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NP-PM-0913-4811-NP - Reactor Coolant System, Connected Systems, and Emergency Core Cooling System, October 15, 2013, Cover through Page 57.

NonproprietaryReactor Coolant System, Connected Systems,and Emergency Core Cooling System* Purpose" Plant overview" Background" Design information for select Chapter 5, emergency corecooling system (ECCS) components, and decay heatremoval" NuScale DSRS Chapters 5 and 6 - infor...

Botsford General Hospital's Letter in Response to F. P. D. Tran's Letter Request Additional Information Regarding Request to Change Radiation Safety Officers.

BOTSFORD HOSPITAL October 16, 2013 Frank Tan US NRC 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Re: Control No. 581645 Dear Mr. Tan: The purpose of this letter is to respond to your communication of September 6, 2013 requesting additonal information regarding our req...

NRC Staff's Response to Citizens Awareness Network's Amended Petition to Intervene.

DOCKETEDUrJ 2 'pri1 20, 1998"98 APP 21 P4 :08UNITED STATES OF AMERICA'NUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARDIn the Matter of ))YANKEE ATOMIC ELECTRIC COMPANY ) Docket No. 50-029-LA)(Yankee Nuclear Power Station) )NRC STAFF'S RESPONSE TO CITIZ...

Oconee Nuclear Station, Unit 1, Supplement 1 to Safety Evaluation.

SUPPLEMENT NO. 1TOSAFETY EVALUATIONBY THEDIVISION OF REACTOR LICENSINGU. S. ATOMIC ENERGY COMMISSIONIN THE MATTER OFDUKE POWER COMPANYOCONEE NUCLEAR STATION UNIT 1DOCKET NO. 50-269MAR 2 4 1972TABLE OF CONTENTSP age1.01.22.03.03.13.23.33.44.0INTRODUCTION. . ................ ......

AREVA Design Control Document Rev. 6 - Tier 2 Chapter 05 - Reactor Coolant System and Connected Systems - Section 5.0 Reactor Coolant System and Connected Systems - 5.1 Summary Description

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 6 Page 5.1-15.0 Reactor Coolant System and Connected Systems 5.1 Summary DescriptionThe reactor coolant system (RCS) is a closed, four-loop system designed to transfer heat generated by the reactor core, located in the re...

Email from NRC to ACE re: Smoke Visible From A 3rd Limerick Source - Again (EDATS Region I-2014-0071).

From: Bower, Fred Sent: Monday, March 31, 2014 4:17 PM To: aceactivists@comcast.net Cc: Scott, Michael; Benner, Eric; Noggle, James; Nimitz, Ronald; Furia, Joseph; Barber, Scott; DiPaolo, Eugene; Montgomery, Richard; Pinkham, Laurie; Thompson, Margaret; Screnci, Diane; Sheehan...

Mercy Imaging Services - Rolla, Amendment Request License No. 24-32615-01.

U.S. NRC Region III 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 To whom it may concern, Mercyil=" Mercy Imaging Services -Rolla 1605 Martin Springs Drive, STE 110 Rolla, MO 65401 Ph: 573-458-6610 I 458-6625 Fax: 573-458-6881 We, Mercy Hospital Lebanon Imaging Se...

Sequoyah Nuclear Plant - Offsite Dose Calculation Manual, Revisions 57 and 58.

ENCLOSURE 3OFFSITE DOSE CALCULATION MANUALSEQUOYAH NUCLEAR PLANTREVISIONS 57 AND 58SEQUOYAH NUCLEAR PLANTOFFSITE DOSE CALCULATION MANUALRevision 57Prepared By: George D. FlahertySponsor: Tonev Cross Date: 05/21/2012PORC Review: Coleen Ware Date: 05/23/2012Approval--Plant Manag...

AREVA Design Control Document Rev. 5 - Tier 2 Chapter 05 - Reactor Coolant System and Connected Systems - Section 5.0 Reactor Coolant System and Connected Systems - 5.1 Summary Description

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 5 Page 5.1-15.0 Reactor Coolant System and Connected Systems 5.1 Summary DescriptionThe reactor coolant system (RCS) is a closed, four-loop system designed to transfer heat generated by the reactor core, located in the re...

08/12/2013, Industry Slides Re: Comments on NEI 13-021 Rev. 2.

Review of NRC 08-02-13 Comments on NEI 13-02 Section 1, 2, 4, 5 and 6August 12, 2013 August 12, 20131Objectives ObjectivesReview of Comment Resolution Review of Comment Resolution– Listing of Accepted CommentsCursory Review of Proposed Alternatives – Cursory Review of Propo...

ER 05000341-13-301(DRS); 09/09/2013 - 09/24/2013; Detroit Edison Company, Fermi Power Plant, Unit 2, Initial License Examination Report.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 October 29, 2013 Mr. Joseph Plona Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI ...

Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual.

BYRON - UNITS 1 & 2 Revision 81Technical Requirements Manual1AFFECTED PAGE LIST - TECHNICAL REQUIREMENTS MANUAL1.0 USE AND APPLICATION1.1-1 ........................................ Revision 11.1-2 ........................................ Revision 751.1-3 .........................

609269 Outgoing Amendment No. 20 for Mid-America Isotopes, Inc. to License No. 24-26241-01MD.

--NRC FORM374 U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE PAGE 1 OF 7 PAGES Amendment No. 20 Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 3...

Children's National Medical Center, License Amendment No. 53, Control No. 609400.

NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE PAGE 1 OF 6 PAGES Amendment No. 53 Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30...

RCHP Billings - Missoula Road; Amendment Request; License 25-18361-01; Docket 030-14921; Control 610947.

