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| | issue date = 08/25/1987 | | | issue date = 08/25/1987 |
| | title = Forwards Proprietary Version of Rev 1 to ANF-87-91(P), DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Rept, Supporting Operation of Facility.Rept Withheld (Ref 10CFR2.790(b)) | | | title = Forwards Proprietary Version of Rev 1 to ANF-87-91(P), DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Rept, Supporting Operation of Facility.Rept Withheld (Ref 10CFR2.790(b)) |
| | author name = ADKISSON D A | | | author name = Adkisson D |
| | author affiliation = SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER | | | author affiliation = SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:lREGULATORY | | {{#Wiki_filter:l REGULATORY )FORMATION DISTRIBUTION SY M (R IDS) |
| )FORMATION DISTRIBUTION SYM(RIDS)~aACCESSIQN NBR:87083i0058DOC.DATE:87/08/25NOTARIZED: | | ~ a ACCESSIQN NBR: 87083i 0058 DOC. DATE: 87/08/25 NOTARIZED: YES DOCKET FACIL: 50-3i6 Donald C. Cook Nuclear Power Plant. Unit 2. Indiana 5 050003i6 AUTH. NAME AUTHOR AFFILIATION ADKISSQNp D.*. Advanced Nuclear Fuels Corp. (formerly Exxon Nuclear Co. p I RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| YESDOCKETFACIL:50-3i6DonaldC.CookNuclearPowerPlant.Unit2.Indiana5050003i6AUTH.NAMEAUTHORAFFILIATION ADKISSQNp D.*.AdvancedNuclearFuelsCorp.(formerly ExxonNuclearCo.pIRECIP.NAMERECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardsadvancednuclearfuelscorptechnical reptANF-87-9i(P)
| | Forwards advanced nuclear fuels corp technical rept ANF-87-9i(P) I Rev ip "DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Reptp" which supports operation of. |
| IRevip"DCCook2Debris-Resistant LowerTiePlatePressureDropTestReptp"whichsupportsoperation of.facility.
| | facility. |
| gW.C~sDIBTRIBUT IONCODE:PAOIDCOPIOUSRECEIVED: | | gW . C~s DIBTRIBUTION CODE: PAOID COPIOUS RECEIVED: LTR l ENCL ~ 0 BI ZE: (0 + |
| LTRlENCL~0BIZE:(0+TITLE:Psspsistasg ReviseDitacit'uti snOpzeta'ingRsastpnfNOTEB:RECIPIENTIDCODE/NAME PD3-3LAMIC('INGTON, D0k+,3INTERNAL:
| | TITLE: Psspsistasg Revise Di tacit'uti snOp zeta'i ng Rsastpn NOT EB: |
| AEOD/DOAOQC/HDSiEXTERNAL: | | f I I REC P ENT ID CODE/NAME COPIES LTTR ENCL RECIPIENT ID CODE/NAME |
| LPDRCOPIESLTTRENCLi33iii00AEOD/DSP/TPAB k~ii044.>NRCPDR0RECIPIENT
| | 'OP IES LTTR ENCL PD3-3 LA i PD3-3 PD MIC('INGTON, D 0 k+,3 3 3 INTERNAL: AEOD/DOA i i AEOD/DSP/TPAB k~ i i OQC/HDSi i 0 0 44.> |
| 'OPIESIDCODE/NAME LTTRENCLPD3-3PDTOTALNUMBEROFCOPIESREQUIRED:
| | EXTERNAL: LPDR 0 NRC PDR 0 TOTAL NUMBER OF COPIES REQUIRED: LTIR 'i ENCL 8 |
| LTIR'iENCL8 Wp-htll'$w,rWt<<)I'',l<<<<h'f"IQHWrIW<<)"'1~J''rI1'1h''W,H,"l( | |
| 'HIVj.HPIw'I~wll)r''1Pwhm,hfjvH4'H"','<<jj>>jjt)",,"'I~)<<jjmP<<HmhgWVIIHIHPI<<V AQVANCEDNUCLEAHFUELSCORPORATION 2101HORNRAPIDSROAD,POBOX130,RICHLAND, WA993524130 (509)375-8100TELEX:15-2878FUELENGINEERING aTECHNICAL SERVICESAugust25,1987DAA:014:8787083i0058 870825'DR ADOCH050003%6PPDRDonaldC.CookNuclearPlantNo.2DocketNo.50-316LicenseNo.DPR-74TRANSMITTAL OFANF-87-91(P),
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| REV.1,DCCOOK2DEBRIS-RESISTANT LOWERTIEPLATEPRESSUREDROPTESTREPORTU.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555
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| ==DearSir:== | | h |
