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Vols 1 & 2 of "1987 TMI Annual Exercise Scenario."

'-1 l''"K*y, ,p>-l/^;", 4;- 1 .' } ', .-( 5 f FPDR. . < .,, - ._-' -- - s I,'j'-)- ' . -|s_ _ _ ._:__ - - - _ _ ~ - _ _ --~13o footer this page_ _ - _ _ _ _ _ - _ _ _ - _ _ - _TABLE OF COMTENTSTOPIC TAB_PAGETable of Contents . . . . . . . . . . . . . . .(White) i . . .Glossary...

"Farley Unit 1 1997 Alternate Repair Criteria 90 Day Rept."

- --Eg7# Tr gass um tu) L@CahKE528KO-U.M. 412 rd2 WI@9 TO B2059925002P 02/34~1-WESTINGHOUSE PROPRIETARY CLASS 3, .;|SG 97 08 004',,!'FARLEY UNIT 1i'1997 ALTERNATE REPAIR CRITERIA 90 DAY REPORT.:a!August 19971;ii;,e:.i4Westinghouse Electric Corporation:Energy Systems Business U...

Diablo Canyon Unit 2 - 2R9 Voltage-Based Repair Criteria 90 Day Report

mFRAMATOME TCH NNO LOG1ERI~l f* ~I' fE wwo1 -2 1 "tCALCULATION SUMMARY SHEET (CSS)Document Identifier 86- 5006208-01Title Diablo Canyon Unit 2 - 2R9 Voltage-Based Repair Criteria 90 Day ReportPREPARED BY: NAME C. G. THURSTONSIGNATUREREVIEWED BY: NAME A. M. BROWN SIGNATURETITLE...

Rev 5 to "Pilgram Station Evacuation Time Estimates & Traffic Mgt Plan Update."

, NUCLEAR ORGANIZATION,CONTROLLED DOCUMENT TRANSMITTAL NOTICE'-&OSk #TITLE:/1 Call IT) Md-ObMadS.ind &taNioR?anoeme.itfA/ne Moa'a/o -(e7~ )e/2.S. /7ac/eaA'dAcafa-/dMRaissin oso,-abONTROLLED COPY NO. [9-/35 RANSMITTAL NO.DATE99_POR DOCUMENT CONTROL USE ONLY/F 1.The attached con...

LICENSED OPERATING REACTORS STATUS SUMMARY REPORT.Data As Of September 30,1988.(Gray Book I)

. . -NUREG-0020~Vol.12, No.10October 1988:_ _ -LICENSEDOPERATINGREACTORSSTATUS SUMMARY REPORTDATA AS OF 09-30-88 .1'|_UNITED STATES NUCLEAR REGULATORY COMMISSION,.~c,,uY.''s . . :. . /A 38488"' 20020 R PDR_ _ _ _ _ _ _ _ . -l1! 1I i 1O,-_--.--___---.------r -o1-f6m ..-1s le a2...

Insp Rept 50-293/85-35 on 851209-13.Deviations noted:failure to fully document qualification of Barton 288A main steam flow switches & GE EB-25 terminal blocks.Three open items also noted,including documentation revs.

...."U.S.' NUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENT_ _ - _ _ - _ _ _ _ . _ _ _IJ.[3...2. PURPOSEThe purpose of this inspection was to review the licensee's implementationof a program to meet the requirements of 10 CFR 50.49.J. BACKGROUNDThe NRC held a ...

"Phase II,Title I Engineering Assessment of Inactive U Mill Tailings Ray Point Site,Ray Point,Texas."

_ . . . _ . . _ _ . _rjW_mnysym%nd.mpq wmm:S@@WW%mav- MW'm nww-w ,h ,h, ,a ,M & Mp m, -,WMh~hh,We kk k,MhWWMW''4|' ''khhn hnhu #@ W_% M gM N d Nk N ed N. h d $ d%Y} j %mhe 'y $' @.-,4M&MA[SMhhA*Phk . I'' ''\ , ,.M W Q $g g g@ w%w? % W & %.n ne ks W:m w w& A :p d 399M'' 'Th?, ....

