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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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RO:on 721020,boot seal on air operated reactor bldg to suppressio chamber vacuum breaker valve found depressurized. Caused by excessive clearance between actuating arm & valve. Procedural changes being initiated.

'.. . . . . ._ --\|h( W h d"$Ab8--d~~DTEGNORTMERN STATES POWER C O M P A'N YMinneapolis, Minnesota55401.Evember 15, 1972.,., .-/y"%;Mr. A. Giambusso,,Deputy Director for Reactor Projects?, ,'5:iUnited States Atomic Energy Connisaien itWashington, D. C.20545Dy.Dear Mr. Giambuss...

LTR-19-0192 Tom Gurdziel, E-mail re: 31 Vogtle 3 & 4 April 2019 Pictures

CHAIRMAN Resource From: Sent: To: Tom Gurdziel Tuesday, May 07, 2019 9:37 PM techols@psc.state.ga.us Cc: Subject: Bridget Frymire; 'Ed Stronski'; Esberg, John R:(GenCo-Nuc); Screnci, Diane; CHAIRMAN Resource [External_Sender] 31 Vogtle 3 & 4 April 2019 Pictures Hi Tim, I enjo...

Forwards "Determination of Ignition Performance Characteristics of Glow Plug Hydrogen Ignitor," conducted by Fenwal Corp.Tests constitute Phase 1 of glow plug ignitor performance tests.Complete results will be sent by 801201.

- - - -,.,.0TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 37401400 Chestnut Street Tower II~"November 13, 1980-3Be MDirector of Nuclear Reactor RegulationI65eQ-Attention W. A. Schwenoer, Chief ._,q,Licensing Branch No. 2'22%,2b'Division of Licensing-_m"U.S. Nuclear Regulato...

Notice of violation from insp on 851223-860103.

._ - -. - _ - _ _ . . - . _ _ _ . - - . --_.=!i!-ii'i!APPENDIX'ANOTICE OF VIOLATIONiPublic Service Electric & Gas Company Docket No. 50-354Hope Creek Generating StationLicense No. CPPR-120!i During an inspection from December 23, 1985 to January 3, 1986, and in accord-ance wit...

LAR-72 Proposed Changes and Supporting Engineering Documentation, Revision 1.

May 6, 2014 LAR-72 proposed changes and supporting engineering documentation: • Connection between Faceplate and Base Concrete – Allows for flexibility in attaching modules to the base concrete. o APP-CA05-S3C-001- CA05 Connection Design: Module Wall to Reinforced Concrete  ...

Proposed Tech Specs allowing reactor water level or drywell pressure instruments to be removed from svc during outages for maint & testing.

Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation And Standby Gas Treatment System InitiationI-A 00cr 00 000Dn 04hu(1) There shall be two operable or tripped system and there shall be one operable per trip system.trip systems for each function w...

Results of Periodic Review of RG 1.63.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 25, 2017 MEMORANDUM TO: Brian E. Thomas, Director Division of Engineering Office of Nuclear Regulatory Research FROM: Ian C. Jung, Chief /RA/ Instrumentation, Controls, and Electrical ...

2013/03/01 - Comment (2790) Form E-mail regarding GE Reactors LTR-12-0782

1SECYLettersCEm ResourceFrom: Henry Lyman [henrylyman@yahoo.com]Sent: Friday, March 01, 2013 6:36 PMTo: NRCExecSec ResourceSubject: Radiation filter requirementChairwoman Allison M. Macfarlane Commissioner Kristine L. Svinicki Commissioner William D. Magwood IV Commissioner Wi...

Press Release-IV-13-007: NRC to Hold Public Meeting to Discuss Fort Calhoun Nuclear Plant.

No. IV-13-007 Contact: Victor Dricks (817) 200-1128 Lara Uselding (817) 200-1519 March 7, 2013 E-Mail: OPA4.Resource@nrc.gov NRC TO HOLD PUBLIC MEETING TO DISCUSS FORT C...

Toshiba Design Control Document Rev. 1 - Tier 2 - Chapter 21 - Engineering Drawings - Chapter 06 Drawings

21-159RS-5146900 Rev. 1Design Control Document/Tier 2 ABWRFigure 6.2-38 Plant Requirements, Group Classification and Containment Isolation Diagram (Sheet 1 of 2)21-160RS-5146900 Rev. 1Design Control Document/Tier 2 ABWRFigure 6.2-38 Plant Requirements, Group Classification ...

Informs that 980320 ltr incorrectly identified LER number as LER 311/98-007-00 instead of LER 272/98-007-00.Ltr w/ original LER being submitted to correct administrative oversight.

e ·O·ps~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAY O 5 1998 LR-N980233 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: LER 272/98-007-00 SALEM GENERATING STAT...

Responds to NRC 790705 ltr re violation noted in IE Insp Repts 50-250/79-20 & 50-251/79-20.Corrective actions: contaminated hose relocated,dose rate reduced to allowable level & health physics shift supervisors cautioned.

P.O. BOX 529100, MIAMI,FL 33152'ILtSIXIRCR<"'.;-Ii,t TC .',

Application to amend License DPR-18,revising Tech Spec Table 3.5-5 re ESF actuation sys instrumentation trip setpoints in accordance w/NUREG-0737.

UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONIn the Matter ofRochester Gas and Electric Corporation(R. E. Ginna Nuclear Power Plant,Unit No. 1))))Docket No.50-244)APPLICATION FOR AMENDMENTTO OPERATING LICENSEPursuant to Section 50;90 of the regulations of the U.S.Nucle...