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| | AQVANCEDNUCLEAHFUELS CORPORATION 2101 HORN RAPIDS ROAD, PO BOX 130, RICHLAND, WA 993524130 FUEL ENGINEERING a (509) 375-8100 TELEX: 15-2878 TECHNICAL SERVICES August 25, 1987 DAA: 014:87 87083i0058 050003%6 870825'DR ADOCH P PDR Donald C. Cook Nuclear Plant No. 2 Docket No. 50-316 License No. DPR-74 TRANSMITTAL OF ANF-87-91(P), REV. 1, DC COOK 2 DEBRIS-RESISTANT LOWER TIE PLATE PRESSURE DROP TEST REPORT U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 |
| | |
| | ==Dear Sir:== |
|
| |
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| ==Subject:== | | ==Subject:== |
| Transmittal ofDonaldC.CookUnit2Debris-Resistant LowerTiePlatePressureDropTestReportEnclosedaretencopieseachoftheAdvancedNuclearFuelsCorporation (ANF)technical reportANF-87-91(P), | | Transmittal of Donald C. Cook Unit 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report Enclosed are ten copies each of the Advanced Nuclear Fuels Corporation (ANF) technical report ANF-87-91(P), Rev. 1, entitled "DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report," which supports operation of the D.C. Cook Unit 2 Nuclear Plant, At the request of American Electric Power Service Company (AEPSC), this report is being transmitted directly by ANF. |
| Rev.1,entitled"DCCook2Debris-Resistant LowerTiePlatePressureDropTestReport,"whichsupportsoperation oftheD.C.CookUnit2NuclearPlant,AttherequestofAmericanElectricPowerServiceCompany(AEPSC),thisreportisbeingtransmitted directlybyANF.Thedocumenttransmitted viathisletterreflectschangesandanalysisofthelowertieplateusedinthemanufacture ofthereloadfueldesignated XN-4whichwillbeloadedinthereactorinApril1988.Thedocumentshowsanalysesandtestsperformed onthedebris-resistant tieplatedesign.ResultsoftheanalysesshowthattheCycle7reloadfueliscompatible withtheexistingANFfuelintheplant.ANFconsiders information contained intheenclosedtechnical reporttobeproprietary. | | The document transmitted via this letter reflects changes and analysis of the lower tie plate used in the manufacture of the reload fuel designated XN-4 which will be loaded in the reactor in April 1988. The document shows analyses and tests performed on the debris-resistant tie plate design. |
| TheAffidavit enclosedprovidesthenecessary information toallowthewithholding oftheproprietary versionfrompublicdisclosure asrequiredby10CFR2.790(b)~fI4'*'ANAFFILIATE OFKRAFTWERKUNIONQ~KSVU(QQ)d
| | Results of the analyses show that the Cycle 7 reload fuel is compatible with the existing ANF fuel in the plant. |
| | ANF considers information contained in the enclosed technical report to be proprietary. The Affidavit enclosed provides the necessary information to allow the withholding of the proprietary version from public disclosure as required by 10 CFR 2.790(b) ~ |
| | f '* ' |
| | I (QQ 4 |
| | )d AN AFFILIATEOF KRAFTWERK UNION Q~ KSVU |
| | |
| | U.S. Nuclear Regulatory DAA:014:87 Commission August 25, 1987 If you have any questions regarding this transmittal, please contact Hr. James G. Feinstein of AEPSC at (614) 233-2040. |
| | Yours very truly, D. A. Adkisson, Acting Hanager Reload Licensing DAA:llh Enclosures cc: Hr. H. P. Alexich (AEPSC) |
| | Hr. T. Georgantis (AEPSC) |
| | Hr. D. L. Wiggington (NRC) (w/Enclosures) |
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| | t Q |
| | Cp S |
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| | AFFIDAVIT STATE OF WASHINGTON ) |
| | ) ss. |
| | COUNTY OF BENTON ) |
| | I, H. E. Williamson being duly sworn, hereby say and depose: |
| | : l. I am Manager, Licensing and Safety Engineering, for Advanced Nuclear Fuels Corporation, ("ANF"), and as such I am authorized to execute this Affidavit. |
