ML17284A900
| ML17284A900 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/31/1999 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
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| References | |
| COLR-99-15, COLR-99-15-R00, NUDOCS 9910260108 | |
| Download: ML17284A900 (67) | |
Text
COLR 99-15, Revision 0 Controlled Copy No.
WNP-2 Cycle 15 Core Operating Limits Report October 1999 Energy Northwest eqaoaeo<08 eqaoa~n.
PDR ADGCK 05000397 P
l I
Cycle 15 Core Operating LimitsReport LIST OF EFFECTIVE PAGES PAGE REVISION 10 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27
Cycle 15 Core Operating LimitsReport LIST OF EFFECTIVE PAGES PAGE REVISION 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 0
LEP WNP-2 Cycle 15 Core Operating Limits Report TABLEOF CONTENTS
1.0 INTRODUCTION
AND
SUMMARY
2.0 AVERAGEPLANARLINEARHEAT GENERATION APLHGR LIMITSFOR USE INTECHNICALSPECIFICATION 3.2.1 3.0 CRITICALPOWER RATIO CPR LIMIT FOR USE INTECHNICALSPECIFICATION 3 2 2 4.0 LINEARHEAT GENERATIONRATE HGR LIMITS FOR USE INTECHNICALSPECIFICATION 3.2 3 5.0 POWER/FLOW INSTABILITY
6.0 REFERENCES
48 51 53 Washington Nuclear - Unit 2 COLR 99-15, 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 Power to Flow Map for WNP-2, Cycle 15 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 6.4 describe the LOCA analysis for rated power.
The analysis was performed with a methodology that results in Single Loop Operation APLHGR limits as well as Two Loop Operation APLHGR LIMITS. The thermal limits for fuel given in this report are documented in the "WNP-2 Cycle 15 Reload Licensing Report" (Reference 6.3) and Reference 6.5. The basis for the power to flow map which addresses the instability operating region limits is documented in Reference 6.3.
The MCPR limitis the maximum of(a) the applicable exposure dependent, fullpower and fullflow 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 willnot 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. Aflow dependent MCPR is specified to define operating limits at other than rated flow conditions.
The reduced flowMCPR 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% ofrated 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 Energy Northwest 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 99-15, Revision 0
2.0 AVERAGE PLANARLINEARHEAT GENERATION RATE APLHGR LIMITS FOR USE INTECHNICALSPECIFICATION 3.2.1 The APLHGRs for use in Technical Specification 3.2.1, as a function ofAverage Planar Exposure, shall not exceed the limits shown in the followingfigures:
a.
Figure 2.1 - SPC 9x9-9X reload fuel b.
Figure 2.2 - ABB SA-and SB-Type SVEA-96 reload fuel - Two Loop Operation c.
Figure 2.3 - ABB SA-and SB-Type SVEA-96 reload fuel - Single Loop Operation d.
Figure 2.4 - ABB SC-and SD-Type SVEA-96 reload fuel - Two Loop Operation e.
Figure 2.5 - ABB SC-and SD-Type SVEA-96 reload fuel Single Loop Operation Washington Nuclear - Unit 2 COLR 99-15, 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 Average Planar Exposure (MWdlMTU) 50000 60000 Average Planar Exposure (MWd/MTU) 0 15500 45000 55000 MAPLHGR(kW/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 COLR 99-15, Revision 0
14.5 14 13.5 13 12.5 12 11.5 CC 11 10.5 Two Lop 0 ration 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average'Planar Ezposure (MWd/MTO)
Average Planar Ezposure (MWd/MTU) 5000 9000 12000 16000 20000 30000 42000 50000 59000 MAPLHGR(kW/ft) 9.6 9.5 9.3 9.2 8.9 8.7 8.6 8.6 8.5 8.0 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure - Two Loop Operation ABB SA-and SB-Type SVEA-96 Figure 2.2 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
