ML21278A302

2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.5, References

ML21278A302
Person / Time
Site:	Calvert Cliffs
Issue date:	09/07/2021
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
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References
NEI 99-04
Download: ML21278A302 (1)

Text

CALVERT CLIFFS UFSAR 16.5-1 Rev. 50

16.5 REFERENCES

1.

NUREG 1705, Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units 1 and 2, dated December 1999

2.

NUREG 1801, Revision 2, Generic Aging Lessons Learned (GALL) Report, December 2010

3.

NUREG 1801, Revision 1, Generic Aging Lessons Learned (GALL) Report, September 2005

4.

Electric Power Research Institute TR-107514, Age Related Degradation Inspection Method and Demonstration

5.

Regulatory Guide 1.35, Revision 1, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments, June 1974

6.

Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants, March 17, 1988

7.

Regulatory Issue Summary 2003-09, Environmental Qualification of Low-Voltage Instrumentation and Control Cables, May 1, 2003

8.

ASTM E185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels

9.

NRC Bulletin 79-01B, Environmental Qualification of Class IE Equipment, January 14, 1980

10. NUREG-0588, Revision 1, Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, July 1981

11. NUREG/CR-5704, Revision 0, Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels, April 1999

12. NUREG/CR 6583, Revision 0, Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, February 1998

13. NUREG/CR 6909, Draft Revision 1, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials - Draft Report for Comment, March 2014

14. Regulatory Guide 1.54, Revision 0, Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants, June 1973

15. ANSI N-101.4-1972, Quality Assurance for Protective Coatings Applied to Nuclear Facilities

16. Material Reliability Program-227A, Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines, December 23, 2011

17. Nuclear Energy Institute 03-08, Revision 2, Guideline for the Management of Materials Issues, January 2010