ML21125A320

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

ML21125A320
Person / Time
Site:	Palisades
Issue date:	04/14/2021
From:	Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
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References
PNP 2021-008
Download: ML21125A320 (2)

Text

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMS Revision 33 REFERENCES Page 6-1 of 6-2

1.

Combustion Engineering Report, "Palisades Long-Term Cooling Performance Evaluation," 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 Progress Report," ORNL-3916, July-September 1965

4.

Oak Ridge National Lab Report, "Gamma Radiation Damage and Decontamination Evaluation of Protective Coatings and Other Materials for Hot Laboratory and Fuel Processing Facilities," ORNL-3589, February 1965

5.

Deleted

6.

Deleted

7.

Letter from Brian Holian (NRC) to GBSlade (CPCo), "Safety Evaluation of the Second Ten-Year Interval Inservice Inspection Program Plan and Associated Requests 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 Generic Letter 88-17, Loss of Decay Heat Removal (60 day Response)",

January 3, 1989

11.

Letter from Kenneth W. Berry (CPCo) to NRC, "Response to Generic Letter 88-17, Loss of Decay Heat Removal (90 day Response)",

January 31, 1989

12.

Letter from NRC to RCYoungdahl (CPCo) concerning boron precipitation post-LOCA, March 14, 1975

13.

Deleted

14.

Generic Letter 90-05, "Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping," June 15, 1990

15.

NRR Memorandum, "Follow-up on Generic Letter 90-05 Regarding Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping," August 16, 1990

16.

Condition Report C-PAL-95-0014, "HPSI Pumps - Design Basis Thermal Transient"

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMS Revision 33 REFERENCES Page 6-2 of 6-2

17.

Engineering Analysis EA-A-PAL-95-008, "Determination of Maximum Allowable Pressure for CSS piping (A-PAL-95-008)"

18.

Engineering Analysis EA-FC-951-08, "Containment Air Cooler Performance Codes for the Replacement Air Coolers (Aerofin Coils)"

19.

Letter from Dennis M Crutchfield (NRC) to David P Hoffman (CPCo), "SEP Topic III-4.C, Internally Generated Missiles," September 21, 1981

20.

Letter from NRC to TCBordine (CE), "Palisades Plant - Issuance of Amendment Re: Shutdown Cooling Technical Specification Change," dated October 10, 1996

21.

Deleted

22.

Deleted

23.

Letter from David H. Jaffe (NRC) to Daniel J. Malone (NMC), Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 221 to Facility Operating License No. DPR-20, dated January 11, 2005

24.

Engineering Analysis EA-CAP037584-01, Revision 0, Containment Air Cooler Internal Flooding Response to a LOCA and a MSLB

25.

NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, September 13, 2004.

26.

NRC Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," January 11, 2008.

27.

Letter from Chris J. Schwarz (ENO) to NRC, "Nine-Month Response to NRC General Letter 2008-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," dated October 14, 2008.

28.

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

29.

Engineering Change EC 63832, "Add an Air Accumulator to CV-0910 and Appendix J Program Update."