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LER 86-048-00:on 860824,25 & 26 containment purge sys automatically isolated.Caused by containment gaseous radiation levels exceeding trip setpoint of containment gas monitor 1EMF39L.Tech Specs revised.W/860923 ltr.

NRC Persn 300 U.S. NUCLE AR LEQULATOM CORA080 BIONar$35APPROVED Onde NO. 31e0-4104LICENSEE EVENT REPORT (LER)**"'''''3"PACILITY NAME HiDOCMET NURESER (2)PAGEe3)Catawba Nuclear Station, Unit 1o |5 | 0 |0 | 0 | 4| 1 |31 |OF| g| qTITLE 148Three Containment Purge System Isolations...

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

EBASCO PLANT SERVICES INC.AS ubs1diaryof ESASCO SERVICES INCORPORATEDwo World Trade Center, New York, N.Y.10048ST. LUCIE PDÃZ UNIT NO. 2NUCLEAR POWER PLANTFZ. PIERCE, FLORIDADOCKET NUMBER 50-389REACZOR CONZAINMENT BUILDINGIÃQMRATI93 LEAKAGE RATE TESTFINAL REPORT Prepared for:F...

Requirements for Containment Systems for CANDU Nuclear Power Plants.

I*1 Atomic Energy Commission de contrb Control Board de Mnergie atomique REP/AECB-R-7/1991 Canada. Atomic Energy Cont Requirements for containment systems c.5 ihyw R-7 SP rep Regulatory Document Requirements for Containment Systems for CANDU Nuclear Power Plants A Regulatory P...

Forwards "Assessment of Hydraulic Peformance of WNP-1 Containment Recirculation Sumps (Hydraulic Evaluation of Design of Containment Recirculation Sumps) & (Hydraulic Model Study of Containment Recirculation Sumps)."

4 -Washington Public Power Supply SystemP.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000-Docket No. 50-460January 11, 1983G01-83-00llMr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D....

"CLEI PNPP Primary Containment 1994 ILRT Final Rept."

,-_ _ - - -,!:iO;;;.ifi!CLEVELAND ELECTRIC ILLUMINATING COMPANYPERRY NUCLEAR POWER PLANTPRIMARY CONTAINMENT,1994 INTEGRATED LEAKAGE RATE TESTOx,,FINAL REPORT'!,te,i*Prepared ByBCP Technical Services, Inc.*July 1994|hs9410050218 940930DRADOCK 0500044oPDR'.__(;~p,I' BCP TGohnica...

Application for amends to licenses DPR-42 & DPR-60,changing TS 4.4.A, "Containment Leakage Tests," Bases to TS section B.4.4, "Containment Sys Tests" & adding TS.6.5.J, "Containment Leakage Rate Testing Program."

..- - - --- - - _- . -. . _. . . . _ _UNITED STATES NUCLEAR REGULATORY COMMISSIONNORTHERN STATES POWER COMPANYPRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-28250-306REQUEST FOR AMENDMENT TOOPERATING LICENSES DPR-42 & DPR-60LICENSE AMENDMENT REQUEST DATED October 25,199...

LER 83-007/01T-0:on 830308,after completing containment vent during full power operation,RM 11/12 sample point not switched from vent to containment position.Caused by operator error.Sample point switched to containment.

MSEWEEE EVEWV REPORT.CON f HOL ULOCK; || | | | ||h (PLEASE PHlfJT OR TYPE ALL REQUlnED INFORMATION),i e%II) | W | I | K |N | p | 1|@l 0 | 0 |- | 0 |0 |0 |0 | 0 | - | 0 | 0 |@|4 |1 |1 |1 | 1]@|||g *W WtlE(N5t t CoM14 tb LIC ENSf. NUMUE H 26 26L8 CENSE 1YPE JJ b 7 C A f b5CON' T...

"Containment Structural Capability of Light Water Nuclear Power Plants."