Regulatory Guide 3.15. Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant

U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE 3.15, REVISION 2 Issue Date: July 2020 Technical Lead: Kevin Ramsey Written suggestions regarding this guide or development of new guides may be submitted through the NRC’s public Web site in the NRC Library at https://...

Matls licensing package for amend 3 to license 45-25383-01 for CTI Core Drilling Svc,Inc.Control:258078.

. .. _ . . - .- . -_ ....i' ""' ".Am ndn nt No. OATERIALS LICENSEPursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Codeof Fcderal Regulations, Chapter 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and...

Responds to telcon inquiry.No precautions not outlined in procedures section of manual can be taken to avoid projection of radioactive matls into fresh water zones.

- -(g-,np./.;.,-v v.(4.61.2-n.,-- ... ..-.a .q c 32g 18-digital legging,Inc.~ *_.-98328 East 58th Stc'jTulsa, Oklahoma 74145C(918) 252-5416_ August 13, 1981..~~Mail Control: 08341-U.:S. Nuclear Regulatory Commission ,Division of Fuel Cycle & Material Safety' Washington, D. C. ...

Rev 20,change 9 to "Northeast Util QA Program TR."

%Northrst' Utilities System|.,,.|plVMemoJ6/30/99 027-PRG-99||TO: Northeast Utilities Quality Assurance Program Topical Report Controlled ,Copyholders)FROM: . OreficeSUBJECl;NUQAP Topical Report Revision 20, Change 091iEnclosed is change number 09 to NUQAP revision 20. Please r...

DG-1370 proposed Revision 1 of Regulatory Guide (RG) 1.191, Fire Protection Program for Nuclear Power Plants During Decommissioning

U.S. NUCLEAR REGULATORY COMMISSION DRAFT REGULATORY GUIDE-1370 Proposed Revision 1 to Regulatory Guide 1.191 Issue Date: August 2020 ...

NUREG/CR-1621, "A Characterization of Faults in the Appalachian Foldbelt."

\ I I I i NUREG/CR-1621 A Characterization of Faults in the Appalachian Foldbelt Prepared by A. L. Odom, R. D. Hatcher, Jr. ' Florida State University Prepared for U.S. Nucle~r Regulatory Commission NOTICE This report was prepared as an account of work sponsored by an agency o...

Revised "Fermi 2 1990 Annual Radiological Environ Monitoring Rept."

- - - - - - - _ . . _ _Ed%:FERMl2~1990 ANNUAL)RADIOLOGICAL ENVIRONMENTALMONITORING REPORT|_ _.-% w >; { f D ,, y; 3 e = s i + x w s -Fgrf3|-n"1.6 ,w,JC~ldu--m f?.ma-.$A1U!: !U ||||~~,_w,I-||||DetroitEdison!Company9n{'DR. omno, e n o s ,sIADoCK 05000341PDRi - - _ _ __-__._._.._...

Forwards rev of MD 5.6, "Integrated Matls Performance Evaluation Program," for review & comment.Rev includes descriptions & evaluation criteria for noncommon performance indicators for Agreement States & Regions.

_ _**. .twoog?,%UNITED STATESp-.y,}NUCLEAR REGULATORY COMMISSION#fWASHINGTON, D.c. 306MMoot%.....July 29, 1997ALL AGREEMENT STATES|OHIO, OKLAHOMA, PENNSYLVANIA|TRANSMITTAL OF STATE AGREEMENTS PROGRAM INFORMATION (SP 97 053 )Your attention is invited to the enclosed corresponde...

"Transient Assessment Program Rept for Rancho Seco Reactor Trip on 810617,Transient Assessment Program RS-82-04."

. *',,,(.l-,sTRANSIENT ASSESSMENT PROGRAM REPORTFORRANCHO SEC0 REACTOR TRIP ONJUNE 17, 1981PREPARED AND RELEASED BYSACRAMENTO MUNICIPAL UTILITY DISTRICTTAP NUMBER - RS-82-04..(-8610220338 860926ADOCK 05002gDRTransient Assessment Program12-1132714-00.- - -- - - , . , , , - , . ...

Requests that encl info re evacuation time estimate & beach population sheltering be forwarded to regional director of FEMA,Region 1,for review.

