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"Summary Rept of Changes,Tests & Experiments Completed," including SEs covering period on 980716-1031.With 981209 ltr.

4 '9Commonwealth filison Comtuny.Quad Cities Generating Station22710 206th Avenue North d|Cordova, 11. 61212 sr140Tei .w><,s4 221iSVP-98-358December 9,1998;!U.S. Nuclear Regulatory Com. mission;Washington, DC. 20555Attention: Document Control Desk!Subject:Quad Cities Nuclear P...

Rev 0 to "Evaluation of Effects of High Energy Line Breaks on Control Sys."

EVALUATIONOF THE EFFECTS OFHIGH ENERGY LINE 5REAKS ONCONTROL SYSTEMSPrepared for:Pennsylvania Power and Light CompanySusquehanna Steam Electric StationPrepared by:EDS Nuclear, Inc.May,1983Revision 08310180509831014t'lPDR *DOCK05000387PPDRReport No. 02-0 I 60-1 l 31Revision 0EV...

IMC 2515 Appendix D Plant Status.

Issue Date: 11/19/18 1 2515 Appendix D NRC INSPECTION MANUAL IRIB INSPECTION MANUAL CHAPTER 2515 APPENDIX D PLANT STATUS Effective Date: January 1, 2019 2515D-01 PURPOSE The Reactor Oversight Process recognizes that resident inspectors have a specific responsibili...

McGuire Nuclear Station - Nuclear Regulatory Commission Integrated Inspection Report - 05000369/2018004 and 05000370/2018004.

January 23, 2019 Mr. Thomas D. Ray Site Vice President Duke Energy Carolinas, LLC McGuire Nuclear Station MG01VP/12700 Hagers Ferry Road Huntersville, NC 28078 SUBJECT: MCGUIRE NUCLEAR STATION – NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000369/20...

Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 15, Accident Analyses.

15-i Reset February 2018 TABLE OF CONTENTS Section Title Page 15.0 ACCIDENT ANALYSES 15.0-1 15.1 CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS 15.1-1 15.1.1 OPTIMIZATION OF CONTROL SYSTEMS 15.1-215.1.2 INITIAL POWER CONDITIONS ASSUMED IN ACCIDENT ANALYSES 15.1...

Proposed tech specs implementing recommended changes from GL 93-05, "Line Item TS Improvements To Reduce SR For Testing During Power Operation."

ENCLOSUREPROPOSED AMENDMENTTO TECHNICALSPECIFICATIONSECTIONS 3/4.0, 3/4.1.3, 3/4.3.3, 3/4.4.5, 3/4.5.2,3/4.6.2, 3/4.7.1, and 3/4.10.1940lli0265 940104„'PDRADOCK 05000528P"PDRI1gtJme ~ -+plA. DESCRIPTION OF THE PROPOSED AMENDMENTREQUESTThe proposed amendment makes the following...

Forwards summary rept of HEDI-TMI 83-16, "Results & Code Predictions for ABCOVE Aerosol Code Validation - Test AB5." Summary of comparison of codes sent on 840830 unacceptable.

.__/" *'o,UNITED STATES[s*jNUCLEAR REGULATORY COMMISSION,.;~/wassiNovos. o. c. rosss%, .....f. . -007 41984Dr. S. Goren201 F. GilmanDepartment of Chemical EngineeringUniversity of CaliforiaBerkeley, CA 95720-Dear Dr. Goren:You wanted to compare the acrosol behavior predictions...

Proposed Tech Specs increasing total number of safety-related snubbers & scope of surveillance requirements.Significant hazards determination encl.

.INDEXLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE SE@lFEMENTSSECTION PAGE3/4.7 PLANT SYSTEMS3/4.7.1 TURBINE CYCLESafety Valves.............................. 3/4 7-1Emergency Feedwater System................. 3/4 7-5Condensate Storage Tank.................... 3/4 7-7Acti...

