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Dresden, Units 2 & 3, Safety Evaluation, Amendments 191 & 185 re Extended Power Uprate.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 191 TO FACILITY OPERATING LICENSE NO. DPR-19AND AMENDMENT NO. 185 TO FACILITY OPERATING LICENSE NO. DPR-25EXELON GENERATION COMPANY, LLCDRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3DOCKET NOS...

NUREG-1433, Vol. 2, Rev. 3, Standard Technical Specifications General Electric Plants, BWR/4.

NUREG-1433 Vol 2, Rev. 3.0 Standard Technical Specifications General Electric Plants, BWR/4 Bases Manuscript Completed: July 2003 Date Published: August 2003 Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation U.S. Nuclear ...

Palisades, License Amendment 67, Changes TS to Incorporate Certain of the TMI Lessons Learned Category A Requirements.

October 8, 1981 Docket No. 50-255 LS05-81 -10-009 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W. Parnall Road Jackson, Michigan 49201 Dear Mr. Hoffman:D ISTR I t-{ IO~ Docket NRC PDR Local PDR NSICRDi gs (w/fee sheet)SUBJECT: TMI LESSONS L...

Watts Bar Unit 1 - Technical Specification (TS) Change 03-02, "Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank (RWST)" - Response to Request for Additional Information.

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-200010 CFR 50.90AUG 18 2003U.S. Nuclear Regulatory ConmnissionATTN: Document Control DeskWashington, D. C. 20555Gentlemen:In the Matter of ) Docket No.50-390Tennessee Valley AuthorityWATTS BAR NUCLE...

POINT BEACH NUCLEAR PLANT, UNITS 1 & 2 EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISIONS.

Wisconsin Electric A WISCONSIN ENERGY COMPANYPoint Beach Nuclear Plant 6610 Nuclear Rd. Two Rivers, Wl 54241 Phone 920 755-2321NPL 2000-0091 February 22, 2000 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Ladies/Gentlemen: D...

September 26, 2000 Public Meeting Summary

September 26, 2000 Public Meeting SummaryA public meeting was held on September 26, 2000, at NRC-Headquarters to present recentresearch results for a Service Level I concrete coating system applied in PWRs when subjectedto simulated post-DBA conditions. Attendees included NEI...

IR, Nine Mile Point, 1999010, Integrated

January 19, 2000EA 99-328Mr. John H. MuellerChief Nuclear OfficerNiagara Mohawk Power CorporationNine Mile Point Nuclear StationOperations Building, 2nd FloorP.O. Box 63Lycoming, NY 13093SUBJECT: NRC INTEGRATED INSPECTION REPORT NOS. 05000220/1999010 AND 05000410/1999010De...

Peach Bottom Atomic Power Station, Units 2 and 3 Submittal of Changes to Technical Specifications Bases

10CFR50.71 (e)PECO NUCLEAR A Unit of PECO EnergyPECO Energy Company 965 Chesterbrook Boulevard Wayne, PA 19087-5691April 26, 2000 Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 U.S,. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Subject: ...

Safety Evaluation Report With Open Items Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant.

Safety Evaluation ReportWith Open Items Related to the License Renewal ofJames A. FitzPatrick Nuclear Power PlantDocket No. 50-333Entergy Nuclear Operations, Inc.U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationJuly 2007THIS PAGE INTENTIONALLY LEFT BLANK.i...

Surry, Units 1 & 2, Updated Final Safety Analysis Report, Revision 39, Chapter 13: Initial Tests and Operations.

Revision 39—09/27/07 SPS UFSAR 13-i 13.1 TESTS PRIOR TO INITIAL REACTOR FUELING . . . . . . . . . . . . . . . . . . . . . . . . 13.1-113.2 FINAL STATION PREPARATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.2-113.2.1 Core Loading . . . . . . ...

Consolidated Safety Analysis Report for Chern-Nuclear Model No. CNS 10-1 60B, Certificate of Compliance No.9204, and Request for Renewal.

r i- cz c-4,CHEM-NUCLEAR SYSTEMS, LLC140 Stoneridge Drive * Columbia, South Carolina 29210 • (803) 256-0450Mr. E. William Brach, Director March 22, 2000 Spent Fuel Project Office 579-022-00 Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Was...

G20120458 - Final Director's Decision, 2.206 - Wallace Taylor, Sierra Club, Iowa Chapter Ltr to EDO - Fort Calhoun Station (TAC No. ME8973).

[7590-01-P] DD-15-04 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION William M. Dean, Director In the Matter of ) Docket No. 50-285 ) OMAHA PUBLIC POWER DISTRICT ) Renewed License No. DPR-40 ) Fort Calhoun Stat...

Responds to 880415 request for addl info re NUREG-0737,Item II.K.3.5, "Reactor Coolant Pump Trip." Emergency operating procedures encl.

I ' ' I~ ' ~ ~---------consumers Power POW ERi Nii MICHlliAN"S PROliRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 • (517) 788-0550 December 1, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR-20 - PALIS...

Provides corrections to TS amend 69 to SER,establishing sys operability requirements for transfer functions of ECCS semiautomatic switchover from SI to recirculation during LOCA,per NRC exit meeting for insp rept 50-311/97-11.

E. C. Simpson • >;,. .· 'l!1\\\'-I. Public Service Electric and Gas Company • Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President - N~clear Engineering MAY 2 7 1997 LR-N970293 United States Nuclear Regulatory Commi...

