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{{#Wiki_filter:COLR 97-13, REVISION 1 Controlled Copy No.-2 CYCLE 13 Core Operating Limits Report July 1997 Washington Public Power Supply System 97omsaa97'7a7~n g pDR hooch osaao397 P PDR!  
{{#Wiki_filter:COLR 97-13, REVISION 1 Controlled Copy No.
~Pa e WNP-2 Cycle 13 Core Operating Limits Report LIST OF EFFE TIVE PAGES Revision 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24~s LEP
                                        -2 CYCLE 13 Core Operating Limits Report July 1997 Washington Public Power Supply System 97omsaa97'7a7~n pDR hooch osaao397 g
~Pa e WNP-2 Cycle 13 Core Operating Limits Report LI T F EFFECTIVE PA ReviceiRn 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 LEP WNP-2 Cycle 13 Core Operating Limits Report TABLE F NTENTS P~ae 1.0 INTR D TI N AND MMARY 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION APLHGR LIMITS FOR USE IN TECHNICAL SPE IFI ATION 3 2.1 3.0 MINIM M CRITICAL POWER RATIO MCPR LIMIT F R SE IN TECHNICAL SPE IFICATI N 3.2 2 4.0 LINEAR HEAT ENERATION RATE LH R LIMITS F R U E IN TECHNICAL SPECIFICATI N,2.3 5.0 P WER FL W INSTABILITY
P             PDR!


==6.0 REFERENCES==
WNP-2 Cycle 13 Core Operating Limits Report LIST OF EFFE TIVE PAGES
~Pa  e                              Revision 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24
~s LEP WNP-2 Cycle 13 Core Operating Limits Report LI T F EFFECTIVE PA
~Pa e                              ReviceiRn 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 LEP WNP-2 Cycle 13 Core Operating Limits Report TABLE F        NTENTS P~ae 1.0   INTR D        TI N AND    MMARY 2.0    AVERAGE PLANAR LINEAR HEAT GENERATION APLHGR LIMITS FOR USE IN TECHNICAL SPE IFI ATION 3 2. 1 3.0    MINIM M CRITICALPOWER RATIO MCPR LIMIT F R SE IN TECHNICAL SPE IFICATI N 3.2 2 4.0    LINEAR HEAT ENERATION RATE LH R LIMITS F R U E IN TECHNICAL SPECIFICATI N,2.3                          45 5.0    P WER    FL W INSTABILITY                                      48


45 48 50 Washington Nuclear-Unit 2 COLR 97-13, Revision 0 1.0, INTROD CTION AND  
==6.0    REFERENCES==
50 Washington Nuclear - Unit 2                             COLR 97-13, Revision 0
 
1.0,   INTROD CTION AND  


==SUMMARY==
==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 Power to Flow Map for WNP-2, Cycle 13 as required by Technical Specification 5.6.5.As required by Technical Specification 5.6.5, 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 6.6 describe the LOCA analysis for rated power.The analysis was performed with a methodology that results in Single Loop Operation being adequately covered by Two Loop Operation.
 
