NRC 2008-0025, Annual Report of Changes to, and Errors Discovered in Emergency Core Cooling System Evaluation Models
| ML081690700 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 06/16/2008 |
| From: | Mccarthy J Florida Power & Light Energy Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2008-0025 | |
| Download: ML081690700 (12) | |
Text
FPL Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 FPL E m e ~ g y Paaiit Beaa;iir Nuarleal Piissrr June 16,2008 NRC 2008-0025 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 ECCS Evaluation Model Chanaes As required by 10 CFR 50.46(a)(3)(ii), FPL Energy Point Beach, LLC, is submitting this annual report of changes to, and errors discovered in, emergency core cooling system (ECCS) evaluation models for Point Beach Nuclear Plant (PBNP), Units 1 and 2. This letter provides a summary of ECCS evaluation model changes and errors identified since the previous annual report dated June 27,2007.
This submittal contains no new commitments or revisions to existing commitments.
Very truly yours, FPL Energy Point Beach, LLC
!/'--l James H. McCarthy Site Vice President Enclosures (4) cc:
Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC An FPL Group company
ENCLOSURE I FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LBLOCA ECCS EVALUATION MODEL CHANGES AND ERRORS Westinghouse Electric Company is the analysis of record holder for the Point Beach, Units 1 and 2 Large Break loss of coolant accident (LOCA) analysis. Large Break LOCA analysis is performed using the 1999 Westinghouse Best Estimate Large Break LOCA Evaluation Model, application to PWRs with Upper Plenum Injection.
There was one error identified in the Large Break LOCA evaluation model during this reporting period that resulted in a change to the calculated PCT for the Point Beach Nuclear Plant. This error, related to the HOTSPOT Fuel Relocation, was reported in a 30-day 10 CFR 50.46 report dated July 3, 2007. The plant-specific impact of this error is 5OF (increaselnon-conservative direction) for blowdown and 45OF (increaselnon-conservative direction) for Reflood 1. There were no other changes during this reporting period that resulted in a change to the calculated peak cladding temperature (PCT). Enclosure 3 provides a summary of PCT changes.
Page 1 of 1
ENCLOSURE 2 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 SBLOCA ECCS EVALUATION MODEL CHANGES AND ERRORS Westinghouse Electric Company is the analysis of record holder for the Point Beach Units 1 and 2 Small Break loss of coolant accident (SBLOCA) analysis. Small Break LOCA analysis is performed using the 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP.
There were no changes or errors to the Small Break LOCA evaluation model during this reporting period that resulted in a change to the calculated PCT for the Point Beach Nuclear Plant. provides a summary of PCT changes.
Page 1 of 1
ENCLOSURE 3 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LARGE BREAK PEAK CLADDING TEMPERATURE MARGIN UTILIZATION FOR BELBLOCA A.
Analysis of Record (1 112000)
B.
Prior Permanent ECCS Model Assessments
- 1. MONTECF Decay Heat Uncertainty Factor
- 2. Revised Blowdown Heatup Uncertainty Distribution
- 3. Inconsistent Vessel Vertical Level Modeling
- 4. Revised Downcomer Gap Inputs C.
Planned Plant Change Evaluations
2007 10 CFR 50.46 Model Assessments
- 1. HOTSPOT Fuel Relocation Error F.
Other Changes (none)
PCT = 21 28°F APCT =
4" F APCT =
5OF APCT =
O°F APCT =
-59OF APCT =
8°F APCT =
45°F APCT =
0°F Licensing Basis PCT + Margin Allocations PCT =
21 31 OF SMALL BREAK PEAK CLADDING TEMPERATURE MARGIN UTILIZATION
/Three Inch Cold Leg)
Unit 1 1 Unit 2 A.
Analysis of Record (1 112000)
PCT = 1 157°F 1 1046°F B.
