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| {{#Wiki_filter:+Pl'4g%t p E4 USAEC MASH US GOVERNMENT ATOMIC ENERGY COMM HDQTRS N M 9MILE OStl%710-547-0657 3"10-70'%00 PM EST k~)LRKl MF 19705(hA l0 pg g g)4O'V.S.ATOHfC EN)RGY COMM.T)YX'uillT | | {{#Wiki_filter:4g% |
| ~Yg ATTENTIONX DR PETER".p DIVISION OF REACTOR LICENSING GENTLEMEN' | | +Pl ' |
| +ffjp, 9/gN lq~SUBJECTS DOCKET NO.50"220,"P~Oi Le XDPR-17 I RADIOGRAPHY AND ULTRASONIC TESTING ON MARCH 8 1970 DISCLOSED THAT A SERIES OF CRACKS EXTENDING AROUND THE UPPER 180 DEGREES bF THE INSIDE DIAMETERS EXISTED IN THE STAINLESS STEEL SAFE-END OF THE CORE r SPRAY NOZZLE LOCATED AT AZIMUTH'40 DEGREES OF THE NINE MILE POlNT NUCLEAR STATION REACTOR VESSELS TMO VERY SMALL LEAKS MERE DETECTED SEVERAL DAYS PREVIOUS'UHICH LED TO THE APPLICATION OF NON-DESTRUCTIVE TESTING+UHEN DISCOVERED~ | | t p E4 USAEC MASH US GOVERNMENT k~)LRKl MF ATOMIC ENERGY COMM HDQTRS 19705(hA l0 pg g g) 4O |
| THE REACTOR HAS OUT OF SERVICE IN A COLD'SHUT-DObN CONDITl ON,'I I*4I 4 | | 'V.S. ATOHfC EN)RGY COMM. |
| .-nkvd'--X'tl~.>W p~s'''''l'p c p a>.,s%tg't IT IS NECESSARY TO REHOVK THE EFFECTED NATERIAL OF THE SAFE"END FOR HETALURGICAL EXAHINATlON AS SOON AS POSSIBLKe THEREFORE'HE HATER LEVEL IN THE REACTOR VEST BE LOL'JERED TO FOUR FEET OVER THE ACTIVE FUEL+, THIS ALLOt'JS A THREE-INCH CONTROL BAND TO THE INVERT OF THE CORE SPRAY NOZZLE~TECHNICAL SPECIFICATIONS 2~1~i XW, PGe 6 DO NOT PERY)lT LOt'JKRING TO BELOW'EVEN FEET ELEVEN'INCHES OF NOld<AL LEVEL.THIS CORRESPONDS TO FOUR FKKTq EIGHT INCHES ABOVE TO TOP OF ACTIVE FUEL.%SEE BASES PG~9%+THEREFORE~ | | N M 9MILE OStl T)YX'uillT ~ Yg |
| t'JK'EQUEST A TKNPORARY CHANGE IN TECHNICAL SPECIFICATIONS TO ALLOtJ LOUERING TO FOUR FEET ABOVE ACTIVE FUEJ.t'JHICH IS ELEVATION 294 FEET.Ig ORDER TO ASSURE CO@)PLKTK SAFETY'HE FOLLOWING'TEPS UILL BK TAI<ENX" tJATKR LEVEL N, HANOHKTL'R LOOP ESTABLISHED TO OUTSIDE DRYtJKLL READABLE SEVERAL FEST ABOVE AND BKLOiJ REQUESTED LEVEL HONITORED BY OPERATOR X UI)H CONY)UNICATIONS TO CONTROL ROON., X, CLOS D CIRCUIT UNDERWATER TYPE TELEVISION, IN VESSEL AT WATERLINE MONITORED'IN CONTROL'ROOH.-743 I I.<XPOSURK 4)Z.II W | | %710-547-0657 3"10-70 '%00 PM EST ATTENTIONX DR PETER " . p 9 |
| >>1A R'FVEL''f'1v'Fxi.'-"'u~-;II EXPOSURE OF 105 R/HR bILL EX>>IST AT VESSEL-FLANGE | | DIVISION OF REACTOR LICENSING +ffjp, GENTLEMEN' /gN lq ~ |
| ~REGULAR CONCRETE FLOOR SHIELD PLU'GS bILL BE.REINSTALLED ABOVE VESSEL ATTENUAT'INC'IELD TO FsZLOt'00 NR/HR~THE FLOOR.AREA.[~JILL BE DECLARED A HIGH-,tADIATIGN ARFA-ANB ACCESS RESTRICTED. | | SUBJECTS DOCKET NO. 50"220, "P ~ Oi Le XDPR- 17 I |
