Category:Calculation
Jump to navigation
Jump to search
(previous page) (next page)
Category Used between: 3 May 1972 to 11 December 2025
Plant
University
Fuel Processing
- BWX Technologies (0)
- Barnwell (0)
- Claiborne (0)
- Consolidated Interim Storage Facility (48)
- Eagle Rock (0)
- Erwin (0)
- Framatome ANP Richland (0)
- Global Nuclear Fuel (0)
- HI-STORE (0)
- Holtec (0)
- Orano USA (0)
- Paducah Gaseous Diffusion Plant (0)
- Portsmouth Gaseous Diffusion Plant (0)
- Triso-X (0)
- West Valley Demonstration Project (2)
- Wood River Junction (0)
Laboratory
- 05000470 (0)
- Battelle Memorial Institute (0)
- Dow Chemical Company (0)
- General Atomics (0)
- Hermes (0)
- Idaho National Laboratory (0)
- Knolls Atomic Power Laboratory (0)
- Los Alamos National Laboratory (0)
- Lynchburg Research Center (0)
- National Bureau of Standards Reactor (0)
- National Institute of Standards and Technology (0)
- National Renewable Energy Lab (0)
- Northwest Medical Isotopes (0)
- Oak Ridge National Laboratory (0)
- PM-1 (0)
- PM-2A (0)
- Pacific Northwest National Laboratory (0)
- Plum Brook (6)
- SHINE Medical Technologies (13)
- SM-1 (0)
- SM-1A (0)
- Sandia National Laboratories (0)
- Tuxedo (0)
- U.S. Geological Survey (1)
- Vanowen (0)
- Waltz Mill (0)
Hospital
- Advocate Illinois (0)
- Avera McKennan Hospital (0)
- Banner Boswell Medical Center (0)
- Bard Brachytherapy (0)
- Dermatology of Seattle and Bellevue (0)
- Fred Hutchinson Cancer Center (0)
- George Washington Hospital (0)
- Karmanos Cancer Institute (0)
- Kennedy Memorial Hospital (0)
- Lincoln Memorial Hospital (0)
- Northwestern Memorial Hospital (0)
- Piedmont Hospital (0)
- UMass Memorial Health Medical Center (0)
- University Hospitals of Cleveland (0)
- West Virginia University Hospital (0)
Manufacturer
- 05200045 (0)
- Braun Intertec Corporation (0)
- Electric Boat (0)
- Martinez Refining Company (0)
- Mistras Group (0)
- Reliable Testing Services (0)
- Sacyr Construction (0)
- Screaming Eagle Coal (0)
- Tilden-Mine (0)
Agency
Pages in category "Calculation"
The following 200 pages are in this category, out of 1,991 total.
(previous page) (next page)0
1
- 1CAN010603, Supplement to Amendment Request, Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (Efic), Enclosure 1, Calculation, Efic System Loop Error and Setpoint Analysis
- 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure
- 1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016
- 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)
3
- 3F0205-05, 10 CFR 50 Appendix R Exemption Request for Pressurizer Level Instrumentation
- 3F0406-05, Off-Site Dose Calculation Manual, Revision 27
- 3F0407-05, Off-Site Dose Calculation Manual, Revision 29
- 3F0409-04, Attachment B Through E - Crystal River, Unit 3 - License Amendment Request 303, Revision 1, Revision to Final Safety Analysis Report Sections 5.4.3, Structural Design Criteria, and 5.4.5.3, Missile Analysis.
