Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

CLOSEOUT OF IE BULLETIN 79-21:TEMPERATURE EFFECTS ON LEVEL MEASUREMENTS.

.eNOREG/CR-4522.Closeout of IE Bulletin 79-21:Temperature Effects onLevel Measurementsct'IiPrepared by R. S. Dean, W. J. Foley, A. HennickPAR AMETER, Inc.U ucle.ar RegulatoryIL- -- .:- ,m__'lN%;%..{. _ _' ,rfMs-gi'- ,NOTICE -- This report .was" prepared as an account of wor'k ...

Chapter 1 of RESAR-SP/90 Westinghouse Advanced PWR Module 3, "Introduction & Site," "Introduction & General Description of Plant."

. _ . - . . . .-. . _ - . .-1.0 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT1.1 INTRODUCTIONThe Westinghouse Electric Corporation (hereinaf ter referred to as Westing-house) has developed this Reference Safety Analysis Report (RESAR-SP/90) for-Ithe Westinghouse Advanced Press...

Kairos Power comments on the NRC staff draft Safety Evaluation for the Kairos Power PDC Topical Report

OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION- Safety Evaluation “Principal Design Criteria for the Kairos Power Fluoride Salt-Cooled, High Temperature Reactor” Docket No. 999020691.0 INTRODUCTION By letter dated December 21, 2018, Kai...

Responds to notice of violation & proposed imposition of civil penalty identified in IE Insp Repts 50-289/83-25 & 50-289/83-26 & IE Enforcement Conference Rept 50-289/83-33. Civil penalty unwarranted or required.

w,-!GPU Nuclear CorporationNuclear :::,ome::=.sMiddletown, Pennsylvania 17057-0191717 944 7621TELEX 84 2386Writer's Direct Dial Number:5211-84-2081March 30, 1984,Mr. R. C. DeYoungDirector, Office of Inspector and EnforcementU. S. Nuclear Regulatory CommissionWashington, D.C. 2...

"Trip Rept:Onsite Analysis of Human Factors of Event at Prairie Island 2 on 920220 (Loss of Shutdown Cooling)."

_ _ _ . _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. .,.EGG-HFRU-10228TRIP REPORT:ONSITE ANALYSIS OFTHE HUMAN FACTORS OF AN EVENTAT PRAIRIE ISLAND 2FECRVARY 20, 1992(LOSS OF SHUTDOWN COOLING)William SteinkeSusan HillOrville MeyerOnsite Analysis Team:John KauffmanWilliam SteinkePub...

Forwards description of NRR technical assistance project "Safety Evaluation of Core-Melt Accidents:Mark I BWRs," for review & concurrence.Concurrences encl.

*-i.--:...,,3 ,*[]''o,'* ~.UNITED STATES./,,g,/, -*Y NUCLEAR REGULATORY COMMISSION*'-.o$ WASHINGTON, D. C. 20556'h' ,, o/ March 18,1983'~4...*MEMORANDUM FOR:. -Martin Hayes, RESAlan P. Muir, I&EJohn Evans, NMSSCarlyle Michelson, AEOD ,John J. Mc0 scar, Region IRichard J. Maley...

"Haddam Neck Combustion Gas Control COGAP Analysis," ltr rept.

,_ .,s,.. .[ ''3|f'..' ".,,,-p-, ,;'MADDAM NECK COMBUSTION GAS CONTROL COGAP ANALYSIS .,(NRC FIN A7272 Letter Report) 4K,by'R. G. Gido'Safety Assessment Group.. Nuclear Technology and Engineering DivisionLos Alamos National Laboratoryt-University of California!Los Alamos, New ...

---- ..........Ref erenceo 7Des ign Change Package' (DU) 2&-2077T~OOS E G tC antainment ICUsSequence T ime Mbd If icat i n02 R3 -2 077- Sf j 0 S 5 Page t of 2SINGR- A ktbDESIGN CHANGE PACKAGE DO CVE SEET1. DCP No.Rev.: 2&3-2077.OOSE I 0 E]Affeced Section Change: ASC No.: E Who...

