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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 1, Introduction And General Description Of Plant, Section 1.2.

WSES-FSAR-UNIT-3 1.2-1 Revision 14 (12/05) 1.2 GENERAL PLANT DESCRIPTION1.2.1 PRINCIPAL SITE CHARACTERISTICS1.2.1.1 Location and PopulationThe Waterford 3 site is located on the west (right descending) bank of the Mississippi River near Taft, Louisiana in the northwest p...

Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features, Section 6.3.

WSES-FSAR-UNIT-36.3-1 Revision 10 (10/99)6.3 EMERGENCY CORE COOLING SYSTEM6.3.1 DESIGN BASISThe Emergency Core Cooling System (ECCS) or Safety Injection System (SIS) is designed to providecore cooling in the unlikely event of a loss of coolant accident (LOCA). The cooling mus...

Diablo Canyon Power Plant, Technical Assessment Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4.

ATTACHMENT 1 Diablo Canyon Power Plant Technical Assessment Enclosure Attachment 1 PG&E Letter DCL-16-101 Prepared by WECTEC Global Project Services Inc. (WECTEC) Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4 \ '·· WE CT EC TECHNICA...

Proposed Tech Specs documenting mods made to comply w/ 10CFR50.62 ATWS rule.

W Attachment 2 NG-87-0468 PROPOSED CHANGE RTS-216 TO THE DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS The holders of license DPR-49 for the.Duane Arnold Energy Center propose to amend Appendix A (Technical Specifications) to said license by deleting current pages and re...

McGuire, Units 1 and 2 - Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049).

Steven D. Capps£r1I1 L' Vice President' DUKE McGuire Nuclear StationENERGY. Duke EnergyMG01VP 112700 Hagers Ferry RoadHuntersville, NC 28078o: 980.875.4805f: 980.875.4809Steven.Capps@duke-energy.com10 CFR 50.4February 26, 2015Serial: MNS-15-005ATTN: Document Control DeskU.S. ...

NUREG/CR-3610, "Neutron Dosimetry at Commercial Nuclear Plants, Final Report of Subtask C: 3He Neutron Spectrometer."

Neutrc)n Dosimetry atComrrlercial Nuclear PlantsFinal Report of Subtask C: 3He Neutron SpectrometerManuscript Completed: July 1984Date Published: SElptember 1984Prepared byL. W. Brackenbush, W. D. Reece, J. E. TannerPacific Northwest LaboratoryRichland, WA 993!52Prepared forDi...

V.C. Summer, Units 2 and 3 - Reporting of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Section VII Departures.

A SCANA COMPANY April Rice Manager New Nuclear Licensing July 30, 2015 NND-15-0472 10 CFR 50.59 10 CFR 52 App D u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3 Docket Numbers 52-027 and ...

Three Mile Island, Unit 1 - Draft - Outlines (Folder 2).

Exelon Gene rat ion Three Mile Island Unit 1 Telephone 717-948-8000 Route 441 South, P.O. Box 480 Middletown, PA 17057 June 30, 2015 TMl-15-075 USNRC, Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 SUBJECT: THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (T...

020_06 ENGINEERED SAFEGUARDS

TMI-1 UFSARCHAPTER 06 6-i REV. 23, APRIL 2016CHAPTER 6 – ENGINEERED SAFEGUARDSTABLE OF CONTENTSSECTION TITLE6.0 ENGINEERED SAFEGUARDS6.1 EMERGENCY CORE COOLING SYSTEM6.1.1 DESIGN BASES6.1.2 SYSTEM DESIGN6.1.2.1 ECCS OPERATION6.1.2.2 CODES AND STANDARDS6.1.2.3 MATERIAL COMPATIB...

Hope Creek Generating Station & Salem Nuclear Generating Station, Units 1 & 2 - Transmittal of 2015 Annual Radioactive Effluent Release Report.

' i PSEG Nuclear LLC) P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 @PSEG Nuclear LLC Technical Specification Section 6.9.1.8 (Salem) Technical Specification Section 6.9.1. 7 (Hope Creek) LR-N16-0053 APR ·28 2016 United State.s Nuclear Regulatory Commission Attn: Docume...

Forwards util responses to BNL comments on sys analysis review of long-term seismic program probabilistic risk analysis.

11LE RATED.DI~I3UTJ0;'EMO.'iS~OYSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8906190066 DOC.DATE: 89/06/12 NOTARIZED: NOFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1,Pacific Ga50-323 Diablo Canyon Nuclear Power Plant, Unit 2,Pacific GaAUTH.NAME...

Tran-M811026: Commission Discussion with Electric Power Research Institute Representatives on Fission Product Behavior (Public Meeting).

\ ... SECRITAR1AT R£CORD8:Y:).A Rl:Gm1'0RY COMMJ:SSION COMMISSION MEETING -- -I: ~ Ma.t::m: of: COMMISSION DISCUSSION· WITH ELECTRIC POWER RESEARCH INSTITUTE REPRESENTATIVES ON FISSION PRODUCT BEHAVIOR ~: October 26, 1981 PAGZS': ____ 1_---6~8 ____ __ ~: Washington, D.C. '00 ~...

Monthly operating rept for May 1983.W/830613 ltr.

.*NZAGARA MOHAWK POWER CORPORATIONNINE MILE POINT NUCLEAR STATION UNIT #1NARRATIVE OF OPERATING EXPERIENCEMay 1983The Station operated during the month of May, 1983, with a monthlyavailability factor of 0.0% and a net design electrical capacity factorof 0.0%.The Station was sh...

Proposed tech specs technical revs agreed upon in 940405-06 meeting.