- 3F0409-04, Attachment B Through E - Crystal River, Unit 3 - License Amendment Request 303, Revision 1, Revision to Final Safety Analysis Report Sections 5.4.3, Structural Design Criteria, and 5.4.5.3, Missile Analysis
- 3F0410-05, Off-Site Dose Calculation Manual, Revision 32
- 3F0413-03, Attachment C, Off-Site Dose Calculation Manual, Revision 34
- 3F0420-01, 2019 Annual Radioactive Effluent Release Report
- 3F0605-07, Calculation M90-0021, Building Spray and Decay Heat Pump Npsha/R, Revision 13, Attachment
- 3F1011-05, Calculation 86-9168766-001, CR-3 EPU Inadvertent Engineered Safeguards Actuation (Iesa) Analysis Summary
- 3F1018-01, Fluor Corporation - Chemical Addition System Sizing Calculations
A
- A000000, Calculation No. BBA000000-01717-0210-00037, Rev. 00, ECN No. 1, Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Intact Mode
- A000277, 30441R00017, Revision C, Ansys Target Cartridge, Housing Structural Analysis Design Calculation Report
- A04977, Ccnpp Calculation No. CA04977, Revision 1, Nutech Horizontal Module System (NUHOMS) 24P ISFSI Dry Shielded Canister (DSC) Structural Analysis for DSC Numbers R.R. and Beyond
- A06012, Calculation CA06012, Atmospheric Dispersion Coefficient (X/Q) Calculation Rev 000
- A06432, Calculation CA06432 for Calvert Cliffs ISFSI
- AEP-NRC-2014-09, Enclosure 3 to AEP-NRC-2014-09, Calculation, PRA-ILRT, Rev. 2, Risk Impact Assessment for Permanently Extending Containment Type a Test Interval
- AEP-NRC-2015-14, Response to March 12, 2012, Request for Information, Enclosure 2, Recommendation 2.1: Flooding, Required Response 2, Hazard Reevaluation Report
- AEP-NRC-2015-49, Emergency License Amendment Request to Extend the Allowed Outage Time for an Emergency Diesel Generator
- AEP-NRC-2016-23, Calculation RWA-1313-001, Rev. 1, AST Radiological Analysis Input Parameter Development
- AEP-NRC-2016-89, To Calculation MD-12-FLOOD-011-N, Flood Hazard Reevaluation Report for the Donald C. Cook Nuclear Plant
- AEP-NRC-2018-04, Enclosure 2 - Technical Support Center Loss of Coolant Accident Radiological Analysis
- AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual
- AEP-NRC-2020-40, Calculation PRA-QNT-009, Rev. 0, Evaluation of Risk Significance of Short-Term ILRT Extension
B
- B000000, Calculation No. B00000000-01717-0210-00006, Rev. 00, CRC Reactivity Calculations for Sequoyah Unit 2, Attachment I, Page 334 of 656 Through Attachment VI
- BSEP 04-0127, Calculation No. 0B21-0112, Rev. 11, 10 CFR 50.46 SAFER/GESTR-LOCA ECCS Analysis Update
- BSEP 05-0020, Off-Site Dose Calculation Manual (ODCM) Revision 28
- BSEP 07-0026, Enclosure 1 - Design Calc. 21321-1267, Revision 0, Brunswick, Unit 2, Cycle 18 Core Operating Limits Report March 2007
- BSEP 09-0064, Enclosure 6 to BSEP 09-0064 - Calculation 0B21-1305, Core Monitoring LPRM Uncertainty and Sensitivity Decay
- BSEP 11-0045, Offsite Dose Calculation Manual, Revision 34, Enclosure 2 to BSEP 11-0045
- BSEP 12-0047, Offsite Dose Calculation Manual Revision 35
- BSEP 13-0042, Off-Site Dose Calculation Manual, Revision 36
- BSEP 17-0019, Enclosure 2 - Response to Request for Additional Information Regarding License Amendment Request for Reactor Protection System (RPS) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.
