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"Independent Design Verification Program," semimonthly rept for Jan 1983.

-ri-TELEDYNEENGINEERINQ SERVICESDIABLO CANYON NUCLEAR POWER PLANTINDEPENDENT DESIGN VERIFICATION PROGRAMSEMIMONTHLY REPORTTES-SN-JANUARYFEBRUARY 11, 1983 CQNRQL59CQPPREPARED BY:TELEDYNE ENGINEERING SERVICESIDVP PROGRAM MANAGER t8302i80~8~000275I Ii830211pgpAQOCK0pop'( A TELEDY...

Forwards amended response to request for addl info re draft SER Open Item 38 concerning technical basis for GDC-51 compliance.Responses to other requests will be provided shortly.

REGULATORY 'ORMATION DISTRIBUTIONSYM (RIDE)ACCESSION NBR; 8310110119,', DOC ~ DATE: 83/09/30 NOTARIZED; NOFACILI50 400 Shearon Harris Nuclear Power Planti Unit ii Carolina50 001 Shearon Harris Nuclear Power Plant~ Unit 2p CarolinaAUTH'AMEAUTHOR AFFILI ATIONMCDUFFIE $f»'' )(Wld...

Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control" (Tac No. MF3487).

December 20, 2016 Technical Specifications Task Force 11921 Rockville Pike, Suite 100 Rockville, MD 20852 SUBJECT: FINAL SAFETY EVALUATION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-542, REVISION 2, "REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL" (TAC NO. MF...

Safety Evaluation LAR 17 013 for Vogtle Units 3 and 4

-1- SAFETY EVALUATION BY THE OFFICE OF NEW REACTORS RELATED TO EXEMPTION AND AMENDMENT NOS. 92 AND 91 TO THE COMBINED LICENSE NOS. NPF-91 AND NPF-92 SOUTHERN NUCLEAR OPERATING COMPANY, INC. GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SP...

IMC 2515 Appendix D Plant Status.

Issue Date: 10/03/17 1 2515 Appendix D NRC INSPECTION MANUAL IRIB INSPECTION MANUAL CHAPTER 2515 APPENDIX D PLANT STATUS Effective Date: 01/01/2018 2515D-01 OBJECTIVES AND PHILOSOPHY OF PLANT STATUS ACTIVITIES The Reactor Oversight Process recognizes that resident in...

Vogtle 3 - 05200025/2016301 Initial NRC Exam - ADAMS 2C - Public Exam Administrative Items - Delay Release 2 Yrs.

ES-301 Administrative Topics Outline Form ES-301-1Facility: Vogtle Units 3&4 Date of Examination: 07/2016Examination Level: RO Operating Test Number:Administrative Topic (see Note)[Type Describe activity to be performedCod&’Detetmine if you can replace a watchstander due to il...

E-Mail from Nike Williams, Zion Solutions, to John Hickman, NRC, dated May 4, 2017, forwarding TSO 17-004 Rev. O, Operational DCGLs.

Hickman, John From: Sent: To: Cc: Subject: Attachments: Nick Williams Thursday, May 04, 2017 4:13 PM Hkkman, John; Vaaler, Madayna Gerard P. Van Noordennen [External_Sender] Zion Ops-DCGL TSD 2017-05-04 TSD 17-004 Rev 0 Operational DCGLs FINAL.pdf . Good Afternoon John and Ma...

Vogtle - NRC Design Bases Assurance Inspection (Programs) Report 05000424/2017009 and 05000425/2017009.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 January 23, 2018 Mr. Darin Myers Vice President Southern Nuclear Operating Company, Inc. Vogtle Electric Generating Plant 7821 River ...

Vogtle, Units 3 and 4, Supplement to Request for License Amendment and Exemption: Consistency and Clarification Changes to Annex Building, Auxiliary Building and Basemat ITAAC (LAR-17-040S1).