Prior Permanent ECCS Model Assessments
- 1. NOTRUMP Mixture Level TrackinglRegion Depletion
- 2. NOTRUMP Bubble RiseIDrift Flux Model Inconsistency C.
10 CFR 50.59 Safety Evaluations (none)
D.
2007 ECCS Model Assessments (none)
F.
Other Margin Allocations (none)
APCT =
13°F APCT =
35°F APCT =
0°F APCT =
0°F APCT =
0°F Licensing Basis PCT + Margin Allocations PCT = 1205°F 1 1094OF Page 1 of 1
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:
Point Beach Unit 1 Utility Name:
FPL Energy Point Beach, LLC Revision Date: 111 5/08 Analysis Information EM:
UP1 (1999)
Analysis Date: 9/1/97 FQ:
2.6 FdH:
1.8 Fuel:
422 Vantage +
SGTP (%):
25 Notes:
Uprate LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS 1 MONTECF Decay Heat Uncertainty Error Composite Limiting Break Size: Split Clad Temp ( O F )
Ref.
Notes 2128 1
- 2.
Revised Blowdown Heatup Uncertainty Distribution 5
4
- 3.
Inconsistent Vessel Vertical Level Modeling
- 4.
Revised Downcomer Gap Inputs B. PLANNED PLANT MODIFICATION EVALUATIONS 1
1.4% Uprate Evaluation C. 2007 ECCS MODEL ASSESSMENTS
- 1. HOTSPOT Fuel Relocation Error D. OTHER
- 1.
None LICENSING BASIS PCT + PCT ASSESSMENTS PCT=
2131
References:
- 1. 99WE-G-0034, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, Final BE UP1 LBLOCA Engineering Report (WCAP-15220) for Point Beach Units 1 and 2 (WEPNVIS)," June 24, 1999.
- 2. WEP-01-008, "10 CFR 50.46 Annual Notification and Reporting for 2000," March 2001.
- 3. OC-WES-B1-29-2003-006, "Point Beach Unit 1, Cycle 29; Final Reload Safety & Licensing Checklist," November 2003
- 4. WEP-05-84, "1 0 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
- 5. LTR-LIS-06-209, "Plant Specific Reporting Text for Various Errors for IR-04-337-M012.08," April 2006.
- 6. LTR-LIS-06-334, "Updates to the Best Estimate Large Break LOCA PCT Rackup Sheets for Kewaunee (WPS) and Point Beach Beach Units 1 (WEP) and 2 (WIS)," July 2006.
- 7. LTR-LIS-07-381, "10 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for Point Beach Units 1 and 2," June 2007.
Notes:
None Page 1 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:
Point Beach Unit 1 Utility Name: FPL Energy Point Beach, LLC Revision Date: 111 5/08 Analysis Information EM:
UP1 (1999)
Analysis Date:
9/1/97 FQ:
2.6 FdH:
1.8 Fuel:
422 Vantage +
SGTP (%):
25 Notes:
Uprate LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS 1 MONTECF Decay Heat Uncertainty Error Blowdown Limiting Break Size: Split Clad Temp (OF)
Ref.
Notes 1936 1
- 2.
Revised Blowdown Heatup Uncertainty Distribution 45 4
- 3.
Inconsistent Vessel Vertical Level Modeling 0
5
- 4.
Revised Downcomer Gap Inputs
-3 6
B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1.
1.4% Uprate Evaluation C. 2007 ECCS MODEL ASSESSMENTS
- 1. HOTSPOT Fuel Relocation Error D. OTHER
2007
References:
- 1. 99WE-G-0034, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, Final BE UP1 LBLOCA Engineering Report (WCAP-15220) for Point Beach Units 1 and 2 (WEPNVIS)," June 24, 1999.
- 2.
WEP-01-008, "10 CFR 50.46 Annual Notification and Reporting for 2000," March 2001
- 3.
OC-WES-B1-29-2003-006, "Point Beach Unit 1, Cycle 29; Final Reload Safety & Licensing Checklist," November 2003.
