. 2.40 Gc 2.20 2.00 1.80 1.60 1.40.

1.20 20 30 40 50 60 70 80 90 100 110 Powe r (%rate d)

Power l TLO MCPRp SLO MCPRp

- (%) .L.. iLimit - ..Limit..-

100 - 1.43 1.44

-60 . 1.56 1.57 30 1.72 1.73 30 at5s50% flow 2.90 2.91 25 at 550% flow '3.23 3.24 30 at > 50% flow. - 3.03 .- 3.04 25 at > 50% flow - ^3.33 -3.34 MCPRp LI-mits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, ATRIUM-10 FFTR/Coastdown Operation Figure 3.24 Columbia Generating Station COLR 05-18 Revision 0

R80 AA A

I Two Loop Operation 3.60 3.40 3.20 3.00 2.80 260 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.UU .

20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power TLO MCPRp SLO MCPR,

(%) Limit Limit 100 1.40 1.41 60 1.54 1.55 30 1.68 1.69 30 at s 50% flow 2.98 2.99 25 at 5 50% flow 3.28 3.29 30 at > 50 flow 3.14 3.15 25 at > 50% flow 3.41 3.42 MCPRp Limits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, SVEA-96 FFTR/Coastdown Operation Figure 3.25 Columbia Generating Station COLR 05-1 a Revision 0

!2 Rn . .

I Two Loop Operation 2.60 I 2.40.

2.20 2.00 0.

L) 1.80 1.60 1.40 1.20 20 30 40 50 . 60- *. 70 s0 90 100 110 Power C.rated)

I.... I .,;. ..

- Power a - -TLG MCPRp SLO MCPRp

.(°) D - Li - 'Limit 100- 1.33 -1.34 65 - 1.46 1.47 30 1.58 1.59 30 at 5 50% flow -2.28 - 2.29 25 at 5 50% flow 2.43 2.44 30 at > 50% flow 2'.36 - 2.37 25 at> 50% flow 2.47 2.48 MCPR, Limits Versus Percent of Rated Power NSS, RPT Inboperable, ATRIUM-1 0 Core Average ExposuIres < 29898.6 MWd/MTU Figure 3.26 Columbia Generating Station COLR 05-1 8 Revision 0

lI iLULL 2.80 I Two Loop Operation 2.60 2.40 2.20 2.00 CL Q.

0.

U 1.80 1.60 1.40 1.20 20 30 40 50 60 . 70 80 90 100 110 Power! rated)

Power TLO MCPRF SLO MCPRp

(%) Limit j Limit 100 1.31 1.32 65 1.44 1.45 30 1.55 1.56 30 at s 50% flow 2.29 2.30 25 at s 50% flow 2.38 2.39 30 at > 50% flow 2.41 2.42 25 at > 50% flow 2.53 2.54 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, SVEA-96 Core Average Exposures < 29898.6 MWd/MTU Figure 3.27 Columbia Generating Station COLR 05-18 Revision 0

2.80

[Two Loop Operation 2.60*

2.40.

2.20 2.00 a.

0.

1.80 1.60 1.40 1.20.

1.1o 4I 20 30 40 50 60 70 80 90 100 110 Power( teratd)

Power' 'TLO MCPRp SLO MCPRp

(%) _ . *. Li mit. Limit_.

