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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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REQUEST FOR LICENSE AMENDMENT CONTAINMENT SYSTEM

0 PSIG G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 2 2000 LR-N000058 LCR S00-01 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 REQUEST FOR LICENSE AMENDMENT CO...

Proposed tech specs re containment isolation valves.

Document Control Desk Attachment 3 SALEM GENERATING STATION LR-N96291 LCR S95-02 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT ISOLATION VALVES MARKED UP TECHNICAL SPECIFICATION PAGES The following Te...

ITS: 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

JAFNPP IMPROVED STANDARD TECHNICAL SPECIFICATIONS (ISTS) CONVERSION ITS: 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) JUSTIFICATION FOR DIFFERENCES (JFDs) FROM NUREG-1433, REVISION 1JUSTIFICATION FOR DIFFERENCES FROM NUREG-1433, REVISION 1 ITS: 3.6.4.2 - SECONDARY CO...

Proposed tech specs re secondary containment integrity.

- .. .. .'United States Nuclear Regulatory Commission-,April 4,1996Pronosed Change 1841Marked-Up Technical Specification Pages.9604090287 960404PDR ADOCK 05000271PPDR- - . . . . - . . . . . _ . -_ - - -. ._ - .- _. - _. . = . . .- . .G *,I', l.,VYt!PS3.7LIMITIt1C CC!!OITICtlS ...

"CANDU 3 Containment Performance & Consequence," dtd 940515.

,.-SEA 93-704-01-A:3Technical Evaluation Report!CANDU 3 CONTAINMENT PERFORMANCE AND CONSEQUENCEMay 15,1994Clinton J. ShafferFrank W. SciaccaScience and Engineering Associates,Inc.Robert S. DunhamIRobert A. DameronYusef R. RashidANATECH Research CorporationRobert E. NickellAppl...

AP1000, Staff Comments on Containment Model.

v-:\ tVll\VV fUUUd. I IivvIage .,:\I LIvIrxuvvuuuui. I IVII- l-'age 1Mail Envelope Properties (3FC364A8.419: 18: 20163)Subject:Creation Date:From:Created By:Staff Comments on Containment Model11/25/2003 9:18AMJoelle StarefosJLS 1 @nrc.govRecipientsnrc.govowf2.po.0WFNDOEDT1 ...

"Secondary Containment Leak Rate Test Performed 871026."

ENCLOSURESECONDARY CONTAINMENT LEAK RATE TESTPERFORMED OCTOBER 26, 1987BROMNS FERRY NUCLEAR PLANT (BFN)1.0 Browns Ferry Nuclear Plant Unit 2 Secondary Containment Leak Rate TestReport, per Technical Specification 6.7.3.C.l.a.2.0 ~pre oseThis report describes the results and an...

LER 06-006-00 for Palisades regarding Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw.

Committed to Nuclear ExcellPalisades Nuclear PlantOperated by Nuclear Management Company, LLCDecember 15, 2006 10 CFR 50.73(a)(2)(i)(A)10 CFR 50.73(a)(2)(v)(C)U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Palisades Nuclear PlantDocket 5...

Proposed Tech Specs adding requirements for long-term containment cooling following non-LOCA event.Description & justification for containment cooler requirements encl.

"'Nde'< fAe [off,P3 t' feFMfN ffeettbOls'if fqe..$.t.1 arms.ssucicanos Ago-'/..tCONTAINMENT STEMS|f.'s |-eetfTAM:NT COOLING SYSTEMS (UT EL' (L e t ;-. f a i; din; r; rec.l by,y~b r:3 y::=:)LowCR Cop 1hN/nf' ff' VCp]f* COOffRS*A~LIMITING' CONDITION FOR OPERATICN,~f.Frak of lowe...

"Reactor Containment Bldg Integrated Leak Rate Test."

. _. ._ _ . _ . . . . _ ._. _. . _9 ./i-BRUNSWICK STEAM ELECTRIC PLANTUNIT NO. 2REACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTMARCH 1988.CAROLINA POWER & LIGHT COMPANYPrepared by:David B. BlackReviewed by:k)ILRT Engine 6rApproved by://gMpds8806290509 880624PDR ADOCK 050...

"Effects of Internal Containment Stratification & Mixing on AP600 Passive Containment Cooling Sys Design Basis Analysis Evaluation Models."

__.:. .'l,,fEffects of Internal Containment Stratification and Mixing onAP600 Passive Containment Coolics SystemDesign Basis Analysis Evaluation Models5|)i9505150130 950508'PDRADOCK 05200003APDRmal 951w.wpf:IbVM2595. -.*!*. . . .Effects of Internal Containment Stratification a...

Proposed tech spec section 3.6, "Containment Sys."

._. . _ - _ _ - _Primary Containment3.6.1.13.6 CONTAINMENT SYSTEMS3.6.1.1 Primary ContainmentLCO 3.6.1.1 Primary containment shall be OPERABLE.APPLICABILITY: MODES 1, 2, and 3.ACTIONSCONDITIONREQUIRED ACTION COMPLETION TIMEA. Primary containmentA.1 Restore primary I hourinoper...

IP 63050, "Containment Structural Integrity Test."

Issue Date: 07/01/83 - 1 - 63050 NRC INSPECTION MANUAL DQASIP INSPECTION PROCEDURE 63050 CONTAINMENT STRUCTURAL INTEGRITY TEST PROGRAM APPLICABILITY: 2512 63050-01 INSPECTION OBJECTIVES To determine whether the containment structural integrity test (SIT) program...

