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| {{#Wiki_filter:AECDISTRIBUTION FORPART50DOCKETMATERIALTEMPORARY FORMFROM'iagara MohawkPowerCorpoSyracuse~ | | {{#Wiki_filter:AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TEMPORARY FORM FROM'iagara Mohawk Power Corpo Syracuse~N.Y.13202 F J.Schneider DATE OF DOC: tion 8<<1-72 DATE REC'D 8.-4 2 LTR FI iRMO RPT To: Mr.Skovholt ORIG CC ('ENT AEC PDR~SENT LOCAL PDR CLASS: U PROP INFO DE IPTION: Ltr reporting an incident on 7-27-72~regarding an increasing recirculation syst va5W packing leakage within the drywell." No CYS REC'D ENCLOSURES: |
| N.Y.13202FJ.Schneider DATEOFDOC:tion8<<1-72DATEREC'D8.-42LTRFIiRMORPTTo:Mr.SkovholtORIGCC('ENTAECPDR~SENTLOCALPDRCLASS:UPROPINFODEIPTION:Ltrreporting anincidenton7-27-72~regarding anincreasing recirculation systva5Wpackingleakagewithinthedrywell." | | DOCKET No: 0 220 PLANT NAMES: Nine Mble 00 NOT REMOVE II%NO'RFtIH Foa ACTION INFORMATION |
| NoCYSREC'DENCLOSURES:
| | -2 AB BUTLER L W/Copies CLARK(L)W/Copies GOLLER(L)W/Copies KNIEL L W/Copies SCHWENCER(L) |
| DOCKETNo:0220PLANTNAMES:NineMble00NOTREMOVEII%NO'RFtIH FoaACTIONINFORMATION
| | W/Copies STOLZ(L)W/Copies VASSALLO L W/Copies H.DENTON W/Copies SCHEMEL (L)W/-=-Copies-ZIEMANN L W/9 Copies CHITtAtOOD(FM |
| -2ABBUTLERLW/CopiesCLARK(L)W/CopiesGOLLER(L) | | )W/Copies DICKER(ENVIRO) |
| W/CopiesKNIELLW/CopiesSCHWENCER(L) | | --=--=--W/-=Copies KNIGHTON ENVIRO W/Copies W/Copies W/Copies iNTERNAL DISTRXBUTION G HAEC PDR VOGCp ROOM P-506A WNi&i'TZING/STAr(('ASE GIAl4BUSSO |
| W/CopiesSTOLZ(L)W/CopiesVASSALLOLW/CopiesH.DENTONW/CopiesSCHEMEL(L)W/-=-Copies-ZIEMANNLW/9CopiesCHITtAtOOD(FM | |
| )W/CopiesDICKER(ENVIRO) | |
| --=--=--W/-=CopiesKNIGHTONENVIROW/CopiesW/CopiesW/CopiesiNTERNALDISTRXBUTION GHAECPDRVOGCpROOMP-506AWNi&i'TZING/STAr(('ASE GIAl4BUSSO | |
| ~BOYD-L(Btla) | | ~BOYD-L(Btla) |
| DEYOUNG-L(PWR) | | DEYOUNG-L(PWR) |
| ~SKOVHOLT-L P.COLLINSREGOPR.SPILEIhREGIOH(2)~ioRRISvSTEELETECHREVIEW+HENDRXEg/SCHROEDER | | ~SKOVHOLT-L P.COLLINS REG OPR.SPILE Ih REGIOH (2)~ioRRIS v STEELE TECH REVIEW+HENDRXE g/SCHROEDER |
| ~MACCARYLANGEPAWLICKX,SHAOVKNUTHv'TELLOiMOORE~THOMPSON>TEDESCOvLONG~LAINASBENAROYAlrVOLL14ER~ENTON(4)GRXMESGAMMXLLKASTNERBALIJQU)FINEEHVIROMOLL?RDICKERKNIGHTONYOUNGBIOOD | | ~MACCARY LANGE PAWLICKX ,SHAO V KNUTH v'TELLO iMO ORE~THOMPSON>TEDESCO v LONG~LAINAS BENAROYA lr VOLL14ER~ENTON (4)GRXMES GAMMXLL KASTNER BALI JQU)FINE EHVIRO MOLL?R DICKER KNIGHTON YOUNGBIOOD |
| 'ROJL'CTLEADERHARLESSPSMSMILEXNUSSBAUMER LICASST.SERVICEMASONWIISONKARISMITHGEARINDXGGSTEETSWADESHAFERBROWNJAPIHDBRAITMANSALTZMANPIAHSMODOHALDDUDEC~MILES~1-'LOCAL PDROsweoNY~l-mIE(LAUGHL-.N Vl<<NSIC(BUCHANAN) 1-ASLB-Yoaz/SAYRE WOODWARD/HE ST.~16CYSACRSHOLDINGEXTERNALDXSTBIBUTXON (X(5)(9)-NATIONAL LAB>sANL/ORNL/PNL 1-R.CARROLL-OC~ | | 'RO JL'CT LEADER HARLESS PSM SMILEX NUSSBAUMER LIC ASST.SERVICE MASON WIISON KARI SMITH GEARIN DXGGS TEETS WADE SHAFER BROWN JAP IHD BRAITMAN SALT ZMAN PIAHS MODOHALD DUDE C~MILES~1-'LOCAL PDR Oswe o N Y~l-mIE(LAUGHL-.N Vl<<NSIC(BUCHANAN) 1-ASLB-Yoaz/SAYRE WOODWARD/HE ST.~16 CYS ACRS HOLDING EXTERNAL DXSTBIBUTXON (X (5)(9)-NATIONAL LAB>s ANL/ORNL/PNL 1-R.CARROLL-OC~ |
