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Forwards revised plant-specific action items list containing info compiled to date,per NRC 860430 request.Clarification of issues for which no update provided requested.

,.CD&L'Carolina Power & Light CompanySERIAL: NLS-86-278JUL 31 1986Director of Nuclear Reactor RegulationAttention: Mr. Dan Muller, DirectorBWR Project Directorate #2Division of BWR LicensingUnited States Nuclear Regulatory CommissionWashington, DC 20555BRUNSWICK STEAM ELECTRIC...

Insp Rept 50-213/89-07 on 890503-0613.Violations noted. Major areas inspected:plant operations,radiation protection, fire protection,security,maint,surveillance testing,licensee events & open items from previous insps.

..,, .- ---nph;.f jI.,# '$ . b M.*~e,y-b'*.| '.:(3U.S.: NUCLEAR REGULATORY COMMISSION -' ''; REGION I''[ [ReportNo.50-213/89-07. .n,Docket No.- 50-213~'License No. DPR-61: 1' Licensee: , Con ~necticut Yankee Atomic Power CompanyP. O..Bok 270u, Hartford, C1'06101,Facility:Hadda...

Forwards request for schedular exemption from requirements of App J to 10CFR50 re periodic schedule for Type C leakage testing.

accz~~a~rco o~smmurrow ozirowsra~rrOw SvSrncREGULATOINFORMATION DISTRIBUTIONTEM(RIDE)i Ll'CCESSION NBR:9211060242 DOC.DATE: 92/ll/03 NOTARIZED: NOFACIL':50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara PoweAUTH.NAME AUTHOR AFFILIATIONTERRYFC.D. Niagara Mohawk Power Corp...

Proposed Tech Specs reflecting new LER sys,per 10CFR50.72 & 50.73.

e .e ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE ~riR12120013 .. 841130-p ADOCK 050002SO PDR I. -TS 1. 0-5 for operational activities provided that they are under adminis­trative control and are capable of being closed immediately if required. 2. Blind flanges are ins...

Forwards addl info re NUREG-0737 Item II.B.1, "RCS Vents," in response to NRC 820222 request.

VIRGINIA ELECTRIC AND POWER COMPANY . RICHMOND~ VIRGINIA 23261 R.H.LEASBUBO VICE PH.ESIDENT NUCLEAR OPERATIONS April 23, 1982 Mr. Harold R. Denton Office of Nuclear Reactor Regulation u.s. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Steven A. Varga, Chi...

Application for amends to Licenses NPF-76 & NPF-80 replacing Tech Spec 3/4.6.2.2, "Spray Additive Sys," w/"Recirculation Fluid pH Control Sys." WCAP-12477, "Spray Additive Elimination Analysis for South Texas Project" encl.

. .*t.x..L. The Light-companyP.O.Ilus289 Wadsworth, Texas 77483llouston Lightm, g & I,ower_ South Texas Project Electric Generating Station _October 30, 1990ST-llL AE-3378File No.: G20.02.01G2.061R'FR50.90-U. S. Nuclear Regulatory CommissionAttention: Document Control Desk>Was...

Waterford Steam Electric Station, Unit - Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2019010

June 28, 2019 Mr. John Dinelli, Site Vice President Entergy Operations, Inc. 17265 River Road Killona, LA 70057-0751 SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 – DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000382/2019010 Dear Mr. Dinelli: ...

Nine Mile Point Station, Unit 1 - Post Exam Comments Resolution (Folder 1).

Question 53 Part 1 - Original Question Examination Outline Cross-Reference: Plant Fire On-site Level Tier# Group# KIA# Importance Rating RO 1 1 600000 AA2.16 3.0 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Vital equipment and control s...

IR 05000219/2015001, January 1, 2015 • March 31, 2015, Oyster Creek Nuclear Generating Station - NRC Integrated Report.

B. Hanson UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 May 14, 2015 Mr. Bryan Hanson Senior Vice President, Exelon Generation President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Roa...

AREVA Design Control Document Rev. 7 - Tier 2 Chapter 07 - Instrumentation and Controls - Section 7.8 Diverse I&C Systems

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 7 Page 7.8-17.8 Diverse I&C SystemsThe safety-related instrumentation and controls (I&C) systems that execute automatic reactor trip (RT) and engineered safety feature (ESF) actuation and control functions for accident mi...

Enclosure: Revised Response to RAI 63-7983 for Questions 06.02.02-14, and 06.02.02-26.

06.02.02-14_Rev.1 - 1 / 2 KEPCO/KHNP REVISED RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONAPR1400 Design Certification Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., LTD Docket No. 52-046 RAI No.: 63-7983 SRP Section: 06.02.02 – Containment Heat Removal ...

LER 2020-002-00 for Sequoyah Nuclear Plant, Unit 1, Safety Injection Signal with Reactor Trip Caused by a Failure with the Main Turbine Control System

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384July 1,202010 CFR 50.73ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Unit 1Renewed FacilityOperating License No. DPR...

NPDES noncompliance notification:on 981102,500 gallons of 12% sodium hypochlorite released to environ.Caused by failure of tank discharge fittings & subsequent leaks from secondary containment.Culvert was flushed repeatedly.

.. , . _ . . _ ~ ~ - ~ . - . . - . . _ - . . . - - . - ~ . . - - - . , . . - . . . . - ~ . ~ - -- . =Lirnarick Genstating stitlan),-6e*_-.w-,EN RGYecco c"e'av e=" "vcPO Box 2200, Sanatoga, PA 19464 0920||!December 21,1998|Mr. H. J. MillerAdministrator, Region iU.S. Nuclear Reg...

