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North Anna Power Station, Unit 1

Location: Louisa, VA (40 miles NW of Richmond, VA); Region II; Type: Westinghouse Three-Loop; Licensed MWt: 2940

North Anna Power Station, Unit 2

Location: Louisa, VA (40 miles NW of Richmond, VA); Region II; Type: Westinghouse Three-Loop; Licensed MWt: 2568

08/22/2013 Summary of Meeting Between The NRC Staff, General Electric Hitachi Nuclear Energy, DTE Electric Company And Dominion Virginia Power To Discuss The Program Status Of The Economic Simplified Boiling Water Reactor Design Center.

September 19, 2013 MEMORANDUM TO: Ronaldo Y. Jenkins, Branch Chief Licensing Branch 3 Division of New Reactor Licensing Office of New Reactors FROM: David Misenhimer, Project Manager /RA/ Licensing Branch 3 Division of New Reactor Licensing Office of New Reactors ...

Potential Part 21 Unqualified Component in Certain Allen Bradley Timing Relays.

0812612016 U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel Part 21 (PAR) Event# 51030 Rep Org: AZZ/NLI NUCLEAR LOGISTICS, "INC Notification Date I Time: 05/01/2015 13:32 (EDT) Supplier: ALLEN BRADLEY Event Date I Time: 04/30/2015 (CDT) Last Modification...

Answer to petitions to intervene & request for hearing. Redwood Alliance,DH Bosco & B Keene petitions should be denied,per 10CFR2.714 requirements.DE Hauser & W Chesbro petitions acceptable.Certificate of Svc encl.

l(.i*1IDOCKETEDUSNRC1UNITED STATES OF AM C2NUCLEAR REGULATORY CO S h 'E3BEFORE THE ATOMIC SAFETY AND QTCENSING- BOARD00Cntiiru a u.!>tEf.BRAIC!4In the Matter of )5)~rTbPACIFIC GAS AND ELECTRIC COMPANY ) Docket No. 50-133 U6)License No. DPR-7(Humboldt Bay Power Plant, Unit No. ...

Summary of 890907 meeting w/util in Rockville,MD to discuss Safety Sys Outage Mods Insp Finding IC-3,alleging that non-Class 1E pressure transmitters powered from Class 1E buses w/o proper isolation.Viewgraphs & attendees list encl.

7f .*,;.,a''.September 26, 1989.Docket Nos. 50-338and 50-339-LICENSEE: Virginia Electric & Power Company (VEPCO)FACILITY: North Anna 1 & 2SUBJECT:SUMMARY OF MEETING HELD WITH VEPC0 (THE LICENSEE) TO DISCUSS SS0MIFINDING 10-3 REGARDING ISOLATION OF NON-CLASS 1E COMPONENTS POWER...

2009/02/13-Southern Nuclear Operating Co., Docket No. 52-011-ESP, March 2009 Evidentiary Hearing on Contested Environmental Issues, List of Re-Revised Direct and Rebuttal Exhibits.

Southern Nuclear Operating Co., Docket No. 52-011-ESP March 2009 Evidentiary Hearing on Contested Environmental Issues Re-Revised Direct and Rebuttal Exhibits Party Exh. # Witness/ Panel Description Direct Exhibits NRC000001 ALL NUREG-1872, Final Environmental Impact St...

SECY-13-0047 - Weekly Information Report - Week Ending 04/26/13

INFORMATION REPORT May 2, 2013 SECY-13-0047 For: The Commissioners From: Reginald W. Mitchell Assistant for Operations Office of the Executive Director for Operations Subject: WEEKLY INFORMATION REPORT - WEEK ENDING April 26, 2013 Contents Enclosure O...

E-mail from L. Burkhart, NRR, to B. Sheron, NRR, Re: Answers to EDO Questions.

LVVIIIL LUNLIL - flu. MI'4QVVrb I 'J LJJ UQI I'.Ji'd raue IFrom: To: Date: Subject:Lawrence Burkha t'J PK 10/15/01 4:03PM Re: ANSWERS TO EDO QUESTIONSWould you like me to send to my EDO contact (Stacy Rosenberg) or will you forward? >>> Brian Sheron 10/15/01 04:02...

