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Containment Audit Plan Oct 22 2009.

AUDIT PLAN TO REVIEW SELECTED AREAS RELATED TO U.S. EPR FSAR CHAPTER 6 AND SUPPORTING TECHNICAL REPORTS APPLICANT: AREVA NP, Inc. APPLICANT CONTACT: Ronda Pederson TIME: 1:00 pm to 4:30 pm on 10/22/2009 LOCATION: AREVA NP, Inc., Twinbrook Office, Rockville,...

Monticello, Additional Containment Design Information.

NRC FORM 195 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL FILE NUMBER TO: FROM: NORTHERN STATES POWR c0 DATE OF DOCUMENT MR VICTOR STELLO MINNEAPOLIS, MINN 2-27-76 L 0 MAYER DATERECEIVED 3-1-76 OLETTER MNOTORIZED PROP INPUT FORM...

Forwards program & budget proposal, "BWR Containment Pool Dynamics - Liaison for Foreign Containment Research."

_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . __ _%'RLAWRENCE LIVERMORE LABORATORYy-i_yAn Equal Opportunity EmployerNUCLEAR SYSTD1S SAFETY PROGRAMDecember 22, 1980EM80-506'Dr. T. LeeAnalysis of Reactor Safety ResearchOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory Commissio...

Proposed tech specs re secondary containment & SGTS to reflect revised secondary containment drawdown & post- accident analyses results.

~~ ~CONTAINMENT SYSTEMS3/4.6.5 SECONDARY CONTAINMENTSECONDARY CONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATIONAttachment 3APage 1 of 83.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be maintained.APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and".ACTION:Without SECONDARY C...

"Sys Design Description for Containment Spray."

._ - ._ . - . . . . . .4'. ii.COMMONWEALTH EDISbN COMPANY-,BYRON /BRAIDWOOD STATIONS UNITS 1 AND 2'SYSTEM DESIGN DESCRIPTION{FOR|.'1CONTAINMENT SPRAY (CS):1Al /. Rfoh/sittapaer-Byron /Date/I;;P(O ( b ,l% parer--Braldwood/DateN.bmkhio/2e/wOReviewer /DateW. fmf o /3t /9f-Approve...

"Reactor Containment Bldg Integrated Leak Rate Test."

, .-g. .Seabrook Nuclear Power PlantUnit No.12Docket Number 50-443REACTOR CONTAINMENT BUILDING..INTEGRATED LEAK RATE TESTIp-..)I- [: .4.F; it -S.'. y; 'm ,g. ..~|-[f f.$,1*- ~'m .,. '_M _" *'' '~ ' : .r. ,-i 'a. ,. ,.,,,.d.,, . ., 7 . .-5'.'$ -[l k h . ," -'E j y k % '& (w. . ...

D.C. Cook, Resolution of Containment Structural Issues

Indiana Michigan Power Company Cook Nudear Plant One Cook Plant Bridgnan, MI149106 616 465 5901 INDIANA MICHIGAN POWER November 18, 2000 C 100-15 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Mr. Geoffrey E. Grant Director, Division of Reactor Projects 8...

Proposed tech specs re containment purge & vent.

' *p y y.yz / srwn rs/he L,[vmpsA&EEE: 3.7 (Cont'd)'The vacuum relief system from the pressure suppression chamber to>,Reactor Building consists of two 100% vacuum relief breakers(2 parallel sets of 2 valves in series).Operation of either systemwill maintain the pressure diffe...

Proposed Tech Specs re limiting condition for operation of containment cooling,iodine removal sys & associated containment isolation provisions.

ATTACHMENT A APPLICATION FOR AMENDMENT TO OPERATING LICENSING Technical Specification Page Revisions Consolidated Edison Company of New York, Inc. Indian Point Unit No. 2 Docket No. 50-247 Facility Operating License No. DPR-26 June, 1985 8506190290 850607 PDR ADOCK 05000247 P...

Proposed Tech Specs Section 3.7, "Containment Sys."

DAEC-1LIMITING CONDITION FOR OPERATION.3.7SU REPlant Containment Systems A. Primary Containment Integrity B. Primary Containment Power Operated Isolation Valves C. Drywell Average Air Temperature D. Pressure Suppression Chamber - Reactor Building Vacuum Breakers E. Drywell - P...

"Reactor Containment Bldg Integrated Leak Rate Test."

_ , , _ _, -_ ,,--a; g-- , - - ~ m- ---mm-ee'D|||l==--tGeneral Public Utahties System.OYSTER CREEKNUCLEAR GENERATING STATION|i|{|!?p{5@|7|SUMMARY TECHNICAL REPORTj4'(PROVISIONAL OPERATING LICENSE NO. DPR-16-REACTOR CONTAINMENT BUILDING INTEGRATED-LEAK RATE TESTJUNE 1980t-Nr,.....

Revised TS 3.6-2 re containment sys.

C . Containment Temperature1. The reactor shall not be taken above the cold shutdown condition unless the containment ambient temperature is greater than 50'F. 2. Containment ambient temperature shall not exceed 1301F when the reactor is above the cold shutdown condition. If ...

Cancellation of Licensee Event Report 05-006, "Inoperable Containment Due to Containment Air Cooler Through-Wall Flaws"

Palisades Nuclear Plant Operated by Nuclear Management Company, LLC March 30, 2006 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Cancellation of Licensee Event Rep...

"Reactor Containment Bldg Integrated Leak Rate Test."

