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ML12339A714  +
05000247  +, 05000286  +, 00247  +  and 00286  +
December 18, 2008  +
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>.
01:27:01, 12 January 2025  +
NUREG-1432 +, NUREG-1793 +, NUREG-1431 +, NUREG-1434 +, NUREG-0452 +, NUREG/BR-0058 +, NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG/CR-4013 +, NUREG/CR-1276 +, NUREG/CR-2919 +, NUREG-0172 +, NUREG/CR-4653 +, NUREG-0851 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-1551, Forwards Info Requested from Sealed Source Safety Section Re NUREG-1551 & SECY-97-273.W/o Encl +, NUREG-1462, Notification of 921209 Meeting w/ABB-C-E in Rockville,Md to Discuss Status of Closure of Open Items in Draft SER for Sys 80+ (NUREG-1462).Meeting Agenda Encl +, NUREG-1503, Supplement 2, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design +, NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG-1512, Provides Advisory Committee on Reactor Safeguards with Attached Suppl to AP600 FSER for Consideration.Suppl FSER Documents Staff Review of Changes to AP600 Design Documentation Since Issuance of FSER NUREG-1512 +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-1530, SECY-23-0020: Enclosure 2 - Regulatory Analysis +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +, NUREG-1302, Forwards Matl on CRGR Meeting 180 Re NUREG-1301 & NUREG-1302 & Summary of Discussions of Proposal to Eliminate CRGR Review of Certain Rev to 10CFR50.55a +  and NUREG-0324, Forwards Crac Code Input for 790328-0402 at Site.Wind Speeds Corrected to 10 Meter Level Using Procedures Outlined in NUREG-0324 +
Request  +
December 18, 2008  +
Official Exhibit - ENTR0352A-00-BD01 - SECY-08-0197, Policy Issue (Notation Vote)  +
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