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Forwards rept of 10CFR50.59 safety evaluations.

-_' , -,ee3...FloridaPowerCORPORATIONcknaat Na 60302December 2, 19943F1294-02U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D. C. 20555Subject: Report of 10 CFR 50.59 Safety EvaluationsDear Sir:Florida Power Corporation (FPC) is subn.itting the attac...

Insp Rept 50-336/88-07 on 880322-0502.Violation & deviation noted.Major areas inspected:plant operation,surveillance, maint,radiation protection,physical security,outage activities,motor-operated valve testing & allegations.

.a|1=c';..U.S. NUCLEAR REGULATORY COMMISSIONREGION IReport No. 50-336/88-07Docket'No. 50-336 1.icense No: OPR-65Licensee: Northeast Nuclear Energy CompanyP.O. Box 270. Hartford, CT06101-0270Facility: Millstone Nuclear Power Station, Waterford, ConnecticutInspection at: Millsto...

Proposed tech specs,modifying bypass logic for MSLI valve isolation acuation instrumentation on condenser low vacuum.

_. .. ._ ._ .. _. . . . . _ _ . _ . . _ . _ _ _ . . . _ _ . _ _ . .*..1'ATTACHMENT 3PROPOSED AMENDMEhTS TO THE .LICEt|SEITECHNICAL SPECIFICATIONS lNPF-11 NPF-18|_3/4 3-11* 3/4 3-11*3/4 3-14 3/43143/4 3-20* 3/4 3-20'3/4 3-22 3/4322B 3/4 3 2* B 3/4 3-2*B 3/4 3 2a B 3/4 3-2a!||Il...

"Functional Design Spec for SPDS Enhancement Program."

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Forwards five discrepancy repts (DRs) identified during review activities for Independent Corrective Action Verification Program.Twelve DRs have been reviewed & accepted.Thirteen DRs have been reviewed but not accepted.

*m.. e-s.';JbN.64$Sar gerit & Luncty"c.Don K. Schopfer"7Senior Vice President312-269 4078March 301998Project No. 9583-100Docket No. 50-423.Northeast Nuclear Energy CompanyMillstone Nuclear Power Station, Unit No. 3iIndependent Corrective Action Verification Program)United Stat...

AREVA Design Control Document Rev. 3 - Tier 2 Chapter 10 - Steam and Power Conversion System - Section 10.4.9 Emergency Feedwater System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 3 Page 10.4-7510.4.9 Emergency Feedwater SystemThe emergency feedwater system (EFWS) supplies water to the steam generators (SG) to restore and maintain water level and to remove decay heat following the loss of normal fe...

AREVA Design Control Document Rev. 6 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.1.3 Fuel Pool Cooling and Purification System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 6 Page 9.1-249.1.3 Fuel Pool Cooling and Purification SystemThe Fuel Pool Cooling and Purification System (FPCPS) is designed to maintain the spent fuel pool (SFP) water temperature and water level within prescribed limit...

Transcript of the Advisory Committee on Reactor Safeguards Fukushima Subcommittee - September 18, 2013.

Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards Fukushima Subcommittee Docket Number: (n/a) Location: Rockville, Maryland Date: Wednesday, September 18, 2013 Work Order No.: NRC-260 ...

U.S. EPR Design Certification RAI 579 Response - U.S. EPR FSAR Markups.

April 28, 2014 David Noxon U.S. EPR Design Certification RAI 579 Response – US EPR FSAR Markups Page 1For Information Only2 NRC Meeting – RAI 579 FSAR Mark-ups– April 28, 2014 --- For Discussion Purposes Meeting Purpose and Outline  Purpose of this meeting is to gain NRC ...

IR 05000306-13-011(DRS); 08/7/2013 - 01/16/2014; Prairie Island Nuclear Generating Plant, Unit 2; Steam Generator Replacement Inspection.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 February 27, 2014 Mr. Kevin Davison Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East W...

Sequoyah Initial Exam 2012-302 Final SRO Written Exam.

ES-401 Site-Specific SRO Written Examination Form ES-401-8Cover SheetU.S. Nuclear Regulatory CommissionSite-Specific SRO Written ExaminationApplicant InformationName:Date: Facility/Unit:Sequoyah Station Unit I & 2Region: I LI ii L] HID IV LI Reactor Type: W[l CELIBWLI GEDStart...

D.C. Cook, Units 1 & 2, Redacted Version of Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Events (Order Number EA-12-049).

NNWA,..A Indiana Mlchlwall PowerHCHWAII Cook Nucleor PlantJim me One Cook PlaceBrldqinen, Ml 49105A unit ofAmedcan Electric Power Indiana M lc9ganPowarxmFebruary 27, 2013 AEP-NRC-2013-1310 CFR 50.54(f)10 CFR 50.4Docket Nos.: 50-31550-316U.S. Nuclear Regulatory CommissionATTN:...