14.5 14 13.5 13 12.5 12 lee 11.5 11 CC 10.5 Sin leloo 0 ration 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWd/MTU)
Average Planar Exposure (MWd/MTU) 0 5000 9000 12000 16000 20000 30000 42000 50000 59000 MAPLHGR(kW/ft) 9.3 9.2 9.0 8.9 8.6 8.3 8.3 8.3 8.2 7.8 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure - Single Loop Operation ABB SA-and SB-Type SVEA-96 Figure 2.3 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
14.5 14 13.5 13 12.5 12 11.5 ll CC 10.5 10 9.5 7woLoo 0 ration 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWd/MTO)
Average Planar Exposure (MWd/MTU) 5000 9000 10000 12000 16000 20000 30000 42000 50000 54000 59000 MAPLHGR(kW/ft) 9.8 9.9 9.7 9.6 9.4 9.1 8.9 8.8 8.8 8.7 8.5 8.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure - Two Loop Operation ABB SC-and SD-Type SVEA-96 Figure 2.4 Washington Nuclear - Unit 2 CQLR 99-15, Revision 0
14.5 14 13.5 13 12.5 12 11.5 11 i'0.5 Si leLoo 0 ratio 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWd/MTU)
Average Planar Exposure (MWd/MTU) 5000 9000 10000 12000 16000 20000 30000 42000 50000 54000 59000 MAPLHGR(kW/ft) 9.4 9.6 9.4 9.3 9.1 8.7 8.5 8.4 8.4 8.3 8.2 7.9 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure - Single Loop Operation ABB SC-and SD-Type SVEA-96 Figure 2.5 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.0 MINIMUMCRITICALPOWER RATIO CPR LIMITFOR 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 3.34. For the purposes ofcycle extension, the feedwater temperature entering the reactor vessel shall 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 1.10 for two loop operation and 1.11 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 1.10 for two loop operation and 1.12 for single loop operation.
Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Table 3.1a
%NP-2 Cycle 15 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Operable Cycle Exposure <9000 MWd/MTU SLMCPR = 1 10 (2)
SLMCPR = 1 10 (2)
Condition Limit SPC 9x9-9X ABB SVEA-96 NSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.39 (3)
Fig. 3.1 Fig. 3.3 1.33 (3)
Fig. 3.2 Fig. 3.7 TSSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.39 (3)
Fig. 3.1 Fig. 3.1 1 1.33 (3)
Fig. 3.2 Fig. 3.15 NSS (1)
RPT Inop.
FullPower Flow Dependent (4)
Power Dependent (5) 1.39 (3)
Fig. 3.1 Fig. 3.27 1.33 (3)
Fig. 3.2 Fig. 3.31 Washington Nuclear - Unit 2 9
COLR 99-15, Revision 0
Table 3.1b WNP-2 Cycle 15 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Operable Cyde Exposure >9000 MWd/MTU SLMCPR SLMCPR 1.10 (2) 1.10 (2) 1.10 (2) 1.10 (2)
Condition Limit SPC 9x9-9X ABB SVEA-96 SPC 9x9-9X ABB SVEA-96 NSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.39 Fig. 3.1 Fig. 3.4 1.40 Fig. 3.2 Fig. 3.8 1.39 Fig. 3.1 Fig. 3.19 1.40 Fig. 3.2 Fig. 3.21 TSSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.42 Fig. 3.1 Fig. 3.12 1.43 Fig. 3.2 Fig. 3.16 1.42 Fig. 3.1 Fig. 3.23 1.43 Fig. 3.2 Fig. 3.25 NSS (1)
RPT Inop.
Full Power'low Dependent (4)
Power Dependent (5) 1.45 Fig. 3.1 Fig. 3.28 1.45 Fig. 3.2 Fig. 3.32 Not Analyzed Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Table 3.2a WNP-2 Cycle 15 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Inoperable Cycle Ezposure <9000 MWd/MTU SLMCPR = 1 10 (2)
SLMCPR = 1 10 (2)
Condition Limit SPC 9x9-9X ABB SVEA-96 NSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.39 (3)
Fig. 3.1 Fig. 3.5 1.33 (3)
Fig. 3.2 Fig. 3.9 TSSS (1)
Full Power Flow Dependent (4)
Power Dependent (~)
1.39 (3)
Fig. 3.1 Fig. 3.13 1.37 Fig. 3.2 Fig. 3.17 NSS(1)
RPT Inop.
FullPower Flow Dependent (4)
Power Dependent (5) 1.39 (3)
Fig. 3.1 Fig. 3.29 1.33 (3)
Fig. 3.2 Fig. 3.33 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Table 3.2b WNP-2 Cycle 15 MCPR Operating Limits Two Loop and Single Loop Operation Turbine Bypass System Inoperable Cycle Exposure >9000 MWd/MTU SLMCPR SLMCPR 1.10 (2) 1.10 (2) 1.10 (2) 1.10 (2)
Condition Limit SPC 9x9-9X ABB SVEA-96 SPC 9x9-9X ABB SVEA-96 NSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.42 Fig. 3.1 Fig. 3.6 1.44 Fig. 3.2 Fig. 3.10 1.45 Fig. 3.1 Fig. 3.20 1.46 Fig. 3.2 Fig. 3.22 TSSS (1)
Full Power Flow Dependent (4)
Power Dependent (5) 1.45 Fig. 3.1 Fig. 3.14 1.47 Fig. 3.2 Fig. 3.18 1.48 Fig. 3.1 Fig. 3.24 1.48 Fig. 3.2 Fig. 3.26 NSS (1)
RPT Inop.
Full Power Flow Dependent (4)
Power Dependent ( )
1.48 Fig. 3.1 Fig. 3.30 1.48 Fig. 3.2 Fig. 3.34 Not Analyzed Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Notes for Tables 3. la, 3.1b, 3.2a, and 3.2b
'ote'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, 3.1.4.3 and 3.1.4.4 show the NSS 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.
The NSS and TSSS MCPR limits include up to eight declared "slow" rods.
Position Inserted From Fully Withdrawn Notch 45 Notch 39 Notch 25 Notch 5 Slowest measured average control rod insertion times (seconds) to specified notches for all operable control rods for each group offour control rods arranged in a two-by-two array. (Excluding rods which have been declared "slow" and that meet the "slow" control rod se aration criteria.
0.430 0.720 1.600 2.950 Note 2:
For Single Loop Operation (SLO), the 9x9-9x SLMCPR increases by 0.01 and the SVEA-96 SLMCPR increases by 0.02. The increases are included in the MCPR operating limits.
Note 3:
For the noted full power MCPR limits, the 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:
Note 5:
Flow dependent MCPRs are not applicable for SLO.
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% ofrated 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 99-15, Revision 0
1.70 Ywo Loo 0 ration 1.60 1.50 n
~W E
1.40 K
gg 1.30 V
1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Total Core Flow (% Rated)
Total Core Flow Rate 108.5%
80 20%
Operating LimitMCPR 1.10 1.34 1.69 Reduced Flow MCPR Operating LimitVersus Total Core Flow SPC 9x9-9X Figure 3.1 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
1.70 Two Lop 0 ration 1.60 1.50 j
1.40 Og 1.30 V
1.20 1.10 1.00 20 30 40 50 60 70 80 90 100 110 Total Core Flow (% Rated)
Total Core Flow Rate 108.5%
80%
20%
Operating LimitMCPR 1.10 1.27 1.48 Reduced Flow MCPR Operating LimitVersus Total Core Flow ABB SVEA-96 Figure 3.2 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Toro Loop and Slnglo Loop Opcrauon 2.20 2.10 2.00 1.90
~c 1.80 o41.60 X
1.50 1.10 60 70 Pcrccnt ofRaced Power 80 90 100 110 Range AllCore Flows, Power >30%
Core'Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.26 1.58 2.20 2.30 2.40 2.50 A
Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures <9000 MWd/MI'U Figure 3.3 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Slnglc Loop Opcratlon 2.10 2.00 1.00 1.80 e
o" 1.70 1.60 1.30 1.30 1.10 30 40 30 60 70 Prrcrnt oCRolrd Power 80 100,1) 0 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP 3P 30%
25%
30%
25%
Operating LimitMCPR 1.39 1.59 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures >9000 MWd/MTU Figure 3.4 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.00 2.50
- 2. 80 2.70 2.60 2.50 2.40 2.30 2.20 I
w 2.10 I 200 Im 1.80
~
1.70 1.60 1.50 1.40 130 1.20 1.10 1.00 20 30 40 50 60 70 80 100 IIO Two Loop and Slnglo Loop Opcratlon Pereeol ofRoled Power Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.29 1.63 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures <9000 MWd/MTU Figure 3.5 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
2.80 2.70 2.60 2.30 Two Loop and Single Loop Opentlon 2.40 2.30 g
2.20 E
~
2.10 j 200 o
1.30 v
1.80 1.70 1.60 1.30 1AO 1.30 1.20 1.10 1.00 20 30 60 70 Pcrccot ofRated Power 80 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.42 1.76 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures >9000 MWd/MTU Figure 3.6 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Operation 2.10 2.00 1.90
