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Proposed TS 2.9 re radwaste disposal sys,deleting 2.9.1 re liquid & gaseous effluents & 2.9.2 re solid radwaste.

g 9.> .TECIINICAL SPECII1 CATIONSTABl,E Ol' CONTESTSPAGEDEITNITIONS 11.0 SAFETY L1h11TS AND LIMITING SAIT:TY SYSTEM SETTINGS 1-11.1 Safety Limits Reactor Core 111.2 Safety Limit Reactor Coolrat System Pressure 141.3 Limiting Safety System Settings. Reactor Protective System 1-...

Responds to NRC 980505 ltr re violations noted in insp repts 50-454/98-09 & 50-455/98-09.Corrective actions:Sys Engineer wrote Action Request 980014475 to investigate & clear blockage in seal table room drain.

- _ - _ . - _ _ _ _ _ _Onnmonwes!A hihon Compan>'.*-* ll> re .i Generating Station,f4 450 North German Church Romill) ron,11. 61010 979 iTel H15-234 5411,June 3, 1998LTR: BYRON 98-0168FILE: 1.10.0101U.S. Nuclear Regula'wory CommissionWashington, DC 20555ATTENTION: Document Con...

San Onofre Units 2 & 3, License Amendment 24 & 13, Modifies TS to Change Maximum Surveillance Interval for 23 ESFAS Subgroup Relays from 6 Months to 18 Months.

1-Docket Nos.: and50-361 50-362Mr. Kenneth P. Baskin Vice President Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770SEP 2 4 1984 Mr. James C. Holcombe Vice President - Power Supply San Diego Gas & Electric Company 101 A...

Draft - Outlines.

ES-401 PWR SRO Examination Outline Printed: 02/24/2003 Facility: Three Mile Island - 1 Form ES-40 1-3 Exam Date: 05/12/2003 Exam Level: SRO IUA Category Points Note: I. Ensure that at least two topics from every IUA category are sampled within each teir (Le., the "Tier Totals"...

Proposed Tech Specs increasing quantity of Cs-137 sealed source for calibr of high-range radiation detection instruments & adding leak test requirements,per Rev 2 to NUREG-0212 (Section 3/4.7.10).

-- - - -ATTACHMENr -·-·· .. --· - -- -- -Consumers Power ·company Palisades Plant Docket 50-255 PROPOSED PAGES PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST ALLOWABLE QUANTITY.OF SOURCE MATERI~L June 20, 1986 _ ....... 10 Pages TSP0686-0097-NL04 · -- -· - UNITED· STATES NUC...

Provides response to RAI re Unit 3 IPE & Unit 2 multi-unit PRA,GL 88-20.

CATEGORY 1REGULA ORY INFORMATION DISTRIBUTIO SYSTEM (RIDS)ACCESSjON NBR:9811100197 DOC.DATE: 98/11/02 NOTARIZED: NOFACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee,. 50'-,296 Browns Ferry Nuclear Power Station, Unit 3, TennesseeAUTH.NAME AUTHOR AFFILIATION'AB...

Rev 6 to CMIP-11, "Classification of Emergency for McGuire Nuclear Station." W/891207 ltr.

~-7_*L!-,s aDUME POWEn Goxiwxy**NUG1JsAH PHODUGTION del %HTMENT il'.O. DOX 33111D,422 Mot' Tit 011U14018 NTita'.1:TCitAlt1DTTI'., N.(L Ull242;.. (704) ara 40.iDecember 7,-1989:rU. S. Nuclear Regulatory CommissionDocument Control Deskwashington, D. C. 20555Subject: McGuire Nucl...

Nonconformance Rept 12 per Condition 2 of CPPR-81 & CPPR-82 re const work performed during Jan-Mar 1976.Resumes of Bechtel Corp & util engineers encl.

,.. .(*dConsumarc Powar CompanyReport #12, December 30, 1975.n)-'\, /Pursuant to Conditions 2 F.B. and 2 F.C. of Construction Permits CPPR-81 and CPPR-82,the following report covers the period January 1 - March 31, 1976.A.Construction work to be performed during the period:JAN...

Bell Bend, Emergency Plan, Revision 4.

BBNPP Rev 4 © 2007-2013 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED BELL BEND NUCLEAR POWER PLANT EMERGENCY PLAN PPL Bell Bend, LLC Revision 4 Approved by ___________________________________________ Date ____________ Senior Vice Presi...

NUREG/CR-7110 Vol 1 Rev 1 "State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis".

State-of-the-Art Reactor Consequence Analyses Project Volume 1: Peach Bottom Integrated Analysis Office of Nuclear Regulatory Research NUREG/CR-7110, Vol. 1, Rev. 1  NRC Reference Material As of November 1999, you may electronically access NUREG-series publica...

AREVA Design Control Document Rev. 5 - Tier 2 Chapter 07 - Instrumentation and Controls - Section 7.8 Diverse I&C Systems

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 5 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...

Forwards response to Generic Ltr 86-06 re implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," per 870417 request for addl info.Info will expedite review & approval of implementation of trip criterion.

RALATORY INFORMATION DISTRISYION SYSTEM (RIDS) ACCESSION NBR:6707150078 DOC.DATE: 67/07/07 NOTARIZED: NO DOCKET # FACIL:50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361 50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUTH.NAME AUTHOR ...

Vogtle, Units 3 and 4, Revised Request for License Amendment: Structural Modules Shear Stud Size and Spacing (LAR 12-001).