. . . . _ . _ _ . .__ __-5$. ,DR w. : _WnAil 'IDCORProgram Report, .4\<- '.h4.Technical Report 10.1ContainmentStructuralCapability of.~Light WaterNuclear Power.Plants,yJuly 1983-- 9h,,B2 5 850724SHOLLYB5-457 PDR~Th-Industry Degraded Core Rulemaking Program Sponsored By the Nuc...

Proposed tech specs SR 3.6.4.1.2,revising wording to maintain requirement that secondary containment is not breached at any time when secondary containment is required.

.. .- . . . . . . . . - . - _.. -. ..- . . - ... ..- - . . . - - . - . - - _-.- - .I...-.:..:,:fJi -1i .IiI.ATTACHMENT4. PEACH BOTTOM ATOMIC POWER STATION|UNITS 2 AND 3!' Docket Nos. 50-277j 50-278i.License Nos. DPR-44*DPR-56.REVISED TECHNICAL SPECIFICATIONS CHANGESList of Att...

NuScale Design-Specific Review Standard Section 3.8.2, Steel Containment.

ADAMS Accession No. ML15355A411 U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD for NuScale DESIGN 3.8.2 STEEL CONTAINMENT REVIEW RESPONSIBILITIES Primary - Organization responsible for mechanical engineering reviews Secondary - Organizations responsi...

Draft Guidance For The Use Of Containment Accident Pressure In Determining The Net Positive Suction Head Margin For Emergency Core Colling System And Containment Heat Removal Pumps And Containment Heat Removal Pumps In Boiling Water And Pressurized...

ENCLOSURE NUCLEAR REGULATORY COMMISSION DRAFT GUIDANCE FOR THE USE OF CONTAINMENT ACCIDENT PRESSURE IN DETERMINING THE NET POSITIVE SUCTION HEAD MARGIN FOR EMERGENCY CORE COLLING SYSTEM AND CONTAINMENT HEAT REMOVAL PUMPS IN BOILING WATER AND PRESSURIZED WATER REACTORS Cont...

Proposed tech specs section 3/4.9.2,modified to permit use of equivalent methods to obtain containment closure during refueling operations for containment equipment hatch.

• ATTACHMENT 3 • . LR-N980415 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request: Technical Specification 3.9.4 BASES 3/4.9.4 3/4 9-4 B 3/4 9-1 B 3/4 9-2 B 3/4...

Attachment - Vogtle Unit 3 LAR-17-043 Containment Pressure Analysis.

ATTACHMENT TO LICENSE AMENDMENT NO. 147 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain mar...

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

~ J ~ ARIZONA PUBLIC SERVICE COMPANYPALO VERDE NUCLEAR GENERATING STATIONUNIT NO. 2REACTOR CONTAINMENT BUILDINGINTEGRATED LEAK RATE TESTSUMMARY TECHNICAL REPORT PREPARED BYWILLIAMD. ROMANARIZONA PUBLIC SERVICE COMPANYOPERATIONS ENGINEERING SECTIONMAY7, 19858506100595 850528APD...

Proposed Tech Spec 3.6.1.7 re containment ventilation sys.

CONTAINMENT SYSTEM CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Containment purge supply and exhaust isolation valves shall be OPERABLE and: a. Each 42-inch containment purge supply and exhaust isolation valve shall either be sealed closed or blind f...

LER 02-003-00, Palisades Inoperable Containment Hydrogen Monitors.

Committed to Nuclear ExcellencePalisades Nuclear PlantOperated by Nuclear Management Company, LLCFebruary 19, 200310 CFR 50.73U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001PALISADES NUCLEAR PLANTDOCKET 50-255LICENSE NO. DPR-20LICENSEE EV...

"Reactor Containment Bldg Integrated Leak Rate Test Completed Oct 1989."

