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Application for amend to License NPF-42,revising TS Tables 3.3-1,4.3-1,3.3-3 & 4.3-2 & associated bases to increase surveillance test intervals & allowed outage times for analog channels of ESFAS & reactor trip sys.

1i|.-,.*|,LF CREEKW@ NUCLEAR OPERATING CORPOfMTIONFonent T. Rhodesvoce PrecedsmeEnsneenne a wennow sewei March 1, 1991ET 91 0047U. S. Nuclear Regulatory Commission;ATTNi Document Control DeskHall Station P1-137Vashington, D. C. 20555Reference: 1) Letter NO 91 0065 dated Februa...

Rev 2 to WCAP-13234, "Test Spec for Long-Term Cooling Test."

iNMEEllllECWA.as$sh.Am.esw.guR HAW,nwyWMRh 8[ Q p qkia(g$P '# -eumh hkhh" Ih44w 'e aengd@@(a$$n$$ng;pM4hbM>is$asgkhkhdhbpww.$.m n$m$$,,$$,mam; nag, ban @gmeNRRENBf Y,%l$la c.a%g eMg yw.hp;$#ha hhfffkg[kjhf$ f ?*p"-sp$a|fshNP$$gp|[!!!pgg.gg.ggg*g[y~sg g.ga;2sfgdkhMkdhkf;b. k * ...

Rev 2 to "GESSAR-II App 15.D.3,BWR/6 PRA," "GESSAR-II App C, Event Trees" & "GESSAR-II App D,Fault Trees."

''.:.^.;; .. ,i.-,..GESSAR-II Appendix 15D.3, BWR/6Probabilistic Risk Assessment (790 pages)1e!?-t:.CURRAN 84-A-66 PDR-._,.iGESSAR II22A7007...238 NUCLEAR ISLANDRev. 2GENERAL ELECTRIC COMPANYPROPRIETARY INFORMATIONClass III'1.4.6Reliability Model Definitions (Continued)BOP sys...

VALUE/IMPACT ANALYSIS FOR EVALUATING ALTERNATIVE MITIGATION SYSTEMS.

. _ _ _ .- -..NUREG/CR-4243Value/ Impact AnalysisforEvaluatingAlternativeMitigation Systems;i;.!;Prepared by W. E. Kastenberg, l. Catton, J. N. Castle, J. L. Dooley, R. P. HammondlR & D AssociatesI)i Prepared forU.S. Nuclear Regulatory'Commission I!! 1:!,w ...U,%88020R-:,_ .__...

Outline Submittal for the Prairie Island Initial Examination - September 2003.

ES-401 PWR Examination Outline Form ES-401-2NUREG-1021, Draft Revision 9 Page 22 of 34Facility: Prairie Island Date of Examination: 09/08/2003Examination Level (circle one): RO / SRO Operating Test Number: ______Administrative Topic Describe activity to be preformed:Conduct...

Final Section A Operating.

-~ ES-301 Administrative Topics Outline Form ES-301-1 Facility: Vermont Yankee Date of Examination: 10/3/03 Examination Level (circle one): / SRO Operating Test Number: 1 Administrative Topic 4ksw@m+ (see Note) w .. &I Conduct of Operations A2 Conduct of Operations fu Equipmen...

Rev 0 to "Westinghouse Test Reactor TR-2 Final Decommissioning Plan."

.- -. . . . - .. .- - - - - _ _.,!| WESTINGHOUSE ELECTRIC|CORPORATIONi4|WESTINGHOUSE TEST|IEACTOR:!;TR-2,;Ia!FINALDECOMMISSIiONING!PLAN,'l!; Revision 0|July 25,1997,!Prepared By NUMEGA ,.2! A Team of:| Westinghouse Electric Corporation! Morrison Knudsen|Public Service Company ...

Rev 0 to J-SPA-269, "ESFAS Radiation Monitoring Single Failure Analysis."

