Report a Safety Concern
Search

The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Responds to RAI re ISI IAW Section XI of 1983 edition of ASME B&PV Code through Summer 1983 Addenda per 10CFR50.55a (g)(4).

g Osmmonwealth 1.dmn Companye v*8Braidw ood Gcncrating Station eRoute al, Hox H enn.ccutie, n. 6o io74,19lret 8isasa2soi), . -March 28,1997i1|!United States Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555-0001ISubject:Braidwood Nuclear Power...

Transcript of ACRS Subcommittee on Class 9 Severe Accidents 860129 meeting in Washington,DC.Pp 1-24.Supporting documentation encl.

. 0Y GI N A _8888-/9'-nUN11ED STATES"NUCLEAR REGULATORY COMMISSIONIN THE MATTER OF: DOCKET NO:-ADVISORY COMMITTEE ON REACTOR SAhEGUARDSSUBCOMMITTEE ON CLASS 9 (SEVERE) ACCIDENTSA\(.)LOCATION:WASHINGTON, D. C.PAGES:1 - 124DATE:WEDNESDAY, JANUARY 29, 1986I4%. . '*c- --= . ~_ -\m...

Rev 0 of Engineering Rept, "Resolution of NRC GL 95-07 'Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves.'"

. . ._TU ELECTRICCOMANCHE PEAK STEAM ELECTRIC STATIONENGINEERING REPORTRESOLimON OF NRC GENERIC 1ETTER 9547" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED CATE VALVES"ER-ME-102REVISION 0JANUARY 30,1996R //fgPREPARED BY: P.C. Chiu(Mechanical Engineering)...

Duane Arnold Energy Center - Integrated Inspection Report 05000331/2020003 and 07200032/2020001

November 6, 2020 Mr. Dean Curtland Director of Site Operations NextEra Energy Duane Arnold, LLC 3277 DAEC Road Palo, IA 52324–9785 SUBJECT: DUANE ARNOLD ENERGY CENTER – INTEGRATED INSPECTION REPORT 05000331/2020003 AND 07200032/2020001 Dear Mr. Curtland: On September 3...

Forwards info re preparedness of facility for licensing. Encls 1-6 include items requiring insp & resolution before recommendations for licensing.

~-c ... o.b/%,, unirro rrArtsCC: D9M!NUCLEAR REGULATORY COMMIMif0Noh WASHINGTON, p. C. 20555,%v '*%. +j'APR - 61989MEMORANDUM FOR: C. I. Grimes, DirectorComanche Peak Project DivisionOffice of Nuclear Reactor' RegulationFROM:R. F..Warnick, Assistant Directorfor Inspection Prog...

Arkansas Nuclear One, Unit 2-2014-02-Final Written Exam.

Data for 2014 NRC RO/SRO Exam 26-Feb-14Bank: 1925Safety Function 1System Number E02 System Title: Reactor Trip Recovery K/A EK1.3Description: Knowledge of the operational implications of the following concepts as they apply to the (Reactor TripRecovery): - Annunciators and con...

Susquehanna Unit 1 Technical Requirements Manual Updates, Revision 78.

Nov. 15, 2013Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2013-51031USER INFORMATION:GERLACH*ROSEY M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSEY M 11/15/2013LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL ...

Grand Gulf-2013-11-FINAL WRITTEN EXAM.

Revisions to the Grand Gulf Written Exam RO QUESTION # 50 Revision: The answer key was changed to accepting distractors ‘A’ and ‘B’. Bases for Change: Distractor ‘A’ for this question states the CRD ‘A’ breaker “will not be capable of any remote or local operation…” and d...

Modification No. 008 to Task Order No. NRC-HQ-13-T-04-0004 Under Contract No. NRC-HQ-11-C-04-0044.

AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT 1 CONTRACT ID CODE PAGE OF PAGES1 132. AMENDMENT/MODIFICATION NO. 3. EFFECTIVE DATE 4 REQUISITION/PURCHASE REQ. NO. 5. PROJECT NO. (if applicable)M0008 06/02/2014 RES-14-03136. ISSUED BY CODE NRCHQ 7. ADMINISTERED BY (If other...

AREVA Design Control Document Rev. 5 - 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 5 Page 10.4-7310.4.9 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...

Columbia, Final Safety Analysis Report, Amendment 62, Chapter 3 - Design Criteria - Structures, Components, Equipment, and Systems, Page 3.6-1 through Page 3.6-101.

Figure Not Available For Public Viewing Figure Not Available For Public Viewing Figure Not Available For Public Viewing Figure Not Available For Public Viewing Figure Not Available For Public Viewing Figure Not Available For Public Viewing Figure Not Available For Public Viewi...

Forwards CRGR review of generic ltr for initiation of severe accident policy statement.

_ _ _ _ ____%'e n:* og UNITED STATES[gNUCLEAR REGULATORY COMMISSIONj WASHING TON, D. C. 20655. (%, ...../March 30 1988fMEMORANDUM FOR: Edward L. Jordan, ChainnanCcnnittee to Review Generic Requirementsi'.FROM: Eric S. Beckjord, DirectorOffice of Nuclear Regulatory Research!'Th...

Directs recipient to take actions necessary to resolve & complete Generic Issue 87, "Failure of HPCI Steam Line W/O Isolation." Issue addressed in near-term OL cases.Resolution depends on specific plant design features.

k.. .SEP 2 61995!MEMORANDUM FOR:Robert M. Bernero, DirectorDivision of Systems Integration,FROM: Harold R. Denton, DirectorOffice of Nuclear Reactor Regulation| SUBJECT: SCHEDULE FOR RESOLVING AND COMPLETING GENERIC'ISSUE NO. 87 - FAILURE OF HPCI STEAM LINEWITHOUT ISOLATIONThe...

Discusses NRC concerns re reliance on feed-&-bleed to address issues associated w/environ qualification & high energy line breaks.Viewgraphs from 860917 meeting encl.

v4-p ,CONNECTICUT YANKEE ATOMIC POWER COMPANYB E R L I N,CONNECTICUTP.o. Box 270 HARTFORD. CONNECTICUT 06141-0270"$"1December 5,1986Docket No. 50-213B12318Office of Nuclear Reactor RegulationAttn: Mr. Christopher 1. Grimes, DirectorIntegrated Safety Assessment Project Director...

Insp Repts 50-245/86-19 & 50-336/86-21 on 860930-1103.No unacceptable conditions identified.Engineered safeguards actuations will be reviewed during next SALP.Major areas inspected:Unit 1 safety insp & Unit 2 refueling outage insp.

. - _ -- - . - - . - ._ ,.- -,',- -U.S. NUCLEAR REGULATORY COMMISSION-:REGION Ii|Report No: 50-245/86-19; 50-336/86-21Docket Nos: 50-245/50-336 License Nos. DPR-21; DPR-65 --Licensee: Northeast Nuclear Energy CompanyFacility: Millstone Nuclear Power Station, Waterford, Connect...

Affidavit of GR Thompson.* Record of 861010 testimony before ACRS & rept on source term debate encl.

..,Affidwit of Gordon Thompson,23 January 1987pap iAffidavit of Gordon R Thompson PhDI, Gordon Thompson, hereby depose and say:My qualifications are set forth in an attached resume (Attachment 1). Thatresume indicates that I have experience in assessing th~e potential foraccid...

U.S. NUCLEAR REGULATORY COMMISSIONDocket Nos: License Nos: Report No: Licensee: Facility: Location: Dates: Inspectors:Approved By:REGION I50-272, 50-311 DPR-70, DPR-75 50-272/99-08, 50-311/99-08 PSEG Nuclear LLC. Salem Nuclear Generating Station, Units 1 & 2 P.O. Box 236 Hanc...

