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PNO-77-066:on 770422,RCS leak into containment basement occurred.Water removed from containment sump by pumping to radwaste sys.Airbone contamination problem existed inside containment & local emergency declared inside containment.

_ _ _ - .---- - - .-. -. - -- -3-,IPRELIMINARY NOIIFICATIONhp,)p,-l,April 25, 1977I-lPRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE-PNO-77-66This preliminary notification constitutes EARLY notice of an event ofPOSSIBLE safety or public interest significance. The infor...

SECY-92-092, "The Containment Performance Goal, External Events Sequences, and the Definition of Containment Failure for Advanced LWRs"

March 17, 1992POLICY ISSUESECY-92-092For: From: Subject: Purpose:Background:Discussion:(Information) The Commissioners James M. Taylor Executive Director for Operations THE CONTAINMENT PERFORMANCE GOAL, EXTERNAL EVENTS SEQUENCES, AND THE DEFINITION OF CONTAINMENT FAILURE FOR A...

WCAP-16608-NP, "Westinghouse Containment Analysis Methodology."

Westinghouse Non-Proprietary Class 3WCAP-16608-NPRevision 0August 2006Westinghouse Containment AnalysisMethodologyOWestinghouseWESTINGHOUSE NON-PROPRIETARY CLASS 3WCAP-16608-NPRevision 0Westinghouse Containment Analysis MethodologyRichard P. OfstunEngineering Services, Systems...

Proposed tech specs 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."

. . _.. _ .- - . . - , _ . . . .,l;-;!.iExhibit B|Prairie Island Nuclear Generating Plant ;!License Amendment Request Dated October 25,1996''Proposed Changes Marked UpOn Existing Technical Specification Pages1i!,JExhibit B consists of existing Technical Specification pages wit...

Forwards proposed changes to Updated FSAR Sections 6.2.4.3 re containment isolation design & 7.3.2.5 re post-accident containment flooding analysis.

. e . ,0.PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department APR 16 1993 NLR-N93042 LCR 93-08 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: REQUEST FOR LICENSE AMENDM...

Proposed Tech Specs re containment isolation valves.

LCA 124, Revision 1.Attachment3/4.6 CONTAINMENT SYSTEMS.3/4.6.1 PRIMARY CONTAINMENT'CONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.APPLICABILITY: MODES 1, 2, 3 and 4.ACTION::Without primary CONTAINMENT INTEGRITY, ...

Advises that structural evaluations of containment sys being performed in response to containment integrity insp.

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9007250220 DOC.DATE: 90/07/20 NOTARIZED- NOFACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1,Rochester GAUTH.NAME AUTHOR AFFILIATIONMCCREDY,R.C. Rochester Gas E Elec...

"Containment Leakage Rate Testing," technical evaluation rept.

TECHNICAL EVALUATION REPORT CONTAINMENT LEAKAGE RATE TESTING IOWA ELECTRIC LIGHT AND POWER COMPANY DUANE ARNOLD ENERGY CENTER UNIT 1NRC DOCKET NO. 50-331 NRCTACNO. 08718 NRC CONTRACT NO. NRC-03-79-118Prepared by Franklin Research Center 20th and Race Street Philadelphia, PA 19...

AOS Application Containment RAIs.

From: Saverot, Pierre Sent: Wednesday, December 16, 2009 4:05 PM To: 'Troy Hedger'; 'Raul Pomares'; 'Schrag, Michael R. (GE Infra, Energy)'; 'Turner, David W. (GE Infra, Energy)' Subject: AOS package containment RAIs Dear Mr. Hedger, As a follow-up to our October 28, 2009 te...

LER 07-002-00 for Palisades re Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw.

March 1 2007U. S. Nuclear Regulatory CommissionDocument ControlWashington, 20555-0001Palisades Nuclear PlantDocket 50-255License DPR-20Palisades Nuclear PlantOperated by Nuclear Management Company, LLC10 CFR 50.73(a)(2)(v)(C)Licensee Event Report 07-002, Inoperable Containment...

Proposed TS change re containment isolation requirements.

( ATTACHMENT 1 SURRY POWER STATION PROPOSED TECHNICAL SPECIFICATION CHANGE ....... FOR -CONTAINMENT ISOLATION REQUIREMENTS 9206120198 920601 PDR ADOC'K 05000280 p . . PDR ... . 2. 3. 4. e TS 1.0-4 CHANNEL FUNCTIONAL TEST Injection of a·simulated signal into an analog channel a...

Training Job Performance Measures - Secure Containment Spray.

NUCLEAR POWER BUSINESS UNIT TRAINING JOB PERFORMANCE MEASURES SECURE CONTAINMENT SPRAYJPM P026.005COT Revision 0 DRAFT October 3, 2000 TOTAL REWRITEK/A REFERENCE: ( (NUREG-1122) ( ( ALTERNATE PATH JPM)26 020 A2.08 (3.2/3.7) )26 A4.01 (4.5/4.3) )26 A4.05 (3.5/3.5) YES X NOPERFO...

Proposed Tech Specs re containment airlocks.

L,N)62605037 9006-.18 p PDC0 0 ATTACHMENT I TO IPN-90-032 PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO CONTAINMENT AIR LOCKS NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR-641.9.2 Instrument Channel Functional Test Injection of a simul...

"Reactor Containment Bldg Integrated Leakage Rate Test."

