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Response to Request for Additional Information for the Consolidated Application to Certificate of Compliance SPEC Model C-1 Transportation Package, Package Identification Number USA/9036/B(U)

RE OF QUALITY February 28, 2001 Mr. Steve O'Conner, Project Manager Licensing Section, Mail Stop 013D13 Spent Fuel Project Office U.S. Nuclear Regulatory Commission One White Flint North 11155 Rockville Pike Rockville, MD 20852 Subject: Docket 71-9036; Response to Request for ...

Cooper Nuclear Station-2015-04-FINAL OUTLINES.

ES-401 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station Date of Exam: February 16, 2015 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G * Total A2 G* Total 1. Emergency & Abnormal ...

FOIA/PA-2015-0205 - Resp 1 - Final, Group B.

GroupFOIA/PA NO: :-2 r 0RECORDS BEING RELEASED IN PARTThe following types of information are being withheld:Ex. 1 :E--i Records properly classified pursuant to Executive Order 13526Ex. 2:D] Records regarding personnel rules and/or human capital administrationEx. 3 :-- Informat...

River Bend Station, Unit 1 - Response to License Amendment Request (LAR) Technical Specification 3.7.7, "Control Building Air Conditioning (CBAC) System" NRC Request for Additional Information (RAI).

• ~. Entergx RBG-47851 March 28, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Entergy Operations, Inc. River Bend Station 5485 U.S. Highway 61 N St. Francisville. LA 70775 Tel 225-381-4374 William F. Maguire ...

Entergy Pre-Filed Hearing Exhibit ENT000193, Entergy Nuclear Operation Inc., Indian Point, Units 2 & 3, Amendment 5 to License Renewal Application (LRA).

ENT000193 Submitted: March 29, 2012'" . ·~·Entergx Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 788-2055 Fred Dacimo Vice President License Renewal June 11, 2008 Re: Indian Point Units 2 & 3 Docket Nos. ...

Attachment 6 - LaSalle County Station Engineering Change (EC) 388666, Revision 0, "Revise Design Analyses for UHS Temperature of 107 'F".

ATTACHMENT 6LaSalle County Station Engineering Change (EC) 388666, Revision 0,"Revise Design Analyses for UHS Temperature of 107 'F"Engineering Change Print Date: 09/13/2012EC NumberStatus/DateFacilityType/Sub-type:0000388666 000REVISED 07/13/2012LASDCR DSGN1111 11111lillilill...

Watts Bar Nuclear Plant, Unit 2, Response to Request for Additional Information Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MD6726).

. VFTennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000September 16, 201310 CFR 50.4610 CFR 50.54(f)U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001Watts Bar Nuclear Plant, Unit 2NRC Docket No. 50-391Subje...

Seabrook, Updated Final Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems, Appendix 3A, Pipe Break Analysis Summary.

SEABROOK UPDATED FSARAPPENDIX 3APIPE BREAK ANALYSIS SUMMARYSEABROOK UPDATED FSARAPPENDIX 3APIPE BREAK ANALYSIS SUMMARYIntroductionThis appendix summarizes the results of the failure mode and effects analysesof breaks in high and moderate energy piping systems.SummaryMain Steam...

Indian Point Station, Unit 2 - Final Outlines Update ES-401-2, ES-401-3.

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: IPEC Unit2 Date of Exam: 10/31/2016 RO K/A Cate:iorv Points SRO-Onlv Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total 1. 1 3 3 3 3 3 3 1B 0 0 0 Emergency & Abnormal 2 2 2 2 N/A 1 2 NIA 0 9 0 0...

Joseph M. Farley Nuclear Plant, Units 1 And 2 - Safety Evaluation Regarding Implementation Of Mitigating Strategies And Reliable Spent Fuel Pool Instrumentation Related To Orders Ea-12-049 And Ea-12-051 (CAC Nos. MF0716, MF0717, MF1429, And MF1430).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. James J. Hutto Regulatory Affairs Director Southern Nuclear Operating Co., Inc. P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295 April 24, 2017 SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - ...

NuScale Power, LLC Supplemental Response to NRC Request for Additional Information No. 71 (eRAI No. 8889) on the NuScale Design Certification Application.

RAIO-0118-58186NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comJanuary 15, 2018 Docket No. 52-048U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockvil...

Palisades Nuclear Plant, Revision 34 to Updated Final Safety Analysis Report, Chapter 1, Tables 1-1 through 1-10.

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT TABLE 1-1 Revision 28 Page 1 of 3 CHRONOLOGICAL LICENSING EVENTS Date Docket 50-255 CPOL Application FSAR Operating License Other June 2, 1966 CP Co Files CPOL Application PSAR Included With Application March ...

Ginna - Post Exam Comments and Technical References (Folder 1).

2018 Ginna Post-Exam Comments and NRC Resolution Index Item 1 Facility Post-Exam Submittal Cover Letter with Comment on a Control Room JPM (2 pages) Item 2 Facility Post-Exam Comments on Written Exam (12 pages) Item 3 Facility Post-Exam Comments and References on #1 Simulator ...

Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, "Reactor Pressure Vessel Water.....

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-19-064 August 8, 2019 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility...

