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SER-Appendix D: References
	ML032370502
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Site:	Robinson
Issue date:	08/25/2003
From:	Kuo P; Office of Nuclear Reactor Regulation
To:	Moyer J; Carolina Power & Light Co
	Mitra, SK, NRR/DRIP/RLEP, 415-2783
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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, Division 1.

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 ScreeningStructures and Structural Components.

Calculation RNP-L/LR-0104, License Renewal ScreeningContainment Structure, Internal and External Structural Component.

Calculation RNP-L/LR-0006, Non Safety-Related Equipment Affecting Safety-Related EquipmentLicense Renewal System/Structure Scoping.

D-1

Calculation RNP-L/LR-0007, System/Structure Scoping for License Renewal.

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 RenewalIdentification 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 ScreeningAuxiliary Feedwater System for H.B.

Robinson Unit No. 2."

Calculation RNP-L/LR-0132, System ScreeningComponent/Closed Cooling Water System, Revision 2.

Calculation No. RNP-L/LR-0134, System ScreeningFeedwater System for H.B. Robinson Unit No. 2."

Calculation No. RNPL/RA 006(1.6)

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 D-2

License Renewal System Flow Diagram, 8379-376LR, Component Cooling Water System, sheets 1 through 4.

License 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-l2 (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 54The License Renewal Rule, Revision 3, August 2001 NEI 95-10, Industry Guidelines for Implementing the Requirements of 10 CFR Part 54The 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 Reveiw of License Renewal Application for Nuclear Power Plants, August 2001. (1.1)

BulletinsBulletin 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)

D-5

GL 97-01, "Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations, April 1, 2002.

GL 97-05, "Steam Generator Tube Inspection Techniques, December 17, 2002.

GL 96-04 (4.6.4.1)

GL 88-05 (3.0.3.4.2)

GL 89-08 (3.0.3.5.1)

GL 89-13 (3.0.3.7.1)

GL 92-01 (3.1.2.3.4.3)

Guidelines DOR Guidelines, Guidelines for Evaluating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors, U.S. Nuclear Regulatory Commission, June 1979.

Information Notices (IN)

IN 89-33, "Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs, March 23, 1989.

IN 89-65, "Potential for Stress Corrosion Cracking in Steam Generator Tube Plugs Supplied by Babcock and Wilcox, September 8, 1989.

IN 90-04, "Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, January 26, 1990.

IN 91-19, "Steam Generator Feedwater Distribution Piping Damage, March 12, 1991.

IN 94-87, "Unanticipated Crack in a Particular Heat of Alloy 600 Used for Westinghouse Mechanical Plugs for Steam Generator Tubes, December 22, 1994.

IN 2000-17, "NRC Information Notice 2000-17: Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. Summer, October 18, 2000.

IN 2000-17, Supplement 1, NRC Information Notice 2000-17: Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. Summer, November 16, 2000.

IN 2000-17, Supplement 2, "NRC Information Notice 2000-17: Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. Summer, February 28, 2001.

IN 1980-38 (3.2.2.4.4.2)

IN 1986-108 (3.0.3.4.2)

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IN 1987-28 (3.3.2.4.5.2)

IN 1987-43 (4.6.4.1)

IN 1993-70 (4.6.4.1)

IN 1995-38 (4.6.4.1)

IN 1997-46 (3.0.3.92)

IN 1999-10 (4.5.2)

NUREG Reports NUREG-0588, Interim Staff Position on Environmental Qualification of Safety-Related Equipment, U.S. Nuclear Regulatory Commission, July 1981.

NUREG/CR-5576," Survey of Boric Acid Corrosion of Carbon Steel Components in Nuclear Plants, June 1990.

NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, April 2001 NUREG/CR-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, July 2001.

NUREG-1801, Generic Aging Lessons Learned Report (GALL), April 2001.

NUREG/CR-1801, "Generic Aging Lessons Learned (GALL) Report, July 2001.

NUREG/CR-1739, Analysis of Public Comments on the Improved License Renewal Guidance Documents, July 2001.

NUREG/CR-1437, Supplement 13, Draft Generic Environmental Impact Statement for License Renewal of Nuclear Power Plants Regarding the H.B. Robison Steam Electric Plant, Unit 2, May 2003.

NUREG/CR-1437, Generic Environmental Impact Statement (GEIS) for License Renewal of Nuclear Plants.

NUREG/CR-0313, Revision 2 (3.1.2.2.7)

NUREG/CR-0612 (3.3.2.3.1.1)

NUREG/CR-1004 (3.1.2.2.12)

NUREG/CR-1437, (1.1)

D-7

NUREG/CR-1522 (3.5.2.3.1.1)

NUREG/CR-1557 (3.5.2.4.1.2)

NUREG/CR-1739 (1.2.1)

NUREG/CR-5704 (3.0.3.1.2)

NUREG/CR-6260 (3.03.1.2)

NUREG/CR-6583 (3.0.3.1.2)

Regulatory Guides (RG)

RG 1.65, "Materials and Inspections for Reactor Vessel Closure Studs, October 1973.

RG 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, July 2001.

RG 1.89, Revision 1, Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants.

RG 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials, May 1988.

RG 1.155 (2.5.4.2)

RG 1.188 (1.2.1)

Westinghouse Topical Reports (Proprietary Reports are printed in bolded print)

Westinghouse Proprietary Class 2 Report No. WCAP-15628, "Technical Justification for Eliminating Large Primary Loop Rupture as the Structural Design Basis for the H.B.

Robinson Unit 2 Nuclear Plant for the License Renewal Program, April 2003.

Westinghouse Non-Proprietary Class 3 Report No. WCAP-15628-NP, Revision 0, "Technical Justification for Eliminating Large Primary Loop Rupture as the Structural Design Basis for the H.B. Robinson Unit 2 Nuclear Plant for the License Renewal Program,April 2003.

Westinghouse Proprietary Class 2 Report No. WCAP-15363, Revision 1, "A Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings of H. B. Robins Unit 2 for License Renewal, April 2003.

Westinghouse Non-Proprietary Class 3 Report No. WCAP-15363 Revision 1-NP, "A Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings of H.B. Robinson Unit 2 for License Renewal, April 2003.

Westinghouse Non-Proprietary Class 3 Report No. WCAP-14574-A, "License Renewal Application: Aging Management Evaluation for Pressurizers, December 2000.

D-8

Westinghouse Non-Proprietary Class 3 Report No. WCAP-15805, "Analysis of Capsule X from the Carolina Power and Light Company H.B. Robinson Unit 2 Reactor Vessel Irradiation Surveillance Program, March 2002.

Westinghouse Non-Proprietary Class 3 Report No. WCAP-15828, "Evaluation of Pressurized Thermal Shock for H.B. Robinson Unit 2, March 2003.

Westinghouse, WCAP-10322, Revision 1 (4.3.1)

Westinghouse, WCAP-12962, (1.3.1)

Westinghouse, WCAP-13045, (4.6.1.1)

Westinghouse, WCAP-13587, (1.3.1)

Westinghouse, WCAP-14209, (1.3.1)

Westinghouse, WCAP-14575A, (3.1.2.2.4)

Westinghouse, WCAP-15338, (1.3.1)

Westinghouse, WCAP-15363, (4.6.1.1)

Miscellaneous CAP-NGGC-0200, Corrective Action Program, Revision 5.

NGGM-PM-0007, Quality Assurance Program Manual, Revision 6.

AP-022, Procedure Review and Approval Process, Revision 36.