ML23107A034
Text
DSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 36 REFERENCES Page 9-1 of 9-5
- 1.
Letter from D A Bixel (CP Co) to A Schwencer (NRC), dated February 8, 1977, spent fuel pool modifications, response to Question S6, (2510/0390).
- 2.
Deleted
- 3.
Johnson, B D, CP Co, to Director, Nuclear Reactor Regulation, Attention Mr Dennis M Crutchfield, "Seismic Qualification of Auxiliary Feedwater System," August 19, 1981.
- 4.
Mr Thomas V Wambach (NRC) to K W Berry (CP Co), letter dated July 24, 1987.
- 5.
Facility change, FC-680, Spent Fuel Pool Rerack, (Cartridges 9576 through 9579).
- a.
Safety Analysis Report, "Spent Fuel Storage Modification," October 16, 1986, amended December 19, 1986.
- b.
Westinghouse, "Design Report of Region 2 Spent Fuel Storage Racks Palisades Plant," WNEP-8626, May 1, 1987, (9579/1589).
- 6.
Letter from K W Berry (CP Co) to NRC, dated January 29, 1990, "Response to Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment."
- 7.
Deleted
- 8.
Deleted
- 9.
Deleted.
- 10.
Engineering Analysis, EA-A-PAL-96-011, Calculation of Spent Fuel Pool Cooling System Design Heat Load, Rev. 2, April, 2000.
- 11.
Deleted
- 12.
Deleted
- 13.
CPCo Internal Correspondence, DTPerry to GBSzczypka, "Heat Exchanger (CCW) Flow Limits," dated November 2, 1988.
- 14.
EI Final Report, "Analysis of Palisades Component Cooling and Service Water Systems," Revision 1, dated October 25, 1988 (D045\\1075).
- 15.
EA-GCP-93-01, "Review of Current Spent Fuel Pool Criticality Analysis and Bounding Conditions," March 19, 1993, Cart/Frame F474/0631.
- 16.
Facility Change, FC-864, Dry Storage of Spent Fuel Nuclear Fuel."
DSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 36 REFERENCES Page 9-2 of 9-5
- 17.
EA-FC-864-026, "Track Alley Load Distribution System (LDS): Evaluation of Load, Load Combination and Acceptance Criteria, Revision 1.
- 18.
EA-FC-864-30, "FC-864 Heavy Loads," Revision 3.
- 19.
Certificate of Compliance (C of C) for Dry Fuel Storage Casks, No 1007 Revision 0, effective 5/7/93.
- 20.
Deleted
- 21.
Safety Analysis Report for the Ventilated Storage Cask System, prepared by Pacific Sierra Nuclear Associates and Sierra Nuclear Corporation, October 1991.
- 22.
Deleted
- 23.
Deleted
- 24.
Engineering Change EC 8368, Replace Existing Control Room HVAC Dampers with Bubble-Tight Dampers, dated June 2007.
- 25.
EA-A-PAL-93-043-01, NPSH Evaluation for Charging and Boric Acid Pumps, Rev 2, November 2003.
- 26.
Deleted
- 27.
Deleted
- 28.
Deleted
- 29.
Deleted
- 30.
Deleted
- 31.
NRC Correspondence from Robert G. Schaaf to Thomas C. Bordine, Docket No. 50-255, October 28, 1997.
- 32.
Deleted
- 33.
Deleted
- 34.
Deleted
- 35.
Deleted
- 36.
EA-JEG-97-01, Revision 0, "Operation of Charging Pumps P-55B & C Without CCW Flow to the Oil Coolers."
DSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 36 REFERENCES Page 9-3 of 9-5
- 37.
Letter from NRC to KMHaas, SER for "Change in Commitments to Perform Post-Accident Containment Hydrogen Concentration Analysis and Sump pH Analysis," dated March 27, 1995.
- 38.
Letter from R L Hauter (Consumers) to J F OLeary (NRC), Docket No 50-255, dated December 1, 1972 (2504/0226)
- 39.
Letter from R A Vincent (Consumers) to D M Crutchfield (NRC), Docket No 50-255 - License DPR Palisades Plant - Systematic Evaluation Program, dated March 31, 1982
- 40.
Deleted
- 41.
EAR-2000-0129, Replacement of Shield Cooling Pumps
- 42.
Deleted
- 43.
Design Basis Document, DBD-7.10, "NFPA 805 Fire Protection Program"
- 44.
