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License Amendment Request Supplement for Catawba Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation.

Duke Power CompanyDuke ~~~~~~~~~~~~~~~~~~~~~~~~A Duke Ewgy Compm~y*rPower. Energy CenterA Duke Ew1Compu P.O. Box 1006Charlotte, NC 28201-1006August 28, 2003U.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001ATTENTION: Document Control DeskSubject: Duke Energy Corpora...

Rev 7 to Design Basis Document, DBD-131, "Shearon Harris Nuclear Power Plant, Component Cooling Water System."

\fr CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT DESIGN BASIS DOCUMENT COMPONENT COOLING WATER SYSTEM DBD-131RECEIVED 'AUG 2 4 1998 HNP DOCUMENT CONTROLINDEPENDENT REVISION DATE PREPARED BY REVIEW BY APPROVED3 7/23/93 Ed Williams4/24/96 Tom Scattergood Mar...

Transmittal of EPRI Report TR-108812, "Response of Isolated Piping to Thermally Induced Overpressurization during a Loss of Coolant Accident (GL96-06).

ELECTRIFY THE WORLD M RP Materials Reliability PrograrrM-2IaI MRP 2001-053July 17, 2001 Mr. James Tatum, NRR/DSSA/SPLB US Nuclear Regulatory Commission 11555 Rockville Pike, M/S 0-1 1AI 1 One White Flint North Rockville, MD 20852-2738 SUBJECT: Transmittal of EPRI Report TR-108...

Palo Verde, Units 1, 2 & 3, License Amendments 54, 39 & 27, Revises Technical Specifications to Maintain Technical Accuracy & Consistency Throughout Documents.

ýDocket Nos. 50-528, 50-529 and 5-530June 27, 1991 Mr. William F. Conway Executive Vice President Arizona Public Service Company f Post Office Box 53999 Phoenix, Arizona 85072-3999 Dear Mr. Conway: SUBJECT: ISSUANCE OF AMENDMENT NO. 54 TO FACILITY OPERATING LICENSE NO. NPF-41,...

HB Robinson Unit 2, License Amendment 97, Deletes Requirements for Maintenance of a Highly Borated Inventory in the BIT and the Associated Heat Tracing Required to Maintain the High Boron Concentration in Solution.

March 7, 1986Docket No. 50-261 DISTRIBUTIONDocket File B. Grimes NRC PDR J. Partlow Local PDR T. Barnhart (4) Mr. E. E. Utley, Senior Executive Vice President PAD#2 rdg W. Jones Power Supply and Engineering & Construction T. Novak V. Benaroya Carolina Power and Light Company C...

IR 05000455/2002-002, IR 05000455/2002-002 (DRP), on 12/30/2001-02/11/2002; Exelon Generation Company, LLC; Byron Station, Units 1 & 2. Post-Maintenance Testing. One green violation identified.

March 8, 2002Mr. John L. Skolds, PresidentExelon NuclearExelon Generation Company, LLC4300 Winfield RoadWarrenville, IL 60555SUBJECT: BYRON STATION, UNITS 1 AND 2INSPECTION REPORT 50-454/02-002(DRP); 50-455/02-002(DRP)Dear Mr. Skolds:On February 11, 2002, the NRC completed an...

Fermi-2, License Amendment 21, Amendment Revises Ferm-2 TS To Delete Non-Regenerative Heat Exchanger Outlet Temperature-High Signal From Listing Of Reactor Water Cleanup System Isolation Signals.

July 6, 1988Docket No. 50-341 Mr. B. Ralph Sylvia Group Vice President - Nuclear Operations Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166 Dear Mr. Sylvia:DISTRIBUTION Docket File NRC & Local PDRs PD31 Plant Gray GHolahan TQuay RIngram OGC DHaganJPartl...

IR 05000456/2002-003 & 05000457/2002-003 (DRP), Braidwood Station Units 1 & 2, Inspection on 02/04/2002 - 02/22/2002 related to identification & resolution of problems. One noncited violation noted.

March 18, 2002Mr. John L. Skolds, PresidentExelon NuclearExelon Generation Company, LLC4300 Winfield RoadWarrenville, IL 60555SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2NRC INSPECTION REPORT 50-456/02-03(DRP); 50-457/02-03(DRP)Dear Mr. Skolds:On February 22, 2002, the NRC comple...

