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TSTF-312, R.1, "Administratively Control Containment Penetrations."

(WOG-76, Rev. 1) TSTF-312, Rev. IIndustry/TSTF Standard Technical Specification Change TravelerAdministratively Control Containment PenetrationsClassification: 5) Plant VariationNUREGs Affected: dV 1430 V. 1431 R 1432 1433 r 1434Description:Add a note under LCO 3.9.4 allowing ...

App C, "Containment Analyzer Seismic Test."

.-rs g.m,,- - _ _ _ _ - - _ . ._ . - -- -- - - - - - - - -- -- -- - - -:t!---_ ... . ...2g. ,g; -' "-. --. . _u?1-p:.,...= .--w.'::~..ag y . x.. ..g.,'$h' #'' '.fi-y c ....;vf, g~$.:*,. _ .t--eet , .,Y. -7**,I-~' i. *)''t: r, y] .f.~ . ;\;!V '1 n . . -,--.:.%:i*,> .a.i.-i ms~q...

LER 90-008-00:on 900627,containment air temp exceeded Tech Spec limit resulting in plant shutdown.Caused by unavailability of containment chilled water units.Tube leak on containment chiller repaired.W/900727 ltr.

. . . . . .i p-- ' Ctmmsnw3Elth Edison ! .j-..Byron Nuclear Station- .* '4450 North German Church Road ,.J,-* -Byron, Illinois 61010July 27, 1990.Ltri BYRON 90-0700U. S. Nuclear Regulatory _ CommissionDocument Control Desk--Washington, D.C.- 20555,Dear' SirThe enclosed T.icens...

Proposed Tech Specs,clarifying Section 1.8.2.b definition of containment integrity & effecting surveillance requirements for manual containment isolation valves.

.-_____- _ _____ -___ - _ _ ..>-..44Docket No. 50-213<,.f.bi1|Attachment 1Haddam Neck Plant-*Proposed Revisions to Technical SpecificationsSurveillance Requirements - Isolation Valves:!1if'1iji;i!>1?sit,.P4August,1986.'fi$8609110250 060929PDR ADOCK 05000213P PDR. . . _ _ . _ _...

Proposed tech specs 1.6 re channel functional test,1.7 re containment vessel integrity,1.8 re controlled leakage,1.9 re core alteration,3/4.6 re containment systems & 3/4.6.1 re containment vessel.

ATTACHMENT 3PROPOSED LICENSE AMENDMENT FORIMPLEMENTATION OF 10 CFR 50~ APPENDIX iT OPTION B1-23/46-1thru 3/46-113/46-143/46-18 thru 3/46-223/46-31B3/46-1B3/46-26-15bInsert PagesVhiiOf0271961028PDR ADOCK 05000335PPDR1.6 A CHANNELFUNCTIONALTEST shall be the injection of a simula...

"Hydraulic Calculation for Containment Hose Reel Project."

_ _ _ _ _ _ _ _... ,.-~ARKANSAS NUCLEAR ONE' -.UNIT-2-CALCOLATION#GE-790-02085-02.|HYDRAULIC CALCULATIONFOR THEANO-2 CONTAINMENT HOSE REEL PROJECTi!.Prepared by: M'Checked by: [[ MeApproved b-|||''~FEBRUARY 4, 1980|.|-'ci!i800.4150579_ _ - _ _ _ -_ _ _ . _ _ .. -. - _. . - - -...

Notifies of 800415 test of containment area monitors fulfilling util 800227 commitment to relocate containment area radiation monitor.

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 • (617) 788-0660 May 27, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Projects Branch No 5 US Nuclear Regulatory Commission Washington, DC 20555...

Proposed tech specs re surveillance requirements for areas within containment.

• , ATTACHMENT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION REVISION OF SURVEILLANCE REQUIREMENTS FOR AREAS WITHIN CONTAINMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 NLR-N94171 DOCKET NOS. 50-272...

Proposed Tech Specs re containment leakage tests.

