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Insp Rept 50-219/87-33 on 871005-1130.No violations noted. Major areas inspected:operations,radiation control,physical security,surveillance,outage activities,emergency drill & restart-related events.

p1.,',U. S. NUCLEAR REGULATORY COMMISSIONREGION IReport-No. 50-219/87-33Docket No. 50-219License No. DRP-16 Priority Category C--Licensee:GPU Nuclear Corporation1 Upper Pond Road,Parsippany, NJ07054Facility Name: Oyster Creek Nuclear Generating' StationInspection At: Forked Ri...

South Texas Project, Units 1 & 2, Technical Specification Bases Control Program (Section 6.8.3.m).

Nuclear Opert gCmpnSouthi Tozs Pqoect ieck Generatng Station P0. Aom 289 Wads.vthw Tew2 77483April 29, 2010NOC-AE-1 00025541 OCFR50.36U. S. Nuclear Regulatory CommissionAttention: Document Control DeskOne White Flint North11555 Rockville Pike.Rockville, MD 20852-2738 South Tex...

Palo Verde-2009-11-Draft RO Written Exam.

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2009 Reactor Operator Exam OPTRNG_EXAM Page: 1 of 135 09/30/09 1 This Exam Level RO Apears on: 2009 SRO EXAM Tier 1 Group 1 K/A # 2.4.11 Importance Rating: 4.00 Unit 1 is operating at 100% power w...

2010 Clinton Power Station Initial License Examination As-Administered Dynamic Simulator Scenarios.

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: One Operating Test No.: 2010301 Examiners: ____Carl Moore ______________ Operators: ____________________ ____Dell McNeil______________...

Calculation CC-AA-309-1001, Rev. 5, "To Establish Limiting Demand for N(2) for the CAD System & the SGIG System for Dual Unit Operation."

ATTACHMENTPEACH BOTTOM ATOMIC POWER STATIONUNITS 2 AND 3NRC Docket Nos. 50-277 and 50-278Renewed Facility Operating License Nos.DPR-44 and DPR-56Calculation PM-0375, Revision 4, "To Establish Limiting Demand for N2 for theCAD System and the SGIG System for Dual Unit Operation"...

Susquehanna, Unit 2, Revisions to Technical Requirements Manual.

Apr. 21, 2011Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2011-21499USER INFORMATION:GERLACH*ROSE M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSE M 04/21/2011LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CE...

"Inadequate Core Cooling Decay Heat Removal Sys Mode of Operation."

~- A j~ ' oi ow ~ ~ '" Au, 0 TF Vell Z _2 2 Ap ~U 4~4BWNP-20004 (6-76)BABCOCK & WILCOX NUCLEAR POWER GENERATION 0IVISION TECHNICAL DOCUMENT EMERGENCY OPERATION SPECIFICATION / 69 - 1106921 - 00 Doc. ID - Serial No., Revision No. for INADEQUATE CORE COOLING DECAY HEAT REMOVAL ...

LER 97-010-01:on 970501,SI actuation occurred while testing MSSVs.Caused by one MSSV MS-46C,on MSL for SG 23 being stuck open.Reactor was safely brought to cold shutdown conditions. W/970909 ltr.

Stephen E. Quinn Vice President Consolidated Edison Company of New York, Inc. Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 734-5340 September 9, 1997 Re: Indian Point Unit No. 2 Docket No. 50-247 LER 97-10-01 Document Control Desk US Nucl...

Pilgrim Watch Reply to Entergys and NRC Staffs Answers to Pilgrim Watch Request for Hearing on A New Contention Regarding Inadequacy of Environmental Report, Post Fukushima.

1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of Docket # 50-293-LR Entergy Corporation Pilgrim Nuclear Power Station Li...

Provides second response to IE Bulletin 79-01B re environ qualification of Class IE equipment.Detailed repts w/sys master lists & equipment qualification forms encl.Repts revise & supersede 800303 submittal re licensee actions.

~' . ,AUft[PHILADELPHIA ELECTRIC COMPANY(I,hly|}2301 M A R K ET STR EETgP.O. BOX 8699PHILADELPHIA. PA.19101SHIELDS L. D ALTROFF.goELECTM C PR CTION'. . aApril 15, 1980Docket Nos. 50-27750-278IE Bulletin 79-OlB.Mr. Boyce II . Grier, DirectorOffice of Inspection & EnforcementReg...

Indian Point Unit 3 - Draft - Outlines (Folder 2).

ES-401 PWR Examination Outline Form ES-401-2 Facilit~: IPEC Printed: 07/25/2014 Date Of Exam: 05/11/2015 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* 1. 1 3 3 3 3 3 3 18 0 0 Emergency 2 1 2 2 1 2 1 9 0 0 & N/A N/A Abnormal Tier...

Final - Outlines

JUSTIFICATION FOR OUTLINE CHANGES: 1. RO WRITTEN EXAM * Tier 2/Group 1 Item 059 MAIN FEEDWATER Changed category A2 11 to category A4 3 due to transposing error from original outline selection 2. SRO WRITTEN EXAM * Tier I/Group 2 Item 00038 Steam Generator Tube Rupture Changed ...

AREVA Design Control Document Rev. 1 - Tier 2 Chapter 06 - Engineered Safety Features - Tables for Section 6.2.4

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 1 Page 6.2-173 Table 6.2.4-1—Containment Isolation Valve and Actuator Data Sheet 1 of 18Pent-ration No. (JMK)GDC Req.System Name Fluid Line Size (in)EssentSystem PotentBypassPathValve NumberValveLocationType C Leak TestVa...