- BVY 03-115, Technical Specification Proposed Change No. 257 Implementation of Arts/Smella at VYNPS Supplemental Information and Proposed Allowable Value, Attachment 2, Calculation VYC-0693A
- BVY 03-116, To Psat 3019CF.QA.09, Alternative Source Term Impact on NUREG-0737 Equipment Qualification, Vital Area Access, and Areas of Continuous Occupancy
- BVY 04-071, Calculation VYC-2314, Rev. 0, Ccn 02, Minimum Containment Overpressure for Non-LOCA Events
- BVY 09-037, Off-Site Dose Calculation Manual, Revision 32
- BVY 09-037, Vermont Yankee - Off-Site Dose Calculation Manual, Revision 31
- BVY 13-097, Proposed Change 306, Areva Document No. 32-9145461-001, Vynpp - Re-analysis of Ast/Fha Radiological Consequences with Open Containment
- BVY 17-009, Attachment 3: Vermont Yankee Supporting Evaluation and Calculation VYC-3200, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant
- BVY 17-009, Calculation ENTGVY036-CALC-001, Revision 1, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant
- BVY 17-009, Vermont Yankee - Calculation ENTGVY036-CALC-001, Revision 1, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant
- BVY-05-068, Attach 4:Response to Request for Additional Information - Instrumentation Technical Specifications, Vermont Nuclear Power Station, Calculation VYC-462A Rev 0, Main Steam Line Areas High Temperature Setpoint, with Calculation Change Notice
- BW110044, CY-BR-170-301, Revision 5, Offsite Dose Calculation Manual (Odcm)
- BW120042, Offsite Dose Calculation Manual (Odcm), CY-BR-170-301, Rev. 6
- BW140031, CY-BR-170-301, Revision 8, Offsite Dose Calculation Manual (ODCM)
- BW190043, CY-BR-170-301, Revision 10, Offsite Dose Calculation Manual
- BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations
- BYRON 2018-0039, BYR16-012, Off Gas Filter Analysis
- BYRON 2020-0026, CY-BY-170-301, Revision 15, Offsite Dose Calculation Manual. (Part 3 of 3)
C
- CNL-13-126, Attachment 6 - NDQ099920010019 - Ex-Containment Removal Coefficients for Alternative Source Term Analyses, Through Attachment 11 - List of Regulatory Commitments
- CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)
- CNL-15-059, Response to NRC Request for Additional Information Regarding the Review Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink, Including Enclosures 1 and 2, Pp. 1 Through 206
- CNL-15-071, Two-Unit Offsite Dose Calculation Manual, Revision 0
- CNL-25-032, Supplement to Application to Revise Browns Ferry Nuclear Plant, Units 1, 2, and 3 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (BFN-TS-550)
- CNRO-2002-00058, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations
- CNS-16-029, Offsite Dose Calculation Manual, Revision 59
- CY-05-002, Letter to NRC Document Control Desk from G. Bouchard, Connecticut Yankee Atomic Power Company, Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002
- CY-07-087, CY-HP-0202, Rev. 0, Calculation of Future Groundwater Dose Resulting from Residual Radioactivity in Concrete to Remain in Groundwater Saturated Zone Using the Cy LTP Basement Fill Model, Attachment 5 Through End
- CY-15-021, ISFSI - Offsite Dose Calculation Manual, Revision 25
D
- DCL-10-059, Calculation Number GEO.DCPP.10.02, Evaluation of Shear-Wave Velocity at the DCPP Isfsi
- DCL-11-072, Attachment 2 - Potential Transformer Characteristic Ratio and Phase Angle Curve
- DCL-12-031, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-072, License Amendment Request 11-06, Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation Dated October
- DCL-13-021, Areva Calculation 32-9200249-000, Diablo Canyon Power Plant Unit 2 Pzr Safety and Spray Nozzles Planar Flaw Analysis - Non Proprietary
- DCL-13-021, Areva Calculation 32-9200291-000, DCPP Unit 2 - Evaluation of Laminar Indications in Pressurizer Nozzles (Non-Proprietary)
- DCL-14-028, Areva Calculation No. 32-9219780-000, Diablo Canyon Unit 2 Pressurizer Safety/Relief Nozzle Weld Overlay Structural Analysis.
- DCL-14-028, Areva Calculation No. 32-9219781-000, Diablo Canyon Unit 2 - Pressurizer Spray Nozzle Weld Overlay Structural Analysis.
