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Application for Proposed Amend 140 to License DPR-54, authorizing increase of RCS high pressure reactor trip setpoint & anticipatory reactor trip on turbine trip arming threshold to increase plant availability.Fee paid.

_.., '$'esuu.SACRAMENTO MUNICIPAL UTluTY DISTRICT 62o1 S Street P.O. Box 15830. Sacramento CA 95852 1830.1916)452 3211AN ELEC TRIC SYSTEM SERVING THE HEAR T OF C ALif-OHNIARJR 85-606January 24, 1986DIRECTOR OF NUCLEAR REACTOR REGULATIONATTENTION FRANK J MIRAGLIAJR DIRECTOR PWR...

Watts Bar Nuclear Plant Unit 2 Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 5.9.9, "Steam Generator Tube Inspection Report," to Use POPCD Methodology (EPID L-2020-LRM-0107)

Watts Bar Nuclear Plant Unit 2Pre-Submittal Teleconference for Proposed License Amendment Request Regarding TechnicalSpecification 5.9.9, “Steam Generator Tube Inspection Report,” to use POPCD MethodologyAgenda• Opening Remarks and Purpose of the Proposed LAR• Proposed Technic...

Point Beach Plant, Error To Amendment 50 & 54, Page 15.6.11-1 Which Was Transmitted With Amendments 50 & 54 Contained a Typographical Error. Please Replace That Page With Enclosed Corrected Page 15.6.11-1.

\7Y-kS kNJUL C 6 1981 Docket Nos. 50-266 and 50-301 fir. Sol Burstein Executive Vice President Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201 Dear Mr. Burstein:DISTRIBUTION: NRC PDR L PDR NSIC TERA ORB63 Rdg DEisenhut RAClark PMKreutzer-...

Responds to 860327 ltr re J Adams concerns on delay of issuance of EIS for plant decommissioning action.Completion & issuance of DES for public comment expected by 860430 & issuance of FES by 860830.

-'. .s.go 10APR 14 316The Honorable Alan CranstonUnited States SenateWashington, D. C. 20510Dear Senator Cranston:1This. is in response to your letter of March 27, 1986 in which you referredto us the concerns of your constituent, Mr. Jim Adams, about the delay inissuance of th...

NPDES noncompliance notification:on 860917 & 18,total suspended solids violations discovered in water treatment plant samples.Caused by temporary bypass of 6 inch discharge line for const purposes.Bypass ended on 860918.

-:Omaha Public Power District1623 Harney Omaha. Nebraska 68102-2247402/536-4000-September 25, 1986kLIC-86-243IOCT - 2 l986LMr. Robert D. Martin, Administratorj _,U. S. Nuclear Regulatory CommissionLRegion IV- _ . ____.611 Ryan Plaza Drive, Suite 1000Arlington, Tx. 76011Referen...

LER 85-024-00:on 850617,determined that post-LOCA radiation monitoring sys recorders were not being calibr once every 6 months.Caused by personnel error.Recorders added in plant surveillance data base.W/850712 ltr.

4.s, .seRC F al336U 8, NUCLEAA LECULATORY COamsemeOedd''APPROVED oms NO. 31:0 4 :04' ' * " " ' ' ' * *LICENSEE EVENT REPORT (LER)7ACiLITY NAASE 115~DOCKET NUeASER (2lPagu (3EDWIN I. HATCH, UNIT I0 |5 | 0 |0 | 0 |3 |2 | 1 i |OF| 0 |2"TITLE telFAILURE TO MEET TECH. SPES. CALIBRA...

LER 85-019-00:on 850913,main steam isolation sys actuated on low steam generator pressure during plant cooldown.Caused by personnel error.Sys restored to preactuation condition. Personnel counseled.W/851013 ltr.

=,NRC Form 366* (9-83)U.S. Nuclear Regulatory (ommission *-Approved OMB No. 3150-0104Expires: 8/31/85LICENSEEEVENT R E P G R'T(L E R)FACILITY NAME (1) Arkansas Nuclear One, Unit TwoIDOCKET NUMBER (2) IPAGE (3)10151010101 31 61 81110Fl011TITLE (4)Main Steam Isolation System Act...

LER 85-044-01:on 850819,plant personnel discovered seven nails installed on main steam line axial support tie rod pins instead of 3/8-inch stainless steel cotter pins.Cotter pins installed.W/851206 ltr.

.r-=RC p.rm see u s. muCLlea s,4avLaroav COMMessiOmAPPROvtD oms NO 3190 10.LICENSEE EVENT REPORT (LER)" a a ' ' ' '' "F ACILITV NAast (1) DOCm E T NuM.4 R til' AGE (LBrowns Ferry - Unit 1o 15 I o 10 t o 1215 I 9 t|or|012T4TLE 444;Use of Unspecified Material on Axial Restraints...

