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Draft "BWR Owners Group Containment Testing Committee Standardized Program for Primary Containment Integrity Testing."

[ NA*$. ,, ,g;| f,r-,NEDD-31722',Class IAugust 1989;."MAFT.I6|6|69.-BWR OWNERS' CROUP-CONTAINMENT. TESTING COMMITTEESTANDARDIZED PROCRAMFORPRIMARY CONTAINMENT INTEGRITY TESTING.... ..0.s.-~i,,,, ,_ ,, ,,175 Curw 4enueSonJose. [A 95125"8909110403 890821PDR PR.. . _ _ _ _ - _ .}...

Table for Primary Containment 3.6.1.1

Primary Containment 3.6.1.13.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary ContainmentLCO 3.6.1.1 APPLICABILITY:Primary containment shall be OPERABLE. MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary I hour inoperable, con...

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

REGULATORY~NFORMATION DISTRIBUTION SY TEM (RIDS)ACCESSION NBR: 79091S0421 DOC. DATE'--iV/uV/12 NOTARIZED: NOFACIL: 50-220 Nine Mile Point Nuclear Stationi Unit ii Niagara PoweAUTH. NAME AUTHOR AFFILIATIONSCHNEIDER> R. R. Niagara Mohawk Power Corp.RECIP. NAME RECIPIENT AFFILIAT...

Proposed tech specs 3.6.1.4, "Containment Systems Internal Pressure," reducing max allowed value for containment pressure specified.

_ _ _ _ _ _ _'_...-.Docket No. 50-1MB166411lAttachment 3Millstone Nuclear Power Station, Unit No. 2Proposed Revision to Technical SpecificationsContainment PressureMarked Up PagesSeptember 1997"9709000231 970902PDR ADOCK 05000336"PPDR,.- - _ __ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _'...

Provides requested info supporting conclusion that containment recombiner capability & atmospheric containment air dilution sys not required.

• Commonwe~Edison One First Nation~za, Chicago, Illinois Address Reply to: Post Office Box 767 . . '• Chicago, Illinois 60690 Mr. Harold R~ Denton, Director Off ice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission . Washington, DC 20555 • June 2 5, 1984 .Subjec...

Proposed tech specs 3/4.6 re Containment Systems & 3/4.6.1 re Primary Containment Integrity.

..*.3/4.6 ' CONTAINMENT SYSTEMS3/4.6.1PRIMARY CONTAINNENT?CONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION3.6.1.1Primary CONTAINMENT INTEGRITY shall be maintained.''APPLICABILITY: MODES 1, 2, 3, and 4. W [ Foo -Mom WMdrACTIONiWithout primary CONTAINHENT INTEGRITY, restore...

Salem, Units 1 & 2 - Request for Change to Technical Specifications Containment Ventilation System, Containment Isolation Valves.

PSEG Nuclear LLCP.O. Box 236, Hancocks Bridge, New Jersey 08038-0236AUGO 4200LR-N06-0233 0 PSEGLCR S06-06 Nuclear LLCUnited States Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONSCONTAINMENT VENTILATION SYSTEM...

Proposed Tech Specs re surveillance requirements for containment sys,containment isolation valves & combustible gas control.

,__ - _ _ - . - _ _ . . . . .. . .-'-...(..L-! .||CONTAINMENT SYSTEMS-SURVEILLANCE REQUIREMENTS4.6.2.3Each containment cooling group shall be demonstrated OPERABLE:a. At least once per 14 days by:1.Verifying-a service water flow rate of 2 1250 gpm to eachgroup of cooling units...

Containment Design Perspectives.

12. Containment Design Perspectives1.0 Ž0.9 S 0.8 0 a. S 0.7 &0.6 C E 0.5 . 0.4 8A 0.3 A C0 AA A ( 0.2 CA o~oI o 0.1AAAA 0.0-A A 1 'jA gAt Isolation Total Failure Early Failure Large Dry plus Subatmospheric Figure 12.25 Comparison of IPE reported conditional probabilities of...

