GO2-07-089, Cycle 19 Core Operating Limits Report (Colr), Revision 0

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Cycle 19 Core Operating Limits Report (Colr), Revision 0
ML071630327
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 06/05/2007
From: Coleman D
Energy Northwest
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-07-089
Download: ML071630327 (41)
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DW Coleman ENERGY Regulatory Programs P.O. Box 968, Mail Drop PE20 NORTHWEST Richland, WA 99352-0968 Ph. 509-377-4342 F. 509-377-4317 dwcoleman@energy-northwest.com June 5, 2007 G02-07-089 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 CYCLE 19 CORE OPERATING LIMITS REPORT (COLR), REVISION 0

Dear Sir or Madam:

In accordance with the Columbia Generating Station Technical Specifications (TS) 5.6.3.d, Energy Northwest herewith submits the Cycle 19 COLR, Revision 0. 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

Attachment:

COLR 07-19, Revision 0 cc: BS Mallett - NRC RIV WA Horin - Winston & Strawn CF Lyon - NRC NRR RN Sherman - BPA/1 399 NRC Sr. Resident Inspector - 988C (2)

A441L-

COLR 07-19 Revision 0 Columbia Generating Station Cycle 19 Core Operating Limits Report May 2007

Columbia Generating Station Cycle 19 Core Operating Limits Report List of Effective Pages PAGE REVISION i................................................................. ........................................................................... 0 1 ........................................................................................................................................... 0 2 ........................................................................................................................................... 0 3 .. ........................................................................................................................................ 0 4...................................... .. ........... 1.............................. ............ 0 5 ........................................................................................................................................... 0 6 ........................................................................................................................................... 0 7 ........................................................................................................................................... 0 8 .. ......................................................................................................................................... 0 9 ........................................................................................................................................... 0 10 ........................................................................................................................................... 0 1 1 ...................................... .................................................................................................... 0 12 ........................................................................................................................................... 0 13 ........................................................................................................................................... 0 14 ........................................................................................................................................... 0 15 ............................................................ .............................................................................. 0 16 ........................................................................................................................................... 0 17 ........................................................................................................................................... 0 18 ........................................................................................ .................................................. 0 19 ........................................................................................................................................... 0 2 0 ......................................... .................................................................................................. 0 2 1 ........................................................................................................................................... 0 2 2 ................................................................. ......................................................................... 0 2 3 ........................................................................................................................................... 0 2 4 ........................................................................................................................................... 0 2 5 ................................................................................... ...................................................... 0 2 6 ................................................................... ........................................................................ 0 2 7 ........................................................................................................................................... 0 2 8 ................................................................................... ....................................................... 0 Columbia Generating Station LEP-1 COLR 07-19 Revision 0

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Columbia Generating Station Cycle 19 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 ....................................................................................................... 8 4.0 Linear Heat Generation Rate (LHGR) Limits for Use in Technical Specification 3.2.3 ...................................................................................... 31 5.0 Oscillation Power Range Monitor (OPRM) Instrumentation Limits for Use in LCO 3.3.1.3 ................................................................................................ 35 6 .0 R e fe re n ce s ...................................................................................................................... 36 Columbia Generating Station COLR 07-19 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 19 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 APLHGR and LHGR limits for ATRIUM-10 fuel given in this report are documented in Reference 6.3. The MCPR limits for all Cycle 19 fuel types (SVEA-96 as well as ATRIUM-10 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 07-19 Revision 0

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 EvaluationMode/,.,Exxon Nuclear Company, March 1984.
2. XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon NuceaprCompany, 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 Criteriafor BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
5. XN-NF-80-19(P)(A) Volume 1 and Supplements I and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design andAnalysis, Exxon Nuclear Company, March 1983.
6. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon NuclearMethodology 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: Evaluationand 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 I and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Programfor Boiling Water Reactor Transient Analysis, Advanced Nuclear Fuels Corporation, August 1990.
12. AN F-i 358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
13. EMF-2209(P)(A) Revision 2, SPCB CriticalPower Correlation,Siemens Power Corporation, September 2003.

