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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Forwards marked-up listing of completed or implemented items from regulatory info tracking sys facility implementation, in response to 860430 request re implementation of generic requirements.

.|Hsconsin Electnc mracoumr231 W. MICHICAN, P.O. BOX 2046, MllWAUKEE, WI 532019VPNPD-86-236NRC-86-48May 30, 1986Mr. H. R. Denton, DirectorOffice of Nuclear Reactor RegulationU. S. NUCLEAR REGULATORY COMMISSIONWashington, D. C. 20555Attention:Mr. George Lear, DirectorProject Di...

Insp Repts 50-369/86-08 & 50-370/86-08 on 860301-0420. Violations noted:failure to perform cumulative offsite surveillance dose test,verify operable equipment & follow estimated critical position re rod bank reinsertion.

, . - -UNITED STATESI*gga rF2og*oNUCLEAR REGU.LATORY COMMISSION''yREGloN 11ng j101 MARIETTA STREET, N.W.*I*ATLANTA, GEORGI A 30323%*...*/Report'N's.: 50-369/86-08 and 50-370/86-0'8 oLicensee: Duke Power Company422 South Church Street*Charlotte, NC 28242Facility Name: McGuire N...

Forwards rept on Limitorque operator lubrication for NRC review.Eight valves found w/mixtures of 12 to 33% of Sun EP50 mixed w/Exxon Nebula EPO/EP1.Mixed grease maintained lubricating capability & will perform intended function.

/N Commonwealth Hieon** '/ C4 Fast Neuonal Plaza. Chicago, L5noisJ Address Reply to; Post omco Box 757O.* *sy CNcago, lihros 60600 0767.August 26, 1988Mr. T. E. MurleyOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionNashington, DC. 20555Attna Document Cont...

Insp rept 50-483/97-21 on 971207-980117.No violations noted. Major areas inspected:operation,maint,engineering & plant support.

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________ -.. . .. ...ENCLOSUREU.S. NUCLEAR REGULATORY COMMISSIONREGION IVDocket No.: 50-483License No.: NPF-30Report No.:-50-483/97-21Licensee: Union Electric CompanyFacility: Callaway PlantLocation:Junc...

REQUEST FOR PUBLICATION IN BI-WEEKLY FR NOTICE - NOTICE OF (TAC NO. 73584) ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE.

November 2, 199Docket No. 50-334 Mr. J. D. Sieber, Vice President Nuclear Group Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania 15077 Dear Mr. Sieber: SUBJECT: BEAVER VALLEY UNIT 1 - ISSUANCE OF AMENDMENT (TAC NO. 74851) The Commission has issued the enclos...

Letter forwarding amend 142 to facility operating license No. DPR-26 for Indian Point Nuclear Generating Unit No. 2.

July 19, 1989Docket No. 50-247 DISTRIBUTION Docket file NRC PDR PDI-1 Rdg Local PDR Mr. Stephen B. Bram SVarga BBoger Vice President, Nuclear Power CVogan RCapra Consolidated Edison Company DBrinkman OGC of New York, Inc. DHagan EJordan Broadway and Bleakley Avenue TMeek (4) W...

01/11/2001 Questions for Discussion at Meeting with NEI, et al., on Risk-Informed Changes to LOCA-Related Regulatory Requirements

Questions on WOG LBLOCA Redefinition ProgramFeasibility of LBLOCA RedefinitionWhether or not the NRC decides to focus exclusively on large break loss-of-coolant accident(LBLOCA) redefinition depends on the feasibility of this approach. Clearly the owner's groupsbelieve this ap...

11/16/2000 Summary of Public Meeting on Risk-Informed Changes to LOCA-Related Regulatory Requirements

January 3, 2001MEMORANDUM TO: Mark A. Cunningham, ChiefProbabilistic Risk Analysis BranchDivision of Risk Analysis & ApplicationsOffice of Nuclear Regulatory ResearchTHRU: Mary T. Drouin, Section Leader /RA/Probabilistic Risk Analysis BranchDivision of Risk Analysis & Applicat...

Forwards NRR input for Feb 1987 SALP Board meeting covering 851019-861231.Overall performance rating of Category 1 assigned in functional area of licensing activities.

