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FSAR CHAPTER 3 - REACTOR Revision 35 REFERENCES Page 3-1 of 3-4
- 1. Advanced Nuclear Fuels, "Mechanical Licensing Report for Palisades High Thermal Performance Fuel Assemblies", ANF-90-079(P)R1, September 1990
- 2. WCAP-15353, Revision 0, "Palisades Reactor Pressure Vessel Neutron Fluence Evaluation," Westinghouse Electric Company, LLC, Roberts, G. K.,
et al, January 2000
- 3. CE Owner's Group Asymmetric Loads Program Report, "Reactor Coolant System Asymmetric Loads Evaluation Program Final Report," Volumes 1, 2 and 3, dated June 30, 1980
- 4. Combustion Engineering Owner's Group, "Leak-Before-Break Evaluation of Primary Coolant Loop Piping in Combustion Engineering Designed Nuclear Steam Supply Systems," CEN-367, November 1987
- 5. Exxon Nuclear Company, "Plant Transient Analysis of the Palisades Reactor for Operation at 2,530 MWt," XN-NF-77-18, July 1977
- 6. Siemens Power Corporation, "Palisades Cycle 14 Safety Analysis Report,"
EMF-98-008, Rev 1, May 1998
- 7. EA-PTS-00-01, Revision 0, "PTS Screening Criterion Date Calculation and Owner's Review of Westinghouse Fluence Report WCAP,15353,"
February 2000
- 8. Hood (NRC) to Haskell (Consumers), "Palisades Plant - Reactor Vessel Neutron Fluence Evaluation and Revised Schedule for Reaching Pressurized Thermal Shock Screening Criteria (TAC No. MA8250)," November 14, 2000
- 9. Siemens Power Corporation, Reactor Analysis System for PWRs, EMF-96-029(P)(A) Volumes 1 and 2, January 1997
- 10. Siemens Power Corporation, Palisades PRISM Benchmark, Cycles 11-14, E-2323-N01-1, April 1999
- 11. EMF-1961(P)(A), Revision 0, Siemens Power Corporation, July 2000, Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors
- 12. Exxon Nuclear Report, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," XN-75-27, June 1975; Supplement 1, April 1977; Supplement 2, December 1980; Supplement 3, September 1981; Supplement 4, 1985; and Supplement 5, 1987
- 13. BAW-2489P, Revised Fuel Assembly Growth Correlation for Palisades.
dated March, 2005.
FSAR CHAPTER 3 - REACTOR Revision 35 REFERENCES Page 3-2 of 3-4
- 14. Siemens Nuclear Power Corporation, "Mechanical Design Report for Palisades N Debris Resistant Design", EMF-91-164(P) Rev 0, November 1991
- 15. Deleted
- 16. Deleted
- 17. Deleted
- 18. Deleted
- 19. Deleted
- 20. Exxon Nuclear Report, "XCOBRA-IIIC: A Computer Code To Determine the Distribution of Coolant During Steady-State and Transient Core Operation,"
XN-75-21, April 1975
- 21. Advanced Nuclear Fuel, "Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events," ANF-87-150(NP), Volume 2, June 1988
- 22. Exxon Nuclear Company, "Exxon Nuclear DNB Correlation for PWR Fuel Design," XN-NF-621(A), Rev 1, April 1982
- 23. Exxon Nuclear Report, "Justification of XNB Correlation for Palisades, XN-NF-709," May 1983
- 24. Randall, D, "Xenon Spatial Oscillations," Nucleonics 16, 3, Pp 82-86, 1958
- 25. Daitch, P B, CEND-TP-26
- 26. Stacey, W M, Jr, "Linear Analysis of Xenon Spatial Oscillations," Nuclear Science Engineering 30, Pp 453-455, 1967
- 27. Poncelet, C G, "The Effect of a Finite Time Step Length on Calculated Spatial Xenon Stability Characteristics in Large PWRs," Trans ANS, 10, 2, P 571, 1967
- 28. Deleted
- 29. Deleted
- 30. Deleted
- 31. Deleted
FSAR CHAPTER 3 - REACTOR Revision 35 REFERENCES Page 3-3 of 3-4