Columbia Generating Station COLR 07-19 Revision 0

14. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation'sCritical Power Correlationsto Co-Resident Fuel, Siemens Power Corporation, August 2000.
15. EMF-2361(P)(A) Revision ý0', EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.
16. EMF-2292(P)(A) Revision 0, A TRIUM.-1O: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
17. EMF-CC-074(P)(A) Volume 4 Revision 0, BWR StabilityAnalysis -*Assessment of S TAIF 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 07-19 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 - SE- and SF-Type SVEA-96 reload fuel - Two Loop Operation
b. Figure 2.2 - SE- and SF-Type SVEA-96 reload fuel - Single Loop Operation
c. Figure 2.3- ATRIUM-10 reload fuel Columbia Generating Station COLR 07-19 Revision 0

10 ___

9.8 9.6 9.4 9.2

!r 9.

0 8.8 3j 8.6 8.4 8.2 8

7.8 7.6 0 10000 20000 30000 40000 50000 60000 Avenge Planar Exposure (MWdIMTU)

Average Planar Exposure MAPLHGR (MWd/MTU) (kW/ft) 0 9.4 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 2.1 Columbia Generating Station COLR 07-19 Revision 0

9.8 9.6 9.4 9.2 V9 8.8 8.

j 8.6 8.2 7.8 7.6 0 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWdIMTU)

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 2.2 Columbia Generating Station COLR 07-19 Revision 0

I

-j a-10000 20000 30000 40000 50000 60000 70000 80000 Average Planar Exposure (MWdlMTU)

Average-Planar -TLO SLO Exposure MAPLHGR MAPLHGR (MWd/MTU) (kW/ft) (kW/ft) 0 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 2.3 Columbia Generating Station COLR 07-19 Revision 0

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 3.1 b, Table 3.2a, Table 3.2b, and Figures 3.1 through 3.17. For the purposes of cycle extension, the feedwater temperature entering the reactor vessel shall not be reduced to less than 355 OF.

The MCPR safety limit for Cycle 19 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 07-19 Revision 0

Table 3.1a Columbia Generating Station MCPR Operating Limits Two-Loop Operation Core Average Exposures. < 31891 MWd/MTU SLMCPR=

E1.09(2)

Conto Limit Condition All Cycle 19 Fuel Types Full power 1.31(3)

NSS(1) Flow dependent(s) Figure 3.1 Power dependent(4) Figure 3.2 Full power 1.34 TSSS(1) Flow dependent(5 ) Figure 3.1 Power dependent(4) Figure 3.6 NSS( 1 ) Full power 1.33 RPT Flow dependent(5) Figure 3.1 Inoperable Power dependent(4 ) Figure 3.14 Columbia Generating Station COLR 07-19 Revision 0

Table, 3.1 b Columbia Generating Station MCPR Operating Limits Two-Loop Operation Core Average Exposures > 31891 MWd/MTU SLMCPR = 1.09(2) SLMCPR = 1.09(2)

FFTR/Coastdown(6)

EOOS Core Average Extended Core Average Condition Limit Exposures Exposures

< 34433 MWd/MTU < 37561 MWd/MTU All Cycle 19 All Cycle 19 Fuel Types Fuel Types Full power 1.35 1.36 NSS(1 ) Flow dependent(s) Figure 3.1 Figure 3.1 Power dependent(4) Figure 3.3 Figure 3.10 Full power 1.38 1.39 TSSS(1) Flow dependent(s) Figure 3.1 Figure 3.1 Power dependent(4) Figure 3.7 Figure 3.12 Full power 1.38 NSS(1 )

RPT Flow dependent(5) Figure 3.1 Not analyzed Inoperable Power dependent(4) Figure 3.15 Columbia Generating Station COILR 07-19 Revision 0

