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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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Redacted Braidwood Station, Units 1 & 2 and Byron Station, Unit 1 & 2, Revision 17 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection.

B/B-UFSAR 12.0-i REVISION 1 – DECEMBER 1989 CHAPTER 12.0 - RADIATION PROTECTION TABLE OF CONTENTS PAGE 12.0 RADIATION PROTECTION 12.1-1 12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE 12.1-1 12.1.1 Policy Considerations 12...

Forwards info re potential interaction between nonsafety- grade sys & safety-grade sys,in response to NRC 790917 ltr. Review has not identified any interaction.

..ARKANSAS POWER & LIGHT COMPANYPOST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4422WILLIAM CAVANAUGH lli October 5,1979Vice PresidentGeneradon & Construction2-109-5Mr. H. R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. Nu c l e a r Reg ul a t o.- -- Com...

Preliminary P2 SER NuScale Ch 15 Redacted Version - Clean

1 15 TRANSIENT AND ACCIDENT ANALYSES SPECIAL NOTE: This PRELIMINARY PHASE 2, CHAPTER 15, “TRANSIENT AND ACCIDENT ANALYSES,” SAFETY EVALUATION REPORT (SER) is based on Chapter 15 of the NuScale design certification application, Revision 2. This preliminary SER chapter incl...

Forwards responses to listed open items discussed at 830118 meeting.Responses to be incorporated in future amend to OL application.

o...o5" * SW'"|PUBLIC SERVICEL,'..z.'_., ONice:Company of New Hampshir e 1671 WorceWer RoadFrominoham, Mossochusetts 01701(617) - 872 8100January 20, 1983SBN- 427T. F. B7.1.2United State Nucicar Regulatory CommissionWashington, D. C. 20555Attention: Mr. George W. Knighton, Chi...

Rev 0 to "IDVP Verification of Diablo Canyon Unit 1 Activities - Rupture Restraints," Interim Technical Rept 65.

.-|Robert L. Cloud and Associates, Inc_lInterim Technical ReportDIABLO CANYON UNIT 1IDVP VERIFICATION OF DCP ACTIVITIES-Rupture Restraints-ITR #65, Revision 0,t..Docket No. 50-275License No. DPR-7644Owh A &'1463 E M De w911sIg3Project Rev:Lewer/DateProject Manager /Date'Techni...

Rev 7 to "Pump & Valve Testing Program."

. . _ - . - _______-__ __.Attachn ent 11jIDISlIRJJ1ErlNUCLE AR OffiERATING STATION11tMP AT1D VQYs1])dl'RVICE TESTING PPOGRAMRevision 7October, 1991911:0401,: 911011PDRADOC K 0":,000;J t 9P f DR_ _ _ - - - - _ - _ _. . . _ _ _ _ . _ __._.._..._.-______,_.._.m._____..__.._____-_...

Forwards proposed amends to proof & review Tech Specs re fire detection instrumentation & chemical treatment ponds & justification.

#o,DUKE PowEn Gomwxyl'.O. lHlx 3:11f18)CitABilA)Trt!, N.O. MI5242II AI. II. TL*CKEHtra.m pesown- , . . . . . . ,no.o ara-m u| April 26, 1984m . . . ,-m||Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory Commission|Washington, D. C. 2055...

Omaha Public Power District - Exigent License Amendment Request 13-02 Revise Current Licensing Basis to Adopt a Revised Design Basis / Methodology for Addressing Design-Basis Tornado / Tornado Missile Impact.

Employment with Equal Opportunity 444 South 16th Street Mall Omaha, NE 68102-2247 July 21, 2013 LIC-13-0061 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 References: 1. Docket No. 50-285 2. Regulatory Guide 1.76, Revision 1, “...

AREVA Design Control Document Rev. 4 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.2.2 Component Cooling Water System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Revision 4 Page 9.2-259.2.2 Component Cooling Water SystemThe component cooling water system (CCWS) is a closed loop cooling water system that, in conjunction with the essential service water system (ESWS) and the ultimate heat sink (UH...

Quad Cities, 2014 NRC Scenario 1.

Quad Cities 2014 NRC EXAM Scenario 1 - 1 - Exelon Nuclear 2014 ILT NRC Exam Scenario Scenario Number: NRC Scenario 1 Revision Number: 00 Date: 10/17/13 Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Repre...

(Quad Cities) 2014 NRC Scenario 1.

Quad Cities 2014 NRC EXAM Scenario 1 - 1 - Exelon Nuclear 2014 ILT NRC Exam Scenario Scenario Number: NRC Scenario 1 Revision Number: 00 Date: 10/17/13 Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Repre...

G20110563 - Final Director's Decision DD-15-11 - David Lochbaum/Union of Concerned Scientists

[7590-01-P] DD-15-11 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION William M. Dean, Director In the Matter of ) ) Boiling-Water Reactor ) (10 CFR 2.206) Operating-Power Reactors ) With Mark I and Mark II ) Conta...

Enclosure 2 - Detailed Status of Generic Issues (GIs).

Enclosure 2 Detailed Status of Generic Issues (GIs) TABLE OF CONTENTS Description of Generic Issues Program iiAcronyms iv4th Quarter FY 2015 GIMCS Report for Active GIs GI-191, Assessment of Debris Accumulation on PWR Sump Performance 1 GI-193, BWR ECCS Suction Concerns ...