_,.'. . . - .03GhINElfT S15HBE.l. 03fN.IMENT IEhKAGEIaxrrnc rnenwrnr FaR OMWPION/ 3.6.1.2Containment leakage ratts shall be limited to:An overall integrated rate of 5 Ig, 0.25 percent by weight of thea.containment air per 24 hours at 2 P , 53.3 psig.ab.A canbined leakage rate ...

Proposed improved TS Section 3.6 re containment sys.

II|l|McGuire & Catawba Improved T Review CommentsITS Section 3.6, Containment Systems(3.6.1 -2 DOC A.3DOC LA.1JFD 6JFD Bases 6CTS 4.6.1.1.cCTS 3.6.1.2.a. b, and c!CTS 4.6.1.2.d|CTS 4.6.1.2.d. 3)CTS 4.6.1.2.e, h, and iCTS 4.6.1.6STS SR 3.6.1.1ITS SR 3.6.1.1ITS B3.6.1 Bases|CTS ...

LER 84-011-01:on 841129,leak path opened from outside containment to outside containment,violating containment integrity.Caused by opened vent valve allowing svc water line to drain for welding repairs.W/841227 ltr.

Nm..e.NRC Per. MS U.S. NUCLEI 4B REGULATORY -_APPROVE 3 OMS NO. 3190-4104'"""Es. e/3umLICENSEE EVENT REPORT ILER)PACILITV NAAsE til00CRET NUaSER talPAGE WH. B. Robinson 0 |5 | 0 |o | 0 |2 I 6| 1 1|OF| |,TITLE leSYSNT DATE ISI LER NUtegn Igl REPORT Daft 179 OTMER PACILITtGS INV...

Proposed tech specs for containment airlock,updating leakage test requirements.

ATTACHMENT 3 AFFECTED PAGES FOR PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES DPR-19. DPR-25. DPR-29 AND DPR-30 DRESDEN AND QUAD CITIES STATIONS DPR-19 DPR-25 DPR-29 DPR-30 iii iii v v 1.0-3 1.0-3 1.0-3 1.0-3 3/4.7-7 3/4.7-7 3.7/4.7-5 3...

0518 - R304B - GE BWR_4 Technology - 4.0 Containment Systems.

General Electric Systems Technology Manual Chapter 4.0 Containment Systems Rev 09/11 4.0-i USNRC HRTD TABLE OF CONTENTS 4.0 CONTAINMENT SYSTEMS ................................................................................... 1 4.0.1 Primary Conta...

Containment Protective Coatings Research

Prepared for Presentation at the ASTM D-33 Committee January 2000 MeetingAleck W. Serkiz, USNRC/RES/DET 301-415-6563, aws@nrc.govAccession No. ML0036813131Containment Protective Coatings ResearchWhy Needed ?1. Failed coatings represent an undesirable debris sourcewhich could...

Clarifies operation of reactor containment bldg carbon filter units prior to containment purge,per SER,Section 11.3.1.Requests that SER be amended to delete statement re circulation for 16 h through containment cleanup sys.

. . _ . ..6The Light.companyllouston I.ighting & Power 5""'h II[* *"' "'"I'_*'_I''IP "ij"_'"*'*'I"" S' *'_i"" P' "'_""* 2 89 * * d "."" h'_ Il* * *'_7 7i 8 3 i __ .September 18, 1992'ST-HL-AE-4201File No.: G 09 .1P.10 C.'R50. 71S. Nuclear Regulatory Commission:ention: Document...

"Reactor Containment Bldg Integrated Leak Rate Test."

DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 1 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST AUGUST 1983 8405040075 840420 PDR ADOCK 05000269 p PDRDUKE POWER COMPANY Oconee Nuclear Station Unit 1 Reactor Containment Building Integrated Leak Rate Test Prepared by Z< ...

ASLB - G114 - Seminar for ASLBP Personnel - BWR - 09 - Containment Systems.

NUCLEAR REGULATORY COMMISSION Reactor T echnology Training Branch Part II Introduction to Reactor Technology Chapter 9.0, Containment Systems Rev 0707 USNRC HRTD 9-2UNITED STATES NUCLEAR REGULATORY COMMISSION HUMAN RESOURCES TRAINING & DEVELOPMENT Introduction to Reactor...

Duane Arnold Energy Center - Second 10-Year Containment Inspection Plan.

FPL Energy Duane Arnold, LLC3277 DAEC RoadPalo, Iowa 52324FPL Energy.Duane Arnold Energy CenterNovember 16, 2007 NG-07-087810 CFR 50.55aU.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Duane Arnold Energy CenterDocket No: 50-331Op. License ...

Corrected proposed Tech Specs re containment isolation sys.

;' ' . " ,.,~ .. •. O' ./ • • ---------- - - - ----- --- ---~- - - -- - -- ------ - - - - - --- - ---- ---- - ---- - - - ------ - - - - ·--- ------- ----ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 CORRECTED PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES 890...

0518 - R304B - GE BWR_4 Technology - 4.2 Secondary Containment System.

General Electric Systems Technology Manual Chapter 4.2 Secondary Containment System Rev 09/11 4.2-i USNRC HRTD TABLE OF CONTENTS 4.2 SECONDARY CONTAINMENT SYSTEM .............................................................. 1 4.2.1 Introduction .......

SECY-18-0096: Enclosure 1 - Functional Containment Performance Criteria Background

Enclosure 1 Enclosure 1: Functional Containment Performance Criteria Background One of the fundamental safety functions of nuclear power reactors is limiting the release of radioactive materials from the facility. The designs of the containment systems for most plants lic...

Proposed tech specs 3.6.1.5 re containment systems & air temp.

._ _----_ . _ _ --- _ _ _ _ _ _'j .1j..4.|!ji| ATTACHMEXT 14;|i!\jiIa!DUKE POWER COMPAXY!McGUIRE XUCLEAR;! STATIOX i:iPROPOSED REVISIOXTO THETECHNICALSPECIFICATION!9610290206 961022PDRADOCK 05000369pPDR. .. .CONTAINMENT SYSTEMS(AIR TEMPERATURE -LIMITING CONDITION FOR OPERATION...

Proposed TS 3/4 6-11 re surveillance requirements for containment sys,3/4 6-12 re limiting condition for operation for containment cooling sys & 3/4 6-15 re surveillance requirements for containment sys.

'. . ....ATTACHMENT (1),UNIT 1TECHNICAL SPECIFICATIONREVISED PAGES3/4 6-113/4 6 ^3/4 6-15.;8Poa868R7488810pPDR_ . . _ . . _ ..."- |.- CONTAINMENT SYSTEMS..(ISURVETLLANCE REOIRREMENTS (Continued)''b. At it.tt once per refueling interval, during shutdo'wn, by:1.-Verifying that e...

"Containment Recirculation Sump Hydraulic Performance, SNUPPS."

.- . . ,.: ...:.. . . ._..*.... a_- de(f@4 . . .. : ,. s..:-; - ,:f. $,,--w c ,. nj i.s.CONTAINMENT RECIRCULATION SUMPf . w$ffX..-.Y: u.ft "HYDRAULIC PERFORMANCE-- -.2WSTANDARDIZED&..#~9. . .i- , 4 s. .NUCLEAR UNIT POWER PLANT SYSTEMyp!J: 74tr .- . A%(SNUPPS)J. ,S ,',. |'&; N....

"Containment Vessel Evaluation."

February 1, 1982ROBERT E. GINNA NUCLEAR POWER PLANTCONTAINMENT VESSEL EVALUATIONbyJ. F. FultonS. S. HsiehPREPARED FORROCHESTER GAS AND ELECTRIC CORPORATIONPREPARED BYGILBERT/COMMONWEALTHREADING, PENNSYLVANIAQberC /Commonwealth8202240085 8202i8PDR -ADOCK 05000244,P;,;.";*.PDR,'...