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Davis-Besse Station, License Amendment 223, Amendment Revises TS Section 3/4.6.1.3, Containment Systems - Containment Air Locks, & Associated Bases.

June 11, 1998 Mr. John K. Wood Vice President - Nuclear, Davis-Besse Centerior Service Company c/o Toledo Edison Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760Distributior Docket File . PUBLIC PD3-3 Reading EGAI GGrant, RIIl JPuls...

"Mark III Containment Ventilation/Purge:IL Power Study of Containment Continuous Vent/Purge Issue as Applicable to Clinton Power Station."

_OMARK IIICONTAINMENT VENTILATION / PURGE:'AN ILLINOIS POWER STUDY OFTile CONTAINMENT CONTINUOUSVENT / PURGE ISSUE AS APPLICABLETO THE CLINTON POWER STATIONTerry L. RileyStaff SpecialistTechnical AssessmentNuclear Station Engineering Dept.March, 1982O8203190340 820310PDRADOCK0...

Updated SER Containment Leak Rate to ACRS.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 5, 2016 MEMORANDUM TO: Andrea Valentin, Executive Director Advisory Committee on Reactor Safeguards FROM: Yoira K. Diaz-Sanabria, Branch Chief /RA/ Projects Branch 1 Division ...

Temporary procedure "Secondary Containment Preventative Maint Program."

*.. .TEMPORARY PROCEDURE ..*.SECONDARY CONTAINMENT FREVENTATIVE MAINTENANCE PROGRAMiiA. PURPOSE,The purpose of this program is to provide a method for the periodicinspection of the Secondary Containment and guidelines on maintenanceperformed during the operating cycle. This pr...

Proposed Tech Specs 3/4.7, "Containment Sys."

• c:\d3407osr.pkg ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Technical Specification 3/4. 7 "CONTAINMENT SYSTEMS" . ~---------- ----~----9309230205 9309 l 7 ---- ' PDR ADOCK 05000237 I : p PDR 1 i ~-. ~ -• CONTAINMENT SYSTEMS 3.7 - LIMITING CONDITIONS FOR OPERATION A. PRIM...

Proposed revs to Tech Spec Section 3.6, "Containment Sys," for conduct of CRD evolutions when containment integrity not intact.

(HBR-09) 3.6 CONTAINMENT SYSTEM Applicability Applies to the integrity of reactor containment. Objective To define the operating status of the reactor containment for plant operation. Specification 3.6.1 Containment Integrity a. The containment integrity (as defined in 1.7) ...

Salem Nuclear Generating Station, Units 1 and 2, Request for Changes to Technical Specifications, Containment Systems - Containment Cooling System.

PSEG Nuclear LLCP.O. Box 236, Hancocks Bridge, New Jersey 08038-0236LR-N04-0089LCR S03-07APR 1 5 20040 PSEGNuclear LLCU. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001REQUEST FOR CHANGES TO TECHNICAL SPECIFICATIONSCONTAINMENT SYSTEMS - CON...

Attachment 1 - BWR Containment Venting.

BWR OWNERS’ GROUP Lesa P. Hill BWROG Chair Tel: (205) 992-5727 LPHILL@southernco.com c/o GE Hitachi Nuclear Energy, P.O. Box 780, 3901 Castle Hayne Road, M/C F-12, Wilmington, NC 28402 USA BWROG...

Viewgraphs entitled "ORNL Containment Iodine Model."

'wg(, f.ORNL CONTAINMENT 10 DINE MODELE. C. BEAHMC. F. WEBERT. S. KRESS.R. J. ANDERMANN.eb!I'i|'m8609300409 860924PDRPNERG86-644ADO_ . _. _ -- ._ _ _ _ _ __ _ _. _,TRENDS(TEANSPORT AllD RETEliT10t; 0F NUCLIDES IN DOMINANT SEQUENCES)WHAT IT DOES*.HOW IT WORKS*MODELS At D DATA*C...

Proposed tech spec 3.7, "Plant Containment Sys."