~e 1.80 1.70 1.60 1.50 1.40 1.10 60 70 Percent ot'Rated Power 80 100 110
'Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.27 1.59 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures <9000 MWd/MTU Figure 3.7 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Operation 2.10 2.00 I.IO cc 1.80 c
1.70 1.60 X
1.50 1.10 60 70 Pcrccnt ofRated Power 80 100 110 Range
'll Core Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
2 Operating LimitMCPR 1.40 1.60 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures >9000 MWd/MTU Figure 3.8 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.00 2.90 2.80 2.70 2.60 2.30 2.40 2.30 w 2.20
~
2.10
( 200 O
I.90 vL1.80 1.70 1.60 I.$0 1.40 1.30 1.20 1.10 1.00 Two Loop and Single Loop Operation 60 70 Pcrccoc ol'Rolcd Power 80 90 100 110
'ange AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.31 1.65 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures <9000 MWd/MTU Figure 3.9 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Operauon 2.70 2.60 2.50 2.40
~<<2.20 2 XX o
2.10
$ 200 1.80 1.70 1.60 1.50 1AO 1.30 1.20 1.10 1.00 50 60 70 Percent ofRated Power 80 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.44 1.76 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures >9000 MWd/MTU Figure 3.10 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Operation 2.30 2.10 2.00 1.90 8
cc 1.80 v
1.60 X
1.30 1.10 20 60 70 Pcrccnt ofRated Power 80 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100 30%
30%
25%
30%
25%
Operating LimitMCPR 1.31 1.57 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures <9000 MWd/MTU Figure 3.11 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Sirqgc Loop Operation 2.10 2.00 I.PO
~c 1.80 1.70 v
1.60 X
I.SO 1.10 30 do IO Pcrccnt ofRaced Power 80 90 100 IIO Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.42 1.58 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures >9000 MWd/MTU Figure 3.12 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.00 2.90 2.80 2.70 2.60 2.30 2AO g
2.30 2.20 c 210
<~ 200 o
1.00 v
1.80 X 170 1.60 1.30 1.40 1.30 1.20 1.10 1.00 20 30 60 70 Pcrccnt ofRated Pocccr 100 I I0 Two Loop and Single Loop Operation
'Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.35 1.69 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures <9000 MWd/MTU Figure 3.13 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3coo 2.30 280 2.70 2.60 2.$0 2AO g
2.30 2 220 2.10 f 2.00 o uo v41.80 X 170 1.60 1.30 1.40 1.30 1.20 1.10 1.00 Two Loop and Slnglc Loop Operation 30 60 70 80 Percent ofRated Pocccr 90 100 110 Range '.
AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.45 1.77 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures >9000 MWd/MTU Figure 3.14 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Tao Loop antt Single Loop Opcratfott 2.10 2.00 E
1.90 oo 1.80 1.70 I,
~o1.10 X
1.50 1.20 1.10 30 40 Porcrnt ofRated Power 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.33 1.59 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures <9000 MWd/MTU Figure 3.15 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Yeeo Loop and Single Loop Operation 2.20 2.10 2.00 1.90 1.80 e~ 1.70 1.60 1.60 1.10 20 50 60 70 80 Percent ofRated Power 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25'/0 30/0 25%
Operating LimitMCPR 1.43 1.59 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures >9000 MWd/MTU Figure 3.16 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.00 2.90 2.80 2.70 2.60 2.30 2.40 2.30 2.20 2.10 I 2.00 O
I.OO v
180 1.70 1.60 I.SO 140 1.30 1.20 1.10 1.00 20 30 60 70 Pccccnt or Rated Ponce 80 100 IIO Two Loop and Single Loop Opcratfon
- Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.37 1.73 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures <9000 MWd/MTU Figure 3.17 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.00 2.90 2.80 2.70 2.60 2.30 240 g
2.30 2.20 o
2.10
) 2.00 4v1.80 1.70 1.60 1.30 1.40 1.30 1.20 1.10 1.00 20 30 40 30 60 70 80 100 llo Two Loop and Slnglc Loop Opcratlon Pcrccnt ofRated Power Range'll Core Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
