APPENDIX D: REFERENCES
American Society of Mechanical Engineers (ASME)
ASME Boiler and Pressure Vessel Code Requirements and Code Cases
ASME Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components” (acceptable editions endorsed by 10 CFR 50.55a are those through the 1995 Edition, inclusive of the 1996 Addenda).
ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWB, Requirements for Class 1 Components of Light-Water Cooled Power Plants.
ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWC, Requirements for Class 2 Components of Light-Water Cooled Power Plants.
ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWD, Requirements for Class 3 Components of Light-Water Cooled Power Plants.
ASME Boiler and Pressure Vessel Code, Code Case N-481, Alternative Examination Requirements for Cast Austenitic Pump Casings, Section XI, Division1.
ASME Boiler and Pressure Vessel Code, Section III (2.3.1.1.1)
ASME Boiler and Pressure Vessel Code, Section VIII (4.3.1)
ASME Material Specification SA-193 (3.1.2.1)
ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWE (3.5.2.3.1)
ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWF (3.5.2.3..3)
ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWL (3.5.2.2.1.1)
Carolina Power and Light Company (CP&L)
Calculations
Calculation RNP-L/LR-0103, “License Renewal Screening—Structures and Structural Components.”
Calculation RNP-L/LR-0104, “License Renewal Screening—Containment Structure, Internal and External Structural Component.”
Calculation RNP-L/LR-0006, “Non Safety-Related Equipment Affecting Safety-Related Equipment—License Renewal System/Structure Scoping.”
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Calculation RNP-L/LR-0396, "Screening and Aging Management Review Criterion 2 Piping.”Calculation RNP-L/LR-0393, “Aging Management Review Seismic Piping (II over I and Seismic Continuity Piping).”
Calculation RNP-L/LR-0120, “Electrical Component Screening for License Renewal for H.B. Robinson Unit No. 2.”
Calculation RNP-L/LR-0121, “License Renewal Mechanical System Evaluation Boundaries for H.B. Robinson Unit No. 2,” Revision 3.
Calculation RNP-L/LR-0124, “License Renewal—Identification of Civil Commodity Types and Bulk Screening Criteria for H.B. Robinson Unit No. 2,” Revision 1.
Calculation RNP-L/LR-0391, “License Renewal Cables Located in the Containment (CV) for H.B. Robinson Unit No. 2,” Revision 0.
Calculation RNP-L/LR-0392, “Scoping of PVC Insulated Cables for License Renewal for H.B. Robinson Unit No. 2,” Revision 0.
Calculation RNP-L/LR-0394, “Environmental Qualification of Electrical Equipment Program Review for License Renewal for H.B. Robinson Unit No. 2,” Revision 0.
Calculation RNP-L/LR-0007, System/Structure Scoping Worksheet, Attachment 26, “Feedwater System.”
Calculation RNP-L/LR-0129, “System Screening—Auxiliary Feedwater System for H.B. Robinson Unit No. 2."
Calculation RNP-L/LR-0132, “System Screening—Component/Closed Cooling Water System,”Revision 2.
Calculation No. RNP-L/LR-0134, “System Screening—Feedwater System for H.B. Robinson Unit No. 2."
Design Basis Documents
Design Basis Document, R87038/SD13, “Component Cooling Water System,” Revision 6. Design Basis Document, DBD/R87038/SD27, “Feedwater System,” Revision 5.
Design Basis Document,  DBD R87038/SD32, “Auxiliary Feedwater System,” Revision 6. License Renewal System Flow Diagrams
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License Renewal System Flow Diagram, 8379-376LR, “Component Cooling Water System,”sheets 1 through 4.
reactor typesLicense Renewal System Flow Diagram, G-190197LR, “Feedwater System,” sheets 1, 3, and 4. License Renewal System Flow Diagram, G-190197LR, “Auxiliary Feedwater System,” sheet 4. Plant Procedures
Standard Procedure EGR-NGCC-0501, “Nuclear Plant License Renewal Program,” Revision 3. Standard Procedure EGR-NGCC-0502, “System/Structure Scoping for License Renewal,”Revision 3.
Standard Procedure EGR-NGCC-0503, “System/Structure Scoping for License Renewal,”Revision 3.