100. - 1.40 1.41 -

65 i.47 1.48 30 - 1.58 1.59 30 at s 50% flow -2.28 2.29-25 ats 50% flow -2.43 2.44 30 at >50% flow 2.36 2.37 25 at> 50% flow - ' 2.47 2.48 MCPRP Limits Versus Percent of Rated Povwer NSS, RPT lnoperable,' ATRIUM-10 29898.6 MWd/MTU < Core Average Exposbres 5 32683.9 MWd/MTU Figuire 3.28 Columbia Generating Station - 45 - COLR 05-18 Revision 0

~~~JLUIL 2.80 I Two Loop Operation 2.60 -

2.40 2.20 -

2.00 1.

0.c 0

1.80 -

1.60 1.40 1.20 1.00 20 30 40 50 60 70 , 80 90 100 110 Power (%rated)

Power TLO MCPRp l SLO MCPRp

,(%) . Limit kLimit

-.100 1.36 1.37 65 1.44 1.45 30 1.55 1.56 30 at S 50% flow 2.29 2.30 25 at s 50% flow 2.38 2.39 30 at > 50% flow 2.41 _ 2.42 25 at > 50% flow 2.53 2.54 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, SVEA-96 29898.6 MWd/MTU S Core Average Exposures S 32683.9 MWd/MTU Figure 3.29 Columbia Generating Station - 46 - COLR 05-18 Revision 0

3.&0 ITwo Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 a.

0. 2.40 a.

2.20 2.00 1.80 1.60 1.40 1.00 20 30 40 50 60 70 60 90 100 110 Power (%rated)

Power . TLO MCPR, TSLO MCPRp MY . .:Imit Limit.

100 1.39 1,40 65 1.52 1.53 30 -1.68 1.69 30 at s 50% flow 2.90 2.9f 25 at 550% flow 3.23 3.24 30 at > 50% flow 3.03 3.04 25 at > 50% flow -3.33 3.343-MCPRp Limiits Versus Percent of Rated Power NSS, RPT Inoperable, Turbinej.Bypasp Inoperable, ATRIUM-10 Core Average Exposures < 29898.6 MWd/MTU Figbre 3.30 Columbia Generating Station COLR 05-18 Revision 0

3.80 Two Loop Operation 3.60 3.40 3.20 3.00 280 Z60 2.40 U

2.20 2.00 1.80 1.60 1.40 1.20 20 30 40 50 60 , 70 80 90 100 110 Power (%rated)

Power -j.TLOMCPRp SLO MCPRp

.__ _ _ _ _ _ Limit Limit 100 1.36 1.37 65 1.49 1.50

_ 31.63 o1 1.64 30 at

• 50% flow *2.98 2.99 25 at

• 50% flow 3.28 3.29 30 at > 50% flow 3.14 3.15 25 at > 50% flow 3.41 3.42 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, SVEA-96 Core Average Exposures < 29898.6 MWd/MTU Figure 3.31 Columbia Generating Station COLR 05-18 Revision 0

3.80 Two Loop Operation 3.60 3.40 3.20 X 3.00 -

2.80 2.60 C.

a.) 2.40 2.20 2.00 1.80 1.60-1.40 1.20 1.00 20 30 40 50 80 70 80 90 100 110 Power'(%rted)

Power ltlLbMCPR, l SLO MCPRp

(%) - 'Lmit , Limit 100 ':1.44 1.45 65 -'1.54 1.55 30  : 1.68 1.69 30 at s 50% flow '2.90 2.91 25 at s 50% flow :3.23 3.24 30 at > 50% flow 3.03 3.04 25 at > 50% flow. .>3.33 3.34 MCPRp Limits Verfus Percent of Ra'ted Power '

NSS, RPT Inoperable, T6'rbirie Bypass Inop'erable, ATRIUM-10 29898.6 MWd/MTU S Core'Average Exposures S 32683.9 MWd/MTU Figure 3.32 Columbia Generating Station - 49 - COLR 05-18 Revision 0

- 4 -

3.,A3 -

I Two Loop Operation 3.60 3.40 3.20 3.00 Z80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00

20. 30 40 50 60 70 80 90 10O 110 Power (%rated)

Power TLO MCPRP SLO MCPRP

