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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Responds to inquiry to Congressman M Synar & follows up 870821 telcon re contamination of residence during 860104 release of U hexafluoride from facility.Soil & vegetation sampling results discussed.

L{QAW1f0f-tfDL |' "SEP 101987jjIJIMrs. Janice E. Tyler-P. O. Box 482Vian, Oklahoma 74962Dear Mrs. Tyler:This is in response to your telephone inquiry to Congressman Mike Synar and ajfollowup to our telephone conversation of August 21, 1987. ;From your description of the locati...

South Texas Project Units 3 & 4 COLA (Environmental Rpt), Rev. 2 - Chapter 01 - Environmental Report- Methodology- Section 1.3S- Pages 1-4

Methodology 1.3S-1STP 3 & 4 Environmental Report1.3S MethodologyFor COL applications that do not refer to an early site permit, NRC regulations under 10 CFR 52.79(a)(2) require an Environmental Report (ER) be prepared in accordance with the provisions of Subpart A of 10 CFR P...

Agenda - 168th ACNW Meeting, March 22-24, 2006

March 1, 2006 AGENDA168th ACNW MEETINGMARCH 22–24, 2006WEDNESDAY, MARCH 22, 2006, COMMISSIONERS' CONFERENCE ROOM (O-1G16), ONEWHITE FLINT NORTH, ROCKVILLE, MARYLAND1) 8:30 - 8:45 A.M. Opening Remarks by the ACNW Chairman (Open) (MTR/JTL)The Chairman will ma...

South Texas Project Units 3 & 4 COLA (Environmental Rpt), Rev. 5 - Chapter 01 - Introduction - Section 01.03S Methodology

Methodology 1.3S-1STP 3 & 4 Environmental Report1.3S MethodologyFor COL applications that do not refer to an early site permit, NRC regulations under 10 CFR 52.79(a)(2) require an Environmental Report (ER) be prepared in accordance with the provisions of Subpart A of 10 CFR P...

Draft Revision 1, Appendix 9, Assessment of Heavy Loads.

Ge rge Hubbard - loaadrop?.wpa page 1 1 Appendix 9 Assessment of Heavy Loads A heavy load drop onto the spent fuel pool wall, or into the spent fuel, can affect the structural integrity of the spent fuel pool. A loss-of-inventory from the spent fuel pool could occur as a resul...

Y020030032 - Thomas Poindexter Ltr re NRC Staff's Response to Task Interface Agreement 2002-02.

TAO 4:ORIGINAL DUE DT: 03/31/03 T: Thomas PoindexterTICKET NO: 020030032 DOC DT: 01/29/03 NRR RCVD DATE: 02/06/03Tad MarshFOR SIGNATURE OF :DESC:** YEL **ROUTING:NRC Staff's Response to Task Interface Agreement 2002-02ASSIGNED TO: DLPMCollins Borchardt Sheron Case NRR Mailroom...

Encl to E-Mail - from GF Eckholt transmitting Draft High Burnup AMP version 2014 06 12 re Prairie Island LRA for Public Meeting 6/16/2014 (Docket 72-10) TAC L25492.

Page 1 of 10 A3.0 HIGH BURNUP FUEL MONITORING PROGRAM The Prairie Island ISFSI provides for long-term dry fuel interim storage for High Burnup spent fuel assemblies, i.e., fuel assemblies with discharge burnups greater than 45 GWD/MTU, until such time that the spent fuel ass...

Davis-Besse Nuclear Power Station, Unit 1, Reply to Request for Additional Information re License Renewal Commitment No. 42.

FE NOC™ RrstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor. Ohio 43449 Brian D. Boles 419-321-7676 Vice President. Nuclear May 12, 2017 L-17-158 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: Davis-Besse ...

Audit and Review Report for Plant Aging Management Programs (AMPs) and Aging Management Reviews (AMRs), Browns Ferry Nuclear Plant, Untis 1, 2 and 3 and Memo.

AUDIT AND REVIEW REPORTFORPLANT AGING MANAGEMENT PROGRAMS (AMPs)ANDAGING MANAGEMENT REVIEWS (AMRs)Browns Ferry Nuclear PlantUnits 1, 2, and 3Docket Nos.: 05000259, 05000260, 05000296 April 26, 2005Prepared byBrookhaven National LaboratoryUpton, New YorkContract No. J-3168Prepa...

Licensee statement of matls facts as to which no genuine dispute.* Submits listed concise statement of matl facts.

.7we.I\'k L00CKETEDNovember Qy48bUNITED STATES OF AMERICA'96 NOV 19 P3 :30NUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARDFFICE Cr sEC0F TARY'DOCKETiliG a ELWICElBRAHV!In the Matter of ),~')Docket No. 50-219-OLAGPU NUCLEAR CORPORATION)(Tech. Spec. 5.3....

Responds to 801204 ltr,on behalf of Sensible ME Power,re published remarks by NRC official in support of long-term storage plan at facility.Position reflects generic issue documented in NUREG-0575.

0 M(q|p3p ~I i D ti h Q ? % Vru qM < v ~ - a...s .# ".DI1IBIBUTION:C Docket Files OELD S. HanauerNRC PDRG. Ertter (ED0-09961)D. RossL POR S. Cavanaugh.B. Snyderg 1 0 1981TERA E. Hughes'R. VollmerDocket No. 50-309NSIC M. Stine O T. Murley|ORB #3 RdgP. Kreutzer (3)~ Gray File OR...

E-Mail from R Palla to G Parry re updated writeups on SFP risk comparisons.

,Jason Schaperow- Writepson SFP Risk ComparisonsRobert Palla A)/-/Gareth Parry, Timothy Collins Thu, Aug 31, 2000 8:01 AM Writeups on SFP Risk Comparisons- Pagel1Attached are updated writeups on the risk comparisons. The second attachment addresses comparisons based on transla...

