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CONTAINMENT LOADS DUE TO DIRECT CONTAINMENT HEATING AND ASSOCIATED HYDROGEN BEHAVIOR.Analysis And Calculations With The CONTAIN Code.

. - _=*'.NUREG/CR-4896|SAND 87-0633'R4'Prinied May 19871||Containment Loads Due to Direct!Containment Heating and AssociatedHydrogen Behavior: Analysis andCalculations With the CONTAIN Code l|D. C. Williams, K. D. Bergeron, D. E. Carroll, R. D. Gasser,J. L. Tills, K. E. Washin...

"Reactor Containment Bldg Integrated Leakage Rate."

__ _ _ . _ _ _ _ _ _ _ _ _ _ _ . - _ --. _ _ . . _ . _ - _ _ . ._ __. _._ _ _ _ .__. _. .-. ., ,,, .( ']-*g..-':.;. . . .i;>i,!Il.:),;iREACTOR' CONTAINMENTBUILDINGj'INTEGRATEDLEAKAGERATE!i.,iv,J U N E.,1989 ii-je-|. c.!'.Y',L.Lje"s.**1mi.)um-O'i.~t......f A _ _r:N. !t..-D. C. ...

Columbia Generating Station, Calculation, "Secondary Containment Drawdown".

BDC/PDC PageX ENERGY CALCULATION PDC 2406/NORTHWEST COVER SHEETPeople -Vision -Solutions ORIGI NALEquipment Piece No. Project Page Cont'd on PageColumbia 1.0 1.1Discipline Calculation No.Secondary Containment NE.02-01-05Nuclear Quality Class39.0 Standby Gas Treatment System iR...

Regulatory Information Conference 2012: Regulatory Actions Regarding Containment Venting and Filtration (TH34). Containment Filtered Venting in Swedish BWR Mark II.

Regulatory Information Conference 2012 Regulatory Actions regarding Containment Venting and Filtration (TH34) Containment Filtered Venting in Swedish BWR Mark II Lars Gunsell Swedish Radiation Safety Authority Content Background Design requirements Arrangements on site De...

LER 03-003-00 for Sequoyah Nuclear Plant Unit 2 re Excessive Leakage of Containment Purge System Containment Isolation Valve.

April 23, 2003 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 2 - DOCKET NO. 50-328 - FACILITY OPERATING LICENSE DPR-79 - LICENSEE EVENT...

RELIABILITY ANALYSIS OF CONTAINMENT ISOLATION SYSTEMS.

'| .NUREG/CR-4220I'PNL-5432 jReliability Analysis ofContainmentIsolationSystems|_Prepared by P. J. Pelto, K. R. Ames, R. H. GallucciPscific Northwest LaboratoryOperated byBattelle Memorial InstitutePrep:rsd forU.S. Nuclear RegulatoryCommission8506260362 050630""PDRc -422Rk.,eN...

"Containment Vessel Structural Integrity Test for Westinghouse."

REPORT ON CONSOLIDATED EDISON'S INDIAN POINT UNIT NO. 2 CONTAINMENT VESSEL STRUCTURAL INTEGRITY TEST FOR WESTINGHOUSE ELECTRIC CORPORATIONPREPARED BY UNITED ENGINEERS & CONSTRUCTORS INC. PHILADELPHIA, PENNSYLVANIA 19105MAY 28, 19713843II '8111140197 710528 PDR ADOCK 05000247 ...

Davis-Besse Station, License Amendment 202, Amendment Revises TS 3/4.9.4, Refueling Operations - Containment Penetrations; Bases 3/4.9.4, Containment Penetrations;

November 17, 1995Mr. John P. Stetz Vice President- Nuclear Centerior Service Company c/o Toledo Edison Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449Distribution wj Docket File PUBLIC PD3-3 Reading JRoe WAxelson, RIIIencl s: GHill (2) C...

DC Cook Resolution of Containment Structural Issues

November 3, 2000Mr.R.P.PowersSenior Vice PresidentNuclear Generation GroupAmerican Electric Power Company500 Circle DriveBuchanan, MI 49107-1395SUBJECT: RESOLUTION OF CONTAINMENT STRUCTURAL ISSUES ATDONALD C. COOK PLANT UNITS 1 AND 2Dear Mr. Powers:This letter acknowledges rec...