| GTB3271>>R.CATLIN)A-170-GT1CONSULANT'S NEWMARK/BLUAA/AGABIAN 1-PDR-SAN/LA/NY, 1-GERALDLELLUCHEBROOKHAVEN NAT.LAB1BOLANDpIDAHOFALLS~IDAHO(50>>331 Only)l-aD..mrzza..F-3o9GT F~~(~'\-*~~~o~IP('i c;.'t"'05~0E-.~>~IN'tuG<
| | GT B327 1>>R.CATLIN)A-170-GT 1 CONSULANT'S NEWMARK/BLUAA/AGABIAN 1-PDR-SAN/LA/NY, 1-GERALD LELLUCHE BROOKHAVEN NAT.LAB 1 BOLANDp IDAHO FALLS~IDAHO(50>>331 Only)l-aD..mrzza..F-3o9GT F~~(~'\-*~~~o~I P ('i c;.'t"'05~0 E-.~>~IN'tuG< |
| >gal~9~IJUITORy | | >gal~9~IJUITORy.,f~~am b j Regtitafory',. |
| .,f~~ambjRegtitafory',. | | Ffte Cy-..NIAGARA~ŽMOHAWK 300 ERIE 8OUI EVARD WEST SYRACUSE, H.Y.IS202 NIAGARA MOHAWK POWER CORPORATION August 1, 1972 Mr.Donald J.Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing United States Atomic Energy Commission Washington, D.C.20545 8 |
| FfteCy-..NIAGARA~ŽMOHAWK300ERIE8OUIEVARDWESTSYRACUSE, H.Y.IS202NIAGARAMOHAWKPOWERCORPORATION August1,1972Mr.DonaldJ.SkovholtAssistant DirectorforReactorOperations DivisionofReactorLicensing UnitedStatesAtomicEnergyCommission Washington, D.C.205458
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| ==DearMr.Skovholt:== | | ==Dear Mr.Skovholt:== |
| | | Re: Provisional Operating License: DPR-17 Docket No.: 50-220 Appendix A (Technical Specifications 3.3.1 a and 3.3.1 b)of Provisional Operating License DPR-17 for Nine Mile Point Nuclear Station, Unit Ol states: 3.3.1 a"After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than five percent oxygen with nitrogen gas whenever the reactor coolant pressure is greater than 110 psig and the reactor is in the power operating condition, except as.specified in"b" below." 3.3.1 b"Within the 24 hour period subsequent to increase of the reactor coolant pressure above 110 psig whenever the reactor is in the power.operating conditj.on, the containment atmosphere oxygen concentration shall be reduced to less than five percent by weight and maintained in this con-dition.Deinerting was commenced 24 hours prior to a major refueling outage or other scheduled shutdown." An orderly shutdown of Unit 81, Nine Mile Point Nuclear Station was begun on July 27, 1972 due to increasing recirculation system valve packing leakage within the drywell.Following repacking of the affected valves, the unit was restarted on July 30, 1972 and reached 110 psig at 0700 that day. |
| Re:Provisional Operating License:DPR-17DocketNo.:50-220AppendixA(Technical Specifications 3.3.1aand3.3.1b)ofProvisional Operating LicenseDPR-17forNineMilePointNuclearStation,UnitOlstates:3.3.1a"Aftercompletion ofthestartuptestprogramanddemonstration ofplantelectrical output,theprimarycontainment atmosphere shallbereducedtolessthanfivepercentoxygenwithnitrogengaswheneverthereactorcoolantpressureisgreaterthan110psigandthereactorisinthepoweroperating condition, exceptas.specified in"b"below."3.3.1b"Withinthe24hourperiodsubsequent toincreaseofthereactorcoolantpressureabove110psigwheneverthereactorisinthepower.operating conditj.on, thecontainment atmosphere oxygenconcentration shallbereducedtolessthanfivepercentbyweightandmaintained inthiscon-dition.Deinerting wascommenced 24hourspriortoamajorrefueling outageorotherscheduled shutdown." | | )~~~~I 4 I 4~~ |