Non-Public Security Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Nuclear Regulatory Commission Physical Security Inspection Report Numbers 05000445/2016402 and 05000446/2016402) - Letter Only.

OFFICIAL USE ONLY—SECURITY-RELATED INFORMATION “Enclosure transmitted herewith contains SUNSI. When separated from enclosure, this transmittal document is decontrolled.” OFFICIAL USE ONLY—SECURITY-RELATED INFORMATION March 1, 2017 Mr. Ken J. Peters, Senior Vice President ...

2017/05/05 NRR E-mail Capture - Watts Bar Nuclear Plant, Unit 2 - Acceptance for Review - Application to Modify Operating License Condition Regarding Actions to Resolve Issues Identified in NRC Bulletin 2012-01 (CAC No. MF9574)

1NRR-PMDAPEm ResourceFrom: Schaaf, RobertSent: Friday, May 05, 2017 2:24 PMTo: Wells, Russell Douglas; Gordon Arent; Hulvey, Kimberly DawnCc: Saba, Farideh; Mathew, Roy; Morris, Shavon; Nadel, Jared; Beasley, Benjamin; 'Edmondson, Carla'Subject: Watts Bar Nuclear Plant, Unit 2...

Responds to NRC 850402 ltr re weaknesses noted in Insp Rept 50-352/85-03.Corrective actions:Procedure A-4, "Plant Operations Review Committee Procedure," revised & access to control room restricted.

.PHILADELPHIA ELECTRIC COMPANY ,.*2301 M ARKET STREETP.O. BOX 8699PHILADELPHIA. PA.19101(zt 5) e415020M. J. COONE YGLECTR CPRODU ON DE ANYMEfeT.May 8, 1985,Docket No. 50-352Inspection Report No. 50-352/85-03Mr. Richard W. StarosteckiDivision of' Project & Resident ProgramsU.S....

EA-14-234_Comanche Peak Nuclear Power Plant, Units 1 And 2 - Final Significance Determination Of A Greater-Than-Green Finding And Notice Of Violation; NRC Inspection Report 05000445/2015406 AND 05000446/2015406.

OFFICIAL USE ONLY – SECURITY-RELATED INFORMATION Enclosure transmitted herewith contains SUNSI. When separated from enclosure, this transmittal document is decontrolled. OFFICIAL USE ONLY – SECURITY-RELATED INFORMATION April 28, 2015 EA-14-234 Rafael Flores, Senior Vice ...

Application for amend to License DPR-24,proposing Tech Spec Change 85 to encompass addl limitations on plant operations assuming reduced RCS flow w/sufficient steam generator tube plugging.Class III amend fee encl.

AMsconsin Electrwrow coww231 E MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201September 17, 1982CERTIFIED MAILMr. H. R.Denton, DirectorOffice of Nuclear Reactor RegulationU. S. NUCLEAR REGULATORY COMMISSIONWashington, D. C. 20555Dear Mr. Denton:DOCKET NO. 50-266TECHNICAL SPECIFIC...

Responds to NRC 820719 ltr re violations noted in IE Insp Repts 50-324/82-20 & 50-325/82-20.Corrective actions: Procedure CQAD 80-1 revised & frequency of plant audits increased to reduce audit scope.

.% e,e . .,y' .'? ,Carolina Power & Light Corppany32 (d]C EU' 4 !6'Brunswick Steam Electric PlantP. O. Box 10429Southport, NC 28461-0429August 16, 1982FILE: B09-13510ESERIAL:BSEP/82-1781Mr. James P. O'Reilly, DirectorU. S. Nuclear Regulatory CommissionRegion II, Suite 3100101 ...

Forwards "Unit 1,Balance-of-Plant,Preservice Insp Program Plan" & "Unit 1,Reactor Pressure Vessel,Preservice Insp Program Plan," in response to SER Outstanding Issue 4, "Preservice & Inservice Testing Programs." W/o encls.

<-.SEABROOK STATION-PUBLIC SERVICEIEngineering ONice:Companyof New Hampshire 1671 Worcester RoadFramingham, Mossochusetts 01701(617).872 8100June 21, 1984SBN- 672 ,T.F. B7.1.2United States Nuclear Regulatory CommissionWashing ton, D. C. 20555Attention: Mr. George W. Knighton, ...

LER 84-036-00:on 841226,diesel generator 1B inoperable w/ centrifugal charging pump 1B operable.Caused by personnel error.Personnel involved reminded to verify plant status when making equipment inoperable.W/850124 ltr.