MPA D-010 - Palisades Plant (Tac No MO8621)" to K W Berry, October 27, 1989
- 33. Advanced Nuclear Fuels, "Palisades Batch K and L Evaluation For Increased Power Peaking For Cycles 9 and 10," ANF-88-087(P) Rev 1 Supplement 1, November 1990
- 34. Deleted
- 35. The PIDAL-3 Users Manual, Rev 10, May 2001
- 36. The PIDAL-3 Methodology Manual, Rev 17, May 2001
- 37. The PIDAL-3 Uncertainty Analysis Manual, Rev 21, October 2020
- 38. Advanced Nuclear Fuels, "Review and Analysis of SRP Chapter 15 Events for Palisades With A 15% Variable High Power Trip Reset," ANF-90-181, November 1990
- 39. Holian, Brian, USNRC, "Safety Evaluation on the Seismic Analysis of High Thermal Performance Fuel Design (TAC No M75590)" to G.B. Slade (CPCo),
April 6, 1992
- 40. Deleted
- 41. NRC Generic Letter, Supplement 1 to Generic Letter 90-02, "Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications"
- 42. Advanced Nuclear Fuels, "Departure From Nucleate Boiling Correlation for High Thermal Performance Fuel," ANF-1224(P)(A) Supplement 1, April 1990
- 43. Advanced Nuclear Fuels, "Justification of the ANFP DNB Correlation for High Thermal Performance Fuel in the Palisades Reactor," ANF-89-192(P),
January 1990
- 44. CE Power Systems Interoffice Correspondence from D.E.Sharrard to L.W.Ward dated March 16, 1979, "Input Data For Analysis of Palisades Batches B and C", P-CA-081, Cart/Frm:F667/2064
- 45. Siemens Power Corporation, "HTP:Departure From Nucleate Boiling Correlation For High Thermal Performance Fuel" and Supplement 1, EMF 153(P)(A), March 7, 1994
- 46. EA-EAR-96-0726-01, Rev 0, Withdrawn/Inoperable Control Rod Worth for the EOPs
FSAR CHAPTER 3 - REACTOR Revision 35 REFERENCES Page 3-4 of 3-4
- 47. Deleted
- 48. Deleted
- 49. Deleted
- 50. ANP-2750 (NP), Revision 1, Palisades Nuclear Plant Realistic Large Break LOCA Summary Report, December 2008
- 51. Deleted
- 52. Deleted
- 53. WCAP-15353, Supplement 1-NP, Revision 0, "Palisades Reactor Pressure Vessel Fluence Evaluation," Westinghouse Electric Company, LLC, May 2010 (filed in Palisades Engineering Report No. PLP-RPT-10-00058).
- 54. Engineering Analysis EA-EC26115-01, Revision 0, "Pressurized Thermal Shock PTS Evaluation for the Palisades Reactor Pressure Vessel,"
February 2012.
- 55. Letter from MChawla (NRC) to Vice President Operations Entergy-Palisades, "Updated Reactor Pressure Vessel Pressurized Thermal Shock Evaluation for Palisades Nuclear Plant (TAC No. ME5263)," December 7, 2011 (contains the Safety Evaluation for the updated PTS evaluation).
- 56. Entergy Nuclear Operations, Inc. letter PNP 2013-046, "Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation," dated June 25, 2013 (ADAMS Accession No. ML13176A412).
- 57. Entergy Nuclear Operations, Inc. letter PNP 2014-049, "License Amendment Request to implement 10 CFR 50.61a, 'Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events,"
dated July 29, 2014 (ADAMS Accession No. ML14211A520).
- 58. WCAP-17628-NP, "Alternate Pressurized Thermal Shock (PTS) Rule Evaluation for Palisades," Revision 1, June 2014 (Palisades Engineering Report PLP-RPT-16-00005).
- 59. NRC letter, "Palisades Nuclear Plant - Issuance of Amendment Re: License Amendment Request to Implement 10 CFR 50.61a, 'Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," dated November 23, 2015 (ADAMS Accession No. ML15209A791).