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IP 53051, "Containment Penetrations (Mechanical) Procedure Review."

Issue Date: 01/27/84 - 1 - 53051 NRC INSPECTION MANUAL DQASIP INSPECTION PROCEDURE 53051 CONTAINMENT PENETRATIONS (MECHANICAL) PROCEDURE REVIEW PROGRAM APPLICABILITY: 2512 53051-01 INSPECTION OBJECTIVES 01.01 To determine whether the technical requirements detai...

Proposed changes to Tech Specs 3/4.6.3,adding two existing automatic primary containment isolation valves for primary containment radiation monitor.

,.115M' A 10 yarne 3/4 6-27Primary Containment Gaseous RadioactivityMonitor Isolation ValvesInboard: T50-F450 60T50-F451 60*tOutboard: T50-F455 60[T50-F456 60i.If,;!iIi.i|i)t!i-!!|1I,ai 8802020291 880129PDR ADOCK 05000341PPDRi!)1- - _ - - _ , - . , . _ . . _ _ _ . . . _ _ _ _ ...

ITS: 3.3.6.2 Secondary Containment Isolation Instrumentation.

JAFNPP IMPROVED STANDARD TECHNICAL SPECIFICATIONS (ISTS) CONVERSION ITS: 3.3.6.2 Secondary Containment Isolation Instrumentation MARKUP OF CURRENT TECHNICAL SPECIFICATIONS (CTS) DISCUSSION OF CHANGES (DOCs) TO THE CTS NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC) FOR LESS RESTRI...

Monticello,Initiation of Containment Purge Prior to Sampling & Analysis of Containment Atmosphere in Violation of Technical Specifications,Licensee Event Report

NMC1Committed to NulearExcellMonticello Nudear Generating Plant2807 West County Road 75Monticello, MN 55362-9637Operated by Nuclear ManagementCompany LLCOctober 2, 2000US Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555MONTICELLO NUCLEAR GENERATING ...

DTE Commitment Regarding Containment Coatings.

Paul FesslerSenior Vice President and Chief Nuclear OfficerDTE Energy Company6400 N. Dixie Highway, Newport, MI 48166Tel: 734.586.4153 Fax: 734.586.1431Email: paul.fessler@dteenergy.comDTESeptember 26, 2019NRC-19-0065U.S. Nuclear Regulatory CommissionAttention: Document Contro...

Corrected pages to proposed Tech Spec changes re surveillance requirements for containment spray sys, containment fan coolers & component verification.

Containment Spray System 4.5.1.3 System tests shall be performed at each refueling interval. The test shall be performed with the isolation valves in the spray supply lines at the containment and spray additive tank blocked closed. Operation of the system is initiated by tripp...

Crystal River Unit 3 Concrete Containment Separation.

Home > Facility Locator > Facility Locator > Operating Nuclear Power Reactors by Location or Name > Crystal River 3 > Concrete Containment Separation Crystal River Concrete Containment Separation In September 2009, Crystal River Unit 3 shut down for a planned refueling out...

Proposed Tech Specs re containment airlock surveillance.

*. .CONTAINMENT SYSTEMS_CONTAINMENT AIR LOCKSLIMITING CONDITION FOR OPERATION3.6.1.3 Each containment air lock shall be OPERABLE with:a. Both doors closed except when the air lock is being used: for normaltransit entry and exit through the containment, then at least one airloc...

"Evaluation of AC-Independent Containment Spray Sys."

- _ _- .- - - ---- -1!'NUSCO 154':|!|1 IMillstone Unit 3JT; .',:! . .' i;_.. 4:'.. .,c,?:u,..%p. ; . .,.N*},jA NT ' *.. , ,'q=.~, ,g:.jggt..%%cW ea, )#'M..f. , , ./ ^ '# ~--tPREPARED BYProbabilistic Risk Assessment Section/ Safety Analysis BranchNortheast Utilities Service Co....

AN OVERVIEW OF BWR MARK-I CONTAINMENT VENTING RISK IMPLICATIONS.An Evaluation Of Potential Mark-I Containment Improvements.

e-,#:NUREG/CR-5225';,.EGG-2548Addendum 1iAn Overview of BWR Mark-1;Sontainment Venting CIRisk Implications!iocument Roominclude NRC correspondence and interna! NRC memoranda: NRC Office of inspection and Enforcementbulletins. circulars, information notices, insnection and inve...

"Reactor Containment Bldg Integrated Leak Rate Test."

REACTOR CONTAINMENT BUILDING INTEGRATEDLEAK RATE TESTUNIT 1DONALD C. COOK PLANTBRIDGMAN, MIINDIANA AND MICHIGAN ELECTRIC COMPANYAUGUST 1985WRITTEN BY: Dave ClimerDATE:12-4-858+0i290i26 86010SPDRADOCK 05000315P —.,PDR'/%3HHTN'JM7ff(JTiJllSMTABLE OF CONTENTS1.0 Introduction2.0 I...

Monticello, Additional Containment Design Information.

NNRC PORM 196 U.S. NUCLEAR REGULATORY CO !SSION DOCKET NUMBER 1.70) .W 50- 6 5 NRCDISTRIBUTION FoR PART 50 DOCKET MATERIAL FILE NUMBER TO: FROM: NSP DATE OF DOCUMENT MR V STELLO MINNEAPOLIS, MINN ?I -'l 6 L 0 MAYER d DATE RECEIVED LETTER ONOTORIZED PROP IA T FORM NUMBER OF COP...

BUCKLING OF STEEL CONTAINMENT SHELLS.Task 1A:Dynamic Response And Buckling Of Offshore Power Systems Floating Nuclear Plant Containment Vessel.

