NUREG/CR-1659/2of4 SAND80-1897/2of4 AN REACTOR SAFETY STUDY METHODOLOGY APPLICATIONS PROGRAM: OCONEE #3 PWR POWER PLANT G. J. Kolb, S. W. Hatch, P. Cybulskis, R. 0. Wooton Printed January 1981 2900-Q(3*80) Prepared for U. S. NUCLEAR REGULATORY COMMISSION 81304)615NUREG/CR-1659...
Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title: Meeting of the Advisory Committee on the Medical Uses of Isotopes Docket Number: (n/a) Location: teleconference Date: Wednesday, December 10, 2014 Work Order No.: NRC-1268 Page...
YUCCA MOUNTAIN PROJECT DOC.20070702.0003 QA: QA TWP-MGR-MM-000003 REV 00 June 2007 Performance Confirmation Test Plan for Seismicity Monitoring Prepared for: U.S. Department of Energy Office of Civilian Radioactive Waste Management Office of Repository Development 1551 Hil!s...
` December 2010 Technical Report Volume 5 of 6 Addenda 2.7-I through 2.9-B Ross ISR Project USNRC License Application Crook County, Wyoming - 1 -SEI014IRoss ISR Project Technical Report i December 2010 TABLE OF CONTENTS VOLUME 1 OF 6 CHAPTER 1 - PROPOSED AC...
NON-PROPRIETARY VERSION SAFETY ANALYSIS REPORT on THE HI-STAR 100 CASK SYSTEM (Holtec International Storage, Transport, And Repository Cask System) (Revision 16.A) by Holtec International Holtec Center One Holtec Drive Marlton, NJ 08053 (holtecinternational.com) USN...
- . - _ _ . ,,,*, ,. $*1e!GCT-91-16,|November 5, 1991!!U. S. Nuclear Regulatory Commir.ston,.ATTN: Document Control Desk'Hashington, D.C. 20555,SUBJECT: Quad Cities Nuclear Station Units 1 and 2Honthly Performance Report_,B C Docket Nos. 50-254 and 50-265,Enclosed for your inf...
- - _ _ _ - _ _ - _ _ _O9Commonwealth Edison-Braidwood Nuclear Power Station mRouto #1, Box 84|Braceville, lilinois b0407Telephone 815/458-2801July 23, 1991BW/91-0622Director, Office of Resource ManagementUnited States Nuclear Regulatory CommissionWashington, D.C. 20555ATTN: D...
__._._.;,__- _ . ., , . .t9 CENTER 00R ENERGYOtm C. SW300 Maison AvenueVce Presdent Nuclea'Toledo, OH 436524001Mb(411r,26230nDocket Number 50-346License Number NPF-3Serial Number 2040April 28, 1992United States Nuclear Regulatory CommissionDocument Control DeskWashington, DC 2...
!-.i,IVIRGINIA Et,ECTRIC AND Powtu COMPANY!RICHMOND, VIRGINIA 23261L!!! ,Oc t.o b e r 30, 1989 |fIU.S. Nuclear Regulatory Commission Serial No. 89-761 ikua: Document Control Desk N0/JEC/acm!Washington, D.C. 20555 Docket Nos. 50-338|50-339iGentlemen: License Nos. NPF-4|NPF-7 !'...
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.- --,NUREGER-2368SAND 81-2164=.Midland Planti Auxiliary Feedwater SystemReliability Analysis EvaluationPrepared by B. J. RoscoeSandia National LaboratoriesPrepared for~^U.S. Nuclear RegulatoryO''4'CommissiongfiE C E4' E D$,$dl\N2 01982n :y " w g e-',',Pk /iggfoolS oIf1820 121...
e* ,., QCf * TI7P.A.C I F I C G-A S AND E IaE C T RICC O 2)IPANY-77 BEALE STREET, SAN FR A N CISCO, C ALIFORNI A 94106 * IE LE PH ON E (415) *fa) 4 211 -IP G w s,iLE' OPIER 415) 543 7813 C *P. O. BOX 7 4 4 2, S A N FRANCISCO, C ALIFORNI A 94120 .ROBERT OHLB ACHV4CE PWtt:Dtti A...