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Shearon Harris Nuclear Plant, Unit 1 - 07/09/13 Summary of Meeting with Duke Energy Regarding a Nonconservative Technical Specification Loss of Offsite Power Voltage Setpoint License Amendment Request (TAC NO. MF1498).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555·0001 September 27, 2013 LICENSEE: Carolina Power and Light Company, Inc. FACILITY: Shearon Harris Nuclear Power Plant, Unit 1 SUBJECT: SUMMARY OF JULY 9, 2013, MEETING WITH DUKE ENERGY REGARDING A NONCONSERV...

Complains that siting issues resolved during CP proceedings being unnecessarily re-evaluated as part of OL review. Reviews nonproductive since plant mods totally impractical. Siting review should be concentrated into CP stage.

82062i0270 820&iiPDR ADOCK 05000397A'PDRItMfashington Public PowerSupplySystemP.O. Box 968 3000 George Washington WayRichland, Washington 99352 (509) 372-5000G02-82-538Docket No. 50-397June ll, 1982The Honorable N. J. PalladinoChairmanU. S. Nuclear Regulatory CommissionWashing...

Ack receipt of 871218 response to Quality Verification Function Insp Repts 50-413/87-23 & 50-414/87-23.Continued concern expressed that QA organization not meaningfully contributing to plant safety & reliability.

_.8 oUNITED STATESI["j NUCLEAR REGULATORY COMMISSIONg, ;E WASHINGTON, D. C. 20555,\ /*****MAR 2 5 1988Docket Nos. 50-413and 50-414Duke Power CompanyATTN: Mr. H. B. TuckerVice PresidentNuclear Production Department422 South Church StreetCharlotte, NC 28242Gentlemen:SUBJECT: NRC...

Forwards "Palisades Plant Info for Use in Responding to Item (A) IE Bulletin 85-003 For HPSI Sys Motor-Operated Valves & Auxiliary Feedwater Sys Motor-Operated Valves." Completion program provided.

-a*%.@ ConsumersKenneth W Berryc ar Exensmgmmunaws encanessGeneral Offees- 1945 West Parnali Road. Jackson, MI 49201 . (517) 788-1636May 15, 1986James G Keppler, AdministratorRegion IIIUS Nuclear Regulatory Commission799 Roosevelt RoadGlen Ellyn, IL 60137DOCKET 50-255 - LICENS...

05/19/2011 Notice of Forthcoming Teleconference Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 7 Instrumentation and Control.

MEMORANDUM TO: FROM: SUBJECT: DATE &TIME: PURPOSE: LOCATION: CATEGORY 1:* PARTICIPANTS: UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 9, 2011 Stephen J. Campbell, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing J...

03/24/2011 Notice of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 7 Instrumentation and Control.

March 11, 2011 MEMORANDUM TO: Stephen J. Campbell, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing FROM: Justin C. Poole, Project Manager /RA/ Watts Bar Special Projects Branch Division of Operating Reactor Licensing SUBJECT: FO...

05/23/2007 Summary of Meeting with Carolina Power & Light Company Regarding the Transition to AREVA Fuel at Brunswick Steam Electric Plant, Units 1 and 2 (TAC NOS. MD4063 and 4064).

July 20, 2007LICENSEE: Carolina Power & Light CompanyFACILITY: Brunswick Steam Electric Plant, Units 1 and 2SUBJECT: SUMMARY OF MEETING WITH CAROLINA POWER & LIGHT COMPANYREGARDING THE TRANSITION TO AREVA FUEL AT BRUNSWICK STEAMELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. MD4063 AN...

06/05/2007 Notice of Significant Meeting with Entergy Nuclear Northeast Regarding the NRC's Assessment of the Safety Performance of the James A. FitzPatrick Nuclear Power Plant for Calendar Year 2006.

May 15, 2007MN No. 07-025U.S. NUCLEAR REGULATORY COMMISSIONREGION INOTICE OF SIGNIFICANT MEETINGLicensee: Entergy Nuclear NortheastFacility: James A. FitzPatrick Nuclear Power PlantDocket No. 50-333Date and Time: June 5, 2007, from 12:30 p.m. to 2:00 p.m.Location: Joint News C...

06/24/2005 Summary of Meeting Between the NRC and NMC, LLC Representatives to Discuss the Results of the Scoping and Screening Methodology Audit for the Monticello Nuclear Generating Plant License Renewal Application.

July 6, 2005LICENSEE: Nuclear Management Company, LLCFACILITY: Monticello Nuclear Generating PlantSUBJECT: SUMMARY OF MEETING HELD ON JUNE 24, 2005, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND NUCLEARMANAGEMENT COMPANY, LLC REPRESENTATIVES TO DISCUSS THERES...