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Responds to Technical Assistance Request 7191 re steam generator water hammer.Safety evaluation & consultant rept encl.Water hammer unlikely.

.Ct5 . ...'',4..Y%.2./'DISTRIBUE0NCentral fileJAN 17 N g NRC PORPSB Reading.y0E s I M COPYMEMORANDUM FOR: R. Reid, Chief, Operating Reactors Branch #4, 00RFROM:G. Lainas, Chief. Plant Systems Branch, DORSUBJECT: MAINE YANKEE STEAM GENERATOR WATER HAMMER EVALUATIONPlant Name: M...

G20010458/LTR-01-0537 - Rep. Olympia J Snowe Ltr re: Request for a Description of What Measures the NRC is Taking for Increased Procedures at Nuclear Power Plants, Including Those in the Process of Decommissioning

EDO Principal Correspondence ControlFROM: DUE: 10/30/01 EDO CONTROL: G20010458 DOC DT: 10/09/01 FINAL REPLY:Senator Olympia J. Snowe TO: Chairman MeserveFOR SIGNATURE OF : ** PRI ** CRC NO: 01-0537ChairmanROUTING:Request a Description of What Measures the NRC is Taking for Inc...

MY SAR Revision June 19, 2000

To: TThompson@nacintl.com cc: Subject: Fwd: MY SAR Revision, 6/19/00 Tom: See David's attached e-mail on the validity of the existing critical flaw size determination for the new SA-182 material. This remains a structural/materials open item for the Maine Yankee review. You sh...

Requests that MK Webb be added to site access authority.Site access were completed & thus capable of safe conduct in radiologically restricted areas.

_. - .. .. - __ _- . . _ _ - - ~ _Scptember 24, 1997MEMORANDUM TO: Thomas L. Harrison, ChiefAdministrative Services BranchDivision of Resource ManagementRegion 1Sefnhurkheks DfrhetorFROM:Non-Power Reactors and DecommissioningProject DirectorateDivision of Reactor Program Manag...

Safety evaluation supporting util response to Item 2.1 of Generic Ltr 83-28.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ . --|s.n Raouqj,g jo,,UNITED STATES .,NUCLEAR REGULATORY COMMISSION e oENCLOSURE 1|;E WASHINGTON, D. C. 20555%,*****p|SAFETY EVALUATION REPORT-GENERIC LETTER 83-28, ITEM 2.1 (PART 1),EOUIPMENT CLASSIFICATION (RTS COMP 0NENTS)MAINE YANKEE ATOMIC POWE...

Advises that "Seismological & Geological Studies,Miramichi Area,New Brunswick & Central New Hampshire" reclassified nonproprietary.

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _|4.PUBLIC SERVICEs u a su mr.-Ar., osc.:Comparyof New HwvpeNro 1671 Worcester RoadFrominohom. Mossochusetts 01701(617) - 872 810CsJanuary 6, 1984SEN- G10T.F. B7.1.2United States Nuclear Regulatory CommissionWashington, D. C. 20555Attention:...

Vermont Yankee Nuclear Power Station, Transcription re: Meeting Summary, 03/31/2004 Category 3 Meeting With Public to Discuss Proposed Power Uprate, Pages 1-124. (TAC MC0761).

Official Transcript of ProceedingsNUCLEAR REGULATORY COMMISSIONTitle: Vermont Yankee Power UpratePublic MeetingDocket Number: (not applicable)Location: Vernon, VermontDate: Wednesday, March 31, 2004Work Order No.: NRC-1401 Pages 1-124NEAL R. GROSS AND CO., INC.Court Reporters ...

Safety evaluation supporting util DCRDR program plan to satisfy Suppl 1 to NUREG-0737 requirements.

- . . - - . . - . ..[',g UNITED STATES*[g NUCLEAR REGULATORY COMMISSION( 5|WASHINGTON, D. C. 20555\...+/SAFETY EVALUATION BY OFFICE OF NUCLEAR REACTOR REGULATIONMAINE YANKEE ATOMIC POWER COMPANYMAINE YANKEE ATOMIC PCKER STATIONDOCKET NO. 50-309DETAILED CONTROL ROOM DESIGN REVI...

G20060352/LTR-06-0169 - Sen. Joseph I. Lieberman Ltr. re Independent Safety Assessment at Indian Point

June 7, 2006The Honorable Joseph I. LiebermanUnited States SenateWashington, D.C. 20510Dear Senator Lieberman:On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to yourletter of March 15, 2006, that forwarded a letter from Connecticut Attorney General ...

