ML17037B960: Difference between revisions
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==DearSir:== | ==DearSir:== | ||
REBOLATQ:i"DQ(,""-T)[LE(0PyL-.-.'--:'nclosedforyourreviewarethreecopiesofthedesignandanalysismethodsfortheRevetment-DitchSystemforNineMilePointUnit2.TAisreportissubmittedinresponsetoSection2.4.5oftheCommission'sSafetyEvaluationReportwhichrequiredcertainadditionalinformationandanalyses.WerequestthatyoufirstreviewandapproveSection4,"PhysicalModelStudy,"heforeevaluatingtheentiredesignsincethatstudywilldeterminetheactualrevetmentdesignrequirements.Expeditiousapprovalisessentialtomaintainourpresentconstructionschedule.Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATIONGERALDK.HODEVicePresident-gineeringEnclosures 0Ill)1f7-.(/fi1-TtC | REBOLATQ:i"DQ(,""-T)[LE(0PyL-.-.'--:'nclosedforyourreviewarethreecopiesofthedesignandanalysismethodsfortheRevetment-DitchSystemforNineMilePointUnit2.TAisreportissubmittedinresponsetoSection2.4.5oftheCommission'sSafetyEvaluationReportwhichrequiredcertainadditionalinformationandanalyses.WerequestthatyoufirstreviewandapproveSection4,"PhysicalModelStudy,"heforeevaluatingtheentiredesignsincethatstudywilldeterminetheactualrevetmentdesignrequirements.Expeditiousapprovalisessentialtomaintainourpresentconstructionschedule.Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATIONGERALDK.HODEVicePresident-gineeringEnclosures 0Ill)1f7-.(/fi1-TtC}} | ||
}} | |||
Revision as of 01:18, 19 May 2018
| ML17037B960 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/05/1976 |
| From: | Rhode G K Niagara Mohawk Power Corp |
| To: | Stolz J F Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B960 (4) | |
Similar Documents at Nine Mile Point | |
|---|---|
Category:Letter
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Report No. 14-09NP, Revision 1, Non-proprietary Version ML15023A0312014-04-30030 April 2014 Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). ML14351A4272014-01-31031 January 2014 000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow). ML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. ML13225A5842013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6632013-12-11011 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129 ML13338A6642013-12-11011 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130 ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) ML13316B1102013-11-0101 November 2013 Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary) ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 ML13197A2222013-07-12012 July 2013 Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic ML13078A3232013-02-28028 February 2013 XGEN-2012-25-NP, Revision 1, Westinghouse Engineering Report, Technical Basis for the Inspection Frequency of the Modified Alloy 718 Jet Pump Beam, Attachment 2 ML13066A1692013-02-28028 February 2013 Units I and 2, Overall Integrated Plan for Reliable Hardened Vents ML12313A2032012-10-26026 October 2012 Attachment 1, NMP2 Extended Power Uprate, Power Ascension Test Report ML12313A2042012-10-26026 October 2012 Attachment 2, Final Steam Dryer Stress Report, Continuum Dynamics, Incorporated Report No. 12-18NP, Attachment 3, Affidavit from CDI ML12277A0902012-10-12012 October 2012 Technical Letter Report on Aging Management Program Audits at Ginna and Nine Mile Point 1 ML12284A1842012-09-30030 September 2012 Attachment 3, Final EPU Steam Dryer Load Definition CDI Report No. 12-20NP, Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point, Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1 ML12284A1852012-06-30030 June 2012 Attachment 4, Steam Dryer Limit Curves CDI Technical Note No. 12-13NP, Limit Curves with ACM Rev. 4.1 for the 100% Power Level Basis at Nine Mile Point, Unit 2, Revision 1 ML12170A8692012-06-30030 June 2012 Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML11221A0132011-08-0505 August 2011 Attachment 3, Continuum Dynamics, Inc Technical Note No. 11-17NP, Limit Curve Analysis with ACM Rev. 4.1 for Power Ascension at Nine Mile Point Unit 2, Revision 1. (Non-Proprietary) ML11208B7732011-07-0808 July 2011 Report No. 1100539.401, Rev. 1, Nine Mile Point Unit 1, Steam Dryer Support Bracket Flaw Evaluation. ML11188A1952011-06-28028 June 2011 Calculation S0VESSELM035 (SIA File No. 1100566.301), Reactor Pressure Vessel Head Weld Flaw Evaluation, Rev. 00.00 ML11171A0602011-05-31031 May 2011 Attachment 3, CDI Report No. 11-04NP, Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Using ACM Rev. 4.1 Acoustic Loads, Revision 0. (Non-Proprietary), Attachment 4, Affidavit from Continuum Dynamics, Inc ML1108803022011-03-31031 March 2011 NEDO-33636, Fuel Storage Criticality Safety Analysis of New Fuel Storage Racks - GE14, Attachment 3, (Non-Proprietary) ML1104601602011-01-31031 January 2011 Attachment 1, CDI Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Revision 3 ML12135A6232011-01-14014 January 2011 Off-Site Dose Calculation Manual (Odcm), Revision 32 