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Category:Annual Report
MONTHYEARL-2015-142, 2014 Annual Environmental Operating Report2015-04-28028 April 2015 2014 Annual Environmental Operating Report L-2015-050, Annual Fitness-For-Duty-Program Report for the Period of January 1 Through December 31, 20142015-02-24024 February 2015 Annual Fitness-For-Duty-Program Report for the Period of January 1 Through December 31, 2014 L-2013-092, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2013-03-18018 March 2013 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2012-091, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2012-03-0101 March 2012 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2010-033, Cy 2009 Corrections to Annual Radioactive Effluent Release Report (L-2010-033 Dated February 25, 2010) Section 8. Process Control Program (PCP) Revisions, Page 8 of 59 and AP 0520025 Revision 13C with mark-up2010-02-25025 February 2010 Cy 2009 Corrections to Annual Radioactive Effluent Release Report (L-2010-033 Dated February 25, 2010) Section 8. Process Control Program (PCP) Revisions, Page 8 of 59 and AP 0520025 Revision 13C with mark-up ML0816504352008-07-21021 July 2008 Allegation Program Annual Trends Report Cy 2007 L-2008-029, St. Lucie, Units 1 & 2, 2007 Annual Radioactive Effluent Release Report2008-02-27027 February 2008 St. Lucie, Units 1 & 2, 2007 Annual Radioactive Effluent Release Report ML0806605792008-02-27027 February 2008 St. Lucie, Units 1 & 2, 2007 Annual Radioactive Effluent Release Report L-2007-051, Annual Radiological Environmental Operating Report for Calendar Year 20062007-03-29029 March 2007 Annual Radiological Environmental Operating Report for Calendar Year 2006 L-2007-040, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2007-03-22022 March 2007 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2005-260, Price Anderson Guarantees/Annual Financial Report2005-12-29029 December 2005 Price Anderson Guarantees/Annual Financial Report L-2005-166, Report of 10 CFR 50.59 Plant Changes2005-08-11011 August 2005 Report of 10 CFR 50.59 Plant Changes L-2003-290, Report of 10 CFR 50.59 Plant Changes2003-12-0202 December 2003 Report of 10 CFR 50.59 Plant Changes L-2003-078, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2003-03-26026 March 2003 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report ML18096B5831975-11-19019 November 1975 St. Lucie, Units 1 & 2 - 11/19/1975 Letter Submittal of Annual Financial Report for 1974 ML18227A9921975-11-19019 November 1975 Submit 1974 Annual Report. ML18096B4031970-12-31031 December 1970 Hutchinson Island Units 1 and 2 - Exhibit II Facts & Figures Florida Power & Light Company Supplement to Annual Report for 1970, Exhibit III, and Exhibit IV ML18096B4021970-12-31031 December 1970 1970 Annual Report Florida Power & Light Company 2015-04-28
[Table view] Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
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Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 0
FPL March 26, 2003 L-2003-078 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report Pursuant to 10 CFR 50.46(a)(3)(ii), the nature of any change to or error discovered in the evaluation models for emergency core cooling systems (ECCS), or in the application of such models, that affect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in the attachment to this letter. The estimated effect from any such change or error on the limiting ECCS analysis for each unit is also addressed. The data interval for the report is from January 1, 2002 through December 31, 2002.
Please contact us should you have any questions regarding this submittal.
Donald E. Jernigan Vice President St. Lucie Plant DEJ/spt Attachment
-o (
an FPL Group company
St. Lucie Plant Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2003-078 Attachment Page 1 St. Lucie Units 1 and 2 10 CFR 50.46 Annual Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed by Framatome ANP, Inc. (FRA-ANP), formerly Siemens Power Corporation, and Westinghouse Electric Company QL), respectively. The following information pertaining to the evaluation models for small break loss of coolant accidents (SBLOCA) and large break loss of coolant accidents (LBLOCA), and the application of such models to each St. Lucie unit, is provided pursuant to 10 CFR 50.46(a)(3)(ii). A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1. The data interval for this report is from January 1, 2002 through December 31, 2002.
1.0 ST LUCIE UNIT 1 1.1 One error/issue was identified related to the SBLOCA ECCS performance analysis. This error/issue, not previously reported in Reference 3.1, is described below. Table 1 summarizes the estimated impact of this error/issue on the St. Lucie Unit I SBLOCA PCT.
The limiting SBLOCA PCT with the estimated effect of the change is 1766 0F.
Error in TOODEE2 Clad Thermal Expansion TOODEE2 uses a correlation for determining clad thermal expansion with 3 ranges: Alpha phase, Beta phase, and a transition region between Alpha and Beta phases. The formulation for the Beta phase is programmed with an incorrect constant coefficient of 2.9E-6 instead of 3.2E-6. This introduces a discontinuity between the transition region and the Beta phase region, and causes all clad thermal expansion calculations at temperatures above 17730 F to be underpredicted.
The PCT impact of correcting this error on the St. Lucie Unit 1 SBLOCA analysis is estimated to be -1OF.
1.2 Several errors/issues were identified impacting the LBLOCA PCT. These errors, not previously reported in Reference 3.1, are described below. Table 1 summarizes the estimated impact of these errors/issues on the St. Lucie Unit 1 LBLOCA PCT. The limiting LBLOCA PCT with the estimated effect of the changes is 20330F.
