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ML20141E659
Show incoming properties
Category
TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT
ASME section
ASME Section XI +
Accession number
ML20141E659  +
Act
Endangered Species Act +
Agency
National Marine Fisheries Service +  and Federal Energy Regulatory Commission +
Atomic Element
Boron +, Nitrogen +  and Lead +
BWRVIP
BWRVIP-25 +, BWRVIP-03 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-05 +, BWRVIP-16 +, BWRVIP-06 +, BWRVIP-17 +, BWRVIP-19 +, BWRVIP-14 +, BWRVIP-07 +, BWRVIP-28 +  and BWRVIP-05F +
CFR
10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.65 +, 10 CFR 50.80 +, 10 CFR 54.21 +, 10 CFR 72.48 +, 10 CFR 100 Appendix A +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.55a#g6iiA +, 10 CFR 50.55a#g6 +  and 10 CFR 50.55#a +
Committee
Advisory Committee on Reactor Safeguards +  and Committee To Review Generic Requirements +
Cornerstone
Emergency Preparedness +
Correspondence
SECY-97-035 +, SECY-97-036 +, SECY-95-059 +, SECY-95-280 +, SECY-95-034 +, SECY-96-134 +, SECY-88-147 +, SECY-96-267 +, SECY 88-147 +, SECY 89-012 +, SECY-95-126 +, SECY-89-012 +, SECY 95-059 +, SECY-97-076 +, SECY 97-035 +, SECY 97-077 +, SECY-94-219 +, SECY-96-242 +, SECY 96-242 +, SECY-96-218 +, SECY 96-218 +, SECY-95-079 +, SECY-96-088 +, SECY-97-077 +, SECY-96-148 +, SECY 93-049 +, SECY-96 242 +, SECY-97-009 +, SECY 93 049 +, SECY 95-126 +...
Drawing
FP-TAP +
Equipment trip
Reactor Trip +
From
NRC (Affiliation Not Assigned) +
General design criterion
GDC 3, Fire protection +
Generic letter
NRC Generic Letter 88-18, Plant Record Storage on Optical Disks +, NRC Generic Letter 91-15, Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-06, Changes in the Operator Licensing Program +, NRC Generic Letter 95-02, Use of Numarc/epri Report TR-102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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>.
ML20141E659 +, ML20141E659 +, ML20141E659 +, ML20141E659 +, ML20141E659 +  and ML20141E659 +
Inspection Manual Chapter
NRC Inspection Manual 2515 +
Inspection procedure
IP 60854 +, IP 62706 +, IP 62707 +  and IP 62002 +
Issue date
April 30, 1997  +
License amendment topic
License Renewal Application +
Manufacturer
Westinghouse +, Limitorque +, General Electric +  and Target Rock +
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>.
20:24:36, 11 December 2024  +
NRC bulletin
NRC Bulletin 80-04 +, NRC Bulletin 85-03 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +
NRC information notice
Information Notice 92-27 +, Information Notice 97-16 +, Information Notice 97-08 +, Information Notice 88-24 +, Information Notice 97-17 +, Information Notice 97-02 +, Information Notice 91-85 +, Information Notice 95-22 +, Information Notice 97-21 +, Information Notice 97-10 +, Information Notice 97-25 +, Information Notice 95-03 +, Information Notice 94-14 +, Information Notice 97-01 +, Information Notice 97-11 +, Information Notice 97-19 +, Information Notice 97-13 +, Information Notice 97-07 +, Information Notice 97-14 +, Information Notice 96-48 +, Information Notice 97-22 +, Information Notice 94-64 +, Information Notice 96-03 +, Information Notice 96-44 +, Information Notice 97-05 +, Information Notice 97-06 +, Information Notice 97-09 +, Information Notice 97-12 +, Information Notice 97-15 +...
NUMARC
NUMARC 93-01 +
NUREG
NUREG-1522 +, NUREG-1544 +, NUREG-1526 +, NUREG-1622 +, NUREG/CR-6412, Submits Detailed Comments Re NUREG/CR-6412 Per Request +, NUREG-0555, For Comment Notice of Issuance & Availability of Proposed NUREG-0555,ESRP Section 7.1.1, Environ Impacts of Postulated Accidents Involving Radioactive Matls - Releases to Groundwater +, NUREG-1560, Forwards Draft NUREG-1560 Public Workshop Summary Rept from Workshop Held on 970407-09 in Austin,Texas.Rept Summarizes Discussions Held During Workshop & Documents All of Presentation Matl Distributed to Workshop by Attendees +, NUREG-1606, Summary of CRGR Meeting 310 on 970909 Re Proposed Rev 1 to GL 91-18,proposed Amends to 10CFR50.55a & Proposed GL on Lab Testing of nuclear-grade Activated Charcoal.Attendee List & Presentation Matl,Encl +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, 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-1352, Informs Commission of Status of Activities That NRC Performing & Has Planned to Resolve Concerns W/Performance of MOVs & Check Valves in Nuclear Power Plants +  and 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 +
Page count
89  +
Person
William Reckley +, Kerri Kavanagh +  and Shirley Ann Jackson +
Procedure
EAP +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20141E659 +
Project reference
TAC:M91898 +, TAC:M94164 +, TAC:M91429 +, TAC:M89586 +, TAC:M88282 +, TAC:M80177 +, TAC:M94269 +, TAC:M78003 +, TAC:M91571 +, TAC:M85648 +, TAC:M92635 +  and TAC:M85142 +
Regulatory Guide
Regulatory Guide 1.160 +
Report
NEDC-32424 +
SECY
SECY-97-035 +, SECY-97-036 +, SECY-95-059 +, SECY-95-280 +, SECY-95-034 +, SECY-96-134 +, SECY-88-147 +, SECY-96-267 +, SECY 88-147 +, SECY 89-012 +, SECY-95-126 +, SECY-89-012 +, SECY 95-059 +, SECY-97-076 +, SECY 97-035 +, SECY 97-077 +, SECY-94-219 +, SECY-96-242 +, SECY 96-242 +, SECY-96-218 +, SECY 96-218 +, SECY-95-079 +, SECY-96-088 +, SECY-97-077 +, SECY-96-148 +, SECY 93-049 +, SECY-96 242 +, SECY-97-009 +, SECY 93 049 +, SECY 95-126 +...
SSC
1edium-Voltage +
Start date
April 30, 1997  +
State
Texas +, Tennessee +, Georgia +, Maryland +, North Carolina +, Washington +, Virginia +, South Carolina +  and Nebraska +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Decay Heat Removal +, Control Room Envelope +  and Control Rod +
Title
Directors Status Rept on Generic Activities,Action Plans, Generic Communication & Compliance Activities,Apr 1997  +
Topic
Hot Short +, Safe Shutdown +, Loop seal +, Ultimate heat sink +, Mission time +, Fire Barrier +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, Emergency Lighting +, Significance Determination Process +, Intergranular Stress Corrosion Cracking +, Severe Accident Management Guideline +, License Renewal +, Earthquake +, Commercial Grade +, Fuel cladding +, Fire Protection Program +, Environmental Justice +, Backfit +, Power Uprate +, Reactive Inspection +  and Gas accumulation +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML2014/ML20141E659.pdf  +
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