"Response to NRC Staff Question 240.03 Concerning Consequences of Liquid Pathway Releases from Core Melt Accident."

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __|' a1)= . ...) .I--.",L..bR OK O) OOCPDRhA Halliburton CompanyNUS-3910RESPONSE TO NRC STAFF QUESTION 240.03CONCERNING CONSEQUENCES OF LIQUID PATHWAYRELEASES FROM A CORE MELT ACCIDENTPERRY NUCLEAR POWER PLANT.Prepared byLawrence 3. Per...

Calculation No. 200-PSA-RF00-00200-000-00B, "Receipt Facility Reliability and Event Sequence Categorization Analysis", Attachment C, Pages C-33 Though Attachment D, Page D-23.

Receipt Facility Reliability and Event Sequence Categorization Analysis 200-PSA-RFOO-00200-000-00B For a data source providing exposure data (given in the form of a number n of recorded failures over an exposure time t), the likelihood function is a Poisson distribution, expre...

OFFICIAL EXHIBIT - NYS000244-00-BD01 - MACCS2 Computer Code Application Guidance for Documented Safety Analysis, Final Report (DOE-EH-4.2.1.4-MACCS2-Code Guidance) (June 2004) ("MACCS2 Application Guidance").

United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Identified: Admitted: Withdrawn: Reject...

Draft: Sandia National Laboratory (SNL).

Sandia National Laboratory (SNL) Project: SNL is working on a report that willupdate NUREG-0170.Peer review concept: Propose that the Academy (i.e., domestic university) and an expertfrom the international arena perform the peer review of the document generated by SNL.The pers...

Responds to NRC 860314,0417 & 0606 requests for addl info re SEP Topics III-2 & III-4.A.Exposed main steam & feedwater piping will be evaluated for 178 mph tornado.Commitment to listed mods contingent upon acceptance of encl matl.

Telephone (617) CF2-8100TWX 710-3807619YANKEE ATOMIC ELECTRIC COMPANY-.5%b 1671 Worcester Road, Framingham, Massachusetts 01701 DCC 86-134.YANxse2.c2.1-.September 5, 1986FYR 86-084United States Nuclear Regulatory CommissionWashington, DC 20555Attention: Ms. Eileen McKennaPWR P...

Forwards responses to Structural Engineering Branch Series 220 820211 requests for addl info re ability of seismic Category I structures to withstand various pressure loads. Responses to listed requests will be submitted by 820312.

~YtpuBLIC SERVICESEABROOK STATIONaEngineering Office:Companyof New Hampshir e1671 Worcester RoadFrominchom, Mossochusetts 01701(617) - G72 - 8100tMarch 5, 1982#SBN-220%,,'T.F. B 7.1.2C AfO-, ;%OL%~,United States Nuclear Regulatory CommissionWashi ng ton, D.C. 20555 g,'Attentio...

State of Utah proposed corrections to revised transcript of pre-hearing conference.* W/Certificate of Svc.

_-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . _ _ _____; 3. fe[f00CKETEDlUNITED STATES OF AMERICAUSHRC'NUCLEAR REGULATORY COMMISSION16 MAR 23 P3 :05BEFORE THE ATOMIC SAFETY AND LICENSING BOARD;gRYOF Fu) AD...

Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Appendix D - Requirements Resulting from TMI-2 Accident.

CPS/USAR APPENDIX D D-i REV. 11, JANUARY 2005 APPENDIX D REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT TABLE OF CONTENTS ITEM PAGE TMI ACTION PLAN REQUIREMENTS FOR APPLICANTS FOR AN OPERATING LICENSE (NUREG-0737 ENCLOSURE 2) Introduction D-1 I.A.1.1 Shift Technical Advisor ...

Pilgrim, Proposed License Amendment Request to Modify Technical Specification 4.3.4, "Heavy Loads" to Facilitate Dry Storage Handling Operations.

we Entergy Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station600 Rocky Hill RoadPlymouth, MA 02360November 26, 2013U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001John A. Dent, Jr.Site Vice PresidentSUBJECT: Entergy Nuclear Oper...

CSGTR Draft Responses to Public Comments.

November 9, 2016 1 Table of Responses to Public Comments on Draft NUREG-2195 PWROG Public Comment RES Response PUT IN NUREG?A.1 USE OF MELCOR Over the past decade there have been ongoing discussions in the technical community regarding the ability of SCDAP/RELAP5 [1] to mod...

OFFICIAL EXHIBIT - NYS000419-00-BD01 - Revised Statement of Position of the State of New York in support of Contention NYS-12C (Jun. 29, 2012).

UNITED STATES NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD -----------------------------------------------------------xIn re: Docket Nos. 50-247-LR; 50-286-LR License Renewal Application Submitted by ASLBP No. 07-858-03-LR-BD01 Entergy Nuclear India...

TSTF-476 FRN - Notice of Availability of Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding Use of the Improved Banked Position Withdrawal Sequence for General Electric Boiling Water Reactors.

[7590-P]NUCLEAR REGULATORY COMMISSIONNotice of Availability of Model Safety Evaluation and Model License Amendment Request onTechnical Specification Improvement RegardingUse of the Improved Banked Position Withdrawal Sequence for General Electric Boiling Water ReactorsUsing th...

Methodology to Assess the Workload of Challenging Operational Conditions In Support of Minimum Staffing Level Reviews.

Project: Critical Task Identification and Evaluation Methodology (NRC-HQ-25-14-D-0002, Task Order 30) Deliverable: Task 2 Draft Technical Letter Report BNL Technical Report No. 20918-1-2015 Methodology to Assess the Workload of Challenging Operational Conditions In Su...