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Safety Evaluation Report Related To The License Renewal Of The Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273).

Safety Evaluation ReportRelated to the License Renewal of Nine MilePoint Nuclear Station, Units 1 and 2Docket Nos. 50-220 and 50-410Constellation Energy Group, LLCU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationJune 2006THIS PAGE IS INTENTIONALLY LEFT BLA...

Ginna Written Retake - Final Outlines (Folder 3).

ES-402 Written Examination Outline Form ES-401-2 Facility: Ginna Date of Exam: 04/2011 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A G Total G* 1 2 3 5 6 * 1. Emergency 1 3 3 3 3 18 3 3 & Plant 2 1 1 2 1 9 2 2 Evaluations Tier Totals 4 4 5 4 27 5 5 1 3 2 2...

LER 97-010-00:on 970501,safety injection actuation while testing main steam safety valves occurred.No conclusive root cause identified.Multi-disciplinary team formed to investigate.W/970602 ltr.

Stephen E. Quinn Vice President Consolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 734-5340 June 2,1997 Re: Indian Point Unit No. 2 Docket No. 50-247 LER 97-10-00 Document Control Desk US Nuclear Re...

Discusses 970305 meeting in Manitowoc,WI re status of facility performance improvement initiatives & issues to be resolved prior to restarting Unit 2.Agenda,core load issues, startup commitment list & restart commitment status encl.

__ _. _ _ . . _ . . __ _ . . _ _ . __ _ _ _ _ ___ ___,,March 13, 1997Mr. S. A. Patuiski, Site Vice President-Point Beach Nuclear Plent6610 Nuclear Road,Two Rivers, Wisconsin 54241SUBJECT: POINT BEACH MANAGEMENT MEETING ,,,Dear Mr. Patuiski:This refers to the meeting conducted ...

Palisades - NAI Report Release, NAI-1149-027, Revision 1, "AST Licensing Technical Report."

Numerical Applications, Inc. Page 2 of 84 AST Licensing Technical Report for Palisades Report Number: NAI-1149-027 Table of Contents 1.0 Radiological Consequences Utilizing the Alternative Source Term Methodology................................. 4 1.1. Introduction.............

AREVA Design Control Document Rev. 0 - Tier 2 Chapter 07 - Instrumentation and Controls - Section 7.5 Information Systems Important to Safety

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 0 Page 7.5-17.5 Information Systems Important to SafetyThe information necessary to monitor the nuclear steam supply systems (NSSS), the containment systems, and the balance of plant is displayed on the operator console a...

IR 05000461-10-002; 01/01/10 - 03/31/10; Clinton Power Station, Unit 1; Fire Protection, Flood Protection Measures, Inservice Inspection Activities, Maintenance Effectiveness, and Surveillance Testing.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 May 4, 2010 Mr. Charles G. Pardee Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road...

IR 05000305-10-004, on 07/01/2010 - 09/30/2010, Kewaunee Power Station, Equipment Alignment, Maintenance Effectiveness, Modifications, Surveillance and Testing, and Radiological Hazard Assessment and Exposure Controls.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 November 3, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Energy Kewaunee, Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen All...

Email From Franke, Mark to Saba, Farideh Cc: Carrion, Robert; 249 10/26/09 Khanna, Meena; Chan, Terence; Lake, Louis Dated Monday, October 26, 2009 2:55 PM, Subject: Crystal River NDE Plan.

Franke,.MarkFrom:Sent:To:Cc:Subject:Attachments:Franke, MarkMonday, October 26, 2009 2:55 PMSaba, FaridehCarrion, Robert; Khanna, Meena; Chan, Terence; Lake, LouisCrystal River NDE planPT0407T.pdfFarideh,Per our discussion, the licensee's testing procedure is attached. The SIT...

McGuire Nuclear Station, Units 1 and 2, Corrected Technical Specification Pages Regarding Steam Generator Tube Integrity, TSTF-449, Rev 4 (TAC MD2036 and MD2037).