. - _ - . . _ _ . _ _ _ _ ___ . _ _ _.~.. ._. _ ._.. _ _ _ _ . _ . _ . _ _~RTS-269Attachment 2 toNG-95-2985Page1of3PROPOSED CHANGE RTS-269 TO THE DUANE ARNOLD ENERGY CENTERTECHNICAL SPECIFICATIONS1The holders oflicense DPR-49 for the Duane Arnold Energy Center propose to amend...

"Reactor Containment Bldg Integrated Leak Rate Test."

|| ,af|':.'OL|J.i!I'i|\li!''|CLEVELAND. ELECT.'IC ILLUMINATING COMPA!!Y |'|- PERRY NULLEAR POWER PLANT'|UNIT 1;!REACTOR CONTAINMENT BUILDING'INTEGRATED LEAK RATE TEST!JULY 1989|:,,';;.,PORC Meeting No. 89-111 October 5, 1989and 89-112 October 12, 1989 ;.3pOCK 05 coo 44n1PDC. ....

"Primary Reactor Containment Structural Integrity Test."

)UTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 PRIMARY REACTOR CONTAINMENT STRUCTURAL INTEGRITY TEST 8207020382 820630 PDR ADOCK 05000362 A PDRSOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 PRIMARY REACTOR CONTAI...

Monticello, Long-Term Containment Analysis, Revision 2.

Attachment 3NUCLEAR MANAGEMENT COMPANY, LLCMONTICELLO NUCLEAR GENERATING PLANTDOCKET 50-263GE NUCLEAR ENERGY REPORT, GE-NE-0000-0002-8817-01-R2MONTICELLO NUCLEAR GENERATING PLANT LONG-TERMCONTAINMENT ANALYSIS, REVISION 2,DATED AUGUST 2003, NON-PROPRIETARY VERSIONGE Report foll...

"Reactor Containment Bldg Integrated Leak Rate Test."

.. . . . . . _ _ _ --DUKE POWER COMPANYMcGUIRE NUCLEAR STATION:,''.''' ' 'm +.- -a .,,., ,h2 -** 's*~:: -~*:,_.,.,"* ..A~ '., ,. , ,,,;'**,4n.,.."':-. :**,.. ..s.,.., ,%_.k,*- *IJ4a- -- ,- -:. ... , _ , ..~' *', - ,. 3;-;, , . ,,.,s*.**> ,_ . ,a. e-,4j. ... . . ._G ~ . w'* * *...

Safety evaluation accepting containment penetration valve configurations.

!Enclosure 2,;-lSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION_GPU NUCLEAR CORPORATIONMETROPOLITAN EDIS0N COMPANYPENNSYLVANIA ELECTRIC COMPANYJERSEY CENTRAL POWER AND LIGHT COMPANYDOCKET NO. 50-320THREE MILE ISLAND NUCLEAR STATION UNIT NO. 2INTRODUCTIONPy letter...

Training Job Performance Measures - Secure Containment Spray.

NUCLEAR POWER BUSINESS UNIT TRAINING JOB PERFORMANCE MEASURES SECURE CONTAINMENT SPRAYJPM P026.005COT Revision 0 DRAFT July 18, 2000 TOTAL REWRITEK/A REFERENCE: (NUREG-1122) ALTERNATE PATH JPV,026 020 A2.08 (3.2/3.7) 026 A4.01 (4.5/4.3) 026 A4.05 (3.5/3.5)X YES NOPERFORMANCE C...

Proposed Tech Specs re primary containment isolation valves & containment sys limiting condition for operation & bases.

TABLE 3.6. 3-1(Continued)PRIMARY COHTAINMENT ISOLATIOH VALVESVALVE FUNCTION ANO NUMBERi NXIMUMISOLATIOH TIMESeconds)ISOLATIONSIGNAL(s)(')Automatic Isolation Valves (Continued)Containnent Instrunent GasHV-12603SV-12605SV"12651SV"12661SV-12671ZQN/AN/AN/AN/AXXX.YYHV-113" 3HV"1131...

