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
Shared Package
ML21278A102	List: ML21257A249 ML21257A253 ML21257A254 ML21257A255 ML21257A256 ML21257A258 ML21257A259 ML21257A260 ML21257A261 ML21257A262 ML21257A263 ML21257A264 ML21257A265 ML21257A267 ML21257A268 ML21257A269 ML21257A278 ML21257A281 ML21257A282 ML21257A283 ML21257A284 ML21257A285 ML21257A286 ML21257A287 ML21257A288 ML21257A289 ML21257A298 ML21257A299 ML21257A300 ML21257A301 ML21257A302 ML21257A303 ML21257A304 ML21257A305 ML21257A306 ML21278A106 ML21278A107 ML21278A108 ML21278A109 ML21278A110 ML21278A111 ML21278A112 ML21278A113 ML21278A114 ML21278A115 ML21278A116 ML21278A117 ML21278A118 ML21278A122 ML21278A123 ... further results
References
NEI 99-04
Download: ML21278A302 (1)

Text

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 CALVERT CLIFFS UFSAR 16.5-1 Rev. 50