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ENN Engineering Standard, Rev. 0, IWE General Visual Containment Inspection.

ENTERGY -llr ENN ENGf NEERING STANDARD ENN-EP-S-001 Rev. 0 Effective Date: 311 9/04 IWE General Visual Containment Inspection IP1 Applicable Site(s): IP2 IP3 IxI JAF IxI PNPS IXI VY Safety Related: X Yes No e Prepared by: Glen Smith Print Nad/$@naiurdDate Approved by: Robert P...

"Reactor Containment Bldg Integrated Leak Rate Test." W/890628 ltr.

DOCKET05000389gCCE1ZRATEDDISTMBUTION DEMONSTRXTION SYSTEMREGULATC INFORMATION DISTRIBUTION+STEM (RIDE)d/BE/NFACIL:50-389 St. Lucie Plant, Unit 2, Florida Power S Light Co.AUTH.NAME AUTHOR AFFILIATIONTREADWELL,J. Florida Power 6 Light Co.MUMPER,D. Florida Power 6 Light Co.WOODY...

Proposed Tech Specs re containment structural integrity surveillance Spec 4.6.1.6.1.

. . .,'' ' *. ATTACHMENT A-1"iBeaver Valley Power Station, Unit No. 1Proposed Technical Specification Change No. 181,.Revise the Technical Specifications as'follows:-Remove Pace Insert Pace3/4 6-10 3/4 6-10@1901019025790g34,DRADOCK 0py_ _ _ _ , . . . . ..- .. . ~ . -!. .', , ....

McGuire, Units 1 and 2, Proposed Technical Specifications Amendment Technical Specification Bases 3.0 (Surveillance Requirement (SR) Applicability), Technical Specifications and Bases 3.6.1 (Containment), 3.6.2 (Containment Air Locks), 3.6.3....

S RDuke Energy.Duke Energy Corporation McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-9340 (704) 875-4800 OFFICE (704) 875-4809 FAXH. B. Barron Vice PresidentDecember 7, 2001U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington,...

Regulatory Guide 1.141, Containment Isolation Provisions for Fluid Systems.

U.S. NUCLEAR REGULATORY COMMISSION July 2010 Revision 1 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in im...

"Containment Sump Zone of Influence for Coatings."

_-__ __ _ _ _ . . _ _ _ . _ ._.MZION CALCULATION COVER SHEETZion Calculation No.:22S-B-040M-002DESCRIPTION CODE.: M00ZION NUCLEAR STATIONSYSTEM CODE:Primary ContainmentTITLE: Containment Sumo Zone ofInfluence for Coatines._REFERENCE NUMBERSTypeNumberType NumberAEDVS&L 202DITZD...

Kewaunee Nuclear Power Plant, Technical Specifications, Remove the Requirement to Have a Containment Spray Pump Suction Flow Path from the Containment Sump.

c. Containment Cooling Systems1. Containment Spray and Containment Fancoil UnitsA. The reactor shall not be made critical unless the following conditions aresatisfied, except for LOW POWER PHYSICS TESTS and except as providedby TS 3.3.c.1.A.3.1. Two containment spray trains ar...

App 3B to GESSAR, "Containment Loads."

. - = _ _ _ _ . - - - . _ . - _ . . - - _ . . _ _ . .-. .. ._ - . .-.- . -- .-.___-. - _. - . -. _ _ -_,i;GESSAR II22A7007238 NUCLEAR ISLAND.;Rev. Oii< >;e i4',if1,i<. ri ,',.!! APPENDIX 3B!l,4CONTAINMENT LOADStiiiI;e,| .'L';iii'i|ii;6;|.18202230022 820212-PDR ADOCK 050004471K...

Draft "Containment Event Analysis & Estimation of Source Term Frequencies."

r-_,ggy I'|DRAFT FOR REVIEWCONTAINMENT EVENT ANALYSIS AND ESTIMATIONOF SOURCE TERM FREQUENCIESbyA. S. BENJAMIN, V. L. BEHR,S. E. DINGMAN,J. M. GRIESMEYER, F. E. HASKIN, D. M. KUNSMAN,and W. B. MURFIN.SANDIA NATIONAL IABORATORIESALBUQUERQUE, NEW MEXICO871854MARCH 22, 1985|||2.8...