- DCL-14-028, Areva Calculation No. 32-9219792-000, Diablo Canyon Unit 2 Pressurizer Spray Nozzle Weld Overlay Residual Stress Analysis.
- DCL-14-028, Areva Calculation No. 32-9221080-000, Diablo Canyon Unit 2 Pressurizer Safety/Relief Nozzles Laminar/Planar Flaw Analysis.
- DCL-14-028, Areva Calculation No. 32-9221082-000, Diablo Canyon Unit 2 Pressurizer Spray Nozzle Laminar Flaw Analysis.
- DCL-14-051, Attachment 4, Areva Calculation No. 32-9221080-001 Diablo Canyon, Unit 2 Pressurizer Safety/Relief Nozzles Laminar/Planar Flaw Analysis - Non Proprietary
- DCL-14-051, Attachment 5, Areva Calculation No. 32-9221082-001 Diablo Canyon, Unit 2 Pressurizer Spray Nozzle Laminar Flaw Analysis - Non-Proprietary
- DCL-14-084, Relief Request SWOL-REP-1-U2: Submittal of Revised Areva Calculations. Part 7 of 15
- DCL-15-131, Diablo Canyon, Unit 1, Pressurizer Spray Line Pipe Weld Flaw Evaluation, Calculation Package, Part 1
- DCL-16-081, PPS Seismic Qualification
E
- E900-03-014, Shonka Line Shack & Warehouse/Garage Pads FSS Survey Design
- E900-03-016, Rev 0 to Calculation E900-03-016, Shinka Discharge & Intake Tunnels FSS Survey Design, Appendices a - C to Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces - Intak
- E900-03-031, Calculation E900-03-031, Rev 0, Shonka Survey of Debris & Soil Piles
- E900-03-032, Rev 0 to Calculation E900-03-032, Top of Seal Chamber 3 - Survey Design, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corp Saxton Steam Generating Station Structural Surfaces - Seal Chamber Roofs SS17 (1&2) &
- E900-04-004, To Calculation E900-04-004, Cv Tunnel Unistrut Survey Design, Appendix B to Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces - Cv Steam Tunnel SS22
- E900-04-006, Rev 0 to Calculation E900-04-006, Cv Yard Boulder and Soil Lift Survey Designs, Appendices D - N to Final Status Survey Report for Saxton Nuclear Experimental Corp Containment Vessel Yard Excavation - Soil and Structural Remnants
- E900-04-007, Rev. 0 to Calculation E900-04-007, Discharge Tunnel Survey Design for Class 1 Areas, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corp Saxton Steam Generating Station Structural Surfaces -Discharge Tunnel SSI,
- E900-04-012, Rev 0 to Calculation E900-04-012, Cv Tunnel & Top of Seal Chambers 1 & 2 Survey Design, Appendix B to Final Status Survey Report for Saxton Nuclear Experimental Corp Saxton Steam Generating Station Structural Surfaces - Seal Chamber Roof
- E900-04-013, Rev 0 to Calculation E900-04-013, Cv Yard Survey Design - North East Side of Cv, Appendices a - D to Final Status Survey Report for Saxton Nuclear Experimental Corp Containment Vessel Yard Excavation - Soil and Structural Remnants
- E900-04-015, Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces Discharge Tunnel Transition Area SS23, SS25, Appendix B SNEC Calculation Sheet
- E900-04-021, Rev. 0 to Calculation E900-04-021, Assessment of Survey Results for Discharge Tunnel Class 1 Areas, Appendix E to Final Status Survey Report for Saxton Nuclear Experimental Corp Saxton Steam Generating Station Structural Surfaces -Discha
- E900-05-004, Calculation E900-05-004, Rev 0, Penelec Switch Yard Class 3 Control Building - Survey Design
- E900-05-009, To Calculation E900-05-009, Westinghouse and Adjacent Areas Open Land - OL2 - Survey Design, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area OL2
- E900-05-011, To Calculation E900-05-011, Westinghouse and Adjacent Areas MA8-5 Concrete Survey Design, Appendix B to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area OL2
