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ML20211H679
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
ASME section
ASME Section XI +
Accession number
ML20211H679  +
Atomic Element
Iron +, Copper +  and Lead +
BWRVIP
BWRVIP-05 +
Docket
05000440  +  and 00440  +
FR
57 FR 34666 +
From
NRC (Affiliation Not Assigned) +
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>.
ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +, ML20211H679 +  and ML20211H679 +
In package
ML20211H590 +
Issue date
September 18, 1997  +
Letter
ML20129J079 +, ML20217Q459 +, ML20211B215 +, PY-CEI-NRR-2200, Requests Change to Unit 1 Design Basis as Described in USAR, Per 10CFR50.59 & 10CFR50.90,NRC Review & Approval.Change Will Add Description of Methodology Utilized for Determining Sys +  and PY-CEI-NRR-1987, Informs That Centerior Electric Co Should Be Substituted Wherever Nomenclature Newco Appears in 940602 Proposed Amend Submittal Re Proposed Merger of Toed & Clei +
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04:08:11, 6 December 2024  +
Page count
5  +
Procedure
RT +
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.
ML20211H679 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.99 +
Site
Perry +
Start date
September 18, 1997  +
State
Washington +
System
High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Standby Liquid Control +  and Control Rod +
Title
Safety Evaluation Authorizing Licensees Request for Alternative from Augmented Insp of Reactor Pressure Vessel Circumferential Weld in Plant,Unit 1  +
Topic
Incorporated by reference +
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http://pbadupws.nrc.gov/docs/ML2021/ML20211H679.pdf  +
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