| | : 2. I am familiar with ANF's detailed document control system and policies which govern the protection and control of information. |
| | : 3. I am familiar with the document ANF-87-91(P), Revision 1, entitled "Donald C. Cook Unit 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report," referred to as "Document." Information contained in this Document has been classified by ANF as proprietary in accordance with the control system and policies established by ANF for the control and protection of information. |
| | : 4. The Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by ANF and not made available to the public. Based on my experience, I am aware that other companies- regard information of the kind contained in the Document as |
| | .pr'opriejyry .and confidential. |
| | : 5. -The Document has been made available to the U.S. Nuclear Regulatory Commission in confidence, with the request that the information 4 t contained in the Document will not be disclosed or divulged. |
| | |
| | T |
| | : 6. The Document contains information which is vital to a competitive advantage of ANF and would be helpful to competitors of ANF when competing with ANF. |
| | : 7. The information contained in the Document is considered to be proprietary by ANF because it reveals certain distinguishing aspects of debris-resistant lower tie plate which secure competitive advantage to ANF for fuel design optimization and marketability, and includes information utilized by ANF in its business which affords ANF an opportunity to obtain a competitive advantage over its competitors who do not or may not know or use the information contained in the Document, |
| | : 8. The disclosure of the proprietary information contained in the Document to a competitor would permit the competitor to reduce its expenditure of money and manpower and to, improve its competitive position by giving it extremely valuable insights into debris-resistant lower tie plate and would result in substantial harm to the competitive position of ANF. |
| | : 9. The Document contains proprietary information which is held in confidence by ANF and is not available in public sources. |
| | : 10. In accordance with ANF's policies governing the protection and control of information, proprietary information contained in the Document has been made available, on a limited basis, to others outside ANF only as required and under suitable agreement providing for nondisclosure and limited use of the information. |
| | ll. ANF policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis. |
| | : 12. This Document provides information which reveals the debris-resistant lower tie plate developed by ANF over the past several years. ANF has invested many thousands of dollars and many man-months of effort in developing the debris-resistant lower tie plate revealed in the Document. |
| | Assuming a competitor had available the same background data and incentives as ANF, the competitor might, at a minimum, develop the information for the same expenditure of manpower and money as ANF. |
| | THAT the statements made hereinabove are, to the best of my knowledge, information, and belief, truthful and complete. |
| | FURTHER AFFIANT SAYETH NOT. |
| | SWORN TO AND SUBSCRIBED before me this 8~~day of 1987. |
| | , noTARy,,PujLIC |
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| | l~ ! |
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| U.S.NuclearRegulatory Commission DAA:014:87 August25,1987Ifyouhaveanyquestions regarding thistransmittal, pleasecontactHr.JamesG.Feinstein ofAEPSCat(614)233-2040.