Turkey Point Nuclear Generating Unit No. 3 and 4, Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 12, 2018 Mr. Mano Nazar President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd. Juno Beach, FL 33408 SUBJECT: TURKEY POINT NUCLEAR GENERA...

"SEP Review of NRC Safety Topic VI-10.A Associated W/ Electrical,Instrumentation & Control Portions of Testing of Reactor Trip Sys & Engineered Safety Features,Including Response Time."

ii!Q/fo u. -tUC1D-18698, Vol. II !! ,Ii!iiSYSTEMATIC EVALUATION PROGRAM REVIEW OF}|NRC SAFETY TOPIC VI-IO.A ASSOCIATED WITH THE|ELECTRICAL, INSTRUMENTATION AND CONTROL :PORTIONS OF THE TESTING OF REACTOR TRIP SYSTEM{AND ENGINEERED SAFETY FEATURES, INCLUDING !RESPONSE TIME FOR ...

LER 84-002-01:on 840307,while performing refueling outage local leak rate testing,measured combined leakage rate for all penetrations & valves found in excess of Tech Specs. Valves,hatches & penetrations repaired.W/840904 ltr.

.~,NRCF Seeu.s. Nuctf Antawony COMMisseoNj''*3'APPROYED OMF. NO.3150 4 104JLICENSEE 8 EVENT REPORT (LER) j' * ' ' " ' * ' ' ' " * *FACILITV NAASE (11 DOCKET NUMBER (2)PAGE GQuad-Cltles Nuclear Power Station, Unit Oneo |5 |0 to |o| 2|514 i |OFl l 15TITLE tesLeak Rate From All V...

"Annual Rept of Facility Changes,Tests & Experiments Conducted W/o Prior Approval & Challenges to Primary & Secondary Sys PORVs & Safety Valves,1981."

r-..*- *.. .a..1981 ANNUAL REPORTOFFACILITY CHANGES, TESTS AND EXPERIMENTSCONDUCTED WITHOUT PRIOR APPROVALANDCHALLENGES TO THE PRIMARY AND SECONDARY SYSTEMPORV'S AND SAFETY VALVES8306020451 830520 , sj ,PDR ADOCK 05000244VR PDR- ,_|^-=.'...'|,)!i1981 Annual Report of Facility ...

Rev 7 to "HB Robinson Steam Electric Plant,Unit 2 ODCM."

Enclosura 2 to forfal: RNPD/92 0409Pegs 4 of 48. .H. B, ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 20FF SITE DOSE CALCUIATIONAL .%WAL(ODCM)Revision 7DOCKET NO. 50-26149 h3/%)DATEPNSC ReviewN C Ch irmanCAROLINA PO'.'ER & LIGHT COMPAFIHBRODC0.- . - - - - - - - . - _ . - _, . - ..IE...

Beaver Valley, Units 1 and 2, Emergency Response Data System (ERDS).

tQftFirstEnergy Nuclear Operating CompanyU. S. NuclearRegulatory CommissionAttention : Document ControlDeskWashington,DC 20555-0001Attachmentsc: Mr. T . G. Colburn,NRR Sr. ProjectManagerMr. J .R. Jolicoeur, USNRC Incident Response DivisionMr. P . C. Cataldo, NRC Sr . Resident ...

Response to Request for Additional Information (RAI) Regarding Severe Accident Mitigation Alternatives for Browns Ferry, Units 1, 2, and 3.

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801Jul, 7, 200410 CFR 5410 CFR 51U.S. Nuclear Regulatory CommissionATTN: Document Control DeskMail Stop: OWFN P1-35Washington, D.C. 20555-0001Gentlemen:In the Matter ofTennessee Valley Authority)Dock...

09/24/2002, Handouts for Meeting with Nuclear Energy Inst. (NEI) Re: Standard Format for License Renewal Applications.

MEETING HANDOUTSEnclosure 3.4  LRA FormatIImproved SRP-LR FormatStatement of the Problem ............ ...............* The SRP-LR summary tables are unable to adequately convey the information necessary for license renewal. 2Difficulties with SRP-LR format * Tables are "roll...

10/22/2002 & 10/23/2002 Proposed Agenda & Staff Presentations of Public Workshop on License Renewal.

PROPOSED AGENDA WORKSHOP ON LICENSE RENEWAL CONTINUING GUIDANCE DEVELOPMENT Tuesday, October 22, 20028:30 a.m. - 9:00 a.m. 9:00 a.m. - 9:10 a.m.9:10 a.m. - 9:20 a.m. 9:20 a.m. - 10:30 a.m.Registration - TWFN Auditorium Welcome and opening remarks Frank Gillespie - NRC Alan N...

Davis-Besse Oversight Panel Restart Action Matrix Closures - Emails.

March 22, 20041RAM Item No. - E-01 Closed: Y Date of E-Mail - 05/09/02Author - BlanchDescription of Issue - If cracking on nozzle #3 was only axial, why did the nozzle fall over? Inorder to do this it had to have circumferential cracking?Restart Checklist Item: N/ADescri...

Draft Outlines

ES-301 Operating Test Quality Checklist Form ES-30 1 -3 Facility: Millstone Unit 3 Date of Examination: 19 - 23 July 2004 Operating Test Number: One (I I 1. GENERAL CRITERIA Q Q '6 07 a. The operating test conforms with the previously approved outline; changes are consistent w...