"Containment Purge Sys Interim Operation Plan."

. .-4- ..-1-..ATTACHMENT CCONTAINMENT PURGE SYSTEMINTERIM OPERATION PLAN!71l!i|-|-|||October 27, 1983|-,-7510N-|8311030186 831027~ ~ ~PDR ADOCK 05000454A PDR_.,,. - . . . . . . _ . - , .. __ _... _ . _ _ . __ . . . _ . _ _ . . . _ _ _ . _ , . . . . . . _ _ . - _ . _ _ _ _ _ . ...

"Primary Reactor Containment Integrated Leakage Rate Test."

- - - - - _ _ _ .O,.,/ ARKANSAS POWER AND LIGilT COMPANYARKANSAS NUCLEAR ONE UNIT 1DOCKET NUMBER 50-313PRIMARY REACTOR CONTAINMENTINTEGRATED LEAKAGE RATE TESTFEBRUARY 25, 1981iGJlSubmitted ToThe United States Nuclear Regulatory CommissionPursuant To ,|Facility Operating Licens...

Kewaunee, Amendment, Containment Isolation Devices (TAC MA8017)

June 8, 2001Mr. Mark ReddemannSite Vice PresidentKewaunee and Point Beach Nuclear PlantsNuclear Management Company, LLC6610 Nuclear RoadTwo Rivers, WI 54241SUBJECT: KEWAUNEE NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENT (TAC NO. MA8017)Dear Mr. Reddemann:The U.S. Nuclear...

"Reactor Containment Bldg Integrated Leakage Rate Test."

REACTOR CONTAINMENT BUILDINGINTEGRATED LEAKAGE RATE TESTNOVEMBER,1988/.>+w:m- > ~ ~- .-c_ ,. N ~ 7, m- e .-,p7 -._...vQ- ~"" _ _. ..-.__,S -- rs*c v- m .._,,,,,sn.--. _ . _ _ _ _y. ,._ --% , . . m.C$mh%x-- y 4 -.,--L>"''--._..m- _ _ _ - _%C.3, %_ _._... " .. .- " ,-_- R.~t - =...

Proposed Tech Specs re containment ventilation sys.

OCNTAIN!-ENT SYSTEM-'S C:'~T2NVENT vTLT:N SYSTEM L:I*ITING CONDITION FOR OPERATION 3.6.1.7 Containment purge supply and exhaust isolation alve s h'1 be OPERABLE and: a. Each 42-inch containment purge supply and exhaust isolation valve shall be sealed closed. b. Each 8-inch co...

Rev 4 to "Evaluation of Containment Coatings."

_ _ _ _ _ _ _ _a ,REPORT NO. DECO-12-2191|REVISION 4mJUNE 1985ENRICO FERMI ATOMIC POWER PLANTUNIT NO. 2EVALUATION OFCONTAINMENT COATINGSgBS7 ABYc" SS8'ySgMULTIPtDYNAMICS CORPORATION-- - _ - - --._ _ _ _s ,|THE DETROIT EDISON COMPANYFERMI 2 NUCLEAR POWER PLANTEVALUATION OFCONTA...

Forwards design info for NUREG-0737 Items II.F.1.4, "Containment Pressure Monitors," II.F.1.5, "Containment Water Level Monitors" & II.F.1.6, "Containment Hydrogen Monitors."

REGULATORY INFORMATION DISTRIBUTION SqCTEM (RIDS).ACCESSION NBR:8201110605 DUCDATE: 81/12/31 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION MAYERL,O. Northern States Power Co. RECIP.NAME RECIPIENT AFFILIATION Office...

"Reactor Containment Bldg ILRT."W/910115 ltr.

.- . . - . . - . . . . _ . - - . . -. .VIROINIA ell:CTHIC AND POWI:H CO)!PANYHicti>toxu,Vruoixir ununJanuary 15,1991U.S. Nuclear Regulatory CommissionSerial No. 91 016Attention: Document Control DeskNAPS /JHL R0Washington, D. C. 20555Docket No. 50 339License No. NPF 7Gentlemen...