. . -- ....a>>.,t4:. ,.. ..fATTACHMENT 3.L- D #/4/-d21-[,,!.1,%4.. )e'9404290298 940414PDR- ADOCK 05200002A-PDR _. . _ . , _ _. .. - - _ . , , . . . . . - ,4TABLE OF CONTENTSCHAPTER 16Section Subiect Page1.0 USE AND API-LICATIONS 1.1-11.1 Definitions 1.1-11.2 Logical Connector...

"Electrical Penetration Protection Control Circuits (Primary & Secondary)."

,!!'-.,.:i|ELECTRICALPENETRATION PROTECTIONi| INSTRUMENTCIRCUITSi'$ 1is!%! t|$NORTH ANNA POWER STATION - UNIT 2!|VIRGINIA ELECTRIC AND POWER COMPANY!!'I ki|STONE & WEBSTER ENGINEERING CORPORATION'BOSTON, MASSACHUSETTS| 1R.ViSauN Nu. *9/.?4/80:__ _ _ _ _ _ _ _ _ _ __ - --. . _ ...

Affidavit of G Klopp re Contention 4.Intervenor interpretation of single failure demonstrates misunderstanding of NRC requirement on accident analysis.

. - -.3['%\)UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION!BEFORE TIIE ATOMIC SAFETY AND LICENSING BOARDIn The Matter of )))COMMONNEALTH EDISON COMPANY )Docket Nos. 50-454 OL)50-455 OL)(Byron Nuclear Power Station, )Units 1 & 2) ).AFFIDAVIT OF GEORGE KLOPPThe attached q...

Forwards util assessment of ability to withstand & recover from station blackout per 10CFR50.63.

. -. . - . _ . --,i,. -|- . . e;,-.!-;1"" ""|| -Log # TXX 901008:": C-File # 10010 (c1o)|'C C908.3Ref. # 10CFR50.637t#ELEG7RlC,,[3$'f,'d,'$'j|,;, November 5, 1990| ,:IU. S. Nuclear Regulatory Commission.Attn Document Control leski*Washington, DC 20555i!iSUBJECT: COMANCHE PEAK ...

FSER Chapter 8 - Electric Power

8-1 8 ELECTRIC POWER This chapter of the final safety evaluation report (FSER) documents the U.S. Nuclear Regulatory Commission (NRC) staff’s (hereinafter referred to as the staff) review of Chapter 8, “Electric Power,” of the NuScale Power, LLC (hereinafter referred to as th...

Advises that no open item repts issued since Jan semimonthly rept.

_sSTONE 6 WEBSTER ENGINEERING CORPORATIONiI245 SUMMER STREET. BOSTON. M ASSACHUSETTSADDRESS ALL CORRE SPONDENCE TO P.O. BOX 2325, BOSTON. e4 A 9 9. 02107w U. TELEX 944000w Canc m s va uCT'Omo amz es tions* E*.',*O* '.*ORI'c'.* ..cPO4?L a mD,. Da s GONwa SMeme 0N. O C.Mr. C.A. ...

Forwards complete structural checklist of audit conducted on 800317-21,per Structural Engineering Branch request.

MISSISSIPPI POWEP % LIGHT COMPANY-Helping Bull . dis sis sippiu" " " -P. O. B O X 164 0, J A C K S O N, MIS SIS SIP PI 3 9 2 0 5July 31, 1981fhi'%NUCLE AR PAoouCTfoN DEFARTMENT(g

Indian Point Unit 3, Revision 8 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System.

IP3 FSAR UPDATE Chapter 4, Page 1 of 109 Revision 08, 2019 CHAPTER 4 REACTOR COOLANT SYSTEM 4.1 DESIGN BASIS The Reactor Coolant System, shown in Plant Drawings 9321-F-27338 and -27473 [Formerly Figure 4.2-2A & -2B], consists of four similar heat transfer loops connected i...

Point Beach Nuclear Plant, Units 1 & 2 - 2018 Update to Final Safety Analysis Report, Chapter 4, Reactor Coolant System

Chapter 4 Table of ContentsFSAR UFSAR 1999 Page TOC - 4-i of i CHAPTER 4 TABLE OF CONTENTS4.1 DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -4.1-14.2 RCS SYSTEM DESIGN AND OPERATION - - -...

Responds to request for addl info re IE Bulletin 79-08. Supporting documentation encl.

o[f&* *PHILADELPHIA ELECTRIC COMPANY2301 M ARKET STREETP.O. BOX 8699PHILADELPHI A. PA.19101SHIELDS L. DALTROFF'stacra ceno e ionAugust 8, 1979Re: Docket Nos.: 50-27750-278IE Bulletin 79-08Additional InformationMr. Boyce H. Grier, DirectorOffice of Inspection & EnforcementRegio...

Forwards addl certified design descriptions & ITAAC for Sys 80+.

_ _ _ _ - _ _ _ _ _ _ _ _ .ABBASE A BROWN BOVE RIFebruary 1, 1993LD-93-014Docket 52-002Attention: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555SUBJECT: SYSTEM 80+ Draft ITAU1 SubmittalREFERENCE ABB-CE Letter LD-93-012, C. B.Brinkman (ABB-CE) toNR...

Submits response to NRC Bulletin 96-003, "Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in BWRs."

!. .N,tEMEmonI|WENERGYPERRY NUCLEAR POWER PLANTMail Address:19 CENTER ROAD.OWO M 81|PERRY, OHIO 44081| ('116) 259 4737|'November 4,1996PY-CEI/NRR-2111LUnited States Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555Perry Nuclear Power PlantDocket No. 50-440...