Diablo Canyon Power Plant, Units 1 & 2 - Revision 25 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems

DCPP UNITS 1 & 2 FSAR UPDATE i Revision 25 June 2020 Chapter 9 AUXILIARY SYSTEMS CONTENTS Section Title Page 9.1 FUEL STORAGE AND HANDLING 9.1-1 9.1.1 NEW FUEL STORAGE 9.1-1 9.1.1.1 Design Bases 9.1-1 9.1.1.2 System Description 9.1-3 9.1.1.3 Safety Evaluation 9....

Insp Repts 50-295/87-32 & 50-304/87-33 on 870921-1026. Violations noted.Major areas inspected:RCS pressure isolation check valves,LERs & related licensing history & associated licensee practices.

kg* ._- . __ _ _ _ _ - - _ _ _ _ _ _ - _ - _ _ _ - _ -*.,,,3--LU.S. NUCLEAR REGULATORY COMMISSION,REGION III1LReports No. 50-295/87032(DRP); 50-304/87033(DRP);!-Docket Nos.- 50-295;.50-304 Licenses No. DPR-39; DPR-48Licensee: : Commonwealth Edison CompanyPost Office' Box 767Ch...

Transmits summaries of telcons between Parsons Power Group, Inc,NRC,NNECO & NEAC on listed dates re Independent Corrective Action Verification Program for facility.

- - . . ...n- _,{'.~PARSONSD'aniel L C"urry, Vce President. Nuclear Soryces* Parsogs Energy & Chemicals Group Inc.' 2675 Morgantown Road * Reading, Pennsylvania 19607 * (610) 855-2366 * Fax: (610) 855-2602March 23,1998Docket No. 50-336Parsons NUM2-PPNR-1282-LU.S. Nuclear Regul...

Emergency Plan Implementing Procedure.

0FPLFlorida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957April 23, 2003L-2003-10710 CFR 50 Appendix EU. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D. C. 20555Re: St. Lucie Units 1 and 2Docket Nos. 50-335 and 50-389Emergency Plan...

Materials Supporting January 28th Meeting on GT-MHR Source Term Ref: Project No. 0716.

"Project: 30103 GA/NRC-379-03 + GENERAL ATOMICS U.S. Nuclear Regulatory Commission 14 January 2003 Attn: Document Control Desk Washington, DC 20555 Subject: Materials Supporting January 28th Meeting on GT-MHR Source Term Reference: NRC Project No. 716 Dear Mr. Rubin: Please fi...

Duke Energy Corporation's Response to Issues Raised by the Licensing Board in the January 31, 2003 Conference Call and February 4, 2003 Order.

February 7, 2003 DOCKETED USNRC UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION February 11, 2003 (3:08PM) BEFORE THE ATOMIC SAFETY AND LICENSING BOARDOFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF In the Matter of ) ) Docket Nos. 50-369 - LR DUKE ENERGY CORPOR...

NUREG 1433, Vol. 2, Rev. 2, Standard Technical Specifications - General Electric Plants - BWR/4 - Bases.

NUREG-1433Vol 2, Rev. 2 Standard Technical SpecificationsGeneral Electric Plants,BWR/4BasesIssued by theU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationApril 2001AVAILABILITY NOTICEAvailability of Reference Materials Cited in NRC PublicationsNRC publicat...

Edwin I Hatch Units 1 & 2, Issuance of Amendments 181 & 122 revising Unit 1 TS 4.6.L & Unit 2 TS 4.7.4 concerning snubber surveillance to reflect the present guidance in NRC GL 90-09.

JUNE 19, 1992Docket Nos. and50-321 50-366Distribution See next pageMr. W. G. Hairston, III Senior Vice President Nuclear Operations Georgia Power Company P. 0. Box 1295 Birmingham, Alabama 35201 Dear Mr. Hairston: SUBJECT: ISSUANCE OF AMENDMENTS - EDWIN I. HATCH NUCLEAR PLANT...