| 'XPOSURE LEVELS i')ILL BE 1 t'MONITORED AS'EVEL IS SLO'>>'EELY LOUERED IN VESSEL~EnPQSU2Z IN THF UORK AREAR'RESENTLY AT 27 NR/HR GN COt<'i ACT Vi LL B~i AI~:T,>I"ZB AS LOU.AS PR>>ACTICAL | | RADIOGRAPHY AND ULTRASONIC TESTING ON MARCH 8 1970 DISCLOSED THAT A SERIES OF CRACKS EXTENDING AROUND THE UPPER 180 DEGREES bF THE INSIDE DIAMETERS EXISTED IN THE STAINLESS STEEL SAFE-END OF THE CORE r |
| <iITH LEAD SHEET SHIELDING INSIDE THE VESSE1.III'ONTROL GF LEVEL LGl" INTO THE VESS L FRGH THE CONT OL ROD DRIVE SY$TEii IS ABOUT 65.GPY~BR>>AII~AGE TO HGLB LEVEL IS AT PRESENT AND WILL BE iiAINTAINED THROUGH R>>EtlOTELY OPERATED" VALVES BET>iEEg THE CLEAN-UP SYSTEti AND ZITHLP CGtJDEiv'SER OR EQUIPhEHT BRAIN TAN<<~OPERATION IS FRGY>THE CONTROL R>>00tl~ONE OF THREE CONDENSATE PUHPS GILL BF, IN" CONTINUOUS OPERATION UHEREBY CONDENSATi". | | SPRAY NOZZLE LOCATED AT AZIMUTH'40 DEGREES OF THE NINE MILE POlNT NUCLEAR STATION REACTOR VESSELS TMO VERY SMALL LEAKS MERE DETECTED SEVERAL DAYS PREVIOUS 'UHICH LED TO THE APPLICATION OF NON-DESTRUCTIVE TESTING+ UHEN DISCOVERED~ THE REACTOR HAS OUT OF SERVICE IN A COLD |
| CA'N BE ADDED TO THE VESSEL BY REhOTE FEED>>~ATER VALVE OPERATION FROM THE CONTROL ROOtio IV+HEAT RLYiGVAL REGULAR hEAT REtiGVAL SYSTEYiSp REACTOR CLEAN"UP ANB/OR SHUT-D04N COOLING<lILL BE AVAILABLE AND IN SERVICE IN THEIR tqGRl>>iAL-OPZRATIivG iiIOBZS. | | 'I |
| I h(ll C U f't I 1 | | 'SHUT-DObN CONDITl ON, |
| -UPON CONPLETION OF PIPE CUTTING OPERATIONS AN EXPANDABLE PIPE PLUG HILL,BE INSERTED IN TPE NOZZLE AND RE1NFORCED | | |
| <~JITH JACK SCREl>S FROH THE OU7SIDE iN ORDER TO PREVENT THE PLUG FROID BEING BLOt'JN OUTo 4ATLR LEVEL UILL THEN BE RETURNED TO A POiNT NEAR THE FLANGE READABLE I OiN CLOSED CIRCUIT'ELEVISION AS AT PRESENTo LEVEL hAY BE INCREASE'D TO REFUELING LEVEL SHOULD INVESTIGATIONS SH04'NEED.FOR CORE UNLOADING~RESULTS Oi'HETALUR'GICAL, EXAMINATION UILL DETERt'1INE METHOD OF REPAIRp.BUT IN NO EVENT KILL REACTOR BE.OPERATED UITHOUT PRIOR NOTICE OF U o So'TOl'1IC ENERG7 COHYiiSSIONo | | I* 4I 4 IT IS |
| //INVESTIGATION OF ALL OTHER SAFEENDS ON VESSEL ARE PROCEEDING bITH P~To p UoTo p AND R~To HETHODS~P.~A~BUiRT STATION SUPERINTENDENT N I~i 9NILE OSLJ u1 l o vl~at<v s"QQG3 p.",:,-'.,:'Q>V'8". | | .-nkvd'-- X'tl~.>W |
| eg a e i>uvAOE6~T N01103S 3',l",'i."..S | | ~ s' '' ' 'l'p c p a >.,s%tg 't p NECESSARY TO REHOVK THE EFFECTED NATERIAL OF THE SAFE"END FOR HETALURGICAL EXAHINATlON AS SOON AS POSSIBLKe THEREFORE'HE HATER LEVEL IN THE REACTOR VEST BE LOL'JERED TO FOUR FEET OVER THE ACTIVE FUEL+, THIS ALLOt'JS A THREE-INCH CONTROL BAND TO THE INVERT OF THE CORE SPRAY NOZZLE ~ TECHNICAL SPECIFICATIONS 2 ~ 1 ~ i XW, PGe 6 DO NOT PERY)lT LOt'JKRING TO BELOW'EVEN FEET ELEVEN 'INCHES OF NOld<AL LEVEL. |
