Report a Safety Concern
Search

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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Virgil C. Summer, Unit 1, Response to NRC Request for Additional Information License Amendment Request - LAR 13-00705, Technical Specification Change to Extend Integrated Leak Rate Test Frequency to 15 Years.

Thomas D. GatlinVice President, Nuclear Operations(803) 345-4342A SCANA COMPANY September 5, 2013RC-13-0135U. S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555-0001Dear Sir/Madam:Subject: VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1DOCKET NO. 50-395O...

FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 110 - Partial, Group - BS. Part 1 of 3.

-OF-FICIAL USE ON'YEarthquake/Tsunami Status Update March 15, 2011 1910 EDTUSNRC Emergency Operations Center Status UpdateMarch 15, 2011Earthquake / Tsunami Status UpdateCompiled by Executive Briefing TeamCaution - This information may be dated and is subject to constantchange...

Nine Mile Point Nuclear Station Unit No. 2, Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit.

Ken Landgon P.O. Box 63Vice President-Nine Mile Point Lycoming, New York 13093315.349.5200315.349.1321 FaxCENG.Ma joint venture of0 Constellation *.J9-eDFwEnergy .0NINE MILE POINTNUCLEAR STATIONJune 1, 2012U.S. Nuclear Regulatory CommissionWashington, DC 20555-0001ATTENTION: D...

2013 Clinton Power Station Initial License Examination Proposed SRO Written Examination.

EXAMINATION ANSWER KEY ILT12-1 NRC Exam (SRO Portion) CPS OPS ILT EXAM Page: 1 of 118 26 June 2013 1 ID: 812650 Points: 1.00 The unit was operating in Mode 2 with NO LCOs in effect when multiple annunciators were received on 1H13-P877-5060. 1H13-P877 indications are as f...

Forwards response to NRC 921028 & 1116 requests for addl info re emergency response facilities,PZR safety valve discharge,flooding,external flooding,equipment protection, groundwater seepage,design criteria & waterproofing.

,, .,!,Westinghouse Energy SystemsBa 355 ;Electric Corporationmeae ommama is23m55iET-NRC-93-3824 iNSRA-APSI 93-0045 j'Docket No.: STN-52-003February 25,1993Document Control Desk !U.S. Nuclear Regulatory CommissionWashington, D.C. 20555,A'ITENTION: R.W.BORCHARDT|SUBJECT: WESTIN...

Byron Station-Integrated Inspection Report 05000454/2019002 And 05000455/2019002

July 26, 2019 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC Exelon Generation Company, LLC President and CNO Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: BYRON STATION—INTEGRATED INSPECTION REPORT 05000454/2019002 AND 05000455/2019002 De...

Applicant Exhibit A-35,consisting of Rev 0 to Emergency Plan Implementing Procedure EP-C-326, "Procedures for Estimating Core Damage During Accident Conditions," dtd 840321.

Awt.Ex.35,-^~U.S. NUCLEAR RECULATORY COMMISS10H d"'':'4#EXHIBIT No. '8{~+BocMtT MUMetaPit 00. si uTIL FAc..d},h -gML Applicant' Staff Intervencr EP-C-326 Rev.0~..r3/21/84identified Received ' RciectedPage 1 of 4' gg jgDate-#/- 3 - FV MJMilmd----w'//[Reporter:p- .>*.p.-.,.._>--...

Quad Cities Nuclear Power Station, Units 1 and 2 - Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 December 13, 2018 SUBJECT: QUAD CITIES NUCL...

Discusses 940527,0616 & 0701 confirmatory action ltrs which confirmed util commitment to address four items prior to restart of station.

- - _ - - - _ _ _ _ _ _ _ _ - - - - _ _ - _ . - _ _ . _ _ - _ - - - - _ _ - _ _ - - _ _ _ - _ . . _ - . . - _ _ - _ _ _ _ _ --, .COOPER NUCLEAR STATEWAP.O. BOX 98. BROWNVLLE, NEBAAEA 68321Nebraska Public Power District *WAE""NLS940001July 28, 1994)!1

Braidwood Station, Units 1 and 2 - Issuance of Amendments Nos. 218 and 218 Re: Revision of Technical Specifications For the Ultimate Heat Sink (EPID L-2020-LLA-0159)

September 24, 2020 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2, - ISSUANCE OF AMENDMENTS NOS. 218 A...

Rev 4 to EOP-14, "Emergency Operating Procedure Enclosures."

fIiDt,vent Transmittal #: 97568 Date: 6/20/98/%+ i, (vTc:NRC (DC DESK)MAC: N/ADestination: Description:jCopy Copy TotalsiDocument: Revision:Comment: # INFO CNTL MSTREOP0014 047 1 0 0Ii.1I1-|1LJInstructions to the Addressee-1iPinse venfy the document (s) received agrees with th...

"1998 Third Quarter 10CFR50.59 Rept," for Dresden Nuclear Power Station of completed changes,tests & experiments.

.- .. . . - .- --. . .- - . - .1-, .,110 CFR 50.59Quarter: 1998-03Safety Evaluation Summary Report||Safety Evaluation Number; 1996-02-128 Type of Safety Evaluation: MiscellaneousjEvaluation Reference Number: Calc. No. 9389-04 02-SW, Sec.Title:Untracked Loads on the LPCI Comer ...

Safety evaluation re amend to license DPR-59 to revise TS Tables 3.2-2 & 4.2-2.