Proposed tech specs change to TS 4.5.2.b & associated bases bringing Byron Unit 1 & Braidwood Unit 1 requirement in conformance w/Unit 2 requirements approved by NRC in 970813 ltr.

...ATTACllMENT B-1,,MARKED UP PAGES FORPROPOSED Cl{ANGES TO APPENDIX A,TECilNICAL SPECIFICATIONS, OFFACILITY OPERATING LICENSES NPF-37 AND NPF-66BYRON STATION UNIT 1 AND UNIT 2REVISED PAGES:3/4 5 43/4 5-4 a3/45-4bB 3/4 5-2B 3/4 5-2a__. n:\byrbwd\newvent. docPage1of 1Attachment...

Responds to observations noted in Emergency Operating Insp Repts 50-373/88-200 & 50-374/88-200.Calculations for standby liquid control shutdown weights revised to reflect mod to standby liquid control sys.

,> .Comm:nwalth Edis n--Z. WOne First National Plaza. Chicago, Illinois --*.VAddress Reply to: Post OTfice Box 767'Chicago, Illinois 60690 0767February 24, 1989Mr. T. E. MurleyU.S. Nuclear Regulatory CommissionAT'IN : Document Control DeskWashington, DC 20555Subject: Quad citi...

Insp Rept 50-424/87-52 on 870831-0904.Violation noted.Major areas inspected:training & qualifications,external & internal exposure control,facilities & equipment,ALARA program,transportation & followup on IE info notices.

1@ MoogUNITED STATES,%'fNUCLEAR REGULATORY COMMISSION|.[ [ ~ 'REGION iln_5.j-101 MARIETTA STREET, N.W.*'2- ATLANTA, GEORGI A 30323%.j*...+SEP 2 41987 .Report No.: 50-424/87-52'Licensee: Georgia Power Company,P. 0. Box 4545Atlanta, Georgia 30302Docket No. 50-424 License No.: NP...

IR 05000018/2012008; 05000070/2012001; 05000183/2012001, on September 24-27, 2012, Vallecitos Nuclear Center in Sunol, California, NRC Inspection Report.

October 09, 2012 Mr. Anthony McFadden Manager, Vallecitos Nuclear Center GE-Hitachi Nuclear Energy 6705 Vallecitos Road Sunol, CA 94586 SUBJECT: NRC INSPECTION REPORT 050-00018/12-008; 050-00070/12-001; 050-00183/12-001 Dear Mr. McFadden: This letter refers to the insp...

NUREG-0347 Supplement 1 Safety Evaluation Related to Construction of Yellow Creek Nuclear Plant Units 1 & 2.

afetyEvaliuautioi ReNprtl/t~/j$UREGO347pp. No.1U. S. NuclearRegulatory Commissionrelated to construction ofYellow Creek Nuclear PlantUnits I Et 2Office of NuclearReactor RegulationDocket Nos. STN 50-566STN 50-567June 1978Tennessee Valley AuthoritySupplement No. III1Available ...

Regulatory Guide 1.96, Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants.

U.S. NUCLEAR REGULATORY COMMISSIONMay 1975.REGULATORY GUIDEOFFICE OF STANDARDS DEVELOPMENTREGULATORY GUIDE 1.96DESIGN OF MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEMSFOR BOILING WATER REACTOR NUCLEAR POWER PLANTSA. INTRODUCTIONGeneral Design Criterion 54, "Piping Systems ...

Notification of Potential Part 21 - Anti-Rotation PIN Failure in 10-Inch Anchor Darling (Flowserve) Double Disc Gate Valve.

0110412013 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze IPower Reactor Event# 48650Site: BROWNS FERRY Notification Date/ Time: 01/04/2013 13:20 (EST)Unit: 1 Region: 2 State : AL Event Date / Time: 12/29/2012 (CST)Reactor Type: [1] GE-4,[2] GE-4,[3] GE...

NuScale Power, LLC Response to NRC Request for Additional Information No. 492 (eRAI No. 9551) on the NuScale Design Certification Application.

RAIO-0818-61388NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comDocket No. 52-048 August 15, 2018U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North11555 Rockvi...

LER 91-021-01:on 910522 & 0603,Tech Spec 3/4.8.3.1 noncompliance discovered.Caused by personnel error.Amend implementation event reviewed w/prior Tech Spec Administrator.W/910906 ltr.

• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sir: SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 S...

Provides basis for authorization request to use noted supplies,summary of test protocol & results & final test repts.

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 27, 1997 United States Nuclear Regulatory Commission ·· · Attention: Document Control Desk · · Washington, D.C. 20555 Dear Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NO...

Requests specific exemption from 10CFR20.1703 paragraphs (a)(1) & (c) & 10CFR20,App A protection factors for respirators,footnote d,to use MSA models 401,ultralite & custom 4500 dual-purpose pressure-demand SCBA supplied.

-· ., ·--~ -·~ , .. •., ( e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 3, 1998 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Dear Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION ...

Comments on new TMI action plan requirements.Use of Reg Guide 1.97,Revision 2,as basis of design requirements for instrumentation is inappropriate.

.ARKANSAS POWER & LIGHT COMPANYPOST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (5011371-4000October 7, 1980l'-100-022-100-05Mr. Darrell G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D. C. 20555Subjec...