Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Cover Letter on Issuance of Exemption and License Amendment No. 23 for Vogtle Units 3 and 4.

August 25, 2014 Mr. B. L. Ivey, Vice President Regulatory Affairs Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway, B022 Birmingham, AL 35242 SUBJECT: VOGTLE ELECTRIC GENERATING PLANT UNITS 3 AND 4 ─ ISSUANCE OF AMENDMENT AND GRANTING OF EXEMPTION RE:...

Authorizes utilization of encl affidavit supporting request to withhold info re steam generator repair from public disclosure,per 10CFR2.790.

_''#:: ,(Westinghouse Water ReactoranassElectric Corporation DivisionsPittsburghPemsylvalla15230April 27, 1983CAW-83-35Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionPhillips Building7920 Norfolk AvenueBethesda, MD 20014Refe...

Affidavit of EM Burns on Contention 9c re flow induced vibration & tube wear in preheater section of Westinghouse Model D steam generators.

,_ _ __ _ . .,or,00qxErEnUNITED STATES OF AMERICA ms -,.NUCLEAR REGULATORY COMMIS$10N''BEFORE THE ATOMIC SAFETY AND LICENSING BOARDIn The Matter of)))'00lHONWEALTH EDISON COMPANY) Docket Nos. 50-454 OL) 50-455 OL(Byron Nuclear Power Station,Units 1 & 2)AFFIDAVIT OF EDWARD M. B...

04/25/2012 Notice of Meeting with SNC To Discuss Issues Related To Licensing Actions for Vogtle Units 3 and 4.

March 23, 2012 MEMORANDUM TO: Mark Tonacci, Chief Licensing Branch 4 Division of New Reactor Licensing Office of New Reactors FROM: Ravindra Joshi, Senior Project Manager /RA Denise McGovern for/ Licensing Branch 4 Division of New Reactor Licensing Office of New...

Vogtle, Units 3 and 4 - Supplement to Request for License Amendment: Core Reference Report Incorporation (LAR-16-001S2).

Southern Nuclear Operating Company, Inc. 42 Inverness Center Parkway Birmingham, AL 35242 June 29, 2016 Docket Nos.: 52-025 ND-16-1017 52-026 10 CFR 50.90 10 CFR 52.98 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern...

Forwards proprietary & nonproprietary versions of "RCS Flow Uncertainties W/Use of Rosemount Resistance Temp Devices," Westinghouse affidavit & authorization ltr & proposed mods to Unit 1 Tech Specs.

TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 374011400 Chestnut Street Tower IIAugust 30, 198)4Director of Nuclear Reactor RegulationAttention: Ms. E. Adensam, ChiefLicensing Branch No. 14Division of LicensingU.S. Nuclear Regulatory CommissionWashington, D.C. 20555Dear Ms....

Notifies of completion of design-basis capability verification of safety-related MOVs,in accordance w/ reporting requirements of GL 89-10,Suppl 6 & GL 89-10.

IWIORITY 1 * (ACCELERATED RIDS PROCESSING) REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9506190460 DOC.DATE: 95/06/13 NOTARIZED: NO DOCKET # FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 05000305 AUTH.NAME AUTHOR AFFILIATION STEINHARDT,C....

Nuclear Regulatory Commission Approval Letter For BWRVIP-44-A, "BWR Vessel And Internals Project, Underwater Weld Repair Of Nickel Alloy Reactor Vessel Internals."

October 16, 2007 Rick Libra, BWRVIP Chairman DTE Energy Fermi Nuclear Plant (M/S 280 OBA) 6400 N. Dixie Highway Newport, MI 48166-9726 SUBJECT: NUCLEAR REGULATORY COMMISSION APPROVAL LETTER FOR BWRVIP-44-A, “BWR VESSEL AND INTERNALS PROJECT, UNDERWATER WELD REPAIR OF ...

05/25/10 Notice of Meeting with Southern Nuclear Operating to Discuss Open Items and Outstanding Requests for Additional Information Responses Related to Southern Nuclear Operating Company's Combined License Application.