Potentially Unqualified Component in Certain Allen Bradley Timing Relays.

0811512016 U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel Part 21 (PAR) Event# 51030 Rep,Org: AZZ/NLI NUCLEAR LOGISTICS, INC Supplier: ALLEN BRADLEY Notification Date I Time: 05/01/2015 13:32 (EDT) Event Date I Time: 04/30/2015 (CDT) Last Modification:...

Surry Power Station, Unit 1 and 2 -Safety Evaluation of Relief Request for S1-I5-ISI-01 & S2-I5-ISI-01 Regarding use of ASME Section XI 2004 Edition (TACS ME8774 and ME8775).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 29, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SUBJECT: SURRY PO...

Enclosure 1 - MFN 06-224 Supplement 2, NEDO-33181, Revision 2, "NP-2010 COL Demonstration Project, Quality Assurance Plan," July 2006.

ENCLOSURE 1MFN 06-224Supplement 2NEDO-33181, Revision 2,"NP-2010 COL Demonstration ProjectQuality Assurance Plan," July 2006General Electric CompanyGE EnergyNuclear3901 Castle Hayne RdWilmington, NC 28401NEDO-33181Revision 2Class IeDRF# 0000-0037-8794July 2006NP-2010 COL DEMON...

Followup to 911121 Part 21 rept re potential defects in Model 763 & 763A transmitters,consisting of listing of customer names,model numbers & serial numbers of all products which could be affected.

4 °, IITTITT Fluid Technology Corponrati Barton 900 South Turnbull Canyon Road P.O. Box 1882 City of Industry, CA 91749-1882 Telephone: (818) 961-2547 Telex 67.7475Rgw F. Muphy GwnerM A&gwrNovember 26, 1991 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Direct...

2008/09/09 North Anna 3 COL Hearing - RE: Request for meeting minutes

1PMNorthAnna3COLPEmails ResourceFrom: Diane Curran [dcurran@harmoncurran.com]Sent: Tuesday, September 09, 2008 12:08 PMTo: Jerry HaleCc: annie@ieer.org; arjun@ieer.org; Jim Blackburn; Charles Irvine; Mark Tonacci; Andrea JohnsonSubject: RE: Request for meeting minutesAttachmen...

2Q/2008 ROP Action Matrix Summary The assessment program collects information from inspections and performance indicators (PIs) in order to enable the agency to arrive at objective conclusions about the licensee's safety performance. Based on this assessment information, ...

Information Notice No. 93-34 – IN 93-34: Potential for Loss of Emergency Cooling Function due to a C

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 April 26, 1993 NRC INFORM...

October 27, 2003 Virginia Electric and Power Company ATTN.: Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Innsbrook Technical Center - 2SW 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SUBJECT: NORTH ANNA POWER STATION - NRC INTEGRATED INSPECTION...

Transmittal of IE Bulletin 77-01: Pneumatic Time Delay Relay Setpoint Drift.

9 * CENTRAL FILES APR 29 1977' DOC~et 17o. 501--2f)63 Docl:'i- ! c 50-106 Nort~hf.ru1 Stirtes Power Com~pany YTi r. LaJo 'Wchter Vic.e P% e id1erzt Power ProilUction and Syatem Opera~tion 'Urneapolis, >~55401 Gent lei-en Enclo-,ed in~ 13 Fulle1tin No. 77-01 Tfi&-c requirea act...

Millstone Nuclear Power Station, Unit 1, 2, and 3 - Termination of Review of Application for Orders and Conforming License Amendments for License Transfers Related to Corporate Restructuring (TAC NOS. MB2850, MB2851, MB2852)

July 9, 2002Mr. J. A. PriceVice President - Nuclear Technical Services - MillstoneDominion Nuclear Connecticut, Inc.c/o Mr. David A. SmithRope Ferry RoadWaterford, CT 06385SUBJECT: MILLSTONE NUCLEAR POWER STATION, UNIT NOS. 1, 2, AND 3 -SUSPENSION OF REVIEW OF APPLICATION FOR...