Susquehanna, Unit 2, Revision to Technical Requirements Manual.

Apr. 26, 2013Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2013-18765USER INFORMATION:GERLACH*ROSE M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSE M 04/26/2013LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CE...

Letter re: Endangered Species Act section 7 consultation at Salem and Hope Creek Generating Stations.

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038 0 PSEG CERTIFIED MAIL RETURN RECEIPT REQUESTED May 29,2013 LR-E13-0072 Ms. Julie Crocker National Marine Fisheries Service Protected Resources Division 55 Great Republic Drive, Suite 04-400 Gloucester, MA 01930 ENDANGERE...

AREVA Design Control Document Rev. 4 - Tier 2 Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation - Appendix 19A

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 4 Page 19A-119A Event Trees for Core Damage Sequences Initiated During Power OperationAppendix 19A presents the event trees that delineate the core-damage sequences for internal events initiated during power operation. T...

Millstone, Unit 3, License Amendment Request for Changes to Technical Specification 3/4.7.5 "Ultimate Heat Sink."

Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060Web Address: www.dom.comMay 3, 2013U. S. Nuclear Regulatory Commission Serial No. 13-228Attention: Document Control Desk NSSL/MAE ROWashington, DC 20555 Docket No. 50-423License No. NPF-49DOMINION N...

Audit Summary For Review of Topical Report WCAP-17524, "AP1000 Core Reference Report" and Supplemental Information.

March 7, 2013 Mr. J. A. Gresham, Manager Westinghouse Electric Company Nuclear Services 1000 Westinghouse Drive Cranberry Township, PA 16066 SUBJECT: AUDIT SUMMARY FOR REVIEW OF TOPICAL REPORT WCAP-17524, “AP-1000 CORE REFERENCE REPORT” AND SUPPLEMENTAL INFORMATION Dear M...

AREVA Design Control Document Rev. 4 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.1.3 Fuel Pool Cooling and Purification System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Revision 4 Page 9.1-249.1.3 Fuel Pool Cooling and Purification SystemThe Fuel Pool Cooling and Purification System (FPCPS) is designed to maintain the spent fuel pool (SFP) water temperature and water level within prescribed limits by r...

Oyster Creek - Submittal of Fifth Ten-Year Interval lnservice Inspection Program Plan.

RA-14-105 December 11, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 10 CFR 50.55a Subject: Submittal of Fifth Ten-Year I...

Florida Power and Light Company's Turkey Point Units 3 & 4, Second Six-Month Status Report in Response to 03/12/2012, Commission Order Modifying Licenses with Re: to Requirements for Mitigation Strategies for Beyond-Design-Basis External External Event.

CFebruary 26, 2014L-2014-041=PL.U. S. Nuclear Regulatory CommissionAttn.: Document Control DeskWashington, D.C. 20555-0001Re: Turkey Point Unit 3 and Unit 4Docket Nos. 50-250 and 50-251Florida Power and Light Company's Turkey Point Units 3 and 4, Second Six-MonthStatus Report ...

Safety Analysis Report of the Aspect 12K Package. Part 2 of 4.

2.12.6 Reduced External PressureThis analysis demonstrates that under the normal condition of transport reduced pressure condition, thepackage will satisfy the applicable performance requirements specified in the regulations:" there will be no loss or dispersal of contents;" t...

Generic Technical Specification Traveler, (GTST) ap1000sts3702_gtst_o42_v0.

GTST AP1000-O42-3.7.2, Rev. 0 Date report generated: Monday, May 19, 2014 Page 1 Advanced Passive 1000 (AP1000) Generic Technical Specification Traveler (GTST) Title: Changes Related to LCO 3.7.2, Main Steam Isolation Valves (MSIVs) I. Technical Specifications Task For...

Provides documentation of NUREG-0737 items.Submittals re emergency preparedness & control room habitability forthcoming.

ReGUL*RY INFORMATION DISTRIBUTIS SYSTEM (RIDS) ACCESSION NBR:8101060465 DOCDATE: 80/12/31 NOTARIZED: NO DOCKET # FACIL:50-261 H. B. Robinson Plant, Unit 2, Carolina Power and Ligh 05000261 AUTH.NAME AUTHOR AFFILIATION UTLEY,E;,E. Carolina Power & Light Co. RECIPNAME RECIPIENT...

AREVA Design Control Document Rev. 7 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.2.2 Component Cooling Water System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 7 Page 9.2-259.2.2 Component Cooling Water SystemThe component cooling water system (CCWS) is a closed loop cooling water system that, in conjunction with the essential service water system (ESWS) and the ultimate heat si...

Turkey Point, Units 3 and 4, License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, "Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B."

0 December 23, 2014FPL. L-2014-36910 CFR 50.90U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555-0001Re: Turkey Point Nuclear Plant, Units 3 and 4Docket Nos. 50-250 and 50-251Renewed Facility Operating Licenses DRR-31 and DPR-41License Amendme...