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Matls licensing package for amend 11 to license 35-16364-01 for Enid Health Sys,Inc.Control:466222.

Application for amend to License NPF-76,allowing use of new power distribution limits described in encl FSAR pages.

,ruThe Lightc omp a nyh Texas hoject Dectdc Generating Stationcwt M. Box 289 Wadmonh, Texas m83! Houston Lighting & PowerJune 1, 1989ST-HL-AE-3118File No.: G9.01, R510CFR50U. S. Nuclear Regulatory Commission. Attention: Document Control DeskWashington, DC 20555South Texas Proj...

Forwards quarterly status rept in response to direction given in House Rept 97-850.Encl rept covers second quarter of 1984.FEMA findings on off-site emergency preparedness are included in rept.

fdd.:geg%n.-O s': Gm fy., .g .,NUCLEAR REGUTORY COMMISSION',,e'--)1WASHINGTON, D. C. 20555+YskY'''. t.':%,, ' August 6,1984-y, ...+.,* rHAIRM2N. , * ,.'PUf!LIC CoccMEtli ROOMThe Honorable Tom Bevill, Chairman 84 AUG 10 P3 52'Subcommittee on Energy and Water-Development.Comitte...

"Fort Calhoun Station Unit 1 Semiannual Rept for Tech Spec Section 5.9.4 Jan-June 1988." W/880830 ltr.

--_ _ _ ---/WOmaha Public Power DistrictFort Calhoun Station Unit No.1Semi Annual ReportforTechnical SpecificationSection 5.9.4January 1,1988 to June 30,1988 inclusive/w v. ..,. m...3 .' [ ^ I.' , j" ' '.,,%,';. . .. ... . ., g,- . ,> .',.y.', , .-. .v- :k,-,'fy-s. ,. . . ,M,~...

Millstone Power Station Unit 2, Revision 38 to Updated Final Safety Analysis Report, Technical Requirement Manual

THIS IS A CONTROLLED COPY OF THE UNIT 2 TECHNICAL REQUIREMENTSMANUAL INCLUDING CHANGE NO. 182UPDATED BY TECHNICAL PUBLISHINGCROSS INDEX - OLD TRM LCOS/SRS TO NEW TRM LCOS/SRSOld TRM Sec LCO/SR TitleCorresponding New TRM section No.General TRM Section No.1.0 Fire Protection S...

Semi-Annual Quality Assurance Church Rock Site, January to June 2012 Sampling Events

SEMI - ANNUAL QUALITY ASSURANCECHURCH ROCK SITE,JANUARY TO JUNE OF 2012 SAMPLING EVENTSAUGUST - 2012TABLE OF CONTENTS1.0 Requirements2.0 Field Sampling Procedures and QA/QC Report3.0 Chain of Custody4.0 Laboratory Quality Control5.0 Data ValidationQuarterly Field data sheetQua...

North Anna Unit 3 COLA (Final Safety Analysis Report) - MACTEC App B.1 - Boring Logs (Soil and Rocks) - B946, B947, B948, B949, & B950

MACTECGEOTECHNICAL BORING LOG SHEET 1 OF 2 MACTEC PROJECT NO.: 6468-06-1472 I COUNTY Louisa, VA I GEOLOGIST S. NicelySITE DESCRIPTION NORTH ANNA COL GROUND WATER (tt) BORING NO. 8-946 I DRILL METHOD: Mud Rotary/Core I SAMPLE METHODS: SPT/CORE OHR. 25.0 COLLAR ELEV. 333.4 ft (N...

Forwards well chart for 800430-0507,Bailly wells w/o recorders,pond levels,pneumatic pressure transducers,water meter readings & USGS wells for 800507 & rainfall data for 800401-30.

,--THIS DOCUMENT CONTAINSPOOR QUAUTY PAGES. . !!!'~'Nnethern Indiana Public Service CompanyneracA*I'Nuclear StaffPR # 3, Box 501Chesterton, IN 46304May 16, 1980BAILLY GENERATING STATION N-1Mr. Ronald BallardEnviron:nontal Projects Branch No.1Directorate of LicensingU.S. Nuclea...

Forwards well charts for 800709-16,Bailly wells w/o recorders,pond levels,pneumatic pressure transducers & water meter reading for 800716 & USGS wells for 800715.