-3-(4) Pursuant to the Act and 10 CFR Parts 30, 40.and 70, to receive, possessand use in amounts as required any byproduct, source or special nuclearmaterial without restriction to chemical or physical form, for sampleanalysis or Instrument calibration or associated with radio...

Indian Point Unit 3 Improved Technical Specifications, Amendment 233.

eFebruary 26, 2007DISTRIBUTION CONTROL LISTDocument Name: IP3 ITS / BASESCC#151119202122232528324750616999106164273319354357424474489492493494496497500501512513518NAMEOPS PROC GP SUPERVISORCONTROL ROOMRES DEPARTMENT MGRCONROY, PATCHEMISTRY SUPERVISORTSC (IP3)SHIFT MANAGERLISSI...

Shearon Harris, Unit 1 - Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds.

'IProgress EnergyJAN 3.1 2007 Serial: HNP-07-015U.S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, DC 20555SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1DOCKET NO. 50-400/LICENSE NO. NPF-63INSPECTION AND MITIGATION OF ALLOY 82/182 PRESSURIZER BUTT WE...

Special rept:on 900312,planned maint outage of 1E BS bus initiated to complete 5-yr bus cleaning surveillance, rendering all fire dectection sys alarms & sprinkler sys inoperable.Containment air temps monitored hourly.

,-- .,if #,h-"j, 4: < ;.a.. , .I ./,was initiated'to complete a 5-year bus cleaning surveillance.- This'~outage rendered all -fire . detection system alarms'and pre-action? ;'sprinkler systems of- the. Units 2 and 3 fire protection cystem,inoperable since these systems are pow...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 6, Table 6.2-1 - Safety Injection System Code Requirements. Page 1 of 1.

I IN ND DI IA AN NA A A AN ND D M MI IC CH HI IG GA AN N P PO OW WE ER R D D. . C C. . C CO OO OK K N NU UC CL LE EA AR R P PL LA AN NT T U UP PD DA AT TE ED D F FI IN NA AL L S SA AF FE ET TY Y A AN NA AL LY YS SI IS S R RE EP PO OR RT T Revision: 22Table: 6.2-...

Unusual Event Rept 269/76-10:on 751202,reactor bldg isolation valve 1RC-7 found inoperable.Caused by point on piston stem.Paint removed & stem lubricated.All recently pointed valves will be inspected.

. - --.--. , . -.DUKE POWER COMPANYOCONEE UNIT 1Report No.:UE-269/75-10Report Date: January 6, 1976Event Date: December 2, 1975Facility: Oconee Unit 1, Seneca, South CarolinaIdentification of Event: Inoperable Reactor Building isolation valveConditions Prior to Event: Unit at ...

Submits response to Generic Ltr 88-14, "Instrument Air Problems in LWR." Due to low concentration of particles in excess of acceptable limits,no operability or safety concerns noted.

t, . E ,.,gg,.r"dt ( _^, ,. (Eg', 'GULF STATES UTEL1T1ES COMPANYiAfdM htND S T ATi(>N 9'Dit 06fiCl tiOE ??D $1 FhANO5vtil L(%HMM.A 70776 !AMAC014bM 64 bOM M6SH1V October 17,1989RBG- 31629: ,x File Code G9.5, G9.33.4|,e|U. S.-Nuclear Regulatory Commission'[Document Control Desk...

Special Rept 89-003:on 891013,fire barrier penetration open for more than 7 days during ninth refueling outage.Hatches opened to support outage activities.Containment personnel & equipment hatches closed on 891014.

,,. _ -1 s. ,Alabama Power Company - **( ; inverness Center ParkwayPost OffSe Box 1295i! Birmingham. Atabama 35201,, ,letophone L'05 8%4501 ,!| W. G. Heireton, liliSenior Vice PrenloentNuclear Oswations g3h3g g,g!t% scuttwn thctrc $> stemi1i,' November 1, 1989i|!'Docket No. 50...

