ML18113A247
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| ML18113A247 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/31/2017 |
| From: | Britting J C Entergy Nuclear Operations |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18113A244 | List: |
| References | |
| PNP 2018-020 | |
| Download: ML18113A247 (147) | |
Similar Documents at Palisades | |
|---|---|
Category:Calculation
MONTHYEARML22087A5002022-03-28028 March 2022
[Table view]And Palisades Nuclear Power Plant - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) -- Entergy Nuclear Operations, Inc ML18152A9312018-05-30030 May 2018 Attachment 5: Second Level Undervoltage Relay Setpoint Calculation ML18152A9322018-05-30030 May 2018 Attachment 6: Second Level Undervoltage Time Delay Relays 162-153 and 162-154 Uncertainty Analysis PNP 2018-010, Attachment 8: LOCA with Offsite Power Available Calculation2018-05-30030 May 2018 Attachment 8: LOCA with Offsite Power Available Calculation PNP 2018-020, Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report2017-12-18018 December 2017 Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report ML18113A2472017-10-31031 October 2017 Enclosure 1 to Pnp 2018-020, Offsite Dose Calculation Manual, Revision 28 and Revision 29 ML18152A9342017-05-17017 May 2017 Attachment 7: 0098-0189-CALC-OO1, Revision 1, Palisades Slur Time Delay Calculation PNP 2015-076, Relief Request Number RR 4-24 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-09-26026 September 2015 Relief Request Number RR 4-24 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML15190A2652015-05-11011 May 2015 1400669.323, Rev. 0, Crack Growth Analysis of the Cold Leg Bounding Nozzle ML15190A2642015-05-11011 May 2015 1400669.313, Rev. 0, Crack Growth Analysis of the Hot Leg Drain Nozzle ML15190A2692015-05-0505 May 2015 1400669.322, Rev. 0, Cold Leg Bounding Nozzle Weld Residual Stress Analysis ML15190A2682015-05-0505 May 2015 1400669.312, Rev. 0, Hot Leg Drain Nozzle Weld Residual Stress Analysis ML15190A2672015-04-0303 April 2015 1400669.320, Rev. 0, Finite Element Model Development for the Cold Leg Drain, Spray and Charging Nozzles ML15190A2662015-03-0909 March 2015 1400669.310, Rev. 0, Finite Element Model for Hot Leg Drain Nozzle ML14301A2552014-10-24024 October 2014 Sargent and Lundy Calculation No. 2007-20168, Revision 00, Palisades Weld Flaw Analysis for Loaded Spent Fuel Cask Msb No. 4. ML14301A2542014-10-24024 October 2014 Calculation No. 1200250.301, Revision 1, Flaw Tolerance Evaluation of Spent Fuel Cask MSB#4 for Palisades Power Plant. ML14099A1612014-04-0404 April 2014 Calculation No. CPC-06Q-303, Revision 1, Analysis of Hypothetical Flaws in VSC-24 Shell and Bottom Plate ML14099A1692014-04-0404 April 2014 Calculation No. 1200250.301, Revision 0, Flaw Tolerance Evaluation of Spent Fuel Cask MSB#4 for Palisades Power Plant ML14070A3422014-03-0606 March 2014 Enclosure 2 - Calculation 1200895.307, Rev. 0, Hot Leg Drain Nozzle Crack Growth Analyses ML14070A3432014-03-0606 March 2014 Enclosure 3 - Calculation 1200895.308, Rev. 0, Hot Leg Drain Nozzle Limit Load Analyses for Flawed Nozzle-to-Hot Leg Weld ML14070A3412014-03-0606 March 2014 Enclosure 1 - Calculation 1200895.306, Rev. 0, Hot Leg Drain Nozzle Weld Residual Stress Analysis and Circumferential Crack Stress Intensity Factor Determination ML1212302952012-04-30030 April 2012 Reply to Request for Additional Information Relief Request - Proposed Alternative - Use of Alternate ASME Code Case N-770-1 Baseline Examination ML11339A1002011-11-30030 November 2011 Calculation EA-EC31177-01, Rev. 0, Calculation of Overspeed Trip Mechanism Linkage Forces ML1012702802010-01-12012 January 2010 Enclosure 1, Palisades Nuclear Plant, Offsite Dose Calculation Manual, Revision 23 ML0726801922007-09-14014 September 2007 NAI Report Release - NAI-1 149-018, Rev. 2, Palisades Design Basis Main Steam Line Break AST Radiological Analysis, Revised Calculations ML0726801912007-09-14014 September 2007 NAI Report Release - NAI-1149-002, Rev. 1, Determination of Atmospheric Dispersion Factors for Palisades, Enclosure 2, Revised Calculations ML0722504072007-08-10010 August 2007 Supplement to Request for Relief from ASME Section XI Code Requirements for Repair of Service Water Pipe ML0721305032007-07-31031 July 2007 Request for Relief from ASME Section XI Code Requirements for Repair of Service Water System Pipe ML0716302492007-04-19019 April 2007 Areva Calculation, 51-5049676-002, Palisades Vent Line Nozzle Repair Analysis Summary, April 