Draft "Containment Performance Design Objective Workshop."

m_o.'/*'.,.- .CONTAINt1ENT PERFORt1ANCE DESIGN OBJECTIVE WORKSHOPDraft dated July 18, 1986.&.' Department of Nuclear Energy,Brookhaven National LaboratoryUpton, New York 11973',Prepared forU.S.Nuclear Regulatory CommissionWashington, DC 20555Contract No. DE-ACO2-76CH00016FIN A...

Modified proposed Tech Specs 3/4.6.1.1, "Primary Containment" & 3/4.6.5.1, "Secondary Containment," listing devices affected by proposed changes.

, - -....-*.. . . ,I. ,s, i(!,iPKPQGED PME CHMMS-.1.|O's',(8906120290 890531PDR ADOCK 05000341PPDC.--_ _ _ _ _ _ _ _ _ _ _- - - - - _ - -/_,CONTAINMENT SYSTEMS3/4.6 CONTAINMENT $YSTEMS.3/4.6.1 PRIMARY CONTAINMENTPRIMARY CONTAI MENT INTEGRITY.=LINITING CONDITION FOR OPERATIONPR...

"Containment Vessel Integrated Leak Rate Test."

- - _ - - . -- - _ -_ _ - - _ --_ -- - ._s:<|-:i'. CONTAINMENT VESSEL.INTEGRATED LEAK RATE TEST:-.(DAVIS-BESSE --NUCLEAR POWERSTATIONUNIT 1,.TOLEDC) EDISON COMPANY-.., c,///6., m m 3.I,gE* * *7#. .. . . - . -.-(.CONTAINMENT VESSEL.INTEGRATED LEAK RATE TESTDAVIS-BESSE NUCLEAR P...

Forwards response to NRC RAI re proposed rev to TS LCO 3.3.6, "Containment Ventilation Isolation Instrumentation" & LCO 3.9.4, "Containment Penetrations."

, ._. ._ .*.~J. Fernie Beasley, Jr., P.E. Seuthern Nuclear ..;- Vice President - Operating Company,Inc.-'Vogtle Project 40 invemess Center Parkway -P.O. Box 1295'|Birmingham, Alabama 35201*Tel 705 9923110'Fax 205.992 0403SOUTHERNCOMPANYEnergy to Sern hur World*November 30, 199...

Dresden Station Units 2 & 3, Atmosphere Containment Air Dilution/Containment Atmosphere Monitor System ACAD/CAM.

ยท- .. .._ -Commonwei Edison One First Nat i~aza , Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 Director Nuclear Reactor Regu Attn: Mr . Richard Snaider Operating Reactors - Branch 2 Division of Operating Reactors U. S . Nuclear Regulatory com...

"Reactor Containment Bldg Integrated Leak Rate Test."

DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST OCTOBER 1990 Prepared by: arc Boyles Test Engineer Reviewed by: f Ma k Patrick Engineering Supervisor Approved by: 2L -ou I7 Dean Hubbard Performance Manager 0401551 PDR ADO...

Proposed Tech Specs Section 3.6, "Containment Sys."

United States Nuclear Regulatory Commission, Attachment II to Serial: RNP-RA/97-0081 O (16 pages) H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING THE TECHNICAL SPECIFICATIONS CHANGE REQUEST TO CONVERT TO THE IMPROVED STA...

Proposed TS 3/4.6.1.2 re limiting primary containment leakage rates for inclined fuel transfer sys containment penetrations.

-~ .- - .- - - . ..'Attachmant'3 .i'to U-602116|. CONTAINMENT SYSTEMSfLS-93-003;PRIMARY CONTAINMENT LEAKAGEPage~ 1 of . 3'-|,.tLIMITING CONDITION FOR OPERATIONi3.6.1.2Primary containment leakage rates shall be limited to:|An overall integrated leakage rate of less than or equa...

Forwards containment purge study for facility,in support of revision to Tech Spec 3.6.1.9 re containment purge limits.

I* *TENNESSEE VALLEY AUTHORITYCH ATTANOOGA, TENNESSEE 37401400 Chestnut Street Tower IIGEIJanuary 8, 1931h,u:egs.)|, N, , + ,Director of Nuclear Reactor Regulation ,''y .y!Attention: Mr. A. Schwencer, Chief1: %$*Licensing Branch No. 2 |-?Division of Licensing3[h*U.S. huclear R...

LER 05-001-00 for Susquehanna, Unit 1 regarding Primary Containment Instrument Lines Located Outside Secondary Containment.

R. A.SacconoVice President - Nuclear OperationsPPL Susquehanna, LLC769 Salem BoulevardBerwick, PA 18603Tel. 570.542.3959 Fax 570.542-1504rasacconeDpplweb.com. I I''I- *.PP'* 4%r'~1,_N e e ClnsU.S. Nuclear Regulatory CommissionAttn: Document Control DeskMail Stop O-P1-17Washing...

Responds to Palladino 860613 memo to HR Denton re containment integrity.Licensing reviews have consistently emphasized containment performance against postulated accidents.

-_, ,''.% /134 ,f~*.. ., 3 ,'$/hklTED sTA ES s .#~ #'o''j>!".- INUCLEAR REGULATORY COMMISSIONo ,jWASHINGTON. D. C. 20655,,,,,,/ JUL 101996.,,k. '''' PEMORANDUM FOR: Chairman Zech+'Commissioner RcbertsCommissioner Asselstine ,Comissioner BernthalFROM:Victor Stello, Jr.'.Executi...

Proposed tech specs & bases re containment systems.

- -. - - .. .-. -. ---- . - - . - . .- -. -. -.*:%. .. . .,*; .-~'3/4.6 CONTAINMENT SYSTEMS%*-.i'w ' ~3/4.6.1 PRIMARY CONTAINMENT -4"CONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION,!': 3.6.1.1Primary CONTAINMENT INTEGRITY shall be maintained.!I!|APPLICABILITY:MODES 1, 2,...