ML23107A034

6 to Updated Final Safety Analysis Report, Chapter 9, References

ML23107A034
Person / Time
Site:	Palisades
Issue date:	03/31/2023
From:	Holtec Decommissioning International
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
HDI PNP 2023-002
Download: ML23107A034 (5)

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."

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10. Engineering Analysis, EA-A-PAL-96-011, Calculation of Spent Fuel Pool Cooling System Design Heat Load, Rev. 2, April, 2000.

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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.

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21. Safety Analysis Report for the Ventilated Storage Cask System, prepared by Pacific Sierra Nuclear Associates and Sierra Nuclear Corporation, October 1991.

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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.

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31. NRC Correspondence from Robert G. Schaaf to Thomas C. Bordine, Docket No. 50-255, October 28, 1997.

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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

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41. EAR-2000-0129, Replacement of Shield Cooling Pumps

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43. Design Basis Document, DBD-7.10, "NFPA 805 Fire Protection Program"

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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

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DSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 36 REFERENCES Page 9-4 of 9-5

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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

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64. Engineering Change EC516, CCW System Temperature Re-Rate Design Change, dated January 25, 2007.

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67. EA-WJB-00-01, Revision 2, Spent Fuel Pool Dilution Analysis, EC0044749.

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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

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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"

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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

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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