Toshiba Design Control Document Rev. 1 - Tier 2 - Chapter 18 - Human Factors Engineering - Appendix 18D - Emergency Procedures Guidelines - Input Data and Calcuation Results

Emergency Procedures Guidelines—Input Data and Calculation Results 18D-1RS-5146900 Rev. 1Design Control Document/Tier 2 ABWR18D Emergency Procedures Guidelines—Input Data and Calculation Results18D.1 IntroductionThe Emergency Procedure Guidelines (EPGs) given in Appendix 18A...

Transmittal of Holtec Safety Analysis Report on the HI-Star 180D Package, HI-2125175, Revision 1 (Non-Proprietary).

IMEN.HOLTECINTERNATIONALHoltec Center, 555 Lincoln Drive West, Marlton, NJ 08053Telephone (856) 797-0900Fax (856) 797-0909January 31, 2013Pierre Saverot, Project Manager - Licensing BranchDivision of Spent Fuel Storage and TransportationOffice of Nuclear Material Safety and Sa...

Submittal of Technical Report "Evaluation for 4S Emergency Planning Zone".

Leading Innovation »>>TOSHIBA CORPORATION1-1 ,SHIBAURA 1-CHOME, MINATO-KU TOKYO 105-8001 ,JAPANTOS-CR-4S-2011-0002Project Number 0760September 26, 2011U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555-0001Subject: Submittal of Technical Report "Evalua...

LER 91-013-00:on 910624,reactor bldg trackway inner door discovered open w/no monitor in attendance.Caused by personnel error.Maint personnel involved counseled & temporary procedure change initiated.W/910716 ltr.

.. • Com·· wealth Edison Dresd clear Power Station · R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 EDE Ltr: # 91-435 U.S. Nuclear Regulatory Commission Document Control Desk · Washin~ton, D.C. 20555 July 16, 1991 Licensee Event Report # 91-013, Docket fl 050237 'is bei...

IE Insp Repts 50-443/79-07 & 50-444/79-07 on 790813-16. Noncompliance noted:failure to reject unacceptable void in cadweld splice & to provide details in Perini procedure for major concrete repairs.

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-443/79-07 Report No. 50-444/79-07 50::443 Docket No.· 50-444 --"'-"''---'--'-'----Region I C PPR- l 35 License No. CPPR-136 Priority ------- Category ---""""A"'"----Licensee: Public Service Companv of N...

Proposed Tech Specs re reduced temp & pressure program.

EMERGENCY CORE COOLING SYSTEMSSURVEILLANCE RE UIREMENTS Continued2. At least once per 18 months.Boron InjectionThrottle ValvesSafety InjectionThrottle ValvesValve Number Valve Number1.2.3.4.1-SI-141 Ll1-SI-141 L21-SI-141 L31-SI-141 L41. 1-SI-121 N2 ~ 1-SI-121 Sh. By performing...

OFFICIAL EXHIBIT - INT022-00-BD01 - Simpson Gumpertz & Heger Document No. 170444-MD-01, Rev. 1, "Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by ASR," for Seabrook (Encl. 3 to Letter SBK-L-18074, re: Seabrook . . .

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD In the Matter of NEXTERA ENERGY SEABROOK, LLC (Seabrook Station, Unit 1) Docket No. 50-443-LA-2 ASLBP No. 17-953-02-LA-BD01 Hearing Exhibit Exhibit Number: Exhibit ...

Part 03 - Applicants Environmental Report - Standard Design Certification (Rev. 3) - Part 03 - Applicants Environmental Report - Standard Design Certification - Section 1.0 - Appendix B

NuScale Standard PlantDesign Certification ApplicationApplicant's Environmental Report - Standard Design CertificationPART 3Revision 3August 2019©2019, NuScale Power LLC. All Rights ReservedCOPYRIGHT NOTICEThis document bears a NuScale Power, LLC, copyright notice. No right to...

Proposed tech specs,proposing to revise TS to implement 24 month plant refueling cycle which includes operating cycle & one refueling/maintenance outage.

.. . . . . . . . . .,., ,ATTACHMENTTechnical Specification Change.P_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _._ _ . _ _e 91.2.7 REFUELING OPERATION |An operation involving a change in core geometry by manipulation of fuel orcontrol rods when the reactor vessel head is...

Application for amend of License NPF-3,changing Tech Specs Sections 3,4 & 6 re proposal to deautomate valve shifts caused by Incident Level 5 of safety features actuation sys. Draft proposed mods to operating procedures encl.

.ODocket No. 50-346License No. NPF-3Serial No. 678January 15, 1981Attachment AAPPLICATION FOR AMENDMENTTOFACILITY OPERATING LICENSE NO. NPF-3FORDAVIS-BESSE NUCLEAR POWER STATIONUNIT 1Enclosed are forty (40) copies of the requested changes to the Davis-Besse Nuclear Power Stati...

Provides addl info to support util 950501 application for amend to license NPF-49,by modifying SRs re Type B & Type C tests & bypass leakage tests.Summary of component leakage results from each refueling outage to present encl.

.y. _ . _.#- 4"Nnd2 7 8*'d'" 8" c. sertin, er 06037--..LUtilities SystemNortheast Uth Ser*e Conngany'P.O. Box 270Ilartford, CT 06141-0270 ,(203) 665-5000October 20, 1995Docket No. 50-423B15396Re: 10CFR50.90U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashi...