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Event Notification Report for November 5, 1999

U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/04/1999 - 11/05/1999 ** EVENT NUMBERS ** 35790 36263 36394 3...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.3.2-2, Pumped Safety Injection Flow Rate - Injection Phase - Faulted Loop CHG Spilling to RCS Pressure - Faulted Loop HHSI / RHR.....

AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-2 Title: Pumped Safety Injection Flow Rate- Injection Phase - Faulted Loop CHG Spilling to RCS Pressure - Faulted Loop HHSI / RHR Spilling to Containment Pressure Chang...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.2.5-5A.

AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.2.5-5A Title: Unit 2 Cycle 19 SLB DER Inside Containment with Power Core Average Temperature, RCS Pressure, and Pressurizer Water Volume versus Time Change Description: UC...

Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.8-1 through 3.8-56.

SECURITY -RELATED INFORMATION-WITHHELD UNDER 10 CFR 2.390 REVISION 6, FEBUARY 15, 1987 PSEG NUCLEAR, L.L. C. CONTAINMENT BUILDING CROSS SECTION SALEM NUCLEAR GENERATING STAT ION Updated FSAR 3.8-1 © 2000 PSEG Nuclear, LLC. All Reserved. Security-Related Info...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.3.9-25.

EDUCTOREDUCTOREastContainmentSpray PumpWestContainmentSpray PumpRecirc SumpTo RHRTo RHRRecirc SumpESWESWESWESWSPRA YADDITIVETANKLower Containment VolumeUpperContainmentVolumeWest RHR East RHR Revision: 22 Change Description: UCR-1917 AMERICAN ELECTRIC POWER COOK NUCLEAR PLA...

Commanche Peak Steam Electric Station Unit 2, Submittal of Unit 2 Fifth Refueling Outage Inservice Inspection Summary Report.

STXUTXU Electric Comanche Peak Steam Electric Station P.O. Box 1002 Glen Rose,TX 76043 Tel: 254 897 8920 Fax: 254 897 6652 Iterryl@txu.comC. Lance Terry Senior Vice President & Principal Nuclear OfficerRef. # 10CFR50.55a(g)CPSES-200100378 Log# TXX-01025 File# 10010.1 905.2 (cl...

Forwards revisions to emergency response data sys data point libraries that clarify & update 920710 libraries.

_.'.'',Northem States Power Company'414 Nicollet MallMinneapolis, Minnesota 55401-1927Telephone (612) 330-5500March 19, 199310 CFR Part 50, Appendix EU S Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555!,PRAIRIE ISLAND NUCLEAR GENERATING PLANTiDocke...

Davis-Besse Nuclear Power Station, Unit 1, Revision 26 to Technical Specification Bases.

Davis-Besse Tech Spec Bases Index B 2.0 SAFETY LIMITS (SLs) B 2.1.1 Reactor Core SLs B 2.1.2 Reactor Coolant System (RCS) Pressure SL B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY B 3.1 REACTIVITY CONTROL SY...

Rev 8 to "Comanche Peak Steam Electric Station Units 1 & 2 Inservice Testing Plan for Pumps & Valves First Interval."

_ - . - _ _ . . _ . _ _ _ . - _ _ . _ _ _ . _ _ _ . . _ - _ _ - _ _ . _ _ _ _ . _ . . _ _ . _ _ _ . _ _:tii:ii:i4 COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2'INSERVICE TESTING PLAN FOR PUMPS AND VALVESFIRST INTERVAL 4!!REVISION 8kb G'5 M Date: /-2N 7Prepared By:Engineerin...

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

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 2 Page 6.2-224 Table 6.2.4-1—Containment Penetration, Isolation Valve, and Actuator Data Sheet 1 of 22Penetra-tion No.GDC Req.System Name Fluid Line Size (in)EssentSystem PotentBypassPathValve NumberValveLocation LLRTValv...

"Revised Rept on Reanalysis of Safety-Related Piping Sys."

... . _ . . _ _ _SURRY F0WEP STA!!CN, UNIT 1REVISED REFCET ON THEREANALYSIS OF SAFETY-RELATED PIPING SYSTEMSSURRY POWER STATION, UNIT 1VIRGINIA ELECTRIC AND POWER CCMPANY>January 1980_.1773 327Stene 2 Webster Insincering CcrporationEcston, M ssachusetts8 0 01210lE L's.___. - -...

Final ASP Analysis - Davis-Besse (LER 346-98-011).

Annendi B LRN.369-1B.6 LER No. 346/98-011 Event Description: Manual reactor trip while recovering from a component cooling system leak and de-energizing safety-related bus D 1 and nonsafety-related bus D2 Date of Event: October 14, 1998 Plant: Davis-Besse 1 B.6.1 Event Summary...

