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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 9 - Chapter 02 - Figure 2.5.2-327

Duke Energy FloridaLevy Nuclear PlantUnits 1 and 2Part 2, Final Safety Analysis ReportFIGURE 2.5.2-327 Rev 6Comparison of Hazard Computed in thisStudy to Results in NUREG-2115 for theHouston Demonstration SiteLNP COL 2.5-21.E-071.E-061.E-051.E-041.E-031.E-021 1 . 0 1 0 . 0Ann...

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 8 - Chapter 02 - Figure 2.5.2-329

Duke Energy FloridaLevy Nuclear PlantUnits 1 and 2Part 2, Final Safety Analysis ReportFIGURE 2.5.2-329 Rev 6Comparison of Hazard Computed in thisStudy to Results in NUREG-2115 for theManchester Demonstration SiteLNP COL 2.5-21.E-071.E-061.E-051.E-041.E-031.E-020 1 1 1 . 0Annu...

NuScale Power, LLC Response to NRC Request for Additional Information No. 258 (eRAI No. 9153) on the NuScale Design Certification Application.

RAIO-1217-57604NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comDocket No. 52-048 December 12, 2017U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North11555 Rock...

Benefit Cost Analysis of Enhancing Combustible Gas Control Availability at Ice Condenser and Mar III Containment Plans.

Benefit Cost Analysis of Enhancing Combustible Gas Control Availability at Ice Condenser and Mark III Containment Plants Draft Letter Report John R. Lehner Vinod Mubayi W. Trevor Pratt Cheryl Conrad Energy Sciences and Technology Department Brookhaven National Laboratory Upton...

Enclosure 4 February 25, 2015 Meeting with the Westinghouse Advanced Passive 1000 Owners Group (APOG)

May 11, 2016 Enclosure 4 APOG Comment Disposition FEBRUARY 25, 2015 MEETING WITH THE WESTINGHOUSE ADVANCED PASSIVE 1000 OWNERS GROUP (APOG) Docket ID NRC-2014-0147: AP1000 Utility Comments on GTST Rev. 0 Final Revision, December 2, 2015 Page 1 of 332 Administrative Types: ...

Fermi, Unit 3 - SER - Chapter 13 - Conduct of Operations.

13-1 13.0 CONDUCT OF OPERATIONS This chapter provides information relating to the preparations and plans for the design, construction, and operation of a nuclear plant. The purpose of this chapter is to provide reasonable assurance that the combined license (COL) applicant ...

SHINE Revised Draft Request for Additional Information Regarding Application for Construction Permit.

SHINE Medical Technologies, Inc. Preliminary Safety Analysis Report (PSAR) Requests for Additional Information General Information Request RAI G-1 10 CFR 50.34(a)(8) states that “an identification of those structures, systems, or components of the facility, if any, which req...

Attachment 6, NEI Draft Comments on NRC Identified Items.

Attachment 6 of Enclosure 2 NEI Draft Comments on NRC Identified Items Meeting Summary of the NRC and Stakeholders Concerning NUREG-1022, Revision 2 Dated June 28, 2010 Draft Industry Comments re – NRC IDENTIFIED ITEMS IN NUREG-1022, REVISION 2 Dated June 8, 2010 P...

"Conformance to Reg Guide 1.97,San Onofre Nuclear Generating Station,Unit 1."

_ _ _ _ _ _ _*o .EGG-NTA-7187..CONFORMANCE TO REGULATORY GUIDE 1.97SAN ON0FRE NUCLEAR GENERATING STATION, UNIT NO.1J. W. StoffelPublished July 1986EG&G Idaho, Inc.Idaho Falls, Idaho 83415.f,Prepared for theU.S. Nuclear Regulatory ComissionWashington, D.C. 20555Under DOE Contra...

Responds to request for addl info on uninterruptible power supply issues in 910910 ltr.

~I~'tcph F. FirlitIce I residenttucieer Generation> NIAGARAU lHOHAWKNINE MILE IVINT MUCLCAI STATION/I'.Q. 60X 32 LYCOMINQ,NBV YORK 13003/Tsl EPHONE I315I 343 2110NMP8 1983September 11, 1991Mr, Steven A, VargaDirector, Division of Reactor Projects-I,IIU. S. Nuclear Regulatory C...

"Comparative Studies of LMFBR Sys Codes:Part 2:FFTF Upper Plenum Mixing & Stratificaiton".Informal rept.Calculations were compared w/test data & results agree well.

}, ; /4 INTERIN REPORToAccession Mo.Contract Program or Project Title:SSC Code ValidationSubject of this Document:Comparative Studies of LMF8R System Codes:,.Part 2: FFTF Upper Plenum Mixing and Stratification .).Type of Document: Informal Report|[!!Author (s):J. W. Yang#Engin...

Forwards listed SSER 4 inputs for transmittal to Board.Memo from Eisenhut to Sheppard re review of Westinghouse response guidelines & inputs on CRDR & SPDS also encl.

s/.),APR 2 5 G6 A,MEMORANDUM FOR: Edward S. ChristenburyDirector & Chief CounselPearing Divison, OEl.DFROM: Thomas M. Novak, Acting DirectorDivision of PWR licensing-ASUBJECT: ASI.B MATTERS PERTAINING TO SEABROOK UNIT 1Attached for your transmittal to the Board are the followi...

Safety evaluation re util 860603 submittal of justification for continuous purging/venting of containment during routine operations.Continuous ventilation acceptable.

/[ .'oUNITED STATESgNUCLEAR REGULATORY COMMISSION e oh.WASHINGTON. D. C. 20555.%*.***$SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONCONCERNING PURGING AND VENTING DURING NORMAL OPERATIONS-DAIRYLAND POWER COOPERATIVELACROSSE BOILING WATER REACTORDOCKET NO. 50-409...

