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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Palo Verde, Unit 1, Issuance of Amendment No. 27, revising TSs in number of areas in order to be consistent with areas of TS.

March 2, 1988Docket No.: STN 50-528 Mr. E. E. Van Brunt, Jr. Executive Vice President Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034Dear Mr. Van Brunt:DISTRIBUTION Docket File NRC & Local PDRs PDV Reading DMCrutchfield GMHolahan JLee EALicitra...

McGuire, Units1 & 2, License Amendments 177 & 159, Revising TS Table 3.3-4, "Engineered Safety Features Actuation System Instrument Trip Setpoints."

November 25, 1997 'Mr. H. B. Barron Vice President, McGuire Site Duke Energy Corporation 12700 Hagers Ferry Road Huntersville, NC 28078-8985SUBJECT: ISSUANCE OF AMENDMENTS - MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TAC NOS. M99763 AND M99764)Dear Mr. Barron: The Nuclear Regulat...

Browns Ferry, Unit 1, Notice of Consideration, Related to Forthcoming Cycle 6 Core Reload and Plant Modifications Being Performed During the Refueling Outage.

October 24, 1983 Docket No. 50-259 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401 Dear Mr. Parris: Re: Browns Ferry Nuclear Plant, Unit No. I The Commission has filed the enclosed "Notice of Considerat...

Part 2 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal.

Nuclear Management Company, LLCMonticello Nuclear Generating PlantATTACHMENT 9MNGP Code Class Color Classifications and Drawings (P & IDs)Page I of 56Revision 0MONTICELLO NUCLEAR GENERATING PLANT 4 AWI-01.03.03TITLE: COLOR CODED P&ID Q-LIST EXTENSION Revision 4Page 8 of 225.0 ...

Draft - Outlines & NRC Comments.

8113/02NMP#1 EXAM OUTLINE COMMENTS 0 RO Admin, Test A, A.2.2 questions are leading - review ST and determine acceptability. 0 SRO Admin, Test A, . A. 1.1 J PM will be revised to 2 questions because of confusion with the contractors. 0 SRO Admin, Test A, A.3 will be revised t...

NRC Staff Pre-Filed Evidentiary Hearing Exhibit NRC-055, (ML13080A034) Redacted Bates - Carla Smith Scenario 6.

Appendix 0 Scenario Outline Form ES-D-1 Facility: VQgtie Scenario No.: 6 Op-Test No.: 2012-301 Examiners: M-.lL Operators: ~~ ~\ Initial Conditions: The plant is at 100% power, BOL, steady state operations, control rods in automatic. (Base IC # 10, snapped to Ie # 186 for HL1...

Surry Power Station, Unit 2 - Alternatives to the Requirements of the ASME Code and Use of a Subsequent Edition and Addenda of the ASME B&PV Code, Section XI (TAC No. MF4129).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd. Glenn Allen, VA 23060 March 16, 2015 SUBJECT: SURRY POWER STATION...

South Texas Project Units 3 & 4 COLA (FSAR), Rev. 9 - Tier 2 - Chapter 01 - Introduction - Appendix 01E Response to NRC Post-Fukushima Recommendations

Response to NRC Post-Fukushima Recommendations 1E-1STP 3 & 4 Final Safety Analysis Report1E Response to NRC Post-Fukushima Recommendations1E.1 IntroductionIn response to the accident at the Fukushima Daiichi Nuclear Power Plant caused by the March 2011, Magnitude 9 Tohoku ea...

Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (UFSAR), Revision 26, Chapter 15, Appendix A, License Renewal.

IP2 FSAR UPDATE Page 1 of 33 Appendix A for License Renewal Revision 26, 2016 A.1 INTRODUCTION This appendix provides the information submitted in an Updated Final Safety Analysis Report Supplement as required by 10 CFR 54.21(d) for the Indian Point Energy Center (IPEC) ...

2015/12/02 NRR E-mail Capture - Diablo Canyon 1 and 2 - Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term per 10 CFR 50.67 (TAC Nos. MF6399 and MF6400)

1NRR-PMDAPEm ResourceFrom: Lingam, SivaSent: Wednesday, December 02, 2015 8:19 AMTo: Schrader, Kenneth (KJSe@pge.com)Cc: Pascarelli, Robert; Shoop, Undine; Bucholtz, Kristy; Mazaika, Michael; 'mjrm@pge.com'; rntt@pge.comSubject: Diablo Canyon 1 and 2 - Requests for Additional ...

Redacted Prairie Island ISFSI - Safety Analysis Report, Addendum, Non-Proprietary.

PRAIRIE ISLAND INDEPENDENT SPENT FUEL STORAGE INSTALLATIONSAFETY ANALYSIS REPORT Revision: 13Page A1.1-1SECTION A1 INTRODUCTION AND GENERAL DESCRIPTION OF STORAGE SYSTEM A1.1 INTRODUCTION Section 1.1 provides historical information regarding the need to provide dry storage at ...

Susquehanna - Final Outlines (Folder 3).

ES-401 Written Examination Outline Form ES-401-1 Facility: Susquehanna Date of Exam: January 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G 1 2 3 4 5 6 1 2 3 4 * Total A2 G* Total . 1 2 3 4 <<• 4 3 3 20 3 4 7 1. .\ .. ,. . Emergency 2 1 1 1 ··:.!•...