NRC Information Notice 2004-009: Corrosion of Steel Containment and Containment Liner.

UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001April 27, 2004NRC INFORMATION NOTICE 2004-09: CORROSION OF STEEL CONTAINMENT ANDCONTAINMENT LINER Addressees:All holders of operating licenses for nuclear power reactors ex...

License Amendment Request 03-14 - Revision to Technical Specification 3.6.3, "Containment Systems/Containment Isolation Valves".

Pacific Gas andElectric CompanyDavid H. Oatley Diablo Canyon Power PlantVice President and PO. Box 56General Manager Avila Beach. CA 93424805.545.4350October 22, 2003 Fax: 805.545.4234PG&E Letter DCL-03-134U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington...

"Containment Recirculation Sump Evaluation."

CAROLINA POWER 5 LIGHT COMPANYSHEARON HARRIS NUCLEAR POWER PLANTCONTAINMENT RECIRCULATION SUMP EVALUATIONTABLE OF CONTENTSI. PURPOSEPAGEII . INTRODUCTIONIII. SUMP AND CONTAINMENT BUILDING LAYOUTIV. PIPE BREAKS AND JET EXPANSION MODELV. TYPE AND LOCATION OF INSULATION INSIDE CO...

Informs NRC that review of containment free volume & heat sinks re integrated containment reanalysis methodology completed.

4<*:~MaineYankee~ --AELIABLE ELECTRICITY SINCE 1972 -329 BATH ROAD + BRUNSWICK. MAINE 04011 * (207) 798-4100January 14,1997' MN-97 003 JRil-97-004qUNITED STATES NUCLEAR REGULATORY COMMISSIONAttention: Document Control DeskWashington, DC 20555References: (a) License No. DPR-36 ...

Forwards plan for Mark I containment safety study at plant. Study consists of containment design review,probability evaluation of containment failure during core melt & review of hydrogen control.

r%VERMONT YANKEENUCLEAR POWER CORPORATION.RD 5. Box 169, Ferry Road. Brattleboro, VT 05301..*June 30,1986J. GAny WEIGANDFRESIDENT ANDCHIEF EXECullVE OFFICERi802n 257-5211Dr. Ilarold DentonDirector, Nuclear Reactor RegulationU. S. Nuclear Regulatory Commission1717 11 Street, N....

"Reactor Containment Bldg Design Rept."

STP-CONTAINMENT BUILDING. . ..DESIGN REPORTSOUTH TEXAS PROJECTELECTRIC GENERATING STATION, UNITS 1 & 2HOUSTON LIGHTING AND POWER COMPANYREACTOR CONTAINMENT BUILDINGDESIGN REPORT(APPENDIX C, CALCULATION CC-5210, REV. 2)PreparedbyBechtel Energy Corporation, Houston, TexasJULY, 1...

Proposed Tech Specs,adding surveillance requirements for containment isolation logic for containment vacuum relief valves.

r-..ENCLOSURE 1- r;:,_PROPOSED TECHNICAL SPECIFICATION CHANGEaSEQUOYAH NUCLEAR PLANT UNITS 1 AND 2-~DOCKET NOS. 50-327 AND 50-328(TVA-SQN-TS-87-31)~LIST OF AFFECTED PAGESUnit 13/4 6-18Unit 23/4 6-18,'.|:8706100390 870602f'DRADOCK 05000327 pPDR4-- - -,,.---,.-v ,- , , . - , . ,...

Waterford 3, Amendment,Reduction in Operable Containment Fan Coolers in Containment Cooling System

Mr. Charles M. Dugger Vice President Operations Entergy Operations, Inc. 17265 River Road Killona, LA 70066-0751SUBJECT:July 6, 2000WATERFORD STEAM ELECTRIC STATION, UNIT 3 - ISSUANCE OF AMENDMENT RE: REDUCTION IN OPERABLE CONTAINMENT FAN COOLERS IN THE CONTAINMENT COOLING SY...