Virgil C. Summer Nuclear Station, Unit No. 1, Issuance of Amendment Regarding Reactor Coolant System Leakage Detection Systems (TAC No. ME6332).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555·0001 February 22, 2012 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric &Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, SC 29065 SUBJECT: VIRGIL ...

HCVS-WP-03 - Hydrogen/Carbon Monoxide Control Measures Revision 0, June 24, 2014.

HCVS-WP-03 – Hydrogen/Carbon Monoxide Control Measures Revision 0, June 24, 2014 1 | P a ge 1.0 Purpose The purpose of this paper is to present a series of viable options, which a site may use to meet requirements 1.2.10 and 1.2.11 of Vent Order EA-13-109 (Reference 1). Th...

NUREG-0800, SRP BTP 3-4 Revision 2 to Draft Revision 3 Redline.

Revision 2 - March 2007 Draft Revision 3 – August 2015 USNRC STANDARD REVIEW PLAN This Standard Review Plan (SRP) NUREG-0800, has been prepared to establish criteria that the U.S. Nuclear Regulatory Commission (NRC) staff responsible for the review of applications to const...

Harris Initial Exam 2014-302 Draft Sim_IN-Plant JPMs.

Appendix C Job Performance Measure Form ES-C-1 Worksheet 2014 HNP NRC Exam Simulator JPM CR a Rev. 3 Facility: Shearon Harris Task No.: 001001H201 Task Title: Perform Control Rod and Rod Position Indicator Exercise JPM No.: 2014 NRC Exam Simulator JPM CR a K/A Ref...

AREVA Design Control Document Rev. 7 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.4.5 Safeguard Building Controlled-Area Ventilation System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 7 Page 9.4-489.4.5 Safeguard Building Controlled-Area Ventilation SystemEach of the four safeguard divisions is separated into two functional areas:● Hot mechanical area (controlled area) serviced by the safeguard buildin...

Sequoyah Initial Exam 2015-301 Draft RO Written Exam.

1. 008 AG2.2.37 001 QUESTIONS REPORT for 1503 RO Exam Given the following plant conditions: Unit 1 is operating at 100% power. - The following alarm is received: PS-68-301 PRESSURIZER RELIEF TANK PRESS HIGH (1-M5A, D-1) PZR PORV 68-340 acoustic monitor indicates discharge. The...

Letter to T. Grochowski re: Application for Certificate of Compliance No. 9365 for the Model No. RT-100 Package - Request For Additional Information.

March 28, 2013 Mr. Teo Grochowski, Chief Executive Officer Robatel Technologies, LLC 5115 Bernard Drive Suite 304 Roanoke, VA 24018 SUBJECT: APPLICATION FOR CERTIFICATE OF COMPLIANCE NO. 9365 FOR THE MODEL NO. RT-100 PACKAGE – REQUEST FOR ADDITIONAL INFORMATION Dear M...

Sequoyah Initial Exam 2012-302 Draft RO Written Exam.

QUESTIONS REPORTforSQN Dec2012 RO Exam1. Given the following plant conditions:- Unit 1 is at 10% power following a refueling outage.- The main turbine is being warmed up in preparation to sync to the grid.- The OATC notes that CB A, rod H6 Red ROD at Bottom light is illuminate...

Arkansas Nuclear One, Unit 2, 2014-02-Draft Outlines.

ES-401 PWR Examination Outline FORM ES-401-2Facility Name:Arkansas Nuclear One Unit 2 Date of Exam:2/7/2014K1K2K3K4K5K6A1A2A3A4G*Total Total1 423 44 1 18 62 212 21 1 9 4Tier Totals 6 3 5 65 2 27 101 32342234122 28 52 11111011111 10 1 1 3Tier Totals...

Rev 11 to "Recovery From Safety Injection."