. . . . - - . ._ .. . .. . . _ _ _ . . . . -- ._ _~_.i 1||! !!'I||i ,';i.ENCLOSURE 2,|Calculation Numb 6r J-SPA-269iInterim Calculation Change Notice Number F-718IESFAS Radiation Monitoring Single Failure AnalysisiSan Onofre Nacisar Generating Station|Units 2 and 3 -|ilIi!|',I...

Comments on final draft Tech Specs per 851021 ltr.Changes discussed w/NRC Tech Spec Review Group reviewer.

_- _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _T!!C;EUEi.JM!i. C e f h i c ! L L U M I N AT b1 G C a ni P A iH ,P.O. box 5000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLDG. - $5 PUBLICSCUAREServing The Best Location in the NationMURRAY R. EDELMA...

LER 95-033-11:on 951114,TS surveillance requirement implementation deficiencies occurred.Caused by lack of documentation of annunciation for previous surveillances. SDV bypass logic were satisfactorily tested.W/961101 ltr.

. . ...---. - - --= - - - - - - ~ - - - . -.2.O PSEG|;j Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236Nm: lear Budmess Un t -iNOV 011996|LR-N96349';:1U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555|Dear S...

"McGuire Nuclear Station Safety Analysis for Upper Head Injection Elimination."

. _..MCGU1RL NUCLEAR STATIONSAFETY ANALYSIS FOR UH1 ELIMINATIONl!||'.SEPitM8tR 1905||t0510000364 05t00['ADOCK OD0% jY *DH,1099hy:10/002005,*_ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-- . _ _ _ - ___ --~.,15.6.4.1 Identification of Causes and Accident Description...

Transcript of ACRS Subcommittee on Metal Components 870326 meeting in Washington,DC.Pp 1-210.Supporting documentation encl.

_ _-_,OgIGINAL..UlN H E.D STATES; o'"1 NUCLEAR REGULATORY COlW4SSIONPk,': < - . u---=,t === ',*DOCKET NO: IN THE MATTER OF:.ADVISORY COMMITTEE ON REACTOR SAFEGUARDStu.jSUBCOMMITTEE ON METAL COMPONENTS ',,\v <.4,Ov.,.LOCATION: WASIIINGTON,D. C. PAGES:1210..,DATE: T!!URSDAY, MAR...

Proposed revised Tech Specs & license conditions,per Generic Ltr 86-10, "Implementation of Fire Protection Requirements." Supporting documentation encl.

- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _*..- >,.x' tI REVIStoy3|3INDEX .'LIMlflNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS(-ISECTIONPAGE'INSTRUMENTATION (Continued) -3/4.3.3 MONITORING INSTRtMENTATIONRadiation Moni toring for Pl ant Operations. . . ....

Forwards proposed response to 980305 RA re proposed conversion to improved std TS.Util would like to use proposed response as basis for telcon to be conducted wk of 980330.

.'{ Nuclear Operating ompany{soah reasinyenstkcowceneratogstat&w ra sarzsr ni,sme th rans77483mMarch 26,1998NOC-AE-000118File No. G20.02.01{10CFR50.90{10CFR50.92U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555South Texas ProjectUnits 1 an...

Millstone Power Station, Unit 3 Chemistry Procedure CP 3804AC, "Liquid Waste Sample Sink," Revision 002-02.

UToFacilityAddress(: DOCUMENT CONTROL DESK: MP Department : 806: NUC REGULATORY COMMISSION (0140)DOCUMENT CONTROL DESKWASHINGTON, DC 20555PASSPORT DOCUMf'TRANSMITTALPage: 1In .IEEEU .. ,_From : NDSDate/Time : 07/27/04 14:Trans No. : 000063343Total Items: 00001CONT DOCUMENTSTra...

LER 02-004-04 Shearon Harris Nuclear Power Plant Unit 1 re Unanalyzed Condition Due to Inadequate Separation of Associated Circuits.

