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ML071210245
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Category
Letter
ASME code
IWB-2500 +
ASME section
ASME Section XI +
Accession number
ML071210245  +
Atomic Element
Lead +
BWRVIP
BWRVIP-74 +, BWRVIP-05 +  and BWRVIP-74-A +
Correspondence
NRC 32 +
Docket
05000410  +  and 00410  +
Document
ML12920549 +
From
Nine Mile Point +, Exelon +  and Laughlin G +
Generic letter
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 +
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>.
ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +, ML071210245 +...
Inspection Manual Chapter
NRC Inspection Manual 2191 +, NRC Inspection Manual 2192 +  and NRC Inspection Manual 2193 +
Issue date
April 20, 2007  +
Letter
ML070370450 +, ML063170034 +, ML051450484 +  and ML050060058 +
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>.
05:45:08, 15 January 2025  +
NRC
NRC 32 +
NUREG
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 +
Page count
16  +
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.
ML071210245 +
Project
TAC:MD3696 +
Project reference
TAC:MA3395 +, TAC:MA6185 +, TAC:MC2181 +, TAC:MD3696 +, TAC:MC2190 +, TAC:MC0331 +, TAC:MB9755 +, TAC:MC3916 +  and TAC:M93925 +
Project stage
Response to RAI  +
Regulatory Guide
Regulatory Guide 1.174 +, Regulatory Guide 1.190 +  and Regulatory Guide 1.99 +
SSC
2RPV-AA +, 2RPV-AB +, 2RPV-AC +, 2RPV-AD +, 21SI-001 +, 21Sl-001 +  and 288TV2-5 +
Site
Nine Mile Point +
Start date
April 20, 2007  +
State
Washington +
System
Reactor Coolant System +, Feedwater +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Reactor Water Cleanup +, Standby Liquid Control +, Decay Heat Removal +  and Control Rod +
Title
Response to NRC Request for Additional Information Regarding Request for Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55a(g) for the Volumetric Examination of Circumferential Reactor Pressure Vessel Welds  +
To
NRC/NRR/ADRO +  and Document Control Desk +
Topic
Large early release frequency +  and License Renewal +
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http://pbadupws.nrc.gov/docs/ML0712/ML071210245.pdf  +
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