Pilgrim Nuclear Power Station - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. John A. Dent, Jr. Site Vice President Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 March 3, 2016 SUBJECT: PILGRIM NUCLEAR POWER STATION - S...

Generic Issue Management Control System Report for Second Quarter FY2016 - Enclosure 2.

Enclosure 2 Detailed Status of Generic Issues (GIs) TABLE OF CONTENTS Description of Generic Issues Program ii Acronyms iv GIMCS Report for Active GIs GI-191, Assessment of Debris Accumulation on PWR Sump Performance 1 GI-193, BWR ECCS Suction Concerns 11 GI-199, Implica...

McGuire, Units 1 and 2 - Offsite Dose Calculation Manual, Revisions 55 and 56.

McGuire Nuclear Station Units 1 and 2 ODCM Offsite Dose Calculation Manual McGuire Nuclear StationUnits 1 and 2 OFFSITE DOSE CALCULATION MANUAL (ODCM) Revision 57 Prepared By: Christopher C. Courtenay 2/11/2016 Fleet Scientific Services RP Signature Date Reviewed By: Tara E...

"Pilgrim Core Shroud Insp Plan."

[t.t--,.ENCLOSURE A-,.PILGRIM CORE SHROUD INSPECTION PLANBACKGROUNDBoston Edison Company (BECo) completed a core shroud modification during refueling outage(RFO) 10 in response to GL 94-03. BECo examined the core shroud modification daring RFO11 in accordance with BWRVIP-07 " ...

Affidavit of AS Masciantonio in response to Board 860313 hearing question re guidance on relationships between qualification test sample,production equipment & margin applied during qualification tests.Reg Guide 1.89 encl.

_ _ . _ _ _ _ _ . _ _ _ _ _ _ ~._ . _ . _ , . _ . . . . __ _ _ _ _ . _ _**,kUNITED STATES OF AMERICA-NUCLEAR REGULATORY COMMISSION..BEFORE THE ATOPUC SAFETY AND LICENSING BOARDIn the Matter of ).)GEORGIA POWER COMPANY ) Docket Nos. 50-424--et al.)50-425) (OL)(Vogtle Electric G...

Rev 0 to NEDO-32645, "Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept."

. .- .- . . . - .,c\g- ,'GENuclear Energy_.NEDO-32645Revision 0DRF B21-00661-00Class IJanuary 1999LIMERICK GENERATING STATIONUNITS 1 AND 2SRV SETPOINT TOLERANCE RELAXATIONLICENSING REPORT| . (Y.C.ChuNuclear & Safety AnalysisiLD E::_4 t/7/99|R. T EarleSystems Engineering|(-w-Ap...

"TMI Unit 1 PRA,Plant Model Rept," Vol 3.

_.!|CopyCopyright 01987, byPLG-0525|GPU Nuclear CorporationVolume 3|,|1Three Mile Island Unit 1!Probabilistic Risk Assessment..PLANT MODEL REPORTProject DirectorB. John GarrickProject ManagerDouglas C. IdenPrincipal InvestigatorFrank R. HubbardTask LeadersMardyros KazariansAli...

Safety evaluation supporting Cycle 2 operations.

*'', . .*.,/I%, UNITED STATES; g NUCLEAR REGULATORY COMMISSION%WASHINGTON, D. C. 20555k....,/'+ENCLOSURE 1SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONSUPPORTING CYCLE 2 OPERATIONSLOUISIANA POWER AND LIGHT COMPANYWATERFORD STEAM ELECTRIC STATION, UNIT 3DOCKET N...

Partially withheld ltr forwarding transcripts of feedback meetings conducted by telcon on 850502 & 0617.

o4[%,U ITED STATESg, g NUCLEAR REGULATORY COMM!SSION,( b',g;WASHINGTON. D. C. 20065*\...../.JUL 2 51985Mrs. Juanita EllisCitizens Association for Sound Energy,1426 South Polk*-Dallas, Texas 75224Re: Transcript of 6/17/85 ."eedback Interview-.,Dear Mrs. Ellis:!Enclosed is one c...

Forwards response to NRC RAI re 961213 amend to plants TS to adopt improved TS of NUREG-1431,Rev 1.Submittal does not include replacement of current TS markup pages as discussed with NRC in 970812 telcon.

|Commonwealth I'dison Company**e e .liraidwood Generating StationRoute *l. Ilox H iIlraceville.11. N) 607-9619|TelHi&l582801|**. .lSeptember 21,1998 IlUnited States Nuclear Regulatory CommissionAttn: Document Control DeskWashington D.C. 20555 - 0001Subject:Commonwealth Edison'...

Insp rept 50-271/97-05 on 970601-07-19.Violations noted. Major areas inspected:licensee operations,engineering,maint & plant support.

tiU.S. NUCLEAR REGULATORY COMMISSIONREGION IDocket No. 60 271ILicensee No. DPR 28_ Report No.97 05 ,,Licensee:Vermont Yankee Nuclear Power Corporation| Facility:Vermont Yankee Nuclear Power StationLocation: Vernon, Vermont!I~Dates: June 1 July 19,1997Inspectors:William A. Cook...

Proposed Tech Specs,providing addl changes for full power OL.

-) 200'F*,4. COLD SHUTDOWN Shutdown # ## ,*** 1 200*F5. REFUELING * Shutdown or Refuel ** #$ 140*F..#The reactor mode switch may be placed in the Run or Startup/ Hot Standby-position to test the switch in,terlock functions provided that the control-rods are verified to remain ...