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The following 200 pages are in this category, out of 1,769 total.
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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.
- 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
- 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-2018-35, 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
- 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 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, Vermont Yankee - Calculation ENTGVY036-CALC-001, Revision 1, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant
- 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-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
- 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 4 Continued
- 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 Octob
- 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
- E900-05-027, Experimental Corporation Final Status Survey Report for OL6 and OL10, Snec Calculation Sheet
- 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-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, Lnservice 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-10-131, Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles
- L-11-150, Offsite Dose Calculation Manual, Rev. 24
- L-12-152, Offsite Dose Calculation Manual, Revision 26
- 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, Revision 20 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, 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-2018-048, Offsite Dose Calculation Manual
- 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-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-12-011, Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals
- L-MT-13-019, Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer.
- L-MT-14-016, Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant
- L-MT-14-082, Exemption Request for Dry Shielded Canisters 11-16 Dye Penetrant Examinations, Supplemental Information
- L-MT-15-056, Redacted - Calculation 1042-0205, Revision 1, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation.
- L-MT-16-001, 54005-CALC-001, Revision 2, Evaluation of Risk Significance of Permanent ILRT Extension
- L-MT-16-016, Redacted - Calculation 11042-0205, Revision 3, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation.
- L-MT-23-030, Subsequent License Renewal Application Supplement 3
- L-PI-03-020, License Amendment Request Dated March 25, 2003 Safety Analyses Transition, Tabs F - H
- L-PI-03-052, Annual Radioactive Effluent Report & Offsite Dose Calculation Manual. Attachment 4 Pages 77 - 211
- L-PI-08-029, Supplement to License Amendment Request (LAR) to Add a Power Factor to the Emergency Diesel Generators' (EDG) 24-Hour Load Test (Surveillance Requirement 3.8.1.9)
- L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5
- L-PI-14-072, License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture
- L-PI-16-037, Transmittal of 2015 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
- LIC-03-0067, Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power Uprate
- LIC-03-0166, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate
- LIC-05-0048, Additional Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
- LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 51 Through 90
- LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 91 Through End
- LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System.
- LIC-08-0067, Response to Request for Additional Information Relief Request for Valve Replacement and Supplemental Information
- LIC-16-0044, Calculation FC08499 Evaluation of FCS Concrete Compressive Strength Test Data
- LIC-16-0109, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Attachments 1, 2, 4, 5 and 6)
- LIC-17-0024, Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)
- LIC-18-0015, CH-ODCM-0001, Revision 26, Off-Site Dose Calculation Manual.
- LIC-18-0015, CH-ODCM-0001, Revision 27, Off-Site Dose Calculation Manual.
- LR-N04-0413, Waste Gas Decay Tank and Volume Control Tank Rupture Accidents - AST Analysis
- LR-N05-0424, Attachment 1, Calculation S-1-SJ-MDC-1539, Revision 2, Accumulator Pressure Decay Time During Discharge Test.
- LR-N08-0308, Attachment 3 - Salem, Units 1 and 2 - Calculation S-2-SJ-MDC-1394, Rev. 5, Accumulator Pressure Decay Time During Discharge Test.
- LR-N09-0074, Letter from Jeffrie Keenan of PSEG Nuclear L.L.C., NRC Decommissioning Funding Status Report for Salem, Hope Creek & Peach Bottom Generating Stations
- LR-N09-0099, Annual Radioactive Effluent Release Report, Page 181 Through End
- LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
- LR-N10-0140, Hope Creek - Attachment 1, Offsite Dose Calculation Manual Revision, 23
- LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual Revision, 24
- LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22
- LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23
- LR-N10-0355, Hope Creek, CC-AA-309-1001, Rev. 3, Hc Class 1E 125 Vdc Station Battery & Charger Sizing
- LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 25
- LR-N10-0355, Offsite Dose Calculation Manual, Rev. 25 for Pseg Nuclear LLC Salem Generating Station
- LR-N17-0044, Enclosure 14 O LR-N17-0044 and LAR H17-03 - Calculation SC-BB-0525, Hope Creek Heat Balance Uncertainty Calculation, Revision 5