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Final Safety Analysis Report Update, Revision 32, Chapter 4 - Primary Coolant System - References
	ML16120A380
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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 4 - PRIMARY COOLANT SYSTEM Revision 32 REFERENCES Page 4-1 of 4-5

1. Energy Inc, "Palisades Plant PCS Ov erpressurization S ubsystem Description" Report, October 1977

2. CEN-5, "Palisades Reactor In ternal Wear Report," April 1974

3. WCAP-15353, Revision 0, "Palisades Reactor Pressure Vessel Neutron Fluence Evaluation," West inghouse Electric Company, LLC, Roberts, G.K., et al., January 2000

4. Deleted

5. 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

6. WASH-1400 (NUREG-75/014), Appendix V, October 1975

7. Combustion Engineering Report, "Input for Response to NRC Lessons Learned Requirements for Combustion Engineering Nuclear Steam Supply Systems," CEN-125, December 1979

8. CE-NPSD-154, "Natural Circu lation Cooldown," October 1981

9. Technical Paper - WAPD-BT18 Bettis Technical Review, Reactor Technology Section, "Application of Stress Concentration Factors" by B F Langer, April 1960

10. US Nuclear Regulatory Commission, Regulatory Guide 1.99, "Effects of Residual Elements on Pr edicted Radiation Damage to Reactor Vessel Materials," Revision 2, May 1988

11. US NRC Standard Review Plan, Directorate of Lic ensing, Section 5.3.2, "Pressure-Temperature Limits"

12. ASME B&PV Code,Section III, Appendi x G, "Protection Against Non-Ductile Failure," 1974 Edition

13. C-PAL-98-1924 Code Analytical Report Fatigue Analysis and Specification for the RV Missing 500 Reactor Trips Listed in FSAR Section 4.2.2

14. 10 CFR 50, Appendix G, "Fracture Toughness Requirement s," May 31, 1983 as Amended November 6, 1986

15. Battelle Report, "Palisades Nuclea r Plant Reactor Vessel Surveillance Program: Capsule A-240," March 13, 1979

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 32 REFERENCES Page 4-2 of 4-5

16. Deleted

17. Consumers Power Company Letter, From Brian D Johnson to Harold R Denton, US Nuclear Regulatory Commission, Dated October 31, 1984

18. Kunka, M K and Cheney, C A, "Analys is of Capsules T-330 and W-290 From the Consumers Power Company Palisades Reactor Vessel Radiation - Surveillance Program," WCAP-10637, September 1984

19. Peter, Lippincott, Wrights and Ma deyski (Westinghouse), "Analysis of Capsule W-110 from the Consumers Power Company Palisades Reactor Vessel Surveillance Program," May 1994

20. Deleted

21. SOER 82-7, "Reactor Vesse l Pressurized Thermal Shock"

22. CEN-152, "Combustion Engineeri ng Emergency Procedure Guideline," Dated May 8, 1984

23. Palisades Technical Spec ifications Basis B3.4.3

24. Palisades Systems Operation Procedure SOP-1, "Primary Coolant System"

25. Deleted

26. Deleted

27. CPCo to NRC dated November 22, 1993, "Palisades Plant - Bulletin 88-11:

Pressurizer Surge Line Thermal Stratification - Additional Information"

28. CPCo to NRC dated April 30, 1994, "Palisades Plant - Bulletin 88-11:

Pressurizer Surge Line Thermal Strati fication - Additional Information"

29. CEN-387-P (Also Numbered CE NPSD-546-P), "Pressurizer Surge Line Flow Stratification Evaluation," July 1988

30. Engineering Anal ysis EA-FC-809-13

31. Engineering Analysis EA-PTS-87010, DOT Benchmarking Model

32. Holian, Brian, NRC Project Manager, to Gerald B. Slade, Palisades Plant General Manger, "Amendment No. 135 to Pr ovisional Operating License No. DPR-20," February 11, 1991

33. 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

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 32 REFERENCES Page 4-3 of 4-5

34. Combustion Engineering Report, "Response to Questions on the Reactor Coolant System Asymmetric Loads Evaluation Program Final Report," Submitted to the NRC on July 31, 1981

35. 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

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

MPA D-010 - Palisades Plant (Tac No MO8621)" to K W Berry, October 27, 1989

37. Deleted

38. Deleted

39. Hsia (NRC) to Slade (CPCo), Sept ember 13, 1993, "Safety Evaluation for Combustion Engineering Owners Gr oup Report CEN-387-P, Revision 1, 'Pressurizer Surge Line Flow Stratification' (Bulletin 88-11) (TAC No. M72151"

