Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Forwards TS pages,converting to Improved Std TS,which were missing or out of order.Pages were originally submitted with licensee 981211 ltr to NRC.Ltr contains no new commitments.

123 Main Street White Plains, New York 10601 914 681.6950 914 287.3309 (Fax) SNewYorkPower 40 AuthorityJames Knubel Senior Vice President and Chief Nuclear OfficerJuly 2, 1999 IPN-99-072U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001Sub...

NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements.

UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555October 19, 1989*;- :, * *,,v:TOi SALL'HOLDERS OF OPERATING. LICENS AND PONSTRUCTIONPERMITS FOR'NUCLEAR POO REACTORS-SUBJECT: REQUE$T46OR INFORMATION CONCERNING STATUS OF IMPLEMENTATION OFUNRESOLVED SAFETY ISSUE....

Part 21 Report - 1995-144

ACCESSION #: 9506010461 ENCLOSURE 1 EVALUATION OF DEVIATION, DEFECT, FAILURE TO COMPLY FORM PART I - REPORTING NINE MILE POINT UNIT 1 (affected unit) DER NO. 1-95-0275 DATE OF DISCOVE...

Draft Regulatory Guide DG-6004 (Proposed Revision 2 of Regulatory Guide 6.2, Dated July 1974) Integrity and Test Specifications for Selected Brachytherapy Sources.

U.S. NUCLEAR REGULATORY COMMISSION December 2007OFFICE OF NUCLEAR REGULATORY RESEARCH Division 6 DRAFT REGULATORY GUIDE Contact: Mark Orr(301) 415-6373 DRAFT REGULATORY GUIDE DG-6004 (Proposed Revision 2 of Regulatory Guide 6.2, dated July 1974) INTEGRITY AND TEST SPECIFIC...

Forwards marked-up safety issues mgt sys listing for plant in response to K Jabbour 870825 ltr.Implementation status of many generic items provided by author 860530 ltr.

. __;.[-1.4c*DUKE POWER GOMPANYP.O. BOX 33189CILARLOTTE N.O. 28242HALH.TUCKEH TELEPHONEvmsremuspent(704) 073-4531wontsam enopoorsonOctober 1, 1987U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D. C. 20555Subject: Catawba Nuclear StationDocket No...

Federal Register Notice - Announcing The Issuance Of The Indian Point Renewed Licenses.

[7590-01-P] NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2008-0672] Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating Unit Nos. 2 and 3 AGENCY: Nuclear Regulatory Commission. ACTION: License renewal and record of decision; issuance. SUM...

Questions from 1/11/08 ltr from Team Members re: Review of NJ Agreement Application.

"-r i fQuestions from 1/11/09 Itr under 4.3 that might be ones I suggested1. Q4 - Attachment BER 2.01-4, titled "Temporary Exemption from DEP Regulation or LicenseCondition," does not include a method for determining the acceptability of and the grantingof exemptions. Please d...

NRC Staff Pre-Filed Hearing Exhibit NRC000104, Statement of Professional Qualifications for On Yee.

Statement of Professional Qualifications On Yee, Mechanical Engineer, Aging Management of Reactor Systems and Guidance Update Branch Division of License Renewal, Office of Nuclear Reactor Regulation, U.S, Nuclear Regulatory Commission Summary Mr. Yee is a Mechanical Engineer ...

Memo re: Issuance Of Technical Letter Report, "Comparison Of Degradation Scenarios In The Proactive Materials Degradation Assessment (PMDA) And The Generic Aging Lessons Learned (Gall) Report".

December 16, 2011 MEMORANDUM TO: Patrick Hiland, Director Division of Engineering Office of Nuclear Reactor Regulation Melanie Galloway, Acting Director Division of License Renewal Office of Nuclear Reactor Regulation FROM: Michael J. C...

GALL Report, Volume 2, Chapter X, April 2001

April 2001 X-i NUREG-1801CHAPTER XTIME-LIMITED AGING ANALYSESEVALUATION OF AGING MANAGEMENT PROGRAMSUNDER 10 CFR 54.21(c)(1)(iii)NUREG-1801 X-ii April 2001This Page Intentionally Left BlankApril 2001 X-iii NUREG-1801TIME-LIMITED AGING ANALYSES: EVALUATION OF AGING MANAGEMENT P...

Frequency Distributions for Additional Initiating Event Categories, Revision 1.

S.A. Eide 9/19/2007 Frequency Distributions for Additional Initiating Event Categories, Revision 1 Introduction Because of requests from industry probabilistic risk assessment (PRA) analysts, several additional initiating event categories (beyond those covered in NUREG/CR-69...

September 27, 2012 PSEG Early Site Permit … RAI 61 Response NRC Public Meeting.

September 27, 2012September 27, 2012PSEG Early Site Permit – RAI 61 ResponseNRC Public MeetingPSEG Early Site Permit – RAI 61 ResponseNRC Public MeetingIntroductionIntroductionƒ Introductionsƒ Purpose of Meeting• Present methodology for performing Rock Hazards Analysis– RAI 61...

G20030139/LTR-03-0159 - Senator Richard Durbin concerns NRC's draft Package Performance Study Test Protocols (NUREG-1768)

April 11, 2003The Honorable Richard J. DurbinUnited States SenateWashington, D.C. 20510Dear Senator Durbin:Thank you for your letter dated March 18, 2003, expressing your comments regardingNUREG-1768, “United States Nuclear Regulatory Commission Package Performance Study Tes...

Draft Regulatory Guide DG-0016 (Proposed Revision 2 of Regulatory Guide RG 10.6) Guide for the Preparation of Applications for an Industrial Radiography License.

