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Technical Specifications 3.7, Plant Systems, Pages 3 .7 .4-1 through 3 .7 .4-3, Dresden Units 2 and 3, to CR Habitability Amendment.

3 .7 PLANT SYSTEMS 3 .7 .4 Control Room Emergency Ventilation (CREV) System LCO 3 .7 .4 The CREV System shall be OPERABLE . APPLICABILITY : ACTIONS REQUIRED ACTION Restore CREV System to OPERABLE status . AND B .2 AND B .3 Initiate action to implement mitigating actions . Ver...

481st Meeting - April 5, 2001

Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards 481st Meeting Docket Number: (not applicable) Location: ...

Forwards ANI Binder EB-72 & MAELU Binder XB-72 re secondary financial protection for plant.

• OPS~G i Public Servic~ Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 Mr. Jerome Saltzman Deputy Chief Office of Antitrust & Indemnity Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D.C. 20555 Dear Mr. Saltzman: SECONDARY ...

08/26/2002, Meeting with Utility to Discuss Tornado Mitigation, Auxiliary Building, Flooding & Extension of KHU Completion Time for Oconee Plant.

NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999) TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting...

Provides response to NRC 940328 RAI re electric power sys design implementation at Watts Bar Nuclear Plant as described in FSAR Chapter 8.

Tennessee Valley Authority, Post Office Box 2000, Spring C ty, Tennessee 37381,JUN 2 9 )4U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Gentlemen:In the Matter of the Application ofTennessee Valley Authority)Docket Nos. 50-39050-391WATTS BAR N...

05/21/2007 Summary of Clarification Telephone Call With Progress Energy Regarding Pilot Plant (Shearon Harris) Transition to National Fire Protection Association Standard 805.

July 27, 2007MEMORANDUM TO: Sunil D. Weerakkody, ChiefFire Protection BranchDivision of Risk AssessmentOffice of Nuclear Reactor RegulationFROM: Paul W. Lain, Senior Fire Protection Engineer /RA/Fire Protection Branch Division of Risk AssessmentOffice of Nuclear Reactor Re...

Susquehanna 1 4Q/2003 Plant Inspection Findings Initiating Events Significance: Sep 27, 2003 Identified By: Self Disclosing Item Type: NCV NonCited Violation Did Not Properly Implement Feed Pump test and Caused Feed Pump trip A self-revealing event resulted in a non...

Susquehanna 2 4Q/2003 Plant Inspection Findings Initiating Events Mitigating Systems Significance: Sep 27, 2003 Identified By: NRC Item Type: NCV NonCited Violation D EDG Bolt Failure - Cause Not Determined Prior to Return to Service The inspectors identified a no...

August 31, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUBJECT: MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN - QUAD CITIES NUCLEAR POWER STATION Dear Mr. Crane...

Safety Insp Rept 50-320/88-01 on 880101-29.Violation noted. Major areas inspected:plant operations,defueling operations, plant housekeeping conditions,shipment of radioactive matls, event followup & control of radioactive matls.

.'.V.S. NUCLEAR REGULATORY COMMISSIONREGION IReport No. 50-320/88-01Docket No. 50-320License No. DPR-73 Priority--Category CLicensee GPU Nuclear CorporationP.O. Box 480Middletown, Pennsylvania 17057Facility Name: Three Mile Island Nuclear Station, Un.t 2Inspection At: Middleto...

Responds to NRC 890808 ltr re violations noted in Insp Repts 50-259/89-27,50-260/89-27 & 50-296/89-27.Corrective actions taken:surveillance test completed & shift technical advisor signoff added to form Plant Manager Instruction 47.

ACCKMWTZD D) STKBU730N DEMONSTRATION SYFI'EMREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)CESSION NBR:8909280178 DOC.DATE: 89/09/21 NOTARIZED: NOFACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee50-...

Suppl to 810701 petition for review of ASLAB 810616 decision,ALAB-644.Commission should take notice of recent disclosures of plant multiple seismic design errors.Errors in siting should be reviewed.W/Certificate encl.

t*..3 ,,UNITED STATES OF AMERICAOgMTEDNUCLEAR REGULATORY COMMISSIONBEFORE THE COMMISSION~El' DCT 30 P253~)DFFICE 07 3ECRETis (In the Matter of)00CHETitiu & SERvicvBRANC,1'),M [7 [KPACIFIC GAS AND ELECTRIC COMPANY) Docket Nos. 50-27d(Diablo Canyon Nuclear Power Plant,) 50- .L/g...

LER 96-004-01:on 961030,deficient failure modes & effects analysis for DC electrical sys resulted in unavailability of automatic functions of plant protective sys.Established administrative controls.W/970130 ltr.

.*+Entergy Operatione, Inc.*-:-:- ENTERGYmssn =HzseMc AR 72801*Tel 501 ESB 6000|!January 30,1997';2CAN019701 iIU. S. Nuclear Regulatory CommissionDocument Control Desk 1Mail Station PI-137|Washington, DC 20555)lSubject: Arkansas Nuclear One - Unit 2|Docket No. 50-368'License N...

LER 96-005-00:on 961120,surveillance testing of some features of plant protective sys & post-accident monitoring instrumentation were not performed due to inadequate procedures.Temp elements will be revised.W/961220 ltr.

.- - - -. . - .- ...|h'ENTERGY!''r.nimu opmuon.. ine.-:::-iaa:a 333tRe/AI A AR 72801Tel 501853-5000iI.December 20,199612CAN129602U. S. Nuclear Regulatory CommissionDocument Control DeskMail Station PI-137;Washington, DC 20555|Subject: Arkansas Nuclear One - Unit 2Docket No. 50...

