The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Proposed Tech Specs,modifying containment & primary containment testing.

- _ _ _Surveillance P3ge No.3.7 CONTAINMENT SYSTEMS 4.7 152*A. Primary Containment A 152B. Standby Gas Treatment System B 158C. Secondary Containment C 15913.8 RADIOACTIVE MATERIALS 4.8 177A. Liquid Effluents A 177B. Airborne Effluents B 179C. (Deleted)D. Environmental Monitor...

3/22/12 - Updated Slides, "Containment and Containment Systems" (Redacted).

generationIContainment and Containment SystemsRedactedMarch 22, 20121 0 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. This presentation is the property of Babcock & Wilcox Nuclear Energy, Inc. I3-1ImPowerReactorContainmentBuilding][CCI per Affidavit 4(a)-(d)]...

"Containment Loads Rept,Mark III Containment," Revision 4.

. - _ -. ._1a122A4365 Rev. 4 'Class I00tKETEDJanuary 1980 |nw r. >, ,f %!Ui'82 JAN -7 A10:02i0FF:'E ~ 3E1 '-DCCKE!J31 !! P 'f!F: AliCHiCON *AIhWENT LOADS REPORT (CLR)!|MARK III CONTAINMENTii;i!Ii!:1:em''Approved: M GwCC M id -fApproved:jF. Reuter, ManagerP. P. Stancavage, Mana...

Application for amend to license NPF-3 re TS 3/4.6.1.2, containment sys,containment leakage & associated Bases 3/4.6.1.2,primary containment & containment leakage.

i.GNFENf0RW ENENC1f.300 edadison AvenueJohn P. SletrVH:e President - Nuclear3Davis-Besse;Docket Number 50-346License Number NPF-3Serial Number 2264,January 30. 1995,United States Nuclear Regulatory CommissionDocument Control DeskVashington, D. C. 20555Subj ect:License Amendmen...

Filtration of Containment Vents.

1776 I Street, NW l Suite 400 l Washington, DC l 20006-3708 l P: 202.739.8094 l F: 202.533.0147 l aph@nei.org l www.nei.org Adrian P. Heymer EXECUTIVE DIRECTOR FUKUSHIMA RESPONSE COORDINATION & STRATEGY June 14, 2012 Mr. David L. Skeen D...

Containment Liner Corrosion - Report.

CONTAINMENT LINER CORROSION Darrell Dunn, April Pulvirenti, and Paul Klein US Nuclear Regulatory Commission Washington, DC Keywords: containment, localized corrosion, concrete, steel liner Abstract Of the 104 currently operating nuclear power plants in the U.S, there are...

Containment Safety Evaluation Report.

CONTAINMENT SAFETY EVALUATION REPORTDocket No. 71-9337Model No. 3979ACertificate of Compliance No. 9337Revision No. 04. CONTAINMENT4.1. Description of the Containment SystemThe containment boundary of the Safkeg-LS 3979A package is formed from the containmentvessel (CV) flange...

Containment Design Perspectives.

12. Containment Design PerspectivesFor seven of the PWR units (four submittals) the containments are kept at an internal pressure that is somewhat below atmospheric pressure. All of these containments rely on structural strength and large internal volume to maintain containmen...

77-9051353NP-001, "Summary of FCS Containment Analysis Without Containment Spray."

LIC-07-0052Attachment 7Page 1Summary of FCS Containment Analysis without Containment SprayAREVA NP, Inc.Document 77-9051353NP-001July 2007Non-ProprietaryAAREVAFCS Document Number FC07247 Revision 077-9051353NP-001Page 1 of 39Summary of FCS Containment AnalysisWithout Containme...

"Interim Containment Loads Rept,Mark III Containment," Revision 3.

.- _ _||00'.f;E TjED22A4365 Rev. 3'' AClass I'V~ Septenber 1979*82 JM -7 N0 :020WiUDC it;g ;aINTERIM CONTAINMENT LOADS REPORT (ICLR)MARK III CONTAINMENTO-Approved:Approved:M bC W {'*-F. Reuter, ManagerP. P. Stancavage, ManagerMark III Containmen', DesignContainment Engineering...

CVTR Containment Final Report.

IN-1403"ENCE copy,.',tto. b@ 'l ffv:_ LibraryUC-80SIMULATED DESIGN BASIS ACCIDENT TESTS OFTHE CAROLINAS VIRGINIA TUBE REACTOR CONTAINMENT --FINAL REPORTR. C. Schmitt, G. E. Bingham, J. A. NorbergI.i.9qLI8RARY L L 0 ,* sWASHINGTON, 6. 205ATOP 50.t1~IDAHO NUCLEAR CORPORATIONN...

Attachment 8 - Containment Isolation.

Containment IsolationESBWRESBWR Pre-application MeetingOctober 12 and 13, 2004ESBWR Pre-application MeetingContainment IsolationContainment Isolation• The ESBWR will comply with the applicable containment isolation requirements as described in General Design Criteria (GDC) 54,...

