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"Reactor Containment Bldg Structual Integrity Test."

sp,T -THREE MILE ISLAND NOCLEAR STATIONO.UNIT 1REACTOR CONTAINMENT BUILDING':NSTRUCTURAL INTEGRITYi2TEST-'|THis DOCUMENT CONTMHSClPOOR QUAUTY PAGESI|i,/'EMETROPOLITAN EDISON COMPANYSUBSIDI ARY OF GENERAL PUBLICUTILITIES CORPORATIONGILBERT ASS CIATES , INC.(RE ADING, PENNSYLVAN...

Vermont Yankee, License Amendment 147 re Secondary Containment Integrity.

UNITED STATES ` NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 .9 July 10, 1996 Mr. Donald A. Reid Vice President, Operations Vermont Yankee Nuclear Power Corporation Ferry Road Brattleboro, VT 05301SUBJECT: ISSUANCE OF AMENDMENT (TAC NO. M95148)Dear Mr. Reid:The Co...

Proposed Tech Specs re post-accident monitoring instrumentation requirements,primary containment isolation valves & primary containment leakage test penetrations.

W:n p# ,1 /.yp m_; _y~. .n gw"-, .-,,<, ,o4, K"3s,, m,N r m,.^. ,s,, , y,s ..,-.,3--t , ,*, m'..*c- ,m-.>..3w @p8 L'y-A _. ' ,Gs'g,% > ,; je* -, ...','- 3 3 , .,i,,-,3;h.-^?, 1~.. ,-7.,, , ,.a n,,- .. ;r ,-g. 4- m. ., ,.., i, -.#~ ._ m 2.2. n'f, t -- *'y: ' h ,E.,m' v .| ''t &...

Proposed TS re SGTS & secondary containment.

1..|.Exhibit BMonticello Nuclear Generating PlantLicense Amendment Recuest dated June 8. 1994Proposed Changes Marked Up on ExistingTechnical Specification Pages.Exhibit B consists of the existing Technical Specification pages with theproposed changes marked up on those pages. ...

Confirmatory Analysis: ANO-2 Design Basis Accident Containment Response

LA-UR-3701CONFIRMATORY ANALYSIS: ANO-2 Design Basis Accident Containment Response Prepared for U.S. Nuclear Regulatory Commission Rockville, Maryland Prepared by D. V. Rao M. T. Leonard Probabilistic Risk and Hazard Analysis Group Technology and Safety Assessment Division Los ...

"BVPS-2 Containment Penetrations Overpressure Protection Analysis/Review Rept."

1-_ ...1ATTACHMENT 1-,BVPS-2 CONTAINMENT PENETRATIONS:,OVERPRESSURE PROTECTION ANALYSIS / REVIEWREPORT*,Ii!Prepared by:8 X Av w' /o/y/pgK. E. Woessner DateReviewed by: .ro/4/qgi.G. V. Cacciani ' D ateReviewed by:&Ghd fo-y-%V'A. J. Dometrovich DateReviewed by:..do/4/6/oG. E. Mi...

0518 - R304B - GE BWR_4 Technology - 4.1 Primary Containment System.

General Electric Systems Technology Manual Chapter 4.1 Primary Containment System Rev 09/11 4.1-i USNRC HRTD TABLE OF CONTENTS 4.1 PRIMARY CONTAINMENT SYSTEM .................................................................... 1 4.1.1 Introduction ........

Revised Tech Spec Table 3.6-1 re containment isolation valve.

COO'4 PENT.NO.QO100101TM3IZ 3.6-1CONTAINMENT ISOIATION VALVESMAXIMUMISOIATION ISOIATIONTIME *(SEC) BOUNDAarISOLATIONBOUNlRHY IDENTIFICATION/DESCRIPTIONFuel transfer tube(1)(2)(5)(5)(2)MV 5129(3)(2)flangeCV 370B charging line to"B"locpSI Pump 1B discharge CV 889BCV 870BCV 383B ...

"Reactor Containment Bldg Integrated Leak Rate Test."

DUKE POWER COMPANY Oconee Nuclear Station Unit 2 Reactor Containment Building Integrated Leak Rate Test Prepared by: rry W,, Collier , , ss' Vfineer Test Reviewed by: 'B. Graham Davenpo tTest Engineer Approved by: 4 o Tony rBarr Perfovance Engineer (ILRT Coordinator) 800826048...

Proposed Tech Specs Section 15.3.6 re containment sys.

.~ -.-- , . ,,:'' r-mw-kTECHNICAL SPECIFICATION CHANGE REQUEST 163. |SAFETY EVALUATIONINTRODUCTION-"- iWisconsin Electric Power Company (Licensee)::is' applying for .'.amendments to Facility Operating License DPR-24.and DPR-27Efor-' Point Beach Nuclear: Plant, Units 1-and.2.Th...

Forwards LER 89-010-00 describing generation of containment high pressure signal during leak testing of containment penetrations for facility.

_ _. - _ _ _ .__ _ _ _ _ _ _ _-..'Wisconsin''' liksctnc1POWER COMPAtH ||231 W Mctsyan, PO Box 2M6. Wwoakee, WI 53201 (414)221 2345|||VPNPD-90-436 10 CPR 50.73NRC-90-103October 11, 1990.U. S. NUCLEAR REGULATORY COMMISSIONDocument Control DeskMail Station P1-137Washington, D. C....

BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 1.

ENCLOSURE 4TENNESSEE VALLEY AUTHORITYBROWNS FERRY NUCLEAR PLANT (BFN)UNIT 1BFN EPU CONTAINMENT OVERPRESSURE (COP) CREDIT RISK ASSESSMENTISee attached.; I I I 1,BFN EPUContainment Overpressure (COP)ACredit Risk AssessmentRev. 1Performed for:ITennessee Valley AuthorityPerformed ...

2010/06/25-Post Accident AP1000 Containment Leakage, Exhibit 4.

Docket Nos. 52-025-COL and 52-026-COL BLUE RIDGE ENVIRONMENTAL DEFENSE LEAGUE EXHIBIT 4 Post Accident AP1000 Containment Leakage Arnold Gundersen, Chief Engineer Fairewinds Associates, Inc June 25, 2010 Presentation to ACRS Post Accident AP1000 Containment Leakage AP1...

IMI Presentation "Filtered Containment Venting System."

© 2012 CCI AG. All rights reserved.Filtered Containment Venting SystemNRC Public Meeting, September 4th2012Rockville, MDIMI Nuclear (CCI AG)Denis Grob – Manager Nuclear Services DivisionPage 1© 2012 CCI AG. All rights reserved.Content� Overview� How it works� Experimental base...

Meeting Slides on Filtered Containment Venting Systems.

IjU.S.NRCUnited States Nuclear Regulatory CommissionProtecting People and the EnvironmentFiltered Comtainmemt Ventimg SystemsBob Fretz, Senior Project ManagerJapan Lessons Learned Project DirectorateOffice of Nuclear Reactor RegulationAdvisory Committee on Reactor SafeguardsFu...

Audit Plan - Regulatory Audit of NuScale Containment and Ventilation Systems.

March 29, 2017 MEMORANDUM TO: Samuel Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Omid Tabatabai, Senior Project Manager /RA/ Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors SUBJECT: AUDIT PLAN...

Submittal of Pebble Bed Modular Reactor Containment Design Position Paper.

Exel ,nm Exelon Generation Telephone 610.765.5661 Generation 200 Exelon Way Fax 610.765.5545 KSA3-N www.exeloncoTp.Com Kennett Square, PA 19348 Project No.: 713 May 31, 2002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Subject: Submitta...

Attachment 5 - Slides - Handouts on AP1000 Containment Vessel Design.

AP1000 Containment Vessel Design 1Att~rhrnont AP1 000 Containment Vessel DesignSpecificationWestinghouse Specification: APP-MV50-ZO-001.. Me'ets requirements of the AP1000 DesignCertification Document. ''. e'Specification reviewed by CB&I.'e'sigCode: ASME Section III, Class MC...

"Debris in Containment Recirculation Sumps," technical review rept.

_ - _ . - -E .1... .-.AEOD TECHNICAL REVIEW REPORTUNITS: Multiple TR REPORT NO.:AEOD/T916DOCKET-NOS: Multiple DATE: September 29, 1989LICENSEES: MultipleEVALUATOR / CONTACT:L.PadovanNSSS/AE:MultipleSUBJECT: DEBRIS IN CONTAINMENT RECIRCULATION SUMPSSUMMARYOn July 8, 1989, durin...

"Sys 80+ Severe Accident Phenomenology & Containment Performance" rept.

-)i:SYSTEM 80+SEVERE ACCIDIWT PHENOMENOLOGYANDCONTAINMENT PERFORMANCEMARCH 1993PreparedbyABD Combustion EngineeringNuclear PowerCombastion Engineering, Inc.9303300242 930323PDR ADOCK 05200002A PDR;. .. .. -.,.|..;!!!TABLE OF CONTENTS,!!iSECTION TITLEPAGE NO.}i1.0INTRODUCTION1-...

1036 - R109P - APWR Intro to Diffs - 05 - Containment, RB Text.

Rev 0210 5-i USNRC HRTD TABLE OF CONTENTS 5.0 CONTAINMENT, REACTOR BUILDING, AND ASSOCIATED SYSTEMS ..... 5-1 5.1 Introduction ............................................................................................... 5-1 5.2 Containment .................................

Transmittal of Containment Safety Analysis Methodology Report.

A AECLTECHNOLOGIES INC.November 25, 2003Our File:Your File:108US-01321-021-001Project No. 722Ms. Belkys SosaACR Project ManagerUS NRC - M/S 0-4D9A11555 Rockville PikeRockville, MD 20852-2738U.S.A.Dear Ms. Sosa,Reference:1. Letter from V.J. Langman to B. Sosa, "Phase 2 of ACR P...

Forwards "Reactor Containment Bldg Structural Acceptance Test."

-SOUTH CAROUNA ELECTRIC a gas COMPANY[q , g_LL4, / , gpost omce so 7..CotuMs:A. south CAROUNA 29288/ 'yT. C. NicHots.JR.UMarch 20, 1981 /f [) (\vez ensrec=1 u.o o=* Ene*'. , ,~(Nuclear Operations)[J o, ,f; 1G gg,U J*'' s.-,Q#3%g.s t/ \MMr. Harold R. Denton, Director'N/Office o...

CONTAINMENT VENTING ANALYSIS FOR THE PEACH BOTTOM ATOMIC POWER STATION.

._** *NUREG/CR-4696**EGG-2464December 1986.Containment Venting AnalysisDuane J. HansonHarold S. Blackmanfor the Peach Bottomwiiii3m n,noisonAtomic Power Station Ronald E. WrightMark T. LeonardRaymond DISalvoF O R M A L R E P O R TE5cGw n.n$o?cin1|c5E$AC07-7CD01570for the U.S. ...

NRC Information Notice 2010-012: Containment Liner Corrosion.

ML100640449 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS WASHINGTON, DC 20555-0001 June 18, 2010 NRC INFORMATION NOTICE 2010-12: CONTAINMENT LINER CORROSION ADDRESSEES All holders of an operating license or con...