Technical Requirements Manual (Unit 1), Revision 3, Change AP-03

Arkansas Nuclear One - Administrative Services Document Control Wednesday, November 01, 2000 Document Update NotificationCOPYHOLDER NO: TO: ADDRESS. DOCUMENT NO: TITLE: REVISION NO: CHANGE NO: SUBJECT.TRM-UI-102 NRC/DOCUMENT CONTROL WASHINGTON, D.C. 20555 TRM-U1 TECHNICAL REQ...

Regulatory Guide 1.196, Control Room Habitability at Light-Water Nuclear Power Reactor - Pages B-5 & B-6.

Programs and Manuals5.55.5 Programs and Manuals5.5.16 Containment Leakage Rate Testing Program (continued)B-5e. The provisions of SR 3.0.3 are applicable to the Containment LeakageRate Testing Program.f. Nothing in these Technical Specifications shall be construed to modify th...

Press Release-III-97-023 NRC ENFORCEMENT CONFERENCE WITH NORTHERN STATES POWER CO. ON APPARENT VIOLATIONS OF NRC REQUIREMENTS AT MONTICELLO STATION.

U.S. NUCLEAR REGULATORY COMMISSIONRegion III Office of Public Affairs801 Warrenville Road, Lisle, IL 60532-4351NEWS ANNOUNCEMENT: RIII-97-23 March 3, 1997CONTACT: Jan Strasma 630/829-9663Angela Dauginas 630/829-9662E-mail: opa3@nrc.govNRC ENFORCEMENT CONFERENCE WITH NORTHERN S...

Receipt of Proposed Differing Professional View.

UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555-0001February 9, 2004MEMORANDUM TO: Ross LandsmanDivision of Nuclear Materials SafetyRegion IIIFROM: J. E. Dyer, DirectorOffice of Nuclear Reactor RegulationSUBJECT: RECEIPT OF PROPOSED DIFFERING PROFESSIONAL VIEW...

3/23/2010, Conference Call With Transnuclear To Discuss Their Responses To The Staff's Second Round Request For Additional Information Concerning the Model No. TN-40 Transportation Package.

March 23, 2010 NOTE TO: FILE DOCKET NO: 71-9313 SUBJECT: 3/23/2010, 2:00PM, CONFERECE CALL WITH TRANSNUCLEAR TO DISCUSS THEIR RESPONSES TO THE STAFF’S SECOND ROUND REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE MODEL NO. TN-40 TRANSPORTATION PACKAGE. Participant...

Document Drawing 80101381RO H02R1, Salem Auxiliary Feedwater.

C0117,-Co"ý,T.KyI4AFAWA- I I -/ -- ICv.1-vrkDL- AIRREVISE .-. IDE-TAIL ",X," -. (4) REO¶YDLQ. NPWAII-11--/NOTES: T. DRILL ES6' IA HOLE FOR /2" x3" LOTHR'D ROD,DOUBLE NUTTED EACH S2. SHIM AS REO'D.3. COAT U-BOLTS AND BASEPLATE WITHCERAMALLOY CL+AC COATING)All-C',DD PER FCR 6008...

Requests acceptance review of info on radioactive discharges in Suppl 2 to environ rept.

Docket No.50-286 ENVIRGH,OCT 10 1972Robert Tedesco, Assistant Director for Containment Safety, L CONSOLIDATED EDISON COMPANY, INC. - INDIAN POINT UNIT NO. 3 ACCEPTANCE REVIEW OF SUPPLEMENT NO. 2 TO ENVIRONMENTAL REPORT Your assistance is requested to comment on Supplement No. ...

Bellefonte Units 3 & 4 COLA (Final Safety Analysis Report), Rev. 2 - FSAR Chapter 02 Figure 2.5-362

SWAMPEL.603.9'615600605610615610625620620615610605605610615610615610605600600605600615610615615620625640635630640645650655660640600615620625610605630 7307257207157006957057106306356406456506556806856906606656706756957007057107156157657607557507457407357307257207157107056956906...

Request for Documents #3, Millstone PI&R.

>>> Joseph Schoppy 01/07/2008 2:22 PM >>> Gary, Attached is a follow-up request for information for the inspection. If you have any questions or comments please don't hesitate to reply. Please acknowledge receipt of this e-mail. Thanks! Regards, Joe Information Reques...

E-Mail from Carrion to Franke re Status Meeting Conducted by Garry Miller.

Carrion, RobertFrom: Carrion, RobertSent: Thursday, October 29, 2009 8:58 AMTo: Franke, MarkCc: Lake, LouisSubject: statusMarkThe SIT attended the 7:30 status meeting conducted by Garry Miller. Yesterday the focus was be on the baywhere the delamination was originally discover...

Bellefonte Units 3 & 4 COLA (Environmental Report), Rev. 1 - ER Chapter03 Figure 3.1-6

SILT FENCEBRUSHSILT FENCESWAMPSWAMPEL.594.5'EL.603.9'NOTES:VALUES ARE BASED UPON AL EAST STATEPLANE COORDINATE SYSTEM NAD 83.2. EXISTING CONDITIONS AND TOPOGRAPHIC CONTOURSMARCH 26, 2006 PROJECT NO. 060319.3. CONTOUR INTERVAL IS 5 FEET.BASED UPON THE SANBORN MAP COMPANY, INC.1...

Nine Mile, Unit 2, Extension of Ten-Year Program Intervals.

Constellation Energy-Nine Mile Point Nuclear StationP.O. Box 63Lycoming, NY 13093June 15, 2007U. S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Attention:Subject:Document Control DeskNine Mile Point Nuclear StationUnit No. 2; Docket No. 50-4 10Extension of Ten-Year...