Browse wiki

ASME Section XI +  and ASME Section X +

Boron +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Sulfur +, Calcium +  and Zinc +

BWRVIP-75-A +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-116 +, BWRVIP-86 +, BWRVIP-03 +, BWRVIP-18 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-26A +, BWRVIP-1 +, BWRVIP-01 +, BWRVIP-02 +, BWRVIP-26-A +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-18-A +, BWRVIP-49-A +, BWRVIP-86-A +, BWRVIP-02-A +  and BWRVIP-58-A +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 50.2 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50.71 +, 10 CFR 50 Appendix H +, 10 CFR 54.21 +, 10 CFR 50.48 Appendix R +, 10 CFR 50.58a +, 10 CFR 50.55a +, 10 CFR 50.49#e +, 10 CFR 50.49#f +, 10 CFR 54.21#c1 +, 10 CFR 54.21#ci +, 10 CFR 54.21#cii +  and 10 CFR 54.21#ciii +

ASME Code Case N-578-1 +, ASME Code Case N-730 +, ASME Code Case N-481 +  and ASME Code Case N-606-1 +

S.1(n) +, P.4(a) +, S.5(a) +, H.0(s) +, S.8(o) +, S.7(y) +, S.8(n) +  and H.9(e) +

05000220  +, 05000244  +, 00220  +  and 00244  +

IR 05000455/2011011 +, IR 05000244/2009007 +, ML003717179 +, ML110490077 +, ML12277A090 +, ML11293A039 +, ML12041A161 +  and ML080570419 +

Constellation +  and Perkins E +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +

ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +, ML12326A467 +  and ML12326A467 +

IR 05000455/2011011 +  and IR 05000244/2009009 +

LR-ISG-2009-01 +  and LR-ISG-2006-01 +

General Electric +  and Westinghouse +

NEI 97-06, Steam Generator Conditioning Monitoring Report +, NEI 09-14, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000168, Guideline for the Management of Underground Piping and Tank Integrity, NEI 09-14 (Rev.1) (December 2010) (NEI 09-14 Rev. 1) +, NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

NFPA 805 +, NFPA 25 +  and NFPA 20 +

NRC Bulletin 80-11 +  and NRC Bulletin 88-09 +

Information Notice 87-67 +, Information Notice 97-11 +, Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues +, Information Notice 2010-14, Containment Concrete Surface Condition Examination Frequency and Acceptance Criteria +, Information Notice 2009-26, Spent Fuel Pool Neutron Absorbing Materials Degradation +, Information Notice 2009-20, Degradation of Wire Rope Used in Fuel Handling Applications +, Information Notice 2009-04, Age-Related Constant Support Degradation +, Information Notice 99-10 +, Information Notice 2010-12, Containment Liner Corrosion +, Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors +  and Information Notice 98-26 +

NUREG/CR-6260 +, NUREG-1786, Safety Evaluation Report, Related to License Renewal of R.E. Ginna Nuclear Power Plant +, NUREG-1900 +, NUREG-1611 +, NUREG/CR-6927 +, NUREG/CR-7027 +, NUREG-1950, Official Exhibit - ENT000528-00-BD01 - NUREG-1950, Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 (Apr. 2011) (Excerpted) +, NUREG/CR-6992 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1933, Containing the Atom, Nuclear Regulation in a Changing Environment, 1962-1971 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0819, Ack Receipt of 850920 Request for Exemption from Postulating Pipe Breaks in Primary Coolant Loop Piping,Per Generic Ltr 84-04, Safety Evaluation of Pipe Breaks in PWR Primary Main Loops. Request Obviated by Issuance of GDC 4 on 860411 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

Joseph Pacher +, Allen Hiser +, Seung Min +, Greg Oberson +, Bennett Brady +, Ganesh Cheruvenki +, Amy Hull +  and Bruce Lin +

AM +, FPP +, ISP +  and IMP +

Regulatory Guide 1.189 +, Regulatory Guide 1.163 +, Regulatory Guide 1.137 +, Regulatory Guide 1.205 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.190 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +, Regulatory Guide 1.133 +, Regulatory Guide 1.35 +, Regulatory Guide 1.35.1 +  and Regulatory Guide 1.245 +

RIS 2008-30, Fatigue Analysis of Nuclear Power Plant Components +  and RIS 2011-07, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000310, NRC Regulatory Issue Summary 2011-07 License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management +

T4MP-2 +, T4we-Ginna +, 8rain-The +, N4MP-1 +  and 4i4-4 +

Nine Mile Point +  and Ginna +

Nine Mile Point +  and Ginna +

Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Circulating Water System +, Control Rod +, Main Steam +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Coatings +, VT-2 +, High Energy Line Break +, Aging Management +, Foreign Material Exclusion +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Subsequent License Renewal +, Earthquake +, Biofouling +, EVT-1 +, Through-Wall Leak +, Through-Wall Leakage +, Preliminary White Finding +, Fire Protection Program +, Dissimilar Metal Weld +, Power Uprate +, Thermography +...

WCAP-17036-NP +  and WCAP-15837-NP +

WCAP-17036-NP +  and WCAP-15837-NP +