_- _ _ _ _ _ _ _ _ _ _ _ _ _o.January 20, 1987Docket No. 50-271MEMORANDUM FOR: William Kane, DirectorDivision of Reactor ProjectsRegion ITHRU: Robert M. Bernero, DirectorDivision of BWR LicensingTHRU: Daniel R. Muller, DirectorBWR Project Directorate #2Division of BWR Licensin...

Comments on 830114 draft NUREG-0956.Recommends effort to recognize all physical processes that will work to reduce radioactivity releases during LWR accidents & bring appropriate realism to source terms.

- -- - - - . -- . - . - - _ ___ - . _ . .og4\..-,5.LGW,INC.son.79s ,)1999 South Sascom AenueCampbell Califomeo 95008-9933USA408/377 4470February 8, 1983 ,;Mr. M. W. JankowskiiDivision of Accident Evaluation, RES; U.S. Nuclear Regulatory CommissionWashington, D. C. 20555,i|Dear...

Forwards revised response to notice of violation & 850507 proposed Civil Penalty EA-84-119 re seal table leak & thimble tube ejection event discussed in Insp Rept 50-327/84-24.Special maint instruction replaced.

-,..,,.TENNESSEE VALLEY AUTHORITYCHATTANOOGA. TENNESSEE 374o1400 Chestnut Street Tower IIrJuly 22, 1985Mr. James M. Taylor, DirectorOffice of Inspection and EnforcementU.S. Nuclear Regulatory ConaissionWashington, D.C. 20555Dear Mr. Taylor:As a result of telephone conversation...

Advises of no digital points for open/closed status of safety valves.Down stream temp available verbally from control room.Plant data & status info encl.

. ., . , , . ..ar .' , ,: . ''. .. . .w .- . :c: 1 n,w, = a -.. .-.-.. ->.:.11. :- . . . w: s ~; :.ma. w : m....n c. .. a;;.u ... .aDuke Power Company-.j!MEMORANDUM~jz._ em ,,,DATE4 b,/ks ...)TOOiiU S N Rc.v:ADDRESSdRVfSo-ely % /,., 3~FROMMSUBJECTd hw av nuL)$dpMb&V|AdWAj6 d,a...

Catawba, Units 1 and 2, Amendment Nos. 213 and 207, Re: Increasing Flexibility in Mode Restraints.

LCO Applicability3.03.0 LCO APPLICABILITY (continued)3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITYLCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in theApplicability, except as provided in LCO 3.0.2 and 3.0.7.LCO 3.0.2 Upon discovery of a ...

Letter forwarding Order confirming Public Service Electric & Gas Co. commitments to implement those post-TMI related items set forth in NUREG-0737 for which the staff requested completion on or after 07/01/81.

DISTRIBUTION Docket OPA 1 4 Ig83 NRC PDR RDiggs L PDR JHeltemes Docket No. 50-272 NSIC Gray ORB#1 Rdg DEisenhut Mr. Richard A. Uderitz ORAB Vice President - Nuclear CParrish Public Service Electric and Gas Company WROEssf\ Post Office Box 236 OELD 4Lf Hancocks Bridge, New Jers...

LER 02-003-00, Catawba Unit 1 Emergency Personnel Hatch Unlatched.

DukePkPower,A Duke Energy CompanyGARY R. PETERSONVice PresidentCatawba Nuciear StationDuke PowerCN01 VP i 4800 Concord Rd.York, SC 29745803 831 4251803 831 3221 faxgrpeters duke-energy. cornJuly 22, 2002U. S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashing...

Draft - NRC Comments For Peach Bottom Unit 2 and 3, SRO-1.

ES-301 Administrative Topics Outline Form ES-301-1Facility: Peach Bottom Unit 2 & 3 Date of Examination: Week of Feb. 5, 2001 Examination Level (circle one): RO (_RO Operating Test Number: SRO - 1 Administrative Describe method of evaluation: Topic/Subject 1. ONE Administrativ...

IR 05000409-05-001(DNMS), on 03/29/2005 - 04/01/2005, La Crosse Boiling Water Reactor (LACBWR), decommissioning inspection.

