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"Containment Loading for Severe Accidents in BWRs w/Mark I Containment."

.h ..BNL Informal ReportLimited Distribution.CONTAINMENT LOADING FOR SEVERE ACCIDENTSIN BWRs WITH A MARK-I CONTAINMENT..4. R. Derkins, W. T. Pratt, and G. A. GreeneDepart. lent of Nuclear EnergyBrookhaven National Laboratory!!Dton, NY 11973 s., . -s-tNovember 19P4a* epared for...

"Secondary Containment Leak Rate Test."

TENNESSEE VALLEY AUTHORITYDivision of Nuclear OperationsSECONDARY CONTAINMENT LEAKRATE TESTBROMNS FERRY NUCLEAR PLANTUNIT 3CONDUCTED AUGUST 22, 1979DxhokP ~,<>~Csutretd 7P>< ~>~~/8BN~PNIRMNNQQY 90CQl fjgSubmitted toThe United States Nuclear Regulatory CommissionPursuant toFaci...

Proposed Tech Specs re containment vacuum sys.

ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES e TECHNICAL SPECIFICATION TABLE OF CONTENTS SECTION 3.15 DELETED 3.16 EMERGENCY POWER SYSTEM 3.17 LOOP STOP VALVE OPERATION 3.18 MOVABLE INCORE INSTRUMENTATION 3.19 MAIN CONTROL ROOM BOTILED AIR SYSTEM 3.20 SHOCK SUPPRESSOR...

FLOW DIAGRAM CONTAINMENT HYDROGEN CONCENTRATION MEASUREMENT & POST ACCIDENT CONTAINMENT VENTING SYSTEM.

114' HOWE. #24i3XI3 WITH 3" LONG WELDING FXTENSION. (TYP.VOr? 3)-GENERAL NOTES: i- ALL PIPING IS IN ACCORDANCE WITH SPEC. 6604-104-248-4 CLASS 15IR & 153R AS NOTED. 2-A DENOTES CONTAINMENT PENETRATION. 34-1 =CONTAINMENT ISOLATION SIGNAL. 5- HAND OPERATOR SHALL BE ADDED TO A...

Forwards addl info re Items II.F.1.4, "Containment Pressure Monitor," II.F.1.5, "Containment Water Level Monitor," & II.F.1.6, "Containment Hydrogen Monitor."

~*.ARKANSAS POWER & LIGHT COMPANYPOST OFFICE BOX 551 Lir'LE ROCK, ARKANSAS 72203 (501) 371-4000July 26, 1982OCAN078223Mr. Darrell G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C. 20555Subject: Arka...

Abnormal Occurrence Primary Containment Leakage.

AEC STBUTIN FOR PART 50 DKET 1AL W ~(TEMPORARY FORM) W4683CONTROL NO:FROM: Northern States Power Company Minneapolis, Minn. 55401 Mr. L.O. MayerTO: J.F. O'LearyDATE OF DOC 5-24-74FILE:DATE REC'D 5-28-74LTR MEMO xt IORIG1 signedCC I OTHERRPT OTHERSENT AEC PDR XXX SENT LOCAL PDR...

Redline SRP 3.8.1 Concrete Containment.

Revision 3 - May 2010 USNRC STANDARD REVIEW PLAN This Standard Review Plan, NUREG-0800, has been prepared to establish criteria that the U.S. Nuclear Regulatory Commission staff responsible for the review of applications to construct and operate nuclear power plants intend...

Forwards LER 97-001-00,re containment structure where internal containment structural members could have damaged containment liner during safe shutdown earthquake.

- _ . - _- . ._ _|.Wisconsin*ElectncPOWER COMPANYFPoint Beoch Nuclear Plant(414) 755-23216610 Nuclear Rd., Two Rivers. WI 54241 cc: NRC Resident InspectorNRC Regional Administrator9702110460 970206PDR ADOCK 05000301S PDRbhNA subsMhn af Hinwsh Ency Gepuativi

ITS: 3.6.3.1 Primary Containment Oxygen Concentration.

