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Application for amend to COC revising Technical Safety Requirement 3.2.2.b.2 as specified in Issue 37 of DOE/ORO-2027,Rev 3,Change A, "Plan for Achieving Compliance w/NRC Regulation at Portsmouth Gaseous Diffusion Plant."

70 'l604**iUnited States{*Enrichment Corporat!oaI,* ~2 Democracy Co.,ter6903 Rockledge DriveBethesda, MD 20817| jTel. (301) 564-3200Fax: (301) 564-3201l'nileil StatesEnrichenent CorporationiJAMES H. MILLERDir: (301) 564-3309VICE PRESIDENT, pro.JUCTIONFax: (301) 571-8279)Decemb...

LER 98-002-00:on 980308,automatic reactor trip caused subsequent to turbine trip were noted due to loss of turbine plant cooling water.Caused by actual lo lo levels in at least two SGs.Level switches was tested.

.NRC FeRM 366U.S. NUCLEAR RE;ULAToRY CoMMISSloN APPROVED BY OMB NO.3 40410414 95)EXPIRES 04/30/98N NA N NLIEN OIST NES E T L SP^c "'fo^L'TPR! "^,'JM8 'is,n'M"t"c"#Ju ^&dia "LTCENBEE EVENT REPORT (LER)gre T,o TgyggReggageggg(See reverse for required number ofoYCeYsSScEu'EdSN5"s...

LER 87-008-01:on 870817,loss of normal power during shutdown occurred.Caused by routing of all sources of offsite power through one set of breakers while plant in outage. Precautions to be added to procedures.W/871104 ltr.

. . . . , , . . . . . ... . . . . . . . ... . . . .. . . . . . . . . . . . . . . . . . - . . . .. . - ' '. . . . -- . . , .':-'-'-~~-~-mi|LER'87-08, Rev.1 .NAC Fw. ageU.S NUCLEl.R S E;ULATDAY COMusessomM AM'ROYED Dest seo. 1190-4104' " ' " " ' ' ' ' * *' LICENSEE EVENT REPORT ...

LER 09-005-00 for Browns Ferry Nuclear Plant Unit 2, re: Reactor Motor Operated Valve Board 2D & Residual Heat Removal Subsystem Inoperable Longer Than Allowed by the Plant's Technical Specifications.

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000September 16, 200910 CFR 50.73U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D. C. 20555-0001Browns Ferry Nuclear Plant Unit 2Facility Operating License No. DPR-52NRC Docket ...

LER 79-004/03L-0 on 790327:condensate storage tank level fell below Tech Spec limit during hot shutdown.Caused by use of steam generator blowdown sys which was being held at max. Onsite demineralization plant to be added.

i-Ill7 8 CON'T 7 8 0 2 0ZI3 78 7 8 7 8SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE WI F I@ X@ 1 Z zl zI zi Z 1 Z 1 ZIG I._O ji_ 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT LER,"RO r-lVENT YEAR REPORT NO. CODE TYPE REPORT 117 I91 NUMBE...

Diablo Canyon Power Plant, Units 1 and 2 - Response to Request for Clarification of NRC Staff Evaluation Dated 12/14/2009 re Technical Specification Interpretation of 230 Kilovolt System Operability (TAC ME3346 and ME3347).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2010 Mr. John T. Conway Senior Vice President - Energy Supply and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant 77 Beale Street, Mail Code B32 San Francisco, CA...

09/11/2007 - Enclosure 2 - Summary of Public Meeting on TVA Proposed Bellefonte Site Combined License, Held in Duncan Crossroads, Alabama. NRC Presentation on Bellafonte Nuclear Plant Combined License Application.

Thomas Bergman, Deputy Director Thomas Bergman, Deputy DirectorLicensing Operations Licensing OperationsDivision of New Reactor Licensing Division of New Reactor LicensingPublic Outreach MeetingBellefonte Nuclear PlantCombined License ApplicationPurposes of this meetingPurpose...

Watts Bar Nuclear Plant, Unit 1 - Calculation WBNTSR-009, "Control Room Operator and Offsite Doses from a Fuel Handling Accident," Revision 14 (Enclosure 2).

ENCLOSURE 2CALCULATION WBNTSR-009, CONTROL ROOM OPERATOR AND OFFSITE DOSESFROM A FUEL HANDLING ACCIDENT, REVISION 14NPG CALCULATION COVERSHEETICCRIS UPDATE Page 1REV 0 E ISRIMS KO- EMS TYPE. EM CIINN AfrRV0M6 890302 008 Ic--ieuca I o 9! I 0Cab Title: Control Room Operator and ...