Error in TOODEE2 Clad Thermal Expansion The description of this error is provided in Section 1.1 above. The PCT impact of this error correction on the St. Lucie Unit 1 LBLOCA analysis is estimated to be -1OF.
RFPAC V&V Findings from Code Documentation Upgrade Program (CDUP)
FRA-ANP committed (in response to the NRC 1997 inspection) to perform additional V&V and to update or create user's manuals, theory manuals, and programmers manuals for Framatome ANP's primary codes. One of the codes was the RFPAC code. The RFPAC code performs the refill and reflood calculations for the LBLOCA event in the SEM/PWR-98
St. Lucie Plant Units I and 2 Docket Nos. 50-335 and 50-389 L-2003-078 Attachment Page 2 evaluation model. A number of minor errors were identified and corrected as a result of the additional V&V activities.
The PCT impact of correcting these errors on the St. Lucie Unit I LBLOCA analysis is estimated to be +23 0F.
Incorrect Pump Junction Area Used in RELAP4 LBLOCA For the SEM/PWR-98 evaluation model, the junction area that should be used for the recirculation pump junctions is the connecting pipe area. It was determined that the current analysis supporting St. Lucie Unit 1 used a smaller area for the pipe junctions. The analysis was corrected by using the full pipe areas. The LBLOCA guideline is being changed to require the use of the full connecting pipe area.
The PCT impact of correcting this error on the St. Lucie Unit 1 LBLOCA analysis is estimated to be +1OF.
2.0 ST. LUCIE UNIT 2 2.1 No errors were found in W's SBLOCA analysis impacting the PCT previously reported in Reference 3.1. The limiting PCT for SBLOCA remains at 21250 F.
2.2 St. Lucie Unit 2 LBLOCA analysis was performed by W using the 1985 evaluation model (EM). There were two errors, not previously reported in Reference 3.1, found in the LBLOCA ECCS performance analysis as described below. Both of these errors were in STRIKIN-I1 code models that affect the results of LBLOCA analyses using the 1985 EM.
Table 1 summarizes the estimated impact of these errors on the St. Lucie Unit 2 LBLOCA PCT. The limiting LBLOCA PCT with the estimated effect of the changes is 2151 0F.
Time Step Alcorithm The algorithms used in the automatic time step selection method for STRIKIN-I1 are designed to automatically adjust the time step length such that STRIKIN-I1 calculates an appropriate solution for the fuel, cladding and coolant temperature and the heat flux to the coolant. In particular, they are designed to ensure that the Courant number is less than or equal to 0.5. This ensures that the solution conserves energy. An error in the implementation of the algorithm that bypassed this test and allowed the Courant number to exceed this limit was discovered and corrected. An error test was also added that would stop the code with an error message if the time step specified by the user would allow the Courant number to exceed 0.99.
St. Lucie Plant Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2003-078 Attachment Page 3 Coffman Plastic Strain Model for Cladding A problem with the implementation of the Coffman plastic strain model for fuel cladding in STRIKIN-I1 produced discontinuous plastic strain behavior. This model is only used when the heating rate and the cladding temperature are within bounds set for application of the model. The calculated plastic strain is continuous except when the cladding conditions move outside these bounds and later return within the bounds at a higher cladding temperature. In order to address the resulting discontinuity, a ramp function is used to introduce the strain over several time steps. The problem occurred when the heating rate fell below the lower bound for the model within the time duration of the ramp. This was corrected by terminating the ramp when the conditions for the use of the model described above are not satisfied.
Effect of Correcting STRIKIN-I1 Errors The total effect on PCT due to the correction of STRIKIN-I1 errors described above is estimated to be less than 10F for the 1985 EM that is used for the LBLOCA analysis of St.
Lucie Unit 2.
3.0 REFERENCES
3.1 FPL Letter L-2002-062, D. E. Jemigan to USNRC (DCD), St. Lucie Units 1 and 2, Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: 10 CFR 50.46 Annual Report, March 27, 2002.
St. Lucie Plant Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2003-078 Attachment Page 4 Table 1: 2002 St. Lucie Units 1 and 2 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary PCT Year 2001 10 CFR 50.46 Annual Report (L-2002-062) 17670F Change due to Error in TOODEE2 Clad Thermal Expansion -10F Year 2002 10 CFR 50.46 Annual Report 17660F Unit I LBLOCA Summary PCT Year 2001 10 CFR 50.46 Annual Report (L-2002-062) 201 00 F Change due to Error in TOODEE2 Clad Thermal Expansion -1OF Change due to RFPAC V&V Findings from CDUP +23OF Change due to Incorrect Pump Junction Area Used in RELAP4 +10F Year 2002 10 CFR 50.46 Annual Report 20330 F Unit 2 SBLOCA Summary PCT Year 2001 10 CFR 50.46 Annual Report (L-2002-062) 21250 F Change during Year 2002 OF Year 2002 10 CFR 50.46 Annual Report 21250 F Unit 2 LBLOCA Summary PCT Year 2001 10 CFR 50.46 Annual Report (L-2002-062) 21500 F Change due to STRIKIN-I1 Errors <1 OF Year 2002 10 CFR 50.46 Annual Report 21510 F