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| {{#Wiki_filter:,A REGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS)'AOCESSION NBR'8303280050 DOC~DATE: 83/03/11 NOTARIZED: | | {{#Wiki_filter:}} |
| NO FACIL:50 3i'5 Donald O~Cook<<Nuclear Power Pl anti Uni.t 1R Indiana L'50 3i6 Donald O.Cook Nuclear Power Planti Uni,t 2i Indiana 8 AUTH~NAME'UTHOR AFF IL-I AT.ION HERINGi R~F~Indiana 8 Michigan Electric Co,'IRBCI.P~NAME-RECIPIENT AFFILIATION OEhlTONiH~R.Office-of Nuclear Reactor Regulationr,Director
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| ==SUBJECT:==
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| Requests extension;to 830615 to;provide addi info<<requested in Gener ic L<<tr 82"28 re,'inadequate core cooling instr umentation
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| <<sys;Summa<
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| y of previously submitted info re Nestinghouse differential pressure-monijtor ing sys encl.Dl'STRISUTION,CODE:
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| A046S COPIES"RECEIVED:LTR ENCI-L SIZE:.TITLE: OR Submittal'.
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| TMI Action Plan.Rgqt NUREG 0737 L NUREG-0660 NOTES!DOCKET 05000315 05000316 RECIPIENT ID<<CODE/NAME NRR ORB1 BC 01 COPIES LTTR ENCL<<7 RECIPIENT-ID'CODE/NAME COPIES'LTTR ENCL INTIERNAL:
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| ELO/HDS3 IE/DEPER/EPB NRRPAWLSON,N NRR/DL DIR 10 NRR/DL/ADSA 17 NRR/DSI/ADRS
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| '27 NRR/OSI/ASB.NRR/OST DIR 30 RGN3 1*0~3 3 1~1 1.1 1 1 1 1~1 1 1 1 1 1 1 1 1 1 1 1"3 3 1 1 1=1 04,1 1'IE/DEPER DIR 33~IE/DEPER/IRB NRR/DHFS/DEPY29 NRR/DL/ADL 16 NRR/OL/DRAB 18 NRR/OS I/AEB NRR/OS I/RAB EXTERNAL: ACRS I.PDR NSIC 10 10'NPOi J;STARNES 03 2 2 NRC'PDR 02 05 1 1 NTIS.1.1 1 1 1 1<<TOTAL NUMBER OF"COPIES REQUIRED: l<<TTR 44 ENCL Q3 tt tl t'1 l>>w(w c' 0.INDIANA R MICHIGAN ELECTRIC COMPANY P.O.8OX 18 80 WLIN G GR E EN ST ATION NEW YORK, N.Y.10004 March 11, 1983 AEP:NRC:0761 Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM (GENERIC LETTER NO.82-28)REQUEST FOR EXTENSION Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
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| ==Dear Mr.Denton:==
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| Upon receipt of Generic Letter No.82-28, an internal review was established, in order to provide the requested additional information concerning our Inadequate Core Cooling (ICC)Instrumen-tation System's conformance
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| 'with NUREG-0737, Item II.F.2.We are, however, presently unable to respond to this request in the format of the Generic Letter's attached checklist.
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| The inability to comply with the 90-day response time arises from a lack of available information concerning the finalization of the replacement in-core thermocouple system's design.AEPSC is currently negotiating with three vendors for the contract to replace existing in-core thermocouple system.Additionally, ongoing discussions are being conducted with Westinghouse regardi'ng the Reactor Vessel Level Instrumentation System's (RVLIS)calibration difficulties and equipment location.Accordingly, we hereby request an extension to June 15, 1983, so that we may appropriately address the concerns of Generic Letter No.82-28.We wish to state for the record, however, that the Westinghouse differential pressure monitoring system (RVLIS)is installed, in the Donald C.Cook Nuclear Plant to serve as the required reactor coolant inventory tracking system.As stated in Generic Letter No.82-28, the NRC has completed its generic review of the RVLIS and deemed it acceptable for tracking reactor coolant system inventory.
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| The subcooling margin monitors are installed and operational.