\ SALEM GENERATING STATION • OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET-Title: Recovery from Safety Injection No.:EI-I-4.2 Unit: 1 Rev.: 11 Remarks: 11 oaaes of text, 1 attachment, 1 table, 1 appendix. Chanqes: Added note and steps a,b,c and d to st.ep 4.12, changed s...

Issue 2 to Rev 5 to "Inservice Testing Program for Pumps & Valves,Unit 1."

. .. _ . . - - _ - _ _ - . _ - _ .. . . . - --.11IDUQUESNE LIGHT COMPANY jBeaver Valley Power StationjINSERVICE TESTING PROGRAM FOR PUMPS AND VALVESAPPROVAL SHEET-i.)Unit 1 - IST Program1,ISSUE 2Unit HuclearOper. Super.OSCA,,,,,.gRey,staw ==ReviewEffeetive iNo. Pages Issuedlat...

Chapter 1 of S&W SWESSAR-P1, "Introduction & General Description of Plant."

SWESSAR-P1CHAPTER 1INTRODUCTION AND GENERAL DESCRIPTION OF PIANTTABLE OF CONTENTSSectionPageForeword Foreword-11.1 INTRODUCTION 1.1-11.2 GENhRAL PLANT DESCRIPTION 1.2-11.2.1 General 1.2-11.2.2 Site 1.2-11.2.3 Structures 1.2-11.2.4 Nuclear Steam Supply System 1.2-2'1.2.5 Instru...

"NUREG-0737,Suppl 1,SPDS Safety Analysis."

NUREG-0737 Supplement 1Safety Parameter Display SystemSafety AnalysisRochester Gas & Electric CorporationR.E. Ginna Nuclear Power PlantDocket 50-244@~801iSoBgg2O50OOGOQO2popAgoGKPggFNovember 1984J11IICtSAFETY PARAMETER DISPLAY SYSTEMIntroductionNUREG-0696 states that the purpo...

LER 87-016-02:on 870912,determined that measured combined leakage rate from all penetrations & valves exceeded TS limit of 293.75 SCFH.Caused by rust on valves & valve stuck open.Gates valves will be replaced.W/920623 ltr.

_ _ . _ - . _ _ _ . _ ...O 22710200 Avenue NodhCommonwealth Edisonound Ctt:s Nucter Power Station ,Cordova, liknois 61242 9740 .Tek. phone 309'654 2241,RLB-92-097|June 22, 1992'U.S. Nuclear Regulatory CommissionDocument Control DeshHashington, DC 20555Heference: Quad. Cities N...

Forwards response to issues re classification scheme of emergency action levels.

||I|.lasa!? n a w n(Me M er compamy -.|' Cataa ba Nixlow C veratinn DmartmmtGchn * nr. we caccornoad.j!mneitx~ ? ~- krt SC515 ,I |r!MildCh~j.-'DUKEPOWER. March'29,.1997U. S. Nuclear Regulatory CommissionAttention':' Document Control DeskWashington,.DC 20555Subject:Catawht. Nuc...

Proposed Tech Specs revising License Condition 2.C.(28) re requirement for corporate mgt officials on nuclear operations staff & modifying Tables 3.3.7.2-1 & 4.3.7.2-1 to reflect design change.

____ _ _ - _ _ _ _ _ _ _ _ _ _ _ .f1o.,.1.OLCR-NLS-85/06 (Supplemental Submittal)SUBJECT:Facility Operating License NPF-29, page 9.DESCRIPTION:It is proposed to change Operating License Condition 2.C.(28)to read as follows:MP&L shall have on its nuclear operations staff,one or...

Surry Initial Exam 2010-301 Draft SRO Written Exam.

1. 000000000015AG2.4.41 1 Unit 1 Initial Conditions: - Reactor Power = 100% Unit 1 Current Conditions: - 1-E-0, Reactor Trip or Safety Injection has been initiated - RCP-1A seal failure exists and the pump has been secured - RCS leakage is 200 gpm - CETs = 550oF - Co...