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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23107A0262023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Reactor ML23107A0552023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Tables ML23107A0202023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 12, Figures ML23107A0502023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Site and Environment ML23107A0542023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 1, References ML23107A0462023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 7, Appendices ML23107A0402023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 1, Figures ML23107A0592023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 1, Tables ML23107A0472023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operations ML23107A0572023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 10, Figures ML23107A0352023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 8, References ML23107A0342023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 9, References ML23107A0382023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML23107A0302023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 11, Tables ML23107A0132023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Design of Structures, Systems, and Components ML23107A0452023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 11, References ML23107A0312023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations ML23107A0422023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 9, Tables ML23107A0562023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 4, Primary Coolant System ML23107A0192023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 10, Tables ML23107A0232023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Figures ML23107A0152023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safeguards Systems ML23107A0122023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Figures ML23107A0292023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 8, Figures ML23107A0162023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Tables ML23107A0272023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML23107A0252023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management and Radiation Protection ML23107A0612023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 1, Introduction & General Description of Plant ML23107A0282023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, List of Effective Pages ML23107A0242023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 15, Figures ML23107A0392023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 15, Quality Assurance Program ML23107A0482023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, References ML23107A0172023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 8, Tables ML23107A0492023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 7, References ML23107A0322023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 4, Tables ML23107A0332023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Table of Contents ML23107A0582023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Figures ML23107A0182023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 7, Figures PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23107A0142023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 14, Figures ML23107A0412023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 11, Figures ML23107A0522023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Tables ML23107A0532023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis ML23107A0432023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, References ML23107A0602023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML23107A0362023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Figures ML23107A0372023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 14, Tables ML23107A0512023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Tables ML23107A0212023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML23107A0222023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 9, Figures 2023-03-31
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FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 REFERENCES Page 7-1 of 7-2
- 1.
Consumers Power Company, "Palisades Plant Reactor Protection System Common Mode Failure Analysis," Docket 50-255, License DPR-20, March 1975.
- 2.
Consumers Power Company, Response to NUREG-0737, December 19, 1980 (Item II.E.4.2 - Special Test of April 15, 1980).
- 3.
Gwinn, D V, and Trenholme, W M, "A Log-N Period Amplifier Utilizing Statical Fluctuation Signals From a Neutron Detector," IEEE Trans Nucl Science, NS-10(2), 1-9, April 1963.
- 4.
Failure Mode and Effect Analysis: Auxiliary Feedwater System, Bechtel Job 12447-039, dated January 14, 1980, Letter 80-12447/039-10, File 0275, dated March 25, 1980 to Consumers Power Company's B Harshe (Consumers Power Company FC 468-3 File).
- 5.
Johnson, B D, Consumers Power Company, to Director Nuclear Reactor Regulation, Attention Mr Dennis M Crutchfield, "Seismic Qualification of Auxiliary Feedwater System," August 19, 1981.
- 6.
VandeWalle, David J, Director, Nuclear Licensing, CP Co, to Director, Nuclear Reactor Regulation, USNRC, "Supplement 1 to NUREG-0737, Safety Parameter Display System, Revised Preliminary Safety Analysis Report," August 21, 1985.
- 7.
Berry, Kenneth W, Director, Nuclear Licensing, CP Co, to Director, Nuclear Reactor Regulation, USNRC, "Response to Request for Additional Information, Safety Parameter Display System," May 19, 1986.
- 8.
Thadani, Ashok C, Director, Nuclear Regulatory Commission, to Kenneth W Berry, Director, Nuclear Licensing, CP Co, "NUREG-0737, Item II.F.2, Inadequate Core Cooling Instrumentation," January 12, 1987.
- 9.
DeAgazio, Albert W, Sr Project Manager, Project Directorate III-1, USNRC, to Kenneth W Berry, Nuclear Licensing, CP Co, "Thermal Margin Monitor (TMM)
Audit Follow-Up (TAC No 72065)," March 28, 1990.
- 10.
Bordine, Thomas C, Plant Licensing Administrator, CP Co to Nuclear Regulatory Commission, "Additional Information Related to Station Blackout Rule 10 CFR 50.63 (TAC No 68578)," March 27, 1990.
- 11.
Berry, Kenneth W, Director, Nuclear Licensing, to USNRC, "Response to Generic Letter 89 Safety Parameter Display System (TAC No 73597)," July 10, 1989.
- 12.
DeAgazio, Albert W, Sr Project Manager, Project Directorate III-1, USNRC, to Kenneth W Berry, Nuclear Licensing, CP Co, "Consumers Power Confirmation Related to Generic Letter 89-06 Safety Parameter Display System (TAC No 73597)," April 19, 1990.
FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 REFERENCES Page 7-2 of 7-2
- 13.
DeAgazio, Albert W, Project Manager, Project Directorate III-1, USNRC, to Kenneth W Berry, Nuclear Licensing, CP Co, "Amendment No 129 to Provisional Operating License No DPR-20: Core Cooling Instrumentation (TAC No 69224),"
September 15, 1989.
- 14.
Howard, B.S., CPCo Plant Risk Analysis-Palisades, to FJYanik, CPCo Palisades, "Palisades ATWS Project (GWO 6858, FC-685) Failure Modes and Effects Analysis," (BSH*90-01), September 10,1990.
- 15.
Advanced Nuclear Fuels, "Review and Analysis of SRP Chapter 15 Events for Palisades with a 15% Variable High Power Trip Reset, November 1990.
- 16.
Gamberoni, Marsha, Project Manager, Project Directorate III-1 USNRC to Kurt M. Haas, Plant Safety and Licensing Director, CPCo, "Palisades Conformance to Regulatory Guide 1.97 (TAC. No M91113)," June 21, 1995.
- 17.
Letter from JNHannon, Director Division of Reactor Projects, Office of the Nuclear Reactor Regulation, to KMHaas, Plant Safety and Licensing Director, Palisades Plant, "Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention for Light-Water Nuclear Power Reactor for Normal Operation (TAC No. M90650)".
- 18.
Letter from Darl S. Hood (NRC) to Douglas E. Cooper (NMC), Palisades Plant -
Issuance of Amendment to Change Technical Specification Maximum Allowable Value for Variable High Power Trip (TAC No. MB3326), dated April 10, 2002.
- 19.
10 CFR 50.44, Combustible Gas Control for Nuclear Power Reactors, effective October 16, 2003.
- 20.
EA-EC27959-01, "Palisades Pressure-Temperature Limit Curves and Upper-Shelf Energy Evaluation," February 2012.