__ _ - __ - _ak -e0M*tunechern Indiana Public Service Company@ Nuclear StaffENRR 3, Box 501Chesterton IN 46304July 22, 1980BAILLY GENERATING STATION N-1Mr. B. J. Youngblood, Chief~Licensing Branch No. 1THIS DOCUMENT CONTAINSDivisicn of LicensingPOOR QUAUTY PAGES'U.S. Nuclear R...

Forwards response to IE Bulletin 80-11, "Masonry Wall Design," supplementing response to NRC 820805 request for addl info.

REGULA'YINFORMATION DISTRIBUTIC YSTEN (RIDS)ACCESSION NBR:6210060264 DOC,DATE: 82/10/04 NOTARIZED: NOFACIL:50"335 St, Lucie Planti Unit ii Florida Power 3 Light Co,AUTH,NA~E AUTHOR AFFILIATIONUhRIGiR,E, Flol ida Power 8 Light Co,RECIP,NAME . RECIPIENT AFFILIATIONCLARKrR.A Oper...

"Nuclear Safety-Related Diaphragm Valves Item 5B-473 Frequency Rept."

( >,;'s -.i./..-Catawba Nuclear StationUnits I and 2~!Nuclear Safety Related Diaphragm Valvesitem 58-473 Frequency Report--A??ROVIDDUKE POWER co,DATE SEP.0119838 K BLACKLEYCHfEE ENGINEERByl MECHANICAL DMSIONDuke SpecifI;ation CNS-1205.04-00-0001'7_.s Duke Valve List CN-0150-30...

Forwards diesel generator history info for facilities,in response to NRC 810709 & 20 requests.

Commonwealt Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 January 12, 1982 Mr. T. A. Ippolito, Chief Operating Reactors - Branch 2 Division of Operating Reactors U.S. Nuclear Regulatory Commission -"' Washingto...

Public version of revs to emergency plan implementing procedures,including Temporary Procedure Change Notice (TPC) 3 to Rev 5 to EPIP-02, "Emergency Classification" & TPC Notice 2 to Rev 11 to EPIP-03.W/870820 release memo.

ATTACHMENTEMERGENCY PLAN IMPLEMENTING PROCEDURE UPDATE| | | 1 i l| Updated || | 1 || "X" | EPIP No. I Revision No. I PCN No. | Marked Pages*|l i I I I ll Xj02 1 05 1 03 |None || X | 03 | 11 1 02 15,7,8,10,19,28|| X | 04| 12 | ' 02 16,7,8,12,16,25,34|| X | 11 1 06 | 03 112,30,3...

Palisades - Determination of Useful Life of Feeder Cables from the Station Power Transformer to the E-Bus Using the Arrhenius Methodology.

• ATTACFIMENT Consumers Power Company Palisades Plant Docket 50-255 Determination of Useful Life of Feeder Cables From the Station Power Transformer To The E-Bus Using The Arrhenius Methodology May 25, 1988 138 Pages OC0588-0021-NL04 • ,, 1 Objective -The objective of this Eng...

Revision 17 to Updated Final Safety Analysis Report for Turkey Point Units 3 and 4.

Non-controlled Document Revision TransmittalPrinted: 1/19/00FSAR Name: U.S.N.R.C. US Loc: US MAIL Note: 11 COPIES DOCUMENT CONTROL DESK WASHINGTON, D.C. 20555 ("L .[.T.fl FEC,....) The holder is responsible for verifying that this revision is complete and for destroying supers...

Forwards supplementary support info to 820408 request for amend to ETS re deleting portions pertaining to water quality monitoring.NRC action requested by 820514.

.______. ______ ___ ___,*aso /B ALTIMOREGAS ANDELECTRICCHARLES CENTER . P.O. BOX 1475 BALTIMORE, MARYLAND 21203'ELECTRIC ENGINEERINGD E PA R T M E N TApril 16,1982,as h@%<| [", '%, , ru/3c3 s q;p, _9Office of Nuclear Reactor Regulation j9b2..U.S. Nuclear Regulatory Commission(...

Forwards detailed discussion of util program & methodology used at plant to satisfy intent of Reg Guide 1.97,Rev 2 re licensing position on post-accident monitoring.

