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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Request for Participation in Cross-Organizational Issue Identification and Ranking Project Advanced Reactors.

May 27, 2011 MEMORANDUM TO: Eric J. Leeds, Director Office of Nuclear Reactor Regulation James T. Wiggins, Director Office of Nuclear Security and Incident Response Brian W. Sheron, Director Office of Nuclear Regulatory Research Catherine Haney, Director ...

12/21/2000, summary of meeting with NEI to discuss open items in the draft generic aged lessons learned (GALL) report and standard review plan (SRP)

February 27, 2001ORGANIZATION: Nuclear Energy InstituteSUBJECT: SUMMARY OF MEETING WITH THE NUCLEAR ENERGY INSTITUTE(NEI) TO DISCUSS OPEN ITEMS IN THE DRAFT GENERIC AGEDLESSONS LEARNED (GALL) REPORT AND STANDARD REVIEWPLAN (SRP)In a December 21, 2000, meeting with NEI, the Nuc...

REVIEW OF DRAFT TECHNICAL STUDY OF SPENT FUEL POOL ACCIDENTS FOR DECOMMISSIONING PLANTS (TAC NO. MA5099).

November 19, 1999MEMORANDUM TO: Gary M. Holahan, Director Division of System Safety and Analysis Office of Nuclear Regulatory Research FROM: John W. Craig, Director Division of Engineering Technology Office of Nuclear Regulatory ResearchSUBJECT:fr2V3)REVIEW OF DRAFT TECHNICAL ...

Draft Appendix 5, containing sub-sections

Appendix 5 Appendix 5 contains the following sub-sections: 5a Original NEI screening criteria, August 18, 1999 5b Craig memo to Holahan forwarding Kennedy report, November 19, 1999. 5c Huffman memo to Richards with staff evaluation of screening criteria, December 3, 1999 5d N...

Submitted Operating Test and Written Examination.

Submitted Operating Test and Written Examination Contains the following: Initial Submittal Cover Letter ES-301-3 Operating Test Quality Checklist ES-301-4 Simulator Scenario Quality Checklist (Op Test 1) ES-301-5 Transient and Event Checklist (test 1)(copy) ES-301-6 Competenci...

Seabrook Station, Unit 1, License Amendment, Relocation of Area Temperature Monitoring Requirements.

October 1, 1999Mr. Ted C. Feigenbaum Executive Vice President and Chief Nuclear Officer North Atlantic Energy Service Corporation c/o Mr. James M. Peschel P.O. Box 300 Seabrook, NH 03874 SUBJECT: SEABROOK STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: RELOCATION OF AREA TEMPE...

"Licensing Support Info for Proposed Changes to Tech Spec:Pressure Switch-to-Analog Replacement,Unit 2."

'_UNITED STATESNUCLEAR REGULATORY COMMISSIONDOCKET N0. 50-324LICENSE NO. DPR-62.#.C AROL INA P01(ER & L IGHT COMP ANYRALEIGH, NORTH CAROLINAesKsNLICENSING SUPPORT INFORMATIONFORPROPOSED CHANGES TO TECHNICAL SPECIFICATIONPRESSURE SWITCH TO ANALOG REPLACEMENTBRUNSWICK STEAM ELEC...

Revision 23Date10/26/99APPENDIX V PUMP AND VALVE TESTING PROGRAM PLANTable 2 -Revision 23 is issued for the following: Table 1 - NoneAdded Pump and Valve Testing Program Plan Key to Table II - Valves (Continued on Page 2)'i-LLNOWS5 POWER, COMPANY" C.U POWENT STATIONi, 2LINT~ON...

LER 89-008-02:on 890126,various plant sys inoperable due to deficiencies in physical separation between Class 1E & non-Class 1E cables & different ESF divs.Caused by inadequate procurement spec.Panels deenergized.W/890524 ltr.

.- - - ._ _. _ - _ __ _ _ _ _ _ _ _-10 CFR 50.73 ., .. , 4JI ...-a.,PHILADELPHIA ELECTRIC COMPANY!-LIMERICK GENER ATING STATION ,P. O. BOX ASAN ATOG A, PENNSYLV ANI A 19464May 24, 1989)(zis) sz7 izoo sur. 2000Docket No. 50-352u. a. u cco n u ic x, ;... e.e. --License No. NPF-3...

