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ML14283A513 +

Atomic Element

Carbon +, Sodium +, Lead +, Aluminum +, Calcium + and Zinc +

CFR

10 CFR 50.46 +, 10 CFR 50.55a +, 10 CFR 50.54#f + and 10 CFR 50.71#e +

Committee

Committee To Review Generic Requirements +

05000327 + and 05000328 +

From

Andrew Hon + and Plant Licensing Branch II +

Generic letter

NRC Generic Letter 04-02 + and NRC Generic Letter 04-04 +

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Hours

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) + and 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months) +

Issue date

November 17, 2014 +

Letter

ML13119A135 +, ML090540857 +, ML092780335 +, CNL-14-109, Submittal Extension to the Fifth Quarterly Status Report to the Flooding Hazard Reevaluation Report Extension Request +, ML12121A233 +, ML041530368 + and 05000327/LER-2008-002, Loss of a Main Control Air Handling Unit in Conjunction with an Emergency Power Source Out of Service +

Licensing Basis Document

Updated Final Safety Analysis Report +

Manufacturer

Westinghouse +

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>.

21:48:37, 10 January 2025 +

NEI

NEI 02-01 + and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +

NRC bulletin

NRC Bulletin 03-01 +

NUREG

NUREG/CR-6808 +, NUREG/CR-6885 +, NUREG/CR-6913 + and NUREG/CR-6224, Requests That Encl Documents Be Available Through NRC PDR & Central Files.Documents Provided Background or Ref Info for Resolution of BWR Strainer Blockage Issue,As Ref by Draft NUREG/CR-6224, Parametric Study of Potential for Bwr.. +

Page count

48 +

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Approval +

Regulatory Guide 1.82 +

November 17, 2014 +

Tennessee + and Texas +

System

Steam Generator +, Reactor Coolant System +, Residual Heat Removal +, Emergency Core Cooling System + and Containment Spray +

Title

NRC Staff Review Documentation Provided by TVA for the Sequoyah Nuclear Plant, Units 1 and 2 Concerning Resolution of GL2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Wate +

To

Tennessee Valley Authority + and James Shea +

Topic

Reactor Vessel Water Level +, Mission time +, Coatings +, Finite Element Analysis +, High Energy Line Break +, Earthquake +, Fuel cladding + and Manual Operator Action +

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http://pbadupws.nrc.gov/docs/ML1428/ML14283A513.pdf +

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