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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 8 - ELECTRICAL SYSTEMS Revision 34 REFERENCES Page 8-1 of 8-2
- 1.
Crutchfield, Dennis M, Chief, Operating Reactors Branch 5, Division of Licensing, USNRC, to David P Hoffman, Nuclear Licensing Administrator, CP Co, "Environmental Qualification of Electrical Equipment,"
August 29, 1980.
- 2.
Darrell G Eisenhut, Director, Division of Licensing, USNRC, to David P Hoffman, Nuclear Licensing Administrator, CP Co, "Environmental Qualification of Electrical Equipment," September 19, 1980.
- 3.
"Environmental Qualification of Safety-Related Electrical Equipment -
Palisades Plant - September 1980," October 7, 1980.
- 4.
David P Hoffman, Nuclear Licensing Administrator, CP Co, to Dennis M Crutchfield, Chief, Operating Reactors Branch 5, USNRC, "Revision 1 to October 7, 1980 Environmental Qualification of Electrical Equipment," October 30, 1980.
- 5.
David P Hoffman, Nuclear Licensing Administrator, CP Co, to Dennis M Crutchfield, Chief, Operating Reactors Branch 5, USNRC, "Revision 2 to October 7, 1980 Environmental Qualification of Electrical Equipment," June 11, 1981.
- 6.
David P Hoffman, Nuclear Licensing Administrator, CP Co, to Dennis M Crutchfield, Chief, Operating Reactors Branch 5, USNRC, "Environmental Qualification of Safety-Related Electrical Equipment -
December 1981 (complete revision)," December 4, 1981.
- 7.
Dennis M Crutchfield, Chief, Operating Reactors Branch 5, USNRC, to David J VandeWalle, Nuclear Licensing Administrator, CP Co, "Safety Evaluation for Environmental Qualification of Safety-Related Electrical Equipment," April 25, 1983.
- 8.
Kerry A Toner, Senior Licensing Engineer, CP Co, to Dennis M Crutchfield, Chief, Operating Reactors Branch 5, USNRC, "Environment Qualification of Safety-Related Electrical Equipment - Response to SER Open Items and 10 CFR 50.49 Rulemaking," May 20, 1983.
- 9.
Brian D Johnson, Staff Licensing Engineer, CPCo, to Dennis M Crutchfield, Chief, Operating Reactors Branch 5, USNRC, "Environmental Qualification of Safety-Related Electrical Equipment Additional Information," February 14, 1984.
- 10.
Thomas C Bordine, 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.
EA-ELEC-LDTAB-009, "Battery Sizing for the Palisades Class 1E Station Batteries ED-01 & ED-02".
FSAR CHAPTER 8 - ELECTRICAL SYSTEMS Revision 34 REFERENCES Page 8-2 of 8-2
- 12.
Ampacity of Cables in Single Open-Top Cable Trays, B L Harshe and W Z Black, IEEE Paper 94 WM 100-8 PWRD.
- 13.
Thomas C Bordine, Licensing Manager, Consumers Energy to Nuclear Regulatory Commission, Response to NRC Request for Additional Information Regarding Cable Ampacity Adjustment Methodology, July 10, 1997.
- 14.
Nathan L. Haskell, Director, Licensing, Consumers Energy to Nuclear Regulatory Commission, Response to Request for Additional Information Regarding Consumers Energy Companys Cable Ampacity Adjustment Methodology, June 25, 1998.
- 15.
Staff Evaluation Report by the Office of Nuclear Reactor Regulation Regarding Cable Ampacity Methodology, Consumers Energy Company, Palisades Plant, March 1, 2000.
- 16.
John A Zwolinski, Chief, Operating Reactors Branch 5, USNRC, to David J VandeWalle, Director, Nuclear Licensing, CPCo, "Environmental Qualification of Electrical Equipment Important to Safety, January 31, 1985.
- 17.
EA-ELEC-EDSA-03, LOCA with Offsite Power Available.
- 18.
Engineering Change (EC) 12118, "Diesel Generator Day Tank Duration Computation."
- 19.
Thomas V. Wambach, Project Manager, Operating Reactors Branch No. 5, USNRC to David J. VandeWalle, Nuclear Licensing Administrator, CPCo, "Integrated Plant Safety Assessment Report (IPSAR) Section 4.26, Electrical Penetrations of Reactor Containment - Palisades Plant", June 10, 1983.
- 20.
NUREG-0820 Supplement 1, "Integrated Plant Safety Assessment Systematic Evaluation Program, Palisades Plant", November 1983.
- 21.
Eric Duncan, Chief, Branch 3, Division of Reactor Projects, USNRCs, to Charles Arnone, Vice President, Entergy Nuclear Operations, Inc., "Palisades Nuclear Plant - NRC Integrated Inspection Report and Exercise of Enforcement Discretion 05000255/2017002", August 8, 2017.