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Proposed License Amendment Supplement re Containment Equipment Door and Containment Airlock Doors Open During Core Alterations.

Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 0 August 24, 2001 I=PL L-2001-199 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment S...

Application for amend to license DPR-65,modifying Definition 1.8, "Containment Integrity," TS 3.6.1.1, "Containment Integrity" & TS 3.6.3.1, "Containment Isolation Valves."

. --_ _m . _._._-.__._ _- ~ m._____ _________ _ _ .Igi'Y #Northeast''"P" '''"Y 'id- ("""'" '56)' **"d"'d C' "385,i : Nuclear Energy staistone Nucica, powe, siationi Northeast Nuclear Energy CompanyP.O.11ox 128-j Waterford, CT 06385-0128|(860) 447-1791]8Fax (860) 444-4277'The N...

Proposed TS SR 4.6.1.1 re primary containment integrity & LCO 3.6.1.3 re operability of containment air locks.

.-,ATTACHMENT 3ST HL-AE-t/o 6 6PAGEl0F _/0-- .,h:1iAPPENDIX B( )'i'MARKED-UP TECIINICAL SPECIFICATION PAGES:.E44!l*.9208110243 920804PDRADOCK 05000499PPDR_-. ..1ATTACHMENT 33/4. 6 CONTAINMENT' SYSTEMS ST HL-AE-40MPAGE A 0F 107)3/4.6.3 PRIMRY CONTAINMENT-'CONTAINMENT INTEGRITYL...

NTTF 5.2 Other Containment Designs.

DRAFT FOR COMMENT DRAFT FOR COMMENT Tier 3 - NTTF Recommendation 5.2 Reliable Hardened Vents for Other Containment Designs Purpose The purpose of this status summary is to provide a rationale for deferring further regulatory action to enhance containment overpressure prot...

"Releases From Containment,Section 2."

. - \Section 2Releases from Containment2.1 GENERAL REMARKSA large portion of the work of the Reactor Safety Study was expended in determining theprobability and magnitude of various radioactive releases. This work is describedin detail in the preceding appendices as well as Ap...

US-APWR Design Certification - SRP Section: 06.02.01 - Containment Functional Design Application Section: 6.2.1 Containment Functional Design.

REQUEST FOR ADDITIONAL INFORMATION 923-6420 REVISION 3 1 4/24/2012 US-APWR Design Certification Mitsubishi Heavy Industries Docket No. 52-021 SRP Section: 06.02.01 - Containment Functional Design Application Section: 6.2.1 Containment Functional Design QUESTIONS for Co...

Proposed Tech Specs re containment leak testing & containment isolation valve table.

r*.*LCA 124Attachment 1 .Page 1 of 21INDEXLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSSECTIONPAGE3/4.6 CONTAINMENT SYSTEMS3/4.6.1 PRIMARY CONTAINMENTContainment Integrity . . . .3/46-1 ............Containment Leakage . . . . . . . . . . . . . . . . .3/4 6-2C...

Application for amend to license DPR-65,changing TS 3.6.1.2, "Containment Sys - Containment Leakage."

.. - _._ . _ ._. _ ._ _ . . _ . _ _ _ . _ _ _ _ . _ . . _ . _ _ _ _ _ _...'-wnope rerry na. (aooie is6), weiertora, cr 06s8s-!Nuclear Energyuin.none Nuclear Power StationNaribeast Nuclear Energy CompanyP.o. Box 128Weserford, Cr 0638s-0128(860) 447 1791,,Far (860) 444-4277The N...

Proposed Tech Spec Section 3/4.6.1, "Primary Containment," revising containment analyses.

3/4.6 CONTAINMENT SYSTEMS3/4. 6. 1 PRIMARY CONTAINMENTCONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.APPLICABILITY: NODES 1, 2, 3, and 4.ACTION:Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY ...

"Containment Internal Structure Design Rept."

n^.('t*/.,I, ,,'VOGTLE ELECTRIC GENERATING PLANTy11; s GEORGIA POWER COMPANY- p s,,R.f..h.r%,-4-^1..P+ s,..s -I~ CONTAINMENT INTERNAL STRUCTURE{tiDESIGN REPORT[:s 'L:(:_,i. :3s );''Prepared;-;s-"by|;Bechtel Power Corporation, Los Angeles, CaliforniaOctober 1984hDR |O..:A,.,Ah-...

Dresden, Units 2 and 3 - Atmospheric Containment Air Dilution / Containment Atmosphere Monitor System.

'i· e Commonw..& Edison One First Nati~~aza, Chicago, Illinois . Address Reply to: Post Office Box 767 Chicago, Illinois 60690 --April 7, 1977 Mr. Dennis L. Ziemann, Chief Operating Reactors - Branch 2 Division of Operating Reactors U.S. Nuclear Regulatory commission Washingto...

Dresden Station, Units 2 & 3 - Atmospheric Containment Air Dilution/Containment Atmosphere Monitor System.

e Commonw&h Edison One First Naii2"Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 \ \\"-;" I l I 9J ! /· April 7, 1977 i.9 ~:\1 ·v,, , . IC)\ . ~~\~\) r /1 Mr. Dennis L. Ziemann, Chief (~\.\.)\. \~\~~0~> \ Operating Reactors - Branch 2 -...

"Containment Venting as Severe Accident Mitigation Technique for BWR Plants W/Mark I Containment," ltr rept.

~>'.,a,'asCONTAINMENT VENTING AS A SEVERE ACCIDENTMITIGATION TECHNIQUE FOR BWR PLANTS!. - WITH MARK I CONTAINMENTR. M. HarringtonS. A. HodgeSevere Accident Sequence Analysis (SASA) ProgramOak Ridge National LaboratoryOak Ridge, TennesseeLet ter Repor tJune 26, 1986Research spo...

Proposed Tech Spec 4.4 re limitations of containment integrated leakage rate & containment leakage tests.

%me.PROPOSEDTECHNICAL SPECIFICATIONREVISIONS.en121ao777/- - - - - , - - - - - - - - - - - - , - - - - - - , - -..3.The affected penetration is isolated within four hours by theuse of a closed manual valve or blind flange.4.The reactor is in the hot shutdown condition within 12...

Timeline for Cook Containment Issue.

Timeline for Cook Containment IssueDate Description Ref.Early 1 970s' D.C. Cook containment structures designed using uncertainty factors of 1Uto15under various load combinations.03/10/1973 Atomic Energy Commission approved Version 4 of the Westinghouse 5Transient Mass Distrib...

LER 12-002-01 for Fort Calhoun Regarding Inadequate Qualifications for Containment Penetrations Renders Containment Inoperable.

--Omaha PublIc PowsrO/slrlct 444 South 16th Street Mall Omaha, NE 68102-2247 UC-13-0085 July 2,2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: 1 . Docket No. 50-285 2. Letter from D. J. Bannister (LlC-12-0043) to Docu...

Email - Subject: Containment Graphic.

4iiLake. LouisFrom: Lake, LouisSent: Tuesday, November 24, 2009 9:23 AMTo: Carrion, Robert; Thomas, George; Masters, Anthony; Dan nausCc: Franke, MarkSubject: FW: 2009 Nov 23 - Containment Unfolded GraphicsIR Mosaic.pptxAttachments: 2009 Nov 23 - Containment Unfolded Graphicsj...

Salem, Units 1 & 2, Revised Request for Changes to Technical Specifications Containment Systems - Containment Cooling System.

PSEG Nuclear LLCP.O. Box 236, Hancocks Bridge, New Jersey 08038-0236AUG 1 1 2004LR-N04-0343 PSEGLCR S03-07 0 ISEGNuclear LLCU. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001REVISED REQUEST FOR CHANGES TO TECHNICAL SPECIFICATIONSCONTAINMENT...

Proposed TS 2.6 re containment integrity & 3.5 re containment bldg leak rate tests.

._ .. - . . -- . .DI!PINITl_ONSMISCELLANEOUS DEFINITIONSOperable - OperabilityA system, subsystem, train, component or devise shall be OPERABLE or haveOPERABILITY when it is capable of performing its specified functions (s). Implicit in .Ithis definition shall be the assumptio...

Proposed tech specs re containment air lock door operability requirements for containment integrity.

. _ - - _ .Docket Number 50-T'e6License Nunber NPF-3.Serial Number 1971,.AttachmentPage 9,;. .''OtttN! TION 5iI REPORTABLE EVENT,11.7 A REPORTABLE EVENT snal) be any of those conditions specified in Sect 1or '50.73 of 1C CFR Part 50.CONTAINMENT INTEGRITY _1.8 CONTAllgENT INTEG...

Proposed Tech Specs 3/4.6.1 & 3/4.6.1.2 re primary containment integrity & containment leakage rates, respectively.

, ,. - _ . . , _ . _ _ _ _ __ . . _ _ _ . . __. _ _ _ _ _ __. _ . _ _ _ -......,,,.Attachment 3 toULNRC- 2378PROPOSED TECHNICAL SPECIFICATIO!1 CilANGESSpecification 3/4.6.1.13/4.6.1.2|.f.9103270346 910315ffDRADOCK0500g,g3. - . _ - _ . . _ _ . . . - . _ . . . - . _ _ _ _ _ _ , ...

"Containment Leakage Rate Testing."

TECHNICAL EVALUATION REPORT CONTAINMENT LEAKAGE RATE TESTING CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON, UNIT 2 NRC DOCKET NO. 50-261 NRC TAC NO- 01954 FRC PROJECT C5257 NRC CONTRACT NO. NRC-03-79-118 FRC TASK 48 Prepared by Franklin Research Center Author: G. J. Overbeck...

"Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment."

.._ . _ - _ _ _ _ _ _ _ _ . __ _ _________-, .e Attachment 2ULNRC-1950' ' . . '54 Pages,SNUPPSCALLAWAY UNIT 1UNION ELECTRIC COMPANY, MISSOURIWOLF CREEK UNIT 1WOLF CREEK NUCLEAR OPERATING CORPORATION-iPOST TENS 10NING SYSTEM EVALUATIONCALLAWAY UNIT 1 CONTAINMENTWOLF CREEK UNIT ...

Proposed Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 re containment sys & containment leakage.

- _ _ _ - _ - _ _ _ _|1i'|FOR|NFeMBHM,.,COIrfAI1OINT SYSTDfS|C0!ffAIMfDT LEAKAGELIMITING CONDITION FOR OPERATION3.6.1.2 Coatsineemt leakage rates shall be limited to:,An overall integrated leakage rate of f L 0.50 percent bys.weight of the contalement air per 24 hourl,at F,,38...

Forwards request for addl info & Containment Sys Branch Technical Position CSB 6-1, "Min Containment Pressure Model for PWR ECCS Performance Evaluation," per review of containment pressure calculations.

" 79C. , -: -~ W ~ y z,in--qj! 4 .i . ,J'JUl.7 TIISNRR Reading File.,CS Reading FileCSB Reading FileDochet Nos. 50-460/513D ket FileMS 2MV. Stallo, Assistant Director for Reactor Safety. TRREQUEST POR ADDITIONAL IMPOEMATION C010CEENING THE WFPS 1 & 4 ECG EVALUATICEI -i CORITAI...