Filtration of Containment Vents.

"Containment Bldg Design Rept."

...- __ _ _ _ _ _ _ _rLiVOGTLE ELECTRIC GENERATING PLANTL-GEORGIA POWER COMPANYr.-..j.CONTAINMENT BUILDINGDESIGN REPORT,PreparedbyBechtel Power Corporatiore, Los Angeles, CaliforniaOctober 19848411050161 841031PDR ADOCK 05000424-APDR '_ _ _ - _ _ - _ - - - - - _ _ _ _ _ _ _ _ ...

Safkeg-HS 3977A, Containment.

Safkeg-HS 3977A Docket No. 71-9338 CTR 2008/11, Rev 15 Page 4-1 CTR2008-11-R15-Sc4-v3-r.docx CONTENTS 4 CONTAINMENT ................................................................................................... 4-1 4.1 Description of the Containment System [71.33 (a)...

"Reactor Containment Bldg,Primary Containment,Integrated Leak Rate Test."

REACTOR CONTAINMENT BUILDING(PRIMARY CONTAIMENT)INTEGRATED LEAK RATE TESTglilNNt68EN|0R90NHilailNINE MILE POINT NUCLEAR STATIONUNIT 1z,zoDochti~auvÃ$<—NIAGARA MOHAWK POWER CORPORATIONJUNE 1979V909180'g~.v ~tlNIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST. SYRACUSE, N.Y....

AP1000 Containment Vessel Design.

Westinghouse Electric Company) Westinghouse Nuclear Power PlantsP.O.Box355Pittsburgh, Pennsylvania 1 5230-0355USAU.S. Nuclear Regulatory Commission Direct tel: 412-374-5355Document Control Desk Direct faxc 412-374-5456Washington, D.C. 20555 e-mail: corletmm@westinghouse.comYou...

Final draft "Containment Tech Spec."

_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ ___ __ ___ _ _ _ _ __._ _ . _ . _ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ .III..,, ,..7..-3,...., , , ., . - . . , , . - . - - , , , s.,___,.,wm....

Proposed Tech Specs re internal pressure of containment sys & containment purge supply & exhaust isolation valves.

._ ._ : _.. T'P.*\,'CONTAINMENT SYSTEMS.dBASES~__[-3/4.6.1.4 INTERNAL PRESSURE' * * * The limitations on containment internal pressure ensure that 1) thejIa* \**; ,Mcontainment structure is prevented from exceeding its design negative pressure#'bdifferential with respect to th...

"Containment Ultimate Capacity Analysis."

ANPP-30284August 20, 1984CONTAINMENT ULTIMATE CAPACITY ANALYSISPALO VERDE NUCLEAR GENERATING STATIONUNITS 1, 2, R 3AUGUST 1984eOOB670>206>880a. Governed by buckling, per ASME allowablesb. Governed byshear4'W"8 SPRINGLINE3'%"8 DOME APPEXEL213'W"SPRING LINE73'-0"R 4'W"THK5NOTE: ...

Attachment 2 - BWR Containment Venting.

BWR Containment Venting Revision 1 dated 10/29/2013 Purpose Discussion Benefits Containment Decay Heat Removal Anticipatory Containment Venting Procedure Guidance Existing Venting Capability Evaluation of the Impact of Anticipatory Containment Venting NRC Guidance on V...

Forwards evaluation of containment depressurization caused by inadvertent containment spray or air return actuation.

TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 37401400 Chestnut Street Tower IIApril 9, 1982Director of Nuclear Reactor Regulation 9 ' =Attention: Ms. E. Adensam, ChiefLicensing Branch No. 4Division of LicensingU.S. Nuclear Regulatory CommissionWashington, DC 20555Dear Ms. ...

Forwards Containment Sys Branch draft SER input re containment sys.Sys acceptable.

. - - _ . - - _ - .. - - - . - - - - . _ - - - - _ . . - - - . - - - _ _ . ---i! 1'| 1o| 'O. gy .--..9, y ., . -'?)'%'''" . w . N . Jr,''. . , , .. ~ m %.,s .w m u -- . a-.4( .,6.v .*/ g 3 g WS ,[E..>|. s.-sese m .....'j N 36-44){ [ "', , , ,,, ,m w.a _. -- - - >, ;. .. , R.%3...

Post CoC Approval Containment.

Chapter 4 – Containment Question What document, consistent with the fuel composition, specifically address the impact of the transuranic constituents in the fuel on the containment performance? Response See attachment titled “Fuel Composition” as it is also applicable to this...

Proposed tech specs 4.4 re containment tests & Table 4.4-1 re containment isolation valves.

°0 ATTACHMENT I TO IPN-97-006 PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ADOPTION OF 10 CFR 50, APPENDIX J, OPTION B PERFORMANCE BASED LEAKAGE-TEST REQUIREMENTS NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR-64 9701170262 970113 PDR A...