Table 3.2a Columbia Gen16erating Station MCPR Operating Limits Two-Loop Operation Turbine Bypass System Inoperable Core Average Exposures < 31891 MWd/MTU 2

)

SLMCPR = 1.09(

EOOSEOOS Limit Condition All Cycle 19 Fuel Types Full power 1.35 NSS(') Flow dependent(5 ) Figure 3.1 Power dependent(4) Figure 3.4 Full power 1.39 TSSS(1 ) Flow dependent(5) Figure 3.1 Power dependent(4) Figure 3.8 Full power 1.38 NSS(')

RPT Flow dependent(5) Figure 3.1 Inoperable 4 Power dependent( ) Figure 3.16 Columbia Generating Station COLIR 07-19 Revision 0

Table 3.2b,,

Columbia Generating Station MCPR Operating Limits

Two-Loop Operation Turbine Bypass System Inoperable Core Average Exposures 2!31891 MWd/MTU SLMCPR = 1.09(2) SLMCPR = 1.09(2)

FFTR/Coastdown(6)

EOOS Core Average Extended Core Average Condition Limit Exposures Exposures

< 34433 MWd/MTU < 37561 MWd/MTU All Cycle 19 All Cycle 19 Fuel Types Fuel Types Full power 1.39 1.41 NSS(1) Flow dependent(s) Figure 3.1 Figure 3.1 Power dependent(") Figure 3.5 Figure 3.11 Full power 1.42 1.43 TSSS(1) Flow dependent~5 ) Figure 3.1 Figure 3.1 Power dependent(4) Figure 3.9 Figure 3.13 Full power 1.42 NSS 1 ),

RPT Flow dependent(5) Figure 3.1 Not analyzed Inoperable Power dependent(4) Figure 3.17 Columbia Generating Station COLR 07-19 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 AREVA NP transient analyses performed using control rod insertion times consistent with the following table. If Technical Specification 3.1.4 is met with the NSS insertion times shown below, the NSS MCPR limits in Tables 3.la, 3.1b, 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.

Control Rod NSS Position Time (notch) (sec) 45 0.43 39 0.72 25 1.60 5 2.95 Note 2: For Single Loop Operation (SLO), the SLMCPR increases by 0.01. This 0.01 increase must also be applied to the Two Loop Operation MCPRp Operating Limit to obtain the SLO operating limit.

Note 3: The Cycle 19 MCPR limits were established assuming a Rod Block Monitor (RBM) setpoint of 1.06. With a 1.06 RBM setpoint, the Rod Withdrawal Error (RWE) event is not limiting. The RWE event remains nonlimiting as long as the RBM setpoint is

< 1.07.

Note 4: Power dependent MCPR limits are provided for core thermal powers greater than or equal to 25% of rated power 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 scrams on turbine throttle valve closure and turbine governor valve fast closure are 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.

Note 6: The NSS FFTR/Coastdown limits support a feedwater temperature reduction down to 3550F or 35°F below nominal, whichever is lower. The NSS with turbine bypass inoperable and all TSSS FFTR/Coastdown limits support a feedwater temperature reduction down to 355°F or 20°F below nominal, whichever is lower.

Columbia Generating Station COLR 07-19 Revision 0

1.8 1.75 1.7 1.65 1.6 1.55 1.5 1.45 0.

U 1.4 1.35 1.3 1.25 1.2 1.15 1.1 1.05 0 10 20 30 40 50 60 70. 80 90 100 110 Flow (% rated)

MCPRf Flow All Cycle 19

(% of-rated) *Fuel Types 0 1.76 20 1.76 30 1.58 100 1.16 108.5 1.16 Reduced Flow MCPR Operating Limit Versus Total Core Flow All Cycle 19 Fuel Types Figure 3.1 Columbia Generating Station COLR 07-19 Revision 0

2.80 Two Loop Operation 2.60 2.40 2.20-2.00 a.

a.