-. _!|NUREG/CR-2836LMSC D812950Vol.1, Part 1|:|Buckling of Steel Containment Shells|1Task 1a: Dynamic Response and Buckling of Offshore PowerSystems' Floating Nuclear Plant Containment Vesselepared by E. Meller, D. BushnellLockheed Palo Alto Research LaboratoryPrepared forU.S....

Dresden Nuclear Power Station, Units 2 and 3 - Atmospheric Containment Air Dilution/Containment Atmosphere Monitor System (ACAD/CAM).

_,_,_ .. ·,, ea . Commonwealth .-Son . One First National Pla9;hicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690. · · May 30, 1978. Mr. George E. Lear, Chief Operating Reactors - Branch 3 Division of Operating Reactors u.s. Nuclear Regulatory Commi...

"Reactor Containment Bldg Integrated Leak Rate Test."

-. . _ __ - . . , .-- . _ --,|[;rsREACTOR CONTAINMENT BUILDING ,INTEGRATED LEAK RATE TESTl;.it!ii:!QUAD-CITIES NUCLEAR POWER STATIONfUNIT ONE!1''DECEMBER 5-6, 1987:,.,i.-t,-,';t5!'i.!'I|.t!,Ii:,ari;i0483H/02142 .,i! 0803180044 880222i'PDR iADOCK 05000254 ~ '-|,| PDR ?P .',- --...

"Reactor Containment Bldg Integrated Leak Rate Test."

ARIZONAPUBLIC SERVICE COMPANYPALO VERDE NUCLEAR GENERATING STATION(PVNGS) UNIT 3REACTOR CONTAINMENTBUILDINGINTEGRATED LEAKRATE TESTPreparedbyBCP Technical Services, Inc.May1991''l083000ib910826PDRADOCK05000530PPDR4fi+i,iSBCP Technical Services, Inc.PVNGS Unit 3Reactor Containm...

Proposed Tech Specs re containment sys.

-. . . . . ..- -. _ - . . . . - . . . .- - _- -. . - . _ . _ _ _ _ _ _ _ _ _>1:, -.. ... ,ATTACHMENT A', .Revise ~the Beaver Valley Power Station, Unit No. 1. Proposed Technical Specification Change No. 183.,.Revise the Technical Specifications as follows:llEgmove Paces. Inser...

Forwards summary of secondary containment test on 910816. Secondary containment demonstrated operable per TS 4.7.C.1.c.

/ 1n cb;/my c:mm:nwealth Edistn . - >.\{-}})r /c'1400 Opus PlaceW]g j-' --Downers Grove, lilinois 60$15(., m, m ,-\6f~,August 30,1991Oldg% ,7ibr ~DMr. A. Bert DavismN-.);eRegional Administrator 'CU.S. Nuclear Regulatory Commission799 Roosevelt Road-RillGlen Ellyn,11- 60137-Sub...

"Containment Control Emergency Procedure."

Submittcd tSP Numbar 29.023.03(Section hard)*App oved.Revision: C(Plant Manager)Effective Date.-CONTAINMENT CONTROL EMERCENCY PROCEDUREiI+.bia.1.0 PURPOSEThe purpose of this procedure is to control primary containmest temperatures,pressure and level. This procedure will be per...

Forwards results of secondary containment leak rate test performed on 910105 for preliminary verification of secondary containment boundary.

. - - - _ _ . . _ . . - . - _ . . _ - . _ . . - ..- - . . - _ _* 't . ,..nnTennet. nee Va' icy Avt'onty i101 Mrket Street Chattancoga. Terrenec 37402MAR 131991U.S. Nuclear Regulatory CommissionATTN Document Control DeskWashington, D.C. 20555Gentlemen:In the Matter of )Docket N...

Integrated Primary Containment Leak Rate Test.

.UNIT 2/3 INTGRATED PRIMARY CONTAIMENTLEAK RATE TEST Ap 1971PURPOSEThe purpose of this procedure s to detail the steps necessary todetermine the integrated primary containment leak rate (Type A-test)-REFERENCES1. -Oresden Nucleart Power Station, Units 2 3 Final Safety* _ analy...

Proof & review combined TS 3.6.1.2 re containment leakage rates & 3/4.6.1.2 re limitations on containment leakage rates.

. . -i', : Attachment to TXX 92407 -Page 1 of 3hh-CONTAINi?ENT SYSTEMSCONTAINMENT LEAKACE$h$YLIMITING CONDITION FOR OPERATivN_3.6.1.2 Containment leakage rates shall be limited to:a. An overall integrated leakage rate of([essthanorequaitol,,0.10%byweightofthecontainment_~1)air...

"Reactor Containment Bldg Integrated Leak Rate Test."

CAROLINA POWER AND LIGHT COMPANYSHEARON HARRIS NUCLEAR POWER PLANTREACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTOCTOBER 1989~2Pg(jpgg900125900DO~y0500g400-PDRpDCPI IgpllgVdS] confidence. interval is 0 '0414o-byweight per day which is below the allowable leakagerate of 0...

"Reactor Containment Bldg Integrated Leak Rate Test."

' •' •• 1. 0 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM UNIT II PURPOSE The purpose of this report is to vresent a description and analysis of the Third Period, Fi~st Interval, Reactor Containment Building Integrate...

Transmittal of Reports on "Substantially Complete Containment."

FEB 1.3 1KK/SCC TO DOEv .1~ - 1 -Mr. Dwight E. Shelor, Acting Associate Directorfor Systems and ComplianceOffice of Civilian Radioactive Waste ManagementU. S. Department of Energy, RW 30Washington, D.C. 20585`-' 89001264Dear Mr. Shelor:SUBJECT: TRANSMITTAL OF REPORTS ON 'SUBST...