Report a Safety Concern
Search

The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

FPL - Turkey Point, Units 6 & 7 COLA (FSAR), Rev. 0 - Part 2 - FSAR - Chapter 2 - Site Characteristics - Section 2.4.14 - Technical Specification and Emergency Operation Requirements

Turkey Point Units 6 & 7COL ApplicationPart 2 — FSARRevision 0 2.4.14-iSUBSECTION 2.4.14:TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTSTABLE OF CONTENTS2.4.14 TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTS ..............................................

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report), Rev. 1 - FSAR Chapter 02 Figure 2.4.2-202

E 1,850,000E 1,848,000E 1,846,000E 1,844,000RAILROADCOOLINGTOWERAREAE 1,846,000E 1,844,000N 1,168,000N 1,166,000N 1,164,000E 1,850,000E 1,846,000E 1,844,000DAMHOLD-UP POND APONDDAMFENCEWAREHOUSE-2WAREHOUSE-1PLANTACCESSPORTALTOSECURITYTRAININGAREAFUTURE DRYCASK STORAGE AREA400 ...

First interim deficiency rept re support for test lines by alternate analysis.Initially reported on 830919.Existing support structure being analyzed to determine if mods necessary for DBA loadings.Next rept by 831205.

- TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II 83 9 3 VMD-50-390/83-57 OND-50-391/83-53 U.S. Nuclear Regulatory Comission Region II Attn: Mr. Jms P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Saite 2900 Atlanta, Georgia 30...

Final - Outlines (Change Summaries - Optional).

ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Millstone Unit 3 Date of Exam: Week of 01/07/02 Exam Level: RO K/A Category Points Tier Group ~K K K K K K A A A A G PonTta Emergency & 2 5 1 2 4 3 2 17 Abnormal 3 0 0 1 1 0 1 3 Plant Tier 8 3 5 8 5 7 36 Evolutions Tota...

Applicant Pre-Filed Mandatory Hearing Exhibit SCE000020, Curriculum Vitae of Timothy W. Schmidt (October 5, 2011).

TIMOTHY W. SCHMIDT PO Box 88, MC P40 Jenkinsville, SC 29065 (803) 941-9843 tschmidt@scana.com EDUCATION AND CERTIFICATION Bachelor of Science, Chemical Engineering, University of South Carolina, 2002 Registered Professional Engineer, South Carolina, License Number 27419...

Forwards RO-270/76-06.

rvTaiic ,Z i.Us[~ ~ ' ~~ ~ ~o.n. nveti An nt outriony coMv nn unexi i noune.n50-270u.roi' 'g'r';c7"' [,' pi.:l uhT yNitG DIGl'lilitU rlON ion PAllT S0 DOCKET MATI:lllAL8%.fitOM:DA10 os noevMr NT,Duke Power Company 7/21/76,Mr. Norman C. MoseleyCharlotte, North Carolina oATtntcu...

FPL - Turkey Point Units 6 & 7 COLA (Final Safety Analysis Report) - Part 2 - FSAR - Chapter 2 - Site Characteristics - Section 2.4.14 - Technical Specification and Emergency Operation Requirements

Turkey Point Units 6 & 7COL ApplicationPart 2 — FSARRevision 6 2.4.14-iSUBSECTION 2.4.14:TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTSTABLE OF CONTENTS2.4.14 TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTS ..............................................

Responds to IE Bulletin 80-20, "Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches." Indicating lights on switches will be rewired as interim solution.List identifying switches encl.

. ---- ---- --- ------~Trc.40915804000-r...L.-PUBLICSERVICEINDIANASeptember 15, 1980S. W. ShieldsSenior Vice Presdent -Nuclear DivisionMr. James C. Keppler, Director Docket Nos.: STN 50-546U.S. Nuclear Regulatory CommissionSTN 50-547Region IIIConstruction Permit Nos.:799 Roose...

Press Release-III-19-021: NRC Issues Confirmatory Action Letter to Fermi Nuclear Power Plant

No: III-19-021 October 8, 2019 Contact: Viktoria Mitlyng, 630-829-9662 Prema Chandrathil, 630-829-9663 NRC Issues Confirmatory Action Letter to Fermi Nuclear Power Plant The U.S. Nuclear Regulatory Commission has issued a Confirmatory Action Letter to the oper...

Discusses plant startup in Cycle 11.On 870106,plant put on-line following refueling outage that began on 861006, ending Cycle 10.Mods performed during Cycle 10 outage listed.

. - - _ _ _ _ - - _ _ _ _ _ _ir C January 7, 1987-Docket No. 50-298MEMORANDUM FOR: R. Bernero, DirectorDivision of BWR LicensingTHRU: D. Muller, Project DirectorProject Directorate #2Division of BWR LicensingFROM: W. Long, Project ManagerProject Directorate #2Division of BWR L...

Forwards table re torus mods for Spring 1979 refueling outage.Analysis is continuing,to determine if further mods are required.Final analysis for major structural components is expected by end of 1979.

0II~I/1 o1nv0t CIIlr:rNl V MllkeklRAKUMQm~KNIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315)474-1511May 16, 1979Mr. Victor Stello, Jr., DirectorDivision of Operating ReactorsOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory ...

Correction to amend to 850808 order,correcting typos in Tech Spec Table 3.6-2 of Encl 3.

f,~ ...-.a.11NITED STATES OF A!iERICA''HUCLEAR REGULATORY C0!iMISSION..In the Matter of ))GENERAL PUBLIC UTILITIES NUCLEAR )Docket No. 50-320,CORFORATION ))'.>(Three Mile Island Nuclear Station, )Unit 2)')>, ,,CORRECTION TO A!!ENDMENT OF ORDER'., dn July 8,1985, the Director, ...