Staff exhibit S-54,consisting of vendor nuclear qualification rept including test methods,actual aging parameters,environ tests & qualified & design life.

___ _ --- - _ - - - - - ----- - ------ --- -- - - --- ---------- - ------ ~3-5YStaff Exh. 54$p- 3 p'3 6 '{d l &z,.e0-e-ei..- .-. ... ,,\ 4&090433'64;UO4-..["*\., , , .-=...,'.'...k8 4 +4 ,cg. , _..".i(*-070Mqg''\ 2.4 Environmental Qualification Acceptance CriteriaThe basic fun...

Requests evaluation & prioritization of generic safety issue re failure of HPCI steam line w/o isolation.Bases for labeling issue generic provided.

' ~4... c.. . >.n,,,..'.y&. .,. _-. . ,-:-~. w... m. % ....s.".-%. . , ....;. :. .s,..x.. c.~.n m. , g.c.g;. . ...-...,.)v. . ,fs..,f:. .:. .i ..:... . + . + . . ~ . .+.y9, -. .. . .. .5. .,- .: . .e. .'i.n.<. . . - -.n , , ... - .. - %.. ,. v . h.- .e ~*: *_n . -.a .. . - . ....

Insp repts 50-282/98-04 & 50-306/98-04 on 980210-13 & 0316-20.No violations noted.Major areas inspected:RP performance during unit 1 refueling outage & unit 2 forced outage,calibration of radiation monitoring sys.

.'U.S. NUCLEAR REGULATORY COMMISSIONREGION |||Docket Nos: 50-282;50-306License Nos: DPR-42; DPR-60Report Nos: 50-282/98004(DRS); 50-306/98004(DRS)Licensee: Northern States Power CompanyFacility: Prairie Island Nuclear Generating PlantLocation: 1717 Wakonade Dr. EastWelch, MN 5...

LER 97-020-00:on 971030,util concluded that plant operated w/torus temp greater than initial temp assumed in some plant transient analyses.Caused by inappropriate assignment of technical review.Procedure improved.W/971126 ltr.

YkRMONT YANKEE.NUCLEAR POWER LCORPORATION. - ..-Ferry Road, Brattleboro, VT 05301 7002Vs3~.(802) 257-5271Nov. 26, 1997BVY 97-158U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. . 20555Reference:(a) License No. DPR 28 (Docket No. 50-271). Subject: R...

Comment (085) of Herschel Specter on behalf of Micro-Utilities, Inc. on PR- 50, 52- Emergency Preparedness for Small Modular Reactors and Other New Technologies

From: MH SpecterTo: RulemakingComments ResourceSubject: [External_Sender] ATTN: Chairman Svinicki, Emergency Planning for SMRs and ONTsDate: Monday, July 20, 2020 12:09:08 PMAttachments: Comments on Emergency Preparedness for SMRs and ONTs.pdfKristine L. SvinickiChairmanNuclea...

Summary of 980729 meeting w/util in Rockville,MD to discuss technical issues associated w/util proposed license change request re UHS for plant.List of attendees encl.

',d*S ucoq-'y iUNITED STATES.jNUCLEAR REGULATORY COMMISSIONg.,g.WASHINGTON, D.C. 20066 4 001;g . . . . . p*August 18, 1998I(iLICENSEE: Public Service Electric and Gas Company'FACILITY:Hope Creek Gmerating StationSUBJECT:SUMMARY OF JULY 29,1998, MEETING REGARDING ULTIMATE HEAT ...

Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Additional Information Regarding License Amendment Request for Extended Power Uprate (TAC Nos. ME9631 and ME9632).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555·0001 September 11, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUBJECT: PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 ...

IR 05000390-14-002; 01/01/2014 - 03/31/2014; Watts Bar, Unit 1; Problem Identification and Resolution, Post-Maintenance Testing.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 April 30, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 3740...