U 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 SLO MCPRp

(%) Limit Limit 100 .. 1.31 1.32 65 1.47 1.48 30 1.62 1.63 30 at < 50% flow 2.33 2.34 25 at < 50% flow 2.47 2.48 30 at > 50% flow 2.39 2.40 25 at > 50% flow 2.55 2.56 MCPRp Limits Versus Percent of Rated Power NSS, All Cycle 19 Fuel Types Core Average Exposures < 31891 MWdIMTU Figure 3.2 Columbia Generating Station COLR 07-19 Revision 0

2.80 Two Loop Operation 2.60 2.40 2.20 2.00 Ia.

0.

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

Power . TLO MCPRp SLO MCPRO

(%) Limit Limit 100 1.35 1.36 65 1.47 1.48 30 1.62 1.63 30 at < 50% flow 2.33 .. 2.34 25 at < 50% flow 2.47 2.48 30 at > 50% flow 2.39 2.40-25 at > 50% flow 2.55 2.56 MCPRp Limits Versus Percent of Rated Power NSS, All Cycle 19 Fuel Types 31891 MWd/MTU < Core Average Exposures < 34433 MWd/MTU Figure 3.3 Columbia Generating Station COLR 07-19 Revision 0

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

W.

I-) 2.40 2.20 2.00-1.80 1.60 1.40-1.20 1.00 20 3 0 40 50 60 70 80 90 100 110 Power (% rated)

Power

(%) TLOLimit MCPRp SLOLimit MCPRp

.100 1.35 1.36 65 1.52 1 53 30 1.70 1.71 30 at < 50% flow 2.98 2.99 25 at* 50% flow 3.34 3.35 30 at > 50% flow 3.12 3.13 25 at > 50% flow . 3.45 3.46 MCPR, Limits Versus Percent of Rated Power NSS, Turbine Bypass Inoperable, All Cycle 19 Fuel Types Core Average Exposures < 31891 MWd/MTU Figure 3.4 Columbia Generating Station COLR 07-19 Revision 0

3.80 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 . TLO MCPRp SLO:MCPRp

(%) Limit Limit 100 1.39 1.40 65 1.53 1.54 30 1.70 1.71 30 at < 50% flow 2.98 2.99 25 at* 50% flow 3.34 3.35 30 at > 50% flow 3.12 3.13 25 at > 50% flow 3.45 3.46 MCPRp Limits Versus Percent of Rated Power NSS, Turbine Bypass Inoperable, All Cycle 19 Fuel Types 31891 MWd/MTU < Core Average Exposures < 34433 MWd/MTU Figure 3.5 Columbia Generating Station COLR 07-19 Revision 0

2.80 2,60 2,40 220 2.00 (L

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 SLO MCPRp

(%) Limit Limit 100 1.34 1.35 65 1.49 1.50 30 1.64 1,65 30 at:<50% flow 2.33 2.34 25 at 50% flow 2.39 2.40 25 at > 50% flow 2.55 2.56 MCPRp Limits Versus Percent of Rated Power TSSS, All Cycle 19 Fuel Types Core Average Exposures < 31891 MWd/MTU Figure 3.6 Columbia Generating Station COLR 07-19 Revision 0

2.80 Two Loop Operation 2.60 2.40 2.20 2.00 12 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 SLO MCPRp

(%) Limit Limit 100 1.38 1.39 65 1.49 1.50 30 1.64 1.65 30 at* 50% flow 2.33 2.34, 25 at < 50% flow 2.47 2.48 30 at > 50% flow 2.39 2.40 25 at > 50% flow 2.55 2.56 MCPRp Limits Versus Percent of Rated Power TSSS, All Cycle 19 Fuel Types 31891 MWd/MTU < Core Average Exposures < 34433 MWd/MTU Figure 3.7 Columbia Generating Station COLR 07-19 Revision 0

3.80 Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60 C.) 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00 20 310 40 50 60 70 80 90 100 110 Power (% rated)