San Onofre Nuclear Generating Station, 2008 End-of-Cycle Plant Safety Performance Summary, Assessment Period: Jan 1, 08 thru Dec 31, 08, Exemption 4, Exemption 20.

San Onofre Nuclear Generating Station2008 End-of-Cycle Plant Safety Performance SummaryAssessment Period: January 1, 2008 - December 31, 20081. Operatinqc Summary.A. Power Operations - Noteworthy Unplanned Operating Events and Forced OutagesUnit 2 Power OperationsJanuary 18, 2...

San Onofre Nuclear Generating Station, 2009 Mid-Cycle Plant Safety Performance Summary, Assessment Period: Jul 1, 08 thru Jun 30, 09, Exemption 4, Exemption 5.

San Onofre Nuclear Generating Station2009 Mid-Cycle Plant Safety Performance SummaryAssessment Period: July 1, 2008 - June 30, 20091 Operating Summary,A. Power Operations - Noteworthy Unplanned Operating Events and Forced OutagesUnit 2 Power OperationsSeptember 22 Power reduce...

Responds to NRC Bulletin 85-003,Suppl 1, "Motor-Operated Valve Common Mode Failures During Plant Transients due to Improper Switch Settings."

AC CELERATEDD]4J'SBUTON .DEMONSTR4OON sy.1STEMyREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:8903010154 DOC.DATE: 89/02/21 NOTARIZED: YES DOCKET # FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTH.NAME AUTHOR AFFILIATION MINECKD...

Response to temporary instruction TI02800/030, Verification of the status of devices authorized for use under a general license, RCode 30864, Muskogee Generating Plant.

APPENDIX AFORM TI-i CASE RESOLUTIONCase Status | Open X ClosedRCODE: 30864Region: IVOLD - Complete Name, Address, Contact, Phone Number:Muskogee Generation PlantP.O. Box 321Oklahoma City, OK 73101NEW - Complete Name, Address, Contact, Phone Number:Oklahoma Gas & Electric Servi...

Watts Bar Nuclear Plant response to request for additional information re tritium production - Holtec analysis. Submits new non-proprietary version (Revision 3) of Holtec International Report HI-2012620.

Tennessee Valley Authority, Post Office E'ox 20C0. Sprng C ty. Ternessee 3331 -2000 FFS 1, 1 2WJ2 10 CFR 50.9 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen: In the Matter of ) Docket No.50-390 Tennessee Valley Authority SUBJEC...

Indian Point, Units 2 and 3, Reply to Request for Additional Information Regarding License Renewal Application - Balance of Plant, Fire Protection, and Nickel Alloy.

SEntergy-Entergy Nuclear NortheastIndian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 10511-0249Tel 914 788 2055Fred DacimnoVice PresidentLicense RenewalMarch 12, 2008Re: Indian Point Units 2 & 3Docket Nos. 50-247 & 50-286NL-08-051IU.S. Nuclear Regulatory Commi...

IR 05000324-07-008, 05000325-07-008; Carolina Power and Light; 02/04/2007 through 02/28/2007; Brunswick Steam Electric Plant, Units 1 & 2.

February 28, 2007EA-07-024Carolina Power and Light CompanyATTN: Mr. James ScarolaVice PresidentBrunswick Steam Electric PlantP. O. Box 10429Southport, NC 28461SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NRC INSPECTION REPORTNOS. 05000324/2007008 AND 05000325/2007008; PRELIMINAR...

IR 05000282-01-03(DRS), IR 05000306-01-03(DRS), on 01/29-02/15/2001, Nuclear Management Company, LLC, Prairie Island Nuclear Generating Plant, Units 1 and 2. Refueling and outage occupational radiation safety.

March 7, 2001Mr. J. SorensenSite General ManagerPrairie Island Nuclear Generating PlantNuclear Management Company, LLC1717 Wakonade Drive EastWelch, MN 55089SUBJECT: PRAIRIE ISLAND - NRC INSPECTION REPORT 50-282/01-03(DRS);50-306/01-03(DRS)Dear Mr. Sorenson:On February 15, 200...

LER 12-005-00 for Browns Ferry Nuclear Plant Unit 2, "Unanalyzed Conditions Discovered during National Fire Protection Association 805 Transition Affecting Division II of the Residual Heat Removal System."

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000December 17, 201210 CFR 50.73ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Browns Ferry Nuclear Plant, Units 2 and 3Facility Operating License Nos. DPR-52 and...

Callaway Plant, Unit 1 - Request for Additional Information Related to Generic Letter 2004-02, "Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (TAC MC4671).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 27, 2009 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251 SUB..IECT: CALLAWAY PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMA...