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"Primary Containment Leakage Rate Testing,1980."

.. - -. ._._. ..- . . - . .. - - -. - . . -~. . . _ . --_ _ . -,. .,'|ijVERMONT YANKEE'PRIMARY CONTAINMENT LEAKAGE RATE TESTING4i'1980.:I,iTEST COORDINATORSiB.R. Webber;S.A. Vekasye!#1PREPARED BY:e,K.A. WhitneyiD.L. Phillipsj!B.R. Webberitis1 I4(.,Iii--!*.i,,I!ififI>.!>I-!:! 8...

Tech Specs re secondary containment instrumentation.

...:.. .*..4ENCLOSURE 3 (Revised)BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 ,'NRC DOCKETS 50 325 & 50 324OPERATING LICENSES DPR 71 & DPR-62REQUEST FOR LICENSE AMENDMENTSECONDARY. CONTAINMENT INSTRUMENTATION,iINSTRUCTIONS FOR INCORPORATIONThe proposed changes to the Technica...

Forwards Rev 15 to "Secondary Containment Leak Rate Signoff," performed on 841028.Satisfactory test results verify integrity of secondary containment.

,_. _ _ _ - -.SOSTON EDISON COMPANY800 BovLaTON STREETBOSTON. MASSACHUSETTS 02199wtLLIAM O. HARRINGTONJanuary 8, 1985 . . . .. . . . . . . . . .BEco Ltr. #85-002""* =Director. 0ffice of Nuclear Reactor Regulation-U.S. Nuclear Regulatory Commission. Washington, D.C. 20555ATTN: ...

CHEMISTRY AND TRANSPORT OF IODINE IN CONTAINMENT.

r" - ..4 INUREG/CR-4697ORNL/TM-10135,[_. _ -,(OAK RIDGENATIONAL::LABORATORYChemistry and Transport oflodine in Containment.. .MARTIN MARIETF"AE. C. BeahmW. E. ShockleyC. F. WeberS. J. Wisbey,Y.-M. WangoIPrepared for theU.S. Nuclear Regulatory CommissionOffice of Nuclear Regula...

Wolf Creek GS - Issuance of AMD. 152 Re: Containment Tendon Surveillance Program and Containment Leakage Rate Testing Program (Tac. MC1068).

March 17, 2004Mr. Rick A. MuenchPresident and Chief Executive OfficerWolf Creek Nuclear Operating CorporationPost Office Box 411Burlington, KS 66839SUBJECT: WOLF CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE: CONTAINMENT TENDON SURVEILLANCE PROGRAM ANDCONTAINMENT LEAKA...

PWR Containment Sump Evaluation Methodology (Draft).

PWR CONTAINMENT SUMP EVALUATION METHODOLOGY DRAFT October 31, 2003 PWR Containment Sump Evaluation Methodology Draft Acknowledgments This guidance document, PWR Containment Sump Evaluation Methodology, was developed by Westinghouse, Framatome ...

Monticello, Additional Containment Design Information.

NRC STRIBUTION FOR PART 50 DOC MATERIAL (TEMPORARY FORM) . CONTROL NO: 6005 FILE:FROM: Northern States. Power.Co. DATE OF DOC DATE REC'D LTR TVX RPT OTHER Minneapolis, Minn. 5540.1 ,L.0. Mayer 5-30-75 6-2-75 XX TO: ORIG CC OTHER SENT AEC PDR XX - Mr. D.L. Ziemann 1 signed 39 ...

Clinton Power Station, Unit 1, License Amendment, Re Operability Requirements for Primary Containment and Secondary Containment Systems.

April 3, 2002Mr. Oliver D. Kingsley, Presidentand Chief Nuclear OfficerExelon NuclearExelon Generation Company, LLC4300 Winfield RoadWarrenville, Illinois 60555SUBJECT: CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT (TAC NO. MB2572)Dear Mr. Kingsley:The U.S. Nu...

CBR012 - Appendix AA-3 - Hydraulic Containment Report.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD In the Matter of CROW BUTTE RESOURCES, INC. (Marsland Expansion Area) Docket No. 40-8943-MLA-2 ASLBP No. 13-926-01-MLA-BD01 Hearing Exhibit Exhibit Number: Exhibit Title: 123 North Colle...