EVALUATION OF AP600 CONTAINMENT THERMAL-HYDRAULIC PERFORMANCE.

NUREG-1632<. _ . . _ _ _ _ _, __%Evaluation of AP600Containment Thermal-HydraulicPerformance- _ - - - _ _!U.S. Nuclear Regulatory Commission;!!'!Omce of Nuclear Reactor Regulation1K. M. Campe|J. A. Kudrick!If? 'f ? ),|%...6)~.8[ fhhk OO 3- -- -_ _ _ - - _ _ _ - _ _ _ _ _ _ _ _...

Indian Point, Unit 3, Proposed Technical Specification Changes Regarding RWST Temperature and Containment Pressure in Containment Integrity Analysis.

Enterqy Nuclear NortheastIndian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 10511-0249Tel 914 254 6700John A VentosaSite Vice PresidentAdministrationNL-13-003January 28, 2013U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001...

Application for amend to License NPF-42,revising TS 3/4.6.1.1, "Containment Integrity," TS 6.8.4i, "Containment Air Locks" & adding TS 6.8.4i, "Containment Leakage Rate Testing Program."

__ _ _ _ __'.. .jWOLF CREEKNUCLEAR OPERATING CORPORATIONOtto L. Maynard ~vice Presdent Plant OperationsFebruary 8; 1996WO 96-0020U. S. Nuclear Regulatory CommissionATTN: Document Control DeskMail Station P1-137Washington, D. C. 20555Reference: Letter WO 95-0187 Dated December ...

"Containment Recirculation Fans Mass Air Flow Check."

Pair'~(ROCHESTER GAS %%3 ELECTRIC CORPORATIONGINNA STATIONCONTROLLED COPY NUiSERGlNNA STAT1GNUNlTffCQI)PLET-DOATE::-TlhtE':--PROCEDURE NO. -37 5REV. NO.CONTAINMEÃZ RECIRCULATION FANS ~iIASS AIR FLOW CHEKTECHNICAL REVIEW(PORC3-24-80QC REVIEWAPPROVED FOR USEPLAil UPERINTENDENTqA...

Provides status on SEP containment analysis for facility. Containment design temp is exceeded in some cases.W/o stated encls.

• • I TFBl-029 W. Butler Containment Systems Branch Divisio~ of Systems Safety Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NUCLEAR SYSTEMS SAFETY P~OGRA~ February 17, 1981 Subject: ~EP Containment Analysis and Evaluation for t...

Proposed Tech Specs re containment sys.

.iIDESCRIPTION OF PROPOSED CHANGES NPF-10-8 AND NPF-15-8AND SAFETY ANALYSISThis is a request to revise Technical Specification 3/4.6.3 " Containment|Isolation Valves.'Existina Specifications:Unit 2: See Attachment "A"Unit 3: See Attachment "C"Proposed Specifications:Unit 2: Se...

"Reactor Bldg Containment Integrated Leak Rate Test."

''<.g .qs .,.,'(: ,fENCLOSURE.f ?'TENNESSEE VALLEY AUTHORITYDIVISION OF NUCLEAR POWER>t'-.I- -1REACTOR' BUILDING CONTAINMENT'INTEGRATED LEAK RATE TESTSEQUOYAH NUCLEAR PLANT UNIT 2CONDUCTED MARCH 18-19, 1989'iI.-Submitted toThe United States Nuclear Regulatory ConunissionPursua...

Proposed Tech Spec re secondary containment integrity.

CONTAINMEHT SYSTEMS3/4.6.5 SECONDARY CONTAINMEHTSECONDARY CONTA!HMEHT INTEGRITYaLIMITING CONDITION FOR OPERATION44.=3.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be maintained.APPLICABILITY: OPERATIONAL CONDITIONS"1,2,3 and".AciiOII:Without SECONDARY COHTAINMEHT INTEGRITY:a. I...