.Date: l-7-91T 'G . 7y aDirector s ing and Plant PerformanceIMh Date:D. E. Spoet9y\' 'General Manager Nuclear Operation ServicesDate: [ [/N. R. Tonet[/'Manager Nuclear SafetysDate:k Approved By:T. P. NoonAnGeneral Manager Nuclear Operations9102040203 910123 ,ADOCK0500gePDRP!_....

Proposed TS re primary & secondary containment integrity.

s s,Attachment to)''NSD931023iPage 1 of 11REVISED TECHNICAL SPECIFICATIONSRevised Pares New Pares11 166 165b5 167 166a165 182 167a165a 205a ;iI. INTRODUCTIONThe Nebraska Public Power District (District) requests that the NRCapprove the proposed changes to the Cooper Nuclear St...

Proposed tech specs re RCS & containment isolation valve listings & containment leakage rate tests.

ATTACHME T 2REVISED TECHNICALSPECIFICATION PAGESPDRADOCH050002209302i20i04930129LIMITINGCONDITIONS FOR OPERATIONTable 3.2.7 (Cont'd)REA T R C LANT Y TEM I LATION VALVESLin r mEm rm L vinlinLocation RelativeNo. of Valves to Primary NormalMaximumOper. Time~SecAction onInitiating...

Forwards open item responses to Auxiliary Sys Branch & Containment Sys Branch re RCPB leakage detection, NUREG-0737,Items II.E.4.2, "Containment Isolation Dependability," & II.F.1.2, "Containment Water Level."

PENHI -=1671 Worcasser RoadPub 5c Service of New HampshireM a h . * * * "* 01701-(617) - 872 - 8100January 28, 1983SBN-438T.F. B7.1.2'United States Nuclear Regulatory CommissionWashington, D. C. 20555Attention: Mr. George W. Knighton, ChiefLicensing Branch No. 3Division of Lic...

Proposed tech specs re containment insp SRs.

| 444|||PROPOSED TECHNICAL SPECIFICATION CHANGES1,|!.9503220313 950317PDR ADOCK 05000368PPDR_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ -P~L~ ~.LEMERGENCY CORE' COOLING SYSTEMS*, ,.". SURVEILLANCE REQUIREMENTS (Continued)'b. At least once per ...

LER 03-002-00 for H.B. Robinson, Unit 2 regarding Failure of Automatic Containment Ventilation Isolation During Containment Pressure Relief.

10 CFR 50.73 q bb Progress Energy Serial: RNP-RA/03-0098 JUL 31 2003 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2003...

Approves 851120 proposal to postpone completion of containment connections for containment pump back sys & continuous containment leakage monitoring until 1987 refueling outage.

P:# FUNITED STATES8 NNUCLEAR REGULATORY COMMISSION%:|WASHINGTON,0. C. 20555*.....December 3,1985Docket No.: 50-245Mr. John F. Opeka, Senior Vice PresidentNuclear Engineering and OperationsNor.heast Nuclear Engineering CompanyPost. Office Box 270Hart ford, Connecticut 06141-027...

NRC Containment Non-Proprietary 10 Sept 2008 SLOAN - Status of U.S. EPR LOCA Containment Pressure Analysis Issue Resolution.

> NRC Meeting, U.S. EPR Containment Pressure Analysis Issue Resolution – September 10, 2008 AREVA NP Inc.1Status of U.S. EPR LOCA Containment Pressure Analysis Issue ResolutionSeptember 10, 2008> NRC Meeting, U.S. EPR Containment Pressure Analysis Issue Resolution – Septembe...

IP2 Containment Lining Concerns Questions and Answers.

IP2 CONTAINMENT LINING CONCERNS Qs & AsQ I hear there's a 6.5-square-inch leak in the IP2 containment steel lining that's causing rust spots. If there's a hole that big and causing rust, why don't you require that the plant be shutdown to fix the hole? A The NRC notes that a r...

Proposed TS 3/4 6-1 re SR for primary containment integrity & 3.6.1.2 re LCO for containment leakage rates.

14-..ENCLOSURE 3V0GTLE ELECTRIC GENERATING PLANTTECHNICAL SPECIFICATIONS REVISIONREVISION TO PEAK CONTAINMENT PRESSUREINSTRUCTIONS FOR INCORPORATIONThe proposed change should be incorporated in the Technical Specification asoutlined below.Remove Pace Insert Pace3/4 6-1 and 3/4...

Draft Paper on Functional Containment Performance Criteria.

SUBJECT: FUNCTIONAL CONTAINMENT PERFORMANCE CRITERIA FOR NON-LIGHT WATER REACTOR DESIGNS PURPOSE: The purpose of this paper is to seek Commission approval of the staff’s recommendation to adopt a technology-inclusive, risk-informed, performance-based approach to establish...

Proposed tech specs 4.4 re containment testing.

.. _ _ . . _ _ _ _ . . - ~ . . . _.. , ,,.J<.. ....1::|1lata' ii'l..;'.ATTACHMENT _A.;.'k!Proposed _ Change _No m200..._ Supplement _No. Ij.',t;..jProposed _TechnicaLSpecif.ication1. ages _4J Land _4A 2i||'si49aI,1[9701230140 970115DRADOCK 05000309pPDR- - .-j'*.'.*.4.4 CONTAIN...