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NRC-2019-000191 - Resp 1 - Final, Agency Records Subject to the Request are Enclosed.

( Document Number Document Title Document Date Received Date Senator Markey, Senate Comrmttee on Environment and Public Works, E-mail re: Questions for the Record for L TR-18-0044 December 13, 2017, hearing entitled Oversight of the Nuclear Regulatory Commission 02/05/2018 02/...

Comment (19) of Mary Lampert on behalf of Pilgrim Watch on Draft Interim Staff Guidance Emergency Planning Exemption Request for Decommissioning Nuclear Power Plants.

Mendiola, DorisSubject: FW: Comment NRC-2014-0002 DRAFT INTERIM STAFF GUIDANCE EMERGENCYPLANNING EXEMPTION REQUESTS FOR DECOMMISSIONING NPSAttachments: 04.10.14 NRC 2014 0002 [ISG EP EXEMPTIONS DECOM NPS].pdfFrom: Mary Lampert [mailto:mary.Iampert(ý)comcast.net] I / //6'j:Sent...

Safety Analysis Report for the West Valley Melter Package, SARWVMP-01, Revision 1, Part 7 of 11.

7 ANALYSIS RESULTSDue to the temperature limits on the spent fuel cladding, closure seals, impact limiter core materials, andneutron shield core materials, these components are the most important elements to consider in evaluatingthe response of the transport systems to the fi...

Part 03 Environmental Report (Rev. 0) - Part 3 - ER - Chapter 3 - Plant Description - Sections 3.1 3.6

Clinch River Nuclear Site Early Site Permit Application Part 3, Environmental Report 3.0-1 Revision 0 CHAPTER 3 PLANT DESCRIPTION Chapter 3 describes the new plant design based on the plant parameter envelope (PPE) and provides general information about the new plant on the ...

Minutes of the Advisory Committee on Reactor Safeguards Regulatory Policies and Practices Subcommittee - March 4, 2015.

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 May 29, 2015 MEMORANDUM TO: ACRS Members FROM: Peter Wen, Senior Staff Engineer /RA/ Technical Support Branch Advisory Committee on Reactor Safeguards SUBJECT: CER...

TS Proposed Change 207 to license DPR-28,increasing spent fuel storage capacity of util spent fuel pool from 2,870 to 3,355 fuel assemblies.Non-proprietary & proprietary rept encl.Proprietary rept withheld (ref 10CFR2.790(a)(4)).

_-fk;VERMONT YANKEE~,- .-ENUCLEAR POWER CORPORATION'-s-185 Old Ferry Road, Brattleboro, VT 05301-7002'i-*; (802) 257-5271.|_|I>Eh"September 4,1998h'?]BVY 98-130p]U. S. Nuclear Regulatory Commission!,r.iAttention: Document Control Desk| jE Washington, DC 20555/:0bSubject:Vermon...

Periodic Assessment of the Activities of the Committee to Review Generic Requirements - Memo to the Commission fr Travers - signed 9/01/00

September 1, 2000MEMORANDUM TO: Chairman MeserveCommissioner DicusCommissioner DiazCommissioner McGaffiganCommissioner MerrifieldFROM: William D. Travers /RA/Executive Director for OperationsSUBJECT: PERIODIC ASSESSMENT OF THE ACTIVITIES OF THECOMMITTEE TO REVIEW GENERIC REQUI...

Chapter 15 Accident Analysis

15-115 ACCIDENT ANALYSIS15.1 Conduct of ReviewThe staff evaluated the applicant’s accident analysis by reviewing Chapter 8, Accident Analysis,of the SAR, documents cited in the SAR, and other relevant publicly available information,including web sites on the internet.Section 8...

1997-98 University of Florida Training Reactor Annual Progress Report

UNIVERSITY OF FLORIDANuclear Reactor Facility Department of Nuclear and Radiological Engineering202 Nuclear Sciences Center P.O. Box 118300 Gainesville, Florida 32611-8300 Tel: (352) 392-1429 Fax: (352) 392-3380 E-mail: vernet@serverl.nuceng.ufl.eduFebruary 5, 2001 ATTN: Docum...

REQUEST FOR ADDITIONAL INFORMATION (TAC NO. L22462)

April 1, 1998Mr. John D. Parkyn, Chairm. Private Fuel Storage, L.L.C. P.O. Box C4010 La Crosse, WI 54602-4010SUBJECT: REQUEST FOR ADDITIONAL INFORMATION (TAC NO. L22462)Dear Mr. Parkyn: The staff of the Nuclear Regulatory Commission (NRC) has completed its request for additi...

Private Fuel Storage Facility - Calculation Package - 07/20/2001 Submittal.

Private Fuel Storage, L.L.C 7677 East Berry Ave., Englewood, CO 80111-2137 Phone 303-741-7009 Fax: 303-741-7806 John L. Donnell, P.E., Project Director U.S. Nuclear Regulatory Commission July 27, 2001 ATTN: Document Control Desk Washington, D.C. 20555-0001 CALCULATION PACKAGE ...

A Letter to J Edwards from A Vietti-Cook; In the Matter of Carolina Power & Light Company (Shearon Harris Nuclear Power Plant).

UNITED STATES * ** NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 16, 2000 //CI //S SECRETARY The Honorable John Edwards United States Senate Washington, DC 20010 Dear Senator Edwards: I am responding to your letter dated May 5, 2000, addressed to Chairman Richa...

Forwards response to 930608 request for addl info re proposed TS Change Request 202,submitted via util 921102 ltr.Encl addresses NRC concerns re seismic analyses performed to rerack spent fuel pool.

. - , , , . + - .- . . . . - _ - ._ . - - .6 ...'Beaver Valley Power StationShippmgpor1. PA 15077-0004 .(412) 393-5206(412) 643-8069 FAXGEOnGE S. THOMASDivision Vice President-'Nuclear ServicesNuclear Power DivisionJuly 9, 1993.U. S. Nucler 11atory Commission ,Attn: Document C...

3-30-20 Petition for Review (9th Cir.)(Case No. 20-70899)

Molly C. Dwyer Clerk of Court Office of the Clerk United States Court of Appeals for the Ninth Circuit Post Office Box 193939 San Francisco, California 94119-3939 415-355-8000 March 30, 2020 No.: 20-70899 Short Title: Public Watchdogs v. USNRC Dear Petitioner/Counse...

Trojan Site-Specific Independent Spent Fuel Storage Installation (ISFSI} License Change Application (LCA) 72-08, Potential Explosion Effects on ISFSI.

Portland General Electric Company Trojan JSFSI 71760 Columbia River Hwy Rainier, Oregon 97048 ATIN: Document Control Desk Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ...

QA Nonconformance Report 1999-02 (Several geophysical software codes were developed without a software requirements description, software development plan, and documented acceptance testing).

%i CENTER FOR h UCLEAR WASTE REGULA'I'ORY ANALYSES ,\-v> NONCONFORMANCE REPORT $? q// L roject No. 20-1402-461, -471. -861 NCRNO. 99-02 PART 1: DESCRIPTION OF NONCONFORMANCE Contrary to the requirements in TOP-018, Development and Control of Scientific and Engineering Software...

Diablo Canyon, Units 1 & 2, Issuance of License Amendment Nos. 162 and 163, Respectively, Authorizing Changes to the Final Safety Analysis Report Update, Together With Other Analyses, Design and Procedure Changes to Implement the NUREG-0612.

September 26, 2003Mr. Gregory M. Rueger Senior Vice President, Generation and Chief Nuclear OfficerPacific Gas and Electric CompanyDiablo Canyon Nuclear Power PlantP.O. Box 3Avila Beach, CA 93424SUBJECT: DIABLO CANYON NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF LICE...

NUREG-0936 Vol. 21, No. 1"NRC Regulatory Agenda," Semiannual Report January - June 2002.

NUREG - 0936 Vol. 21, No. 1NRC Regulatory Agenda Semiannual Report January - June 2002 U.S. Nuclear Regulatory Commission Office of Administration Washington, DC 20555-0001AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONSNRC Reference Material As of November 1999, you ma...

07/10/1997 Summary of Meeting with NAC International Re Actions Taken to Resolve Issues with Confirmatory Action Letter No. NMSS 96-01.

UNITED STATES o NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055-1001 July 28, 1997 7" I MEMORANDUM TO: William F. Kane, Director Spent Fuel Project Office, NMSS FROM: Timothy J. McGinty, Project Man aer 4 Spent Fuel Licensing Section (--ao/'-7 Spent Fuel Project Office, NM...

Trojan Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report 07200017/2020001

October 27, 2020 Mr. Bradley Y. Jenkins Vice President, Utility Operations Portland General Electric Company 121 SW Salmon Street Portland, OR 97204 SUBJECT: TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) - NRC INSPECTION REPORT 07200017/2020001 Dear Mr...

Mpc24-20.des - Description file for 20 meter case input file (7 hour fire).

0,mpc24-20.des 01/27/2003!1 mpc24.desDesign paramters and boundary condition dataI for the HOLTEC HISTAR 100 MPC-24I Required macros and files:I mpc24.inp - main input deck (calls this file)I boral.mac - boral gap radiation/conduction macroI fuel.mac - fuel conductivity macro!...

SECY-02-0026 - "Weekly Information Report - Week Ending 02/01/02"

February 7, 2002 SECY-02-0026For: The CommissionersFrom: John W. Craig, Assistant for Operations, Office of the EDOSubject: SECY-02-0026 WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 1, 2002Contents EnclosureNuclear Reactor Regulation ANuclear Material Safety...

10/27/05 - Ltr from Robert R. Loux, Executive Director, State of Nevada, to Allen Hansen, Federal Register Notice of Availability, Documents Regarding Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario.

a;,KENNY C. GUINN STATE OF NEVADA ROBERT R. LOUXGovernor Executive DirectorOFFICE OF THE GOVERNORAGENCY FOR NUCLEAR PROJECTS1761 E. College Parkway, Suite 118Carson City, Nevada 89706Telephone: (775) 687-3744 * Fax: (775) 687-5277E-mail: nwpo@nuc.state.nv.usOctober 27, 2005All...

E-mail from T. Jones of Entergy to J. White of USNRC, Regarding Submittal to NRC.

John Wte - F-: Submittal to NRCFrom: IIJo02To: /06 4:40PMSubmittal to NRCFrom: Hinrichs, Gary HSent: Friday, April 28, 2006 4:25 PMTo: Jones, T. R.Subject: Submittal to NRCAs per our Tuesday Conference call we promised ...

Appendix C - Fuel Response to Loads, C-2 though C-23.

APPENDIX C: Fuel Response to LoadsC-2This page is intentionally blankC-3Appendix CFuel Response to LoadsC.1 Fuel Response to Mechanical LoadsC.1.1 Fuel Rod BucklingFor cask vertical drop accidents, the fuel rods in the assemblies are analyzed as long slender columns withinterm...