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ML19309E840
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Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
Accession number
ML19309E840  +
Act
Energy Reorganization Act of 1974 +
Atomic Element
Lead +  and Carbon +
CFR
10 CFR 2.206 +  and 10 CFR 10 +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
SECY-79-106 +
Docket
05000247  +, 05000286  +, 05000295  +, 05000304  +, 00295  +  and 00304  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Harold Denton +  and Office of Nuclear Reactor Regulation +
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>.
ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +, ML19309E840 +  and ML19309E840 +
IEEE
IEEE 323 +
In package
ML19309E842 +
Intervenor
Union of Concerned Scientists +
Issue date
April 9, 1980  +
Manufacturer
Westinghouse +
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07:56:28, 2 January 2025  +
NRC bulletin
NRC Bulletin 79-01 +
NUREG
NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +  and NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +
Page count
33  +
Procedure
CP +
Regulatory Guide
Regulatory Guide 1.82 +, Regulatory Guide 1.79 +  and Regulatory Guide 1.139 +
SECY
SECY-79-106 +
Site
Indian Point +  and Zion +
Start date
April 9, 1980  +
State
Washington +  and Illinois +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Containment Spray +
TS
TS-3.8 +
Title
Forwards Addl Info Re Review of Unresolved Safety Issues, Trip Rept of Lessons Learned Implementation Team,& Task Action Plan in View of High Population Density Surrounding Plants  +
To
Reed C +  and Exelon +
Topic
Safe Shutdown +, High winds +, Stress corrosion cracking +, Earthquake +, Control of Heavy Loads +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1930/ML19309E840.pdf  +
WCAP
WCAP-8330 +
Westinghouse report
WCAP-8330 +
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