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LER 88-002-00:on 880125,reactor trip signal & safety injection occurred.Caused by personnel error.Injection terminated,running equipment secured & Loop 396 restored to original configuration.W/880223 ltr.

___ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _.*LICE 45EE EVENT RETORT (LER)*Facility Bame (1)Docket Number (2)Pace (3).lof|hBraidwoed. Unit 101 51 01 01 01 41 Sl 6 1 3Title (4)Reactor Trip and Safety injection Oue to Cognitive Personnel ErrorEvent Date (5) LER msneer (6)Reco...

Forwards request for addl info re licensee 980408 renewal application,specifically,integrated plant assessment for heating & ventilation systems.

-. _ _ . _ _ _ . _ _ _ _ . . _ _ _ _ _ . . _ . _ _...,l ySeptember 4, 1998'Mr. Chirits H. Cruss, Vice Presid:ntNuclear Energy Division.Baltimore Gas & Electric Company'1650 Calvert Cliffs Parkway ,Lt.aby, MD 20657-4702SUBJECT:REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW O...

August 11, 2003, AP1000 Telephone Conference Call Summary.

November 24, 2003MEMORANDUM TO: Laura A. Dudes, Section ChiefNew Reactors SectionNew, Research and Test Reactors ProgramDivision of Regulatory Improvement Programs, NRROffice of Nuclear Reactor RegulationFROM: John P. Segala, Senior Project Manager /RA/New Reactors SectionNe...

Duane Arnold, Order Modifying Order Dated 01/13/1981 by Continuing Exemption & Extending Completion Dates for installation of plant modifications needed to comply with staff's acceptance criteria contained in Appendix A to NUREG-0661.

Docket No. 50-331 JN1~18Mr. Duane Arnold, President Iowa Electric Light & ower Conpany P.O. Box 351 Cedar Rapids, Iowa 52406 fleitr tlr. Arnold: The Co~iuisSion has issued the enclosed Order vydifying the Order dated January 13, 1961 for the Duane Arnold Enerwy Center. This OU...

Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request.

" EntergyEntergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360Charles M. Dugger Vice President - OperationsFebruary 4, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555SUBJECT: Entergy Nucl...

Oconee, Special Report per Technical Specification 5.6.6., Problem Investigation Process No.: 0-03-0154, 0-03-0415.

Duke R. A JONES10 WPowern Vice PresidentA Duke Energy Company Duke Power29672 / Oconee Nuclear Site7800 Rochester HighwaySeneca, SC 29672864 885 3158864 885 3564 faxFebruary 25, 2003U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Subject: Oconee Nu...

MC 2515 App B, "Supplemental Inspection Program"

1 Note that the assessment process allows the option of not performing a supplementalinspection for a white issue identified as part of a licensee self assessment activity. This is notconsidered a deviation from the action matrix.Issue Date: 03/23/05 B-1 2515 Appendix BAPPEN...

2011/01/17 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 411, FSAR Ch. 14, Supplement 4

1ArevaEPRDCPEm ResourceFrom: BRYAN Martin (EXTERNAL AREVA) [Martin.Bryan.ext@areva.com]Sent: Monday, January 17, 2011 10:13 AMTo: Tesfaye, GetachewCc: DELANO Karen (AREVA); ROMINE Judy (AREVA); BENNETT Kathy (AREVA); WELLS Russell (AREVA)Subject: Response to U.S. EPR Design Ce...

Proposed Tech Spec Pages 3.1-3a,3.6-3,3.8-5,& 3.8-6, correcting typos.

ATTACHMENT I to IPN-89-029REVISED TECHNICAL SPECIFICATION PAGES New York Power Authority Indian Point Unit 3 Nuclear Power Plant Docket No. 50-286 DPR-64 8906010328 890523 PDR ADOCK 05000286I -- PDC: .The dombined capacity of the three pressurizer safety valves is greater than...