Rev 1 to "Containment Recirculation Sump Evaporation."

b b.b.|Page 1 of /dNORTHEAST UTILITIESTotal Number of Document Pages /d~ ~ """" ~ ~''9[$ N O U U I.*n"en'''.|||''~"gO^g*m".'"Totet Naber of Appendia Pages- - s,. $,e.,,,-y_,CALCULATION TITLE PAGECalculation Number : 6787'/8-/243 'NRevision No. :ITITLE :n,,|M e| ce|rz/JJhmDb'AM...

"Reactor Containment Bldg Integrated Leak Rate Test."

. _ _. _ _ _ . . _ _ _ . _ _ _ _ . _- . . ._ _ _____ .J ', . -'.,..- -R. E. GINNA.NUCLEAR POWER STATION1:1 ...: i. :., :) %REACTOR CONTAINMENT BUILDING ,c. . n.. . - 1-||'... ,INTEGRATED LEAK RATE TEST -,an !|-,..:n-'FEBRUARY,1976--.. - . --ICfL-.=,._-[.'*. .ROCHESTER GAS & EL...

Revision 3 pages to 22A4365, "Interim Containment Loads Rept - Mark III Containment," nonproprietary version.

NUCLE AR ENERGY BUSINESS GROUP + GENER AL ELECTRIC COMPANYSAN JOSE, CALIFORNI A 95125hD ggGENERAL h ELECTRICAPPLICABLE TO:22A4365PU8LICATION NO.T.1. E. NO.S EHTITLEInterim Containment Loads Reportj"*November 21,1979DATENOTE: Correct all copies of the applicableNovember 20,1979...

Proposed TS 3.3.3.1,Table 3.3-6,revising alarm setpoints for in-containment high range monitors & containment purge monitors.

. . - .. - .-_ _ - -. .- _- --.- ._ . -- . _ -- _.-.. . .'ATTACHMENT A*-,! Beaver Valley Power Station, Unit No. 2i Proposed Technical Specification Change No. 103il.The following is a list of the affected pages:Affected Pages:3/4 3-403/4 3-413/4 3-42;;|4<1.?9603200013 960311P...

"Reactor Containment Bldg Integrated Leak Rate Test."

-.4CAROLINA PONER & LIGHTBRUNSWICK STEAM ELECTRIC PLANT.UNIT 2REACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTJULY, 1982GP-R-74002.PREPARED BY4. ERNEST D. LEVINSONGENERAL PHYSICS CORPORATION.08306240012 830621PDR ADOCK 05000324P PDR---_ _ _ _ - - _ - . - .,._,GP-R-74002GE...

Proposed Tech Specs re containment isolation valves.

ATTAcitMINT IPit 0 POSED CitANGES TOTECHNICAL SPECITICATIONSl|19004120217 900329FDRADOCK 05000413 /\{P 'PDC._. -_ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.i ,!-'*OtFINIT! " .'IPIA*j|*.7 CONTA!WWff INTEGR!TY shall exist when:|8e17a. All penetrations req...

"Reactor Containment Bldg Integrated Leak Rate Test."

_-- - - ---'.,,, .e,- , . . .... .DONALD C. COOKNUCLEARPLANT||UNIT 1|INDIANA & MICHIGANPOWER COMPANY||||~~~.INGTHE ATTACHED FILES ARE OFFICI AL RECORDSOF THE OFFICE OF REGULATION. THEY HAVE[BEEN CHARGED TO YOU FOR A LIMITED TIMEPERIOD ANS MUST BE RETURNED TO THE'CENTRAL RECORD...

"Reactor Containment Bldg Integrated Leak Rate Test."

_ - _ . _-. -, . . . . ,,, ) |\'i'*,4 BRUNSWICK' STEAM ELECTRIC PLANTUNIT NO. 1REACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTMAY 1987 ..l..CAROLINA' POWER & LIGHT COMPANY'l'lPrepared by:John J. BlessingE. S 4dk- Reviewed by:ILRT EngineerApproved by: '[z1/I. Mdev' f %SM ...