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"Conformance To Reg Guide 1.97:Nine Mile Point-1."

- _ _ - _ _ _ _ _ - _ _ - _ _ _.N...EGG NTA-9161.TECHhlCAL EVALVATION REPCRT..CONFORMANCE TO REGULATORY GUIDE 1.97: NINE MILE POINT-1 .-Docket No. 50-220Alan C. UdyPublished September 1991EG&G Idaho, Inc.Idaho National Engineering LaboratoryIdaho Falls, Idaho 83415.Prepared fo...

Insp rept 50-331/92-23 on 921204-930111.No violations noted.Major areas inspected:operational safety,maint, surveillance & cold weather preparations.

. . . .- . . - .- . . , -.*,.-- U. S. NUCLEAR REGULATORY COMMISSIONREGION IIIReport No. 50-331/92023(DRP)Docket No. 50-331 License No. DPR-49.Licensee: Iowa Electric Light and PowerCompanyIE Towers, P. O. Box 351Cedar Rapids, IA 52406facility Name: Duane Arnold Energy CenterIn...

"Draft Rept to AEC Regulatory Staff Adequacy of Structural Criteria for Monticello Nuclear Generating Plant Unit 1."

_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _'.<.N A T H A N M . 'N E W M A R Ksit vatsov L Ason Avony. U n s A N A. ILLIHoisCON 3ULv1NG ENGINEERING SERVICESD Rt. r TReport to AEC Rcgulatory StaffADE00ACY OF THE STRU"TURAL CRITERI A FOR THEMONTICELLO NUCLEAR GENEPATING PljsNT UNIT INORTHE...

R.E. Ginna Nuclear Power Plant, Technical Specification Pages Re Dose Caclulation Methodology to Alternate Source Term.

Definitions1.1CHANNELOPERATIONALTEST(COT)COREALTERATIONSCORE OPERATINGLIMITS REPORT(COLR)DOSEEQUIVALENT 1-1 31A COT shall be the injection of a simulated or actual signal into thechannel as close to the sensor as practicable to verify the OPERABILITYof required alarm, Interloc...

Transmittal of April 15, 2004 Meeting Handout Materials from NRC Staff Meeting with Westinghouse Regarding the IRIS Pre-application Review.

AgendaWestinghouse/NRC IRIS Pre-application Review MeetingApril 15, 2004Introductions Westinghouse, NRC 20 minutesOverview of IRIS pre-application documentation and Westinghouse 20 minutesproposed scheduleOutline of IRIS design with emphasis on "safety-by- Westinghouse 30 minu...

Prairie Island, Units 1 & 2, Corrected Amendments 77 & 90 changing Amendment numbers to 78 & 71, respectively.

.2September 11, 1986Docket Nos. 50-282/306 Mr. D. M. Musolf, Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall Midland Square, 4th Floor Minneapolis, Minnesota 55401 Dear Mr. Musolf: SUBJECT: CORRECTION TO AMENDMENTS NUREG-0737, ITEM II.F.2ON GEN...

Hatch, Units 1 & 2, License Amendment, Re: Issuance of Amendments.

December 18, 2002Mr. H. L. Sumner, Jr.Vice President - Hatch ProjectSouthern Nuclear Operating Company, Inc.Post Office Box 1295Birmingham, Alabama 35201-1295SUBJECT: EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 RE: ISSUANCE OFAMENDMENTS (TAC NOS. MB5484 AND MB5485) Dear Mr. ...

Revision 6 to "Safety Analysis Report for Model CNS 8-120B Type B Shipping Packaging," Table of Contents through Figure 14.

IJATTACHMENT 1GUIDE PAGE FOR INCORPORATINGREVISION 6INTO 8-120B SARGUIDE PAGE FOR INCORPORATING REVISION 6 INTO 8-120B SARREMOVE THESE PAGES FROM INSERT THESE REVISION 6 PAGESREVISION 5 OF THE 8-120B SAR INTO THE 8-120B SARTitle Page Title PageTable of Contents Table of Conten...

GG-2/2004 - Post exam Performance Analysis/Post Exam Comments.