Rev 0 to "Indian Point Unit 3 PRA-Based Sys Insp Plans."

~, LC~A~A5LP~X Rev. 0IDIAN POINT UNIT 3 PROBABILISTIC RISK ASSESSMENT-ASKD SYSTEM INSPECTION PLANS Prepared by:A. Fresco, A. Coppola, W. Cunther, Engineering TechnologyJ. Usher, Division& J. TaylorMarch 1987DEPARTMI --- erparedENT OF NUCLEAR ENERGY, BROOKHAVEN NATIONAL UPTON, ...

CO Insp Rept 50-247/71-01 on 701216 & 710106-07.Major areas inspected:preoperational testing,core loading,power ascension,mechanical sys cleanup & Con Ed response to questions raised at 701202 preoperational testing meeting.

U. S. ATOMIC ENERGY COMMISSION REGION I DIVISION OF COMPLIANCE Report of Inspection CO Report No. 247/71-1Licensee:Dates of Inspection: Dates of Previous Inspection: Inspected By: ,Consolidated Edison Company Indian Point No. 2 (iP-2) License No. CPPR-21 Category B December 16...

"Annual Operating Rept 1978."

I, CHANGES MOD-78-3-001 SIS INSTALLATION OF KEY LOCK SWITCH TO DEFEAT AUTOMATIC SAFETY INJECTION ACTUATION DURING COLD SHUTDOWN CONDITIONS A key lock switch was placed in series with the automatic safety injection system actuation relays, thereby, providing the means to defeat...

Susquehanna Steam Electric Station Technical Specification Bases Unit 1 Manual, Revision 1.

Jul. 07, 2005Page 1 of 3MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2005-28957USER INEOMAGE E M EMPL#:028401 CA#: 0363AddrP e: 254-3194TRANSMITTAL INFORMATION:TO: bL ki 07/07/2005LOCAT A): IO UfM,FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHANGE...

Watts Bar Nuclear Plant, Unit 2, Developmental Revision B - Technical Specifications Bases, Table of Contents.

WATTS BAR - UNIT 2 TECHNICAL SPECIFICATIONS BASES TABLE OF CONTENTS TABLE OF CONTENTS (continued)Watts Bar - Unit 2 i (developmental) A TABLE OF CONTENTS ………………………………………………………………….... i LIST OF TABLES …………………………………………………………………………… vi LIST OF FIGURES ………………………………………...

Waterford, Unit 3 - Licensee Slides from 3/8/2010 Meeting Re: Generic Letter 2004-02 Response to RAIs (TAC No. MC4729).

Waterford 3 Generic Letter 2004-02Response to RAIsMarch 8, 2010March 8, 2010 Waterford 32Agendaz Introductionsz Meeting Purposez RAI Discussionz Going ForwardMarch 8, 2010 Waterford 33Introductionsz Entergy– Nicholas Petit – Mechanical Design Engineer– Greg Ferguson – Civil De...

Watts Bar, Unit 2 - Final Safety Analysis Report, Amendment 96, Table of Contents - Section 9 - Table of Contents, Auxiliary Systems, Page 9-i through 9.3-126.

Table of Contents 9-iWATTS BAR WBNP-76TABLE OF CONTENTSSection Title Page9.0 AUXILIARY SYSTEMS9.1 FUEL STORAGE AND HANDLING 9.1-19.1.1 New Fuel Storage 9.1-19.1.1.1 Design Bases 9.1-19.1.1.2 Facilities Description 9.1-19.1.1.3 Safety Evaluation 9.1-19.1.2 SPENT FUEL STORAGE 9....

Calculation, DC00040-110, Revision 0, "Post LOCA Sump pH Effect From Miscellaneous Sources".

ES-0412ATTACHMENT IPAG-E1-0F2REVISION 5Subject Code004SOUTH CAROLINA ELECTRIC AND GAS COMPANYCALCULATION RECORD Page 1 of 38OPartial Calc. Revision~Com Jete Calc. RevisionOrganization DateWorle Parsons 10/22/2009XREF NumberNACalculation TitlePost LOCA Sump pH Effect FromMiscel...

Safety evaluation supporting plant inservice testing program & request for relief.

