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An Independent Critique of Containment Loads Modeling Used in the Direct Containment Heating (DCH) Issue Resolution Effort-S100893

An Independent Critique of Containment Loads Modeling Used in the Direct Containment Heating (DCH) Issue Resolution Effort" David C. Williams March 9,1997 ABSTRACT The U.S. NRC's program to resolve the DCH issue depends primarily upon the two-cell equilibrium (TCE) and convect...

Sequoyah, Units 1 & 2, License Amendments 130 & 117, Modifies Sections 1.0, Definitions, and 3/4.6.1, Primary Containment of TSs, Revise Definition of Containment Integrity and Surveillance Requirements 4.6.1.1.b and 4.6.1.2.f for Containment Air Locks.

Doc'2.4C, Oi, C.C, C0 00 C!.Fehruiarv 16. 1990ket Nos. 50-327 . and 50'328 Mr. Oliver D. Kingsley, Jr. Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Dear Mr. Kingsley: SUBJECT: CONTA...

Monticello, Relief, Containment Inspection Examination Plan, MA9104

November 16, 2000Mr. Michael F. HammerSite General ManagerMonticello Nuclear Generating PlantNuclear Management Company, LLC2807 West County Road 75Monticello, MN 55362-9637SUBJECT: MONTICELLO NUCLEAR GENERATING PLANT - EVALUATION OF REQUESTFOR RELIEF FROM CERTAIN ASME CODE RE...

Removal Of Iodine and Particles From Containment Atmospheres - Containment Systems Experiments, Pacific Northwest Laboratories report, BNWL-1244

t ' * k, *" , * 1 -. " - . "... . BATTELLE MEMORIAL INSTITUTE PACIFIC BATTELkE BOULEVARD, P 0. BOX 999, RlCHL 4. . 3 3679 00061 6393 BNWL-1244 UC-41, Health and Safety REMOVAL OF IODINE AND PARTICLES FROM CONTAINMENT ATMOSPHERES BY SPRAYS-- CONTAINMENT SYSTEMS EXPERIMENT INTER...

Draft "SBWR Containment Natural Aerosol Removal" rept.

.-|.DRAFTSBWR. CONTAINMENTNATURALAEROSOL REMOVALPrepared by:David E. LeaverPolestar Applied Technology,Inc.4 Main St.Los Altos, CA 94022Jun LiTENERA, L.P.1340 Saratoga-Sunnyvale Rd.San Jose, CA 95129Rudolph SherRudolph Sher Associates740 Mayfield Ave.Stanford. CA 94305YPrepare...

BUCKLING EVALUATION OF SYSTEM 80+(TM) CONTAINMENT.

_NUREG/CR-6161I3-5103.Buckling Evaluation ofSystem 80+m Containment' * * * ' ". - _ __Prepared byL Greirnann. E Fannus. S. Safar, R. Challa, D. Bluhm>Ames LaboratoryIowa State UniversityPrepared forU.S. Nuclear Regulatory CommissionEsA288u 02888a02APDR- _ _ _ _ _ _ _ _ _ - - _...

"Reactor Containment Bldg Integrated Leak Rate Test."

--O:: =.,a eut.cuni .svu.= - - .c.aOYSTER CREEKNUCLEAR GENERATING STATION$i$SGMARY TEGEICAL REPORTPROVISIONAL OPERATING LICENSE NO. DPR-16REACTOR CChTAIMENT BUILDING IhTEGR/~2DLEAK RATE TESTNOVBBER 197879031207&31 -_ _ _ .REACIOR CONIADNENT BUILDING INTEGRATEDLEAK RATE TESTNOV...

"Primary Reactor Containment Integrated Leakage Rate Test."

OARKANSAS POWER & LIGHTARKANSASNUCLEAR ONEOUNIT 2PRIMARY REACTOR CONTAINMENT!INTEGRATED LEAKAGE RATE TESTORsAis88Poiss8E .P PDR'i. . . - - - . . - _ _ , _ - . _ . . - - . - - - - . - - _ . . - - - _ - . . . . - . . _ . _ _ . - _ . . . . _ _ . . _ - . . - - . - .. -_OARKANSAS P...