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| Information regarding the RVLIS and the subcooling margin monitors has o~4 8303280050 8303ii l Fan AOOCK 050003is I'i P PDR Jl
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| 'P*I K Ih IJ IJ\~lg g~eV...i ,~rQ 9 gI/td(J I3~J r ai.>i a~wa~"J i v'a~a~la~~a)~t~~
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| Mr.Harold R..on A.i RC:0761 been previously submitted to the NRC via various letters as summarized in Attachments 1 and 2, of this letter.We are in the process of conducting engineering studies concerning the in-core thermocouple system for Unit l.It is currently anticipated that the installation of this new thermocouple system should commence during the 1985 refueling outage.This schedule is based on an anticipated one year lead time for the equipment.
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| Following Unit 1's installation a plan will be developed to install a new thermocouple system in Unit 2.This document has been prepared following corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
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| Very truly yours,/os R.F.Hering Vice President cc: John E.Dolan-Columbus R.S.Hunter M.P.Alexich R.W.Jurgensen W.G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff NRC Resident Inspector at Cook Plant-Bridgman Attachment 1 to AEP:NRC:0761 The following submittals have been transmitted by AEP or by Westinghouse Electric Company (W)to the NRC in support of the RVLIS design.'a)
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| Letter No.AEP:NRC:0398D, dated March 31 1981 This letter served to transmit a version of the"Summary Report, Westinghouse Reactor Vessel Level Instrumentation System for Monitoring Inadequate Core Cooling (7300 System), December, 1980", which is applicable to the Donald C.Cook Nuclear Plant.(b)Letter Nos.AEP:NRC:0398F and AEP:NRC:0398G, dated Se tember 17 1981 and November 20, 1981 respectively These letters responded to Mr.S.A.Varga's letter of August 8, 1981 which requested additional information on the Westinghouse Summary Report on the RVLIS.(c)Su lementary Information Submittal letter from Mr.E.P.Rahe (W)to Mr.L.E.Phillips (NRC)NS-EPR-2579 of March 19, 1982.(d)'Westin house Evaluation of Tests Mr.E.P.Rahe's (W)letter to Mr.L.E.Phillips (NRC)NS-EPR-2526 of December 9, 1981 provided the results of tests S-UT-3, S-UT-6, S-UT-7, S-NC-2, S-NC-3, and S-NC-8, which support the evaluation of the RVLIS design.(e)Westin house Evaluation of Tests S-UT-8 Letter from Mr.E.P.Rahe (W)to Mr.L.E.Phillips (NRC), NS-EPR-2542 of January 13, 1982.(f)Westinghouse Evaluat'ion of Test S-1B-1 and Functional Test Letter from Mr.E.P.Rahe (QW to Mr.L.E.Phillips (NRC), SED-SA-0081 of June 28, 1982.(g)Response to Re uest to WOG for Additional Information Letter from Mr.E.P.Rahe (W)to Mr.Dennis M.Crutchfield (NRC), NS-EPR-2597 of May 14, 1982.
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| (h)RCS Mi.de Range Pressure Instrumentation r Letter from Mr.E.P.Rahe (W)to Mr.R.C.Young (NRC), NS-EPR-2586 of April 21, 1982.
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| Attachment 2 to AEP:NRC:0761 Thc following submittals have been transmitted to the NRC in-support of the subcooling margin monitor design..(a)Letter No.AEP:NRC:0253 dated October 24 1979 This letter served to notify the NRC of our intention to install subcooling margin monitors and of our interim method of determining subcooling margin.(b)Letter No.AEP:NRC:0253A, dated November 26, 1979 This letter responded to an NRC request for additional information on the subcooling margin monitor contained in Mr.Harold R.Denton's letter of October 30, 1979.(c)Letter No.AEP:NRC:0253B, dated December 19 1979 This letter provides a description of the plant parameters employed to calculate subcooling margin arith the Prodac plant computer, and display options available.(d)Letter No.AEP:NRC:0334 dated January 18 1980 This letter details our compliance with NUREG-0578 Section 2.1.3.b,"Instrumentation for Inadequate Core Cooling".(e)Letter No.AEP:NRC:0334B, dated March 10 1980 This letter provides a description of the subcooling margin monitor input processing employed to calculate the subcooling margin.The qualification of the subcooling margin monitor components is also addressed.(f)Letter No.AEP:NRC:0346 dated January 30, 1980 This letter provides the subcooling margin criteria for the termination of safety injection.
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| The NRC review determined that the saturation margin monitors meet the short term lessons learned requirements for Section 2.1.3.b of NUREG-0578.
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| The summary of this review is included in a letter from Mr.A.Schwencer to Mr.J.Dolan (AEP)dated March 20, 1980.
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