The thermal limits for all fuel types for Single Loop Operation are the same as Two Loop Operation.
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 Power to Flow Map for WNP-2, Cycle 13 as required by Technical Specification 5.6.5.     As required by Technical Specification 5.6.5, 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 6.6 describe the LOCA analysis for rated power. The analysis was performed with a methodology that results in Single Loop Operation being adequately covered by Two Loop Operation. The thermal limits for all fuel types for Single Loop Operation are the same as Two Loop Operation. The thermal limits for fuel given in this report are documented in the "WNP-2 Cycle 13 Reload Report" (Reference 6.3), the "WNP-2 Cycle 13 Transient Analysis Report" (Reference 6.4),
The thermal limits for fuel given in this report are documented in the"WNP-2 Cycle 13 Reload Report" (Reference 6.3), the"WNP-2 Cycle 13 Transient Analysis Report" (Reference 6.4), and Reference 6.5.The basis for power to flow map which addresses the instability operating region limits is documented in Reference 6.3.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 throughout the WNP-2 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.
and Reference 6.5. The basis for power to flow map which addresses the instability operating region limits is documented in Reference 6.3.
A flow dependent MCPR is specified to define operating limits at other than rated flow conditions.
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 throughout the WNP-2 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 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 WNP-2 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%.Preparation, review, and approval of this report were performed in accordance with applicable Supply System procedures.
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 WNP-2 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 referenced in Technical Specification 5.6.5.Washington Nuclear-Unit 2 COLR 97-13, Revision 0 2.0 AVERA E PLANAR LINEAR HEAT ENERATI N RATE APLH R LIMITS FOR U E IN TE HNI AL SPE IFICATI N 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 when in two loop or single loop operation:
Preparation, review, and approval of this report were performed in accordance with applicable Supply System procedures.       The specific topical report revisions and supplements which describe the methodology utilized in this cycle specific analysis are referenced in Technical Specification 5.6.5.
a.Figure 2.1-SPC 9x9-9X reload fuel b.Figure 2.2-ABB SVEA-96 reload fuel 0 Washington Nuclear-Unit 2-2-COLR 97-13, Revision 0 14.5 14 13.5 13 12.5 12 Two Loop and Single Loop Operation 11.5 11 10.5 10 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure lMWd/MTU)Average Planar Exposure (MWd/MTU)15500 45000 55000 MAPLHGR (ICW/ft)12.5 12.5 9.3 7.9 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)Versus Average Planar Exposure SPC 9x9-9X Figure 2.1 Washington Nuclear-Unit 2-3-COLR 97-13, Revision 0 14.5 14 Two Loop and SingIe Loop Operation 13.5 13 12.5 12 11.5 11 10.5 10 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure{IVIWd/NITUI Average Planar Exposure (MWd/MTU)14000 18000 59000 MAPLHGR (kW/ft)9.3 9.3 9.0 8.5 8.5 8.4 8.0 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)Versus Average Planar Exposure ABB SVEA-96 Figure 2.2 Washington Nuclear-Unit 2-4-COLR 97-13, Revision 0 3.0, MINIMUM RITI AL POWER RATI MCPR LIMIT FOR USE IN TECHNICAL PE IFICATION 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 3.31 through 3.34.For the purposes of cycle extension, the feedwater temperature entering the reactor vessel should not be reduced to less than 355'F.The MCPR limits given apply to both two loop and single loop operation.
Washington Nuclear - Unit 2                                                   COLR 97-13, Revision 0
The MCPR safety limit for SPC 9x9-9X is 1.13 for two loop operation and 1~14 for single loop operation.
 
Note: ATRIUM-9X and SPC 9x9-9X are equivalent terms for the same fuel type and may be used interchangeably.
2.0     AVERA E PLANAR LINEAR HEAT ENERATI N RATE APLH R LIMITS FOR U E IN TE HNI AL SPE IFICATI N 3.2.1 The APLHGRs for use in Technical Specification 3.2.1, as a function of Average Planar 0
Exposure, shall not exceed the limits shown in the following figures when in two loop or single loop operation:
: a.     Figure 2.1 - SPC 9x9-9X reload fuel
: b.     Figure 2.2 - ABB SVEA-96 reload fuel Washington Nuclear - Unit 2                                         COLR 97-13, Revision 0
 
14.5 Two Loop and Single Loop Operation 14 13.5 13 12.5 12 11.5 11 10.5 10 9.5 8.5 7.5 10000       20000       30000       40000       50000       60000 Average Planar Exposure lMWd/MTU)
Average Planar Exposure (MWd/MTU)                     MAPLHGR (ICW/ft) 12.5 15500                                      12.5 45000                                        9.3 55000                                        7.9 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure SPC 9x9-9X Figure 2.1 Washington Nuclear - Unit 2                                                     COLR 97-13, Revision 0
 
14.5 Two Loop and SingIe Loop Operation 14 13.5 13 12.5 12 11.5 11 10.5 10 9.5 8.5 7.5 10000       20000       30000       40000       50000       60000 Average Planar Exposure {IVIWd/NITUI Average Planar Exposure (MWd/MTU)                         MAPLHGR (kW/ft) 9.3 9.3 14000                                            9.0 18000                                            8.5 8.5 8.4 59000                                            8.0 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure ABB SVEA-96 Figure 2.2 Washington Nuclear - Unit 2                                                   COLR 97-13, Revision 0
 