JAFNPP IMPROVED STANDARD TECHNICAL SPECIFICATIONS (ISTS) CONVERSION ITS: 3.6.3.1 Primary Containment Oxygen Concentration MARKUP OF CURRENT TECHNICAL SPECIFICATIONS (CTS)K5f, e- e- C ik I70 V%~SOxygen Concentration1 t{o S .o(" ,. T h ma be a.. b.JAFNPP 'F, (O. . }- . (Oxygen...

Provides update of containment bldg seismic capacity, including seismic reanalysis of Unit 2 containment bldg fragilities.Reanalysis results indicate possibility of containment failure due to seismic event eliminated.

CONSOLIDATED EDISON COMPANY OF NEW YORK, INC. 4 IRVING PLACE NEW YORK, N.Y. 10003 POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMBUS CIRCLE NEW YORK, N.Y. 10019 February 4, 1983 Re: Indian Point Unit No. 2 Docket No. 50-247 Indian Point Unit No. 3 Docket No. 50-286 Director...

Proposed Tech Specs for containment pressure monitor & containment water level monitor.

.-w, . .ATTACHMENTConsumers Power CompanyBig Rock Point PlantDocket 50-155..eT|PROPOSED TECHNICAL SPECIFICATION PAGE CHANGESJuly 19, 1985||t1!,18507250108 850719PDR ADOCK 05000155p PDR3 PagesIC0785-0239-NLO4, . *," *.60~6.3.2 Refueling Operation ControlsInterlocks shall be pro...

Technical Specification Change Request NPF-38-226 Containment Building Penetrations During Core Afterations and Irradiated Fuel Movement in Containment

Entergy Operations, Inc. 17265 River Road Killona, LA 70066 Tel 504 739 6242 Early C. Ewing III Director, Nuclear Safety Assurance Waterford 3 W3FI-99-0122 A4.05 PR January 12, 2000 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Subject:...

Proposed tech specs re instrumentation that initiates primary containment isolation & initiates or controls core & containment systems.

, -- - -0||1ATTACHMENT B BECO LETTER 94-097AMENDED TECHNICAL SPECIFICATION PAGESPAGE,\1454868|i||||9409130402 940906PDRADDCK 05000293PPDR.._ _m _ _ _ ..PE(PS TABLE 3.2.AINSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION .Operable Instrumentchannels Per Trip System (1...

Proposed tech spec 3.9.4, "Containment Penetrations," allowing containment personnel airlocks to be open during core alterations & movement of irradiated fuel in containment provided certain conditions met.

*.AFACIIMENT (1)UNIT 1TECIINICAL SPECIFICATIONREVISED PAGES3/48-63/48-73/4 8-103/4 8-113/4 8-163/49-33/49-4).3/49-5lBASES 3/4 9-1'dd!|9311170054 931105'"fDRADOCK 05000317PDR..~_ _ _ _ _ _ _ _- - . . ._. ~ . . . . -- - - ._;1:]1 .I(3/4.8 ELECTRICAL POWER SYSTEh5i' :|'I3/4.8.1 A...

DG-1203, Containment Performance for Pressure Loads.

DG-1203, Page 1 U.S. NUCLEAR REGULATORY COMMISSION December 2008OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 DRAFT REGULATORY GUIDE Contact: S. Shaukat(301) 251-7646 DRAFT REGULATORY GUIDE DG-1203 (New Regulatory Guide) CONTAINMENT PERFORMANCE FOR PRESSURE LOADS A. INT...

Proposed tech specs bases 3/4.6.2.1, "Containment Spray Sys," clarifying LCO for operation for containment spray sys.

