ML15226A020
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ML15226A020 | |
Person / Time | |
---|---|
Site: | Palisades ![]() |
Issue date: | 09/15/2014 |
From: | Entergy Nuclear Operations |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML15226A139 | List: |
References | |
PNP 2014-086 | |
Download: ML15226A020 (4) | |
Text
FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 30 REFERENCES Page 4-1 of 4-4
- 1. Energy Inc, "Palisades Plant PCS Overpressurization Subsystem Description" Report, October 1977
- 2. CEN-5, "Palisades Reactor Internal Wear Report," April 1974
- 3. WCAP-15353, Revision 0, "Palisades Reactor Pressure Vessel Neutron Fluence Evaluation," Westinghouse Electric Company, LLC, Roberts, G.K., et al., January 2000
- 4. Deleted
- 5. 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
- 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 Circulation 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 Predicted Radiation Damage to Reactor Vessel Materials," Revision 2, May 1988
- 11. US NRC Standard Review Plan, Directorate of Licensing, Section 5.3.2, "Pressure-Temperature Limits"
- 12. ASME B&PV Code,Section III, Appendix 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 Requirements," May 31, 1983 as Amended November 6, 1986
- 15. Battelle Report, "Palisades Nuclear Plant Reactor Vessel Surveillance Program: Capsule A-240," March 13, 1979
FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 30 REFERENCES Page 4-2 of 4-4
- 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, "Analysis 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 Madeyski (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 Vessel Pressurized Thermal Shock"
- 22. CEN-152, "Combustion Engineering Emergency Procedure Guideline," Dated May 8, 1984
- 23. Palisades Technical Specifications 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 Stratification - Additional Information"
- 29. CEN-387-P (Also Numbered CE NPSD-546-P), "Pressurizer Surge Line Flow Stratification Evaluation," July 1988
- 30. Engineering Analysis 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 Provisional 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 30 REFERENCES Page 4-3 of 4-4
- 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 Group, "Leak-Before-Break Evaluation of Primary Coolant Loop Piping in Combustion Engineering Designed 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), September 13, 1993, "Safety Evaluation for Combustion Engineering Owners Group 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 Manual-Steam Generators- Palisades Plant Consumers Power Company, Combustion Engineering Inc., Nuclear Components Department, Chattanooga, Tennessee, January 1982
- 42. Combustion Engineering Calculation 82688-STS-602, "Steam Generator Inventory", Contract 82688-Palisades Replacement 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 Operating 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 30 REFERENCES Page 4-4 of 4-4
- 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 Capsule W-100 from the Nuclear Management Company Palisades Reactor Vessel Material Surveillance Program," February 2004
- 52. NRC Order EA-03-009, "Issuance of First 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 Chapter 14 Safety Analysis Parameter Changes Due to FC-977 Power Uprate"
- 54. Appendix G to the 1998 through the 2000 Addenda Edition of the ASME Boiler and Pressure Vessel Code,Section XI, Division 1, "Fracture Toughness Criteria for Protection 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 Palisades 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. ME5263)," 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.