Matls licensing package for amend 9 to license 40-11733-01 for State of South Dakota,South Dakota Dept of Health. Control:465341.

3-- ___- _ _ _ _ _ _ _U.s. NUCLEAR REGULATOR" CommissionAmendment No. 93MATERIALS LIC'dNSE MC)Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10,Cods of Federal Regulations, Chapter 1, Parts 30,31,32,3...

July 2, 1998 SECY-98-164FOR: The CommissionersFROM: L. Joseph Callan /s/Executive Director for OperationsSUBJECT: FINAL RULE ON FINANCIAL ASSURANCE REQUIREMENTS FORDECOMMISSIONING NUCLEAR POWER REACTORSPURPOSE:To request Commission approval to publish in the Federal Register ...

Rev 0 to "Brunswick Steam Electric Plant,Unit 1,Reload 6 (Cycle 7) (W/O Recirculation Pump Trip)."

___ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _ . . _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _23A5896REVISION OCLASS I :JUNE 1988 l|I(23A5896, REY. 0)SUPPLEMENTAL RELOAD LICENSING REPORTFORBRUNSWICK STEAM ELECTRIC PLANTUNIT 1, RELOAD 6 (CYCLE 7)(WITHOUT RECIRCULATION PUM...

"Control of Heavy Loads at Nuclear Power Plants,Cleveland Electric Illuminating Co,Perry Nuclear Power Plant,Units 1 & 2 (Phase I)."

. ..- -EGG-HS-6264APRIL 1983CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTSTHE CLEVELAND ELECTRIC ILLUMINATING COMPANYPERRY NUCLEAR POWER PLANT, UNITS 1 AND 2 (PHASE I)Ir-!iI* s IJ. P. SekotT. H. Stickley~..Idaho National Engineering LaboratoryOperated by the U.S. Department of...

Summary of 860909 meeting w/utils re improving lines of communication between NRC & licensees,including Sholly process,interpretation of 10CFR50.59,Tech Spec improvement program & discretionary enforcement.Related info encl.

___- -__##'o ,UNITED STATESl' "%NUCLEAR REGULATORY COMMISSION$WASHINGTON, D. C. 20555,k ..... f/November 18, 1986Docket Nos: 50-373/374,50-387/388,50-397/410,and 50-341/354LICENSEES: Commonwealth Edison CompanyPennsylvania Power and light CompanyWashington Public Power Supply ...

Transcript of 980826 ACRS Reliability & Probabilistic Risk Assessment meeting in Rockville,MD.Pp 1-235.W/Certificate & viewgraphs.

fa.wg.agg.gggg.ggg,gmme-yj l h . ,g _r g ,. #spg ,hggg g |,|._.Q,e -,rc..+Mh' &y'4 ppiLgff gge|hymerums on101 Nit n ,kh;yh;. %a.; s%yeh ggg jse e@ga$ges/s T-2s2s ijjj||[g,f43>TO BJWHITEyenp t ? sps-.!7g' K ; .?z % wad '%~''Q' oj "aggy p@P$ Kl AyAj}w$|;V{f$k |.A ' ggg*4y>ah d S...

VERMONT YANKEE NUCLEAR POWER STATION, AMENDMENT, ISOLATION VALVE SURVEILLANCE REQUIREMENTS

Mr. Samuel L. Newton March 9, 2000 Vice President, Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road Brattleboro, VT 05301SUBJECT:O6ne- A(VERMONT YANKEE NUCLEAR POWER STATIOi AMENDMENT UNDER EXIGENT CIRCUMSTANCi ISOLATION VALVE SURVEILLANCE REQUIREMEDear M...

GUIDANCE FOR FEBRUARY 2000 PLANT PERFORMANCE REVIEWS

UNITED STATES ** NUCLEAR REGULATORY COMMISSION * WASHINGTON, D.C. 20555-0001 January 25, 2000 MEMORANDUM TO: Hubert J. Miller, Regional Administrator, RI Luis A. Reyes, Regional Administrator, RII James E. Dyer, Regional Administrator, RIII .llis W. Mers.off, Regional Administ...