40. ESS Specification SP-MP-8304-002(Q), Revision 1 of Conformed Palisades Specification M1-LBA, Data Sheet 1 for PRV-1042B

41. C.E. Book No. 70277, Instruction M anual-Steam Generators- Palisades Plant Consumers Power Company, Combus tion Engineering Inc., Nuclear Components Department, Chatta nooga, Tennessee, January 1982

42. Combustion Engineering Calculat ion 82688-STS-602, "S team Generator Inventory", Contract 82688-Palisades Replacem ent Steam Generator, J.C.Lowry, December 20, 1989

43. Combustion Engineering Report, "Specification for Steam Generator Assemblies for Consumers Power Company", Specification No. 19377-PE-

120 dated June 24, 1982

44. Combustion Engineering Calculation Number PSEC-36, "Sizing of Pressurizer Spray Nozzle and Piping," dated 2/14/67

45. Hannon (NRC) to Bordine (Consumers), December 20, 1996, "Palisades:

Evaluation of Updated Reactor Pressure Vessel Fluence Values (TAC No.

M95134)"

46. Specification Change 95-038, Revision of LTOP Program

47. Amendment No. 163 to Facility Oper ating License No. DPR-20 for the Palisades Plant.

SUBJECT:

PALISADES PLANT - ISSUANCE OF AMENDMENT RE: PRESSURE-TEMPERATURE LIMITS (TAC NO. M90650)

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 32 REFERENCES Page 4-4 of 4-5

48. Combustion Engineering, Engineering Specification for a Pressurizer Assembly, Specification No 70P-001, Revision 3 (F679/1631)

49. NRC, SER "Approval of ASME Code Case N-474-2 to Use Forged Alloy 690 (SB-564) Material," May 4, 1995

50. Hood (NRC) to Cooper (NMC), October 11, 2001, "Palisades Plant - Revised Withdrawal Schedule for Reactor for Vessel Surveillance Capsule T-150 (TAC No. MB2862)"

51. BWXT Report, "Analysis of Capsul e W-100 from the Nuclear Management Company Palisades Reactor Vessel Ma terial Surveillance Program,"

February 2004

52. NRC Order EA-03-009, "Issuance of Fi rst Revised NRC Order (EA-03-009)

Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors"

53. EA-RCH-01-05, "Calculation of C hapter 14 Safety Analysis Parameter Changes Due to FC-977 Power Uprate"

54. Appendix G to the 1998 through t he 2000 Addenda Edition of the ASME Boiler and Pressure Vessel Code,Section XI, Division 1, "Fracture Toughness Criteria for Pr otection Against Failure"

55. Engineering Analysis EA-EC27959-01, "Palisades Pressure-Temperature Limit Curves and Upper-Shelf Energy Evaluation," February 2012.

56. 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).

57. Engineering Analysis EA-EC26115-01, Revision 0, "Pressurized Thermal Shock PTS Evaluation for the Pali sades Reactor Pressure Vessel," February 2012.

58. Letter from MChawla (NRC) to Vice President Operations Entergy-Palisades, "Updated Reactor Pressure Vessel Pressurized Thermal Shock Evaluation for Palisades Nuclear Plant (TAC No. ME 5263)," December 7, 2011 (contains the Safety Evaluation for the updated PTS evaluation).

59. Letter from MChawla (NRC) to Vice President, Entergy Nuclear Operations, "Palisades Plant - Evaluation of Relief Request to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination (TAC No.

MD9265)," February 11, 2009.

60. Letter from Entergy Nuclear Operat ions, Inc. to NRC, "License Amendment Request for Approval of Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margins Analysi s," dated November 12, 2014.

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 32 REFERENCES Page 4-5 of 4-5

61. NRC Amendment No. 258 to Facility Operating License No. DPR-20 for the Palisades Plant,

Subject:

"Palisades Nu clear Plant - Issuance of Amendment Re: Request for Approval of 10 CFR 50 Appendix G Equivalent Margins Analysis (CAC No. MF5163)," dated November 23, 2015.

62. Entergy Nuclear Operations, Inc.

letter PNP 2014-049, "License Amendment Request to Implement 10 CFR 50.61a, 'Alternate Fracture Toughness Requirements for Protection Against Pr essurized Thermal Shock Events,'" dated July 29, 2014 (ADAMS Accession No. ML14211A520).

63. WCAP-17628-NP, "Alternate Pressu rized Thermal Shock (PTS) Rule Evaluation for Palisades," Revision 1, June 2014 (Palisades Engineering Report PLP-RPT-16-00005).

64. 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).