Hill, Carol From: Sent: To: Cc: Subject: Attachments: Carol: Daniel Dugan Thursday, December 20, 2018 4:45 PM Hill, Carol 'Ryan-O'Hara, Kimberly' [External_Sender] Amendment Request Amendment Request Add AU.pdf Please find attached an amendment request to add authorized users...

Proposed Environmental Technical Specifications for St. Lucie Unit No. 1.

,eNRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL(TEMPORARY FORM)CONTROL NO:F I LE'NVIROFRQM:Florida Power & Light CMiami, Fla. 33101R.E Uhri~ DATE OF DOC9-2-75DATEREC'D LTR9-5-75TW)( RPT OTHE RTO:Mr. Daniel R. MullerCLASS UNCLASS PROPINFOXXXORIG1 signedINPUTCC OTHERNO CYS REC'D1...

NuScale Power, LLC Supplemental Response to NRC Request for Additional Information No. 356 (eRAI No. 9253) on the NuScale Design Certification Application.

September 19, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 RAIO-0918-61868 Docket No. 52-048 SUBJECT: NuScale Power, LLC Supplemental Response to NRC Request for Additional Information N...

Application for amend to license NPF-62,revising TS 3/4.6.6.3, "SGTS" & 3/4.7.2, "CR Ventilation Sys" to update rev of ASTM std utilized to periodically perform lab testing of charcoal adsorber samples.

1| mas Power CornpanyChnton Power etcon')'=P O. Box 670Chrsan,IL 61727Tol 217 950801. Ext 32C0,John G. CookV

Forwards CH Bell 810515 ltr to DOE re delays in facility restart.NRC considered responsible for delay in startup.DOE 810604 response encl.

C...'4 *<%.fdim sDepartment of EnergyJUn,,4 1981Washington, D.C. 20545Mr. William DircksExecutive Director for OperationsU.S. Nuclear Regulatory CommissionWashington , D.C. 20555Dear Mr. Dircks:The enclosed correspondence has been direc '.cd to the Department of Energy.The con...

LER 93-003-00:on 930216,discovered that portion of CS sys channels between process instrumentation & ESFA not properly performed due to deficient written communication.Procedures revised to include circuit continuity checks.W/930317 ltr.

".- v ..,Il.I.|'' Dake f%utr Company(FW) MiJ000 .Catawba kckarStatwn ih4R00 Concord Rd)brk,S C 29745|;DUKEPOWERMarch 17,1993|.!-!Document Control DeskU. S. Nuclear Regulatory Commission !'Washington, D.C. 20555!Subject: Catawba Nuclear Station'Docket No. 50-413LER 413/93-003Ge...

Responds to exercise weakness noted in NRC insp rept 50-458/93-01 on 930224.C/As:procedures will be reviewed to locate any possible problem area that could be used to issue NMF when significant changes in emergency condition warrant.

- __ _-. . . _. __ _ _ _ _ _;'-.I-t*GULF STATES UTILITIESCOMPANY,nua ntso stuospost omet sox m sryarmasvue touis>4~* 7077s!'ARE A Cor>E S04 635 6094 346 BESt.!April 12,1993|RBG- 38327jFile Nos. G9.5, G15.4.1iU.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D....

Forwards document list referred to in intervenors' 710610 ltr.List is not exhaustive of intervenors' evidentiary matl.

_ _ __ _ - g_w --. _;_~~,_s -1OCT NUMBER'PROD. & uTR, EAC. (C M9,9981iMcDEnxoTT. WILL & EMERYCDlli WEST MON ROC STREETf" SCHICAGO, ILLINOIS 60603S000XEfED 9,,,,,aa~ a u s a-ac corJECcaste 4ocacss-5JUN 1 ? 1971 * 31Juno l$, 1971witA<(w:a n .:.,w e. ~ . , .9 usuec;w-4 'THis DOCU...

Forwards SSAR markups addressing DFSER Confirmatory Items 6.2.5-1,6.2.5-2 & Open Item 20.3-10.Requests that copy of transmittal be provided to G Gou.

'e >_;.' GENuclear Energycenew ormr cocvun775 Ce:v Awwe Sr.b5n CA %125,April 2,1993 Docket No. STN 52-001,Chet Poslusny, Senior Project ManagerStandardization Project DirectorateAssociate Directorate for Advanced Reactorsand License RenewalOffice of the Nuclear Reactor Regulat...

Application for amend to License NPF-3,changing frequency requirements in TS 1.32,3.3.3.9,3.11.1,6.5.1.6,6.9.1.11 & 6.15 re radioactive effluent release rept & TS re notification to NRC of SG tube insp Category C-3 results.

. _ _ _ - . _ . . _ _ _ _ _ . . . . _ _ . _ m . _ , __.tDocket Number 50-346..License Number NPF-3!'.Serial-Number 2130 | ..,Enclosure |Page 1!!Ii||APPLICATION FOR AMENDMENT].iTO!FACILITY OPERATING LICENSE NUMBER NPF-3 |IDAVIS-BESSE NUCLEAR POVER STATION i!UNIT NUMBER 1jitIrAt...

TS Change Request 224 to License DPR-50,requesting change to low limit of exhaust flow of auxiliary & fuel handling bldg ventilation sys & deletion of several refs to Flow Recorder (FR-151) as monitoring device.

,_. _ . _ . _ _ - _ _ __ _ . _ . -,3' 'METROPOLITAN EDISON COMPANY .'JERSEY CENTRAL POWER & LIGHT COMPANY||AND iPENNSYLVANIA ELECTRIC COMPANY,!'THREE MILE ISLAND NUCLEAR STATION, UNIT 1|:i.!iOperating License No. DPR-50Docket No. 50-289!Technical Specification Change Request N...