Power TLO MCPRp SLO MCPRp

(%) Limit Limit 100 1.39 1.40 65 1.55 1.56 30 1.75 1.76 30 at < 50% flow 2.98 2.99 25 am s 50% flow 3.34 3.35 30 at > 50% flow 3.12 3.13 25 at > 50% flow 3.45 3.46 MCPRP Limits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, All Cycle 19 Fuel Types Core Average Exposures < 31891 MWdlMTU Figure 3.8 Columbia Generating Station COLR 07-19 Revision 0

Two Loop Operation 3.60 3.40 3.20-1 3.00 2.80 2.60 C) 2.40 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 r TLO MCPRp SLO MCPRp

(%) Limit Limit 100 1.42 ..1.43 65 1.55 1.56 30 1.75 1.76 30 at < 50% flow 2.98 2.99 25 at5<50% flow 3.34 '3.35 30 at > 50% flow 3.12 23.13' 25 at > 50% flow 3.45 3.46 MCPRp Limits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, All Cycle 19 Fuel Types 31891 MWd/MTU < Core Average Exposures <34433 MWd/MTU Figure 3.9 Columbia Generating Station COLR 07-19 Revision 0

2.80 2.60 2.40 2.20 2.00 0.

it CL 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 SLO MCPRp

(%) Limit Limit 100 1.36 1.37 60 - 1.51 1.52 30 1.65 1.66 30 at ,- 50% flow 2.33 2.34 25 at < 50% flow 2.47 2.48 30 at> 50% flow 2.41 2.42 25 at.> 50% flow 2.61 2.62 MCPRp-Limits Versus Percent of Rated Power NSS, All Cycle 19 Fuel Types FFTR/Coastdown Operation Core Average Exposures < 37561 MWdIMTU Figure 3.10 Columbia Generating Station COLR 07-19 Revision 0

3.80 Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60

a. 2.40 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 TLO MCPRp SLO MCPRp

(%) Limit Limit 100 " 1.41 1.42 60 1.55 1.56 30 1.70 1.71 30 at < 50% flow 2.98 2.99 25 at < 50% flow 3.34 3.35 30 at > 50% flow 3.12 3.13 25 at > 50% flow 3.45 3.46 MCPRp Limits Versus Percent of Rated Power NSS, Turbine Bypass Inoperable, All Cycle 19 Fuel Types FFTR/Coastdown. Operation Core Average Exposures<5 37561 MWd/MTU Figure 3.11 '

Columbia Generating Station . COLR 07-19 Revision 0

2.80 2.60 2.40 2.20 2.00 0.

I-1.80 1.60 1.40 1.20 1.00 20 30 40 50 60 70 s0 90 100 110 Power (%rated)

Power TEO MCPRp SLO MCPRP

(%) Limit Limit 100 1.39 1.40 60 1.52 1.53 30 1.64 1.65 30 at < 50% flow 2.33 2.34 25 at < 50% flow 2.47 2.48 30 at'>'50% flow 2.39 2.40 25 at > 50% flow 2.55 2.56 MCPRp Limits Versus Percent of Rated Power TSSS, All Cycle 19 Fuel Types FFTR/Coastdown Operation Core Average Exposures < 37561 MWd/MTU Figure 3.12 Columbia Generating Station COLR 07-19 Revision 0

3.80 Two Loop Operation 3.60 3.40 3.20 3.00 2.80 2.60

a. 2.40 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 TLO MCPRp SLO MCPRp

(%) Limit- Limit 100 .1.43 1.44 60 1.58 1.59 30 1.75 1.76 30 at <50% flow 2.98 2.99 25 at < 50% flow 3.34 3.35.

30 at > 50% flow 3.12 -3.13.

25 at > 50% flow 3:45' 3.46 MCPRp Limits Versus Percent of Rated Power TSSS, Turbine Bypass Inoperable, All Cycle 19 Fuel Types FFTR/Coastdown Operation Core Average Exposures 5 37561 MWd/MTU Figure 3.13 Columbia Generating Station - 26 - COLR 07-19 Revision 0

Two Loop Operation 2.60 2.40 2.20 2.00 0.