U. S. Nuclear Regulatory Senior Reactor Operator Written Examination Review February 2004 Question 22 had a 60% miss rate The question and answer was reviewed and determined the identified correct answer is correct per station procedures and no other correct answers exist....

Browns Ferry, Unit 1, Update to the Probabilistic Safety Assessment.

September 15, 2005 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: In the Matter of ) Docket No. 50-259 Tennessee Valley Authority ) BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 1 - UPDATE TO T...

Millstone, Unit 2 Proposed Revision to Technical Specifications (LBDCR 05-MP2-007) Pressurizer Power Operated Relief Valves (PORVs) and Pressurizer Safety Valves Position Indication.

Dominion Nudear Connecticut, Inc. 5000 Dominion Boulevard, Glen Allen, Virginia 23060 Web Address: www.dorn.com January 4, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11 555 Rockville Pike Rockville, MD 20852-2738 DOMINION NUC...

Browns Ferry Units 2 and 3, Calculation MDQ0999970046, Rev. 008, NPSH Evaluation of Browns Ferry RHR and CS Pumps.

ENCLOSURE 6TENNESSEE VALLEY AUTHORITYBROWNS FERRY NUCLEAR PLANT (BFN)UNITS 2 AND 3CALCULATION MDQ0999970046NPSH EVALUATION OF BROWNS FERRY RHR AND CS PUMPSSee attached.QA RecordITVAN CALCULATION COVERSHEETICCRIS UPD:. I Page 1REV 0 EDMS/RIMS NO . EDMS TYPE: EDMS ACCESSION NO (...

Toshiba Design Control Document Rev. 0 - Tier 2 - Chapter 18 - Human Factors Engineering - Appendix 18D - Emergency Procedures Guidelines - Input Data and Calcuation Results

Emergency Procedures Guidelines—Input Data and Calculation Results 18D-1RS-5146900 Rev. 0Design Control Document/Tier 2 ABWR18D Emergency Procedures Guidelines—Input Data and Calculation Results18D.1 IntroductionThe Emergency Procedure Guidelines (EPGs) given in Appendix 18A...

Diablo Canyon, Units 1 & 2, Submittal of Revision 4 to Emergency Plan Update.

* -I'I Pacific Gas and6 Electric Company*Diablo Canyon Power PlantP. 0. Box 56Avila Beach, CA 93424November 19, 2008PG&E Letter DCL-08-097U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Docket No. 50-275, OL-DPR-80Docket No. 50-323, OL-DPR...

NUREG-1503, Vol. 1, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, Main Report," July 1994. Cover Page through Part 9, "Auxiliary Systems".

Final SafetyEvaluationReportRelated to the Certification of the AdvancedBoiling Water Reactor DesignMain ReportI' ~HQU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationJuly 1994AVAILABILITY NOTICEAvailability of Reference Materials Cited in NRC PublicationsM...

2008/06/26-NRC Staff's Brief in Opposition to CCAM and Ms. Burton's Appeal from LBP-08-09.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION In the Matter of ) ) Docket No. 50-423-OLA Dominion Nuclear Connecticut, Inc. ) ) ) (Millstone Power Station Unit 3) ) ) _________________________________________...

Waterford, Unit 3, License Amendment Request to Modify Technical Specification 3/4.9.6, Refueling Machine.

Entergy Nuclear SouthEntergy Operations, Inc.17265 River RoadKillona, LA 70057Tel 504 739 6660Fax 504 739 6678kwalshl @entergy.comKevin T. WalshVice President, OperationsWaterford 3W3F1-2008-0063September 18, 2008U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWas...

G20110251/EDATS: OEDO-2011-0256 - Response to House of Appropriations, Request re: Post Hearing Questions from the March 31, 2011 Hearing on 2012 Budget Request for the Nuclear Regulatory Commission and Development of Energy's Nuclear Energy Programs

Responses to Post-Hearing Questions from the March 31, 2011 Hearing on 2012 Budget Request for the Nuclear Regulatory Commission and Department of Energy’s Nuclear Energy Programs Ticket: G20110251 1. Impact of events in Japan on nuclear industry QUESTION 1. Given that nu...