3.0,     MINIMUM RITI AL POWER RATI               MCPR LIMITFOR USE IN TECHNICAL PE IFICATION3.2.2 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 3.31 through 3.34. For the purposes of cycle extension, the feedwater temperature entering the reactor vessel should not be reduced to less than 355'F. The MCPR limits given apply to both two loop and single loop operation.
The MCPR safety limit for SPC 9x9-9X is 1.13 for two loop operation and 1 14 for single
                                                                              ~
loop operation. Note: ATRIUM-9Xand SPC 9x9-9X are equivalent terms for the same fuel type and may be used interchangeably.
The MCPR safety limit for SVEA-96 is 1.07 for two loop operation and 1.08 for single loop operation.
The MCPR safety limit for SVEA-96 is 1.07 for two loop operation and 1.08 for single loop operation.
The MCPR safety limits
The MCPR safety limits are applicable to Cycle 13 only.
Washington Nuclear - Unit 2                                            COLR 97-13, Revision 0
 
Table 3.1a WNP-2 Cycle 13 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Operable Cycle Exposure ( 5000 MWd/MTU SLMCPR =      1 13 (2) SLMCPR =    1 07 (2)
SPC                  ABB Condition              Limit                9x9-9X              SVEA-96 NSS (1)      Full Power                      1.40 (3)              1.30 (3)
Flow Dependent (4)            Fig. 3.1              Fig. 3.2 Power Dependent (5)            Fig. 3.3              Fig. 3.7 TSSS (1)    Full Power                      1.40 (3)                1.31 Flow Dependent (4)            Fig. 3.1              Fig. 3.2 Power Dependent (5)          Fig. 3.11              Fig.

Revision as of 12:05, 29 October 2019

Rev 1 to COLR 97-13, Cycle 13 Colr.
ML17292A938
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 07/31/1997
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM
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References
COLR-97-13, NUDOCS 9707230097
Download: ML17292A938 (54)


Text

COLR 97-13, REVISION 1 Controlled Copy No.

-2 CYCLE 13 Core Operating Limits Report July 1997 Washington Public Power Supply System 97omsaa97'7a7~n pDR hooch osaao397 g

P PDR!

WNP-2 Cycle 13 Core Operating Limits Report LIST OF EFFE TIVE PAGES

~Pa e Revision 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24

~s LEP WNP-2 Cycle 13 Core Operating Limits Report LI T F EFFECTIVE PA

~Pa e ReviceiRn 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 LEP WNP-2 Cycle 13 Core Operating Limits Report TABLE F NTENTS P~ae 1.0 INTR D TI N AND MMARY 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION APLHGR LIMITS FOR USE IN TECHNICAL SPE IFI ATION 3 2. 1 3.0 MINIM M CRITICALPOWER RATIO MCPR LIMIT F R SE IN TECHNICAL SPE IFICATI N 3.2 2 4.0 LINEAR HEAT ENERATION RATE LH R LIMITS F R U E IN TECHNICAL SPECIFICATI N,2.3 45 5.0 P WER FL W INSTABILITY 48

6.0 REFERENCES

50 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

1.0, INTROD CTION 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 Power to Flow Map for WNP-2, Cycle 13 as required by Technical Specification 5.6.5. As required by Technical Specification 5.6.5, 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 6.6 describe the LOCA analysis for rated power. The analysis was performed with a methodology that results in Single Loop Operation being adequately covered by Two Loop Operation. The thermal limits for all fuel types for Single Loop Operation are the same as Two Loop Operation. The thermal limits for fuel given in this report are documented in the "WNP-2 Cycle 13 Reload Report" (Reference 6.3), the "WNP-2 Cycle 13 Transient Analysis Report" (Reference 6.4),

and Reference 6.5. The basis for power to flow map which addresses the instability operating region limits is documented in Reference 6.3.