250io 30%
25%
Operating LimitMCPR 1.47 1.77 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures >9000 MWd/MTU Figure 3.18 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Tcco Loop and Single Loop Operation 2.20 2.10 2.00 1.90 6
1.$0 e
O 1.70 V~
1.60 X
1.50 1.40 1.10 Pcrccnc ofRated Power 80
)00 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.39 1.63 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X FFTR Operation Figure 3.19 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
2.80 2.70 Two Loop and Single Loop Operation 2.30 2.20 E
e 2.10
<~ 200 O
L5O C
o 1.80
~
L70 1.60 1.50 lAO 1.30 1.20 1.10 1.00 50 60 70 80 Pcrccoc ofRolcd Power 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
250 Operating LimitMCPR 1.45 1.75 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X FFTR Operation Figure 3.20 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Toro Loop attd single Loop opcmnon 2.10 2.00 1.90 8
1.80 c
$ I.70 v
1.60 X
1.50 1.10 20 30
$0 60 70 Percent ofRated Poncr 80 IIO Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25 3000 25 Operating LimitMCPR 1.40 1.64 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 FFTR Operation Figure 3.21 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Operation 2.70 2.30 2 220 a
o 2.10 g~ 200 O
I.IO C
1.80 1.70 1.60 I.SO 1.40 1.30 1.20 1.10 1.00 20 40 50 60 70 Pcrccnt ofRated Power 80 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP 30%
30%
25%
30%
25%
Operating LimitMCPR 1.46 1.78 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 FFTR Operation Figure 3.22 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Slnglc Loop Opcnnon 2.10 2.00 1.90 o
1.80 c
ott 1.70 v
1.60 X
1.50 1.10
'0 70 PcrccnloCRotcd Pocccr 80 100 110
~ Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP 30%
30%
25%
30%
25%
Operating LimitMCPR 1.42 1.62 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Operable, SPC 9x9-9X FFTR Operation Figure 3.23 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
2.90 2.80 Two Loop antt single Loop Opcratlon 2.70 2.60 2.50 2.40 g
2.30 2 220 6
2.10
$ Zoo o
1.90 4v1.80 X 170 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 50 60 70 Pcrcc ot ofRated Power 80 90 100 110
.Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.48 1.76 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Inoperable, SPC 9x9-9X FFTR Operation Figure 3.24 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Slnglt Loop Opcrauon 2.10 2,00 1.90 E
1.80 1.70 R.
o 1.60 X
1.50 1.10 60 70 Pcrccnt ofRaced Power 80 90 100 110 Range AllCore Flows, Power >30%
Cor'e Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.43 1.63 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Operable, ABB SVEA-96 FFTR Operation Figure 3.25 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3,00 2.90 2.80 Two Loop antt Slttgle Loop Operation 2.50 240 2.30 2 220 E
o 2.10
<~ 200 1.9O o418O 1.70 1.60 I.SO IAO 1.30 1.20 1.10 1.00 20 60 70 Percent ofRated Power 80 90 100 llo Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.48 1.78 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, Turbine Bypass Inoperable, ABB SVEA-96 FFTR Operation Figure 3.26 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Operation 2.20 2.10 2.00 I.90 1.$0 e
0 1.70 40I.60 X
I.SO 1.10 60 70 Pcrccnc ofRotcd Pocccr 80 100 IIO
. Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.30 1.54 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures <9000 MWd/MTU Figure 3.27 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Ttro Loop and Single Loop Operation 2.10 2.00 1.90 6
1.80 1.70 v
1.60 X
I.SO 1.10 20 60 70 Pcrccnt ofRated Power 80 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 1PP%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.45 1.59 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus'Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Operable, SPC 9x9-9X Cycle Exposures >9000 MWd/MTU Figure 3.28 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
3.00 2.90 2.80 2.70 2.30 2.40 2.30 2.20 2.10