| '11VN SU3lHVAAV~H p%p al''~r}} | | THIS CORRESPONDS TO FOUR FKKTq EIGHT INCHES ABOVE TO TOP OF ACTIVE FUEL. %SEE BASES PG ~ 9%+ |
| | THEREFORE~ t'JK'EQUEST A TKNPORARY CHANGE IN TECHNICAL SPECIFICATIONS TO ALLOtJ LOUERING TO FOUR FEET ABOVE ACTIVE FUEJ. t'JHICH IS ELEVATION 294 FEET. Ig ORDER TO ASSURE CO@)PLKTK SAFETY'HE FOLLOWING'TEPS UILL BK TAI<ENX |
| | " |
| | tJATKR LEVEL N, HANOHKTL'R LOOP ESTABLISHED TO OUTSIDE DRYtJKLL READABLE SEVERAL FEST ABOVE AND BKLOiJ REQUESTED LEVEL HONITORED BY OPERATOR X UI)H CONY)UNICATIONS TO CONTROL ROON., |
| | X, CLOS D CIRCUIT UNDERWATER TYPE TELEVISION,IN VESSEL AT WATERLINE MONITORED 'IN CONTROL 'ROOH.- |
| | 743 I I. <XPOSURK |
| | |
| | 4 ) |
| | Z. |
| | II W |
| | |
| | >>1A R'FVEL' 'f '1v' Fxi.'-"'u ~-; |
| | II EXPOSURE OF 105 R/HR bILL EX>>IST AT VESSEL-FLANGE ~ REGULAR CONCRETE FLOOR SHIELD PLU'GS bILL BE .REINSTALLED ABOVE VESSEL ATTENUAT'INC'IELD TO FsZLOt'00 NR/HR ~ THE FLOOR. AREA.[~JILL BE DECLARED A HIGH- |
| | ,tADIATIGN ARFA -ANB ACCESS RESTRICTED. 'XPOSURE LEVELS i')ILL BE 1 |
| | SLO'>>'EELY t'MONITORED AS 'EVEL IS LOUERED IN VESSEL ~ |
| | AREAR'RESENTLY EnPQSU2Z IN THF UORK AT 27 NR/HR GN COt<'i ACT ViLL B~ |
| | i AI~:T,>I"ZB AS LOU.AS PR>>ACTICAL <iITH LEAD SHEET SHIELDING INSIDE THE VESSE1. |
| | III'ONTROL GF LEVEL LGl" INTO THE VESS L FRGH THE CONT OL ROD DRIVE SY$ TEii IS ABOUT 65. |
| | GPY ~ BR>>AII~AGE TO HGLB LEVEL IS AT PRESENT AND WILL BE iiAINTAINED THROUGH R>>EtlOTELY OPERATED" VALVES BET>iEEg THE CLEAN-UP SYSTEti AND ZITHLP CGtJDEiv'SER OR EQUIPhEHT BRAIN TAN<< ~ OPERATION IS FRGY> THE CONTROL R>>00tl ~ ONE OF THREE CONDENSATE PUHPS GILL BF, IN" CONTINUOUS OPERATION UHEREBY CONDENSATi". CA'N BE ADDED TO THE VESSEL BY REhOTE FEED>>~ATER VALVE OPERATION FROM THE CONTROL ROOtio IV+ HEAT RLYiGVAL REGULAR hEAT REtiGVAL SYSTEYiSp REACTOR CLEAN"UP ANB/OR SHUT-D04N COOLING <lILL BE AVAILABLE AND IN SERVICE IN THEIR tqGRl>>iAL- OPZRATIivG iiIOBZS. |
| | |
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| | 't I |
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| | |
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| | UPON CONPLETION OF PIPE CUTTING OPERATIONS AN EXPANDABLE PIPE PLUG HILL,BE INSERTED IN TPE NOZZLE AND RE1NFORCED <~JITH JACK SCREl>S FROH THE OU7SIDE iN ORDER TO PREVENT THE PLUG FROID BEING BLOt'JN OUTo 4ATLR LEVEL UILL THEN BE RETURNED TO A POiNT NEAR THE FLANGE READABLE I |
| | OiN CLOSED CIRCUIT'ELEVISION AS AT PRESENTo LEVEL hAY BE INCREASE'D TO REFUELING LEVEL SHOULD INVESTIGATIONS SH04 'NEED. FOR CORE UNLOADING~ |