CONSOLIDATED EDISON COMPANY INDIAN POINT NUCLEAR OWER PLANT UNIT NO. 2 REACTOR CD INT BUILDING IN'ATED LEAK RAM TEST SUW4ARY TECHNICAL REPORT PREPARED FOR CONSOLIDATED EDISON (a4PANY PREPARED BY EBASCO SERVICES,- INCROROMAT PLANT OPERATIONS & BITM DEPAR ENT THIS DOCLMENT IS TH...

Millstone, Unit 2, RAI, - Containment Systems.

December 31, 2002Mr. J. A. PriceSite Vice President - MillstoneDominion Nuclear Connecticut, Inc.c/o Mr. David A. SmithRope Ferry RoadWaterford, CT 06385SUBJECT: REQUEST FOR ADDITIONAL INFORMATION - CONTAINMENT SYSTEMS,MILLSTONE POWER STATION, UNIT NO. 2 (TAC NO. MB6109)Dear ...

Revised "Decommissioning Plan for Containment Cell Portion."

originai;Decommissioning PlanU.S. Nuclear Regulatory Commission|License No. SMB-911|Containment Cell PortionIFansteel Inc.Muskogee, Oklahoma.lO'l||Earth Sciences Consultants, Inc.One Triangle Lane iExport, PA 15632 |'724/733-3000FAX: 724/325-3352Branch OfficesAkron, OhioPhilad...

Forwards secondary containment leak rate test data to verify that containment not violated by work performed during refueling.

',.*M~"" Edison --. -PILGRIM NUCLEAR POWER STATIONRFD #1 ROCKY HILL ROADPLY M O UTH, MASSACHUSETTS O2360February 16, 1982BECo Ltr. #82-53\g,MED\\.2 [4R04sgghDirector of Nuclear Reactor Regulation (12)c/o Distribution Services Branch{'Attn: Document Distribution Center Administ...

Forwards info re secondary containment penetration program completion,for review & concurrence.Piping penetrating secondary containment boundary presents listed inleakage flow.

~. - = - ..u 3; F,!*L ,'j'j,,.c[ +*: TENNESSEE VALLEYi AUTHORITY-;j'CHATTANOOGA. TENNESSEE 37401- );Uj,SN 1578 Lookout Place.j'00T 06 BBS!U.S._ Nuclear Regulatory' Commission- !,; ATTN: Document _ Control Desk':Hashington, D.C.20555,Gentlemen:.;n.In the. Matter of- .) Docket N...

"Reactor Containment Bldg Integrated Leak Rate Test."

,,. ,.--..,9;-DUKE POWER COMPANY'I eLMcGUIRE NUCLEAR STATION| UNIT ||?'.,~.g .>REACTOR CONTAINMENT BUILDING-'INTEGRATED LEAK RATE TEST'.>t .Ii,.-|ooI;-- . _- - :^_ _._ . _ . - _.._ .--_. _._ .. ..- . _ _ . - . . -. _. --....- _ . _ . .- _ - _ _ _ _ . - _ _ . _ _ - . - . _ . - ...

PWR Containment Sump Evaluation Methodology - Baseline Evaluation.

1776 I STREET, NW SUITE 400 WASHINGTON, DC 20006-3708 PHONE 202.739.8081 FAX 202.533.0164 arp@nei.org N U C L E A R EN ERGY INSTI T UTE Anthony R. Pietrangelo SENIOR DIRECTOR, RISK REGULATION NUCLEAR GENERATION April 19, 2004 Mr. John N. Hanno...

Rev 3 to "Evaluation of Containment Coatings."

..,"REPORT NO. DECO-12-2191um REVISION 3OCTOBER 1984.ENRICO FERMI ATOMIC POWER PLANTUNIT NO. 2EVALUATION OFCONTAINMENT COATINGSeggogggg;aggg8 MULTIPLE DYNAMICS CORPORATION gA..,., . .. . . .- .. . . . , , . . .. . . . ..,......,.,. . ., ,_ g-|,iTHE DETROIT EDISON COMPANYFERMI ...

Proposed changes to Tech Specs implementing containment normal sump & containment wide range level schedule, containment pressure schedule & RCS high point vents.

l-.aKFACTOR COOV. ANT SYSTEMlilC11 POINT [ENTS,JLIMITING CONDITION FOR OPERATION3.4.11The Feactor Coolant System will have two high point ventsOne of these vents shall be OPERABLE.installed on it', one in each loop.For the vent to be OPERABLE, both valves in the vent will have...

Proposed Tech Spec changes on containment purge supply & exhaust isolation valves & containment pressure-vacuum relief isolation valves.

-· ... -... , . -'· --PROPOSED CHANGE TECHNICAL SPECIFICATIONS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DESCRIPTION OF CHANGE :~~·---. ..:~~ ... ~········~- ·-- ·.-· - ... -;-_. -Ref: LCR 81-25 A new page, 3/4 6-8a, containing specifications on Containment Purge Supply and E...

Advises that containment pressure-high-1 setpoint complies w/TMI Action Item II.E.4.2, "Containment Isolation Dependability" & SER requirements.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ __________ - -**SNUPPSStandard aed Nucleat UnitPower Plant System8C *C'Y **dNicholas A. PetrickgExecutive Directorm,3 m,,March 15, 1984.SLNRC 84-0043 FILE: 0278SUBJ: Containment IsolationDependability

"Reactor Containment Bldg Integrated Leak Rate Test."

A.IMAINE YANKEE ATOMIC POWER COMPANYREACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TESTAugust, 1985B601210096 860107PDRADOCK 05000309PpmTABLE OF CONTENTSPAGEList of Figures11List of Tables and GraphsiiiReferencesiv1.0 Introduction 1.2.0 Integrated Leak Rate Test (Type A) 2....