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Final Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant.

Safety Evaluation ReportRelated to the License Renewal of James A.FitzPatrick Nuclear Power PlantDocket No. 50-333Entergy Nuclear Operations, Inc.U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationFebruary 2008'Ovo' REG&Z111C,)THIS PAGE INTENTIONALLY LEFT BL...

NUREG-1905 "Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant."

TU.S.P4IVC NUREG-1 905United States Nuclear Regulatory CommissionProtecting People and the Environmentsaf(y EwaýUBUaO RepoRelated to the License Renewal ofJames A. FtzPatrickNuclear Power PlantDocket No. 50-333Entergy Hud©law Ft Pactkikl LLCEn~teirgy lHudlar Olpsraf~ons, I...

South Texas Project, License Amendment 64 & 53, Amendments Revise TS 4.6.1.3.e To Add An Option That Will Allow Personnel Airlock Pneumatic System Leak Test To Be Completed In 8 Hours With a Pressure Drop Of 0.50 Psi.

August 29, 1994Docket Nos. 50-498 and 50-499 Mr. William T. Cottle Group Vice-President, Nuclear South Texas Project Electric Generating Station Houston Lighting & Power Company P. 0. Box 289 Wadsworth, Texas 77483DISTRIBUTION: Docket File NRC PDR Local PDR PDIV-2 Reading JWRo...

Arkansas Nuclear One, Unit 1, Amendment 26 re changes to TS to allow additional time (beyond 36 hours) for repair of failed reactor building emergency cooling fan.

Docket No. 50-313JUN 9 1977Arkansas Power & Light Company ATTN: Mr. J. D. Phillips Senior Vice President Production, Transmission and Engineering Sixth and Pine Streets Pine Bluff, Arkansas 71601Gentlemen: By letter dated June 3, 1977, you requested ivmediate changes to the Ar...

Perspectives on Severe Accident Mitigation Alternatives for U.S. Plant License Renewal.

Perspectives on Severe Accident Mitigation Alternatives for U.S. Plant License Renewal Tina Ghosh U.S. Nuclear Regulatory Commission, Rockville, MD, USA Robert Palla U.S. Nuclear Regulatory Commission, Rockville, MD, USA Donald Helton U.S. Nuclear Regulatory Commissio...

Chapter 5 - Reactor Coolant System and Connected Systems.

5-1 5.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS 5.1 Introduction .................................................................................................................. 5-1 5.2 Integrity of Reactor Coolant Pressure Boundary ....................

Page TS6-17 of Tech Specs re safety-related equipment & listing of current Tech Spec pages.

steady state conditions greater than or equal to $1.00; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or,...

03/01/07 Ltr to S Sisley re: Request for Additional Information - Model No. MIDUS Package.

March 1, 2007Mr. Steven E. SisleyEnergySolutions2105 South Bascom Ave., Suite 160Campbell, CA 95008SUBJECT: REQUEST FOR ADDITIONAL INFORMATION - MODEL NO. MIDUS PACKAGEDear Mr. Sisley:This refers to your application dated November 1, 2006, as supplemented November 17, 2006,req...

Audit Summary for the JAFNPP LRA Safety Site Audits.

Enclosure-1-AUDIT SUMMARY REGARDING THE LICENSE RENEWAL APPLICATION FOR THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT I. IntroductionBy letter dated July 31, 2006, Entergy Nuclear Operations, Inc., submitted, for the U.S. NuclearRegulatory Commission’s (NRC) review, an applicat...

Seabrook - Updated Final Safety Analysis Report, Revision 12, Appendix 2D, Geologic Bedrock Logs of Boring in the Site Area.

SEABROOK UPDATED FSARAPPENDIX 2DGEOLOGIC BEDROCK LOGS OF BORING IN THE SITE AREAThe information contained in this appendix was not revised, but has beenextracted from the original FSAR and is provided for historical information.APPENDIX 2DLIST OF BORINGS DONE FOR SEABROOK STAT...

Callaway Plant, Unit 1 - Request for Additional Information Related to Generic Letter 2004-02, "Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (TAC MC4671).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 27, 2009 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251 SUB..IECT: CALLAWAY PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMA...

Vogtle, Early Site Permit (ESP) Application, Rev. 5, Part 2, Site Safety Analysis Report, Chapter 2, Site Characteristics, Section 2.5, Appendix 2.5E, AP1000 Vogtle Site Specific Seismic Evaluation Report. Cover through Page 93.

Southern Nuclear Operating CompanyVogtle Early Site Permit ApplicationPart 2 – Site Safety Analysis Report2.5E -1 Revision 5December 2008Appendix 2.5E—AP1000 Vogtle Site Specific Seismic Evaluation ReportPrepared byWestinghouse Electric Company LLCOctober 2008 Southern Nuclear...

Requests NRC approval to eliminate arbitrary intermediate breaks from design considerations for steam generator blowdown sys piping replacement.

123 Main Street. White Plains, New York 10 914 681.6200 NewYorkPower M 12, 1987 Authority IPN-87-026 U. S, Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Subject: Indian Point 3 Nuclear Power Plant Docket No. 50-286 Criteria for Postulated Hi...

"Decision Analysis Rept for US Army Matls Technology Lab Research Reactor/"

. - _ _ - - - - -!M1 t4avenber 1990b,,3,,as-,~.US Army Cc .ps.of EngineersToxic and HazardousMaterials AgencyDECISI0f1 AllALYSIS REPORTFORU.S. ARMY MATERI ALS TECitt10 LOGY LABORATORYRESEARCil REACTOR:.*9110200000 911000PDRADOC): 05000047PPDRTHAM A F orrn 45 1 Jul 90_ _ _ _ - ...

"Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2," informal rept.

-. ,ATTACHMENT.EGG-EA-6734|.,MARCH 1985i;||CONFORMANCE TO REGULATORY GUIDE 1.97, BRUNSWICKSTEAM ELECTRIC PLANT, UNIT NOS.1 & 2.1i:, ,[..M. S. Tawfik,Idaho National Engineering Laboratory Informal ReportOperated by the U.S. Department of Energy4fjd ~ : ' 'M i*o,'.,[&~.- .L 2; \...

Forwards response to 961016 RAI re license amend request for performance-based drywell bypass leakage test program.

.. .- . - _ _ --.Y^.C:NTERDOR-3pENERGYPERRY NUCLEAR POWER PLANT Mail Address:10 CEMER ROADR ,O 10 44081,PERRY. OHIO 44081(216) 259-37374December 6,1996PY-CEl/NRR-2119LIUnited States Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555,Perry Nuclear Power Pl...

Insp repts 50-266/96-16 & 50-301/96-16 on 961028-0906. Violations noted.Major areas inspected:procedures & representative records,observations & interviews w/ personnel.

_ _ _ . . _ _ . . - .i*|.U.S. NUCLEAR REGULATORY COMMISSIONREGION 111|lDocket Nos: 50-266; 50-301|Licenses No: DPR-24; DPR-27;:Reports No:50-266/96016(DRS) !50-301/96016(DRS)jLicensee: Wisconsin Electric Power Company.|Facility: Point Beach Nuclear Plant, Units 1 and 2|;Locati...

Discusses enforcement conference held on 961204,providing considerable info related to various apparent violations resulting from insp 50-213/96-201,96-06,96-07,96-08 & 96-80. W/encl.

__..December 20, 1996Mr. Ted C. FeigenbaumExecutive Vice President and Chief Nuclear OfficerNortheast Utilities Service Companyc/o Mr. Terry L. HarpsterP.O. Box 270Hartford, CT 06141-0270SUBJECT:HADDAM NECK ENFORCEMENT CONFERENCEAt the December 4,1996, enforcement conference, ...

Forwards addl info to justify acceptability of plant design for several accident monitoring parameters.Commitment provided to modify design re safety injection accumulator pressure & pressurizer heater status.

,Log # TXX-4382-File # 10010 -.TEXAS UTILITIES GENERATING COMPANY907.5MKYWAY TOWER * 400 NORTH OLIVE MTREET. L.B. M8 * DALLAM, TEXAM 73208|'f,H ?,ECJanuary 28, 1985iDirector of Nuclear Reactor Regulation 1'Attention: Mr. B. J. Youngblood, ChiefLicensing Branch No.1 ,'Division ...

Forwards draft AP600 PRA Table 59-30,AP600 PRA-based insights,summarizing important design features,operational assumptions & risk insights of AP600 PRA.

_ -_ _ _ . _ . . . . _ _ _ , _. _ _ _ . _ . . _ . . _ . ...g..a. .iWestinghouse Energy Systemssa 355.Electric CorporationPittsbu@ Pcnisylvania 15230 0355.NSD-NRC-97-5005IDCP/NRC07564Docket No.: STN-52-003|February 28,1997Document Control Desk 1U.S. Nuclear Regulatory Conunissi...

Insp rept 50-285/96-12 on 961015-1101.Violation noted.Major areas inspected:inservice insp program,maint program & followup insp effort in operations & engineering areas.

. . _ _ . . . _ . . _ . . . . . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ . . _ _ . . _ _ _ _ . . . . _ _ _ _ . . _ _ . _ _ -.li|*)'ENCLOSURE 2U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDocket No.. 50-285License No.: DPR-40Report No.:50-285/96-12Licensee:Omaha Public Pow...

Vol I of "Review of Modular Accident Analysis Program/PWR Code,Subtask 16.1."

r-'f f , s .*i,,._a-VOLUMEIREVIEW OF THE M AAP/PWR CODE$U8T ASK 16.1Prepared byP. Nakayama and M. Ringham#Prepared forIDCOR ProgramM anaged byTechnology for Energy CorporationOne Energy CenterKnoxville, Tennessee 37922.M ay 19838507130172 850425PDR FOIAALVAREZ85-110 PDR~|01-r'...

Vogtle, Units 1 and 2 - Notification of Full Compliance of Required Action for NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events.

Charles R. Pierce Regulatory Affairs Director May 23, 2016 Docket No.: 50-424 50-425 Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 U. S. Nuclear Regulatory Commission . ATTN: Doc...

LER 91-016-00:on 910611,TS 4.6.1.3.a surveillance missed. Caused by personnel error.Operations training lesson guide revised & appropriate plant procedures revised.W/911028 ltr.

'CCELERATEDDISTRIBUTIONDEMONSTRATION SYSTEM *'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)TACCESSION NBR:9111060213 DOC.DATE: 91/10/28 NOTARIZED: NOFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit1, Pacific GaAUTH.NAME AUTHOR AFFIL'IATIONHUG,M.T. Pacific Gas & Electric...

Donald C. Cook Nuclear Power Plant, Units 1 and 2 - NRC Pilot Design Bases Inspection (Programs) Inspection Report 05000315/2016008; 05000316/2016008 (AXD).

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 June 7, 2016 Mr. Joel Gebbie Senior VP and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUBJECT: DON...