ML103190479
| ML103190479 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/15/2010 |
| From: | Subin L NRC/OGC |
| To: | |
| Subin, Lloyd B., 415-1988 | |
| References | |
| 50-275-LR, 50-323-LR | |
| Download: ML103190479 (2) | |
Text
Staffs Generic and Standard Guidance Documents Used by the Staff in its Review of the Diablo Canyon License Renewal Application Title Acces s ion No.
Generic Letter 88 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping ML031430193 Generic Letter 89 Safety-Related Motor-Operated Valve Testing and Surveillance ML031150300 Generic Letter 89 Service Water System Problems Affecting Safety-Related Equipment ML031150348 Generic Letter 98 Protection for Degradation of the Emergency Core Cooling System and the Containment Spray System after a Loss-of-Coolant-Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment ML031110081 Generic Letter 98 BWR Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential shell welds ML082460066 Information Notice 92 Inadequate Local Leak Rate Testing ML031200473 Information Notice 94 Boric Acid Corrosion of Charging Pump Casing Caused by Cladding Cracks ML031060393 Information Notice 2006 Torus Cracking in a BWR Mark I Containment ML053060311 NUREG-0313, Revision 2 - Technical Report on Material Selection and processing Guidelines for BWR Coolant Pressure Boundary Piping ML031470422 NUREG-0619, Revision 1 - BWR Feedwater Nozzle and Control Rod Driven Return Line Nozzle Cracking ML031600712 NUREG-1339 - Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants ML031430208 NUREG-1437 - Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GEIS) Volume 1 and Volume 2. Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Main Report Section 6.3 Transportation Table 9.1 Summary of Findings on NEPA Issues for License Renewal of Nuclear Power Plants, Final Report, Volume 1, Addendum 1 ML040690705 ML040690738 ML040690720 NUREG-1555 - Standard Review Plans for Environmental Reviews for Nuclear Power Plants: Environmental Standard Review Plan for Operating License Renewal October 1999. Volume 1. Volume 2. Supplement 1.
ML003702134 ML003701937 ML003702019 NUREG-1800, Revision 1 - Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants ML052110007 NUREG-1801, Revision 1 - Generic Aging Lessons Learned (GALL) Report Volume
- 1. Volume 2.
ML052110005 ML052780376 NUREG-1833 - Technical Bases for Revision to the License Renewal Guidance Documents ML052110003 NUREG/CR-4513, Revision 1 - Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems ML052360554 NUREG/CR-5704 - Effects of LRW Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels ML031480394 NUREG/CR-6260 - Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components ML031480219 NUREG/CR-6583 - Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels ML031480391 NUREG/CR-6909 - Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials ML070180623
Staffs Generic and Standard Guidance Documents Used by the Staff in its Review of the Diablo Canyon License Renewal Application Title Acces s ion No.
Generic Letter 88 Individual Plant Examination for Severe Accident Vulnerabilities ML031150465 Generic Letter 88-20, Supplement 4 - Individual Plant Examination of External Events for Severe Accident Vulnerabilities ML031150485 NUREG-0586 - Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities: Regarding the Decommissioning of Nuclear Power Reactors, Supplement 1, Volume 1: Main Report, Appendices A through M and Supplement 1, Volume 2: Appendices N, O and P ML023500412 ML023500228 NUREG-0800, 1975. Standard Review Plan for the Review of Safety Analysis Report for Nuclear Power Plants NUREG-1150 - Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants. Volume 1. Volume 2. Volume 3.
ML100780066 ML100780067 ML100780063 NUREG/BR-0184 - Regulatory Analysis Technical Evaluation Handbook..
ML050190193 Non-Publicly Available. NUREG-1560 - Individual Plant Examination Program:
Perspectives on Reactor Safety and Plant Performance. Volume 1. Volume 2, Parts 2-5. Volume 3, Part 6.
ML063550244 ML063550228 ML063470259 Non-Publicly Available. NUREG/CR-6613 - Code Manual for MACCS2: Volume 1, Users Guide. Volume 1. Volume 2.
ML063550020 ML063550023 NUREG/CR-6525, Revision 1 - SECPOP2000: Sector Population, Land Fraction, and Economic Estimation Program ML032310279 NUREG/BR-0058, Revision 4 - Regulatory Analysis Guidelines of the USNRC ML042820192 NUREG/CR-6595, Revision 1 - An Approach for Estimating the Frequencies of Various containment Failure modes and Bypass Events. Revision 1, ML032330225 Regulatory Guide 1.200, Revision 1 - An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities ML063170035 Regulatory Guide 1.200, Revision 2 - An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities.
ML090410014 Regulatory Guide 4.2S1 - Supplement 1 to Regulatory Guide 4.2 Preparation of Supplemental Environmental Reports for Applications to Renew Nuclear Power Plant operating Licenses ML003710495 Non-Publicly Available. NRR Office Instruction, LIC-203, Revision 2 - Procedural Guidance for Preparing Environmental Assessments and Considering Environmental Issues ML080840323