B. H. Whitley Southern Nuclear Director Operating Company, Inc. Regulatory Affairs 42 Inverness Center Parkway Birmingham, AL 35242 Tel 205.992.7079 Fax 205.992.5296 April 6, 2018 Docket Nos.: 52-025 ND-18-0425 52-026 10 CFR 50.90 10 CFR ...

Final version of limited appearance statement at ASLB 820414 hearings,supporting facility licensing.NRC current requirements for emergency planning & public perception of nuclear accident consequences are excessive.

.., . Limitcd Appsarrnca Statemint of Andrew P. Hull bafora Atomic Safety and Licansing*B ard of th2 U.S. Nuclear Rsgulatory Commission - In ths MStter of. .* Long Island Lighting Comptny (Shorchtm Nuclear Powar Statien --Unit 1) Docket No. 50-322-OL, April 14, 1982Andrew P. H...

Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 13 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls

DRESDEN — UFSAR Rev. 13June 20197.0 INSTRUMENTATION AND CONTROLSTABLE OF CONTENTSPage7-i7.0 INSTRUMENTATION AND CONTROLS7.1 INTRODUCTION 7.1-17.1.1 Identification of Systems 7.1-1a7.1.1.1 Protective Systems 7.1-1a7.1.1.2 Safe Shutdown 7.1-27.1.1.3 Display Instrumentation ...

Pilgrim - Attachment 1 to 2.18.045, EP-AD-301, Emergency Action Level Technical Bases Document, Revision 9 and Associated 10 CFR50.54(q) Review.

Attachment 1 Letter Number 2.18.045 EP-AD-601, Emergency Action Level Technical Bases Document, Revision 9 and associated 1 O CFR 50.54(q) Review • • • a PNPS NON-QUALITY RELATED EP-AD-601 Revision 9 -=-Entergy . EMERGENCY PLAN PROCEDURE ADMINISTRATIVE PROCEDURES -REFERENCE US...

Rev 1 to Procedure RTP-46, "Core Estimation Damage, Post-Accident Sampling Sys."

Y |l'Fd[I' [ i [] ,[ .hD'3.ia lG@ll !! "'' 'l( J)ej_L'-.fNEW YORK POWER AUTHORITYJAMES A. FITZPATRICK NUCLEAR POWER PLANTRADIdLOGICAL AND ENVIRONMENTAL SERVICES DEPARTMENTfIiPROCEDURE NO.:RTP-46iTITLE:CORE DAMAGE ESTIMATION, PASSi!PORC Review No./Date Meeting No.:N/A DateJ3 8f...

Vols 1 & 2 to "Byron Generating Station Limiting Conditions for Operation Relaxation Program."

._ . _ ~ . ._ _ . - _ . _ _ _ _ . _WESTINGHOUSE CLASS 3CUSTOMER DESIGNATED DISTRIBUTIONO'BYRON GENERATING STATIONLIMITING CONDITIONS FOR OPERATIONRELAXATION PROGRAM|J. C. Butler J. F. MerzOS. K. Erwin S. SancaktarS. T. Maher C. A. SherbineApril, 1984Prepared by Westinghouse El...

Turkey Point, Units 3 and 4 - Supplement to License Amendment Request 230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, "Generic Letter 2008-001, Managing Gas Accumulation," Using....

0F:PL,July 15, 2015L-2015-18510 CFR 50.90U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555-0001Re: Turkey Point Nuclear Plant, Units 3 and 4Docket Nos. 50-250 and 50-251Supplement to License Amendment Request 230, Application to Revise Techni...

Fermi 3, Revision 0 to Updated Final Safety Analysis Report, Chapter 15 - Safety Analyses.

15-1 Revision 0October 2015Fermi 3Updated Final Safety Analysis ReportChapter 15 Safety AnalysesThis chapter addresses all ESBWR plant safety analyses. The details of most of the safetyanalyses are contained within this chapter; however, per the Regulatory Guide 1.70 format, s...

Attachment 9 - EP-AA-1007, Revised Radiological Emergency Plan Annex Information for Peach Bottom Atomic Power Station.