ML1035003652010-12-13013 December 2010 Holtec Report No. HI-2012621 (Non-Proprietary), Criticality Safety Evaluation for the Nine Mile Point 2 Rack Installation Project ML1021702952010-07-30030 July 2010 Attachment 5, Continuum Dynamics, Inc., CDI Report No. 10-12NP, Design and Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Modifications for EPU Operation ML1021701862010-07-28028 July 2010 Attachment 4, Structural Integrity Associates, Inc., Flaw Evaluation of Indications in the Nine Mile Point Unit 2 Steam Dryer Vertical Support Plates Considering Extended Power Uprate Flow Induced Vibration Loading ML1019004492010-06-30030 June 2010 C.D.I. Report No. 10-10NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1, Rev. 1 ML1021701852010-06-30030 June 2010 Attachment 3, Global Nuclear Fuel - Americas, LLC, MCNP01A, Low Enriched UO2 Pin Lattice in Water Critical Benchmark Evaluations Using ENDF/B-V Nuclear Cross-Section Data, Revision 1 ML1019004482010-06-30030 June 2010 C.D.I. Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Rev. 1 (Non-Proprietary) 2023-08-04 Category:Safety Evaluation Report MONTHYEARML0628901292006-09-30030 September 2006
[Table view]NUREG-1900, Vol 1 Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station Units 1 & 2 ML0614603132006-06-0101 June 2006 Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) ML0610201662006-04-0303 April 2006 Safety Evaluation Report with Open Items Related to the License Renewal of Nine Mile Point, Dated March 2006 - NMPNS Comments (TAC Nos. MC3272 and MC3273) ML0605807582006-03-0303 March 2006 Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application ML17037B5881978-05-26026 May 1978 Letter Regarding a Request for Evaluation of the Effect on Unit 1 Containment of Multiple Subsequent Actuations of Safety/Relief Valves Following a Postulated Isolation Event ML17037B9231977-08-22022 August 1977 Letter Regarding a Report Describing the Unit 2 Reactor Building Polar Crane and a Review of the Information Provided in a July 20, 1977 Letter ML17037B6251977-06-0202 June 1977 Letter Regarding a Review of Licensee Responses to Previous Generic Request for Information Relative to the Electrical Power Distribution Systems and an Enclosed Safety Evaluation and Statement of Staff Positions ML17037B9601976-03-0505 March 1976 Letter Regarding a Review of the Design and Analysis Methods for the Revetment-Ditch System and Requesting a First Review and Approval of Section 4, Physical Model Study. ML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C0291973-06-15015 June 1973 Letter Regarding the Safety Evaluation of Niagara Mohawk Power Corporation Application for a Permit to Construct the Nine Mile Point Nuclear Station Unit 2 2006-09-30 |
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U.S.NUCLEARREGULATORYCC'SSIONNRCFoRM195I27GINPNRCDISTRIBUTIONFoRPART60DOCI(ETMATERIALDOCKETNUMBERFILENVMSERTo:NiagaraMohawkPwrCorMrStolzNiagar'aMohawkPwrCorp,Sy'racuse,NY.GKRhodeDATEOFDOCUMENT3-5-76DATERECEIVED3-10-76%LETTERJRORIGINALDcopvQNOTORIZED@UNCLASSIFIEDPROPINPUTFORMNUMBEROFCOPIESRECEIVED/onesignedDESCRIPTIONLtrtransthefollowing:ENCLOSVRE1Design6AnalysisMethodsforRevetmentDitchSystemNineMilePoint'uclearStatioUnit2....dtdFeb1976..................;.(3cysenclrec'd)'.IACKNOWLZDGggPLANTNAME:NineMilePt82DONOTREMOVESAFETYASSXGNEDAD:BRANCHCHIEF:FORACTION/INFORMATIONASSIGNEDAD:BRANCHCHIEF~ENVIROPROJECTMANAGER:LlC~PSST,epalIPROJECTMANAGER:LIC~ASSTEGFILEPL+VIREINTERNALDISTRIBUTIONBENAROYAERNSTALLADSPANGLERGOSSICK6STAFFPROJECTMANAGEMENTBOYDP.COLLINSHOUSTONPETERSONMELTZHELTEMESSKOVHOLTLPDR'ETXCNSASLB8-ltllICl5NRCFORM1GSI2.7GIENINEENKNIGHTSIHvlEILPAMLICKIREACTORSAFETYROSSNOVAKROSZTOCZYCHECKAT6ISALTZMANEXTERNALDISTRIBUTIONATLLABGoV"IELAPDRCONSULTANTSXPPOLITOOPERATINGREACTORSSTELLOOPERATINGTECHEISENHUTSHADBAERSCHICENCERGRIMESSITESAFETY6cERANALYSXSDENTONScMULLERBROOK11AVENNATLLABULRXKSON(ORNL)SITETECHGAMMILLSTEPPHlKtfANSITEANALYSISVOLL?IERBUNCHJ~COLLINSKREGERCONTROLNUMBER
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NIAGARAMOHAWKPOWERCORPORATIONNIAGARA~MOHAWK300ERIEBOULEVARD,WESTSYRACUSE.N.Y.13202March5,1976DirectorofReactorRegulationAttn:Mr.J'.F.Stolz,ChiefBranch2-1U.S.NuclearRegulatoryCommissionWashington,D.C.20555Re:NineMflePointUnit2Docket'o.50<<410
DearSir:
REBOLATQ:i"DQ(,""-T)[LE(0PyL-.-.'--:'nclosedforyourreviewarethreecopiesofthedesignandanalysismethodsfortheRevetment-DitchSystemforNineMilePointUnit2.TAisreportissubmittedinresponsetoSection2.4.5oftheCommission'sSafetyEvaluationReportwhichrequiredcertainadditionalinformationandanalyses.WerequestthatyoufirstreviewandapproveSection4,"PhysicalModelStudy,"heforeevaluatingtheentiredesignsincethatstudywilldeterminetheactualrevetmentdesignrequirements.Expeditiousapprovalisessentialtomaintainourpresentconstructionschedule.Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATIONGERALDK.HODEVicePresident-gineeringEnclosures 0Ill)1f7-.(/fi1-TtC
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