Indian Point Station, Unit 2 - Draft - Outlines (Folder 2) (Facility Letter Dtd - 07/18/2016).

• ~Entergx NL-16-080 July 18, 2016 Mr. William Dean Regional Administrator Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd Suite 100 King of Prussia, Pennsylvania 19406-2713 Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 T...

Columbia Generation Station - Volume 13, Emergency Preparedness Procedures 13.1.1, Rev. 049; 13.1.1A, Rev. 033; 13.8.1, Rev. 038 and 13.14.11, Rev. 013.

DISTRIBUTION -VOLUME 13- EMERGENCY PREPAREDNESS PROCEDURES Distribution.Date: 01/17/18 LMB Filed By: Procedure Number Revision Procedure Number Revision Procedure Number Revision 13.1.1 049 13.1.1A 033 13.8.1 038 13.14.11 013 TO: ENERGY NORTHWEST EXTERNAL CONTROLLED COPY PROCE...

Fermi 2 Technical Requirements Manual, Volume I, Revision 39

K3'iDETROIT EDISON - FERMI 2 AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST 06/22/00To: 00935PAGE 1US NRC DOCUMENT CNTRL DESKWASHINGTON, DC 20555 Media: 8 1/2 X 11 Number Cnt Issue DTC Doc. Serial Number Page Rev Copies Lvl Date Sec Status TMTRM TRM VOL I 39 11 IR 06/...

Columbia Generating Station - Init Exam - 09/2004 - Draft RO Written Examination.

Columbia Generating Station Written Examination Key September 2004 With a LOCA initiation signal present, an automatic trip of the HPCS Emergency Diesel Generator will occur if there is a(n): A. low lube oil pressure. B. high crankcase pressure. C. generator overcurrent. D. in...

IR 05000336-98-002 & IR 05000423-98-002, On 05/18/1998 - 05/22/1998, Millstone Nuclear Power Station, Units 2 & 3, implementation of the maintenance rule, as required by 10 CFR 50.65.

U.S. NUCLEAR REGULATORY COMMISSIONREGION IDocket Nos.License Nos.Report Nos.Licensee:Facility:Location:Dates:50-336,50-423DPR-65, NPF-4950-336/98-02,50-423/98-02Northeast Nuclear Energy Company (NNECo)Millstone Nuclear Power Station, Units 2 and 3Waterford, ConnecticutMay 18 -...

Waterford, Unit 3, License Amendment 109, Amendment Changes Appendix A TS By Revising Administrative Controls Section of TS by Removing Functions Under Review Audit from TS by Relocating Those Items In Quality Assurance Program Manual.

Mr. Ross P. Barkhurs Vice President Operat'rons Entergy Operations, Inc. P. 0. Box B Killona, LA 70066July 6,-.,495SUBJECT: ISSUANCE OF AMENDMENT NO. 109 TO FACILITY OPERATING LICENSE NPF-38 - WATERFORD STEAM ELECTRIC STATION, UNIT 3 (TAC NO. M90172) Dear Mr. Barkhurst: The C...

LaSalle, Units 1 & 2, Issuance of Amendment No. 20, changing TS for Units 1 & by eliminating the reactor water cleanup pump room ambient and differential temperature monitoring requirements.

UNITED STATES A ,NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-373/374 JAN 0 8 1M5 Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690 Dear Mr. Farrar: Subject: Issuance Amendment No. 20 to F...

Draft - RO & SRO Written

QUESTION: #1 (1.0) You have transitioned to FRP.1 responding to an orange path on containment integrity. Identify which condition would warrant you to transition out of FRP.1 prior to its completion. a. An orange path on heat sink. b. A yellow path on subcriticality. c. A r...

Peach Bottom Station, License Amendments 49 & 48, Revising TS To Increase Total Storage Capacity Of Spent Fuel Pools At Peach Bottom Station Units No.2 & 3 From 2220 To 5632 Fuel Assemblies.

Distribution L.,Pocket ORB #3 Local PDR NRC PDR VStel lo .NOVEMBER 3 0 I BGrimes aket Nos. 50-277R TIppolito and 50-276f." SSheppard DVerrelli Attorney, OELD OI&E (5) WBones (8) Mr. Edward G. Bauer, Jr., Esquire BScharf (10) Vice President and General Counsel JMcGough Philadel...

Technical Specifications for Indian Point Nuclear Generating Unit No. 2, License Amendment, Issuance of Amendment, Re: Conversion to Improved Technical Specifications (TAC No. MB4739).

ATTACHMENT 2 TO NL-03-158Copy of 1P2 Improved Technical Specifications Annotated as Amendment 238Entergy Nuclear Operations, Inc.Indian Point Unit No. 2Docket No. 50-247Facility Operating License No. DPR-26Appendix A - Technical SpecificationsTABLE OF CONTENTS1.0 USE AND APPLI...