ATTACHMENT 9DISCUSSION OF REVISIONTO THEREVISED RADIOLOGICAL EMERGENCY PLANANNEX INFORMATIONFORPEACH BOTTOM ATOMIC POWER STATIONEP-AA-1 007Enclosures000Enclosure 9A - Revised EAL Comparison Matrix DocumentEnclosure 9B - Revised EAL Red-Line Basis DocumentsEnclosure 9C - Revise...

Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.1-1 - 3.8.4-182.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-114m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornad...

Insp repts 50-424/97-11 & 50-425/97-11 on 971102-1213. Violations noted.Major areas inspected:operations & maint.

33.}|+[ w, _'' ~.. .-,'.,. _U. S. NUCLEAR REGULATORY-COMMISSIO,N'(NRC).-'"4:-. REGION ll-~i,-y--|-Docket Nosi:50-424:and.50-425: -'7 License Nos. NPF-68 and NPF.-81: ;I~ Report No:--- 50-424/97-11,;50-425/97-11Licensee: ' Southern Nuclear rating. Company. Inc.-Facility:- Vogtl...

"RWCU Sys Automatic Isolation & Safety Considerations."

~i >I,''1y..|.|,1 ."LAEOD/E705.:ENGIt'EERING EVALUATION PEPORT*1IiRWCU SYSTEM AUTOMATIC ISOLATION AND SAFETY CONSIDERATIONSI-.March 198711,':'.:'Prepared by: Neill Thomassen!1!>dqlOffice for Analysis and Evaluationof Operational Data4iU.S. Nuclear Regulatory Commission3i!,*Thi...

Final Deficiency Rept (CDR-86-00-07) re valve alignment of ECCS during cold leg recirculation phase of post-LOCA ECCS operation.Initially reported on 860606.Low head safety injection sys valve alignment will be used & FSAR updated.

'.'l5)" ~SEABROOK STATION|,Enginssring Offica* '... uJuly 18, 1986Put2c Service of New HampeNro SBN- 1162T.F.Q2.2.2NEW UAMPSHIRE YANKEE DIVISIONUnited States Nuclear Regulatory CommissionRegion I631 Park AvenueKing of Prusola, PA 19406Attention: Mr. Richard W. Starostecki, Dir...

Comments on draft NUREG-1150 re core melt accident & source term evaluation.Description of how core melt progression affects hydrogen generation supported.Rept should refer to meltdown model as oppposed to meltdown temp.

"slOH@Wet$f|m-zduE88*-1.D @',f*,o .Ig" .I,._.--. --- ~y*-. ,-.s ....y.-_-.----_ ;.$=*8 $a -. gyf 8 H a-c'oH $ hg- o goaha o$@ ga a@0a*Z" sEr2 4 62 4 64 2 - - - 2 0 - - -0 00 0 0 0 0 0 01 1 1 1 1 1 1 1 1 10t0- - '- _ -.0 c--1u-d-or-PHGn -U0o )O\ 0 i I-R ts 8s C[j',s\g" H\g s PT...

Pre-Application Review Meeting: Seismic Analysis of APR1400-E-S-EC-120002-NP.

0 APR1400 6th Pre-application Review Meeting Seismic Analysis APR1400-E-S-EC-120002-NP Pre-Application Review Meeting ▣ Seismic Analysis of APR1400 1 APR1400 6th Pre-application Review Meeting Seismic Analysis APR1400-E-S-EC-120002-NP Seismic Analysis of APR1400  Structure...

Pilgrim Nuclear Power Station, Unit 1 - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC NO. MF0777).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. John Dent, Jr. Site Vice President Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 December 16, 2013 SUBJECT: PILGRIM NUCLEAR POWER STATION- INTERIM STAFF EVALUATION RELATING ...

Watts Bar Nuclear Plant, Unit 2 - Final Safety Analysis Report (FSAR), Amendment 110, Section 3.8, "Design of Category I Structures".

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-110m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornad...