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Responds to questions related to use of nonsafety-related coatings inside containment & on exterior of containment shell,to support 980211 meeting to discuss paint & other coatings in AP600 containment.

_ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ _.er.'" Westin'ghouseEnergy SystemsBox 355Electric CorporationPittstugh Pennsylvania 152304 355DPC/NRC1251NSD NRC 98 5565February 10,1993Document Control DeskjU.S. Nuclear Regulatory Commission1 h

"Reactor Containment Bldg Integrated Leak Rate Test." W/870625 ltr.

'!' Dresden Unit ·2 Reactor Containment·Building Integrated Leak Rqte Test . ',l ·~' ----r-·-·····- ---.-----·-. · ---·-'-1 . i (-. -.;...8-7~0-7_0_1_0_5_30 __ 8-709"30 ( ,, l ... .PDR·· · ADOCK 05900231 /.; . 1 •• ·1 P . . PDR 1 .: \ -·I" . ' . . . _J ' ' ~~ l _, -~ .,,! Marc...

Forwards containment mod supplemental rept for review.Rept describes initial Type C containment leakage rate test conducted between 871026 & 1208.

'4OCommonwealth Edison-'s- / One First N;tional Plan, Chicago, lilinois\<3"J Address Riply to: Post Office Box 737(f Chicago, lilinois 60690 - 0767 'December 17, 1987Mr. Thomas E. Murley, DirectorOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington,...

Chapter 5 to Indian Point,Unit 2 PSAR, "Containment Sys."

5.0 CONTAINMENT SYSTEM5.1 CONTAINMENT SYSTEM STRUCTURE_ 5.1.1 DESIGN BASIS The reactor containment completely encloses the entire reactor and reactor coolant system and ensures that essentially no leakage of radioactive materials to the environment would result even if gross f...

Proposed Tech Specs,adding containment isolation valves & containment penetrations to Tables 3.6-1,3.6-2a & 3.6-2b & deleting info no longer applicable.

. ..'Pog{ g,h{ _So,ng ( fa.nc bI'88Co - 4 ushum o /t~88 $ (/DD n5SECONDARY C0!4TAINMEllT BYPASS LEAKAGE PATHSon >I PENETRATIONTEST''$$ .NUMBER SERVICERELEASE LOCATIONTYPEooty8$ :c 'M386 Containment Air ReleaseAuxiliary Building Type CZEON" v1'.OM204 Containment Air AdditionAux...

"Outside Containment Limitorque Wire Rept."

TURKEY POINT LI.l TORQUE WIRE REPORT page Z o f'>0FLORIDA POWER AND LIGHT COMPANYTURKEY POINT UNITS 3 AND 4OUTSIDE CONTAINMENT LINITORQVE WIRE REPORTJPE-PTPO-87-35087i2i50096 87i2iiPDRADQCN, 05000250PPDRJjlTURKEY POINT'LIN RQUE WIRE REPORTpage 3 of 20TABLE OF CONTENTSSect'ion....

NUREG/CR-6906, "Containment Integrity Research at Sandia National Laboratories."

NUREG/CR-6906SAND2006-2274PContainment Integrity Research atSandia National LaboratoriesAn OverviewSandia National LaboratoriesU.S. Nuclear Regulatory CommissionOffice of Nuclear Regulatory ResearchWashington, DC 20555-0001S RGAVAILABILITY OF REFERENCE MATERIALSIN NRC PUBLICAT...

Forwards info re reanalysis of main steam line break inside containment,per NRC Bulletin 80-004.Reanalysis of containment response determined that containment design pressure exceeded w/o operator action to isolate feedwater.

ACCELERATU. DOCUMENT DISTRIBUION SYSEM1v REGULATOR INFORMATION DISTRIBUTION OSTEM (RIDS) ACCESSION NBR:9306070393 DOC.DATE: 93/05/27 NOTARIZED: NO DOCKET # FACIL:50-269 Oconee Nuclear Station, Unit 1, Duke Power Co. 05000269 50-270 Oconee Nuclear Station, Unit 2, Duke Power Co...