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 throughout the WNP-2 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 WNP-2 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%.

Preparation, review, and approval of this report were performed in accordance with applicable Supply System procedures. The specific topical report revisions and supplements which describe the methodology utilized in this cycle specific analysis are referenced in Technical Specification 5.6.5.

Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.0 AVERA E PLANAR LINEAR HEAT ENERATI N RATE APLH R LIMITS FOR U E IN TE HNI AL SPE IFICATI N 3.2.1 The APLHGRs for use in Technical Specification 3.2.1, as a function of Average Planar 0

Exposure, shall not exceed the limits shown in the following figures when in two loop or single loop operation:

a. Figure 2.1 - SPC 9x9-9X reload fuel
b. Figure 2.2 - ABB SVEA-96 reload fuel Washington Nuclear - Unit 2 COLR 97-13, Revision 0

14.5 Two Loop and Single Loop Operation 14 13.5 13 12.5 12 11.5 11 10.5 10 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure lMWd/MTU)

Average Planar Exposure (MWd/MTU) MAPLHGR (ICW/ft) 12.5 15500 12.5 45000 9.3 55000 7.9 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure SPC 9x9-9X Figure 2.1 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

14.5 Two Loop and SingIe Loop Operation 14 13.5 13 12.5 12 11.5 11 10.5 10 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure {IVIWd/NITUI Average Planar Exposure (MWd/MTU) MAPLHGR (kW/ft) 9.3 9.3 14000 9.0 18000 8.5 8.5 8.4 59000 8.0 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Versus Average Planar Exposure ABB SVEA-96 Figure 2.2 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.0, MINIMUM RITI AL POWER RATI MCPR LIMITFOR USE IN TECHNICAL PE IFICATION3.2.2 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 3.31 through 3.34. For the purposes of cycle extension, the feedwater temperature entering the reactor vessel should not be reduced to less than 355'F. The MCPR limits given apply to both two loop and single loop operation.

The MCPR safety limit for SPC 9x9-9X is 1.13 for two loop operation and 1 14 for single

~

loop operation. Note: ATRIUM-9Xand SPC 9x9-9X are equivalent terms for the same fuel type and may be used interchangeably.

The MCPR safety limit for SVEA-96 is 1.07 for two loop operation and 1.08 for single loop operation.

The MCPR safety limits are applicable to Cycle 13 only.

Washington Nuclear - Unit 2 COLR 97-13, Revision 0

Table 3.1a WNP-2 Cycle 13 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Operable Cycle Exposure ( 5000 MWd/MTU SLMCPR = 1 13 (2) SLMCPR = 1 07 (2)

SPC ABB Condition Limit 9x9-9X SVEA-96 NSS (1) Full Power 1.40 (3) 1.30 (3)

Flow Dependent (4) Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.3 Fig. 3.7 TSSS (1) Full Power 1.40 (3) 1.31 Flow Dependent (4) Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.11 Fig. 3.15 NSS (1) Full Power 1.40 (3) 1.30 (3)

RPT Inop. Flow Dependent (4) Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.27 Fig. 3.31 Washington Nuclear - Unit 2 COLR 97-13, Revision 1

Table 3.1b WNP-2 Cycle 13 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Operable Cycle Exposure ) 5000 MWd/MTU SLMCPR SLMCPR 1.13 (2) 1.07 (2) 1 13 (2) 1.07 (2)

SPC ABB SPC ABB Condition Limit 9x9-9X SVEA-96 9x9-9X SVEA-96 NSS (1) Full Power 1.40 (3) 1.33 1.40 (3) 1.33 Flow Dependent (4) Fig. 3.1 Fig. 3.2 Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.4 Fig. 3.8 Fig. 3.19 Fig. 3.21 TSSS (1) Full Power 1.42 1.38 1.42 1.38 Flow Dependent (4) Fig. 3.1 Fig. 3.2 Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.12 Fig. 3.16 Fig. 3.23 Fig. 3.25 t

NSS (1) Full Power 1.44 1.38 RPT Inop. Flow Dependent (4) Fig. 3. 1 Fig. 3.2 Not Analyzed Power Dependent(5) Fig. 3.28 Fig. 3.32 Washington Nuclear - Unit 2 COLR 97-13, Revision 1

Table 3.2a WNP-2 Cycle 13 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Inoperable Cycle Exposure < 5000 MWd/MTU SLMCPR = 1 13 (2) SLMCPR = 1.07 (2)

SPC ABB Condition Limit 9x9-9X SVEA-96 NSS (1) Full Power 1.40 (3) 1.30 (3)

Flow Dependent (4) Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.5 Fig. 3.9 TSSS (1) Full Power 1.40 (3) 1.34 Flow Dependent (4) Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.13 Fig. 3.17 NSS() Full Power 1.40 (3) 1.31 RPT Inop. Flow Dependent (4) Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.29 Fig. 3.33 Washington Nuclear - Unit 2 COLR 97-13, Revision 1

Table 3.2b WNP-2 Cycle 13 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Inoperable Cycle Exposure ) 5000 MWd/MTU SLMCPR SLMCPR 1.13 (2) 1.07 (2) 1.13 (2) 1.07 (2)

SPC ABB SPC ABB Condition Limit 9x9-9X SVEA-96 9x9-9X SVEA-96 Full Power 1.41 1.36 1.42 1.38 NSS (1)

Flow Dependent (4) Fig. 3.1 Fig. 3.2 Fig. F 1 Fig. 3.2 Power Dependent (5) Fig. 3.6 Fig. 3.10 Fig. 3.20 Fig. 3.22 Full Power 1.45 1.41 1.46 1.41 TSSS (1)

Flow Dependent (4) Fig. 3.1 Fig. 3.2 Fig. 3.1 Fig. 3.2 Power Dependent (5) Fig. 3.14 Fig. 3.18 Fig. 3.24 Fig. 3.26 NSS() Full Power 1.46 1.41 RPT Inop. Flow Dependent (4) Fig. 3.1 Fig. 3.2 Not Analyzed Power Dependent (5)>>g 3 30 Fig. 3.34 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

Notes for Tables 3. la, 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 the ABB transient analysis performed using the control rod insertion times shown below (defined as normal scram speed: NSS). In the event that SRs 3.1.4.1, 3.1.4.2, and 3.1.4.4 show these scram insertion times have been exceeded, the MCPR limit shall be determined from the applicable Technical Specification Scram Speed (TSSS) MCPR limits in Tables 3.1a, 3.1b, 3.2a, and 3.2b.

Slowest measured average control rod insertion times to specified notches for all operable control rods for Position Inserted each group of four control rods arranged in a two-by-From Full Withdrawn two arra seconds Notch 45 0.430 Notch 39 0.720 Notch 25 1.600 Notch 5 2.950 Note 2: For Single Loop Operation (SLO), the SLMCPR increases by 0.01. The increase is included in the MCPR operating limits.

Note 3: For the noted full power MCPR limits, the Rod Withdrawal Error (RWE) event is limiting. When turbine bypass is operable, the Generator Load Rejection No Bypass (GLRNB) event is limiting for the full power limits. When turbine bypass is inoperable, the Feedwater Controller Failure No Bypass (FWCFNB) event is limiting for the full power limits. The RWE analysis was performed with a nominal Rod Block Monitor (RBM) setpoint of 1.06.

Note 4: Flow dependent MCPRs are not applicable for SLO.

Note 5: 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, respectively. 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.

Washington Nuclear - Unit 2 COLR 97-13, Revision 0

1.70 Two Loop Operation 1.60 1.50

.~ 1.40 P

1.30 O

O

~ 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Total Core Flow {% Rated)

Total Core How Rate Operating LimitMCPR 108.5Fo 1.13 809o 1.37 20% 1.69 Reduced Flow MCPR Operating Limit Versus Total Core Flow SPC 9x9-9X Figure 3.1 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

1.60 Two Loop Operation 1.50 1.40 E

1.30 a

0 o

o 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Total Core Flow (% Rated)

Total Core Flow Rate Operating Limit MCPR 108.5% 1.07 80% 1.18 20% 1.37 Reduced Flow MCPR Operating Limit Versus Total Core Flow ABB SVEA-96 Figure 3.2 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 5