- E900-05-014, Rev 0 to Calculation E900-05-014, SNEC Plant Area Open Land - OL1 - Survey Design, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corp Open Land Area OL1
- E900-05-015, Rev. 1 to Calculation E900-05-015, OL1 Paved & Miscellaneous Concrete Surfaces MA8, PF1, DB5, DB1, SS12, SS24-Survey Design, Appendices B - D to Final Status Survey Report for Saxton Nuclear Experimental Corp Residual Concrete in OL1
- E900-05-023, Calculation E900-05-023, Rev 1, Miscellaneous Chain Link Fences MA9 - Survey Design
- E900-05-027, Experimental Corporation Final Status Survey Report for OL6 and OL10, SNEC Calculation Sheet
- E900-05-028, Rev 2 to Calculation E900-05-028, Open Land FSS Design - OL7 Paved Surfaces & Concrete, Appendices a & B to Final Status Survey Report for Saxton Nuclear Experimental Corporation OL7 Paved Surfaces and Concrete
- E900-05-029, To Calculation E900-05-029, Assessment of Cv Tunnel Unistrut, Appendix C to Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces - Cv Steam Tunnel SS22
- E900-05-032, Rev 2 to Calculation E900-05-032, Open Land FSS Design - OL3 Paved Surfaces & Concrete, Appendices a - B to Final Status Survey Report for Saxton Nuclear Experimental Corporation 0L3 Paved Surfaces and Concrete
- E910-04-023, Calculation, E900-03-014, Rev 0, Shonka Line Shack & Warehouse/Garage Pads FSS Survey Design
- E910-05-016, Calculation E900-05-018, Rev 0, Miscellaneous Area FSS Design - MA2, Appendix a with Attachments to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area MA2
- E910-05-017, Calculation E900-05-016, Rev 1, Northeast Dump Open Land Area OL5 - Survey Design, Appendix F to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area OL5
- E910-05-018, Calculation E900-05-020, Rev 0, OL9 Open Land Area - Survey Design, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area OL9
- E910-05-019, Calculation E900-05-012, Rev 0, Yard Storage Tank Excavation - OL1-7 - Survey Design, Appendix a, with Attachments to Final Status Survey Report for Saxton Nuclear Experimental Corporation East Yard Excavation OL1-7
- E910-05-020, Calculation E900-05-005, Rev 0, Spray Pond - Survey Design, Appendix a, with Attachments, to Final Status Survey Report Saxton Nuclear Experimental Corporation Spray Pond Area
- E910-05-029, Calculation E900-05-013, Rev. 0, Open Land FSS Design - OL8, Appendix a, with Attachments, to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area OL8
- E910-05-030, Calculation E900-05-003, Rev. 0, Penelec Switch Yard, Class 2 Area, Survey Design, Appendix C-1, with Attachments, to Final Status Survey Report for Saxton Nuclear Experimental Corporation Penelec Switch Yard Area
- E910-05-037, Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces - Basement SS14, SS15, SS16, SS17, Appendix E, E900-05-008 Calculation Sheet
- E910-05-046, Rev 0 to E900-04-017, Upper Spray Pump Area and Discharge Tunnel Entrance Survey Design, Appendix B & Attachments, to Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfa
- E910-05-052, Rev. 0 to Calculation E900-04-027, Cv Yard Survey Design - Temporary Water Supply Trench in Cv Yard, Appendix A-1 to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area Survey Unit OL1-6
- E910-05-054, Rev. 0 to Calculation E900-03-014, Shonka Line Shack & Warehouse/Garage Pads FSS Survey Design, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corporation Structural Surfaces - Small Penelec Garage GA1-1
- E910-05-055, Rev. 0 to Calculation 6900-02-025, Multiple Source Term Bounding Calculation, Appendix B to Final Status Survey Report for Saxton Nuclear Experimental Corporation Embedded / Buried Piping