"Primary Reactor Containment Integrated Leak Rate Test."

, _ _ __ _ .. _ . - . ._---OONUh'' -Rev. 2.:. .:. . -f A! ASAMA PC'

Oyster Creek Secondary Containment Capability Results.

AmerGenSM AmerGen Energy Company, LLC An Exelon/British Energy Company Oyster Creek US Route 9 South PO Box 388 Forked Rwer, NJ o8731-0388 Technical Specification 4.5.G September 30, 2002 2130-02-20279 US Nuclear Regulatory Commission Attention: Document Control Desk Washingto...

Tech Specs re containment sys air locks.

COHTAIHMEHT SYSTEMS~ ...COHrAIHMEHT AIR LOC St )lliiF5I'L'"P3glith the containment air lockinoperable,except as tt e result of aninoperable air lock door, maintain at least one air lock door closed,restore thc inoperable air lock to OPERABLE status within 24 hoursor be in at l...

Palisades - Conduct of Containment Leak Testing.

__ ,., • • September 11, Mr Karl L. Goller Division of Reactor Licensing US Nuclear Regulatory Commissi Washington, DC 20555 DOCKET 50-255, LICENSE DPR-20 - PALISADES PLANT consumers Power company By letter dated August 4, 1975 you noted that 10 CFR 50, Appendix J, was publish...

"Reactor Containment Bldg Integrated Leakage Rate Test."

-- . .: 3. .:,,. . . - - - _._ -. . . . - . - - __ _ _ _-.._._,- _,.-_____ .. .s+a ap % :, .' , .i.n ;!? y% w, ,Y, , ,A,i?-''L--.g ). Wi+ (E.?'j,-f = / * ' ;.n -f f,t *\,,-. ,. . - ,JAFP 90-0742 ",,,-. gb 4gg '.; 'f, r, .,y'qv ,ATTACEMENT (1). ',1.- i ,,. > . ,., [|$i it*3., -...

0519 - R304P - Westinghouse Technology 5.6 Containment Penetration and Isolation Systems.

Westinghouse Technology Systems Manual Section 5.6 Containment Penetrations and Isolation Systems USNRC HRTD 5.6-i Rev 0408 TABLE OF CONTENTS 5.6 CONTAINMENT PENETRATION AND ISOLATION SYSTEMS ................... 5.6-1 5.6.1 Introduction ...................

"Liaison to Foreign Containment Research Containment Pool Dynamics,Discussion of Activities,Goals & Issues."

F*..LIAISON TO FOREIGN CONTAINMENT RESEARCHCONTAINMENT POOL DYNAMICS.A Discussion of Activities, Goals, and IssuesEdward W. McCauley..Lawrence Livermore National LaboratoryUniversity of CaliforniaLivermore, California.t;January 29, 1981.r~8702050263 870120PDRFOIAMORROW 85-702P...

03/05/08-Summary of Open and Closed Meeting with GEH on Containment Design Features and Containment Pressure Analysis.

March 19, 2008 APPLICANT: GE-Hitachi Nuclear Energy Americas, LLC PROJECT: Economic Simplified Boiling Water Reactor (ESBWR) Design Certification SUBJECT: SUMMARY OF MARCH 5, 2008, OPEN AND CLOSED MEETING WITH GE-HITACHI NUCLEAR ENERGY AMERICAS, LLC ON CONTAINMENT DES...

"Reactor Containment Bldg Integrated Leak Rate Test."

1--1'.i-- - - - - - - - .'s;asfek',.(j---- - __ __- _"9304300372 930424PDR ADOCK 050003734PDR-_ - . - ,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-_..LASALLE COUNTY NUCLEAR STA TIONUNIT 1REACTOR CONTAINMENT BUILDINGINTEGRATED LEAKRATE TEST<- _ _ _ _ _ _ _ .. . _ _ _ ...

