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Proposed tech specs 3/4.3 re adding MS & FW isolation sys actuation logic & relays to functional units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2 & revising Table 3.3-3 by adding Action Statements 27a & 34a.

1. ,||A'ITACHMENT 1TECHNICAL SPECIFICATION CHANGES(MARKED UP)I9604240102 960417PDRADOCK 05000483PPDR_- _ _ _ - _ _ - - - _ - . . ._. _ - - - _ _ _ _ _ _ _. . _ _ _ _ - - _ - - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ - _ - - _ _ _ _ _ _ - _ - _ - _ . _ - - _ - _ - - _ - _...

Rev 2 to Radiation Control Procedure RCP G-5, "Control of Access for Radiation Protection Purposes." Related documentation encl.

e*. .'.'.TNuueER RCP G-5L (3r*S'SPacific Gas and Electric Company'REVISION 2i(-mDEPARTMENT OF NUCLEAR PLANT OPERATIONSDATE1/25/83,OIABLO CANYON POWER PLANT UNIT NO(S)1 AND 2 PAGE 1 OF 8RADIATION CONTROL PROCEDURETm.E; CONTROL OF ACCESS FOR RADIATIONWPROTECTION PURPOSESl 3APPRO...

Fort Calhoun 03-2004 - Final Examination Outline.

02/26/2004 Printed:ES-401Facility: Fort CalhounPWR Examination Outline Form ES-401-23 3 3 3 3 30 2 2 2 123 5 5 5 4 53 2 2 3 3 1 4 3 1 3 31 0 1 1 1 1 1 1 1 1 14 2 3 4 4 2 5 4 2 4 43 2 2 3RO K/A Category PointsTier GroupTotal K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&Abnorma...

Proposed TS Change, Various Administrative Changes.

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 19, 2002 U.S. Nuclear Regulatory Commission Serial No. 02-721 Attention: Document Control Desk SPS-LICJTJN RO Washington, D.C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen: VIRGINIA E...

Safety evaluation re Oyster Creek Nuclear Power Plant Unit 1.

4t, erin'Je:ST D JFILE COPYDecember 23, 1968SAFETY EVALUATIONBY THEDIVISION .OF REACTOR LICENSINGU. S. ATOMIC ENERGY COMMISSIONIN THE MATTER OFJERSEY CENTRAL POWER & LIGHT COMPANYOYSTER CREEK NUCLEAR POWER PLANT UNIT NO. 1DOCKET NO. 50-219Frrnosre 1TABLE OF CONTENTSPage1.0 INT...

NRC Comments on Operating Test and ES-401-9 for NRC Comments on Written Exam for the D.C. Cook Initial Examination - March 2004.

NRC COMMENTS ON THE OPERATING TEST AND ES-401-9 FOR THE NRC COMMENTS ON THE WRITTEN EXAM FOR THE D. C. COOK INITIAL EXAMINATION - MARCH 2004 DC COOK 2004 INITIAL LICENSE EXAM SUBMITTED OPERATING EXAM COMMENTS ADMlN JPMs A. 1 .a (RO) A.2 (RO) A.3 (RO) A.4 (RO) A.1.b (SRO) A.2 (...

North Anna Units 1 & 2 Emergency Response Data System (ERDS) Database Updates.

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 26, 2002 U.S. Nuclear Regulatory Commission Serial No.: 02- 606 Attention: Document Control Desk NLOS/mm Washington, D.C. 20555 Docket Nos.: 50-338/339 License Nos.: NPF-4/7 Gentlemen: VIRGINIA ELECTRIC AND...

Kewaunee, Technical Specifications for Amendment No. 165, Corrected Pages.

Section Title Pane3.2 Chemical and Volume Control System ..................................... 3.2-13.3 Engineered Safety Features and Auxiliary Systems . ........................... 3.3-13.3.a Accumulators ...................... 3.3-13.3.b Emergency Core Cooling System .........

Peach Bottom, Units 2 and 3, Submittal of Changes to TS Bases, Table of Contents Through Bases 3.3.2.1.

! .&:.-N..PECOENERGYPeach BottomAtomic Power StationIMPROVEDTECHNICALSPECIFICATIONS.(UNIT #2 BASES)I .PBAPS UNIT 2 - LICENSE NO. DPR-44TECHNICAL SPECIFICATIONS BASESPAGE REVISION LISTINGB TABLE OF CONTENTSpage(s) i......................... Rev 25B 2.0 SAFETY LIMITS (SLs)B 3.0 ...

Final - Section B Operating (Folder 3), Indian Point 2.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Indian Point 2 Task No: 0140040401 Task Title: Perform the required actions for a malfunction of rod position indicator 01 4A2.06 (2.6/3.0) K/A Reference: 01 4A4.03 (2H2.7) Job Performance Measure No: Sim-A Exa...

Susquehanna - Unit 1 - Technical Requirements Manual Unit 1.

Oct. 28, 2004Page 1 of 1MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2004-43953USER INFORMATIO /Name. RLACH* SE M EMPL#:028401 CA#:0363Address: A2Phone#:T ITTAL INFORMATION:TO: a 0- - ...a.. ....... 10/28/2004LOCATION:r USNRC -FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER...

SAND2010-6109-Revised, "PAT-1 Safety Analysis Report Addendum, Revision 1, Final December 2010," Chapter 2 Cover Page through Section 2.12.4.

PAT-I Safety Analysis Report Addendum Docket No. 71-0361Rev. I2. STRUCTURAL EVALUATIONThe structural evaluation in this addendum examines the incorporation of plutonium metal as anew payload for the PAT-I package. The Pu metal is packed in an inner container (T-AmpouleAssembly...

ABWR Standard Plant Design Certification Renewal Application Design Control Document, Revision 5, Tier 1 and Tier 2.

GE Hitachi Nuclear EnergyRichard E. KingstonVice President, ESBWR LicensingGE Hitachi Nuclear EnergyRegulatory AffairsSecurity Notice P.O. Box 780 M/C A-653901 Castle Hayne RoadThis letter forwards Security-Related Information to Wilmington, NC 28402-0780be withheld in accorda...

"Supplemental Rept to ACRS."

4,01IFRA US NJanuary 8, 1969U. S. ATOMIC ENERGY COMMISSION-. 90 '545"201 40to g lafoiy, file py.DIVISION OF REACTOR LICENSINGSUPPLEMENTAL REPORT TO ADVISORY COMMITTEE ON REACTOR SAFEGUARDS CONSOLIDATED EDISON COMPANY OF NEW YORK. INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3N...

Davis-Besse, Unit 1 - Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9.

FENOC"-A% 5501 North State Route 2FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449Barry S. Allen 419-321-7676Vice President - Nuclear Fax: 419-321-7582June 17, 2011L-1 1-203 10 CFR 54ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555...

Columbia-2009-10-Draft Simulator Scenarios.

INSTRUCTIONAL COVER SHEET PROGRAM OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION LESSON TITLE Swap CRD pumps; RPS-B Trip with a Scrammed Rod That Fails To Insert and FDR-V-4 that Fails to Close; RFP-B Control Oil Pressure Drop; Steam...

2010/04/19 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 326, FSAR Ch 3, Supplement 2

1ArevaEPRDCPEm ResourceFrom: WELLS Russell D (AREVA NP INC) [Russell.Wells@areva.com]Sent: Monday, April 19, 2010 11:55 AMTo: Tesfaye, GetachewCc: BRYAN Martin (EXT); BENNETT Kathy A (OFR) (AREVA NP INC); DELANO Karen V (AREVA NP INC)Subject: Response to U.S. EPR Design Certi...

Proposed TS Figure 3.1-4 re LTOP curve applicable for periods up to end of operating cycle 20,3.1-3 re PORV & PORV & block valve reliability & 3.1-6 re heatup & cooldown limit curves for normal operation.

ATTACHMENT 7 To Letter from C. R. Steinhardt (WPSC) to Document Control Desk (NRC)DatedMarch 26, 1993 PROPOSED TS AMENDMENT NO. 101C Affected TS Pages Table of Contents Section 3.1 Figure TS 3.1-4TABLE OF CONTENTS TECHNICAL SPECIFICATIONS APPENDIX A Section Title Page 1.0 Defi...

Proposed Tech Spec 6.2.3 re plant staff qualifications.

ATTACHMENT 2 TO Letter from C. R. Steinhardt (WPSC) to Document Control Desk (NRC) Dated November 20, 1991PROPOSED TS AMENDMENT NO. 104Affected TS Sections Table of Contents (TS i through TS v) TS Section 6.09112270072 911120 F'R ADOCK 050003 r PDRTABLE OF CONTENTS TECHNICAL S...

2010/07/29 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 354, FSAR Ch. 3, Supplement 4

1ArevaEPRDCPEm ResourceFrom: BRYAN Martin (EXTERNAL AREVA) [Martin.Bryan.ext@areva.com]Sent: Thursday, July 29, 2010 7:40 PMTo: Tesfaye, GetachewCc: DELANO Karen (AREVA); BENNETT Kathy (AREVA); ROMINE Judy (AREVA); CORNELL Veronica (EXTERNAL AREVA)Subject: Response to U.S. EP...

Rotork Inc. Part 21 Notification Sintered Gear.

U.S. Nuclear Regulatory Commission,Washington, DC 20555-0001rotorw8ControlsFrom:To:Date:Subject:Patrick A. Shaw, P.ENRC Document Control DeskSeptember 81h 2010Rotork Inc. Part 21 Notification Sintered GearDear Sir/Madame,Rotork designs and manufactures Valve Actuators; a produ...

Toshiba Design Control Document Rev. 0 - Tier 2 - Chapter 19 - Response to Severe Accident Policy Statement - Appendix 19K - PRA-Based Reliability and Maintenance

PRA-Based Reliability and Maintenance 19K-1RS-5146900 Rev. 0Design Control Document/Tier 2 ABWR19K PRA-Based Reliability and Maintenance19K.1 IntroductionIn this appendix, the results of the PRA are reviewed to determine the appropriate reliability and maintenance actions th...

E-mail from OHara to Bearde, Salem Unit 1 ISI Feeder.

Contil, RichardFrom:Sent:To:Cc:Subject:Attachments:OHara, Timothy .,Wednesday, June 30, tIOT114 PMBearde, DianeConte, Richard; Cook, WilliamSalem Unit 1 ISI FeederSalem 1-(2010003)(OHara)(ISI-Rpt)(Tl-1 72)(04-10)(6-28-201 0).docHello Diane,Attached is the completed Salem Unit...

2010/11/15 Seabrook LR - Draft Phone Call Summary

1SeabrookNPEm ResourceFrom: Wentzel, MichaelSent: Monday, November 15, 2010 7:35 AMTo: Cliche, RichardSubject: Draft Phone Call SummaryAttachments: 110810, Summary of Telephone Conference Call Held Between NRC and NextEra Seabrook, Concerning the Draft RAIs Pertaining to the S...

Wolf Creek, License Amendment 176 re: Replacement of Main Stream and Feedwater Isolation Valves.

March 21, 2008 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 SUBJECT: WOLF CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE: REPLACEMENT OF MAIN STEAM AND MAIN FEEDWATER ISO...