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ML20237K365 +

Act

Atomic Energy Act of 1954 +

Atomic Element

Boron +, Iron +, Lead + and Tin +

CFR

10 CFR 50 Appendix A + and 10 CFR 50 Appendix B +

Committee

Committee To Review Generic Requirements +

Cornerstone

Emergency Preparedness +

Docket

05000445 +, 05000446 +, 00446 + and 00445 +

FR

37 FR 15127 +

From

Moseley N + and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) +

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ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 +, ML20237K365 + and ML20237K365 +

Hours

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) + and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +

Inspection Manual Chapter

NRC Inspection Manual 2512 +

December 5, 1979 +

ML20009G502 + and ML19309B277 +

Manufacturer

Westinghouse + and Chicago Bridge & Iron +

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>.

02:58:11, 27 June 2025 +

NRC bulletin

NRC Bulletin 79-14 + and NRC Bulletin 79-28 +

NRC information notice

Information Notice 82-02 +

NUREG

NUREG-0797, Summary of Meeting on 890905 in Rockville,Md to Discuss Ground Motion Estimates for Criner Tectonic Structure of Southern Oklahoma Aulacongen in Wichita Tectonic Province, Per Section 2.5.2 of Fsar.Viewgraphs Encl + and NUREG-0302, Ack Receipt of Re 10CFR21.Part 21 Only Requires That Internal Procedures for Evaluating & Reporting Identify Responsible Officer.Rev 1 to NUREG-0302 Encl to Clarify Issue.W/O Encl +

Page count

166 +

Procedure

AM +, RT +, CP +, CP-84-27 +, CP-QP-16.1 +, CP-QP-15.6 +, CP-85-14 +, CP-85-12 +, CP-85-11 +, CP-85-04 +, CP-85-05 +, CP-84-31 +, CP-85-13 +, CP-0707 +, CP-55-12 + and CP-84-2 +

Regulatory Guide

Regulatory Guide 1.16 + and Regulatory Guide 1.123 +

SSC

0F-1 +, N0E-205 +, R1s-bbIfa + and 42M-l +

December 5, 1979 +

Texas + and Washington +

System

Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel + and Residual Heat Removal +

TS

TS-6.0 +

Title

Forwards IE Bulletin 79-28, Possible Malfunction of Namco Model 180 Limit Switches at Elevated Temps. Bulletin Should Be Dispatched for Action on 791207 to All Power Reactor Facilities W/Ol or Cp.Related Info Re Plant Encl +

To

James Keppler +, NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +, Grier B +, NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) +, NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) + and James O'Reilly +

Topic

Fire Barrier +, B.5.b +, Loctite + and Basic Component +

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http://pbadupws.nrc.gov/docs/ML2023/ML20237K365.pdf +

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