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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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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4.14.1: Inservice Inspection (ISI) Program, Evaluation of Aging Management Programs, 01/25/2006.

Vermont Yankee License Renewal Project Evaluation of Aging Management Programs 4J4.1: Inservice Inspection (Ism) Program .1 LRPD-02 Revision 1 Page 158 of 275 VYNPS License Renewal Project Aging Management Program Evaluation Results lnservice Inspection (ISI) Program 4.1 4.1 l...

Clinton, Unit 1 - CPS/USAR, Chapter 5, "Reactor Coolant System and Connected System," Revision 11.

CPS/USAR CHAPTER 05 5-i REV. 11, JANUARY 2005 CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS PAGE 5.1 SUMMARY DESCRIPTION 5.1-1 5.1.1 Schematic Flow Diagram 5.1-2 5.1.2 Piping and Instrumentation Diagram 5.1-3 5.1.3 Elevation Drawings 5.1 3 5.2...

Response to Portion of NRC Request for Additional Information Letter No. 214 Related to ESBWR Design Certification Application ESBWR RAI Numbers 19.1.0-4 S02 and 19.1-144 S02.

S HITACHI GE Hitachi Nuclear EnergyRichard E. KingstonVice President, ESBWR LicensingPO Box 7803901 Castle Hayne Road, M/C A-55Wilmington, NC 28402 USAT 910 675 6192F 910 362 6192rick.kingston@ge.comMFN 06-442, Supplement 2 Docket No. 52-010October 1,2008U.S. Nuclear Regulator...

Final Outlines (Folder 3)

UNIT 1 NRC (RO) ES-401 BWR Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 1 Date of Exam: March 12, 2007 Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (i e., except for one categor...

Calculation No. 000-PSA-MGR0-00900-000-00B, "Intra-Site Operations and BOP Reliability and Event Sequence Categorization Analysis," Attachment A, Page A-39 through Attachment B, Page B1-14.

Intra-Site Operations and BOP Reliability 000-PSA-MGRO-00900-000-00B and Event Sequence Categorization Analysis Table AS-1. Correspondence between Event Trees and ESDs (Continued) ESD# ESD Title IE Event Tree Name IE Event Tree Location Response Tree Name Response Tree Locatio...

Fort Calhoun-2009-03-Final Written Exam - Site-Specific RO and SRO Written Examinations.

ES-401, Page 30 of 33ES-401 Site-Specific RO Written Examination Form ES-401-7 |Cover SheetU.S. Nuclear Regulatory CommissionSite-Specific RO Written Examination |Applicant InformationName:Date: Facility/Unit:Region: I II III IV | Reactor Type: W CE ...

Beaver Valley, Units 1 & 2, Reply to Follow-Up Questions Pertaining to Request for Additional Information Regarding Severe Accident Mitigation Alternatives for License Renewal.

FENOCFirstEnergy Nuclear Operating CompanyKevin L. Ostrowski 724-682-7773Director, Site OperationsMay 2, 2008L-08-148 10 CFR 54ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001SUBJECT:Beaver Valley Power Station, Unit Nos. 1 and 2BV-1 Dock...

Beaver Valley, Units 1 and 2, License Renewal Application Audit Report.

November 5, 2008 Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB-1 P.O. Box 4, Route 168 Shippingport, PA 15077 SUBJECT: AUDIT REPORT REGARDING THE BEAVER VALLEY POWER STATION, UNIT 1 AND 2, LICENSE...

Event Notification Report for February 13, 2024: 56959

Power Reactor Facility: Hatch RX Type: [1] GE-4,[2] GE-4 Emergency Class: Non Emergency
Event Text PRIMARY CONTAINMENT DEGRADED The following information was provided by the licensee via email: "At 1011 EST on 02/11/2024, during a refueling outage at 0 percent power, while performing local leakage rate testing (LLRT) of the feedwater check valves [part of the con...

Event Notification Report for September 29, 2023: 56759

Power Reactor Facility: Monticello RX Type: [1] GE-3 Emergency Class: Non Emergency
Event Text EN Revision Imported Date: 9/28/2023 EN Revision Text: ACTUATION OF REACTOR PROTECTION AND CONTAINMENT ISOLATION SYSTEMS The following information was provided by the licensee via fax: "[On 09/27/2023] at 1041 CDT, with the plant at 75 percent power and main turb...

Notice of violation from insp on 890417-21 & 27.Violation noted:no tests performed after unit shut down in Aug 1988 & before repairs done in Sept 1988 in order to determine amount of leakage rate improvement prior to Type A test.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ __- -_ __--- - - .- . __. - _ - - .__ ____ _ - -- .. .;. ."'.NOTICE OF VIOLATIONoNorthern States Power Company Docket Nos. 50-282; 50-306As a result of the inspection conducted on April 17-21, and 27, 1989, and'inaccordance with 10 CFR Part 2, Appen...

Forwards safety evaluation re lift of I-beam over exclusion area inside facility containment.Concludes that proposed activities can be accomplished w/o significant risk to health & safety of public.Svc list encl.

- - _ _ _ _ _- .DISTRIBUTION:'*[Central FileDN 50-320NRC .& LocL1 PDR'sTMI HQ r/fAugust 5, 1987TMI Site r/fNRC/THI 87-059AD/ Region I Bruce BogarLChandlerSLewisEJordanJPartlowDocket No. 50-320FSchroeder|WDTraversMTMasnikMr. F. R. StanderferJAThomasVice Pres % nt/ Director, TMI...

