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Event Notification Report for May 05, 2025: 57689

Power Reactor Facility: Callaway RX Type: [1] W-4-LP Emergency Class: Non Emergency
Event Text BOTH TRAINS OF EMERGENCY CORE COOLING SYSTEM INOPERABLE The following information was provided by the licensee via phone and email: "On May 4, 2025, with the plant in mode 4 during restart from a refueling outage, operators were flushing the chemical volume and cont...

Davis-Besse Unit 1 Technical Specification Bases, Revision 20.

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...

Forwards marked-up procedures generation package showing deviations from emergency response guidelines,in response to SER Confirmatory Item 44.

r6Georgi:a Powzf Company. Rout 3 2. Box 299AWayrusboro. Georgia 30830Telephone 404 554-9%1404 724-8114Southern Comparty Services, Inc.Post Office Box 2C25Birmingham, Alabama 35202Telephone 205 870-6011Vogtle Proj.ectSeptember 16, 1985Director of Nuclear Reactor Regulation File...

Event Notification Report for April 08, 2021: 55174

Part 21 Rep Org: Meggitt Safety Systems Inc. Licensee: City: Simi Valley State: CA Agreement: Y Emergency Class: Non Emergency
Event Text PART 21 INTERIM REPORT OF DEVIATION "Meggitt Safety Systems, Inc. (Meggitt) has recently identified situations where the appropriate amount of testing was not performed to verify the acceptability of critical characteristics for commercially procured materials for use ...

Event Notification Report for March 05, 2024: 57004

Power Reactor Facility: Nine Mile Point RX Type: [1] GE-2,[2] GE-5 Emergency Class: Non Emergency
Event Text AUTOMATIC REACTOR SCRAM DUE TO MAIN TURBINE TRIP ON LOW CONDENSER VACUUM The following information was provided by the licensee via email: "On 3/3/24 at 1942 EST, while performing a plant shutdown in preparation for a refuel outage, Nine Mile Point Unit 2 experienced ...

Event Notification Report for June 02, 2025: 57737

Power Reactor Facility: Browns Ferry RX Type: [1] GE-4,[2] GE-4,[3] GE-4 Emergency Class: Non Emergency
Event Text MANUAL REACTOR TRIP The following information was provided by the licensee via phone and email: "At 2247 CDT on 5/30/25, with Unit 2 operating in mode 1 at 39 percent reactor power, the reactor was manually tripped due to a trip of the only operating reactor recircu...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.3.9-24.

LOOP 4 LOOP 1LOOP 2LOOP 3LOOP 1LOOP 4EWLOOP 2 LOOP 3SNUpper Containment RHR Spray HeaderEWRECIRC.SUMPEastRHRHXWestRHRHXRCSCOLDLEGSRCS HOTLEGSChargingPumpsRHR PumpsSI PumpsOutsideContainmentInsideContainmentBoron InjectionTank 900 Gal. R vision: 22 e Change Description: UCR-1...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 5, Figure 5.8-4.

Revision: 24.0 Change Description: UCR-1997, Rev. 0 Title: D. C. COOK UNIT NO. 2 CONTAINMENT PLAN ABOVE ELEVATION 715’ Sheet 1 of 1 UFSAR Figure: 5.8-4 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN For similar locations, in some cases...

Salem - Handouts to Applicants (Folder 3).

List of Handouts for 2014 Written Exam R021: R039: R071: SR013: SR020: A-5-500-EEE-1686, Artificial Island Operating Guide Steam Tables Core Operating Limits Report Unit 2, Rev 5 CFST Table A Subcooling Table Normal Containment S2.0P-IO.ZZ-0006, Hot Standby to Cold Shutdown, R...

Comanche Peak CPSES-04-2007 - Draft Operating Exam Outline Comments.

Draft Operating Exam Outline CommentsScenario 3: BOP may lose component malfunction credit for CCW pump fail to startdepending on how scenario progresses.Scenario 2: BOP may lose component malfunction credit for Containment Isolation Valvefailures depending on how scenario pro...

Responds to open issues identified in NRC 850403 ltr re inservice testing program.Rev B to "Kewaunee Nuclear Power Plant Inservice Testing Plan" encl.

DOCKET # 05000305SUBJECT: Responds to open issues Identified in NRC 850403 tr fe inservice testing programRev B to "Kewaunee Nucleaoe Plant Inservice Testing Plan" end. DISTRIBUTION CODE: A041D COPIES RECEIVED:LTR . ENCL SIZE TITLE: OR Submittal: Inservice Inspection/Testing0...