Attachment BPG&E Letter DCL-98-045MARKED-UP TECHNICALSPECIFICATION BASES PAGERemove Pa eB 3/4 6-3~Insert Pa eB 3/4 6-398033i0085 9803i8PDR ADOCK 05000275PPDRCONTAINMENT SYSTEMBASES3 4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS3 4.6.2.1 CONTAINMENT SPRAY SYSTEMThe OPERABILITY of ...

Proposed tech specs making TS 3.6.2.2 & Surveillance Requirement 4.6.2.2 consistent w/containment cooling assumptions in Waterford 3 containment analysis.

_ . . . _ . _ _ _ _ - - _ _ _ _ _ . _ _ _ _ . . _ _ . _ _ _ _ . _ _ _ _ _ . _ . _______.7i-:-.--\il*!CONTAINMENT SYSTEMSi |-BASES,i3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM (Continued)

0519 - R304P - Westinghouse Technology 5.3 Containment.

Westinghouse Technology Systems Manual Section 5.3 Containment USNRC HRTD 5.3-i Rev 0101 TABLE OF CONTENTS 5.3 CONTAINMENT ............................................................................................ 5.3-1 5.3.1 Introduction ...............

Proposed Tech Specs re containment isolation valves.

CONTAINMENT SYSTEMS CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containl'lent isolation valves specified in Table 3.6-1 shall be either OPERABLE with isolation times as shown in Table 3.6-1 or administratively maintained closed. APPLICABILITY: MOD...

Containment Standard ITAAC for Jan 21.

ITAAC C01, C02, & C08 were moved to the structural section S0 No. ITAAC Category/Type Design Commitment Inspections, Tests, Analyses Acceptance Criteria C03 As-built Inspection Containment Combustible Gas Control – Location The [XXX system] controls the combustible gas conc...

Early Containment Failure Considerations for Brunswick.

3/25/2004Early Containment Failure Considerations for Brunswick1. Early containment failure by liner melt-through can be dismissed at Brunswick becauseof its unique design (full concrete containment that backups up the steel liner). This isconsistent with the IPE and IPE SER./...

Callaway Plant - Proposed Revision to Technical Specification 3.9.4 "Containment Penetrations," 3.3.6 "Containment Purge Isolation Instrumentations" & 3.3.7 "CREVS Actuation Instrumentation."

One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166-6149 314.621.3222June 17, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P 1-137 Washington, D.C. 20555-0001Gentlemen:ULNRC-04674VAmeren ffUnion ElectricDOCKET NUMBER 50-48...

"Containment Venting:Responses to NRC Staff Questions."

- -. ."ov~ -.,. ,,.'", , .-.W, .2.. ...Containment. Venting:-'Responses to $RC Staf~ Questions...'Submitted'' y- e.The^BWR Owners; Group'-.to-'. ;. .. Tae NRC ~ Staff.' *~ , ,.. ....('. o,,..4e4 .D h9,.yet644 . y. . ., ,(" J.'A..' [.,., _ a.. ..-.,'i'^,*!.ui .'; i--x,, ,------...

Proposed TS 3/4.6.1.3, "Containment Airlocks."

- . . . .- . - . . .-I.DPR-663/4.6 CONTAINMENT SYSTEMS1BASES'I,|3/4.6.1 PRIMARY CONTAINMENTi3/4.6.1.1 CONTAINMENT INTEGRITY||PrimaryCONTAINMENT INTEGRITY ensures that the release of radioactivei1 materials from the containment atmosphere will be restricted to those ;Ileakage p...

Proposed Tech Specs,changing Table 3.6-1, "Containment Leakage Paths" & Table 3.6-2, "Containment Isolation Valves."

ATTACHMENT IMarked-up Technical Speci fication Pages:3/46-53/46-63/46-73/4 6-83/4 6-2I3/46-22EJW2/0 I 3/28709010080870825IIPDR ADOCK05000335PPDRQIIIL'l,CIIc. rrr>"3ZS)TABLE 3.6-1CONTAINMENT LEAKAGE PATHSPenetration SystemLocationValve a Numbe ,-.. to Containment ServiceTestT~e...