Watts Bar Nuclear Plant (WBN), Unit 2 - Final Safety Analysis Report (FSAR), Amendment 109 - Section 3, Design of Structures, Components, Equipment, and Systems - Page 3.8.1-1 through 3.8.4-182.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-109m3.8 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...

Fermi 2013 Exam ILO NRC - SRO.

EXAMINATION ANSWER KEY2013 ILO NRC - SRO1 ID: S76 Points: 1.00The plant is operating at rated power with all systems functioning normally when the following indicationsoccur:9D23, DIV I 4160V ESS 64B BKR TRIPPED 9D22, DIV I BUS VOLTAGE LOW TRIPPED indication on Bus 64B Pos B...

AREVA Design Control Document Rev. 7 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.2.3 Safety Injection System and Residual Heat Removal System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 7 Page 2.2-642.2.3 Safety Injection System and Residual Heat Removal System Design Description1.0 System DescriptionThe safety injection system and residual heat removal system (SIS/RHRS) is a safety-related system. The ...

Proposed TS 3/4.1.2.8 re reactivity control sys - borated water sources - shutdown TS 3/4.1.2.8 re reactivity control sys - operating & TS 3/4.5.1 re ECCS - core flooding tanks.

- _ _ _ _ . - _ _ .___ - _______LAR 95-0010Page 14||.3/4.1REACTIVITY CONTROL SYSTEMS3/4.1.1 B0 RATION CONTROLSHUTDOWN MARGINLIMITING CONDITION FOR OPERATION|3.1.1.1 The SHUTOOWN MARGIN shall be 2 1% Ak/k.APPLICABILITY: MODES 1, 2*, 3**, 4 and 5. |ACTION:.With the. SHUT 00WN MA...

"Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,June-Jul 1985."

_*,.~iTECHNICAL HIGHLIGHTS / ADMINISTRATIVE REPORTFORTHE NUCLEAR REGULATORY COMMISSION (NRC)REACTOR SAFETY RESEARCH PROGRAMJune-July 1985Sandia National LaboratoriesiAlbuquerque, NM 87185Operated byjSandia Corporationfor theU.S. Department of EnergyPrinted September 1985Prepar...

Toshiba Design Control Document Rev. 1 - Tier 2 - Chapter 09 - Auxiliary Systems - Appendix 09B - Summary of Analysis Supporting Fire Protection Design Requirements

Summary of Analysis Supporting Fire Protection Design Requirements 9B-1RS-5146900 Rev. 1Design Control Document/Tier 2 ABWR9B Summary of Analysis Supporting Fire Protection Design Requirements9B.1 IntroductionThis appendix is included to discuss in detail some of the analysi...

NRC Staff Pre-Filed Hearing Exhibit NRC000107, Indian Point Nuclear Generating Units 2 and 3 - NRC License Renewal Inspection Report 05000247/2008006 and 05000286/2008006.

August 1, 2008 Mr. Joseph Pollock Site Vice President Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUBJECT: INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 - NRC LICENSE RENEWAL INSPECTION REPORT 05000...

Palo Verde, Units 1, 2, and 3 - Issuance of Amendment Nos. 189, 189, and 189, Modify Technical Specifications to Implement Administrative Changes Including Corrective Actions from U2 Event in LER 50-529/2011-001 (TAC Nos. ME7621, ME7622 & ME7623).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555·0001 June 18, 2012 Mr. Randall K. Edington Executive Vice President Nuclear! Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 SUBJECT: PALO VERDE...

SOARCA Peer Review Comments.

SOARCAPeer ReviewComments(Feb. 25 ,2010)DSE. K(2.--SOARCAPeer ReviewComments(Feb. 25, 2010)keg- P'CV&(A~/ ~ ~K 2 ~S ~ "'I 1 :m __ ___ _ _ ______-1A,/4$ OzId k017 be, #e,,r-pcLc ,/Jr1, fv hb14' Pecl, if e> y647R edt- c-'o L~~4,~ ,ers%SOARCA Summary Rev I Extracted Paaes - Peach...