"Final Status Survey Rept Magnesium-Thorium Slag Storage Area,Dow Chemical Co,Bay City,Michigan Facility."

-,Final Status Survey ReportMagnesium-Thorium Slag Storage AreaThe DOW Chemical Company'sBay City, Michigan Facility|||l|lDOW U.S.A. |The DOW Chemical CompanyMidland, Michigan 48674September 21,1998/Prepared with'RADIAN laternational, LLCMidland Michiganand & Grande Radiologic...

Contract: "Telecommunication Svcs to Support Emergency Notification Sys & Health Physics Network at Three Sites," awarded to Southern New England Telephone Co.

i THis cONTR ACT IS A R ATE D 0%DE RP A IINGPAGE OF P A(. L 5' , AWARD / CONTRACTUNDE R DPAS 115 CF R 350)|1|,**2. CON T R AC1 trror J .s t idr48 A NO. 3. E F F LC T evL DAT L <. RE Gussei SON / PURCHASE REQUEST /PROJE C T NONRC-10-86-25910/1/85 RFPA ADM-86-2595. ISSUE D Sv 5....

Forwards info re facility preparedness for licensing,per IE Manual Chapter 94300.Encls include items requiring insp & resolution before Region III can make recommendation for licensing.Util estimates fuel load date in Dec 1985.

- . ~ . _ - - . - . . . . . - .-. .|2 h-,N.DEC1 3 $85MEMORANDUM FOR: R. Bernero, Director, Division of Boiling Water ReactorLicensing, NRRFROM:Charles E. Norelius, Director, Division of Reactor Projects,Region IIISUBJECT:CLEVELANDELECTRICILLUMINATINGCOMPANY(CEI),'PERRYUNIT1STA...

Transcript of 850821 investigative interview of LF Fikar in Arlington,TX.Pp 1-37.

, . . ....... : . . . . a n:. . :. = . . , .. .. - _ . '. :, 2i.: *:::.. c .:~:M._ ... . . .M.. ,':::1..';.1- -4-85-008 . .I'.- *''BEFORE THE'NUCLEAR REGULATORY COMMISSION.-3''OFFICE OF INVESTIGATION'..,4.i:b53.-,-..:,*;p 8 ,, .m.A 7.*. . .s}'-g. .INVESTIGATIVE INTERVIEWI,.OF-...

LER 2002-072 for AT&T Corp. re: Lost Generally Licensed Tritium (H-3) Exit Signs on 1/2002.

Region I NMSS Licensee Event ReportLicensee Event DescriptionAT&T Corp. Basking Ridge, NJLost Generally Licensed Tritium (H-3) Exit SignsLicense # IVIA Docket # Event Date Report Date 1. REPORTING REQUIREMENT H 10 CFR 20.2201 Theft or Loss 10 CFR 20.2203 30 Day Report 10 CFR 3...

Final - Outlines (Change Summaries - Optional)

ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)Facility: FitzPatrick Date of Exam: November 2001 Exam Level: SROK/A Category PointsTier Group PointK K K K K K A A A A G Totall1 2 3 4 5 6 1 2 3 4 *1. 1 3 6 _ 5 5 2 26Emergency & 2 2 3 3 3 4 2 17AbnormalPlant Tier 5 9 8...

Part 7 of 21 - Revision 1 to Final Safety Analysis Report for Holtec International Storage & Transfer Operation Reinforced Module Cask System (HI-STORM 100 Cask System), Volume I of II.

APPENDIX 3.D: VERTICAL HANDLING OF OVERPACK WITH HEAVIESTMPC3.D.11 IntroductionThere are two vertical lifting scenarios for the HI-STORM 100 during the normal operationprocedures at the ISFSI pad. The first scenario considers the vertical lifting of a fully loadedHI-STORM 100 ...

CP - INIT EXAM - 11/2002 - Final Outline.

ES-301 Administrative Topics Outline Form ES-301-1Revision 2Facility: CPSES Date of Examination: 11/2002Examination Level: RO Operating Test Number:AdministrativeTopic/Subject Description Describe method of evaluation:1. ONE Administrative JPM, OR2. TWO Administrative Que...