- 4.
WEP-05-84, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005
- 5.
LTR-LIS-06-209, "Plant Specific Reporting Text for Various Errors for IR-04-337-M012.08," April 2006
- 6.
LTR-LIS-06-334, "Updates to the Best Estimate Large Break LOCA PCT Rackup Sheets for Kewaunee (WPS) and Point Beach Units 1 (WEP) and 2 (WIS)," July 2006.
- 7.
LTR-LIS-07-381, "1 0 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for Point Beach Units 1 and 2," June 2007.
Notes:
None Page 2 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:
Point Beach Unit 1 Utility Name:
FPL Energy Point Beach, LLC Revision Date: 111 5/08 Analysis Information EM:
UP1 (1999)
Analysis Date: 9/1/97 FQ:
2.6 FdH:
1.8 Fuel:
422 Vantage +
SGTP (%):
25 Notes:
Uprate LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
- 1. MONTECF Decay Heat Uncertainty Error I
Reflood 1 Limiting Break Size: Split Clad Temp ( O F )
Ref.
Notes 2128 1
- 2.
Revised Blowdown Heatup Uncertainty Distribution 5
4
- 3.
Inconsistent Vessel Vertical Level Modeling 0
5
- 4.
Revised Downcomer Gap Inputs
-59 6
B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1.
1.4% Uprate Evaluation C. 2007 ECCS MODEL ASSESSMENTS
- 1. HOTSPOT Fuel Relocation Error D. OTHER
2131
References:
- 1. 99WE-G-0034, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, Final BE UP1 LBLOCA Engineering Report (WCAP-15220) for Point Beach Units 1 and 2 (WEPNVIS)," June 24, 1999.
- 2. WEP-01-008, "10 CFR 50.46 Annual Notification and Reporting for 2000," March 2001.
- 3.
OC-WES-B1-29-2003-006, "Point Beach Unit 1, Cycle 29; Final Reload Safety & Licensing Checklist," November 2003
- 4.
WEP-05-84, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
- 5.
LTR-LIS-06-209, "Plant Specific Reporting Text for Various Errors for IR-04-337-M012.08," April 2006.
- 6.
LTR-LIS-06-334, "Updates to the Best Estimate Large Break LOCA PCT Rackup Sheets for Kewaunee (WPS) and Point Beach Units 1 (WEP) and 2 (WIS)," July 2006.
- 7. LTR-LIS-07-381, "10 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for Point Beach Units 1 and 2," June 2007.
Notes:
None Page 3 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name:
Point Beach Unit 1 Utility Name: FPL Energy Point Beach, LLC Revision Date: 111 5/08 Analysis Information EM:
NOTRUMP Analysis Date: 6/1/99 FQ:
2.6 FdH:
1.8 Fuel:
Vantage +
SGTP (%):
25 Notes:
422 Vantage +
Limiting Break Size: 3 inch CL Hi Tavg Clad Temp (OF)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT 1157 I
A. PRIOR ECCS MODEL ASSESSMENTS
- 1. NOTRUMP Mixture Level Tracking I Region Depletion Errors 13 3
- 2.
NOTRUMP Bubble Rise 1 Drift Flux Model Inconsistency Corrections 35 4
B. PLANNED PLANT MODIFICATION EVALUATIONS 1
None C. 2007 ECCS MODEL ASSESSMENTS
- 1. None D. OTHER
1205
References:
- 1.
CAB-99-226, Rev. 1, "Fuel Upgrade I Power Uprating Reload Transition Safety Report for Point Beach Units 1 and 2 Revision 1," July 13, 1999.
- 2. WEP-00-009, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, 10 CFR 50.46 Annual Notification and Reporting for 1999," February 23, 2000.
- 3. WEP-00-027, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, 10 CFR 50.46 Appendix K (BARTIBASHINOTRUMP) Evaluation Model Mid-Year Notification and Reporting for 2000," June 30, 2000
- 4.