1.80 C

1.70 1.60 o 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.31 30% 1.57 Core Flow M<0%, Power <30%o 30% 2.10 25% 2.20 Core Flow >50%, Power <30% 30%o 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures 55000 MWd/MTU, Figure 3.3 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 I

1.80 C

1.70 1.60 o 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Range Power Operating Limit MCPR All Core Flows, Power >30% 1009o 1.38 309o 1.58 Core Flow <M0%, Power <30% 30% 2.10 2.20 Core Flow > 50%, Power 530% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures >5000 MWd/MTU Figure 3.4 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10

.c= 2.00 1.90 O 1.80 n- 1.70 O

~ 1.60

~

1.50 1.40 1.30 1.20 1.10 1.00

. 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.33 30% 1.65 Core Flow 550%, Power <30% 30% 2.50 2.60 Core Flow ) 50%, Power <30% 30% 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures 55000 MWd/MTU Figure 3.5 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10

.c= 2 00 1.90 CL 0 1.80

a. 1.70 2 1.60 1.50 1.40 1.30 1.20 1 ~ 10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Range Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.41 309o 1.68 Core Flow &<Ohio, Power <309o 309o 2.50 2.60 Core Flow ) 50%, Power 5309o 30fo 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures >5000 MWd/MTU Figure 3.6 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1 ~ 10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 1009o 1.33 30% 1.55 Core Flow <50Fo, Power <30% 30Fo 2.10 2.20 Core Flow ) 50%, Power <30Fo 30Fo 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures >5000 MWd/MTU Figure 3.8

%washington NUclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100%

30% 1.53 Core Flow <M0%, Power <30% 30% 2.10 2.20 Core Flow >50%, Power 530% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures <5000 MWd/MTU Figure 3.7 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2;20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100% 1.27 30% 1.63 Core Flow M<0%, Power 530% 30% 2.50 2.60 Core Flow >50%, Power <30% 30% 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures <5000 MWd/MTU Figure 3.9 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50

'l .40 1.30 1.20 1 10

~

1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100% 1.36 30% 1.67 Core Flow <50%, Power <30% 30% 2.50 2.60 Core Flow >50%, Power <30% 30% 2.90 3.00 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures >5000 MWd/MTU Figure 3.10 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2AO 2.30 2.20 2.10 2.00 1.90 1.80 C

5 1.70 a

0 1.60 o 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 1.36 30% 1.58 Core Flow <M0%, Power <30% 30% 2.10 2.20 Core Flow ) 50%, Power 530% 30% 2.40 25% 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures <5000 MWd/MTU Figure 3.11 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Singie Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 E

1.80 C

1.70 O 1.60 o 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 307o 1009o 1.42 309o 1.59 Core Flow <&0%, Power 5309o 309o 2.10 2.20 Core Flow ) 509o, Power 5309o 30Fo 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures >5000 MWd/MTU Figure 3.12 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 6

220 2.10 g 200 1.90 O 1.80

n. 1.70 O

1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100% 1.38 30% 1.68 Core Flow <M0%, Power <30% 30% 2.50 2.60 Core Flow >50%, Power <30% 30% 2.90 25%

Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures 55000 MWd/MTU Figure 3.13 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10

.F 2.00 P) 1.90 o 1,80 n- 1.70 C3 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power )30% 100% 1.45 30% 1.70 Core Flow <&0%, Power 530% 30% 2.50 25% 2.60 Core Flow )50%, Power 530% 30% 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures >5000 MVd/MTU Figure 3.14 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.31 30% 1.56 Core Flow <M0%, Power <30% 30% 2.10 2.20 Core Flow > 50%, Power <30% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures <5000 MWd/MTU Figure 3.15 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 80 100 1'l0 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100Fo L38 30Fo 1.56 Core Flow &0%, Power 530% 30% 2.10 2.20 Core Flow >50%, Power <30% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures >5000 MWd/MTU Figure 3.16 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power )30% 100% 1.34 30% 1.66 Core Flow &0%, Power <30% 30% 2.50 25% 2.60 Core Flow ) 50%, Power 530% 30% 2.90 3.00 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures <5000 MWd/MTU Figure 3.17 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1 ~ 10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR AII Core Flows, Power ) 309o 1009o 1 41 309o 1.69 Core Flow &0%, Power 530% 309o 2,50 2.60 Core Flow ) 50%, Power <309o 309o 2.90 3,00 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures >5000 MWd/MTU Figure 3.18 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 E