$ 200 0
1.P0 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 1.00 20 60 70 Pcrccnt ofRated Power 80 100 Two Loop and Singlo Loop Opcratlon 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.33 1.65 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures <9000 MWd/MTU Figure 3.29 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
'3.00 2.90 2.80 2.70 2.60 2.50 2AO
~
2.30
~ Xm o
2.10
$ 2.00 V 180 1.70 1.60 1.50 1.40 130 1.20 1.10 1.00 Two Loop and Single Loop Operation 60 70 Pccccnt orRctcd Pocccc 80 90 100 I lo
~ Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.48 1.80 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, SPC 9x9-9X Cycle Exposures >9000 MWd/MTU Figure 3.30 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Opccauon 2.10 2.00 1.00
~c 1.80 v
1.60 X
1.50 1.10 50 60 70 80 Pcrccnt ofRated Power 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
25%
Operating LimitMCPR 1.29 1.55 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures <9000 MWd/MTU Figure 3.31 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Two Loop and Single Loop Opcratlott 2.30 2.10 2.00 1.90 1.80 e
o v
1.60 X
1.30 1.10 60 70 Pcrccttt ofRated Power 80 90 100 110 Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100 30%
30%
25%
30%
25%
Operating LimitMCPR 1.45 1.57 2.20 2.30 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Operable, ABB SVEA-96 Cycle Exposures >9000 MWd/MTU Figure 3.32 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
~ o
~r 3.00 2.00 2.80 2.70 2.60 2.30 2.40 2.30 2.20 2.10 j zoo I.OO 4v1.80
~
1.7O 1.60 1.30 1.40 1.30 1.20 1.10 1.00 Two Loop and Single Loop Operation 60 70 Pcrccnc ofRolcd Pocccr 80 100 Ilo
'Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100%
30%
30%
25%
30%
250/
Operating LimitMCPR 1.32 1.66 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures <9000 MWd/MTU Figure 3.33 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Tcco Loop and Single Loop Operation 2.70
<<2.30 2.20 n
2.10
<~ Zoo I.00 1.80 5
170 1.30 1.40 1.30 1.20 1.10 1.00 30 60 70 Pcrccnt o( IIotcd PoNcr 80 90 100 110
. Range AllCore Flows, Power >30%
Core Flow <50%, Power <30%
Core Flow >50%, Power <30%
Power 100 30%
30%
25%
30%
25%
Operating LimitMCPR 1.48 1.78 2.70 2.80 2.90 3.00 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Inoperable, Turbine Bypass Inoperable, ABB SVEA-96 Cycle Exposures >9000 MWd/MTU Figure 3.34 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
4.0 LINEARHEAT GENERATION RATE LHGR LIMITS FOR USE IN TECHNICAL SPECIFICATION 3 2 3 The LHGRs for use in Technical Specification 3.2.3, as a function ofAverage Planar Exposure, shall not exceed the limits shown in the followingfigures:
a.
Figure 4.1 - SPC 9x9-9X reload fuel b.
Figure 4.2 - ABB SVEA-96 reload fuel Washington Nuclear - Unit 2 COLR 99-15, Revision 0
17 16 15 14 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWdiMTU)
Average Planar Exposure (MWd/MTU) 15500 60000 LHGR (kW/ft) 13.1 13.1 7.3 Linear Heat Generation Rate (LHGR) Versus Average Planar Exposure SPC 9x9-9X Figure 4.1 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
17 16 15 14 13 E
12 g
11 10 0
10000 20000 30000 40000 50000 60000 Average Planar Ezposure (MWd/MTU)
Average Planar Ezposure (MWd/MTU) 12628 58087 LHGR (kW/ft) 13.4 10.9 7.2 Linear Heat'Generation Rate (LHGR) Versus Average Planar Exposure ABB SVEA-96 Figure 4.2 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
5.0 POWER/FLOW INSTABILITY 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 CQLR 99-15, Revision 0
/+
~ ~
'0.0 70.0 REGION A 50.0 5o.o REGION B
REGION C
i0.0 U nre stricte d Region 30.0 20.0 20.0 25.0 30.0 35.0 4 0.0 C ore Flow (% Rated) 45.0 50.0 Region A Region B Region C Core Flow Power Core Flow Power Core Flow Power
%Rated
%Rated
% Rated
% Rated
% Rated
% Rated 23.8 32.0 40.0 43.0 45.0 45.0 47.0 48.0 31.3 42.5 56.0 61.3 62.8 65.0 69.5 70.3 23.8 23.8 32.0 36.5 39.0 39.0 31.3 26.3 37.5 45.1 46.7 54.3 39.0 40.0 43.0 45.0 45.0 48.0 48.0 46.7 47.3 49.1 50.3 60.0 66.8 70.3 Operating Region Limits ofSpecification 3.4.1 Figure 5.1 Washington Nuclear - Unit 2 COLR 99-15, Revision 0
0 6.