PNO-II-96-060A:on 961004,licensee notified NRC that extended shutdown was being initiated to accomplish design mod to increase safety margins.On 960902,plant was shutdown due to problem w/turbine oil sys.Meeting scheduled on 961009.

. . .- . . - . . . - -- . . _ - . -- - - _ _ -._. - ~ . .- . - _ =e tI4-1- October 4, 1996PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-II-96-060AThis preliminary notification constitutes EARLY notice of events of POSSIBLEsafety or public interest significance. T...

TASK INTERFACE AGREEMENT (TIA 2000-16) SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REVIEW OF ADDITIONAL INFORMATION PROVIDED BY LICENSEE FOR RESOLUTION OF FIRE PROTECTION INSPECTION FIRE BARRIER QUALIFICATION ISSUES

UNITED STATES - NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET SW SUITE 23T85 ATLANTA, GEORGIA 30303-8931 September 25, 2000 MEMORANDUM TO: John A. Zwolinski, Director Division of Licensing Project Management Office of Nuclear Reactor...

IR 05000335-00-07, IR 05000389-00-07 on 10/1-12/30/2000, Florida Power & Light Company, St. Lucie Plant, Units 1 & 2. One finding in area of Response to Contingency Events.

January 29, 2001Florida Power and Light CompanyATTN: Mr. T. F. PlunkettPresident - Nuclear DivisionP. O. Box 14000Juno Beach, FL 33408-0420SUBJECT: ST. LUCIE NUCLEAR PLANT - NRC INSPECTION REPORT50-335/00-07, 50-389/00-07Dear Mr. Plunkett:On December 30, 2000, the NRC complete...

IR 05000321-05-002, IR 05000366-05-002 & IR 0720000360-05-001, on 01/01/2005 - 03/31/2005, Edwin I. Hatch Nuclear Plant Unit 1 and Unit 2, Radioactive Material Processing and Transportation.

April 29, 2005Southern Nuclear Operating Company, Inc.ATTN: Mr. H. L. SumnerVice President - Hatch ProjectP. O. Box 1295Birmingham, AL 35201-1295SUBJECT: EDWIN I. HATCH NUCLEAR PLANT - NRC INTEGRATED INSPECTIONREPORT 05000321/2005002, 05000366/2005002, AND 072000036/2005001De...

United States Nuclear Regulatory Commission Southern Nuclear Operating Company ET AL. Docket No. 52-011 Vogtle Electric Generating Plant Site Early Site Permit and Limited Work Authorization Environmental Assessment and Finding of No Significant Impact.

1 UNITED STATES NUCLEAR REGULATORY COMMISSION SOUTHERN NUCLEAR OPERATING COMPANY ET AL. DOCKET NO. 52-011 VOGTLE ELECTRIC GENERATING PLANT ESP SITE EARLY SITE PERMIT AND LIMITED WORK AUTHORIZATION ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT By letter dat...

Event Notification Report for April 19, 2011

U.S. Nuclear Regulatory CommissionOperations Center Event Reports For04/18/2011 - 04/19/2011 ** EVENT NUMBERS ** 467504676546766Agreement StateEvent Number: 46750 Rep Org: PA BUREAU OF RADIATION PROTECTION Licensee: TEAM INDUSTRIAL SERVICES Region: 1 City: CHARTIERS TOWNSHI...

Information Notice No. 98-24: Stem Binding in Turbine Governor Valves in Reactor Core Isolation Coo

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001June 26, 1998NRC INFORMATION NOTICE 98-24:STEM BINDING IN TURBINE GOVERNOR VALVES IN REACTOR CORE ISOLATION COOLING (RCIC) AND AUXILIARY FEEDWATER (AFW) SYSTEMSAddressee...

May 4, 2005 Mr. Theodore Sullivan Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant Post Office Box 110 Lycoming, NY 13093 SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC INTEGRATED INSPECTION REPORT 05000333/2005003 Dear Mr. Su...

Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Plant Summaries> Pilgrim 1 > Quarterly Plant Inspection Findings Pilgrim 1 – Quarterly Plant Inspection Findings 4Q/2017 – Plant Inspection Findings On this page: • Initiating Events • Mitigating S...

2012/05/08 Vogtle RAI for SER - RE: REQUEST FOR ADDITIONAL INFORMATION LETTER NO. 02 RELATED TO LICENSE AMENDMENT REQUEST (LAR) 12-001 FOR THE VOGTLE ELECTRIC GENERATING PLANT UNITS 3 AND 4 COMBINED LICENSES

1VogtlecolRAIsPEm ResourceFrom: Joshi, RavindraSent: Tuesday, May 08, 2012 6:34 AMTo: VogtlecolRAIsPEm ResourceSubject: RE: REQUEST FOR ADDITIONAL INFORMATION LETTER NO. 02 RELATED TO LICENSE AMENDMENT REQUEST (LAR) 12-001 FOR THE VOGTLE ELECTRIC GENERATING PLANT UNITS 3 AND 4...

South Texas Project Units 3 & 4 COLA (FSAR), Rev. 6 - Tier 2 - Chapter 02 - Site Characteristics - Section 02.01 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant

Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard Plant 2.1-1STP 3 & 4 Final Safety Analysis Report2.1 Limits Imposed on SRP Section II Acceptance Criteria by ABWR Standard PlantThe information in this section of the reference ABWR DCD, including all table...

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