_ _ _ _ - . _ _ _ _ ._ . _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -FC.kh k k 4I'PR,&15 ' * " = " " "%gH7:sosrmems. _F g 93ses "z'E xecutive Off'ces '96SEE{lcylggcavoc7800 Boylston stree*qBoston, Massachusetts 02199g p 3gl' F .Ay'Ralph G. Bird5''' r Vice Pr...

Application for renewal of License 29-05218-29,authorizing use of 50-Ci Co-60 sealed source in radiation studies & instrument calibr.Radiation safety guide dtd May 1984 encl.

i! *,O-.NAC FORM 313U.S. NUCLE AR REGUL ATORY COMMi$$10NAPPROVED BY OM8$8Mto CFR 30,32,33,34,3160 012035 =na 40 APPLICATION FOR MATERIAL LICENSEE P.res s3iefINSTRUCTIONS: SEE THE APPROPRIATE LICENSE APPLICATION GUIDE FOR DETAILED INSTRUCTIONS FOR COMPLETING APPLICATION SEND TW...

8/22/2018 - PREDECISIONAL-ACRS Subcommittee Meeting RE: Proposed Rule for Emergency Preparedness for Small Modular Reactors and Other New Technologies, DG-1350 Performance Based EPSMR Non-Light-Water Reactors, and Non-Power Prod or Utilization Facilities

This draft document is being released to support the August 22, 2018 Advisory Committee on Reactor Safeguards Sub-Committee public meeting. This draft document has not been subject to Commission, NRC management, and legal reviews and approvals, and its contents should not be ...

CRDM Thermal Sleeve LIC-504 - rev 2.

1 TECHNICAL ASSESSMENT OF POTENTIAL CONTROL ROD DRIVE MECHANISM THERMAL SLEEVE FAILURE INTRODUCTION During a spring outage in 2014, a control rod drive mechanism (CRDM) thermal sleeve wear issue was identified at a U.S. plant when a single thermal sleeve fell from the rea...

Analytical Report J22327-1 Std_Tal_L4 Final Report.

ANALYTICAL REPORTJob Number: 160-22327-1Job Description: WR 111 - Little Mountain Test AnnexFor:EA Engineering, Science, and Technology7995 E. Prentice Ave, Suite 206EGreenwood Village, CO 80111Attention: Pamela J Moss_____________________________________________Approved for...

Office Instruction - TEC-002, Generic Issues Program Revision 3.

OFFICE OF NUCLEAR REGULATORY RESEARCH RES OFFICE INSTRUCTION Office Instruction No. TEC-002, Revision 3 Approved by: Ray Furstenau Date: July 17, 2019 Office Instruction Title Generic Issues Program Effective Date Review Date July 17, 2019 November 17, 2...

NRC-2018-000659 - Resp 1 - Final.

NRC FORM 464 Part I U.S. NUCLEAR REGULATORY COMMISSION NRC RESPONSE NUMBER (04-2018) j>r;,..J).'flllEac,<.t_..o I 2018-000659 11 I I !J '>. RESPONSE TO FREEDOM OF ~ i • ' . INFORMATION ACT (FOIA) REQUEST i" I RESPONSE D INTERIM 0 FINAL '%-,.,••*•"' +o' TYPE REQUESTER: DATE: !J...

Westinghouse Hematite Decommissioning Project - Final Status Survey Final Report Volume 6, Chapter 7, Post-Remediation Groundwater Monitoring Summary, J18740-1 Std_Tal_L4 Final Report.

ANALYTICAL REPORTJob Number: 160-18740-1Job Description: HDP RFP-CBA-022 (21 DAY TAT)For:Westinghouse Electric Company LLC3300 State Road PFestus, MO 63028Attention: Mr. Martin Swanson_____________________________________________Approved for release.Rhonda E RidenhowerManager...

Turkey Point, Units 3 & 4 - Submit "Drift Data Acquired on Mechanical Salt Water Cooling Devices."

EPA-650/2-75-060sC+P~+~'RIFTDATA AC(UIRED ON MECHANICALSALT WATER COOLING DEVICESbyGunter 0. SchreckerRonald 0. WebbDavid A. RutherfordFrederick M. ShofnerEnvironmental Systems CorporationP;0., Box 2525'noxville, Tennessee 37901Contract No. 68-02-1365ROAP No. 21ARW-002Program ...