1.80 C

1.70 o 1.60 IX!

o 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 '80 90 100 1 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 309o 100% 1.38 30% 1.64 Core Flow <MOFo, Power 5309o 30% 2.10 2.20 Core Flow ) 50%, Power 530% 309o 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X FFTR Operation Figure 3.19 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 c 2,00 1.90 Q 1.80 n- 1.70 O

~ 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power )309o 100Fo 1.42 309o 1.73 Core Flow <MOD, Power <30Fo 309o 2.50 2.60 Core Flow ) 509o, Power <309o 309o 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X FFTR Operation Figure 3.20 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1 ~ 60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power )30% 100% 1.33 30% 1.63 Core Flow M0%, Power <30% 30% 2.10 2.20 Core Flow ) 50%, Power <30% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 FFTR Operation Figure 3.21 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

~ ~

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.38 30% 1.74 Core Flow <50%, Power 530% 30% 2.50 25% 2.60 Core Flow ) 50%, Power <30%o 30% 2.90 3.00 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 FFTR Operation Figure 3.22 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 C

1.70 CL O 1.60 o 1.50 Z

1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 309o 1009o 1.42 30Fo 1.64 Core Flow <MOD, Power 5309o 30Fo 2.10 2.20 Core Flow )50Fo, Power <309o 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X FFTR Operation Figure 3.23 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2

2.20 2.10

,F 2,00 1.90 a

0 1.80

a. 1.70 O

2 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 1009o 309o 1.74 Core Flow &0%, Power <309o 309o 2.50 25~o 2.60 Core Flow )509o, Power <30% 309o 2.90 3.00 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X FFTR Operation Figure 3.24 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% L38 30% 1.63 Core Flow &0%, Power <30% 30% 2.10 25% 2.20 Core Flow ) 50%, Power <30% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 FFTR Operation Figure 3.25 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.41 30% 1.75 Core Flow &0%, Power 530%o 30% 2.50 2.60 Core Flow ) 50%, Power 530% 30% 2.90 25%

Reduced Power MCPR Operating Limit Versus Percent of Rated Power TSSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 FFTR Operation Figure 3.26 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Singte Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 E

g) 1.80 C

1.70 O 1.60 o 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.36 30% 1.54 Core Flow M<0%, Power 530% 30% 2.10 2.20 Core Flow ) 50%, Power 530% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures <5000 MWd/MTU

"

Figure 3.27 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2AO 2.30 2.20 2.10 2.00 1.90 I

1.80 C

1.70 Q

O 1.60 u 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100%o 30%o 1.57 Core Flow <M0%, Power 530% 30% 2.10 2.20 Core Flow >SO%, Power 530% 30% 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures >5000 MVd/MTU Figure 3.28 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 E

2.20 2.10 c 200 1.90 O 1.80 n- 1.70 O

1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 1009o 1.38 30Fo 1.66 Core Flow <&0%, Power <30% 30Fo 2.50 2.60 Core Flow )509o, Power <309o 30Fo 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures 55000 MWd/MTU Figure 3.29 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00

,

2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 E

2.20 2.10

,F 2.00 1.90 O 1.80 n- 1.70 D

2 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Range Power Operating LimitMCPR All Core Flows, Power ) 30% 100% 1.46 30% 1.72 Core Flow <&0%, Power 530% 30% 2.50 2.60 Core Flow ) 50%, Power 530% 30% 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures >5000 MWd/MTU Figure 3.30 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operatmg Limit MCPR All Core Flows, Power ) 30% 100fo 1.29 309o 1.50 Core Flow <M0%, Power <30% 30% 2.10 2.20 Core Flow ) 50%, Power 530Fo 30Fo 2.40 2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures 65000 MWd/MTU Figure 3.31 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