"Reactor Containment Bldg Integrated Leak Rate Test," final rept.

EBASCO SERVICES INCORPORATEDIEB6SCO.Two World Trade Center, New York, N.Y. 10048 PLANT OPERATIONS & BETTERMENT SERVICES INDIAN POINT NO. 3 NUCLEAR PUR-3R PLANT BUCHANAN, NEW YORK DOCKET NUMBER 50-286 REACTOR CoNTA2NMNT BUILDING INTEGRATED LEAK RATE TEST ____FINAL REPOTTHE STAT...

Rev 2 to CP 3804L, "PASS Containment Air Sample"

To Facility Address From Date/Time: DOCUMENT CONTROL DESK : MP Department : 806 : NUC REGULATORY COMMISSION (0140) DOCUMENT CONTROL DESK WASHINGTON, DC 20555NDS 03/27/01 09:32Trans No. : 000016317 Total Items: 00001CONT DOCUMENTSTransmittal Group Id: 01086KA-1PASSPORT DOCUMENT...

Application for amend to License NPF-38,revising allowable containment pressure operating range based on reanalysis of limiting peak containment pressure event (main steam line break).Fee paid.

f 11 .|9 _. i**j*ifLOUISIANA POWER & LIGHT COMPANY e Post Office Box 6008 New Orleans. louisiana 70174.J .1N%i MuNEW ORLEANS PUBLIC SERVICE INC. * Post Office Box 60340 = New Orleans. Louisiana 70160! = :=July 29, 1987W3P87-2006 IA4.05'{QAj{l!i.IU.S. Nuclear Regulatory Commiss...

BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 2.

BFN EPUContainment Overpressure (COP)Credit Risk AssessmentRev. 2Performed for:Tennessee Valley AuthorityPerformed by:ERIN Engineering and Research, Inc.July 10, 2006BFNEPU COP Probabilistic Risk AssessmentTennessee Valley AuthorityBrowns Ferry Nuclear (BFN)BFN EPUContainment ...

Proposed Tech Spec Change 87-33,amending Table 3.6-1 of Limiting Condition for Operation 3.6.1.2, "Containment Sys, Containment Leakage."

- - _ _ _ - _ - _ _ _ __ _ _ _ - .-..ENCLOSURE 1PROPOSED YECHNICAL SPECIFICATION CHANGESEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2DOCKET NOS. 50-327 AND 50-328i(TVA-SQN-TS-87-33)PROPOSED AMENDMENT TOLIMITING CONDITION FOR OPERATION (LCO) 3.6.1.2," CONTAINMENT SYSTEMS, CONTAINME...

"Reactor Bldg Containment Integrated Leak Rate Test," conducted 810214-15.

r<.. .9[ TENNESSEE VALLEY AUTHORITY'DIVISION OF NUCLEAR POWERF1l|'III'REACTOR BUILDING CONTAINMENTINTEGRATED LEAK RATE TESTSEQUOYAH NUCLEAR PLANT UNIT 2CONDUCTED FEBRUARY 14-15, 1981DOCKET NUMBER 50-328IIIIIISubmitted toThe Uniterf States Nuclear Regulatory Commission|Pursuant...

Proposed Tech Specs,incorporating Mark I containment mods.

_.COOPER NUCLEAR STATIONTABLE 3.2.FPRIMARY CONTAINMENT SURVEILLANCE INSTRUMENTATION-Minimum Number Action Required WhenInstrument of Operable Minimum ConditionInstrument I.D. No. Range Instrument Channels Not Satisfied (1).Reactor Water Level NBI-LI-85A -150" to +60" 2 A,B,CNB...

Hope Creek, HC.OP-EO.ZZ-0318(Q), Rev. 6, "Containment Venting."

