ML21125A301
Text
FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 35 REFERENCES Page 4-1 of 4-5
- 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 35 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, "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 35 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 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 35 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 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.
- 60.
Letter from Entergy Nuclear Operations, Inc. to NRC, "License Amendment Request for Approval of Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margins Analysis," dated November 12, 2014.
FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 35 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 Nuclear 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 Pressurized Thermal Shock Events,'"
dated July 29, 2014 (ADAMS Accession No. ML14211A520).
- 63.
WCAP-17628-NP, "Alternate Pressurized 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).
- 65.
Entergy Nuclear Operations, Inc. Letter PNP 2019-026 Proposed Revision to Palisades Nuclear Plant Reactor Vessel Surveillance Capsule Withdrawal Schedule, dated June 24, 2019 (ADAMS Accession Number ML19175A102)
- 66.
NRC Letter Palisades Nuclear Plant-Reactor Vessel Material Surveillance Capsule Withdrawal Schedule (EPID L-2019-LRO-0051), dated December 2, 2019 (ADAMS Accession No. ML19318E394)
- 67.