Completion of Commitment for Implementation of Technical Specifications Change Regarding Post-Accident Sampling System Elimination.

CP&L :, Progress Energy Serial: RNP-RA/02-0169 NOV 1 1 2002 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 COMPLETION OF COMMITMENT FOR IMPLEMENTAT...

River Bend Station, Unit 1 - re: Response to Generic Letter 96-06 ( TAC M96858).

June 7, 2001MEMORANDUM TO: FileFROM: Robert E. Moody, Project Manager, Section 1 /RA/Project Directorate IV Division of Licensing Project ManagementOffice of Nuclear Reactor RegulationSUBJECT: RIVER BEND STATION, UNIT 1 - RE: RESPONSE TO GENERICLETTER 96-06 (TAC NO. M96858) In...

ES-301-1 Administrative Topics Outline Form (RO) (copy)

ESg-301IAdministrative.Topics1Outline Form Form ES-301-1 Facility: LaSalle Units 1 & 2 Date of Examination: Nov 13 throuah 24. 2000 Examination Level (circle one):@ SRO Operating Test Number: 1 & 2 Administrative Describe method of evaluation: Topic/Subject 1. ONE Administrati...

Forwards acceptance criteria for evaluation operator action within 30 minutes after onset of PWR main steam line break w/continued feedwater addition.

.- .'(3 ( (p'...,.,.e00f aa butMfMOR AtlDilH FOR:E. Butcher, Chief, Technical AntistanceProgramManaanment Rrotip, OLFPOM:W. Riitler, Chief, Containment Systemt Oranch, 05191nJECT1OPERATOR ACTION ACCCPTANCC CRITCRIA . PWR MAIN $ TEAM LINFRRCAK WITil CONTINUED FEEDWATER A00lil0f...

Summarizes severe accident sequence analysis program activities during Jul 1984.

-~-.a ...r 'Sandia National LaboratorieslAIDucuercue. New Menco 871851iJuly 30, 1984Dr. Thomas J. WalkerContainment Systems Research BranchU. S.Nuclear Regulatory Commission7915 Eastern AvenueSilver Springs, Maryland20910-Dear Tom:This letter summarizes the Severe Accident Seq...

PNO-II-85-120:on 851119 & 1217,concentrated hydrazine/ ammonia mixture leaked from steam generator vent valve. Personnel evacuated.Several cases of breathing difficulties noted.

_December 20, 1985| -PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PN0-II-85-120This preliminary notification constitutes EARLY notice of events of POSSIBLE safety orpublic interest significance.The information is as initially received without verifi-,cation or evalu...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Table 14.3.2-2, Time Sequence of Events for Small Break Loss-of-Coolant Accident.

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Table: 14.3.2-2 Page: 1 of 1 Unit 1 Last Revised: Revision 25.0 Time Sequence of Events for Small Break Loss-of-Coolant Accident Event Time (sec) 1.5-inch 2-...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Table 14.3.2-2, Time Sequence of Events for Small Break Loss-of-Coolant Accident, Page 1 of 1.

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 24.0 Table: 14.3.2-2 Page: 1 of 1 UNIT 2 Time Sequence of Events for Small Break Loss-of-Coolant Accident Event Time (sec) 1.5-inch 2-inch 3-Inch 4-Inch 6-Inch 8.75-inch Break...

EN-04-030, FirstEnergy Nuclear Operating Company.

PRELIMINARY INFORMATION - NOT FOR PUBLIC DISCLOSURE UNTIL VERIFICATION THAT LICENSEE HAS RECEIVED ACTIONMay 7, 2004 EN-04-030 OFFICE OF ENFORCEMENTNOTIFICATION OF SIGNIFICANT ENFORCEMENT ACTIONLicensee: FirstEnergy Nuclear Operating Company (EA-03-209) Davis Besse Nucle...

05/25-26/2004 Presentation, "Codes and Standards to be Applied to the ACR-700 Design in the U.S".

Codes and Standards to be Applied to the ACR-700 Design in the U.S. Al Stretch, Principal Engineer, Safety Concepts Presentation to US Nuclear Regulatory CommissionWashington DC May 25-26, 2004Pg 2Application of Codes and Standards• U.S. regulations, codes and standards will b...

Tech Spec Pages for Callaway, Amendment, Extending the Inspection Interval for Reactor Coolant Pump Flywheels (TAC No. MC2697).

Programs and Manuals5.55.5 Programs and Manuals5.5.4 Radioactive Effluent Controls Program (continued)j. Limitations on the annual dose or dose commitment to any member of thepublic, beyond the site boundary, due to releases of radioactivity and toradiation from uranium fuel c...

FPL - Turkey Point Units 6 & 7 COLA (Final Safety Analysis Report) - Part 2 - FSAR - Chapter 2 - Site Characteristics - Section 2.4.14 - Technical Specification and Emergency Operation Requirements

Turkey Point Units 6 & 7COL ApplicationPart 2 — FSARRevision 7 2.4.14-iSUBSECTION 2.4.14:TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTSTABLE OF CONTENTS2.4.14 TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTS ..............................................

2013/02/27 - Comment (2522) Form E-mail regarding GE Reactors LTR-12-0782

1SECYLettersCEm ResourceFrom: yes [yes@sover.net]Sent: Wednesday, February 27, 2013 5:46 PMTo: NRCExecSec ResourceSubject: Mark I and II BWRsFollow Up Flag: Follow upFlag Status: CompletedChairwoman Allison M. Macfarlane Commissioner Kristine L. Svinicki Commissioner William ...