PSEG Internal Use Only PSEG NUCLEAR L.L.C. Page 1 of 1 HOPE CREEK GENERATING STATION HC.OP -EO.ZZ-0318(Q) - Rev. 6 CONTAINMENT VENTING USE CATEGORY: I • Biennial Review Performed: Yes No NA 9 • Packages and Affected Document Numbers incorporated into this revision: C...

LER 99-009-00:on 990617,failure to satisfy secondary containment bypass leakage rate TS was noted.Caused by failure to properly classify containment penetrations. Procedures revised.With 990715 ltr.

lilinois Power Company=c P O Box 678Clinton. IL 61727 .Tel 217 935 8881 x3'.s00,Fax 217 935-4632 ,,John P. McElwainChief Nuclear OfficerP6WERm 323o2C.220An Illinova CompanyJuly 15, 1999Docket No. 50-461 10CFR50.73Document Control Desk ,Nuclear Reguistory Commission' Washington...

"Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept."

ARIZONA PUBLIC SERVICE COMPANYPALO VERDE NUCLEAR GENERATING STATIONUNIT NO. IREACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTS&1MARY TECHNICAL REPORTPREPARED BYWILLIAMD. ROMANARIZONA PUBLIC SERVICE COMPANYOPERATIONS ENGINEERING SECTIONMARCH 7, 1983~oWagseao+8304190464 830...

"Engineering Evaluation of Turkey Point Units 3 & 4 Containment Structures."

ENCLOSUREFLORIDA POWER & LIGHT COMPANYENGINEERING EVALUATION OFTURKEY POINT UNITS 3 & 4 CONTAINMENT STRUCTUREI'503010390 950220PDR ADOCK 05000250P PDRTABLE OF CONTENTS1.0 PURPOSE / SCOPE2.0 BACKGROUND3.0 ENGINEERING EVALUATIONJi.o CONCLUSION5.0 REFERENCESATTACHMENTS 1 & 2Enclo...

Proposed TS re containment sys testing & 24-month operating cycles.

ATTACHMENT I TO IPN-92-034PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO CONTAINMENT SYSTEMS TESTING AND 24 MONTH OPERATING CYCLES NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR-64 9207270005 92071 7- ... PDR ADOCK 05000286 P PDR* It pe...

Proposed tech specs re containment leakage A test schedule.

. -...4Rpeket No. 50-336B15013Attachment 1Millstone Nuclear Power Station, Unit No. 2Proposed Revision to Technical SpecificationsContainment Leakage Type A Test ScheduleMarked-up PagesOctober 19949410270317 941018PDR ADOCK 05000336PPDR-- -- . -. -$# " gi: 3, 1992- ....~Z-tc,-...

"Reactor Containment Bldg Integrated Leak Rate Test."

.-*.'.,|REACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTMay/ June 1987YANKEE ATOMIC ELECTRIC COMPANYR0WE, MASSACHUSETTS 01367Nhju0 0. 2

Forwards License Amend Request 91-08 to Licenses DPR-80 & DPR-81,revising TS 1.8, "Containment Integrity," 3.4.6.1, "Containment Integrity" & 3.4.6.3, "Containment Isolation Valves," per guidance in Generic Ltr 91-08.

ACCELERATED DIF~RIBUTIONDEMONS 4.TION SYSTEMcQ»g~~0tREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9201070273 DOC.DATE: 91/12/26 NOTARIZED: YESFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1,Pacific Ga50-323 Diablo Canyon Nuclear Power Plant, Unit 2, Pac...

Responds to DA Beckman 781220 request re containment Type A leak test.Test was performed during Nov 1978.After start of initial containment pressurization,personnel air lock was found at same pressure as containment (leaking solenoids).

.-, .-. sy_. - - ,.r ph-.=ent.t. :_. m .- - ,.d g LT.~r ?'"2 a *9.!Mii'Duquesne Ligit *j.. m*435 S sth Avenue . -HM2unA Pernsylvama. gyggggg Lyg*; ggyyA;,y1521%Ecaver Vality Pcuer Stationlost Office Eox 4*. Shippingport, PA 13077.Janca n 3, 1979-|idPS: JAW:t?Of,Beaver Llley Po...