E~lR!
N 66 4
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-835-P, Rev.
1, "WNP-2 Cycle 15 Reload Licensing Report," ABB Combustion Engineering Nuclear Power, August 1999.
6.4 CE NPSD-801-P, Rev. 4, "WNP-2 LOCA Analysis Report," ABB Combustion Engineering Nuclear Power, May 1999.
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.
Washington Nuclear - Unit 2 COLR 99-15, Revision 0
Distribution Sheet Distri74.txt Priority: Normal From: Esperanza Lomosbog Action Recipients:
NRR/DLPM/LPD4-2 J Gushing E Peyton Copies:
1 Paper Copy Paper Copy Paper Copy Internal Recipients:
RidsRgn4MailCenter RidsOgcRp Rids NrrWpcMail RidsNrrDssaSrxb Rids Manager RidsAcrsAcnwMailCenter OGC/RP NRR/DSSA/SRXB CENTER 01 ACRS 0
0 0
OK OK OK OK OK 0
OK Paper Copy Paper Copy Paper Copy Paper Copy External Recipients:
NOAC Paper Copy Total Copies:
Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003694647:1
Subject:
WNP-2 1999 ANNUALOPERATING REPORT Body:
ADAMS DISTRIBUTIONNOTIFICATION.
Electronic Recipients can RIGHT CLICKand OPEN the firstAttachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003694647.
Page 1
V
Distri74.txt A001 - OR Submittal: General Distribution Docket: 05000397 Page 2
0
~ ~
EH~RQF NORTH !IVEST PO. Box 968 a Richland, Washington 99352-0968 February 29, 2000 G02-00-040 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 1999 ANNUALOPERATINGREPORT The annual operating report for calendar year 1999 is attached. Ifyou have any questions or desire additional information pertaining to this report, please contact either me or WA Kiel at (509) 377-4490.
Respectfully, DW Coleman Manager, Regulatory AfFairs MailDrop PE20 Attachment cc:
EW MerschofF, NRC - Region IV JS Cussing, NRC - NRR REIRS Project Manager, NRC NRR NRC Resident Inspector - 927N DLWilliams - BPA - 1399 TC Poindexter - Winston 2 Strawn
'E
0 Dj.stri71.txt Distribution Sheet j/g/su~
Priority: Normal From:
Andy Hoy Action Recipients:
J Cushing E Peyton Internal Recipients:
RES/DET/MEB RES/DET/ERAB OGC/RP LE CENTER 0
ACRS Copies:
1 1
Paper Copy Paper Copy Paper Copy Paper Copy Paper Copy Paper Copy Paper Copy External Recipients:
NOAC INEEL Marshall Paper Copy Paper Copy Total Copies:
Item:
ADAMS Package Library: ML ADAMS"HQNTAD01 ID: 003678106
Subject:
OR Submittal: Inservice/Testing/Relief from ASME Code Body:
ADAMS DISTRIBUTION NOTIFICATION.
Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS.
The Document may also be viewed by searching f or Accession Number ML003678106.
A047 OR Submittal: Inservice/Testing/Relief from ASME Code Docket:
05000397 Page 1
1 ENERGY NORTHWEST PO. Box 968 a Richland, Washington 99352-0968 January 13, 2000 G02-00-010 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 INSERVICE INSPECTION SU1VQCARY REPORT R-14 MAINTENANCEANDREFUELING OUTAGE The WNP-2 Inservice Inspection Summary Report for the R-14 Maintenance and Refueling Outage is attached.
This report is submitted in accordance with Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Article IWA-6240.
Pursuant to ASME Code Section XI, Article IWA-6230, the NIS-1 Owner's Data Report for inservice inspection and NIS-2 Owner's Reports for repairs and replacements are included.
Should you have any questions or require additional information pertaining to this report, please contact PJ Inserra at (509) 377-4147.
Respectfully, RL Webring Vice President, Operations Support/PIO MailDrop PE08 Attachments cc: EW Merschoff - NRC-RIV JS Cushing - NRC-NRR TC Poindexter - Winston 8c Strawn NRC Sr. Resident Inspector - 927N DLWilliams - BPA/1399
0 E.
t