| | RESULTS Oi'HETALUR'GICAL,EXAMINATION UILL DETERt'1INE METHOD OF REPAIRp |
| | .BUT IN NO EVENT KILL REACTOR BE. OPERATED UITHOUT PRIOR NOTICE OF U o So'TOl'1IC ENERG7 COHYiiSSIONo / |
| | / |
| | INVESTIGATION OF ALL OTHER SAFEENDS ON VESSEL ARE PROCEEDING bITH P ~ To p UoTo p AND R ~ To HETHODS ~ |
| | P. ~ A~ BUiRT STATION SUPERINTENDENT N I~i 9NILE OSLJ |
| | |
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| | ~ s "QQG3 p.",:, -'.,:'Q>V'8". |
| | eg a e T i> uvAOE6~ |
| | N01103S 3',l",'i."..S '11VN SU3lHVAAV~H al ''~r p %p}} |
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Category:Letter
MONTHYEARIR 05000220/20244022024-11-20020 November 2024 Material Control and Accounting Program Inspection Report 05000220/2024402 and 05000410/2024402 (Cover Letter Only) IR 05000410/20240032024-11-0808 November 2024 Integrated Inspection Report 05000220/1014003 and 05000410/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24268A3382024-10-16016 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) IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing 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 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 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report 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 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
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t p E4 USAEC MASH US GOVERNMENT k~)LRKl MF ATOMIC ENERGY COMM HDQTRS 19705(hA l0 pg g g) 4O
'V.S. ATOHfC EN)RGY COMM.
N M 9MILE OStl T)YX'uillT ~ Yg
%710-547-0657 3"10-70 '%00 PM EST ATTENTIONX DR PETER " . p 9
DIVISION OF REACTOR LICENSING +ffjp, GENTLEMEN' /gN lq ~
SUBJECTS DOCKET NO. 50"220, "P ~ Oi Le XDPR- 17 I
RADIOGRAPHY AND ULTRASONIC TESTING ON MARCH 8 1970 DISCLOSED THAT A SERIES OF CRACKS EXTENDING AROUND THE UPPER 180 DEGREES bF THE INSIDE DIAMETERS EXISTED IN THE STAINLESS STEEL SAFE-END OF THE CORE r
SPRAY NOZZLE LOCATED AT AZIMUTH'40 DEGREES OF THE NINE MILE POlNT NUCLEAR STATION REACTOR VESSELS TMO VERY SMALL LEAKS MERE DETECTED SEVERAL DAYS PREVIOUS 'UHICH LED TO THE APPLICATION OF NON-DESTRUCTIVE TESTING+ UHEN DISCOVERED~ THE REACTOR HAS OUT OF SERVICE IN A COLD
'I
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~ s' ' 'l'p c p a >.,s%tg 't p NECESSARY TO REHOVK THE EFFECTED NATERIAL OF THE SAFE"END FOR HETALURGICAL EXAHINATlON AS SOON AS POSSIBLKe THEREFORE'HE HATER LEVEL IN THE REACTOR VEST BE LOL'JERED TO FOUR FEET OVER THE ACTIVE FUEL+, THIS ALLOt'JS A THREE-INCH CONTROL BAND TO THE INVERT OF THE CORE SPRAY NOZZLE ~ TECHNICAL SPECIFICATIONS 2 ~ 1 ~ i XW, PGe 6 DO NOT PERY)lT LOt'JKRING TO BELOW'EVEN FEET ELEVEN 'INCHES OF NOld<AL LEVEL.