2010/05/10 AP-1000 DCD Review - OI-SRP9.1.5-SBPB-01 AP1000 (2A)] for Review / Comments Due: 5/13/2010

1AP1000DCDFileNPEm ResourceFrom: Loza, Paul G. [lozapg@westinghouse.com]Sent: Monday, May 10, 2010 3:31 PMTo: Cummins, Ed; Sisk, Robert B.; Winters, James W.; Corletti, Michael M.; Vijuk, Ronald P.; Russ, Paul ACc: Aiuppy, Sara A; Drog, Elizabeth M.; Lindgren, Donald A.; Loza,...

AREVA Design Control Document Rev. 2 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.4.24 Diverse Actuation System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Tier 1 Revision 2 Page 2.4-124 2.4.24 Diverse Actuation System 1.0 Description The diverse actuation system (DAS) is a non-safety related digital I&C system. The DAS provides the following non-safety related functions:  Automatic antici...

Forwards markup of realistic accident section for facility DES,including revision to dose table.Environ risk remains extremely low.

APR 5 1912 G. W# Knighton, Chief, Project Branch No4 1, DREP INDIAN POINT 2 REALISTIC ACCIDENT ASSESSMENT Enclosed is a mark-up of the Realistic Accident Section for the Indian Point 2 draft Environmental Statement.* There are a number of minor revisions to the dose table due ...

GE-Hitachi ESBWR Design Control Document Tier 2, Rev. 9 - Chapter 15-Safety Analyses

GE Hitachi Nuclear Energy 26A6642BP Revision 9 December 2010 ESBWR Design Control Document Tier 2 Chapter 15 Safety Analyses 26A6642BP Rev. 09 ESBWR Design Control Document/Tier 2 ii Contents 15.0 Analytical Approach ................................................

Westinghouse AP1000 Design Control Document Rev. 16 - Tier 1 Chapter 3 - NON-SYSTEM BASED DESIGN DESCRIPTIONS AND ITAAC - 3.7 Design Reliability Assurance Program

3. Non-System Based Design Descriptions & ITAAC AP1000 Design Control Document Tier 1 Material 3.7-1 Revision 16 3.7 Design Reliability Assurance Program The Design Reliability Assurance Program (D-RAP) is a program that will be performed during the detailed design a...

Westinghouse AP1000 Design Control Document Rev. 17 - Tier 1 Chapter 3 - NON-SYSTEM BASED DESIGN DESCRIPTIONS AND ITAAC - 3.7 Design Reliability Assurance Program

3. Non-System Based Design Descriptions & ITAAC AP1000 Design Control Document Tier 1 Material 3.7-1 Revision 17 3.7 Design Reliability Assurance Program The Design Reliability Assurance Program (D-RAP) is a program that will be performed during the detailed design a...

Final Outlines of Administrative Topics.

ES-301 Administrative Topics Outline Facility: Hope Creek Examination Level: SRO(I1 Date of Examination: 1/5/04 Operating Test Number: 1 A. 1 A.2 Administrative Topidsubject Description A.3 A.4 Conduct of Operations Questions Conduct of Operations JPM Equipment Control JPM Rad...

Press Release-93-171, NRC STAFF PROPOSED $50,000 FINE AGAINST CONSUMERS POWER COMPANY FOR VIOLATIONS OF NRC SAFETY REQUIREMENT AT BIG ROCK POINT PLANT.

No. 93-171 FOR IMMEDIATE RELEASETel. 301-504-2240 (Wednesday, November 17,1993)NRC STAFF PROPOSED $50,000 FINE AGAINST CONSUMERS POWER COMPANYFOR VIOLATIONS OF NRC SAFETY REQUIREMENT AT BIG ROCK POINT PLANTThe Nuclear Regulatory Commission staff has proposed a$50,000 fine agai...

Kewaunee Power Station - Technical Assistance Request for Review of Dominion Energy Kewaunee's LAR No. 263 Regarding Drop Load Analysis (CAC No. L53143).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 4, 2016 MEMORANDUM TO: Jason Piotter, Acting Chief Containment, Structural and Thermal Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards FROM: ...