| AnorderlyshutdownofUnit81,NineMilePointNuclearStationwasbegunonJuly27,1972duetoincreasing recirculation systemvalvepackingleakagewithinthedrywell.Following repacking oftheaffectedvalves,theunitwasrestarted onJuly30,1972andreached110psigat0700thatday.
| | Mx.Donald J.Skovho1t United States Atomic Energy Commission 0 Page 2 An agreement had been made prior to shutdown with National Cylinder Gas, a nitrogen gas supplier in Conshohocken, Pa.for delivery of two trucks of nitrogen on July 30, 1972.Normal inerting requires 4-6 hours and could easily be accomplished that day, well within the required 24 hours.However, unknown to station personnel, the gas supplier was having difficulty in obtaining drivers for the necessary two trucks of nitrogen.The startup of the Unit beyond 110 psig continued, based upon the prior agreement that nitrogen would be arriving for inerting that day.At midnight, July 30, 1972 with no nitrogen for inerting on site, it was deemed necessary by station personnel to hold thermal power to 1200 MN(t)and not continue with the normal scheduled startup until the drywell was inerted.The first truck of nitrogen arrived at the station the morning of July 31, 1972 and inerting began immediately. |
| )~~~~I4I4~~ | | The drywell atmosphere was reduced to less than five percent oxygen at 134S that day, reaching 3.9 percent at 1400.The start up scheduled then continued. |
| Mx.DonaldJ.Skovho1tUnitedStatesAtomicEnergyCommission 0Page2Anagreement hadbeenmadepriortoshutdownwithNationalCylinderGas,anitrogengassupplierinConshohocken, Pa.fordeliveryoftwotrucksofnitrogenonJuly30,1972.Normalinertingrequires4-6hoursandcouldeasilybeaccomplished thatday,wellwithintherequired24hours.However,unknowntostationpersonnel, thegassupplierwashavingdifficulty inobtaining driversforthenecessary twotrucksofnitrogen. | | The drywell atmosphere remained within specification following inerting and with the arrival of the second truck late in the evening, July 31, 1972 was reduced to its present level of one percent by weight of oxygen.Very truly yours, F.J.Schn'eider Vice President e Operations 1 t l l J t}} |
| ThestartupoftheUnitbeyond110psigcontinued, basedupontheprioragreement thatnitrogenwouldbearrivingforinertingthatday.Atmidnight, July30,1972withnonitrogenforinertingonsite,itwasdeemednecessary bystationpersonnel toholdthermalpowerto1200MN(t)andnotcontinuewiththenormalscheduled startupuntilthedrywellwasinerted.ThefirsttruckofnitrogenarrivedatthestationthemorningofJuly31,1972andinertingbeganimmediately.
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| Thedrywellatmosphere wasreducedtolessthanfivepercentoxygenat134Sthatday,reaching3.9percentat1400.Thestartupscheduled thencontinued.
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| Thedrywellatmosphere remainedwithinspecification following inertingandwiththearrivalofthesecondtrucklateintheevening,July31,1972wasreducedtoitspresentlevelofonepercentbyweightofoxygen.Verytrulyyours,F.J.Schn'eider VicePresident eOperations 1tllJt}}
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARML16319A0982016-11-0808 November 2016 Special Report: Inoperable Drywell Pressure Monitor/Suppression Chamber Water Level Instrumentation ML15174A1282015-06-19019 June 2015 Special Report: Containment High Range Radiation Monitor Instrumentation Channel #12 Inoperable NMP1L2980, 10 CFR 50.46 30-Day Report2014-12-12012 December 2014 10 CFR 50.46 30-Day Report ML12268A0492012-09-12012 September 2012 Discovery of Tritium in Groundwater In-Leakage - 30-Day Report in Accordance with the Industry Ground Water Protection Initiative ML11165A2212011-06-0606 June 2011 Day Report Pursuant to 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors ML1109701512011-04-0101 April 2011 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML0919505792009-07-0808 July 2009 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable ML0913904002009-05-11011 May 2009 Submittal of Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable ML0802305112008-01-11011 January 2008 Special Report: Inoperable Suppression Chamber Water Level Instrument ML0701704682007-01-11011 January 2007 Report of Changes or Errors Discovered in the Current Acceptable Emergency Core Cooling System Evaluation Models ML0618703962006-06-19019 June 2006 Special Report; Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Unplanned Maintenance ML0526401672005-09-12012 September 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0525004162005-08-29029 August 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0522402502005-08-0303 August 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0506901722005-03-0101 March 2005 Special Report, Channel No. 11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0502501452005-01-17017 January 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0420403002004-07-12012 July 2004 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Nine Mile Point Unit 1 ML0407607562004-03-0505 March 2004 Special Report, Channel #11 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0406409232004-02-20020 February 2004 Special Report, Channel #12 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0236101942002-12-13013 December 2002 Special Report, Channel #12 Accident Monitoring Instrumentation Inoperable Due to Loss of Power ML0233304002002-10-31031 October 2002 Special Report, Channel #11 Containment High Range Radiation Monitor Declared Inoperable to Repair Failed Chart Recorder ML0207905522002-03-0404 March 2002 Special Report Re Channel 12 Chamber Water Level Indicator Inoperable ML0208404412002-02-25025 February 2002 Special Report, Channel #11 Containment High Range Radiation Monitor Inoperable ML0206502942002-02-20020 February 2002 Special Report Re Channel #12 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0205801952002-02-0808 February 2002 Special Report, Channel #12 Suppression Chamber Water Level Indicator Inoperable ML0205002372002-01-21021 January 2002 Special Report Re Channel 11 Containment Hydrogen Monitoring System Inoperable for Scheduled Elective Maintenance ML18094A0311977-09-0707 September 1977 Telecopy Message from Niagara Mohawk Power Corp Re Event on 9/7/1977 Re August 1977 Liquid Waste Monthly Chemical Composite Analysis ML17037C1301972-08-0101 August 1972 Letter Reporting an Orderly Shutdown on July 27, 1972 Due to Increasing Recirculation System Valve Packing Leakage within the Drywell ML17037C1011972-04-19019 April 1972 Letter Reporting Findings on Incident That Occurred on 12/31/1971 in Which Unit 1 Tripped Off Line as Result of Surveillance Testing ML17037C1021972-04-18018 April 1972 Letter Reporting an Incident Tripped Off-Line as a Result of a Malfunction in a Continuous Power Supply on 02/28/72 ML17037C1371971-09-25025 September 1971 Letter Regarding a Maintenance Item Occurring During the Outage of Unit 1 in April-May 1971 ML17037C1421970-03-10010 March 1970 Letter Reporting an Incident, During Radiography and Ultrasonic Testing, That Disclosed a Series of Cracks Extending Around the Upper 180 Degrees of the Inside Diameter, Exist in the Stainless Steel Safe-End of the Core Spray.. ML17037C1431970-03-0606 March 1970 Letter Notifying the Commission of a Situation in Which Waste Discharge in Excess of Technical Specifications Has Taken Place on February 26, 1970 ML17037C1441969-12-0606 December 1969 Letter Reporting That the Nine Mile Point Reactor Was Scrammed from 25 Percent Power on November 20, 1969 and Advising That the Reactor Will Be Brought Critical and the Turbo-Generator Set Placed on the Line on December 8, 1969 ML17037C1451969-11-18018 November 1969 Letter Reporting an Incident on November 8, 1969 Where the Reactor Scrammed on Momentary Upscale Trips from Intermediate Range Monitoring Channels 2016-11-08
