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Application for amend to License DPR-49,revising LCO & surveillance requirements for primary containment integrity, secondary containment integrity & other sys & equipment of TS Section 3.7, "Containment Sys."

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULAI1 INFORMATION DISTRIBUTIO*YSTEM (RIDS)ACCESSION NBR:9204070327 DOC.DATE: 92/03/27 NOTARIZED: YES DOCKET # FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTH.NAME AUTHOR AFFILIATION FRANZ,J.F. Io...

Forwards Containment Sys Branch request for addl info re containment & subcompartment analysis & combustible gas control,containment spray,isolation & shield bldg ventilation sys,per review of PSAR.

.,n.-..~,- ~ , u n .. ... ., n w.-- . . - ~ - - --en .. _ - - . -... htf.th~,O'? x ' _ jf;G |"~. W.&i p$DI';%).?m%[?)f Q[-tf4'MR M dihn%n_fAf..a. hg p: 4J~?.M.w J.; .:w&1wxau,. . ..%..'gp 3 01974!,.f Dockat'Nos. ~50-508/509v,, ..'-;.,. .. ~ . ...,e..: m.n... ' . _ -,-g, , ,, -...

Amend 57 to License DPR-21,changing TS,per NUREG-0737 & Generic Ltr 83-36 re containment high-range monitors, containment pressure monitors & containment water level monitors.

. . _ _ _ _ . _ _ . _ . . . . . _ .:*, . .1 ). M Cfg'c5 %c'-!*": .|* ?- * *UNITED S7" a-I i-.NUCLEAR'REGUl *~ ,r6 COMMISSION*b 1 W ASHit. TON, D.C. 20666 -'y\'/*****. , !NORTHEAST NUCLEAR ENERGY COMPANY- ,' DOCKET NO. 50-245 i'tILLSTONE NUCLEAR POWER STATION. UNIT 1AMENDMENT-T...

Summary of R1 Containment Vents.

Summary of Region I BWR Containment VentsPrepared by the Senior Reactor AnalystsFebruary 2012Summary:There are 8 Mark I Containments in Region I (Nine Mile Point Unit 1, Vermont Yankee, Oyster Creek, Pilgrm, FitzPatrick, Peach Botom Units 2and 3, Hope Creek)o All have a harden...

Proposed Tech Specs reflecting revised sections re primary containment & primary containment testing.

,._ _ _ . _ - - - -SurveillancePage No.3.7 . CONTAINMENT SYSTEMS 4.7 152A. Primary Containment A 1528. Standby Gas Treatment System B 158C. Secondary Containment C 15913.8 RADI0 ACTIVE MATERIALS 4.8 177A. Liquid Effluents A 1778. Airborne Effluents B 179C. (Deleted)D. Environm...

Proposed TS 3.9.4, "Containment Bldg Penetrations" & bases section,allowing containment personnel airlock doors to be opened during core alterations & movement of irradiated fuel in containment & TS 4.9.4.

..*.Attachment IV to ET 95-0100.,.Page 2 of 5'** . ',,R'EFUELING OPERATIONS,3/4.9.4 CONTAINMENT BUILDING PENETRATIONSLIMITING CONDITION FOR OPERATION3.9.4 The containment building penetrations shall be in the following status:a. The equipment door closed and held in place by a...

Application for amend to License NPF-3,changing TS Definition 1.8, "Containment Integrity," TS 3/4.6.1.1, "Containment Integrity & Bases," TS 3/4.6.1.2, "Containment Leakage" & TS 3/4.6.1.3, "Containment Air Locks."

- - . . . . . .Docket Number 50-346-.-o License Number NPF-3Serial Number 1971Enc 40sure'Page 1.APPLICATION FOR AMENDHENTTOFACILITY OPERATING LICENSE NUMBER NPF-3DAVIS-BESSE NUCLEAR P9VER STATIONUNIT NUMBER 1Attached are requested changes to the Davis-Besse Nuclear PowerStatio...

"Reactor Containment Bldg ILRT Rept."