- _ - - - _ _ _puoy.,. .,kUNITED STATESp ?>NUCLEAR REGULATORY COMMISSION5 :jWASHINGTON, DI C. 20555k,[SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO THE INSERVICE, TESTING PROGRAMAND REQUEST FOR RELIEFWOLF CREEK NUCLEAR OPERATING CORPORATIONWOLF CREEK ...

Susquehanna 1 2000-2017 Q1-Q4 ROP Inspection Findings

Susquehanna 1 Initiating Events Significance: Dec 01, 2000 Identified By: NRC Item Type: FIN Finding Identification and Problem Resolution Effectivenessof Corrective Actions The inspectors identified a finding regarding the effectiveness of corrective actions for breaker over-...

Forwards marked-up pages to transcript of 880107 Kennedy hearings for correction.

..:.. . L.a . : -: . - - .a ~~--~ ~ -'%I' ' s[UNITED STATESSNUCLEAR REGULATORY COMMISSIONj j REoloNI*g* *475 ALLENOALE ROAD**/KING oF PRUSSIA. PENNSYLVANIA te404FEB 081988* " * *'MEMORANDUM FOR: Michael S. Callahan, Congressional Affairs Officer-Office of Governmental and Publ...

Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, "Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b"

1717 Wakonade Drive Welch, MN 55089 September 1, 2020 L-PI-20-026 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Facil...

Insp Repts 50-338/89-22 & 50-339/89-22 on 890601-0714.No violations or deviations noted.Major areas inspected:plant status,maint,surveillance,ESF walkdown,operational safety verification,Generic Ltr 88-17 & plant startup.

_. _ _ _ _ _ _ _ _ _ - _ _ ., -1 .*WM;| f$ " . 4oUNITED STATES'o; _NUCLEAR REGULATORY COMMISSION -*'I,[~-RE210N il'' '.yj; 101 MARIETTA STREET,N.W.- '%'s ATLANTA, GEORGIA 30323% . . . . ./Report.Nos.:50-338/09-022 and 50-339/89-022 ,Licensee: Virginia. Electric & Power Company...

Provides preliminary review evaluation of draft questions re PSAR.Mechanical Engineering Branch area of review concerns design criteria of Sections 3.6,3.9,3.10,4.2,5.2 & 5.5 of Oct 1972 std format (Reg Guide 1.70).

., . , . . _ , . ..e ..,-. .- . . y_4$ N'~~L. . . >~ ''~:,48pN7Nh,Qr$ifWhndGM MgVNAMbh.[x hb$2'bbdh E--., ..-,. . ,0." ".- SEP 131974e'..s. .. ..~.0-' .!.r"''.c . '^x., 1 ~,|. e.;3: :~k C h.? N -' _: a, ; c ;T ... W e,,1. N. . for.(L.ight Water Beesters Group 17 g.,?. d, ,-. ,...

Forwards results of initial review of probabilistic safety assessment.No significant omissions identified re overall contribution of dominant sequences to core melt probability.

7. .k:JAN 3 0 '1985.1~MEMORANDUM FOR: -Darrel G. Eisenhut, DirectorDivision of LicensingFROM: Themis P. Speis, DirectorDivision of Safety TechnologySUBJECT: INITIAL REVIEW 0F THE SEABROOK STATION PROBABILISTICSAFETY ASSESSMENTWe have completed our initial review of the Seabroo...

Lists allegations that fall into discipline not appearing under any category.Allegation should be placed in category or reason why allegation not pursued given.

- _ - ____ ,_________-____ - _ _.,(,ca utg),eUNITED 3TATES%NUCLEAR REGULATORY COMiAISSIONe35,i, .4 ^ ,IWASHINGTON, o. C. 20555s, v /*****5eptember 7, 1984..NOTE FOR: ELivermoreLShaoRBangsrtThe following allegations that fall into your discipline do not appear underany category...

REVIEW OF INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) FOR WOLF CREEK GENERATING STATION (TAC NO. M83696)

UNITED STATES NUCLEAR REGULATORY COMMISSION -0lp WASHINGTON, D.C. 20555-0001 February 29, 2000 civi -i'd Mr. Otto L. Maynard President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KA 66839 SUBJECT: REVIEW OF INDIVIDUAL PL...