"Valve Inlet Fluid Conditions for Pressurizer Safety & Relief Valves in C-E Designed Plants," interim rept.

'· ~ • • VALVE INLET FLUID CONDITIONS FOR PRESSURIZER SAFETY AND RELIEF VALVES IN COMBUSTION ENGINEERING-DESIGNED PLANTS NP-RESEARCH PROJECT Vl02-20 (PHASE B) INTERIM REPORT, MARCH 1982 Prepared by COMBUSTION ENGINEERING, INC. 1000 Prospect Hill Road Windsor, Connecticut 06095...

Safety evaluation supporting Amend 104 to License DPR-36.

___ __ _ _ _ _ _ . ___________ _ - __ _ _ ._____ _ _ _ _ - _ _ _ _ _ ._ ______ -____ ______ ____________. .,ge esc4oUNITED STATES,'g!,r(g NUCLEAR REGULATORY COMMISSION. -'J;E WASHINGTON, D. C. 20555$*,,.*SAFETY EVALVATION RY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO A...

Attachment 10 - slide presentation by NAC International Subject: High Burnup Site Specific Approach

IHigh Burnup Site Specific Approach Willington (Bill) Lee Vice President & Chief Engineer NAC International NEI/NRC Meeting April 27, 2000 NAC llE INTERNATIONALSite Specific Approach Focused on the characteristics and attributes of 90 specific Maine Yankee fuel assemblies with...

Safety evaluation supporting Amend 101 to License DPR-36.

,:.,8[(oUNITED STATESg ,g NUCLEAR REGULATORY COMMISSION$ rj WASHINGTON, D. C. 20555o,'f,, .-.--.u,,, m._.' ' . . . . . *iSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATING TO AMENDMENT N0.101 TO FACILITY OPERATING LICENSE NO. DPR-36 |MAINE YANKEE ATOMIC POWE...

Summary of 861022 meeting w/util in Bethesda,MD re selection of axial power shape for large break LOCA analysis.List of attendees & supporting documentation encl.

. _ . _ _ _ __ _ ._- _ __ . _. _ _ _ _ _ _. .,Novemb3r 4, 1986~MEMORANDUM FOR: Ashok C.-Thadani, DirectorPWR Project Directorate #8Division of PWR Licensing-B|.FROM: Patrick M. Sears, Project Manageri~PWR Project Directorate #8uivision o: rwrt i.iciens ing oSUBJECT: SupMARY 0F...

Appendix B to Encl 1 - Approved Contents and Design Features for the NAC-UMS System, Amendment 3 (DraftUMSTechSpecsforAmendment3-Appendix B-9-16-03.pdf).

____________________________________________________________________________Certificate of Compliance No. 1015 B-1 Amendment No. 3 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE NAC-UMS SYSTEM AMENDMENT 3 LIST OF EFFECTIVE PAGES ________________...

Forwards EGG-NTA-7436, "Conformance to Generic Ltr 83-28, Item 2.2.1, 'Equipment Classification for All Other Safety- Related Components,' Main Yankee," technical evaluation rept.Plan conforms to generic ltr requirements.

5s.TM - MINE|Idaho Nedor,el EngH,,eerk,g LaboratoryApril 14, 1987|Mr. M. Carrington, Project Manager 6 0 - G d i?Office of Nuclear Reactor RegulationiU.S. Nuclear Regulatory CommissionWashington, D.C. 20555;TRANSMITTAL OF FINAL REPORT, "CONFORMANCE TO GENERIC LETTER 83-28,ITEM...

Safety evaluation re adequacy of offsite power sys.Further evaluation cannot continue until all requested info received.Surowiec line not acceptable substitute for Mason line during startup or normal operations.

- . - - - - - . . - - . .- - - . - - - - - , - _..-.___- _!-.~ ';.;SAFETY EVALUATION BY THE'0FFICE OF NUCLEAR REACTOR REGULATIONRELATING TO THE ADEQUACY'0F THE,;- 0FFSITE POWER SYSTEMMAINE YANKEE ATOMIC POWER COMPANY (MYAPCO)| MAINE YANKEE ATOMIC POWER STATION'(MYAPS)iDOCKET N...

Licensee response to contentions of Commonwealth of MA.* Responds to Commonwealth of MA contentions re spent fuel pool amend.Certificate of Svc encl.