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 02 Figure 2.4.2-202

E 1,850,000E 1,848,000E 1,846,000E 1,844,000RAILROADCOOLINGTOWERAREAE 1,846,000E 1,844,000N 1,168,000N 1,166,000N 1,164,000E 1,850,000E 1,846,000E 1,844,000DAMHOLD-UP POND APONDDAMFENCEWAREHOUSE-2WAREHOUSE-1PLANTACCESSPORTALTOSECURITYTRAININGAREAFUTURE DRYCASK STORAGE AREA400 ...

Fort Calhoun Station Response To Notice Of Violation NRC Inspection Report 05000285-14-002.

May 8, 2014 EA-14-037 Louis P. Cortopassi, Site Vice President Omaha Public Power District Fort Calhoun Station FC-2-4 P.O. Box 550 Fort Calhoun, NE 68023-0550 SUBJECT: RESPONSE TO NOTICE OF VIOLATION AND NRC INSPECTION REPORT 05000285/2014002 Dear Mr. Cortopassi: On...

APR1400-E-P-NR-13003-NP, Rev. 0, Appendix-B, "Severe Accident Analysis Report for MCCI," Page B-44 through Page B-48.

KEPCO & KHNP SEVERE ACCIDENT ANALYSIS APR1400-E-P-NR-13003-13 KEPCO & KHNP B-44 Figure 3-21: Pressure in containment...

Responds to IE Bulletin 80-16 re Rosemount,Inc pressure transmitter.Pressure transmitter PT-950A subj to exposure of 140% input resulting in anomalous output signal has no safety-related function.Corrective actions not required.

Carolina Power & Light Co pany4 NTA, GH July 29, 1980 0AUG 1 All : 1b FILE: NG-3513 SERIAL: NO-80-1102 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, GA 30303 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. ...

Diablo Canyon, Units 1 & 2, Amendment No 149 & 149, Technical Specifications re: elimination of post accident sampling requirements.

Programs and Manuals 5.55.5 Programs and Manuals (continued) 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious tr...

Nine Mile Point Unit 1 Supplement to special Report Dated November 2, 2000.

Niagara MMohawk®March 16, 2001NMP1L 1569U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555RE: Nine Mile Point Unit 1Docket No. 50-220DPR-63Subject: Supplement to Special Report Dated November 2, 2000Gentlemen:In Niagara Mohawk Power Corporation'...

PNO-I-00-024, Oyster Creek - Technical Specification Required Shutdown.

DCS: 05000219081500Date: 08/15/00PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-I-00-024This preliminary notification constitutes EARLY notice of events ofPOSSIBLE safety or public interest significance. The information is asinitially received without verificatio...

Proposed tech specs change request 189,Rev 0,changing definition of channel calibration to address alternate techniques for instrument channels w/resistance temp detectors & thermocouple sensors.

. _ _ . ,- _ . _ _ - . - _ _ _ . _ . _-. -,[DEFINITIONS-". * E__.REPORTABLE EVENT:17AL REPORTABLE- EVENT shall be_ one of those conditions specified in--Section 50.73 to 10 CFR Part 50..CONTAINMENT'lNTEGRITY:-1. _8CONTAINMENT INTEGRITY shall exist when:a.. All penetrations req...

Forwards licensee response to NRC GL 96-06.

. _ . . _ _ ._ _ .. . . _ . _ . _ _ _ ._- . _ _ ...__-_ _ . . . .;FromPAUL BLANCH To:JZ ,|Date 1/23/97 5:21pm|Subjects Bridge for sale!John:'I have to give them credit for creativity. Because we haveleakage, whichwas not part of the design, we have integrity.iMaybe we don't n...

Interim deficiency rept re failure of flow switches FIS-68-53 & FS-68-66.Initially reported on 730508.Glass graduated flow tubes & glass windows on flow switches found broken after integrated leak rate test completed.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ --O . y . . ._. . " ; O , +, .,_ , , - -, , , .^. , . _ _ . _ - _ . . ., .. s ,.."--a .. wE.~ _1x,..p.* e/I.rW' +>June 6, 1973 ., ,,. ,.4- . .*'_ ,.-i ., s.iMr. F. E. Krucci, DirectorDirectorate of Regulatory OperationsU.S. Atomic ...

Responds to NRC request to review applicability of Reg Guide 1.106, "Thermal Overload Protection for Electric Motors on Motor Operated Valves," for new valves resulting from NPSH mods.

.. __\*..e . p'Af(412) 456-6000435 $ ism Avemii"#'"^August 6, 1980Director of Nuclear Reactor RegulationUnited States Nuclear Regulatory CommissionAttn: Mr. Steven A. Varga, ChiefOperating Reactors Branch No. 1Division of LicensingWashington, DC 20555Reference: Beaver Valley P...

Provides proposed resolution of hydrogen monitor sampling problem,per Item II.F.1 of NUREG-0737.Redundant sample line will be installed to monitor torus atmosphere for hydrogen concentration.

.. . .. . . . .. . _ - - - _ - _ _ - _ - - _ - - - - _ _ _ _ _ - _ - _ _ _ _ _ _ - _ _|-|.123 Main Street.,White Plains, New Wrk 13301,~' *914 0616240...A NewYorkPower.aesac.o ea.4# Authority fl%20f"'January 3, 1991JPN-91-001U.S. Nuclear Regulatory CommissionATTN: Document Con...

Submits supplemental response to NRC Bulletin 90-001, "Loss of Fill-Oil in Transmitters Mfg by Rosemount." Suspect lots of transmitters & schedule for replacement provided.

_ - _ _ _ . _ _ _ _ _ - _ _ _ . _ _ . _ _ _ _ _ _ - - _ _ _ - _ - _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ - _l*i,! B ALTIMORE i'OAS AND *ELECTRIC,CHARLES CENTER e P.O. BOX 1476 e BAL.TIMORE, MAR.YLAND 21203 1475JGromot C CRttL'viet Paanothe; Nveta an r ...