ML16120A419

Final Safety Analysis Report Update, Revision 32, Chapter 6 - Engineered Safeguards Systems - References

ML16120A419
Person / Time
Site:	Palisades
Issue date:	04/18/2016
From:	Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16120A302	List: ML16120A321 ML16120A325 ML16120A326 ML16120A327 ML16120A344 ML16120A345 ML16120A347 ML16120A359 ML16120A360 ML16120A361 ML16120A362 ML16120A379 ML16120A380 ML16120A381 ML16120A382 ML16120A415 ML16120A416 ML16120A417 ML16120A419 ML16120A420 ML16120A421 ML16120A571 ML16120A573 ML16120A574 ML16120A575 ML16120A588 ML16120A589 ML16120A590 ML16120A591 ML16120A596 ML16120A597 ML16120A598 ML16120A599 ML16120A602 ML16120A603 ML16120A604 ML16120A608 ML16120A609 ML16120A610 ML16123A314 ML16123A315 ML16123A316 ML16123A320 ML16123A321 ML16123A326 ML16123A328 ML16123A329 ML16126A109 PNP 2016-015, Final Safety Analysis Report Update, Revision 32, Table of Contents
References
PNP 2016-015
Download: ML16120A419 (2)

Text

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMSRevision 30REFERENCES Page 6-1 of 6-2 1.Combustion Engineering Report, "Palisades Long-Term Cooling PerformanceEvaluation," P-CE-5627, May 8, 1981 2.Code of Federal Regulations - 10 CFR 50.46 and Appendix K 3.Oak Ridge National Lab Report, "Unit Operation Section Orderly ProgressReport," ORNL-3916, July-September 1965 4.Oak Ridge National Lab Report, "Gamma Radiation Damage andDecontamination Evaluation of Protective Coatings and Other Materials forHot Laboratory and Fuel Processing Facilities," ORNL-3589, February 19655.Deleted6.Deleted 7.Letter from Brian Holian (NRC) to GBSlade (CPCo), "Safety Evaluation of theSecond Ten-Year Interval Inservice Inspection Program Plan and AssociatedRequests for Relief for Palisades Nuclear Plant," dated September 3, 1991 8.Combustion Engineering Inc, Calc No P-PEC-170, Dated January 16, 1979,"Head Losses and Flow Requirements for Hot Leg Injection Line for Palisades"9.Deleted 10.Letter from Kenneth W. Berry (CPCo) to NRC, "Response to GenericLetter 88-17, Loss of Decay Heat Removal (60 day Response)", January 3 , 1989 11.Letter from Kenneth W. Berry (CPCo) to NRC, "Response to GenericLetter 88-17, Loss of Decay Heat Removal (90 day Response)",January 31, 1989 12.Letter from NRC to RCYoungdahl (CPCo) concerning boron precipitationpost-LOCA, March 14, 197513.Deleted 14.Generic Letter 90-05, "Guidance for Performing Temporary Non-Code Repairof ASME Code Class 1, 2, and 3 Piping," June 15, 1990 15.NRR Memorandum, "Follow-up on Generic Letter 90-05 Regarding Guidancefor Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3Piping," August 16, 1990 16.Condition Report C-PAL-95-0014, "HPSI Pumps - Design Basis ThermalTransient" FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMSRevision 30REFERENCES Page 6-2 of 6-2 17.Engineering Analysis EA-A-PAL-95-008, "Determination of MaximumAllowable Pressure for CSS piping (A-PAL-95-008)" 18.Engineering Analysis EA-FC-951-08, "Containment Air Cooler PerformanceCodes for the Replacement Air Coolers (Aerofin Coils)" 19.Letter from Dennis M Crutchfield (NRC) to David P Hoffman (CPCo), "SEPTopic III-4.C, Internally Generated Missiles," September 21, 1981 20.Letter from NRC to TCBordine (CE), "Palisades Plant - Issuance ofAmendment Re: Shutdown Cooling Technical Specification Change," datedOctober 10, 199621.Deleted22.Deleted 23.Letter from David H. Jaffe (NRC) to Daniel J. Malone (NMC), SafetyEvaluation by the Office of Nuclear Reactor Regulation Related toAmendment No. 221 to Facility Operating License No. DPR-20, datedJanuary 11, 2005 24.Engineering Analysis EA-CAP037584-01, Revision 0, Containment AirCooler Internal Flooding Response to a LOCA and a MSLB25.NRC Generic Letter 2004-02, Potential Impact of Debris Blockage onEmergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, September 13, 2004.

26.NRC Generic Letter (GL) 2008-01, "Managing Gas Accumulation inEmergency Core Cooling, Decay Heat Removal, and Containment SpraySystems," January 11, 2008.

27.Letter from Chris J. Schwarz (ENO) to NRC, "Nine-Month Response to NRCGeneral Letter 2008-001, Managing Gas Accumulation in Emergency CoreCooling, Decay Heat Removal, and Containment Spray Systems," datedOctober 14, 2008.

28.Letter from Chris J. Schwarz (ENO) to NRC, "Nine-Month Supplemental (PostOutage) Response to NRC Generic Letter 2008-01," dated July 20, 2009.

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMSRevision 30REFERENCES Page 6-1 of 6-2 1.Combustion Engineering Report, "Palisades Long-Term Cooling PerformanceEvaluation," P-CE-5627, May 8, 1981 2.Code of Federal Regulations - 10 CFR 50.46 and Appendix K 3.Oak Ridge National Lab Report, "Unit Operation Section Orderly ProgressReport," ORNL-3916, July-September 1965 4.Oak Ridge National Lab Report, "Gamma Radiation Damage andDecontamination Evaluation of Protective Coatings and Other Materials forHot Laboratory and Fuel Processing Facilities," ORNL-3589, February 19655.Deleted6.Deleted 7.Letter from Brian Holian (NRC) to GBSlade (CPCo), "Safety Evaluation of theSecond Ten-Year Interval Inservice Inspection Program Plan and AssociatedRequests for Relief for Palisades Nuclear Plant," dated September 3, 1991 8.Combustion Engineering Inc, Calc No P-PEC-170, Dated January 16, 1979,"Head Losses and Flow Requirements for Hot Leg Injection Line for Palisades"9.Deleted 10.Letter from Kenneth W. Berry (CPCo) to NRC, "Response to GenericLetter 88-17, Loss of Decay Heat Removal (60 day Response)", January 3 , 1989 11.Letter from Kenneth W. Berry (CPCo) to NRC, "Response to GenericLetter 88-17, Loss of Decay Heat Removal (90 day Response)",January 31, 1989 12.Letter from NRC to RCYoungdahl (CPCo) concerning boron precipitationpost-LOCA, March 14, 197513.Deleted 14.Generic Letter 90-05, "Guidance for Performing Temporary Non-Code Repairof ASME Code Class 1, 2, and 3 Piping," June 15, 1990 15.NRR Memorandum, "Follow-up on Generic Letter 90-05 Regarding Guidancefor Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3Piping," August 16, 1990 16.Condition Report C-PAL-95-0014, "HPSI Pumps - Design Basis ThermalTransient" FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMSRevision 30REFERENCES Page 6-2 of 6-2 17.Engineering Analysis EA-A-PAL-95-008, "Determination of MaximumAllowable Pressure for CSS piping (A-PAL-95-008)" 18.Engineering Analysis EA-FC-951-08, "Containment Air Cooler PerformanceCodes for the Replacement Air Coolers (Aerofin Coils)" 19.Letter from Dennis M Crutchfield (NRC) to David P Hoffman (CPCo), "SEPTopic III-4.C, Internally Generated Missiles," September 21, 1981 20.Letter from NRC to TCBordine (CE), "Palisades Plant - Issuance ofAmendment Re: Shutdown Cooling Technical Specification Change," datedOctober 10, 199621.Deleted22.Deleted 23.Letter from David H. Jaffe (NRC) to Daniel J. Malone (NMC), SafetyEvaluation by the Office of Nuclear Reactor Regulation Related toAmendment No. 221 to Facility Operating License No. DPR-20, datedJanuary 11, 2005 24.Engineering Analysis EA-CAP037584-01, Revision 0, Containment AirCooler Internal Flooding Response to a LOCA and a MSLB25.NRC Generic Letter 2004-02, Potential Impact of Debris Blockage onEmergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, September 13, 2004.

26.NRC Generic Letter (GL) 2008-01, "Managing Gas Accumulation inEmergency Core Cooling, Decay Heat Removal, and Containment SpraySystems," January 11, 2008.

27.Letter from Chris J. Schwarz (ENO) to NRC, "Nine-Month Response to NRCGeneral Letter 2008-001, Managing Gas Accumulation in Emergency CoreCooling, Decay Heat Removal, and Containment Spray Systems," datedOctober 14, 2008.

28.Letter from Chris J. Schwarz (ENO) to NRC, "Nine-Month Supplemental (PostOutage) Response to NRC Generic Letter 2008-01," dated July 20, 2009.