Deleted
- 45.
EA-SFP-99-03, Revision 0, New Fuel Storage Fuel Pool and Fuel Handling Criticality Safety Analysis (4996/1664)
- 46.
Facility Change FC-976, Modify L-3 to Single Failure Proof and Increase Capacity from 100 Tons to 110 Tons
- 47.
EA-D-PAL-88-222B, Revision 0, Minimum Lake Level Calculation for P-5 Suction With Five Discharge Tubes Open (F043/1540)
- 48.
Engineering Analysis EA-MOD-2003-019-05, Evaluation of Heavy Loads for NUHOMS System, Revision 0
- 49.
Standardized NUHOMS Horizontal Modular Storage System Certificate of Compliance (C of C) Number 1004, Amendment No. 5
- 50.
Stang, John F., Senior Project Manager, Project Directorate III-1, USNRC, to Daniel J. Malone, Palisades Nuclear Plant Site President, Amendment No. 215 to the Palisades Operating Licensee No DPR-20: Palisades Spent Fuel Pool Crane Upgrade (TAC No. MC1862), June 16, 2004
- 51.
Deleted
- 52.
Deleted
- 53.
Deleted
- 54.
Deleted
DSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 36 REFERENCES Page 9-4 of 9-5
- 55.
Deleted
- 56.
Deleted
- 57.
Deleted
- 58.
Bechtel Specification 5395-M-73, Specification for the Reactor Crane, Revision 1, dated March 8, 1967
- 59.
Letter from Dresser Crane, Hoist & Tower Division to Bechtel Corporation dated September 9, 1970 (Cart./Frame G728/1146)
- 60.
Bechtel Inter-office Memo dated December 18, 1969 (Cart/Frame 0447/2123)
- 61.
Bechtel Field Procedure Number 3, Revision 6, Change #7, Load Test of Up-Rated Polar Crane, 2/22/1970 (Cart./Frame 0183/0181)
- 62.
NRC letter from Dennis M. Crutchfield to David J. VandeWalle, Control of Heavy Loads (Phase 1) - NUREG-0612, dated November 9, 1983
- 63.
Deleted
- 64.
Engineering Change EC516, CCW System Temperature Re-Rate Design Change, dated January 25, 2007.
- 65.
Deleted
- 66.
Deleted
- 67.
EA-WJB-00-01, Revision 2, Spent Fuel Pool Dilution Analysis, EC0044749.
- 68.
Deleted
- 69.
AREVA NP Inc., ANP-2858P-003, Palisades SFP Region 1 Criticality Evaluation with Burnup Credit, January 2011.
- 70.
EA-EEQ-TEMP-01, Revision 2, EEQ Average Arrhenius Temperature Outside Containment Building Based on Temperature Monitoring
- 71.
EA-BHS-EQ-2000-01, Revision 4, Results of Temperature Monitoring in Containment and Suggested Methods for Use of the Temperature Data in EQ Qualified Life Calculations
- 72.
EA-BDM-88-02, Revision 0, Impact on EEQ Files Due to Increase of Containment Operating Temperature from 138°F to 145°F
- 73.
EA-EC46993-01, Revision 0, E-53A/B Spent Fuel Pool Heat Exchanger Tube Plugging Calculation
DSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 36 REFERENCES Page 9-5 of 9-5
- 74.
Deleted
- 75.
EA-EC32159-05, Revision 0, Criticality Safety Evaluation for Region 1 Spent Fuel Racks at Palisades (HI-2115017)
- 76.
PLP-RPT-12-00053, "NFPA Code Conformance Review"
- 77.
Deleted
- 78.
EA-EC32159-01, Revision 0, "Bulk Thermal-Hydraulic Analyses for the Palisades SFP and Tilt Pit with New Region 1 Racks (HI-2114999)"
- 79.
Final Safety Analysis Report for the HI-STORM FW MPC Storage System, Holtec Report HI-2114830, Revision 4
- 80.
Certificate of Compliance No. 1032, Amendment 1, Revision 1, for HI-STORM FW MPC Storage System
- 81.
Deleted
- 82.
Certificate of Compliance for Dry Fuel Storage Casks, Certificate No. 1007 Revision 0 Renewal, effective September 20, 2017.
- 83.
Final Safety Analysis Report for the VSC-24 Ventilated Storage Cask System, prepared by Energy Solutions, Revision 9, October 2017.
- 84.
Deleted