Southern NuclearOperating Company, Inc.42 Inverness Center ParkwayBirmingham, Alabama 35242SOUTHERNAMLMAR 1 22012 COMPANYDocket Nos.: 52-025 ND-12-054852-026 10 CFR 50.90U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Southern Nuclear Oper...

Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000022 - RG 1.70.

REGULATORYGUIDE 1.70REVISION 3NOVEMBER1978OFFICE OF STANDARDSDEVELOPMENTU. S. NUCLEARREGULATORYCOMMISSIONSTANDARDFORMATANDCONTENTOFSAFETYANALYSISREPORTSFORNUCLEARPOWERPLANTSLWR EDITIONENT000022 Submitted: March 28, 2012*PAWOOUNUAMDOPA UOWýAc*4 P=A$=l 'Awa. Apo Pamopvm PLN opw...

Vogtle Electric Generating Plant - License Amendment Request to Revise the Minimum Nitrogen Cover Pressure Specified in Technical Specification Surveillance Requirement 3.5.1.3 and Make an Administrative Change to Technical Specification Surveillance...

Mark J. Ajluni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc. 40 Invemess Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7673 July 26, 2011 Fax 205.992.7885 SOUTHERN A COMPANY Docket Nos.: 50-424 NL-11-1004 50-425 U. S. Nuc...

Advanced Topical Report Safety Evaluation (public version) for the US-APWR Non-LOCA Topical Report in support of the US-APWR DCD chapter 15.

- 1 - ADVANCED SAFETY EVALUATION BY THE OFFICE OF NEW REACTORS TOPICAL REPORT MUAP-07010-P, REVISION 4 “NON-LOCA METHODOLOGY” MITSUBISHI HEAVY INDUSTRIES, Ltd DOCKET NO. 52-021 Contents 1.0 INTRODUCTION ..................................................................

Cooper, 10 CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 2012.

NNebraska Public Power DistrictAlways there when you need usNLS2012085 50.59(d)(2)October 10, 2012U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555-0001Subject: 10 CFR 50.59(d)(2) Summary ReportCooper Nuclear Station, Docket No. 50-298, D...

AREVA Design Control Document Rev. 6 - Tier 2 Chapter 07 - Instrumentation and Controls - Section 7.8 Diverse I&C Systems

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 6 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...

NUREG-0800, (160:237) Chpt 10, Section 10.4.8 Draft Rev. 4, Steam Generator Blowdown System (PWR), of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants. LWR Edition, Draft Report for Comment.

NUREG-0800(Formerly NUREG-75/087)U.S. NUCLEAR REGULATORY COMMISSIONSTANDARD REVIEW PLANOFFICE OF NUCLEAR REACTOR REGULATIONDRAFT Rev. 3 - April 1996USNRC STANDARD REVIEW PLANStandard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff r...

Susquehanna, Units 1 & 2, Request for an Amendment to the Technical Specifications: Request for Adoption of TSTF-484, Rev. 0, "Use of TS 3.10.1 for Scram Time Testing Activities" Using the Consolidated Line Item Improvement Process (CLIIP).

N T.C. J. GannonVice President Nuclear OperationsU.S. Nuclear Regulatory CommissionAttn: Document Control DeskMail Stop OP 1 -17Washington, DC 20555PPL Susquehanna, LLC769 Salem BoulevardBerwick, PA 18603Tel. 570.542.3050 Fax 570.542.1504cjgannon@pplweb.comSUSQUEHANNA STEAM EL...

Safety Analysis Report for the HI-STAR 100 Cask System. Table of Contents to Chapter 1.

SAFETY ANALYSIS REPORTfor theHOLTEC INTERNATIONALSTORAGE, TRANSPORTr a aw r n "I- d-u & IxA f V l r~ .~ a- nw.,a AND KbLFU311UKY CASK SYT IhM(HI-STAR 100 CASK SYSTEM)NRC DOCKET NO. 71-9261HOLTEC REPORT HI-951251Prepared by'Eu..'IH LT EI N T E R N AT I O N A LHOLTEC INTERNATION...

NUREG-1433 Vol 1 Rev 3, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications."

NUREG- 1433Vol. 1, Rev. 3Standard TechnicalSpecificationsGeneral Electric Plants,BWR/4SpecificationsU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationWashington, DC 20555-0001NUREG-1433Vol. 1, Rev. 3Standard TechnicalSpecificationsGeneral ElectricBWR/4Speci...

V. C. Summer April 2004 Exam 50-395/2004-301 Sample Plans/Outlines.

Final Submittal V. C. SUMMER EXAM 50-39512004-301 APRIL 19 23,2004 April 28,2004 (written) . . . . . . . . . .:*.++: - c Fac lity: V.C. Summer Date of Examination: 04/19/2004 Exan Level (circle one): mi SRO(l) I SRO(U) Operating Test No.: 1- -- Control Room Systems (8 for RO; ...

Columbia GS TS Pages - Issuance of AMD. 187 Re: Increasing Flexibility in Mode Restraints (Tac. MC1324).

LCO Applicability3.03.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITYLCO 3.0.1 LCOs shall be met during the MODES or other specifiedconditions in the Applicability, except as provided inLCO 3.0.2 and LCO 3.0.7.LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Re...

Salem - Draft Outlines.

Form ES-401-2 ES-401 PWR Examination Outline Facility: Salem 1 & 2 Printed: 0 1 /07/2004 Date Of Exam: 06/11/2004 RO WA Category Points I SRO-Only Points Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the '...