. .. .. __-_________-__ __;,.* ,Attachment IV..SAFETY EVALUATION- CORE AND CONTAINMENT COOLING SYSTEMINITIATION AND CONTROL INSTRUMENTATION(JPTS-%002)00.~[New York Power AuthorityJAMES A. FITZPATRICK NUCLEAR POWER PLANTDocket No. 50-333DPR-599802200246 980206*PDRADOCK 05000333...

"Detailed Comments on NRC Draft Risk-Informed Regulation & Guidance Documents," NUREG-1602.

_ _ - - _ - - _ .APPENDIX A'DETAILED COMMENTS ON NRC DRAFT RISK-INFORMEDREGULATION AND GUIDANCE DOCUMENTS'GE BWR OWNERS' GROUPINTEGRATED RISK BASE REGULATION COMMITTEESEPTEMBER 1997-'*9710010272 970929PDR TOPRP ENVQENEC PDR' Most of these comments are based on the March 1997 i...

LaSalle,Units I and 2 - Response to Request for Additional Information License Amendment Request for Power Uprate Operation

( omllillOm,\,a't';lh Edlison (,lllpaililN LaTallec Generating Statioll 2601 North 21 st Road Mar'sc-itl-s, 11, 61 3,j 1-975Tel 815-.5 (-67 61 CorEd February 23, 2000 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle C...

LaSalle County Station, Units 1 and 2 updated final safety analysis report.

:(t)1,mnonv,wcalthi Edison Conipany LaiSallC (cfncratiflg Station 260t North 21st Road Marseilles, 11 613 i41-9757 Tel 8 !5-357-6761 CorEd April 7, 2000 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, ...

Letter forwarding amend 146 to Facility Operating License NO. DPR-53 for Calvert Cliffs Nuclear Power Plant Unit 1.

Sept,!oer 18, 1990Docket No. 50-317 Distribution: Docket rile GHill(4) PDI-1 RF Wanda Jones NRC/Local PDRs JCalvo SVarga ACRS(10) Mr. G. C. Creel RWessman GPA/PA Vice President - Nuclear Energy CVogan OC/LFMB Baltimore Gas and Electric Company DMcDonald OGC Calvert Cliffs Nucl...

R.E. Ginna Nuclear Power Plant, Amendment 11, Approve Changes to Technical Specifications Relating to Overpressure Protection System Operability

"- JUL ' 0 198 5Docket No. 50-244Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas & Electric Corporation 89 East Avenue Rochester, New York 14649 Dear Mr. Kober: SUBJECT: SEP RELATED TECHNICAL SPECIFICATIONSRe: R. E. Ginna Nuclear Power PlantThe C...

Oyster Creek - Technical Specification Change Request No. 287 Regarding Suppression Chamber to Drywell Vacuum Breakers.

AmerGen AmerGen Energy Company, LLC An Exelon/British Energy Company Oyster Creek US Route 9 South P.O. Box 388 Forked River, NJ o8731-0388 10 CFR 50.90 September 19, 2001 2130-01-20107 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Su...

Rev 34 to EI-1, "Emergency Classification & Actions."

Date Entered: Jul 28, 2000TO:TRANSMITAL NUMBR 51 Ea59 16PROCEDURE NUMBER: El-1 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL. Action Required Sec...

Inservice Inspection Summary Report of Twelfth Refueling Outage Activities for Davis-Besse, Unit 1

FirstEnerDafvs-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, Ohio 43449-9760Guy G. Campbell 419-321-8588 Vice President- Nuclear Fax: 419-321-8337 Docket Number 50-346 License Number NPF-3 Serial Number 2669 August 22, 2000 United States Nuclear Regulatory C...

Edwin I. Hatch, Unit 1, Amendment No. 137, modifying TSs to permit hydrostatic and leak testing with non-critical reactor core.

May 26, 1987Docket No.: 50-321Mr. James P. O'Reilly Senior Vice President - Nuclear Operations Georgia Power Company P. 0. Box 4545 Atlanta, Georgia 30302 Dear Mr. O'Reilly: Subject: Issuance of Amendment No.137 to Facility Operating License DPR-57 - Edwin I. Hatch Nuclear Pla...

Brunswick Units 1 & 2, License Amendments 23 & 47, Changing Technical Specifications to Establish Revised Safety & Operating Limits for Operation in Fuel Cycle Number 2.

APR I L 6 1979147r0.A.Jones Executive Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Dear Mr. Jones:Di stri bution to Docket ORB #3 NRR Reading Local PDo NRC PDR HDenton VStel lo BGrimes TJCarter RVolImer 14Ru5sel 1 SSheppar...

Proposed tech specs re revision to TS Administrative Controls section 6.1.F.1 stating that either 8 or 12 h shifts will be considered "normal" & 40 h will be considered "nominal."

|!<;'Exhibit BMonticello Nuclear Generating Plant-License Amendment Reauest Dated Auaust 15.1996Technical Specification Pages Marked Upwith Proposed Wording Changes||Exhibit B consists of the existing Technical Specification pages marked up with ithe proposed changes. Existing...

Insp repts 50-456/96-11 & 50-457/96-11 on 960615-0726. Violations noted.Major areas inspected:operations, maintenance,engineering & plant support.

_ > . _ _ . _ _ . . ._ _ - . _ . _ . -~ _ _ - _ . _ . _ _ . . . _ .,U.S. NUCLEAR REGULATORY COMMISSION,REGION IIIDocket Nos: 50-456, 50-457License Nos: NPF-72, NPF-77;!Report No: 50-456/96011; 50-457/96011Licensee:Commonwealth Edison (Comed)Facility: Braidwood Nuclear Plant, U...