Monticello Mark I Containment Information.

IRC FORM 195 U.S. NUCLEAR REGULATORY COMMISSION DOCKET'NUMBER , C DISTRIBUTION FOR PART 50 DOCKET MATERIAL FILE NUMBER TO: FROM: DATE OF DOCUMENT Northern States Power Company 3/8/77 Mr. Victor Stello Minneapolis, Minnesota . DATE RECEIVED L. 0. Mayer 3/15/77 WLETTER WNOTORIZE...

Proposed Tech Specs,incorporating new containment mini-purge sys & deleting requirements associated w/old 48-inch containment purge sys.

Attachment ARevise the Technical Specification pages as follows:Remove3.5-223.6-53.6-63.6-7'.6-113.8-14.4-74.4-8Insert3.5-223.6-53.6-63.6-73".6-7A3.6-113.8-14.4-74.4-8ggj0',031~0g000244jjg102>.DRPQOCKoPQRPITABLE 3.5-7,Radiation Accident Monitorin InstrumentationInstrument1. Co...

"Containment Leak Test." W/840823 ltr.

NIAGARAMOHAWKPOWER COMPANYNINE MILE POINTUNIT 1CONTAINMENTLEAKTEST8409110187840531PDRADOCK05000220PPDRe0V RIIIASA,IRA,g PgQog@%gRIP-9289T RUCLEA'RETATIOIQPITITIg:II'>"'INEMILE POIN 'OX 32 LYCOMING, NEWYORK 13093/TELEPHONE (315) 343-2110Augur23,1984A,. Thomas E. NurLeyRegs one ...

STEEL CONTAINMENT RESISTANCE UNDER GENERAL DYNAMIC PRESSURES.

. .. .NUREG/CR-4223,IS-4554Steel Containment ResistanceUnder GeneralDynamic PressuresPrepared by L. Greimann, F. Fanons, D Bluhm'Am:s LaboratoryPr:p: red forU.S. Nuclear RegulatoryC:mmission*e#38#!! e6o22eCR-4223 RPDR- _ , .. .- _ _ . _ . - . . _ _ _ . _ _ _ _ , - . . _ - - . ...

"Reactor Containment Bldg Integrated Leakage Rate."

REACTOR CONTAINMENTBUILDINGINTEGRATED LEAKAGERATEMay,1989forR.E.. GINNANUCLEAR POWER PLANTUNIT 0g"~K+4~8'Qi"'. rgm i.pi!uI!~i!X!'g l"iii!:/I/i/lillllI,I",,'ll;".'lI'IIXII'OCHESTERGAS AND ELECTRIC;r.;ORPORATIONP44ROCHESTER GAS AND ELECTRIC CORPORATIONTABLE OF CONTENTSSection It...

Requests info re potential for containment bldg explosions & Mark I containment structures.

,. .oo,OQMarch 25, 1980515 West Point AvenueUniversity City, Missouri 63130Office of public InformationU.S. Nuclear Reg. Comm.Washington, D.C.20555To Whom it May Concern:May I please have a copy of the report of NRC staff of-ficials released to the Commission March 21, 1980, r...

Rev 0 to General Test Procedure GT-M-106, "Containment & Containment Encl Surface Insp." Related documentation encl.

.GT-M-106REY. OPage 1 of 15.:SEABROOK STATIONGENERAL TEST PROCEDURE.GT-M-106CONTAINMENT AND CONTAINMENT ENCLOSURESURFACE INSPECTIO'Ni-',PREPARED BY: G. KannSECTIONTITLEPAGE1.0'''OBJECTIVES2I2.0REFERENCES230 PREREQUISITES34.0SPECIAL PRECAUTIONS35.0 INITIAL CONDITIONS36.0TEST IN...

"Reactor Containment Bldg:Integrated Leak Rate Test."

,g-,-,1- - - - -- - -.j, - - - ' - - - . - - - - - - - - ' NT-'-"--'--'---.g . e- ,' . . .4.,.. .~. sq . .. . .m~. e-o r . .,.,. . x. . .pr.N*, ? ' f, ., .f-~ '. -m. .p. . . >7s ,t .a.9swe.e9,.-.- - -..m vw-_; .... + .s.4.. ~.-e ... . *r.W ., . , , ,es*'. ; 4 's. s ei , f *w ....

Columbia Generating Station - Mark II Containment Program Letter Report, "Lead Plant Containment Response to Improved Chugging Load Definition," June 1978.

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >DISTRIBUTION FOR INCOMING MATERIALTOPREPQRG: SOBON L J DOCDATE: 07/07/78GEN ELEC DATE RCVD: 07/ii/78REC: STOLZ J FNRCDQCTYPE: LETTER NOTARIZED: NO COPIES RECEIVEDSUBJECT:REQUESTING WITHHOLDING PURSUANT TO 2. 790 INFO... FORWARD...

"Reactor Containment Bldg Integrated Leak Rate Test."

. ._'P;,rID/TS-4C,4D ,i'41.!REACTOR CONTAINMENT BUILDINGiINTEGRATED LEAK RATE TEST::;)i1,. ~~ .1iI49|QUAD-CITIES NUCLEAR POWER STATION;. UNIT TWOFEBRUARY 9-10, 1984iiifI (fI!i."'B405040288 840423PDR ADOCK 05000265Pf _ _ ,. PDR.-,-, ,>----.-e9-y e- er,, ,ww+-. ,,..,r, ,e.--es,-...

Proposed tech specs revising TS LCO 3.6.1.3.b of TS 3/4.6.1.3, "Containment Air Locks," Bases 3/4.6.1.4, "Internal Pressure," Bases 3/4.6.1.6, "Containment Structural Integrity" & Section 6.16, "Containment...."

ENCLOSURE 1PROPOSED AMENDMENTTO TECHNICALSPECIFICATION 3/4.6.1.3, Bases 3/4.6.1.4, Bases 3/4.6.1.6,and 6.16970i060ii0 '761227PDR *DOCK 05000528('PDRg(\ENCLOSURE 1The proposed Technical Specification (TS) amendment revises Technical SpecificationLimiting Condition for Operation...

Proposed Tech Spec Table 3.3.4 re primary containment isolation valves entering free space of containment.

ATTACHMENT ANIAGARA MOHAWK POWER CORPORATIONLICENSE DPR-63DOCKET NO. 50-220Pro osed Chan es to Technical S ecifications (A endix A)The existing page146 will be replaced with one of the two attached pages.These pages have been reprinted in their entirety with marginal markings ...

"Sequoyah Containment Analysis."

- _ _ee-.SEQUOYAH CONTAINMENT ANALYSIS1. INTRODUCTIONThis letter report is in respon".a to a request from theU.S. Nuclear Regulatory Commission to review and critique theultimate strength analyses of the Sequoyah containment.The description of the containment vessel and the an...

"Feasibility of Predicting Containment Leak Rate."

.\/s,FEhSTRTTTTY & PIIEDICTDE GMRIIEE!NT IJIhK MEECharles K. BayneCaputer Sciences DivisionUnion Carbide Corporation-Nuclear DivisionOak Ridge, Tennessee,8506180158 850325PDR FOIAREYTBLA85-143 PDR. . _ . . _ - _ _ _ ._ _ _ _ . . ._- . _ . . . . _ . . _ _ _ _ - . - _ _ _ _ _ _....

"Addendum to Reactor Containment Bldg Integrated Leak Rate Test Conducted 860520-26.Investigation of Containment Deviations From 'As-Found' Conditions."

3-.DUKE POWER COMPANY.MCGUIRE NUCLEAR STATION.UNIT 2ADDENDUM TO THEREACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTCONDUCTED MAY 20 - MAY 26, 1986INVESTIGATION OF CONTAINMENT DEVIATIONS FROM; "AS FOUND" CONDITIONS;|[ //] A Add //Prepared By: _xzaw~ L //w' Kephen'K. Morale...

Proposed TS Surveillance Requirement 4.6.1.2, "Containment Leakage."

_,..ATTACHMENT 2PROPOSED CHANGES TO APPENDIX ATECHNICAL SPECIFICATIONSFORFACILITYOPERATING LICENSES NPF-37, NPF-66, NPF-72, and NPF-77AFFECTED PAGE INDEXByron Revised Page: 3/4 6-2Braidwood Revised Page: 3/4 6-29403160060 940307PDRADOCK 05000454Ppyg*..'1.1|CONTAINMENT SYSTEMSC...