2007 IR 05000496/19760022007-04-19019 April 2007 Areva Calculation, 51-5049676-002, Palisades Vent Line Nozzle Repair Analysis Summary, April 2007 ML0632602042006-10-19019 October 2006 NMC Calculation (Doc) No: EA-EC7408-02, Revision 0, Re-evaluation of Slope Stability Under ISFSI Pad for Revised Load Due to 24PTH System. ML0628304472006-09-14014 September 2006 NAI Report Release, Calculation NAI-1149-014, Revision 3, Palisades Design Basis AST Mha/Loca Radiological Analysis. ML0628304502006-09-13013 September 2006 NAI Report Release, NAI-1149-024, Revision 3, Determination of Direct Shine Doses for a Design Basis LOCA for Palisades. ML0702306222006-06-28028 June 2006 to VSC-03.3606, Criticality Analysis for Transport of the Palisades Msbs in the Fuelsolutions TS125 Cask. ML0619202402006-06-23023 June 2006 Calculation EA-EC976-09, Determine Post-LOCA Sodium Hydroxide Amount. ML0628304652006-06-0808 June 2006 NAI Report Release, Calculation NAI-1149-015, Revision 2, Palisades Design Basis Control Rod Ejection AST Radiological Analysis. ML0628304592006-06-0808 June 2006 NAI Report Release, Calculation NAI-1149-018, Revision 1, Palisades Design Basis Main Steam Line Break AST Radiological Analysis. ML0628304522006-06-0808 June 2006 NAI Report Release, NAI-1180-002, Revision 2, LOCA Direct Shine Doses from the SIRWT for Palisades. ML0702306142006-01-23023 January 2006 to VSC-03.3605, Palisades Msb Transportation Fuel Depletion Analysis. ML0628304622006-01-18018 January 2006 NAI Report Release, Calculation NAI-1149-019, Revision 1, Palisades Design Basis Steam Generator Tube Rupture AST Radiological Analysis. ML0628304282005-07-19019 July 2005 NAI Report Release, Calculation, NAI-1149-001, Revision 2, Source Terms for Palisades Dose Calculations. ML0712903532005-07-0606 July 2005 Rev. 20 to Offsite Dose Calculation Manual ML0628304692005-06-22022 June 2005 NAI Report Release, Calculation NAI-1149-026, Revision 0, Design Basis Cask Drop Accident AST Radiological Analysis. ML0517503182005-06-21021 June 2005 Enclosure 4, Proposed Exemption from the Requirements of 10 CFR 50.68(b)(1), Spent Fuel Pool Dilution Analysis ML0517503162005-06-21021 June 2005 Enclosure 3, Proposed Exemption from the Requirements of 10 CFR 50.68(b)(1), Criticality Analysis, Calculation 11030-01, Rev 0 ML0628304562005-06-17017 June 2005 NAI Report Release, Calculation NAI-1149-016, Revision 1, Palisades Design Basis Fuel Handling Accident AST Radiological Analysis. ML0628304432005-06-0909 June 2005 NAI Report Release, Calculation NAI-1149-001, Revision 0, Primary Coolant Source Term Determination for Palisades Dose Calculations. ML0628304672005-06-0909 June 2005 NAI Report Release, Calculation NAI-1149-001, Revision 0, Design Basis Small Line Break Outside Containment AST Radiological Analysis. ML0802906742005-04-12012 April 2005 EA-ELEC08-001, Rev. 12, Uncertainty Calculation for Secondary Calorimetric Heat Balance. ML0434503572004-12-0707 December 2004 Framatome Calculation, Areva Document 32-5054514-01, Palisades CRDM Nozzle Idtb Weld Repair Analysis, December 2004 2022-03-28 Category:Manual MONTHYEARML22104A0782022-04-14014 April 2022
[Table view]Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G PNP 2018-020, Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report2017-12-18018 December 2017 Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report ML18113A2472017-10-31031 October 2017 Enclosure 1 to Pnp 2018-020, Offsite Dose Calculation Manual, Revision 28 and Revision 29 ML17109A4872017-04-10010 April 2017 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G ENOC-13-00029, Planned Modification of the Entergy Quality Assurance Program Manual (EA-11-096)2013-11-0404 November 2013 Planned Modification of the Entergy Quality Assurance Program Manual (EA-11-096) CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML0904103222008-04-15015 April 2008 Entergy'S Quality Assurance Program Manual, Revision 18; Effective: April 15, 2008 ML0904101242008-01-30030 January 2008 EN-WM-100, Rev. 3, Work Request (WR) Generation, Screening and Classification. ENOC-07-00020, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 162007-06-15015 June 2007 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 16 ML0602405892006-01-20020 January 2006 Consumers Energy Environmental Procedure LM-300, Environmental Review - Permitting and Land Transactions ML0712903532005-07-0606 July 2005 Rev. 20 to Offsite Dose Calculation Manual 2022-04-14 |
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