WEP-05-84, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
Notes:
None Page 4 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:
Point Beach Unit 2 Utility Name:
FPL Energy Point Beach, LLC Revision Date: 111 5/08 Analysis Information EM:
UP1 (1999)
Analysis Date: 9/1/97 FQ:
2.6 FdH:
1.8 Fuel:
422 Vantage +
SGTP (%):
25 Notes:
Uprate LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
- 1.
MONTECF Decay Heat Uncertainty Error I
Composite Limiting Break Size: Split Clad Temp (OF)
Ref.
Notes 21 28 1
- 2.
Revised Blowdown Heatup Uncertainty Distribution 5
4
- 3.
Inconsistent Vessel Vertical Level Modeling 0
5
- 4.
Revised Downcomer Gap Inputs
-59 6
B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. 1.4% Uprate Evaluation C. 2007 ECCS MODEL ASSESSMENTS
- 1. HOTSPOT Fuel Relocation Error D. OTHER
2131
References:
- 1. 99WE-G-0034, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, Final BE UP1 LBLOCA Engineering Report (WCAP-15220) for Point Beach Units 1 and 2 (WEPNVIS)," June 24, 1999.
- 2.
WEP-01-008, "10 CFR 50.46 Annual Notification and Reporting for 2000," March 2001.
- 3.
NPL 2003-0071, "Final RS&LC Point Beach Nuclear Plant, Unit 2 Cycle 2 7, February 2003
- 4. WEP-05-84, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
- 5.
LTR-LIS-06-209, "Plant Specific Reporting Text for Various Errors for IR-04-337-M012.08," April 2006
- 6.
LTR-LIS-06-334, "Updates to the Best Estimate Large Break LOCA PCT Rackup Sheets for Kewaunee (WPS) and Point Beach Units 1 (WEP) and 2 (WIS)," July 2006.
- 7.
LTR-LIS-07-381, "10 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for Point Beach Units 1 and 2," June 2007.
Notes:
None Page 5 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:
Point Beach Unit 2 Utility Name:
FPL Energy Point Beach, LLC Revision Date: 111 5/08 Blowdown Analysis Information EM:
UP1 (1999)
Analysis Date:
9/1/97 Limiting Break Size: Split FQ:
2.6 FdH:
1.8 Fuel:
422 Vantage +
SGTP (%):
25 Notes:
Uprate LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS 1. MONTECF Decay Heat Uncertainty Error I
2. Revised Blowdown Heatup Uncertainty Distribution 3. Inconsistent Vessel Vertical Level Modeling 4. Revised Downcomer Gap Inputs B. PLANNED PLANT MODIFICATION EVALUATIONS 1. 1.4% Uprate Evaluation C. 2007 ECCS MODEL ASSESSMENTS 1. HOTSPOT Fuel Relocation Error D. OTHER 1. None Clad Temp (OF)
Ref.
Notes 1936 1
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
2007
References:
- 1. 99WE-G-0034, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, Final BE UP1 LBLOCA Engineering Report (WCAP-15220) for Point Beach Units 1 and 2 (WEPNVIS)," June 24, 1999.
- 2. WEP-01-008, "10 CFR 50.46 Annual Notification and Reporting for 2000," March 2001.
- 3.
NPL 2003-0071, "Final RS&LC Point Beach Nuclear Plant, Unit 2 Cycle 27", March 2003
- 4.
WEP-05-84, "1 0 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
- 5.
LTR-LIS-06-209, "Plant Specific Reporting Text for Various Errors for IR-04-337-M012.08," April 2006.
- 6.
LTR-LIS-06-334, "Updates to the Best Estimate Large Break LOCA PCT Rackup Sheets for Kewaunee (WPS) and Point Beach Units 1 (WEP) and 2 (VVIS)," July 2006.