Progress EnergyOCT 1 2 ?OB4U.S. Nuclear Regulatory Commission Serial: HNP-04-128ATITN: NRC Document Control Desk 10 CFR 50.73Washington, DC 20555SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1DOCKET NO. 50-400/LICENSE NO. NPF-63LICENSEE EVENT REPORT 2002-004-04Ladies and Gentlemen:T...

Emergency operating procedures generation package,consisting of emergency procedure guidelines,plant-specific writers guide for emergency procedures,procedure validation program & emergency operating procedures training program.

WNP-2EMERGENCY PROCEDURE GUIDELINESFEBRUARY 1, 19838304080297 830323PDR ADOCK 05000397A PDRINTRODUCTIONThis RPV Control Guideline maintains adequate core cooling, shuts down the reactor,and cools down the RPV to cold shutdown conditions. This guideline is enteredwheneverlow=-R...

NRC-2016-000558 - Resp 3 - Final, Agency Records Subject to the Request are Enclosed (Part 1 of 2).

Branch Chief Turnover for Tony- Nov 16- Nov 20, 2015 Meetings Monday • 8:00 a.m. - 8:30 a.m. Management Meeting - 13D20 • 1 :00 p.m. - 2:00 p.m. Division Leadership Meeting - 0884 • 2:00 p.m. - 2:30 p.m. Fukushima Interactions - 0884 Tuesday • Commission Meeting on Tier 2/3 - ...

LER 88-018-01:on 881030,drywell head seal had as found leak rate higher than TS 3.7.A.2.b(2)(a) limits.Caused by improper seating of outer gasket due to installation procedure deficiency.Procedure revised.W/910506 ltr.

' ' ... 0 Comm9'ealth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois .60450 Telephone 815!942-2920 EDE LTR #91-259 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 May 6, 1991 ·Licensee Event Report #88-018-1, Docket #050237 is bei...

Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 07, Instrumentation and Controls.

DRESDEN — UFSAR Rev. 8June 20097.0 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 ...

LaSalle County Station, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-334-A, "Relaxed Surveillance Frequency for Excess Flow Check Valve Testing," and Inservice Testing (IST) Relief Request RV-02 Related .....

_ow 4300 Winfield Road Warrenville, IL 60555 ExeLon Generation 630 657 2000 Office 10 CFR 50.55a 10 CFR 50.90 RS-18-017 February 7, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Renewed ...

Indian Point Unit 3 Revision 7 to Updated Final Safety Analysis Report, Chapter 18, Appendix A, License Renewal,

IP3 FSAR UPDATE Appendix A, Page 1 of 36 Revision 07, 2017 APPENDIX A LICENSE RENEWAL A.1 INTRODUCTION This appendix provides the information submitted in an Updated Final Safety Analysis Report Supplement as required by 10 CFR 54.21(d) for the Indian Point Energy Center (I...

Redacted - Susquehanna Steam Electric Station, Units 1 & 2, Revision 68 to Final Safety Analysis Report, Chapter 1, Introduction.

SSES-FSAR Text Rev. 60 FSAR Rev. 64 1.1-1 1.1 INTRODUCTION 1.1.1 TYPE OF LICENSE This FSAR is submitted by PPL Susquehanna, LLC in support of its application for an operating license for Susquehanna Steam Electric Station (Susquehanna SES) Units 1 and 2. 1.1.2 IDENTIF...

Part 02 - Final Safety Analysis Report (Rev. 1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Design Cat I Structures - Pages 1 - 140

NuScale Final Safety Analysis Report Design of Category I StructuresTier 2 3.8-1 Revision 13.8 Design of Category I StructuresThe NuScale Power Plant design includes two Seismic Category I structures, the Reactor Building and the Control Building, and one Seismic Category II s...

Peach Bottom Atomic Power Station, Units 2 and 3 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 9, 2018 Mr. Bryan Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: PEACH BOTTOM ATOMIC PO...