Arkansas Nuclear One, Unit 1, Tech Spec pages for Amendment 219 re: One Time Extension of the Integrated Leak Rate Test.

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.16 Reactor Building Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the reactor building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendi...

Davis-Besse Nuclear Power Station, Unit 1, Revision 31 to Updated Final Safety Analysis Report, Drawing E-0058B, Rev 14, Sheet 0001A.

NEWFAX 3/85 > a. ~ z ~ 5 % ... ~ ~ >-CD 0 0 > ~ - 0 0 I - 0 0 I ,_ - 0 0 I c:> -z :::::> 0 °" c::> c::> 0 0 ::> > UJ UJ a: a: U"') 0 - 0 0 I I - - 0 0 0 0 I I M ,_ en ,.,., lt') ,.._ 0 c::> I I ...... ~ -Cl z ~ :::::> Cl Q c..> 0 ~ ~ -I;' 0 - I ~ N ~ I ~ N58313 MCC El4 480V 3~...

RO 83-29:drawing reviews identified components requiring corrective measures to prevent operation in manner less than assumed in accident analysis.Tubing installation between pressure transmitter seismically unqualified.

General Offices * Selden Street. Berkn, Connecticut. ca c,,cu m:ro.a . caP.o. BOX 270rmsw w. macs.use ,,s etactaic coHARTFORD CONNECTICUT 06141-0270x .o a ..... no*= co****(203) 666-6911 , , o,. . a co-esOpT*(48,8sLACLEma tednQv CO.PAsswNovember 28, 1983Dr. Thmas E. MurleyMP-5...

Responds to FOIA request for all records re 850220 meeting between NRC & Hydrogen Control Owners Group.Documents listed on encl app responsive to request.

_h"4gioUNITED STATES\ gNUCLEAR REGULATORY COMMISSIONkW$ ,IWASHINGTON, D. C. 20555$ ...../ MAR 2 51985Ms. Susan L. HiattOCRE Representative8275 Munson RoadIN RESPONSE REFERMentor, OH 44060TO F01A-85-127Dear Ms. Hiatt:This is in response to your letter dated February 20, 1985, i...

Confirms completion of listed activities as of end of 14R refueling outage,in response to request.

*w ..s?.'-.il Nuclear :: = = ": L os.GPU Nuclear Corporadon201-316-7000TELEX 136-482'Writers Direct Dial Number. - jii'March 29, 1993C000-93-2049C321-93-2091U.S. Nuclear Regulatory CommissionAttn: Docuruent Control Desk rWashington, DC 20555Gentlemen:Subject: Oyster Creek Nucl...

RO 269/77-22:on 770707,pressurizer water sample valve,RC-6, discovered inoperable.Caused by dirty "finger" on motor contactor preventing motor contactor from energizing & closing valve.Valve RC-6 repaired & tested.

- _ _. .-DUKE POWER COMPANY , ,OCONEE UNIT 1Report No.: RO-269/77-22ggbkeport_Date: July 21, 1977Occurrence Date: July 7, 1977Facility: Oconee Unit 1, Seneca, South CarolinaIdentification of Occurrence: Pressurizer water sample valve, RC-6,discovered inoperableConditions Prior...

Modified Tech Specs Change 23,changing Table 3.6-1 to add automatic valves 1-1A-55 & TV-1A-102B & deleting valve TV-102A.

.TABLE 3.6-1 (Cont.) .5 VALVE ISOLATION TlHEyNUMBER FUNCTION (SEC.)y 12. TV-CC1040 Reactor Coolant Pumps. Cooling Water In 605y 13. TV-CC104C Reactor Coolant Pumps. Cooling Water In 60=*14. TV-CC102A Reactor Coolant Pumps, Dearing and Shroud, 60"Cooling Water OutIS. TV-CC1020 ...