*Commissioner’s Policy Statement on “Enhancing Public Participation in NRC Meetings” (67 FR 36920), May 28, 2002. May 11, 2010 MEMORANDUM TO: Jeffrey Cruz, Branch Chief AP1000 Projects Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Ravin...

338884-TMEM-129 Rev. 2, Evaluation and Management of Materials Dredged from the Cross Florida Barge Canal for the Construction of Barge Slip, Intake Structure, and Pipeline Facilities Associated with the Levy Nuclear Plant, Florida.

Form No.: 338884-FM-TM-001, Rev 0 338884-TMEM-129, REV 2 CH2M HILL NUCLEAR BUSINESS GROUP CONTROLLED DOCUMENT PAGE 1 OF 28 Tech Memo Approval Form Tech Memo Number: 338884-TMEM-129 Revision: 2 Project: 338884 Review Date: 09/07/2011 Tech Memo Title: Evaluation and Managemen...

Proposed Tech Specs adding Centerior Svc Co as nuclear power plant licensee.

_ . _ _ __ _ _ .____ _ _ _-___ _ _ _ _ __ _ _ __ _ _ _ _ _ _ _|Attechment 2 ;..*PY-CEI/NRR I189 L,**Page 3 of 8,i 6.0 ADMINISTRATIVE CONTROLS6.1 RESPONSIBILITY6.1.1 The General Manager, Perry Plant Operations Department, shall beresponsible for oversal unit operation and shall...

"Pacific Gas & Electric Co,Humboldt Bay Power Plant,Unit 3 SAFSTOR QA plan."

_ _ - _ _ - _ _ _ _ _ _ _ _ _ .~~, . ,.'<. ....".ePACIFIC GAS AND ELECTRIC COMPANYHUMBOLDT BAY POWER PLANTUNIT 3 SAFSTOR-QUALITY ASSURANCE PLAN-.,1992S/0057KRevision 4April 1988'8804260234 880421PDR ADOCK 05000133PDCD_ - - - - _ - - - _ - _ _ ,-gI.'..,- -,,HUMBOLDT BAY POWER P...

Proposed Tech Spec change to allow plant operation w/o forced recirculation flow.

-,,ATTACHMENT 1MIC DOCKET 50-321OPERATING LICENSE DPR-57EDWIN I. HATCH NUCLEAR PLANT UNIT 1. REQUEST FOR TECHNICAL SPECIFICATION CHANGEALLOWING PLANT OPERATION WITHOUT FORCED RECIRCULATIONThe proposed changes to Technical Specifications (Appendix A to OpoeratingLicense DPR-57)...

Issuance of Amendment for the James A. FitzPatrick Nuclear Power Plant (TAC No. M88458).

4- . 0 0UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 16, 1994Docket No. 50-333 Mr. William A. Josiger, Acting Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601 Dea...

Rev 0 to "Design Baseline & Verification Program,Browns Ferry Nuclear Plant."

]~ P ~V ~r~I,July 2, 1986Revision 0DESIGN BASELINE AND.VERIFICATION PROGRAMBROGANS FERRY NUCLEAR PLANTPApproved by:PreparersProject Engine rwlilriSi e DirectorManagerProject EngineeringX>p~JJk~PP'anagerEngineering AssuranceDirectorDivision of Nuclear Engineering870325002987032...

2017 Perry Nuclear Power Plant Initial Licensed Operator Examination Scenario Review Comments.

2017 PERRY NUCLEAR PLANT INITIAL LICENSE EXAMINATION SCENARIO REVIEW COMMENTS SCENARIO/EVENT COMMENT RESPONSE/RESOLUTION GENERIC 1. There is no low power scenario. The lowest power initial condition is 40%. 1. (Facility) The low power scenario is Scenario #4, which is the sp...