Forwards list of NUREG-0737 items which will be deferred during Unit 3 Cycle 4 outage.Util is not able to meet 8-h emergency lighting requirement of 10CFR50,App R.Basis for deferrals described in 811028 ltr.

TENNESSEE VALLEY AUTHORITY+ *j CH ATTANOOGA, TENNESSEC 374o1400 Chestnut Street Tower II,.M 1h'N% . November 3, 1981g{-& fl.i (f,NOVO 6198>9. .,.C-Mr. Harold R. Denton, Director,,,, m a m COffice of Nuclear Reactor RegulationC,**WU588-U.S. Nuclear Regulatory Commissiong/fWashi...

Advises that EQE Engineering Consultants granted permission to util to remove copyright statement from rept entitled, "Design Criteria for Soil-Structure Interaction Analysis..." as indicated in attached ltr dtd 940112.

- = .,b|r;.-',#'GPU Nuclear Corporation'g3 g g gsOne Upper Pond Road- . MW wMEParsfppany, New Jersey 07054.201-316-7000 iTELEX 136-482jWnters Direct Dial Number.!'January 18, 1994C321-94-2008i5000-94-0005U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington,...

RG 1.174, Revision 3, 9/1/16 Public Meeting Industry NRC Presentation.

Public Meeting on the Development of Regulatory Guide (RG) 1.174, Revision 3September 1, 2016Three White Flint North, Room 3A-2811601 Landsdown StreetRockville, MDAgenda - Morning29/1/16 Public Meeting on the Development of Regulatory Guide 1.174, Revision 3Time Topic Speaker9...

Informs of completion of program re superheated blowdowns outside containment.Temp envelopes for each plant to be established within min of 90 days.List of equipment potentially affected by envelopes expected within 60 days.

f I|*|SNUPPSse asneia.e mes.n unitOG-162s cm. chewy n**dWOG-HELB/SB00-019$ 7g .",f,'*"d''''' October 28, 1985'Mr. D. L. Wigginton, Program ManagerFarley Units 1 & 2Office of Nuclear Reactor RegulationCook Units 1 & 2|U.S. Nuclear Regulatory Commission{lonUnits1&2>Phillips Buil...

Confirms 860530 enforcement conference at Region II ofc to discuss apparent failure to adequately verify operability of circuit breakers,per 860514 telcon.Proposed meeting agenda, identifying specific issues of concern,encl.

'ok% cla. \ ,^;-MAY 1 g ;gggTennesspe Valley AuthorityATTN y/Mr. S. A. WhiteManager of Nuclear Power6N 38A Lookout Place1101 Market StreetChattanooga, TN 37402-2801Gentlemen:SUBJECT: CONFIRMATION OF MEETING - SEQUOYAH - DOCKET NOS. 50-327 AND 50-328This confirms the telephone ...

Clinton Power Station, Unit 1, Special Report Follow-Up: Inoperable Drywell High Range Gamma Radiation Monitor.

Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604406 B March 20, 2018 U. S. Nuclear Regulatory Commission ATTN: Documerit Control Desk Washington, D.C. 20555-0001 ,. ,, Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 10CFR5...

Requests reprogramming of funds from FINs B-8625 & B-8634 to FINs A-3712 & A-3711.

.a,3.,1 [ * %,h+UNITED STATES+NUCLEAR REGULATORY COMMisslON.

Forwards "Seismic Reanalysis of Liquid Poison Sys Piping" & "Seismic Reanalysis of Core Spray Sys Piping." Both sys acceptable per ASME Code,Section III requirements.

yt1%wGPU Nuclear Corporation'-@E|M7100 lnterpace Parkway.Parsippany, New Jersey 07054-1149(201)263-6500TELEX 136-482Writer's Direct Dial Number:September 4,1984Mr. Den'nis M. Crutchfield, ChiefOperating Reactors Branch #5U.S. Nuclear Regulatory CommissionWashington, D. C. 2055...