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ML20023D721
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Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
ANSI code
ANSI-N18.7-1976 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +
ASME section
ASME Section IV +
Accession number
ML20023D721  +
Area
Switchyard +
Atomic Element
Boron +, Copper +, Hydrogen +, Lead +  and Tin +
CFR
10 CFR 21 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 59.49#g +, 10 CFR 50.49#b2 +, 10 CFR 50.49#b1 +  and 10 CFR 50.49#g +
Committee
Advisory Committee on Reactor Safeguards +
Cornerstone
Emergency Preparedness +
Docket
05000369  +, 05000370  +, 00399  +, 00369  +, 00370  +, 00413  +, 00414  +, 00327  +, 00328  +, 00295  +  and 00304  +
Equipment trip
Reactor Trip +
From
Novak T +  and Office of Nuclear Reactor Regulation +
General design criterion
GDC 23 +
Generic letter
NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +  and NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +
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ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +, ML20023D721 +  and ML20023D721 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 308 +  and IEEE 279 +
Isotope
C-14 +
Issue date
May 24, 1983  +
Manufacturer
Westinghouse +  and Magnetrol +
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>.
06:05:37, 21 December 2024  +
NRC bulletin
NRC Bulletin 83-04 +  and NRC Bulletin 83-01 +
NRC form
NRC Form 310 +
NRC information notice
Information Notice 83-18 +  and Information Notice 79-22 +
NUREG
NUREG/CR-1891 +, NUREG/CR-2730 +, NUREG/CR-3278 +, NUREG-0954, Advises That 860619 Submittal Summarizing Results of Survey Quantifying Insulation in Containment by Type & Location Complies W/Guidance in Generic Ltr 85-22 & Sser 2 (NUREG-0954) +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0422, Requests Comments on Review of Encl marked-up Tech Spec Concerns Resulting from Differing Prof Opinion.Some Concerns Should Be Resolved on plant-specific Basis.Proposed Amend Requests & Reply Needed within 90 Days +, NUREG-0011, Notice of Availability of SER (NUREG-0011) +  and NUREG-0977, Requests Util Review of NUREG-0977 Re ATWS Events to Identify & Explain Apparent Inconsistencies Based on Latest Available Info & Provide Basis for Relevance of New Info +
Page count
44  +
Regulatory Guide
Regulatory Guide 1.150 +  and Regulatory Guide 1.97 +
SSC
3nzjle-used +
Scram
Manual Scram +  and Automatic Scram +
Site
McGuire +  and Mcguire +
Site license
McGuire +
Start date
May 24, 1983  +
State
Tennessee +, Pennsylvania +, Georgia +, North Carolina +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Control Rod +  and Containment Spray +
Title
Forwards Draft SER,NUREG-0422,Suppl 7 & Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept & Draft Full Power OL Amend  +
To
Tucker H +  and Duke Energy +
Topic
Safe Shutdown +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Emergency Lighting +, Finite Element Analysis +, High Energy Line Break +, Loss of Offsite Power +, Safeguards Contingency Plan +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2002/ML20023D721.pdf  +
WCAP
WCAP-8687 +, WCAP-8077 +  and WCAP-8078 +
Westinghouse report
WCAP-8687 +, WCAP-8077 +  and WCAP-8078 +
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