Application for withholding proprietary summary rept "Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling." Affidavit,response to 810710 confirmatory order & nonproprietary summary rept encl.

0Westinghouse Electric CorporationWater Reactor DivisionsNuclear Technology Division Box 355 Pittsburgh Pennsylvania 15230 July 21, 1981 CAW-81-43 Docket 50-247 DPR-26Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Phillips Building ...

"Protective Action Recommendations Based on Plant Conditions."

_ . _ . . _ _ _ . . ._ ~_ _ . -. ..:-.... VIONcutx*^r >'xur ErcI - 94-04 Rev. oEMERGENCY PREPAREDNESSlg{DEPARTMENTCALCULATION COVER SHEETCallaway PlantSUBJECT:Protective Ac' tion Recommendations Based on Plant Conditions.PURPOSE AND SCOPE:Using plant conditions as a bases, thi...

San Onofre, SO-2008-09-Final Operating Test

Appendix C JPM WORKSHEET Form ES-C-1 NUREG 1021, Revision 9.1 Page 1 of 212 ML082750289.doc Facility: SONGS JPM # 2008 NRC RO A-1a Task # 141283 K/A # G 2.1.23 4.3 / 4.4 Title: Perform Boric Acid Makeup Tank Inventory Determination Examinee (Print): Testing Method: Sim...

2018/03/10 NuScale SMR DC RAI - Request for Additional Information No. 382 eRAI No. 9402 (Ch. 18)

1NuScaleDCRaisPEm ResourceFrom: Chowdhury, ProsantaSent: Saturday, March 10, 2018 7:44 PMTo: Request for Additional InformationCc: Lee, Samuel; Cranston, Gregory; Murray, Demetrius; Rivera-Varona, Aida; Scheetz, Maurin; NuScaleDCRaisPEm ResourceSubject: Request for Additional ...

Request for Additional Information Walsh Construction - Indiana to License No. 13-35270-01.

Tran, Frank From: Sent: To: Subject: Dear Mr. Raymond: Tran, Frank Thursday, September 24, 2015 10:55 AM 'fraymond@wa lshg rou p.com' Request for additional information re Walsh Construction - Indiana We have reviewed your application. It appears that your application was prep...

Responds to ltr sent to K Hutchison re "Eternal Storage Vault" for storage of spent nuclear fuel.Forwards matl that may be used to generate & submit application to NRC for review & approval.

. - . _ _ . _ _ _ _ . _ _ _ . _ _ _ . _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ . . . _ _.,p~m,p UNITED STATES%= gNUCLEAR REGULATORY COMMISSICh*WASHINGTON, D.C. segeHootJ*****-1%December 8,1998{Mr. Robert W. ButlerP. O. Box 36Dublin, Texas 76446..Dear Mr. Butler.1T...

Response to February 13, 1992 letter which requested U.S. Nuclear Regulatory Commission (NRC) information to support the establishment of a public reading room in Caliente, including an NRC contact who could support a speaker's bureau.

-3- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 0Ms. Judy Foremaster IPR 3 1992Project CoordinatorCity of Caliente NuclearWaste ProjectPost Office Box 158Caliente, Nevada 89008Dear Ms. Foremaster:I am writing in response to your February 13, 1992 letter which requestedU.S. Nuclear Regulatory Co...

E-mail from A. Bjornsen, FSME to P. Bubar, FSME, et al; Subject: FW: ?? Status of the MOU with NRC.

Remsburg,,KristyFrom: Olmstead, JoanSent: Tuesday, January 19, 2010 10:43 AMTo: Bjornsen, Alan 1Subject: RE: Invitation: Teleconference with NRC Project Managers of NUREG 1910-Supplements(Lost Creek, Moore Ranch, Nichols Ranch ISR EIS) (Jan 22 08:00 AM MST)Per voice mail messa...

Memorandum from William G. Snell, Senior Radiation Specialist, NRC to Gary L. Shear, Chief, Fuel Facilities Section, NRC, RE: Review of Final Survey Plan for ABB Combustion Engineering.

I#rctQ4_1RSeptember 28, 1995MEMORANDUM TO:THRU:FROM:SUBJECT:Gary L. Shear, Chief, Fuel Facilities SectionJ. W. McCormick-Barger, Chief, Decommissioning SectionWilliam G. Snell, Senior Radiation SpecialistREVIEW OF FINAL SURVEY PLAN FOR ABB COMBUSTION ENGINEERINGPer your reques...

Reply brief re certified questions on definition & implementation of "medical svcs." Emergency provisions for general public not medically required during Class 9 accidents.Certificate of Svc encl.

e6 00tKETE0 .USNRCUNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION 82 00129 Ali:i6c py. . _ _ _ _ _ , -In the Matter of )~')SOUTHERN CALIFORNIA EDISON )DOCKET NOS. 50-361 OLCOMPANY, et al.)50-362 OL)(San Onofre Nuclear Generating)Station, Units 2 and 3)))APPLICANTS' REPLY...

Loca-Hybrid-Final.

Uncertainty modeling of LOCA frequenciesand break size distributions for the STPGSI-191 resolutionElmira Popova, David MortonThe University of Texas at AustinMay 20121 IntroductionIn the initial quanti cation (Crenshaw, 2012), Fleming et al. (2011) per-formed a substantial stu...

Response to Technical Assistance Request, dated March 24, 2014, for the Review of DCGL Values for the Pfizer, Inc. Cyclotron Facility in Groton CT.

July 10, 2014 MEMORANDUM TO: James Clifford, Director Division of Nuclear Materials Safety Region I FROM: Gregory Suber, Deputy Director (Acting) /RA/ Environmental Protection and Performance Assessment Directorate Division of Waste Management and Environmenta...