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ML20069Q523 +
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ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 +, ML20069Q523 + and ML20069Q523 +
December 7, 1982 +
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15:11:56, 16 December 2024 +
NUREG/CR-1345 +, NUREG-0705 +, NUREG-0677 +, NUREG-0773 +, NUREG-0872 +, NUREG/CP-0032 +, NUREG/CR-2585 +, NUREG/CR-0388 +, NUREG/CR-1151 +, NUREG-625 +, NUREG-0144 +, NUREg/CR-0463 +, NUREG/CR-2546 +, NUREG/CR-1226 +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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/CR-1433, Reassigns Differing Professional Opinion Position to RES for Informal Review IAW Mc 4125.Key Issue Raised in Adequacy of cost-benefit Conclusion Originally Made in NUREG/CR-1433 & Adoption/Endorsement by NUREG-1355 & NUREG-1251 Discuss +, NUREG-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0674, Advises That Guard Training & Qualification Plan Does Not Meet Requirements of 10CFR73,App B.Requests Revision to 790817 Plan to Replace Pages 1-9 Through 1-17 Re Training Commitments.Response Should Be Submitted within 60 Days +, NUREG/CR-1582, Forwards Aug 1980 NUREG/CR-1582,Vols 2 & 3, Seismic Hazard Analysis,Solicitation of Expert Opinion, Prepared by Tera Corp.W/O Encl +, NUREG/CR-0181, Forwards NUREG/CR-0181 Which Provides Basic Barrier & Penetration Data Needed for Physical Security Sys Assessment +, 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 + and NUREG-0478, Confirms 790508 Deliery of Metropolitan Siting - Historical Perspective (NUREG-0478,Oct 1978) +
17 +
SECY-82-203 + and SECY-77-28 +
December 7, 1982 +
Supplemental Response to Interrogatories on Commission Questions 1 & 2.Certificate of Svc Encl +
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