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Event Notification Report for June 24, 2010

U.S. Nuclear Regulatory CommissionOperations Center Event Reports For06/23/2010 - 06/24/2010 ** EVENT NUMBERS ** 46022460264602746028460294603046031460364603746038460394604146042General Information or OtherEvent Number: 46022 Rep Org: PA BUREAU OF RADIATION PROTECTION Licen...

Event Notification Report for April 18, 2013

U.S. Nuclear Regulatory CommissionOperations Center Event Reports For04/17/2013 - 04/18/2013 ** EVENT NUMBERS ** 4886448902489034892248934489354893648937489384893948940Agreement StateEvent Number: 48864 Rep Org: TEXAS DEPARTMENT OF HEALTH Licensee: ROSA OF NORTH DALLAS LLC ...

NUREG-1611 "Aging Management of Nuclear Power Plant Containments for License Renewal."

NUREG-161 1Aging Management of NuclearPower Plant Containments forLicense RenewalU. S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationW. C. Liu, P. T. Kuo, S. S. LeeAVAILABILITY NOTICEAvailability of Reference Materials Cited in NRC PublicationsMost documents...

ALLEGATION PROGRAM 2005 ANNUAL TRENDS REPORT CONTENTS EXECUTIVE SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 OVERVIEW OF SIGNIFICANT PROGRAM ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . ....

February 4, 2004 Mr. Fred R. Dacimo Site Vice President Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT 3 - NRC INTEGRATED INSPECTION REPORT 05000286/2003009 Dear...

UNITED STATES NUCLEAR REGULATORY COMMISSION + + + + + BRIEFING WITH DOE ON NEW REACTOR ISSUES + + + + + THURSDAY APRIL 27, 2006 + + + + + The Commission convened at 1:30 p.m., Nils J. Diaz, Chairman, presiding. NUCLEAR REGULATORY COMMISSION: NILS J. DIAZ, CHAIRMAN ...

f f (FSME-111-008, Janu ary, Programm, 10 CFR 440) January 118, 2011 ALL AGRREEMENT S TATES, MICCHIGAN OPPORTUNITY TO CCOMMENT OON DRAFT...

20963 Federal Register / Vol. 73, No. 75 / Thursday, April 17, 2008 / Notices that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counse...

OFFICIAL EXHIBIT - NRC-006P-MA-CM01 - SHINE Medical Technologies, Inc., Construction Permit Application - Environmental Report, [PSAR] Chapter 19 Figure 19.4.1-1 through Figure 19.4.13-1 (August 27, 2015), ADAMS Accession No. ML15258A428.

Chapter 19 – Environmental Review Land Use and Visual Resources SHINE Medical Technologies Rev. 0 Figure 19.4.1-1 – Conceptual Rendering of SHINE Facility View of SHINE Facility from U.S. Highway 51, Looking Southeast View of SHINE Facility from East NRC-006P United States N...

A COMPUTATIONAL MODEL FOR CRITICAL FLOW THROUGH INTERGRANULAR STRESS CORROSION CRACKS.

,.1NUREG/CR-5133i LBL-21967i:'-_.iA Computational Model forCritical Flow Through)Intergranular StressL,orroSlonCracks.!j.i_._! Prepared by V.E. Schrock, S.T. Revankar, S.Y. Lee, C H WangUniversity of CaliforniaLawrence Berkolay Laboratory,Prepared forcU.S. Nuclear RegulatoryiC...

December 17, 2008 The Honorable Thomas R. Carper Chairman, Subcommittee on Clean Air and Nuclear Safety Committee on Environment and Public Works United States Senate Washington, D.C. 20510 Dear Mr. Chairman: The Energy Policy Act of 1992 modified ...

Email D. Hills to T. Bilik et al., FW: ASME Code Meeting Report - Subgroup on Evaluation Standards.

Neurauter, JamesFrom:Sent:To:Subject:Hills, DavidMonday, August 27, 2012 4:19 PMBilik, Tom; Bozga, John; Holmberg, Mel; Jones. Donald; Meghanl, Vijay; Neurauter, James;Sanchez Santiago, Elba; Shalkh, AtifFW: ASME Code Meeting Report -- Subgroup on Evaluation StandardsFrom: Ste...

Progress Energy Harris Nuclear Units 2 & 3 COLA (Emergency Plan), Rev. 0 - Emergency Plan

Shearon Harris Nuclear Power Plant Units 1, 2, and 3 COL Application Part 5, Emergency Plan Rev. 0 i TABLE OF CONTENTS Section Title Page TABLE OF CONTENTS ......................................................................................... i INTRODUCTION..............

01/06/2009-Summary of Public Scoping Meetings Related to the Combined License Application Review of the Comanche Peak Nuclear Power Plant, Units 3 & 4.

February 2, 2009 MEMORANDUM TO: William Burton, Branch Chief Environmental Projects Branch 1 Division of Site and Environmental Reviews Office of New Reactors FROM: Michael Willingham, Project Manager /RA/ Environmental Project...

Columbia Pulaski Community Hospital, Amendment Request for License No. 45-21206-01, dated 01/12/2005.

Pulaski Community HospitalTrust Your Health To Us2400 Lee Highway, Post Office Box 759Pulaski, Virginia 24301-0759Phone (540) 994-8100 Fax (540) 994-8333Internet: http://www.pch-va.com 6iJCAHO Accredited / ISO-9002 Certified12 January 2005-vr' -~Licensing Assistant SectionNucl...

Matls licensing package for amend 3 to license 07-28190-01 for Omega Nuclear Diagnostic Center,LP.Control:126477.

,""U'u.s. NUCL R REGULATORY COMMtsSloNAmend ent No. 03MATERIALS LICENSEPursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 Codeof Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36, 39,40, and 7...

Matls licensing package for amend 22 to license 34-00738-07 for Case Western Reserve Univ.Control:301679.

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"1984 Annual Rept."

:: :n ~- 8 w?, .? v ,.,".g.3g'|:;yeg;.. g;;9;, 3.q;gh_,g.y.,..q,. ,;f:._y,.q. ;...y ; % - '.,( . .. y o '[ .,.. , a3_e, _ , ;,.:, . v. 3. .m .: -,p ,3m . . -,: .e9;.., cr_n ;- O ,-- ,m.... , - - .. . ... . m. yv , _ g ; . . . n. 7: yy? '!fs -) |,.<; ';. 5-b &ft| W_ .. .#\ ^ ' ...

Discusses NRC evaluation of readiness review of mechanical equipment Module 4 submitted on 880118.Mechanical equipment acceptable based on current info & complies w/applicable regulatory requirements except encl items.

'' ^ ~..*:.,'(;-. .- -,IIMAY 2 3 19884i- j/' BTU / Hour , . , , ' ,2 31,,y, ,f4d126P'p3 j4914.00 9.2.1-1 NSCW Sys. Min. NSCW'( Design From Per,'j' Train During*'','. #iAccident,.ConditionsiI15,733 GPM".i ,j!384.00, 9.2.1-3 NSCW; Equip. NSCW Pumps DC 1010-T1: $ ,,Desip.; ASME I...

NuScale Power, LLC Response to NRC Request for Additional Information No. 149 (eRAI No. 8955) on the NuScale Design Certification Application.

RAIO-1117-56989NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comNovember 02, 2017 Docket No. 52-048U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockvi...

"Socioeconomic Monitoring & Mitigation Rept," for Jan-June 1979.

_ ._ . . . _ _ . _ . . . . - _ _ . _ . . . . _ . _ _ . . . . . _ _ . - _ _ . . ~ . . _ _ - .:O'l;.! II |14.i.:,t .TENNESSEE VALLEY AUTHORITYj 1'*!:'-- e a v-.. _ _ . . -.6*|apartments, sleeping rooms,-and other accommodations. The "other"category includes tents, campers, and r...

2009/07/31 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 253, FSARCh. 14

1ArevaEPRDCPEm ResourceFrom: Pederson Ronda M (AREVA NP INC) [Ronda.Pederson@areva.com]Sent: Friday, July 31, 2009 6:08 PMTo: Tesfaye, GetachewCc: BENNETT Kathy A (OFR) (AREVA NP INC); DELANO Karen V (AREVA NP INC); DUNCAN Leslie E (AREVA NP INC)Subject: Response to U.S. EPR D...

Progress Energy Harris Nuclear Units 2 & 3 COLA (Final Safety Analysis Report), Rev. 3 - Chapter 01 - Introduction and General Description of the Plant - Sections 1.1 - Appendix 1AA

Shearon Harris Nuclear Power Plant Units 2 and 3 COL Application Part 2, Final Safety Analysis Report Rev. 3 1-i CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT TABLE OF CONTENTS Section Title Page 1.1 INTRODUCTION....................................................

2001/10/22-Part 22 of 29 - Reference documents used in preparation of Duke Cogema Stone & Webster's Mixed Oxide Fuel Fuel Fabrication Facility Construction Authorization Request. G-SAR-G-00001, Rev 4.

G-SAR-G-00001 Rev. 4 DOE Review Copy I CONTENTS Page 8.0 HAZARDOUS MATERIAL PROTECTION ............................................................... 8.1-1 8.1 IN TR O D U C TIO N ............................................................................................. 8....

BMI-2104, Vol. 4, "Radionuclide Release Under Specific LWR Accident Conditions, IV, PWR Ice Condenser Containment Design".

DRAFTBMI-2104Volume IVRadionuclide Release UnderSpecific LWR Accident ConditionsVolume IVPWR, Ice Condenser Containment DesignPrepared byJ. A. Gieseke, P. Cybulskis, R. S. Denning,M. R. Kuhlman, K. W. Lee, H. ChenBattelle Columbus LaboratoriesColumbus, Ohio 43201July 1984DRAFT...

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