-N., --c vw' ;J1 . 4. 4,# *V TENNESSEE VALLEY AUTHORITY.*,s CH ATTANOOGA. TENNESSEE 37401,,'' 5N 157B Lookout PlaceiMAY 071990;F1,,'U.S. N'uclear. Regulatory _ Commission-J ,:ATIN: -Document-Control' Desk**aWashingtonL D.C. 20555,Gentlemen:tW the' Matter of ) Docket Nos. 50-32...

Cycle III startup test rept.

'.CYCLE 3 STARTUP TEST REPORTCycle 3 operations commenced December 5, 1978 with the withdrawalof the first control rod. The startup test program was conducted fromDecember 3, 1978 through February 23, 1979, in accordance with ReactcrAnalyst Procedure (RAP) 7.1.17, titled Refue...

Forwards results of initial engineering judgment for accessible sys,in response to Item 2 of IE Bulletin 79-14. List of sys isometrics & vendor design drawings encl.

i rf3pb.-ARKANSAS POWER & LIGHT COMPANYPOST OmCE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501)371 4000September 14, 1979l-099-82-099-10Mr. K. V. Seyfrit, Director,Office of Inspection & EnforcementdjU. S. Nuclear Regulatory Comm.'Region IV611 Ryan Plaza DriveSuite 1000Arlington, T...

Exelon Generation - Victoria County Station ESP, Geotechnical Final Data Report, Rev. 1 - Part 05 - Enclosures - Subsurface Investigation Reports - Power Block - Volume 02 - Pages 051-075

MACTEC Engineering and Consulting, Inc. Exelon COL - Victoria County Site Project 6468-07-1 777 Table 8. Boring B-2162A OFFSET, Suspension R1-R2 depths and P- and &-wave velocities GEOVision Report 7534-01 Exelon COL Victoria Boring Geophysical Logging rev 0 Volume 2, Rev. 0 -...

RTM 141 Issue 1 Flat Rack Tie Down.

RTM 141 issue 1 page 2 of 30 1. PURPOSE AND SCOPE This document calculates the stresses in the R7021 transport container and its tie-down system when it is transported on an R8055 ISO flatrack using the REVISS clamp plates, under the combined worst-case IAEA and US accelerati...

Suppl 1 to NRC Info Notice 88-063, "High Radiation Hazards From Irradiated In-Core Detectors & Cables." Continuation of Svc List.

100WC JUBU.JS7 . 41'(-GTC)'J 1~ 4716~2 1 310 5 1 .3 7 1 1C,71CYIFrU1M1 4A,- '.'.1;rR0P U - LC CI C -, V CI 0 M 'A-0 Ei PU T2 C, -~ it ~ L I TY ,A*T (, 1- . A*4C 'ýUg T Ct4A ý"A115222142030 1 1CO1CY1F,311J41 PULLMAN4 POWER PROOUCTS CORP GE~4ERAL CONSTRUCTION J E M4ILLER DIRECTO...

IE Info Notice 86-051, "Excessive Pneumatic Leakage in Automatic Depressurization Sys." Svc list encl.

SSINS No.: 6835 IN 86-51 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 June 18, 1986 IE INFORMATION NOTICE NO. 86-51: EXCESSIVE PNEUMATIC LEAKAGE IN THE AUTOMATIC DEPRESSURIZATION SYSTEM Addressees: All boiling water re...

Response to Questions 6 & 8 re fire protection program,in response to NRC 780420 ltr.

RESPONSE TO NRC LTR DTD 4/20/78 trans response to remaining questions 6&8 concerning Applicant's Fire Protection Program w/att drawings NOTCE THE ATTACHED FILES.ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AN...

"Owners Data Rept for Inservice Insps," documenting inservice insp activities conducted during refueling Outage 11 (880308-0525) Spring 1988 refueling outage.

_- _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ - -*1Page _1 of 44, ,5??D Coc;er Nu: lear StatELht ilCcuercial Sernee rate hly 1974Nattocal ioard s207 RNIS-1 FORMOWNER'S-DATA REPORT FOR INS _ERVICE INSPECTIONSAs required by the Provisions of the ASME Code Rules1. OWNE...