. . ..s%6bff\DOCKETED-USNHCDated: April 9, 1987,57 MW 13 P3:47-UNITED STATES OF AMERICA0FF!CE F M .. _ m-00CKliit:'.+, p iei'eNUCLEAR REGULATORY COMMISSION ERANCc-before theATOMIC SAFETY AND LICENSING BOARD)In the Matter of))VERMONT YANKEE NUCLEAR) Docket No. 50-271-OLAPOWER C...

Forwards recent exigent Tech Spec change re mgt changes at facility.Legal notice published in newspaper,amend to license & safety evaluation encl.

'0-c,acqFcbrutry 21, 1988+.MEMnRANDUM T0: Frank J. Miraglia, Jr.Associate Directnr for ProjectsDennis Crutchfield. DirectorDivision of Raactor Projects I!!, IV, Vof Special ProjectsFROM: Steven A. Varga, PirectorDivision of Reactor Projects I/IISUBJECT: EXIGENT TECHNICAL SPECI...

Rev 1 to M01-1258-002, "Decommissioning Cost Analysis for MYAPS."

_ _ _ - - . - .. - .. - . . - - ~ . . - . . - - - - _ - - . _ _ _ _ _ _ _ _Document .Vo. M01-L?58-002..4DECO 3DIISSIONING COST ANALYSISfor the' 'MAINE YANKEE ATOMIC POWER STATIONY). .. - .y. . .w..y.... u-yg....s,-u.... ..-:q pp; ; , .c-2. .s . _ - . .y. .. . . .Lr%,44--,g\._[...

Replacement pages 2-48,2-49 & 2-50 to rev 14 of "Defueled SAR."

p..or1Proc. No. 0-061Rev. No. 528 THRU 38 - NRC HEADQUARTERSDOCUMENT CONTROL DESKPage 4 of 5H. MILLER(11)(' COPY NUMBER:ATTACHMENT AMAINE YANKEE CONTROLLED DOCUMENT TRANSMITTAL FORM!| DOCUMENT:DEFUELED SAFETY ANALYSIS REPORT|LTRANSMITTAL ISSUE DATE: 8-31-99 TRANSMITTAL RETURN ...

Mgt Review Board Rept, "Corrective Actions Associated w/Multiple Events Involving Incorrect Assembly of Eccentric Butterfly Valves."

__,E86Il{/(/)....'TECH E&g. cg i,,.'*.,;.To:G.M. Leitch, Vice President Operations !(-From:. Management Review Board-,.s..... .1I;..;... . . ..- -. . ..: Management Review Board Report.: '/;,,' . . . ..'*. . ...,.. . ..-.. .,Corrective Actions Associated with Mu'ltiple Events-...

Refers to 960913 & 960916 ltrs re noncomplying conditions discovered in recent monthes at MYAP.Conditions raise questions as to whether,overall,MYAP in substantial compliance w/NRC regulations assuring low radiological risk.

,d 9s J ifi *..I1,I1r.t. .xc:o.' -? q .1 - e. . A , .N'T. D' inca.xP.,geu a .. r b a. ". '. .' .4 9 4*,1||rL i . c.4 .,3. e , , w, a .v._ n.. n , . .-ChairmwomanU.S. !belear Regulatory C:nmissionWashingtcn, D.C. 23555 000.Oear Madame Chairw man:' 4. ^ c^ , .' " e ' c^ .- - ^. ...

Responds to 801204 ltr,on behalf of Sensible ME Power,re published remarks by NRC official in support of long-term storage plan at facility.Position reflects generic issue documented in NUREG-0575.

0 M(q|p3p ~I i D ti h Q ? % Vru qM < v ~ - a...s .# ".DI1IBIBUTION:C Docket Files OELD S. HanauerNRC PDRG. Ertter (ED0-09961)D. RossL POR S. Cavanaugh.B. Snyderg 1 0 1981TERA E. Hughes'R. VollmerDocket No. 50-309NSIC M. Stine O T. Murley|ORB #3 RdgP. Kreutzer (3)~ Gray File OR...

Responds to 970820 ltr to Chairman Jackson expressing concerns re stds to which MYAP will be held during decommissioning of MYAPS.NRC will provide oversight for plant decommissioning.

'37)-3W/'.,.y~gV y*tUNITED STATESJs}NUCLEAR REGULATORY COMMISSION**WASHINGTON. D.C. 300w0001k.4...,/September 25, 1997Mr. Stanley R. TupperTupper & Tupper Law Offices102 Townsend AvenuePost Office Box 430Boothbay Harbor. ME 04538Dear Hr. Tupper:Your letter of August 20. 1997, ...