(%) Limit I Limit 100 1.40 1.41 65 1.49 1.50 30 1.63 1.64 30 at S 50% flow 2.98 2.99 25 at s 50% flow 3.28 3.29 30 at > 50 flow 3.14 3.15 25 at > 50% flow 3.41 3.42 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, SVEA-96 29898.6 MWd/MTU < Core Average Exposures S 32683.9 MWd/MTU Figure 3.33 Columbia Generating Station COLR 05-18 Revision 0

4.0 Linear Heat Generation Rate (LHGR) Limits for Use in Technical Specification 3.2.3 The LHGRs for use in Technical Specification 3.2.3 are given as a function of nodal pellet exposure for both the ATRIUM-10 and SVEA-96 fuel. The LHGRs shall not exceed the limits shown in the following figures:

a. Figure 4.1 - SVEA-96 reload fuel

b. Figure 4.2 - Cycle 17 ATRIUM-1 0 reload fuel C. Figure 4.3 - Cycle 18 ATRIUM-1 0 reload fuel

.. ... . . X . . . I.,

I O ... , . . . ..

.. t ..

! P

. I, ,

N A- "

. I' t .4 Columbia Generating Station COLR 05-18 Revision 0

111111 14 13 12 11 I,

10 10000 20000 - 30000 40000 50000 60000 70000 PMd Exposurv (MW4UTU)

Pellet Exposure . LHGR .

(MWd/MTU) I (kW/ft) 0 1 13.4 16000 11.0 65000 7.2 Linear Heat Generation Rate (LHGR)

Versus Pellet Exposure SVEA-96 Figure 4.1 Columbia Generating Station COLR 05-18 Revision 0

14 13 12 11

- I E 10 9

8 6

0 10000 20000 30000 , ' 40000.-- 50000 60000 70000 80000 Pellet Exposure (MWdlMTU)

Pellet Exposure - LHGR (MWd/MTU) (kW/ft)

0. 13.4 18900 13.4 732-00 7.0 Linear Heat Generation'Rate (LHGR)

Versus Pellet Exposure Cycle 17 ATRIUM-10 Reload Fuel Figure 4.2 Columbia Generating Station COLR 05-18 Revision 0

14 13 12 11 e

E 10

3 9

8 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWd!MTU)

Pellet Exposure LHGR (MWd/MTU) I (kW/ft) 0 13.4 18900 j 13.4 74400 1 7.1 Linear Heat Generation Rate (LHGR)

Versus Pellet Exposure Cycle 18 ATRIUM-10 Reload Fuel Figure 4.3 Columbia Generating Station COLR 05-18 Revision 0

5.0 Oscillation Power Range Monitor (OPRM) Instrumentation Limits for Use in LCO 3.3.1.3 The OPRM instrumentation limits for use in LCO 3.3.1.3 shall not exceed the following:

Function I Trip Setpoint Period Based Detection Algorithm (PBDA)

Amplitude Setpoint: Sp l1.1 1 Peak/AverageI Confirmation Count Setpoint: N2 l 14 I

Columbia Generating Station COLR 05-18 Revision 0

liii 6.0 References 6.1 CE NPSD-883-P, Revision 0, "COLUMBIA Cycle 16 Reload Licensing Report,"

Westinghouse CE Nuclear Power LLC, March 2001.

6.2 CE NPSD-801-P, Revision 5, 'Columbia LOCA Analysis Report," Westinghouse CE Nuclear Power LLC, February 2001.

6.3 EMF-3164 Revision 0, "Columbia Generating Station Cycle 18 Reload Analysis,"

Framatome ANP, February 2005.

6.4 EMF-3172 (P) Revision 1, "Columbia Generating Station LOCA-ECCS Analysis MAPLHGR Limit for ATRIUMh 4 -10 Fuel," Framatome ANP, June 2005.

6.5 NE-02-00-03, Revision 0, "Oscillation Power Range Monitor (OPRM) Trip Setpoints," Energy Northwest, June 17, 2000.

6.6 CE NPSD-792-P, "Fuel Assembly Mechanical Design Report for WNP2," ABB Combustion Engineering Nuclear Operations, May 1996.

Columbia Generating Station COLR 05-18 Revision 1