Standard Procedure EGR-NGCC-0505, “Electrical Component Screening and Aging Management Review for License Renewal,” Revision 3.
Standard Procedure EGR-NGCC-0506, “Civil/Structural Screening and Aging Management Review for License Renewal,” Revision 3.
Reports
RNP Updated Safety Analysis Report Supplement
"Aging and Life Extension of Major Light Water Reactor Components,” edited by V.N. Shaw and P.E. MacDonald, 1993, Elsevier Science Publishers.
Electric Power Research Institute (EPRI)
EPRI Tropical Report 105714, "PWR Primary Water Chemistry Guidelines,” versions through Revision 4, 1999.
EPRI TR-103834-P1-2, "Effects of Moisture on the Life of Power Plant Cables, Part 1: Medium-Voltage Cables, Part 2: Low-Voltage Cables,” prepared by Ogden Environmental and Energy Services Company, Final Report, August 1994.
EPRI NP-1558, “A Review of Equipment Aging Theory and Technology,” Electric Power Research Institute, September 1980.
EPRI  NSAC-202L, Revision 2, “Recommendations for an Effective Flow Accelerated Corrosion Program, December 1998. (3.0.3.5.2)
EPRI TR-107569-VI (3.0.3.3.2)
EPRI TR-102134 (3.0.3.3.3)
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EPRI TR-107621 (3.1.2.3.2.2)
EPRI TR-103842 (4.6.2.1)
Nuclear Energy Institute
NEI 95-10, “Industry Guideline for Implementing the Requirements of 10 CFR Part 54—The License Renewal Rule, Revision 2,” August 2000.
NEI 95-10, “Industry Guidelines for Implementing the Requirements of 10 CFR Part 54—The License Renewal Rule,” Revision 3, Nuclear Energy Institute, March 2001.
NEI 97-06, "Steam Generator Program Guidelines, ”Revision 1, January 2001.
Sandia National Laboratories
SAND96-0344, "Aging Management Guideline for Commercial Nuclear Power Plants -Electrical Cable and Terminations,” Sandia Contractor Report prepared by Ogden Environmental and Energy Services, Inc., September 1996.
U.S. Nuclear Regulatory Commission (NRC)
(Draft) Standard Review Plan for the Review of License Renewal Application for Nuclear Power Plants, August 2001. (1.1)
Bulletins
Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles,” August 3, 2001.
Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity,” March 18, 2002.
Bulletin 2002-2, "Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs,” August 9, 2002.
Bulletin 1988-11, (2.03.1.2)
Bulletin 1979 B, (4.4.1.2)
Bulletin 1988-08, (3.0.3.1.2)
Bulletin 1987-01, (3.0.3.5.2)
Bulletin 1982-02, (3.0.3.6.1)
Bulletin 1988-02, (3.1.2.2.11)
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Bulletin 1989-01, (3.1.2.2.112.03.1.2)
Bulletin 1988-09, (3.1.2.3.3.2)
Code of Federal Regulations
10 CFR 50.49, “Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.”
10 CFR 50.55a, "Codes and Standards”
10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.”
10 CFR Part 50, Appendix G, "Fracture Toughness Requirements.”
10 CFR Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements.”
10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants.”
10 CFR Part 51 (1.1)
10 CFR Part 140.92 (1.3)
10 CFR Part 100 (1.5)
Correspondence
NRC letter to Alan Nelson and David Lochbaum, “Staff Guidance on Scoping of Equipment Relied on to Meet The Requirements of the Station  Blackout (SBO) Rule (10 CFR 50.63) for License Renewal (10 CFR 54.4(a)(3),” April 1, 2002.
C.I. Grimes letter (NRC) to
D. Walters (NEI), “Guidance on Addressing GSI 168 for License Renewal,” Project No. 690, June 2, 1998.
C.I. Grimes (NRC) to
D. Walters (NEI), License Renewal Issue No. 98-0030, “Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components,” Project No. 690, May 2000. NRC letter to Alan Nelson and David Lochbaum, dated January 28, 2002 (Appendix A) Executive Orders
Order EA-03-009, "Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors,” February 11, 2003.
Generic Letters (GL)
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