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Final Safety Analysis Report Update, Revision 32, Chapter 3 - Reactor - References
	ML16120A360
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Site:	Palisades
Issue date:	04/18/2016
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
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FSAR CHAPTER 3 - REACTOR Revision 32 REFERENCES Page 3-1 of 3-4

1. Advanced Nuclear Fuels, "Mechanica l Licensing Report for Palisades High Thermal Performance Fuel Assemblies", ANF-90-079(P)R1, September 1990

2. WCAP-15353, Revision 0, "Palisa des Reactor Pressure Vessel Neutron Fluence Evaluation," Westinghouse Electr ic 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 Gr oup, "Leak-Before-Break Evaluation of Primary Coolant Loop Piping in Combus tion Engineering De signed 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, "Palisa des 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 Evaluati on and Revised Schedule for Reaching Pressurized Thermal Shock Screening Criteria (TAC No. MA8250)," November 14, 2000

9. Siemens Power Corporation, "R eactor Analysis System for PWRs,"

EMF-96-029(P)(A) Volumes 1 and 2, January 1997

10. Siemens Power Corporation, "Palis ades 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 Met hodology 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 32 REFERENCES Page 3-2 of 3-4

14. Siemens Nuclear Power Corporat ion, "Mechanical Design Report for Palisades N Debris Resistant Design", EMF-91-164(P) Rev 0, November 1991

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19. Deleted

20. Exxon Nuclear Report, "XCOBRA-IIIC

A Computer Code To Determine the Distribution of Coolant During Steady-S tate 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 Nu clear 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 Fini te Time Step Length on Calculated Spatial Xenon Stability Characteristics in Large PWRs," Trans ANS, 10, 2, P 571, 1967

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FSAR CHAPTER 3 - REACTOR Revision 32 REFERENCES Page 3-3 of 3-4

32. DeAgazio, Albert, USNRC, "Safety Evaluation on Asymmetric LOCA Loads -

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 M anual, Rev 9, January 2001

36. The PIDAL-3 Methodology Manual, Rev 16, January 2001

37 The PIDAL-3 Uncertainty A nalysis Manual, Rev 8 January 2001

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

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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, "Justificat ion 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 Co rrespondence 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, "H TP:Departure From Nucleate Boiling Correlation For High Thermal Perfo rmance Fuel" and Suppl ement 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 32 REFERENCES Page 3-4 of 3-4

47. Deleted

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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 Pali sades 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 Pressu rized 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 (ADA MS Accession No. ML15209A791).