April 8, 2005Mr. W. L. BergGeneral ManagerDairyland Power Cooperative3200 East Avenue SouthP.O. Box 817La Crosse, WI 54602-0817SUBJECT: NRC INSPECTION REPORT 05000409/2005-001(DNMS) -LA CROSSE BOILING WATER REACTOR (LACBWR)Dear Mr. Berg:On April 1, 2005, the NRC completed an ...

Handout 1 - GSI-191 Resolution for Kewaunee Power Station.

GSI-191 RESOLUTION FOR KEWAUNEE POWER STATION1KEWAUNEE POWER STATION – GSI-191 RESOLUTION• KEWAUNEE TELECONFERENCE PARTICIPANTS:• DOMINION:– JACK DILLICH, DIRECTOR NUCLEAR ENGINEERING– MICHAEL L. MILLER, MANAGER NUCLEAR DESIGN ENGINEERING– SCOTT PUTMAN, PROJECT MANAGER– LORI C...

Beaver Valley, Unit 1, Response to Request for Additional Information on ASTRUM Best-Estimate Large-Break Loss of Coolant Accident Methodology License Amendment Request.

FENOC Beaver Valley Power StationN OP.O. Box 4FirstEnergy Nuclear Operating Company Shippingport, PA 15077Paul A. Harden 724-682-5234Site Vice President Fax: 724-643-8069March 8, 2010L-10-045 10 CFR 50.90ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, ...

2011/06/29 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 429, FSAR Ch. 6, Supplement 6

1ArevaEPRDCPEm ResourceFrom: WILLIFORD Dennis (AREVA) [Dennis.Williford@areva.com]Sent: Wednesday, June 29, 2011 1:47 PMTo: Tesfaye, GetachewCc: BENNETT Kathy (AREVA); DELANO Karen (AREVA); ROMINE Judy (AREVA); RYAN Tom (AREVA); GUCWA Len (EXTERNAL AREVA)Subject: Response to U...

DTE Energy - Detroit Edison Fermi 3 COLA (Final Safety Analysis Report), Rev. 2 - Chapter 06 - Engineered Safety Features

6-1 Revision2March 2010Fermi 3Combined License ApplicationPart 2: Final Safety Analysis ReportChapter 6 Engineered Safety Features6.0 GeneralThis section of the referenced DCD is incorporated by reference with nodepartures or supplements.6.1 Design Basis Accident Engineered Sa...

LER 10-003-00 for St. Lucie, Units 1 & 2 Regarding Unanalyzed Condition Resulting from Alignment of Non-Essential CCW Header Under Certain Accident Scenarios.

0IFPLFlorida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957June 18, 2010L-2010-12710 CFR 50.73U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555Re: St. Lucie Unit I and 2Docket No. 50-335Reportable Event: 2010-003Date of Ev...

NUREG-0800, (106:234) Chpt 6, Section 6.5.1, Rev. 2, ESF Atmosphere Cleanup Systems, to the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants. LWR Edition.

NUREG-0800{Formerly NUREG-75/087)U.S. NUCLEAR REGULATORY COMMISSIONSTANDARD REVIEW PLANOFFICE OF NUCLEAR REACTOR REGULATION6.5.1 ESF ATMOSPHERE CLEANUP SYSTEMSREVIEW RESPONSIBILITIESPrimary - Effluent Treatment Systems Branch (ETSB)Secondary - NoneI. AREAS OF REVIEWAt the cons...

MHI's Responses to US-APWR DCD RAI No. 507-3993, Revision 0.

AkMITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANFebruary 22, 2010Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-10050Subject: MHI's Responses to US-AP...

"Basic Motor-Operated Valve Description & Design Base Info & Bases for Establishing Max Expected Differential Pressures."

ATTACHMENT B iP3-88-004 Basic MOV Description And Design Base Information And Bases For Establishing Maximum Expected Differential Pressures Table 1 - High Head SI Cold Leg Stop Valves Table 2 - SI Pump 32 Suction Isolation Valves Table 3 - Bit Isolation ValvesNew York Power A...