LER 88-010-00:on 880421,containment ventilation isolation initiated by high containment radioactivity signal.Caused by gases being forced out of reactor vessel into containment. Temporary procedure implemented.W/880520 ltr.

_ _ _ _ _ _ _ _ _ _ _'elDC Pere 338 U 8 IruCLEMI AEQULATOaY CQamsenssom#A79eovi0 osse eso 31to-c104LICENSEE EVENT REPORT (LER)" ' * ' ' " " ' *.ACE 3TY NA888 til DoCati esbee84 A (21PAGE63Troian Nuclear Plant 0|5i01 0 [ 0 l 314 | 4 1 |0F| 012firts i eContainment Ventilation Is...

R E Ginna. Request relief, Containment Insp

March 21, 2000Dr. Robert C. MecredyVice President, Nuclear OperationsRochester Gas and Electric Corporation89 East AvenueRochester, NY 14649SUBJECT REQUESTS FOR RELIEF NOS. 09 THROUGH 13 FROM THE AMERICANSOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSELCODE (ASME CODE...

"Reactor Containment Bldg Structural Integrity Test."

- - - - - - .- . - - - - - - - - - - - - - -CRYSTAL RIVER UNIT/-NUCLEAR GENERATING PLANT,REACTOR CONTAINMENT BUILDING-STRUCTURALINTEGRITY TESTW .-,.-..'PREPARED FOR: IFLORIDA|-,i POWER,i |CORPORATIONj;'(;8003120 Pfg'gGilbert / Commonwealthn.-.---.. -..to-- -_ . --. . . - _ . ....

Revised Procedure 4000, "Containment Bldg Pressure Test."

m*,s'.. . -GEOfGIA TECH RESEARC11 REACTORChapter Procedure 40006 Approved 3-10-72Maintenance CONTAINMENT BUILDItG PRESSURE TEST Latest Rev. 4-19-84& Testing Page 1 of 19ObjectiveMonth and YearThe objective of this test is to accertain the ability of thebuilding containment nys...

Forwards "Reactor Containment Bldg Integrated Leak Rate Test," containing results of Type A,B & C containment tests during refueling outages.

William J. Cahill Vice President Consolidated Edison Company of New York, Inc. 4 Irving Place, New York, N Y 10003 Telephone (212) 460-3819 January 29, 1980 Re: Indian Point Unit No. 2 Docket No. 50-247 Director of Nuclear Reactor Regulation ATIN: Mr. A. Schwencer, Chief Oper...

"Reactor Containment Bldg Integrated Leak Rate Test."

0O5 160 DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 1 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST MAY 1980DUKE POWER COMPANY Oconee Nuclear Station Unit 1 Reactor Containment Building Integrated Leak Rate Test Prepared by: 1 . Walter G. NeumaA, III Ass't Engineer...

Forwards "Containment Vessel Evaluation of Dome Liner & Studs," re SEP Topic III-7.B, "Load Combinations (Containment Liner Analysis)."

I '4„~~sREGULATOR) FORMATION DISTRIBUTION S EM,(RIDS)'ACCESSION NBR:8305060271 DOC ~ DATE: 83/04/28 NOTARIZED: NO DOCKETFACIL:50 244 Robert Emme,t Ginna Nuclear Plant~ Unfit ii Rochester G 05000244'AUTHBYNAMEAUTHOR AFFILIATIONMAIERgJ,E ~Rochester Gas 8 ElectricCorp'ECIP~NAME R...

Discusses TMI-2 containment isolation.Suggests that open containment ventilation valves could have caused greater radioactive release.Requests review.

- . - -'''. . --I"' . , *. , *g" " %,'c,;s. v.- UNITED STATEST' NUCLEAR REGULATORX COMMISSION"3@'kq.[,/%96*,yE W ASHIN GTON,0.C. 20555'/.....7 ,!OFFICE OF THECOMMISSIONER {iJune 4, 1979-.MEMORANDUM FOR:Harold Denton,fDirector, Nuclear Reactor Regulation'FROM:Commissioner Gilin...