-...,--. Department of Energyw . Washington, DC 20585 W 0037p,L+NOV < 71986126 my n gMr. John J. LinehanRepository ProjectsNuclear Regulatory CommissionWashington, D.C.20555Dear Mr. Linehan:Thank you for the opportunity to review and comment on the follow-ing Draft Generic Tec...
_ - _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ . _ _ - _ _ _* 'j. .',RAR-91-28July 2, 1991 i|||U. S. Nuclear Regulatory CommissionATTH: Document Control DeskHashington, D.C. 20555SUDJECT: Quad Cities Nuclear Station Units 1 and 2Mon...
.s. ..NUREG/CR-4478ORNL/TDMC-4L1|..UPDATE - AFORTRAN 77Source File ManipulatorAdapted for the Data General MV Series Eclipse ComputersUnder AOS/VSPrepared by B.L. KirkOck Ridge National LaboratoryPrepared forU.S. Nuclear RegulatoryCommissiong 30BJ g B90131-CR-4478 RPDR_ _ _ _ ...
___ _-_ -__ - ______ __ _Peter G. Crane 4X09 Drummond Avenue Chevy Chase, MD 20X15 301-656-39PN pgcrane@eroh.cToid|dose, etc. It is, I thmk, a thoughtful and balanced discussion of the pros and cons of evacuation and;sheltering. (Rather than characterize what the EPA Manual sa...
e-- ,76-/M6*- 'RETURN TO 396-SS- > .. . . . .License SNM-1067Docket 70-1100c- SPNovember 6, 19868Y,RECEIVED9. gNOV171986 %)2U. S. Nuclear Regulatory Commission;/{UELEAR REGULATORYU. {Washington, DC 20555cgottAttention: Mr. W. T. Crowe, Acting Chief 99*g,Uranium Fuel License Br...
i|OFFICE OFTHE INSPECTOR GENERALIIU.S. NUCLEAR.|REGULATORY COMMISSIONI.|CONTROLS OVER FUNDING FOR CISSCONEEDIMPROVEMENTOlG/98A-18 May 11,1999II'AUDIT REPORTiIggaREGyI0g434g$%Ieijji,i,/ItF~ g Bo,
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.. mDOE /WIPP 89-004Rev.11TRUPACT-IICONTENT CODES(TRUCON)AUGUST 1997*SEbCONSOLIDATED SARPJ"'*88st U?8412.BPDRJ. . . . .. ..IDOE /WIPP 89-0044iRev.11,ITRUPACT-IICONTEXT CODES(TRUCOX).< >AUGUST 1997|*fs'Jd'V@.EA)) .V<1*4|DOE /WIPP 89 004 Rev. I1, August 1997||[TABLE OF CONTENTS|...
*Commonwealth EdisonDresden Nuclear Power St tionR.R. #1Morris, Illinois 60450Telephone 815/942-2920March 21, 1986DJS LTR: 86-213Director, Office of Inspectionand EnforcementUnited States Nuclear RegulatoryCommissionWashington, DC 20555Attention: Document Control DeskDear Sir:...
ANALYTICAL REPORTTestAmerica Laboratories, Inc.TestAmerica St. Louis13715 Rider Trail NorthEarth City, MO 63045Tel: (314)298-8566TestAmerica Job ID: 160-4764-1Client Project/Site: RFP-CBA-022 (7 DAY TAT)For:Westinghouse Electric Company LLC3300 State Road PFestus, Missouri 630...
Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M) Effective Date: May 4, 2018 Office of Nuclear Material Safety and Safeguards NUREG/BR-0006, Rev. 8 iii NUREG/BR-0006, Rev. 8 ABSTRACT U.S. Nuclear Regulat...
Catawba Nuclear Station UFSAR Chapter 2 (14 APR 2018) 2 - i Table of Contents 2.0 Site Characteristics 2.1 Geography and Demography 2.1.1 Site Location and Description 2.1.1.1 Specification of Location 2.1.1.2 Site Area 2.1.1.3 Boundaries for Establishing Effluent Releas...
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 5A 1-15 1.2 GENERAL DESCRIPTION OF HI-STORM UMAX SYSTEM 1.2.1 System Characteristics The HI-STORM UMAX System consists of interchangeable MPCs, which maintain the configuration of the fuel and is the confineme...