,_- . . . . . _ . . .!>I. .!'|GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION; .|Three Mile Island Nuclear Station !!Unit I|| i|| |'|IREACTOR CONTAINMENT BUILDING INTEGRATEL)ii'LEAKAGE RATE TEST REPORT!||iii(;September, 19931I:I.tILRT Sections Prepared By: h AA d Date: t t-2- 4- ...

FLOW DIAGRAM CONTAINMENT HYDROGEN CONCENTRATION MEASUREMENT & POST ACCIDENT CONTAINMENT VENTING SYSTEM.

/4" HOKE #2413X13 WITH 3" LONG WELDING EXTENSION. (TYP.FOR 3)-PRESSURIZATION AIR. FOR CONTINUATION SEE DWG 9321-F--27263PS-PCV-I1101768VENTING SYSTEM SEE NOTES #5 & 6GENERAL NOTES: I- ALL PIPING IS IN ACCORDANCE WITH SPEC. 6604-104-248-4 CLASS 15IR & 153R AS NOTED. 2- A DENO...

Containment of a Reactor Meltdown.

JAN BEYEA and FRANK VON HIPPEL Containment of a reactor meltdown Any good scientist or engineer be- reactor failing, the fuel melting and (NRC), its successor in the area of lieves implicitly in Murphy’s law: “If the volatile radioactive isotopes in the nuclear safety regulati...

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

• Commonwealth.ison One First National Pl , Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 May 30, 1978 :.~J ·--.\ Mr. George E. Lear, Chief Operating Reactors - Branch 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washing...

Iodine Behavior in Containment.

Iodine Behavior in ContainmentJungsook Clara WrenAECL Chalk River LaboratoriesPresented to US Nuclear Regulatory CommissionWashington DCMay 6-7, 2003Pg 2Background• Iodine is the single most important nuclide with potential for public dose in the event of a severe core damage ...

Application for amend to license NPF-42,revising TS 1.7, "Containment Integrity," TS 3/4.6.1, "Containment Integrity" & TS 3/4.6.3, "Containment Isolation Valves."

'?; .!:,. ;'Iit /|T!f JiLW9LF CREEK!'~INUCLEAR OPERATING CORPORATION !|! Richard A. Muench IVice President EngineeringilFebruary 17, 1997IET 97-0003!U. S. Nuclear Regulatory CommissioniATTN: Document Control Desk 1Mail Station P1-137 iWashington, D. C. 20555Reference: 1) Lette...

Forwards design info for NUREG-0737 Items II.F.1.4, "Containment Pressure Monitors," II.F.1.5, "Containment Water Level Monitors" & II.F.1.6, "Containment Hydrogen Monitors."

4|'o1Northern States Power Company414 Nkollet Mallv,nneapons. Minnesota 55 01Telephone (612) 330-5500December 31, 1981~'DirectorOf fice of Nuclear Reactor RegulationJ-%Attn: Document Control Desk-hU S Nuclear Regulatory Commission _J[JJ g y, g ,. 7Washington, DC 20555'g.~-]'PR...

Hydrogen Behavior in Containment.

Hydrogen Behavior in ContainmentCalvin K. ChanExperimental Thermalhydraulics and Combustion BranchPresented to US Nuclear Regulatory CommissionWashington DCMay 6-7, 2003Pg 2Outline• Phenomenon and Definition• Limited and Severe Core Damage Accidents• Hydrogen Source Terms• R&D...

Forwards "Primary Reactor Containment Integrated Leakage Rate Test" & "Primary Reactor Containment Structural Integrity Test."

REGULATO INFORMATION DISTRIBUTION STEM (RIDS) ACCESSION NBR:8103100390. DOC.DATE: 81/03/06 NOTARIZED: NO DOCKET # FACIL:50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361 AUTH.NAME AUTHOR AFFILIATION BASKIN,KP. Southern California Edison Co. RECIP.NAME. REC...

"Containment Vessel Stability Analysis."

_ _ _ _ . _ - . . . _H!pfHARSTEAD ENGINEERING ASSOCIATES * INC.v169 KINDERKAMACK ROAD, PARK RIDGE, N.J. 07656 * Phone:(201)3912115||.CONTAINMENT VESSEL STABILITY ANALYSISCATAWBA NUCLEAR STATION, UNITS 1 & 2DUKE POWER COMPANYREPORT NO. 8106-2 ,MAY 27, 1982-Prepared by: .A. I. U...

LER 90-013-00:on 901022,actuation of containment weld channel & containment penetration pressurization sys occurred.Caused by change in containment cooling fan operating configuration.W/901121 ltr.

Stephen B. Brain Vice PresidentConsolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116November 21, 1990Re: Indian Point Unit No. 2 Docket No. 50-247 LER 90-13-00 Document Control Desk US Nuclear...

Provides justification for containment purging w/flow diagram of primary containment atmospheric control sys.

-.,.~'i' ))'VERMONT Y ANIWE NUCLEAR 130WER COR PORATIONSCVENTY SEVEN GROVE STREETB.3.2.1FC 76-2RUTI. AND, VEltMONT 05701HE PLY TO:January 9, 1979ENGINEERING OFFICETURNPlKE RO AoWESTDORO, M ASS ACHUSETTS 01581TELEPHONE 617-366-9011Ur.i':ed States Nuclear Regulatory CommissionWY...

Containment Design Perspectives.

12. Containment Design PerspectivesThe exceptions are the Prairie Island 1&2 and Shearon Harris IPEs. In the Prairie Island l&2 IPE, the conditional probability of bypass is almost 45% of total CDF, of which two-thirds is attributed to temperature-induced SGTR and one third to...

Documents containment margin improvement program.

PRI(3RI EY 1.ACCELERATED RIDS PROCESSINGREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION N5R:9512150207 DOC,.DATE: 95/12/11 NOTARIZED: NOFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1, Pacific Ga50-323 Diablo Canyon Nuclear Power Plant, Unit2,Pacific GaAUTH.N...

Forwards response to 800820 ltr re manual sys level actuation features for containment isolation & containment spray.Discusses proposed mod to containment ventilation isolation circuitry.

Peter Zaralkas Consolidated Edison Company of New York, Inc. 4 Irving Place, New York, NY 10003 Telephone (212) 460-3000 September 22, 1980 Re: Indian Point Unit No. 2 Docket No. 50-247 Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga, Chief Operating Reactors...

Proposed Tech Specs re surveillance requirements for containment sys & Bases Section 3/4 3.1.2, "Containment Leakage."

- - _ _ - _ _ _ _ _ _ _ _ _ . . ,h'I. ..*.eENCLOSURE 1PROPOSED TECHNICAL SPECIFICATION CHANGESEQUOYAH NUCLEAR PLANT UNIT 1DOCXET NO. 50-327m(TVA-SQN-TS-89-14)LIST OF AFFECTED PAGES~Unit 13/4 6-33 3/4 6-1siPDC_ - _ _ _ - _ - _ _ _ _ _ _ _ - - - _ - _ -_ _ _ _ - _ - _8 4.CONTAIN...

Containment Backpressure for ECCS Kewaunee Power Plant.

JUN 2 1975 Docket No. 50-305 V. Stello, Assistant Director for Reactor Safety, TR CONTAINMENT BACKPRESSURE FOR ECCS KEWAUNEE POWdER PLANT (TAR-1557) Originating Organization: Wisconsin Public Service Corporation Responsible Branches: RSB; ORB-1 Principal Reviewers: A. Thadani,...

Proposed Tech Spec 5.4, "Containment," deleting general statements made about containment penetrations & associated basis.

__4'W,-Docket No. 50-213B12601Attachment iHaddam Neck PlantProposed Revision to Technical SpecificationsContainment Penetration,JSeptember 1987B709150348 870909PDRADOCK 0F000213'.-1PPDR1-_-_________O, __ __-- _ _'.t4y*L|'5.4 ContainmentApplicability:Applies to those design, fe...