2.50 e

Two Loop and Single Loop Operation 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 1009o 1.38 309o 1.52 30% 2.10 Core Flow <M0%, Power <30%

2.20 30fo 2.40 Core Flow >50%, Power <30%

2.50 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures >5000 MWd/MTU Figure 3.32 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power ) 30% 100% 1.31 30% 1.63 Core Flow M<0%, Power <30% 30% 2.50 2.60 Core Flow ) 50%, Power <30% 30% 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures 55000 MWd/MTU Figure 3.33 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

i" 3.00 2.90 Two Loop and Single Loop Operation 2.80 2.70 2.60 2.50 2.40 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Percent of Rated Power Power Operating Limit MCPR All Core Flows, Power >30% 100%o 30% 1.70 Core Flow <&0%, Power 530% 30% 2.50 25% 2.60 Core Flow >50%o, Power <30% 30%o 2.90 Reduced Power MCPR Operating Limit Versus Percent of Rated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures >5000 MWd/MTU Figure 3.34 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

4.0 LINEAR HEAT GENERATI N RATE H R LIMITS FOR USE IN TECHNICAL SPECIFICATI'ON 2 The LHGRs for use in Technical Specification 3.2.3, as a function of Average Planar Exposure, shall not exceed the limits shown in the following figures:

a. Figure 4.1 - SPC 9x9-9X reload fuel
b. Figure 4.2 - ABB SVEA-96 reload fuel Washington Nuclear - Unit 2 COLR 97-13, Revision 0

17 16 15 14 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWd/MTU)

Average Planar Exposure (MWd/MTU) LHGR (ICW/ft) 0 ~ 13.1 15500 13.1 7.3 Linear Heat Generation Rate (LHGR) Versus Average Planar Exposure SPC 9x9-9X Figure 4.1 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

17 16 15 13 1 2 E

11 C9 x

10 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWd/MTU)

Average Planar Exposure (MWd/MTU) LHGR (kW/ft) 13.4 13950 10.9 59000 7.3 Linear Heat Generation Rate (LHGR) Versus Average Planar Exposure ABB SVEA-96 Figure 4.2 Washington Nuclear - Unit 2 COLR 97-13, Revision 0

5.0 P WER FL W IN TABILITY The power/flow conditions for use in Technical Specification 3.4.1 shall conform to the limits

.

shown in Figure 5.1.

Washington Nuclear - Unit 2 COLR 97-13, Revision 0

80 70 (4QF. 5k 1P)

Regs A (45@, CLIP) 80 g

0'0 cj 30 20 20 35 40 50 Core Flaw (S Rated)

Operating Region Limits of Specification 3.4.1 Figure 5.1 Note: Applicable up to and including 3000 MWD/MTU Washington Nuclear - Unit 2 COLR 97-13, Revision 0

6.0 ~HE NC 6.1 NEDO-32269, "Washington Public Power Supply System Nuclear Project 2, Supplement to SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis,"

GE Nuclear Energy, September 1993.

6.2 Letter, Kaveh Taghavi (GE) to J. D. Fisher (WPPSS), "Extended MAPLHGR Curve for SNP 9x9-9X," October 4, 1995.

6.3 CE NPSD-821-P, Rev. 3, "WNP-2 Cycle 13 Reload Report,".ABB Combustion Engineering Nuclear Operations, July 1997.

6.4 CE NPSD-820-P, "WNP-2 Cycle 13 Transient Analysis Report," ABB Combustion Engineering Nuclear Operations, April 1997.

6.5 Letter KVW-95:050, K. V. Walters (Siemens Power Corporation) to R. A. Vopalensky (WPPSS), "WNP-2 Fuel Misorientation Error -Analysis,"

October 16, 1995.

6.6 CE NPSD-801-P, "WNP-2 LOCA Analysis Report," ABB Combustion Engineering Nuclear Operations, May 1996,

,

Washington Nuclear - Unit 2 COLR 97-13, Revision I