"Rept of Plant Startup Following Sixth Refueling Outage, 840428-850713."

r*,,%PHILADELPHIA ELECTRIC COMPANY!Peach Bottom Atomic Power StationUnit No. 2Docket Number 50-277;k-i|-,i;REPORT OF PLANT START-UP FOLIOWINGSIXTH REFUELING OUTAGEAPRIL 28, 1984TOJULY 13, 1985'iSUBMITTED TOTHE UNITED STATED NUCLEAR REGULATORY COMMISSIONPURSUANT TOe,FACILITY OP...

Comment on draft GL re testing of safety-related circuits. Util primary concern w/requested actions of proposed GL is schedule.

u b309N57 M i13.Gd cres5 - h- 95*wg g-g,,. , ,; i u 3: 23': .'" ? ! I;i 3: 23<'" ~ '"LgCLL3~', ,FloridaPowerCORPORATIONJuly 18, 1995NL95-0061Chief, Rules Review and Directives BranchU. S. Nuclear Regulatory CommissionWashington, DC 20555Subject: Comments on NRC Generic Letter ...

RO:on 730529,during performance of monthly surveillance undervoltage & underfrequency protection,device armature of knife switches for solenoid coil discovered not dropping to assume deenergized condition.Caused by scale accumulation.

. .- . . . . . . - .(vh'O,,1 y. . - .--|,, f-. _ . . .,, ,w.1r ..!,[,.. ,. . .,',,y. , .ROCHLSTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE) ROCHESTER, N.Y. .Z.;=.: 14649-! .m,.nm ,i. .. _, . . . s u .m.;,,.....*June 8, 1973f 'l% sQ ;.y un cr ic .na an au,.4dMr. John F. O'...

Forwards safety evaluation re second ten-year inservice testing program relief requests.Proposed alternatives in relief requests VR-6,PR-3 & PR-6 may be authorized.Relief request VR-8 denied.

d.TMarch 31, 1999Mr. Lew W. MyersDistribution:Vice President - Nuclear, PerryPUBLIC yMNFirstEnergy Nuclear Operating Company . PDill-2 r/f DTerao;P.O. Box 97, A200 JZwolinski,GGrant, R3{'Perry, OH 44081qISUBJECT:GAFETY EVALUATION OF THE INSERVICE TESTING (IST) PROGRAMREllEF RE...

Callaway, Unit 1 - Special Report 2014-03: Inoperability of a Seismic Instrument for Greater Than 30 Days.

~~ 'WAmeren MISSOURI Callaway Plant ·················································································································································································································································...

Wisconsin Public Service Corp., Information Concerning the Requirements for Individual Qualified in Radiation Protection Procedures.

DISTRIBUTION AFTER ISSUANCE OF OPERATING LICENSE NRC FORM 195 U.S. NUCLEAR REGULATORY COIsSSION DOCKET NUMBER FILE NUMBER NRC DISTR.!SBUTfON FOR PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Wisconsin Pub. Svc. Corp. 8/15/77 Green Bay, Wisconsin Mr. A. Schwencer Ge W aye ...

Monticello, Notice of Withdrawal of Letter of Intent to Transition to 10CFR50.48(c).

fe Xcel Energya July 16, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant 2807 W County Road 76 Monticello, MN 55362 L-MT-10-031 'lo CFR 50.48 Monticello Nuclear Generating Plant Docket 50-263 Renewed ...

Applicants Environmental Report - Operating License Renewal Stage Monticello Nuclear Generating Plant.

Applicant’s Environmental Report – Operating License Renewal Stage Monticello Nuclear Generating Plant Nuclear Management Company Docket No. 50-263 License No. DPR-22 March 2005 Monticello Nuclear Generating Plant Application for Renewed Operating License Ap...

Callaway Plant, Unit 1, Revision 14 to Technical Specification Bases, Chapter B 3.4, Reactor Coolant System.

CALLAWAY PLANT 3.4-iCHAPTER TABLE OF CONTENTSCHAPTER B 3.4REACTOR COOLANT SYSTEMSection PageB 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ..............................................................B 3.4.1-1BACKGROUND ..............