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MONTHYEARAEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. 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Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) 2024-09-09
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AEC DISTRI i IG I FOR PART 50 DOCVET f,IAAF IAL (TEi'iPORARY FOAi'.I)'ONTROL NO: FILE: FRp;~.American Elec;Power NY, NY 10004 T.ED Ti ton DATE OF DOC DATE REC'D 1 2 LTR~I~I\~I vow RPT OTHcR'O: Region III, Keppler ORIG 1 signed CC OTHER SENT AEC'PDR SENT LOCAL PDR CLASS UN CLASS XXXXX D ESCR I P7 I Q N: PROPINFO INPUT NO CYS RFC'D 1 signed ENCLOSURES:
OC.,ET No: 0-3 S16 Ltr trans.copies of ltrs sent to Knuth re: deficiencies in coils on certain Westinghouse relays and improper wiring of the Foxboro Reactor Protection System on>>line test panel.PLANT NA11E: Cook 1&2 BUTLER (S)W/Copies.CLARK (S)g/Copies PARR (S)/Copies KNIEL (S)~N/Copies SCHWENCER (S)W/Copies.STOLZ (S)W/Copies vASSALLo (s)W/Copies PURPLE (S)W/Copies EG FI TECH REVIEW@GC, ROOM P-506-A+iIACCARRY
~L OSSICK/STAFF MIGHT SQASE 8'A>ILICKI GIAI BUS SO BOYD@TELLO MOORB (S)(BHR)HOUSTON DEYOUNG (S)(PI/IR)WlOVAK SKOVHOLT{S)0%0SS GoLLEl~(s)'PP0LITO P~COLI INS TEDESCO DENXSE~4NG REG OPR EAINAS~~ILE'REGXON QQ CENAROYA i.R.WILSON~STEELE~VOLIMER.ZIEMANN (S)W/Copies DXCKER (E)W/Copies KNIGHTON{E)$1/Copies YOUNGBLOOD (E)W/Co ies INTERNAL DISTill)U DE NEON GRIME S GAMMILL 4KASTNER BALLARD SPANGLER ENUIRO MULLER.DXCKER KNIGHT OH YOUNGBLOOD REGAN PROJECT LDR HARLESS REGAN (E)*M/Copies LEAR (S)W/Copies SPEXS (S)W/Copies 7 ION LIC.ASSI.~AI IND DIGGS (S)BRAITMAN GEARIN (S)SALTZMAN GOULBOURNE (S)B.HURT KREUTZER (E)LEE (S)PLANS MAIGRET (S)MCDDNALD EED{E)CHAPMAN SERVXCE (S)DUBE w/input'HEPPARD (S)E.COUPE SLIT',ER (E)'.Hirtf ield (2)SMITH (S)~KLEGJKR'TEETs (s)YF.wILLIAMs WILLIAMS (E)WILSON (S)INGRAM (S).Ii E>:TER~."LL DISTR IEUTIOM N=~4.<<TIC (ABERNATHY)(Pi-NS IC (BUCHANAN) 1<<.ASLB"NEIITON ANDERSON'-ACRS SENT,TO, LXC~ASST.QC.rVtC4 fŽ49=7+(1)(2)(10)"NATXONAL LABS 1<<1'..PENNX lGTON, RM E-201 G.T~1"CONSULTANTS NEWAARK/BLUHE/ASBABIAN 1-PDR SAN/LA/NY 1 BROOKHAVEN NAT LAB 1<<G~ULRXKSON, ORNA 1>>AGMED(RUTH GUSSMAN)RM B>>127 G.T.,1-J~RUNKLES, RM E-201 G.T.
t s AMERICAN EI.ECYRIC PORGIES Service Corporation 2 Broadfoay, Eno York, N.Y.10004 (2)2)422-4800 50-315 and 50-316 January 21)1975 Nuclear Regulatory Commission Directorate of Regulatory Operations Region IXX 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attention:
Mr.James G.Keppler Re ional Director Gentlemen:
Enclosed are copies of letters sent to Mr.Donald F.Knuth, Director, Directorate of Regulatory Operations on December 20, 19'Ii4.ibese letters addressed deficiencies in coils on certain Westinghouse relays and improper wiring of the Foxboro Reactor Protection System on-line test panel.Your office was not listed on the letter as receiving carbon copies.I apologize for any inconvenience this may have caused, Regulatory Operations.
Cd/pOCRE(EP cl USAEC Very truly yours, TET:ma Enclosure REGULATORY PAn.SECaON 6 POCKET CLERK T.E.Tipton Head Nuclear Safe4 and Licensing Section cc: R.S.Hunter/S.J.Milioti G.E.Lien S.Je Trippy-Bridgman AEC Letter Pile
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~~~e~AEC Letter File x h~.December 20>X974 Qoaket Vio.$0-31>~<aDC 50>>>2.6 CPPR Ha.61 and Df'8-$8 U.Be Atomic Zncrg7 Commission Diroclox'Gte of HeglllatoI'g Operations 792G Korfolh.t'avenue~Bethesda,~ary3.end 20&Attentionc Hr~Donald Fi 1Qmth, Mractor Gentle~."tens Pursuant to the regulations of'0GPFtg'O.gy~{o) ve here'~ith..ubmit t: htoxxrx.Seen rocorh ooxxcorntxxg an o<tux,pmexxe Gofict.ency that;occurred during construction at the Don&5 C.Cook fluc3.ear Plant, 3ridI;man, l!ichigm..
Unit 1 i" currently operat9.n, under.xiC Operating license 9Pik-58 aml Uni.2 is under construction.
under~NQ ConsB'uction Pemit No CPIii-.61.4 The c'equipment de'iciency has been idcntifiod as open circuited coils on certai'n Ke QtiQP~QI'3e relays{Catalog No'23)1AOZHg Stylo)is E4<49 Coil 177C/72 GGZ 240 VQC)>]1U.ch are u ed.in ylant sefegumds sy"gems.This doficioncy
.@as discovered aftor the above relays hah been in service for approximately 5 months and,.@as reported.by NET Re 8e ll'unter, Vice 1'resident, ihxcleax'ngineering, merican Flectric i'o~.er dervice Corporation to Hri Ceci3.Jones in a telephone conversation'on 13eceaber 2, 3.974 An investigation into this deficiency has determined that the voltage ratit~g of these pmticular relays i" insufficiont for all circuit coniitions Although thc voltage rating of 240 VDC is sufficient fox'ormal operation of the plant Direct Current Systeu<, they>>ore placed under voltages of approx'.ately 2GOVDO during periodic equal%.Dng charging of the plant batteries Repeated expo ure to this increased volt;age: hich caused a higher-than-"atcd current fd.o throu,".h the coi3.o resulted m overheating and opening of ttzeso co33.circuits~e'3 2975 1~~~
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)v~C Letter Pile'December 20, 19/4.Docket:fo.50-315 and 50-316'CPPB'No.'61 and DPH-.58 U.,'3.Atomic Enerpy Comnission Directq'rate of Bepulatory Operations 79:;0 Norfolk".venue Bethesda~Haryland<.0$4$Attention:
Hr, Donald F.Knuth, Director Gentleaen-'ursuant Co the regulations of 10 (TB5'O.g$(e3,:.?ere;.'ith subnit this written report concerning an equip!ment deficiency Ch:..t occurred during construction at Cho Donald C.Coo!<i!uclear Plant,~3ridgman, lQ.chigan.
Unit 1 is operating under Liconse Dl'H-q8 m!3 Uzd.t 2 is under construction u:vier l;~C construction perL!it CI'P.'".-61.
'he equi.praont deficiency has bean identified as i.aproper miring of the Poxboro ice"ctor Protection System on-line test panel.TM.s eouipmont is"upplied by::lestinghouse-TMs deficiency
~>as reported by Hr.R.0-Hunter, Vice President,.
nuclear Hngin ering, erican I'lectric Power service Corporation, to Hr~Coci1 iones in'telephone conversation on December 2, 19/4'ignals from the process sensors, vhich!;",easure various'safety-rolated parallleters are 8'Pocess 8, through Cho Poxboro Reactor Protection;-~y"Cea.
The on-lin'e test panel is provided Co enable periodic testing of protection circuitry during plant operation The difficulty arose because Cho bistable (comparator) output test sw5.tches used are double pole and, therefore, break both sides of the output to the load.~:nile the bistables only brea'.one side.Therefore; certain types of short qircuits could remain undetected.
As can oe seen in Pigure 1, a short circuit which shunts tho hist"bio" itching element'".6 th s"itch contact is undetected.
This is true because the return line is opened.Thus I e~p 4"-V l 4 g IP\E
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