THIS CORRESPONDS TO FOUR FKKTq EIGHT INCHES ABOVE TO TOP OF ACTIVE FUEL. %SEE BASES PG ~ 9%+
THEREFORE~ t'JK'EQUEST A TKNPORARY CHANGE IN TECHNICAL SPECIFICATIONS TO ALLOtJ LOUERING TO FOUR FEET ABOVE ACTIVE FUEJ. t'JHICH IS ELEVATION 294 FEET. Ig ORDER TO ASSURE CO@)PLKTK SAFETY'HE FOLLOWING'TEPS UILL BK TAI<ENX
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tJATKR LEVEL N, HANOHKTL'R LOOP ESTABLISHED TO OUTSIDE DRYtJKLL READABLE SEVERAL FEST ABOVE AND BKLOiJ REQUESTED LEVEL HONITORED BY OPERATOR X UI)H CONY)UNICATIONS TO CONTROL ROON.,
X, CLOS D CIRCUIT UNDERWATER TYPE TELEVISION,IN VESSEL AT WATERLINE MONITORED 'IN CONTROL 'ROOH.-
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II EXPOSURE OF 105 R/HR bILL EX>>IST AT VESSEL-FLANGE ~ REGULAR CONCRETE FLOOR SHIELD PLU'GS bILL BE .REINSTALLED ABOVE VESSEL ATTENUAT'INC'IELD TO FsZLOt'00 NR/HR ~ THE FLOOR. AREA.[~JILL BE DECLARED A HIGH-
,tADIATIGN ARFA -ANB ACCESS RESTRICTED. 'XPOSURE LEVELS i')ILL BE 1
SLO'>>'EELY t'MONITORED AS 'EVEL IS LOUERED IN VESSEL ~
AREAR'RESENTLY EnPQSU2Z IN THF UORK AT 27 NR/HR GN COt<'i ACT ViLL B~
i AI~:T,>I"ZB AS LOU.AS PR>>ACTICAL <iITH LEAD SHEET SHIELDING INSIDE THE VESSE1.
III'ONTROL GF LEVEL LGl" INTO THE VESS L FRGH THE CONT OL ROD DRIVE SY$ TEii IS ABOUT 65.
GPY ~ BR>>AII~AGE TO HGLB LEVEL IS AT PRESENT AND WILL BE iiAINTAINED THROUGH R>>EtlOTELY OPERATED" VALVES BET>iEEg THE CLEAN-UP SYSTEti AND ZITHLP CGtJDEiv'SER OR EQUIPhEHT BRAIN TAN<< ~ OPERATION IS FRGY> THE CONTROL R>>00tl ~ ONE OF THREE CONDENSATE PUHPS GILL BF, IN" CONTINUOUS OPERATION UHEREBY CONDENSATi". CA'N BE ADDED TO THE VESSEL BY REhOTE FEED>>~ATER VALVE OPERATION FROM THE CONTROL ROOtio IV+ HEAT RLYiGVAL REGULAR hEAT REtiGVAL SYSTEYiSp REACTOR CLEAN"UP ANB/OR SHUT-D04N COOLING <lILL BE AVAILABLE AND IN SERVICE IN THEIR tqGRl>>iAL- OPZRATIivG iiIOBZS.
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UPON CONPLETION OF PIPE CUTTING OPERATIONS AN EXPANDABLE PIPE PLUG HILL,BE INSERTED IN TPE NOZZLE AND RE1NFORCED <~JITH JACK SCREl>S FROH THE OU7SIDE iN ORDER TO PREVENT THE PLUG FROID BEING BLOt'JN OUTo 4ATLR LEVEL UILL THEN BE RETURNED TO A POiNT NEAR THE FLANGE READABLE I
OiN CLOSED CIRCUIT'ELEVISION AS AT PRESENTo LEVEL hAY BE INCREASE'D TO REFUELING LEVEL SHOULD INVESTIGATIONS SH04 'NEED. FOR CORE UNLOADING~
RESULTS Oi'HETALUR'GICAL,EXAMINATION UILL DETERt'1INE METHOD OF REPAIRp
.BUT IN NO EVENT KILL REACTOR BE. OPERATED UITHOUT PRIOR NOTICE OF U o So'TOl'1IC ENERG7 COHYiiSSIONo /
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INVESTIGATION OF ALL OTHER SAFEENDS ON VESSEL ARE PROCEEDING bITH P ~ To p UoTo p AND R ~ To HETHODS ~
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