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ML12334A679 +
BWRVIP-190 +, BWRVIP-74 +, BWRVIP-05 +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-18-A +, BWRVIP-49-A + and BWRVIP-74-A +
10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 2 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 2.101 +, 10 CFR 50.4 +, 10 CFR 50.12 +, 10 CFR 50.30 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50.71 +, 10 CFR 50.90 +, 10 CFR 50.109 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.19 +, 10 CFR 54.21 +, 10 CFR 54.22, Contents of Application--Technical Specifications +...
SECY-95-245 +, SECY 99-148 +, SECY-93-049 +, SECY-94-191 +, SECY 94-225 +, L-03 +, L-02 +, L-01 +, L-04 + and L-05 +
ML042790085 + and ML041190564 +
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 80-95, Generic Activity A-10 +, 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 +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds + and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML12334A679 +, ML12334A679 +, ML12334A679 +, ML12334A679 +, ML12334A679 +, ML12334A679 +, ML12334A679 +, ML12334A679 + and ML12334A679 +
IEEE 323-1974 + and IEEE 323-1971 +
December 31, 2010 +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
00:31:29, 12 November 2019 +
NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +, NEI 97-06, Steam Generator Conditioning Monitoring Report + and 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 +
Information Notice 87-67 +, Information Notice 97-46 +, Information Notice 94-63 +, Information Notice 90-04 +, Information Notice 90-10 +, Information Notice 96-11 +, Information Notice 99-10 +, Information Notice 93-61 +, Information Notice 90-30 +, Information Notice 91-19 + and Information Notice 2001-09, Main Feedwater System Degradation in Safety-Related ASME Code Class 2 Piping Inside the Containment of a Pressurized Water Reactor +
NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG-1723 +, NUREG/CR-6674 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1211, Informs of CRGR Meeting 98 Agenda Mod +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +, NUREG-1555, Supplement 1, Revision 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants Supplement 1: Operating License Renewal Final Report +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +, 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 +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated + and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
377 +
Approval +
Regulatory Guide 1.155 +, Regulatory Guide 1.121 +, 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 1.29 +, Regulatory Guide 1.188 +, Regulatory Guide 1.13 +, Regulatory Guide 1.89 +, Regulatory Guide 1.35 +, Regulatory Guide 1.154 +, Regulatory Guide 1.35.1 + and Regulatory Guide 1.207 +
December 31, 2010 +
Washington + and New York +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Shield Building +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +, Main Steam +, Containment Spray + and Extraction steam +
Official Exhibit - NYS000161-00-BD01 - NUREG-1800, Rev. 2, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants +
Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Fire Barrier +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Coatings +, Nondestructive Examination +, VT-2 +, Emergency Lighting +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Integrated leak rate test +, Eddy Current Testing +, Severe Accident Management Guideline +, Moisture barrier +, License Renewal +, Earthquake +, Biofouling +, Dissimilar Metal Weld +, Backfit +, Power Uprate +, Thermography +, Water rod +, Control Room Habitability +...
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