Virgil C. Summer Nuclear Station - Relief Request for Utilization of Code Case N-597.

Stephen A. Byrne Senior Vice President, Nuclear Operations 803.345.4622 May 13, 2002 A SCANA COMPANY RC-02-0093 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen: Subject: VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICEN...

NRC Request for Information on AREVA Creusot Forge Forgings in U.S. Components and Carbon Segregation.

A AREVA February 3, 2017 NRC:17:008 Mr. Paul Krohn U.S. Nuclear Regulatory Commission Deputy Director, Division of Construction Inspection and Operational Programs Office of New Reactors 11555 Rockville Pike Rockville, MD 20852 NRC Request for Information on Creusot Forge Forg...

Updated LER 80-062/03X-1:on 810724,15 block walls determined to not meet design requirements of IE Bulletin 80-11.Caused by upgrading of design requirements for masonry walls. Design changes being developed.

UPDATEDREPORT-PREVIOUSREPORTDATE08-20-dN,U.S. NUCLEAR REGULATORY COMMISSION-*LICENSEE EVENT REPORTCONTROL BLOCK / / / / / / / (1) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)/0/1/ /V/A/N/A/S/5/ (2) /0/0/-/0/0/0/0/0/-/0/0/ (3) /4/1/1/1/1/ (4) / / / (5).LICENSEE CODE LICENSE ...

LER 81-084/03L-0:on 811203,while in Mode 1 operation,doors between rod drive room & auxiliary bldg failed to close & latch automatically.Caused by closure & latching mechanism failure or by door misalignment.Doors repaired.

__ .. - --_ - . - . . .. . .'U.S. NUCLEAR REGULATORY COMMISSION-~" "LICENSEE EVENT REPORT--CONTROL BLOCK'/ / / / / / / (1)(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)/0/1/ /V/A/N/A/S/1/s(2)-./0/0/-/0/0/0/0/0/-/0/0/ (3) /4/1/1/1/1/ (4) / / / (5)-LICENSEE CODE > LICENSE' NUMB...

Proposed Tech Spec change revising audit frequencies for emergency & security plans to once every 12 months.

-,o ..--ADMINISTRATIVE CONTROLS6.5.3QUALITY ASSURANCE DEPARTMENTFUNCTION6.5.3.1 The Quality Assurance Department shall function to audit stationactivities. These audits shall encompass:The conformance of facility operation to provisions containeda.within the Technical Specific...

Safety evaluation accepting util 880301 response to NRC Bulletin 88-002, "Rapidly Propagating Fatigue Cracks in Steam Generator Tubes."

peng,' JP IoUNITED STATESgNUCLEAR REGULATORY COMMISSION8 eATTACHMENT 1a,{iw AssisotoN. o. c. aosss\, . . . . . /'-..SAFETY EVALUATION BY THE OFFICE OF SPECIAL PROJECTSTVA'S RESPONSE TO NRC BULLETIN NC. 88-02"PAPIOLY PROPAGATING FATIGUE. CRACKS IN STEAM GENERATOR TUBES"TENNESSE...

Forwards response to NRC 821026 questionnaire re steam generator tube integrity.Data for each facility compiled in separate sections.

e e. • A VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART' VICE PRESIDENT NUCLEAR OPERATIONS December 1, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Darrell G. Eisenhut9 Director Division of Licensing U. S. Nucle...

Enclosure 7 - Attachment 4 - Post-Accident Radiation Response for Primary Sample Line.

Serial No.: 18-364 Docket Nos.: 50-245/336/423/338/339/280/281 72-2/16/4 7 /55/56 Enclosure 7 ATTACHMENT 4 POST-ACCIDENT RADIATION RESPONSE FOR PRIMARY SAMPLE LINE • Fleet Calculation RA-0079, Post- Accident Radiation Response Curves for Primary Hot Leg Sample Lines Dominion E...