Forwards simulator four yr certification rept in accordance with 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(vi).Required info included in attachments to ltr.

0Indian Point 3 Nuclear Power Plant P.O. Box 215 Buchanan, New York 10511 914 736.8001March 1, 1999 IPN-99- 025 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555SUBJECT: Indian Point 3 Nuclear Power Plant Docket No. 50-286 License...

Rev 0 to "Oconee MSLB/EQ Analysis."

CERTIFICATION OF ENGINEERING CALCULATION STATION AND UNIT NUMBER - Oconee Nuclear Station, Units 1 2 3 TITLE OF CALCULATION - OCONEE MSLBIE CALCULATION NUMBER - OSC-5460 ORIGINALLY CONSISTING OF: PAGES 1 THROUGH 5 TOTAL ATTACHMENTS -4 TOTAL MICROFICHE ATTACHMENTS - None TOTAL ...

Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Responses to NRC Requests for Additional Information Regarding License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type A and Type C Leak Rate Test Frequencies

~ Southern Nuclear Charles R. Pierce Regulatory Affairs Director 40 Inverness Center Parkway Post Office Box 1295 Bim1ingham. AL 35242 205 992 7872 tel 205 992 760 I fax FEB ~ C 2017 crpierce@southemco.com Docket Nos.: 50-321 50-366 NL-17-0152 U.S. Nuclear Regulatory Commissio...

Summary of 740524 meeting w/util,B&W & United Engineers & Constructors in Bethesda,MD re design criteria for high energy fluid lines.List of attendees & meeting agenda encl.

t..=2JUN 6 274DOCKET NO.: 50-460APPLICANT : WASHINGTON PUBLIC POWER SUPPLY SYSTE:t (WPPSS)FACILITY : WASHINGTON NUCLEAR ONE (WNP-1)'SU19fARY OF MEETING HELD ON MAY 24, 1974 TO DISCUSS DESIGN CRITERIAFOR HIGH ENERGY FLUID LINESOn May 24, 1974, representatives of WPPSS, Babcock ...

Provides W response to FSER open items on AP600.Summary of encl provided in Table 1.W status will be changed to confirm W.

/p-.,i iI!\j.v!'""i-.ja anWestinghouse Energy SystemsPittstugh Prinsytoma 16730 03%Electric Corp 0 fall 00DCP/NRCl209NSD NRC-98 S$l$Docket No.: 52 003January 9,1998.Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20$$$ATiliN110N: T. R. QUAYSulljECT: AP600...

"Sodium Fires Evaluation for FFTF."

'PRELIMINARY/-. ,/Accession No.Contract Program or Project Title: Advanced Reactor Safety Analysis...Subject of this Document: Sodium Fires Evaluation for the Fast FluxTest FacilityType of Document:Technical Report - BNbNUREG-24635iAuthor (s), Affiliation and Address:S.S. Tsai...

Issue 2,Rev 1 to "Inservice Testing (IST) Program for Pumps & Valves."

_l.ODUQUESNE LIGHT COMPANYBeaver Valley Power StationUnit 2INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVESO.Issue 2 Revision 1LPagesissuedOSC Review Date Effective DatedLhY6=" y ,$[Engineering Department ReviewDate/==gFg MjZZ7//gjManager, System and Performance,// |Y $fu ...

Catawba, Units 1 and 2 - Revision 11-1, Update to Emergency Plan.

DukeEnergy®JAMES R. MORRISVice PresidentDuke EnergyCatawba Nuclear Station4800 Concord Rd.York, SC 29745803-701-4251803-701-3221 faxMay 19, 2011U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555-0001SUBJECT: Duke Energy Carolinas, LLCCataw...

Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (FSAR), Chapter 4 - Reactor Coolant System - Design Basis.

Chapter 4 Table of ContentsFSAR UFSAR 1999 Page TOC - 4-1 of 1 CHAPTER 4 TABLE OF CONTENTS4.1 DESIGN BASIS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -4.1-14.2 RCS SYSTEM DESIGN AND OPERATION - - -...

Braidwood Station, Unit 2 - Issuance of Amendments Regarding 2A Essential Service Water Pump Technical Specifications for Pump Repair (CAC No. MF8138).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 23, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: BRAIDWO...