- E910-05-056, Rev. 0 to Calculation E900-05-024, Open Land FSS Design-OL3, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area OL3
- ET 13-0035, Fire Protection Program Re Alternative Shutdown Capability
G
- GNRO-2004/00057, Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology
- GO2-04-170, Calculation, Secondary Containment Drawdown
- GO2-09-043, Independent Spent Fuel Storage Installation - Offsite Dose Calculation Manual, Including Revision Made During 2008
- GO2-11-039, Offsite Dose Calculation Manual
- GO2-12-031, Offsite Dose Calculation Manual
- GO2-13-067, Offsite Dose Calculation Manual
- GO2-14-069, Offsite Dose Calculation Manual
- GO2-18-063, Offsite Dose Calculation Manual
H
- HBL-05-005, Response to NRC Request for Additional Information Regarding License Amendment Request 04-02, Spent Fuel Cask Handling (TAC L52634). Calculation File No. PRA04-08 Enclosed
- HBL-13-004, ODCM, Revision 22, Volume 4, Safstor/Decommissioning Offsite Dose Calculation Manual
- HBL-13-007, ENG-HB-005, Rev 0, Area Factors for Use with Humboldt Bay Soil Dcgls
- HNP-03-046, Off-Site Dose Calculation Manual, Revision 16
- HNP-09-014, Calculation HI-971760, Licensing Report for Expanding Storage Capacity in Harris Spent Fuel Pools C and D
- HNP-11-075, Attachment 1, Response to Request for Additional Information Regarding License Amendment Request Measurement Uncertainty Recapture Power Uprate, HNP Calculation HNP-I/INST-1010, Rev. 4
- HNP-13-001, License Amendment Request to Revise Technical Specification Table 3.3-4 Degraded Voltage Time Delay Values Acceptance Review Supplement
- HNP-13-122, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program- Third Ten-Year Interval Supporting Calculations
- HNP-16-095, Relief Request l3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval, Non-Proprietary Version of Calculation
J
- JAFP-05-0179, Enclosure 13, Calculation JAF-CALC-ELEC-02610 125VDC B Station Battery Sizing & Voltage Drop Revision 2, Appendix 4, Page 2 of 2, SBO
- JAFP-07-0125, ENT-FLU-002-R-005, Rev 0, James A. FitzPatrick, License Renewal Application - Amendment 14, Fluence Calculation, Non-Proprietary Version
- JAFP-08-0067, Calculation No. 0800846.301, Revision 0, 2 Instrument Nozzle Stress Analysis
- JAFP-08-0067, Calculation No. 0800846.302, Revision 0, Comparison of Instrument Nozzle (N16) and Beltline P-T Curves.
- JAFP-08-0067, Calculation No. FITZ-10Q-301, Revision 0, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts.
- JAFP-08-0067, Calculation No. FITZ-10Q-302, Revision 0, Revised Pressure-Temperature Curves.
- JAFP-08-0131, Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C
- JAFP-08-0131, Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report
- JAFP-10-0033, Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4
- JAFP-13-0035, Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 23
- JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
L
- L-03-008, Additional Questions Related to Supplemental Blasts & Explosions Responses to Additional NRC Questions for Diablo Canyon Independent Spent Fuel Storage Installation Application
- L-08-056, Reactor Protection System High Flux Trip Setpoint Calculation
- L-08-349, Calculation for Contingency Flaw Evaluation Support
- L-09-111, Offsite Dose Calculation Manual, Revision 22
- L-09-122, Calculation 0900354.301, Rev. 0, Flaw Evaluation for N6A and C Nozzle to Safe End Welds
- L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches)
- L-10-050, RTL A9.621B, 1/2-ODC-1.01, Revision 8, ODCM: Index, Matrix and History of ODCM Changes.