Docket # 1-o 63 Accession # 9063 Date of Ltr Regulatory Docket File NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT MONTICELLO, MINNESOTA REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION DIVISION OF NUCLEAR REACTOR REGULATION LICENSE NO. DPR-22 DOCKE...

Forwards final version of NUREG/CR-4896, "Containment Loads Due to Direct Containment Heating & Associated Hydrogen Behavior;Analysis & Calculation W/Contain Code," in advance of direct containment heating program review for month.

q_. , .:sn.-ta xw~'L.-g y '.lSandia National Laboratories'. Albuquerque, New Mexico 87185..June-4, 1987..,'J.-HulmanRES'U.S.Nuclear Regulatory Commission--. Washington, DC 20555-Dear Mr. Hulman:.,Enclosed is a copy of the final version of our'NUREG reporton CONTAIN analyses of...

DC Cook Units 1 & 2 Resolution of Containment Structural Issues.

October 15, 2000Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 RESOLUTION OF CONTAINMENT STRUCTURAL ISSUES Reference: Letter from M. W. Rencheck...

Oyster Creek, License Amendment 168, Secondary Containment Maintenance

March 7, 1994Docket No. 50-219 Mr. John J. Barton Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 Dear Mr. Barton:Distribution: Docket File NRC & Local PDRs PD 1-4 Plant SVarga JCalv...

NEDO-33911, Revision 0, "BWRX-300 Containment Performance."

ENCLOSURE 2 M200054 Licensing Topical Report NEDO-33911, Revision 0, BWRX-300 Containment Performance Non-Proprietary Information IMPORTANT NOTICE This is a non-proprietary version of the BWRX-300 Reactor Pressure Vessel Isolation and Overpressure Protection Lice...

"Reactor Containment Bldg Integrated Leak Test - May 1974."

-- - - .. .. - .. - . . - -. --'l|',,50'363'iD|NORIMERN STATES POWER COMPANY ai~R{l.CiETICELID N0 CLEAR GENEPATING PIRE-h'OG111974w $;;"p/Q!|gpr3iian sc*M!REPORT TO THEUNITED STATES ATOMIC ENERGY C0hMISSION,DIRECTORATE OF LICENSING.,LICENSE NO. DPR - 22 i,!'!:.REACTOR CONTAISE...

Forwards info on NUREG-0737,Item 2.F.1.4, "Containment Pressure Monitor," Item 2.F.1.5, "Containment Water Level Monitor" & Item 2.F.1.6, "Containment Hydrogen Monitor," in response to NRC 830105 request.

,.PHILADELPHIA ELECTRIC COMPANY2301 M ARKET STREETP.O. BOX 8699PHILADELPHIA. PA.19101SHIELt>S L. DALT;40FF.JM,!"/l5%o, March 4, 1983Docket Nos. 50-27750-278Mr. V. F.Stolz, ChiefOperating Reactors Branch #4Division of LicensingU.S. Nuclear Regulatory CommissionWashington, D.C. ...

NUREG/CR-6920, "Risk-Informed Assessment of Degraded Containment Vessels."

NUREG/CR-6920SAND2006-3 772PRisk-Informed Assessment ofDegraded Containment VesselsSandia National LaboratoriesU.S. Nuclear Regulatory CommissionOffice of Nuclear Regulatory ResearchWashington, DC 20555-0001AVAILABILITY OF REFERENCE MATERIALSIN NRC PUBLICATIONSNRC Reference Ma...

"Containment Tendon Surveillance Lift-Off Acceptance Criteria."

- _ - - _o ,;( ('V.%ATTACHMENT NO. ICONTAINMENT TENDON SURVEILLANCELIFT-OF ACCEPTANCE CRITERIAl|).1l8004230f Gii|.- - _,. . . _ . . _-. . . _,, . . . .-*' I ( , . ;-....-.!CONTAINMENT TENDON SURVEILLANCE,LIFT-0FF ACCEPTANCE CRITERIA-.Prepared By:T. E. Johnson_,,'..Ii.\Bechtel ...