Regulatory Guide 1.141, Containment Isolation Provisions for Fluid Systems

U.S. NUCLEAR REGULATORY COMMISSIONREGULATORY GUIDE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.141 CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMSA. INTRODUCTION General Design Criteria 54, 55, 56, and 57 of Appendix A, "General Design Criteria for Nuclear Power Plan...

"Containment P/T Analysis for Design Basis MSLB - Suppl B."

i 1-,e||'|N-4080-027 Suppl A&B Rev 0: MSLB Containment P/T.|{9606040039 960529PDR ADOCK 05000361P PDR_ _ _ . _ _ . - - - -- - .- - -CALC. NO.PAGE TOTAL NO. OFSouthern California Edison CompanyN-4080-027ICm e 'N-2 1 PAGESgg,(fEEUM.C h O.INTERIM CALCULATIONBASE CALC. REV.UNIT CC...

RISK IMPORTANCE OF CONTAINMENT AND RELATED ESF SYSTEM PERFORMANCE REQUIREMENTS.

-_ -NUREG/CR-6418BNL-NUREG-52489Risk Importance of Containmentand Related ESF SystemPerformance Requirements|iIPrepared byILP. Nourbakhsh, A.L. Ilanson, W T. PrattIBrookhaven National LaboratoryPrepared forU.S. Nuclear Regulatory Commission...o ,if 'ge.E jf , -{'% +!h"98112302...

Provides results of containment valve torque & stress analysis completed by Henry Pratt,Co,valve manufacturer. Containment purge valves operable under DBA-LOCA conditions. Forwards completion of containment purging justification.

REGULATORY INFORNATIOM DISTRIBUTION SYSTEN (RIDS)ACCESSIOM MBR:80121502 DOC. DATE; 80/12/09 NO IZED: NOFACIL: 50-335 St. LucieWlanti Unit 1 i Florida Power 8c Light Co.AUTH. MAt'tE AUTHOR AFFILIATIONUHRIGs R. E. Florida Power 5 Light Co.REC IP. NAt'IE RECIPIENT AFFILIATIONCLAR...

Forwards "Reactor Containment Bldg Integrated Leak Rate Test."

"!) '" •. ... ;· .. ~. ~ ' ' • Commonweal di son · One First National P aza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 · BBS LTR: 79-479 Mr, Harold R. Denton Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Corrnnission Washi...

Proposed Technical Specification Changes Deleting The Requirements For The Containment Purge And Exhaust System And Revising The Containment Penetration Requirements Of Specification 3.9.4

Entergy Operations, Inc. -E nitcergy{ 1448 S.R. 333 E..._W Russellville, AR 72801 Tel 501-858-4888 Craig Anderson Vice President Operations ANO August 10, 2000 2CAN080002 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OP 1-17 Washington, DC 20555 Subje...

NuScale Design-Specific Review Standard Section 6.2.1, Containment Functional Design.

ADAMS Accession No. ML15356A259 U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD for NuScale SMR DESIGN 6.2.1 CONTAINMENT FUNCTIONAL DESIGN REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of Containment Integrity Secondary - ...

Proposed tech specs re containment spray pump differential pressure.

,Enc 1:sure 1 to TXX 95050Page 1 of 5TECHNICAL REQUIREMENTS MANUAL-TABLE OF CONTENTSTECHNICAL REOUIREMENT NUMBER SYSTEM / TITLE-(Related Tech Spec _if required)0Administrative Controls0.1 (1.0)- Definitions0.2 (3/4.0)Applicability1.1 (3/4.3.1)Reactor Trip Response Time1.2 (3/4...

Proposed Tech Specs,incorporating mods to containment leak test program.