- 7. LTR-LIS-07-381, "10 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for Point Beach Units 1 and 2," June 2007.
Notes:
None Page 6 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:
Point Beach Unit 2 Utility Name:
FPL Energy Point Beach, LLC Revision Date: 111 5/08 Reflood 1 Analvsis Information EM:
UP1 (1999)
Analysis Date: 9/1/97 Limiting Break Size: Split FQ:
2.6 FdH:
1.8 Fuel:
422 Vantage +
SGTP (%):
25 Notes:
Uprate Clad Temp (OF)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS 1
MONTECF Decay Heat Uncertainty Error
- 2.
Revised Blowdown Heatup Uncertainty Distribution 5
4
- 3.
Inconsistent Vessel Vertical Level Modeling 0
5
- 4.
Revised Downcomer Gap Inputs
-59 6
B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. 1.4% Uprate Evaluation C. 2007 ECCS MODEL ASSESSMENTS
- 1. HOTSPOT Fuel Relocation Error D. OTHER
2131
References:
- 1. 99WE-G-0034, "Wisconsin Electric Power Company, Point Beach Units 1 and 2, Final BE UP1 LBLOCA Engineering Report (WCAP-15220) for Point Beach Units 1 and 2 (WEPNVIS)," June 24,1999.
- 2. WEP-01-008, "10 CFR 50.46 Annual Notification and Reporting for 2000," March 2001.
- 3.
NPL 2003-0071, "Final RS&LC Point Beach Nuclear Plant, Unit 2 Cycle 27", February 2003
- 4.
WEP-05-84, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005
- 5.
LTR-LIS-06-209, "Plant Specific Reporting Text for Various Errors for IR-04-337-M012.08," April 2006
- 6.
LTR-LIS-06-334, "Updates to the Best Estimate Large Break LOCA PCT Rackup Sheets for Kewaunee (WPS) and Point Beach Units 1 (WEP) and 2 (WIS)," July 2006.
- 7. LTR-LIS-07-381, "10 CFR 50.46 Reporting Text for HOTSPOT Fuel Relocation Error and Revised PCT Rackup Sheets for Point Beach Units 1 and 2," June 2007.
Notes:
None Page 7 of 8
ENCLOSURE 4 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 PCT RACKUP SHEETS FOR LBLOCA AND SBLOCA Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name:
Point Beach Unit 2 Utility Name: FPL Energy Point Beach, LLC Revision Date: 111 5/08 Analysis Information EM:
NOTRUMP Analysis Date: 6/1/99 FQ:
2.6 FdH:
1.8 Fuel:
Vantage +
SGTP (%):
25 Notes:
422 Vantage +
Limiting Break Size: 3 inch CL Lo Tavg LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
- 1.
NOTRUMP Mixture Level Tracking I Region Depletion Errors
- 2.
NOTRUMP Bubble Rise I Driff Flux Model Inconsistency Corrections B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. None C. 2007 ECCS MODEL ASSESSMENTS
- 1. None D. OTHER
Ref.
Notes 1046 1
0 PCT =
1094
References:
- 1.
CAB-99-226, Rev. 1, "Fuel Upgrade I Power Uprating Reload Transition Safety Report for Point Beach Units 1 and 2 Revision 1," July 13, 1999.
- 2. WEP-00-009, 'Wisconsin Electric Power Company, Point Beach Units 1 and 2, 10 CFR 50.46 Annual Notification and Reporting for 1999," February 23, 2000.
- 3.
WEP-00-027, Wisconsin ~lectric Power Company, Point Beach Units 1 and 2, 10 CFR 50.46 Appendix K (BARTIBASHINOTRUMP) Evaluation Model Mid-Year Notification and Reporting for 2000," June 30, 2000.
- 4.
WEP-03-142, "10 CFR 50.46 Mid-Year Notification and Reporting for 2003," November 2003.
Notes:
None Page 8 of 8