- L-10-050, RTL A9.621B, 1/2-ODC-1.01, Revision 8, ODCM: Index, Matrix and History of ODCM Changes
- L-10-131, Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles
- L-11-143, Operations Manual, Offsite Dose Calculation Manual, Revision 18
- L-11-150, Offsite Dose Calculation Manual, Rev. 24
- L-12-152, Offsite Dose Calculation Manual, Revision 26
- L-12-167, Enclosure B, Offsite Dose Calculation Manual, Revision 18 and Enclosure C, Process Control Program, Revision 12
- L-13-138, Enclosure B to L-13-138, Offsite Dose Calculation Manual, Revision 20 and Enclosure C, Process Control Program, Revision 12
- L-14-135, Offsite Dose Calculation Model, Revision 27
- L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations
- L-15-010, Offsite Dose Calculation Manual, Revision 29
- L-15-143, 0 to Offsite Dose Calculation Manual
- L-15-257, Calculation PRDC-0015, Rev. 2, Addendum A02, Division 2,125 Vdc System Load Evaluation, Voltage Drop, Battery/Battery Charger Sizing Calculation
- L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits
- L-16-125, ODCM: Index, Matrix and History of ODCM Changes
- L-16-134, Offsite Dose Calculation Manual, Revision 31
- L-17-126, ODCM: Index, Matrix and History of ODCM Changes
- L-20-093, Offsite Dose Calculation Manual, Revision 37
- L-2004-203, Request for Additional Information Alternate Source Term License Amendment
- L-2008-029, Annual Radioactive Effluent Release Report January 1, 2007 Through December 31, 2007, Attachment C, C-200, Offsite Dose Calculation Manual Revision 30
- L-2008-130, Supplement to 2007 Annual Radioactive Effluent Release Report
- L-2009-039, Attachment C, C-200, Offsite Dose Calculation Manual Revision 31B, Annual Radioactive Effluent Release Report, January 1, 2008 Through December 31, 2008
- L-2010-033, Offsite Dose Calculation Manual (Odcm), Chemistry Operating Procedure C-200, Rev 31B, Marked Up Pages
- L-2010-033, St. Lucie, Units 1 and 2, Offsite Dose Calculation Manual (Odcm), Chemistry Operating Procedure C-200, Rev 31B, Marked Up Pages
- L-2010-033, St. Lucie, Units 1 and 2, Offsite Dose Calculation Manual, Chemistry Operating Procedure C-200, Rev 32.
- L-2011-064, Annual Radioactive Effluent Release Report - January 1, 2010 Through December 31, 2010, Enclosures 2 and 3, Offsite Dose Calculation Manual Revisions
- L-2012-080, Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011, C-200, Offsite Dose Calculation Manual Revision 35
- L-2013-078, C-200, Rev. 38, Offsite Dose Calculation Manual
- L-2014-044, Offsite Dose Calculation Manual for Gaseous and Liquid Effluents, Revision 20
- L-2014-053, Enclosure 2 - Procedure C-200, Rev. 41, Offsite Dose Calculation Manual (Odcm)
- L-2015-052, Enclosures 2, 3, 4 & 5: St. Lucie, Units 1 and 2 - Revision 43 to C-200, Offsite Dose Calculation Manual and Revision 14 to Process Control Program, Including Marked Up Pages from ODCM and PCP
- L-2016-037, C-200, Revision 45, Offsite Dose Calculation Manual
- L-2018-048, Offsite Dose Calculation Manual
- L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55
- L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)
- L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt
- L-MT-03-031, Operability Evaluation of the EDG Exhaust Piping for a Tornado Event, Rev 0, Attachments F Through H
- L-MT-04-031, Offsite Dose Calculation Manual - Appendix C, Revision 0
- L-MT-05-042, ODCM-APP-C, Rev 0, Appendix C
- L-MT-06-028, Calculation CA-04-042, Rev 0, MNGP AST - Post LOCA Ph Analysis
- L-MT-07-032, Off-Site Dose Calculation Manual
- L-MT-08-045, Response to Requests for Additional Information for License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function
- L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis
- L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac)
- L-MT-09-037, Enclosure 3 - Monticello Revisions to ODCM-01.01, Offsite Dose Calculation Manual
- L-MT-10-035, Revisions to Offsite Dose Calculation Manual, Enclosure 3