ATTACHMENT AINIAGARA MOHAWK POWER CORPORATIONLICENSE NO. OPR-6300CKET NO. 50-220Pro osed Chan es to Technical S ecifications endix AReplace the existing pages with the attached revised pages as shown below.These pages have been retyped in their entirety with marginal markings ...

Proposed Tech Specs 4.6.1.2.a re containment sys.

:..- ..,**.,' '3/4.6 CONTAINMENT SYSTEMS-3/4.6.1PRIMARY CONTAINMENTCONTAINMENT INTEGRITY'LIMITING CONDITION FOR OPERATION3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.APPLICABIL111: MODES 1, 2, 3, and 4.ACTION:Without primary CONTAINMENT INTEGRITY, restore CONTAINM...

Proposed Tech Spec changes,moving tables listing secondary containment bypass leakage paths & containment isolation valves into bases,adding three penetrations & updating tables for planned mods.

f9 hATTACHMENT 1PROBOSED TECHNICAL TECHNICAL SPECIFICATION CHANGES-8605200071 860514PDR ADOCK 05000369p PDRL., - _- -. ,(3/4.6 CONTAINMENT SYSTEMS3/4.6.1PRIMARY CONTAINMENTCONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION3. 6.1.1Primary CONTAINMENT INTEGRITY shall be maint...

Forwards License Amend Request 93-05 to License NPF-86, changing TS to permit mod of containment structure air purge & heating subsystem to provide more reliable means of containment isolation for two containment penetrations.

c..' ''' eabr k NH 03874,Telephone (603)474-9521f=h ( Facsimile (603)474-2987Energy Service CorporationTed c. Feigenbaum'Senior Vice President andChief Nuclear Officer -NYN-93070May 7,1993United States Nuclear Regulatory CommissionWashington, D.C. 20555Attention: Document Cont...

Proposed tech specs 4.6.2.3 re containment cooling sys.

-.'Att~ chm *nt V t0 ET 91-0135' Pag] 1 of 5.ATTACIMENT VPROPOSED TECIINICAL SPECIFICATION CllANCE.9109170172 910911PDR ADOCK OSOC0482P PDR--' Attachment V to ET 91-0135'Page 2 of 5-*r! ,.CONTAINMENT SYSTEMSfIiCONTAIN'4ENT COOLING SYSTEMLIMITING CONDITION FOR OPERATION |P3.6.2...

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

Secondary Containment System y304B Chapter 4.2Objectives1. Identify the system's purposes.2. Explain the function and operation of the following secondary containment features:a. Reactor building gb. Relief panelsc. Airlocksd. Reactor building normal ventilation system isolati...

Response to SC Sholly followon interrogatories re implementation of containment isolation signal,procedures of containment isolation reset & modified containment isolation circuitry.W/Certificate of Svc & cover ltr.

. .800509oyrscrLic 4/7/80UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARDIn the Matter of))METROPOLITAN EDISON COMPANY)Docke t No . 50-289) (Restart)(Three Mile Island Nuclear )Station, Unit No. 1))LICENSEE'S RESPONSE TO STEVEN ...

NuScale Design-Specific Review Standard Section 6.2.4, Containment Isolation System.

ADAMS Accession No. ML15356A332 U.S. NUCLEAR REGULATORY COMMISSION DESIGN- SPECIFIC REVIEW STANDARD for NuScale SMR DESIGN 6.2.4 CONTAINMENT ISOLATION SYSTEM Primary - Organization responsible for the review of containment integrity Secondary - None I. AREAS OF REVIEW ...

Comment opposing proposed generic communication re lab testing of nuclear grade activated charcoal,M97978.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _MQnf 75Er|JSJpA2[jf/g n C 5 CORPORATION4555 Groves Rd. No. 41 Columbus, Ohio 4323R E C EIV E D614-864-7613 * FAX 614-864-2296 [199B HAR 19 Fil 3: 50RULES & DR BiKNCHUS NRCChief, Rules and Directives Branch3/9/98Division ...