Proposed Tech Specs changing Table 3.3.4, "Primary Containment Isolation Valves Line Entering Free Space of Containment."

ATTACHMENT ANIAGARA MOHAWK POWER CORPORATIONLICENSE NO. DPR-63DOCKET NO. 50-220PROPOSED CHANGES TO TECHNICAL SPECIFICATIONSExisting Page 147 will be replaced with the attached revised page.This pagehas been retyped in its entirety with a marginal marking to indicate thechange....

"Containment Sump Operability Determination."

ATTACHMENT 1 TO AEP:NRC: 1260G6OVERHEAD SLIDES USED DURINGJANUARY 8, 1998, PUBLIC MEETING'ANERfCAN—HECTRlCPOMtERADDITIONALREVIEWSJANUARY8,1998NIERtt,'ANRECTKICpomERJIM KOBYRACHIEF NUCLEAR ENGINEER'AMER!CANRECTRfCNNB~December 16,1997—Public meeting on CAL response~December22,19...

Application for amend to License NPF-41,revising Tech Spec Section 3/4.6.1, "Primary Containment," & bases.Revised containment analyses demonstrate acceptability of containment spray pump flow rate change.Fee paid.

'EGULA INFORMATION DISTRIBUTIO YSTEM (RIDB)ACCESSION NBR: 8610100502 DOC. DATE: 86/10/02 NOTARIZED: NO DOCKET ¹FAG IL: BTN-50-528 Palo Uerde Nuclear Stationi Unit 1. Arizona Pub li 05000528AUTH. NAl'IE AUTHOR AFFILIATIONHAYNES> J. Q. Arizona Nuclear Pouer Pro Ject (formerly Ar...

Proposed Tech Specs Sections 3/4.6.1, "Primary Containment" & 3/4.6.5, "Secondary Containment."

*.|||1CONTAINMENT SYSTEMS '3/4.6 CONTAINMENT SYSTEMS3/4.6.1 PRIMARY CONTAINMENTPRIMARY CONTAINMENT INTEGRITY|!LIMITING CONDITION FOR OPERATION;I3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.ACTION:Without PRIMARY CO...

Forwards proposed revision to Tech Specs to allow unlimited containment purges.Revisions deal w/containment isolation valves.

(,-.c 0......NOffrHEA!Tr IFFILrrIIISl;''.'"HART ORD. CONNECTICUT 06101(203) 666-6911m ,k kj., ..*April 27, 1979Docket No. 36Director of Nuclear Reactor RegulationAttn: Mr. R. Reid, ChiefOperating Reactors Branch #4U. S. Nuclear Regulatory CommissionWashington, D. C. 20555(']'R...

IP 65001.11, Construction Inspection Program Inspection of ITAAC-Related Containment Integrity and Containment Penetrations.

Issue Date 08/19/08 1 65001.11 ATTACHMENT 65001.11 CONSTRUCTION INSPECTION PROGRAM INSPECTION OF ITAAC RELATED CONTAINMENT INTEGRITY AND CONTAINMENT PENETRATIONS 65001.11-01 INSPECTION OBJECTIVES 01.01 Verify that materials such as welding consumables, plate material, incl...

SIMPLIFIED CONTAINMENT EVENT TREE ANALYSIS FOR THE SEQUOYAH ICE CONDENSER CONTAINMENT.

. - - - .- - - -- _..NUREG/CR-5602EGG-2606LSimplified ContainmentEvent Tree Analysis for theSequoyah Ice CondenserContainment|,l lV. S.$alycan, J. A. Schrmder. D. J. Pafford'iIdaho Nationa Engineering LaboratoryLEG&G Idaho, Inc.|Prepared farU.S. Nuclear Regulatory CommissioniL...

"Rept on Containment Purge Operational Data Gathering & Evaluation Program & Proposed Containment Purge Criteria."

q_,,- - - - - - - - - - - - - - - - - - - - - - - -j; 9; q .CrN CC')NS1 81 771-2A)