LER 96-011-00:on 961202,safety injection sys leakage test were not performed in verbatim compliance with TS.Caused by failure to implement TS rev when problem was previously identified.Testing will be performed.W/970102 ltr.

CATEGORY 1 REGULATO INFORMATION DISTRIBUTIONOSTEM (RIDS)ACCESSION NBR:9701070200 DOC.DATE: 97/01/02 NOTARIZED: NO FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic AUTH.NAME AUTHOR AFFILIATION HARRINGTON,G.I. Wisconsin Public Service Corp. MARCHI,M.L. Wiscons...

Proposed Tech Specs & license conditions,removing fire protection requirements,per Generic Ltr 86-10.Safety assessment encl.

ATTACHMENT A Technical Specification Page RevisionsConsolidated Edison Company of New York, Inc. Indian Point Unit No. 2 Docket No. 50-247 87102100E1 871013 October, 1987 PDR ADOCK 05000247 P. PDRSectionAmendment No.3.10S. w TABLE OF CONTENTS (Cont'd) Title Control Rod and Po...

Proposed tech specs allowing repair of SG tubes via either sleeving or implementation of F criteria as alternative to plugging.

0ATTACHMENT A PROPOSED TECHNICAL SPECIFICATIONS CONSOLIDATED EDISON COMPANY OF NEW YORK, INC. INDIAN POINT UNIT NO. 2 DOCKET NO. 50-247 APRIL, 1994 9404290275 940413 PDR ADOCK 05000247 P - PDR ;'2. Operational Leakage Limits a. Primary to Secondary Leakage (1) Primary to seco...

Forwards response to followon question re AP600 SSAR Section 14.3 & AP600 insps,tests,analyses & acceptance criteria.W status column will be changed to "Closed" in open item tracking sys.

N*[hI!9\|i.w*... 'Westingh0use Energy Systemsg3yg,g,g3g33Electric C0fp0I8tl0DDCP/NRCi135NSD-NRC 97 5435Docket No.: 52-003;Noa . :. , o .u. c ,4A g x;pn.g.._,.-_q'|f'I!i'Mpap h!gRc rj.',;% ;n L r?.,- . . -.n - . 4 --.,,.,;- .a y = : 2, m xJ _.,, , s ,__ a.n. ,<> )!-. ' V u )ua ...

"Seabrook Station Emergency Planning Sensitivity Study."

, - --,I.i|PLG-0465i!|!SEABROOK STATIONI;EMERGENCY PLANNING SENSITIVITY STUDY!,tI:iii!,I'!!Prepared forNEW HAMPSHIRE YANKEE DIVISION[PUBLIC SERVICE COMPANY OF NEW HAMPSHIRESeabrook, New HampshireApril 1986(I |;,::,,1060724018e 860721P DitADOCK 05000* 3aPickard.,Lowe andGarrick...

Rev 0 to M-771, "RBCCW Heatup Immediately Following DBA- LOCA."

IATTACHMENT DCALC. NO. M-771 REV. ORBCCW HEATUP IMMEDIATELY FOLLOWING A DBA-LOCAPage 1 of 159002230275 900211ADOCK0500g3DR1;iCALCULATION COVER SHEETP!LGRIM NUCLEAR POWER STATIONSHEET 1OFhincluding AttachmentsCALC. NO. M-771 REV. @ FILE NO. SR@ RTYPENSR RB4.01Subject: RBCCW Hea...

Forwards comments on draft low power license.Expresses appreciation for making draft license available for review & for NRC effort in supporting scheduled fuel load date of 851115.

.tGeneral Offices e Selden Street, Berlin. ConnecticutH'ARTFORD, CONNECTICUT 06141-0270*L L T;%%CLT'g,(203) s6 5 5000November 5,1985Docket No. 50-423A05342Director of Nuclear Reactor RegulationMr. T. M. NovakAssistant Director for LicensingDivision of LicensingU.S. Nuclear Reg...