L) 2 1.80 1.60 1.40 1.20 1.00 -

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

Power . TLOMCPRp SLO MCPRp

(%) Limit :Limit 100 1.33 1.34 65 1.47 1.48 30 1.62 1.63 30 at s 50% flow 2.33 2.34 25 at < 50% flow 2.47 2.48 30 at>50% flow 2.39 2.40 25 at->.50% flow 2.55 2.56 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, All Cycle 19 Fuel Types CoreAverage Exposures < 31891 MWdlMTU Figure 3.14 Columbia Generating Station COLR 07-19 Revision 0

280 Two Loop Operation 2.60 2.40 2.20 2.00 2.

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

Power TLO MCPRP SLO MCPRp

(%) Limit Limit 100 1.38 1.39 65 1.48 1.49 30 1.62 1.63 30 at < 50% flow 2.33 .21.34 25 at < 50% flow 2.47 2.48 30 at > 50% flow 2.39 2.40 25 at > 50% flow 2.55 . 2.56 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, All Cycle 19 FuelTypes 31891 MWd/MTU < Core Average Exposures <34433 MWd/MTU Figure 3.15 Columbia Generating Station COLR 07-19 Revision 0

3.80 ITwo Loop Operation 3.60-3.40 3.20-3.00-2.80 2.60 a.

0. 2.40 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 ILO MCPRp SLO MCPRp

(%) Limit Limit 100 1.38 1.39 65 1.52 1.53 30 1.70 1.71 30 at< 50% flow 2.98 2.99 25 at <.50% flow 3.34 3.35 30 at > 50% flow 3.12 3.13 25 at > 50% flow 3.45 3.46 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, All Cycle 19 Fuel Types Core Average Exposures < 31891 MWd/MTU Figure 3.16 Columbia Generating Station COLR 07-19 Revision 0

Two Loop Operation 3.60 3.40 3.20 3.001 2.80 2.60

9) 2.40 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 TLO MCPRP SLO MCPRP

(%) Limit Limit 100 1.42 1.43 65 1.54 1.55 30 1.70 1.71 30 at - 50% flow 2.98 2.99 25 at - 50% flow 3.34 3.35 30 at > 50% flow 3.12 3.13 25 at > 50% flow 3.45 3.46 MCPRp Limits Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, All Cycle 19 Fuel Types 31891 MWd/MTU < Core Average Exposures < 34433 MWd/MTU Figure 3.17 Columbia Generating Station COLR 07-19 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-10 reload fuel
c. Figure 4.3 - Cycle 18 and 19 ATRIUM-10 reload fuel Columbia Generating Station COLR 07-19 Revision 0

14 .. . ...........................................

13 12 01

(~10 5j 7

0 10000 20000 30000 40000 50000 60000 70000 Pellet.Exposure (MWd/MTU)

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

... 0 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 07-19 Revision 0

14 13 12 11 E 10 9

a 7

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 73200 7.0 Linear Heat Generation Rate (LHGR)

Versus Pellet Exposure Cycle 17 ATRIUM-10 Reload Fuel Figure 4.2 Columbia Generating Station COLR 07-19 Revision 0

E

_j

(.

z 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWd/MTU)

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

Versus Pellet Exposure Cycle 18 and 19 ATRIUM-10 Reload Fuel Figure 4.3 Columbia Generating Station COLR 07-19 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 1.11 Peak/Average Confirmation Count Setpoint: N2 14 Columbia Generating Station COLR 07-19 Revision 0

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 ANP-2602 Revision 0, "Columbia Generating Station Cycle 19 Reload Analysis,"

AREVA NP, March 2007.

6.4 EMF-3172(P) Revision 1, "Columbia Generating Station LOCA-ECCS Analysis MAPLHGR Limit for ATRIUMTM-1 0 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 07-19 Revision 0

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