[Table view] |
Text
AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TEMPORARY FORM FROM'iagara Mohawk Power Corpo Syracuse~N.Y.13202 F J.Schneider DATE OF DOC: tion 8<<1-72 DATE REC'D 8.-4 2 LTR FI iRMO RPT To: Mr.Skovholt ORIG CC ('ENT AEC PDR~SENT LOCAL PDR CLASS: U PROP INFO DE IPTION: Ltr reporting an incident on 7-27-72~regarding an increasing recirculation syst va5W packing leakage within the drywell." No CYS REC'D ENCLOSURES:
DOCKET No: 0 220 PLANT NAMES: Nine Mble 00 NOT REMOVE II%NO'RFtIH Foa ACTION INFORMATION
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)W/Copies DICKER(ENVIRO)
--=--=--W/-=Copies KNIGHTON ENVIRO W/Copies W/Copies W/Copies iNTERNAL DISTRXBUTION G HAEC PDR VOGCp ROOM P-506A WNi&i'TZING/STAr(('ASE GIAl4BUSSO
~BOYD-L(Btla)
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Ffte Cy-..NIAGARA~ŽMOHAWK 300 ERIE 8OUI EVARD WEST SYRACUSE, H.Y.IS202 NIAGARA MOHAWK POWER CORPORATION August 1, 1972 Mr.Donald J.Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing United States Atomic Energy Commission Washington, D.C.20545 8
Dear Mr.Skovholt:
Re: Provisional Operating License: DPR-17 Docket No.: 50-220 Appendix A (Technical Specifications 3.3.1 a and 3.3.1 b)of Provisional Operating License DPR-17 for Nine Mile Point Nuclear Station, Unit Ol states: 3.3.1 a"After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than five percent oxygen with nitrogen gas whenever the reactor coolant pressure is greater than 110 psig and the reactor is in the power operating condition, except as.specified in"b" below." 3.3.1 b"Within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to increase of the reactor coolant pressure above 110 psig whenever the reactor is in the power.operating conditj.on, the containment atmosphere oxygen concentration shall be reduced to less than five percent by weight and maintained in this con-dition.Deinerting was commenced 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a major refueling outage or other scheduled shutdown." An orderly shutdown of Unit 81, Nine Mile Point Nuclear Station was begun on July 27, 1972 due to increasing recirculation system valve packing leakage within the drywell.Following repacking of the affected valves, the unit was restarted on July 30, 1972 and reached 110 psig at 0700 that day.
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Mx.Donald J.Skovho1t United States Atomic Energy Commission 0 Page 2 An agreement had been made prior to shutdown with National Cylinder Gas, a nitrogen gas supplier in Conshohocken, Pa.for delivery of two trucks of nitrogen on July 30, 1972.Normal inerting requires 4-6 hours and could easily be accomplished that day, well within the required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.However, unknown to station personnel, the gas supplier was having difficulty in obtaining drivers for the necessary two trucks of nitrogen.The startup of the Unit beyond 110 psig continued, based upon the prior agreement that nitrogen would be arriving for inerting that day.At midnight, July 30, 1972 with no nitrogen for inerting on site, it was deemed necessary by station personnel to hold thermal power to 1200 MN(t)and not continue with the normal scheduled startup until the drywell was inerted.The first truck of nitrogen arrived at the station the morning of July 31, 1972 and inerting began immediately.
The drywell atmosphere was reduced to less than five percent oxygen at 134S that day, reaching 3.9 percent at 1400.The start up scheduled then continued.
The drywell atmosphere remained within specification following inerting and with the arrival of the second truck late in the evening, July 31, 1972 was reduced to its present level of one percent by weight of oxygen.Very truly yours, F.J.Schn'eider Vice President e Operations 1 t l l J t