Peach Bottom, Units 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-484, "Use of TS 3.10.1 for Scram Time Testing Activities," Revision 0, Using the Consolidated Line Item Improvement Process.

Exelon Generation® December 23, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 Peach Bottom Atomic Power Station, Units 2 and 3 Subject: Renewed Facility Oper...

Cooper Nuclear Station - Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, "Elimination of Requirements for a Post Accident Sampling System (PASS)" (TAC No. MF4452).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Oscar A. Limpias Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 May 29, 2015 SUBJECT: COOPER NUCLEAR STATION - ISSUANCE OF AMENDMENT TO ELIMINATE R...

McGuire, Units 1 and 2 - Offsite Dose Calculation Manual (ODCM), Revision 55.

McGuire Nuclear Station Units 1 and 2 ODCM Offsite Dose Calculation Manual DUKE ENERGY~ McGuire Nuclear Station Units 1 and 2 OFFSITE DOSE CALCULATION MANUAL (ODCM) Revision 55 b;{:!~ , . rr'L Prepared By: Christopher C. Courtenay/ Fleet ...

15-0681-FMEA-001, Revision 0, "System Level Failure Modes & Effects Analysis (FMEA)."

S Prepar PacifDiablProce MarchSystem red for: fic Gas lo Canyess Proh, 2016 Level FN& Elecyon PowotectionFailure (FDocuRevi Nuclear Stric Cower Plan SysteModesFMEA)ument Nsion 0 Safety-R . ant Unitem Reps & EffeNo. 15-06Relatedts 1 & 2placemeects An681-FME2 ent...

Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 16, 2016.

[7590-01-P] NUCLEAR REGULATORY COMMISSION [NRC-2016-0026] Biweekly Notice Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations AGENCY: Nuclear Regulatory Commission. ACTION: Biweekly notice. SUMMA...

Byron Station, Unit 1 - Relief From the Requirements of the ASME Code (TAC No. MF5554).

Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 30, 2015 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: BYRON STATI...

Clinton - Updated Safety Analysis Report (USAR), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems.

CPS/USAR CHAPTER 05 5-i REV. 13, JANUARY 2009 CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS PAGE 5.1 SUMMARY DESCRIPTION 5.1-1 5.1.1 Schematic Flow Diagram 5.1-2 5.1.2 Piping and Instrumentation Diagram 5.1-3 5.1.3 Elevation Drawings 5.1 3 5.2...

Diablo Canyon, Units 1 and 2 - Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - "Updated Final Safety Analysis Report Markup," Revision 1. Part 3 of 3.

DCPP UNITS 1 & 2 ESAR UPDATETABLE 15.5-9ALOSS OF ELECTRICAL LOADANALYSIS ASSUMPTIONS & KEY PARAMETER VALUESParameter ValuePower Level 3580 MWtReactor Coolant Mass 446,486 IbmPrimary to Secondary SG tube leakage 0.75 gpm (total for all 4 SGs); leakagedensity 62.4 Ibm/ft3Failed/...

Diablo Canyon, Units 1 and 2 - Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, "Application of Alternative Source Term."

771 Pacitic Gas and[ ~~Electrof CpanlyeEdward D. Halpin Diablo Canyon Power PlantSenior Vice President P.O. Box 56Power Generation and Avila Beach, CA 93424Chief Nuclear Officer805.545.4100El H8@pge.comnDecember 17, 201510 CFR 50.90PG&E Letter DCL-1 5-1 52U.S. Nuclear Regulato...

Columbia Generating Station - Response To Request For Additional Information Related To License Amendment Request To Adopt Emergency Action Level Scheme Pursuant To NEI-99-01 Revision 6 (MF8219).

W.Grover Hettel Columbia Generating Station P.O. Box 968, PE023 Richland, WA 99352-0968 Ph. 509.377.8311 | F. 509.377.4150 wghettel@energy-northwest.com GO2-17-048 10 CFR 50.90 February 23, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control ...

Forwards matls addressing draft SER open items discussed in 850320-22 meetings.

Georgia Power Company/ Project ManagementRout] 2. Box 299AWaynesbor , Georgia 30830Telephone 404 724-8114404 554-9961hMarch 26, 1985Director of Nuclear Reactor RegulationFile: X7BC35Attention: Ms. Elinor G. Adensam, ChiefLog: GN-563Licensing Branch 14Division of LicensingU. S....

"Environmental Qualification of Okonite Tape Splice ( (T-95/No 35) Under Local Submergence for Power & Control Applications," calculation rept.

. .. _ . . . . .- ._ _.-,..o-,bENVIRONMENTAL. QUALIFICATIONf,OF OKONITE TAPE SPLICE(T 95/No. 35) UNDER LOCAL SUBMERGENCEFOR POWER AND CONTROL APPLICATIONS,1COMMGhWEALTII EDISON COMPANYDESIGN SUPPORT ENGINEFRINGI400 OPUS PLACEDOWNERS GROVE, IL 60515,.'I*CALCULATION REPORT NO. 9...

"Licensing Submittal to Support Replacement SG TS Changes for VSNS."

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _________ ______ _________________ _ _______________________________LICENSING SUBMITTAL4)TO SUPPORT REPLACEMENT STEAM GENERATOR|TECHNICAL SPECIFICATION CHANGESFOR THEVIRGIL C. SUMMER NUCLEAR STATIONSECL-93-036|OCTOBER 1993|||Prepared by: Mau...