U.S. NUCLEAR REGULATORY COMMISSION January 2008OFFICE OF NUCLEAR REGULATORY RESEARCH Division 10 DRAFT REGULATORY GUIDE Contact: Mark Orr(301) 415-6373 DRAFT REGULATORY GUIDE DG-0016 (Proposed Revision 2 of Regulatory Guide 10.6, dated December 1981) GUIDE FOR THE PREPARAT...

Comment (13) - OAS Comments - Sherrie Flaherty - Minnesota Department of Health - 5-13-16 - STC-16-032 Part 37 Effectiveness OAS Comments.

Alabama, Arizona, Arkansas, California, Colorado, Florida, Georgia, Illinois, Iowa, Kansas, Kentucky, Louisiana, Maine, Maryland, Massachusetts, Minnesota, Mississippi, Nebraska, Nevada, New Hampshire, New Jersey, New Mexico, New York, North Carolina, North Dakota,...

OL MANUAL CHAPTER UPDATE ATTACHMENT 1; OLMC-110.

OLMC-110August 2002Attachment 1 - 1 - CONTROL OF OPERATOR LICENSINGGUIDANCE DOCUMENTSA. PURPOSEThe purpose of this Operator Licensing Manual Chapter (OLMC) is to outline therequirements for issuing and revising the following operator licensing guidancedocuments:� NUREG-1021, “...

DRAFT-Advanced Alarm Systems: Revision of Guidance and Its Technical Basis

Advanced Alarm SystemsRevision of Guidance and Its Technical BasisACCESSION NUMBER ML003714955NUREG/CR-xxxxBNL-NUREG xxxxPrepared byWilliam S. Brown, John M. O’Hara, and James C. HigginsBrookhaven National LaboratoryPrepared forU.S. Nuclear Regulatory CommissionAdvanced Alarm ...

Lists RG series (active RG),bibliography of physical security documents published by NRC,bulletins & circulars & safeguards history.

, . . _ _ _ _ _ _ _ _ - - - - _ _ .- - - - - _ _ -REGULATORY GCIDE S." RIES,-!!etyDIVISION 5 - MATERIAIE AND PLANT PROTECITON -AC'ITVE REGULATORY GUIDES,PublishedGuide- Numbe rTitleRev. Month / Year12025.1- Senal Numbering of Fuel Assemblies for Light Water Cooled Nuclear Powe...

"Conformance to Reg Guide 1.97:Summer," technical evaluation rept.

- . - - -. .. .-*.,.'*, .E*, .LOG-NTA-7231,1a4).TECHNICAL EVALUATION REPORT ,:'CONF 0Miwr.i TO REGULATORY GUID' 1.97: SUMMER>Docket No. 50-395'||.J. W. Stoffel||.Published April 19881I iiIdaho National Engineering LaboratoryEG&G Idaho, Inc.;Idaho Falls, Idaho 83415|.,Prepared ...

Response to Portion of NRC Request for Additional Information Letter No. 100 Related to ESBWR Design Certification Application - Auxiliary Systems - RAI Numbers 9.1-37 and 9.1-38.

0 1 HITACHIGE Hitachi Nuclear EnergyJames C. KinseyVice President, ESBWR LicensingPO Box 780 M/C A-55Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 08-090 Docket No. 52-010February 7, 2008U.S. Nuclear Regulatory CommissionDocument Control DeskWash...

Testimony of GR Thompson & SC Sholly on Commission Question 2,Contentions 2.1(a) & 2.1(d).Implementation of filtered vented containment sys or compartment venting sys would reduce risk of accidents.Certificate of Svc encl.

r. ..2DOCKETEDUWC'82 EC 30 till M4UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION.BEFORE THE ATOMIC SAFETY AND LICENSING BOARDIn the Matter of ))CONSOLIDATED EDISON COMPANY OF NEW YORK ) Docket Nos. 50-247-SP(Indian Point Unit 2) ) 50-286-S P)POWER AUTHORITY OF THE STATE...

Wolf Creek Generating Station, Fire Protection Evaluations for Unique and Unbounded Fire Barrier Configurations - M-663-00017A W08 G3D-27 to Att H.

M-663-00017 A, Revision W03 Page G3D-27 of G3D-50 Structural Steel Fireproofing Data Appendix G3D 3101-1974 Thermal Short #1 Sketch Thermal Short .. · ~·. ,. . ., ,. o ·. ' £,) ' "' . () • • • ;o •• Thermal Short #1 Photo 1 Thermal Short #1 Photo 2 M-663-00017A, Revision W03 P...

Large Break LOCA Initiating Event Frequency Estimates.

e e G,T3500 ;] 0511 UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555·0001 January 29, 2002 MEMORANDUM TO: ACRS Members ;;/A! FROM: Hossein Nourbakhsh, Senior Fellow SUBJECT: LARGE BREAK LOCA INITIATING EVENT FREQUE...

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 02 Figure 2.5.2-256

CEUS SSC Mmax Zones and RLMEsin the Site RegionFIGURE 2.5.2-256 Rev 8WILLIAM STATES LEE IIINUCLEAR STATION UNITS 1 & 2^Site200-mile radius75°W 80°W 85°W35°N 30°NWLS COL 2.5-2^Site200-mile radius75°W 80°W 85°W35°N 30°NNotes: MESE-N and NMESE-N geometries (left panel) modified a...

Draft Regulatory Guide DG-8035, Administrative Practices in Radiation Surveys and Monitoring.

U.S. NUCLEAR REGULATORY COMMISSION August 2010 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 8DRAFT REGULATORY GUIDE Contact: H. Karagiannis ...