| | ADVANCEDNUCLEARFUELS CORPORATION 2101 HORN RAPIDS ROAD, PO BOX 130, RICHlAND. WA 993524130 FUEL ENGINEERING 8 I509I 375 8100 TELEX: 15.2878 TECHNICAL SERVICES August 25, 1987 DAA: 014: 87 Donald C. Cook Nuclear Plant No. 2 Docket No. 50-316 License No. DPR-74 TRANSMITTAL OF ANF-87-91(P),,REV. 1, DC COOK 2 DEBRIS-RESISTANT LOWER TIE PLATE PRESSURE DROP TEST REPORT U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 |
| Yoursverytruly,DAA:llhEnclosures D.A.Adkisson, ActingHanagerReloadLicensing cc:Hr.H.P.Alexich(AEPSC)Hr.T.Georgantis (AEPSC)Hr.D.L.Wiggington (NRC)(w/Enclosures) tQCp@@Cap+1')Sw%+>al0>ocr AFFIDAVIT STATEOFWASHINGTON
| |
| ))ss.COUNTYOFBENTON)I,H.E.Williamson beingdulysworn,herebysayanddepose:l.IamManager,Licensing andSafetyEngineering, forAdvancedNuclearFuelsCorporation,
| |
| ("ANF"),andassuchIamauthorized toexecutethisAffidavit.
| |
| 2.IamfamiliarwithANF'sdetaileddocumentcontrolsystemandpolicieswhichgoverntheprotection andcontrolofinformation.
| |
| 3.IamfamiliarwiththedocumentANF-87-91(P),
| |
| Revision1,entitled"DonaldC.CookUnit2Debris-Resistant LowerTiePlatePressureDropTestReport,"referredtoas"Document."
| |
| Information contained inthisDocumenthasbeenclassified byANFasproprietary inaccordance withthecontrolsystemandpoliciesestablished byANFforthecontrolandprotection ofinformation.
| |
| 4.TheDocumentcontainsinformation ofaproprietary andconfidential natureandisofthetypecustomarily heldinconfidence byANFandnotmadeavailable tothepublic.Basedonmyexperience, Iamawarethatothercompanies-regardinformation ofthekindcontained intheDocumentas.pr'opriejyry
| |
| .andconfidential.
| |
| 5.-TheDocumenthasbeenmadeavailable totheU.S.NuclearRegulatory Commission inconfidence, withtherequestthattheinformation 4tcontained intheDocumentwillnotbedisclosed ordivulged.
| |
| T 6.TheDocumentcontainsinformation whichisvitaltoacompetitive advantage ofANFandwouldbehelpfultocompetitors ofANFwhencompeting withANF.7.Theinformation contained intheDocumentisconsidered tobeproprietary byANFbecauseitrevealscertaindistinguishing aspectsofdebris-resistant lowertieplatewhichsecurecompetitive advantage toANFforfueldesignoptimization andmarketability, andincludesinformation utilizedbyANFinitsbusinesswhichaffordsANFanopportunity toobtainacompetitive advantage overitscompetitors whodonotormaynotknoworusetheinformation contained intheDocument, 8.Thedisclosure oftheproprietary information contained intheDocumenttoacompetitor wouldpermitthecompetitor toreduceitsexpenditure ofmoneyandmanpowerandto,improveitscompetitive positionbygivingitextremely valuableinsightsintodebris-resistant lowertieplateandwouldresultinsubstantial harmtothecompetitive positionofANF.9.TheDocumentcontainsproprietary information whichisheldinconfidence byANFandisnotavailable inpublicsources.10.Inaccordance withANF'spoliciesgoverning theprotection andcontrolofinformation, proprietary information contained intheDocumenthasbeenmadeavailable, onalimitedbasis,toothersoutsideANFonlyasrequiredandundersuitableagreement providing fornondisclosure andlimiteduseoftheinformation.
| |
| ll.ANFpolicyrequiresthatproprietary information bekeptinasecuredfileorareaanddistributed onaneed-to-know basis. 12.ThisDocumentprovidesinformation whichrevealsthedebris-resistant lowertieplatedeveloped byANFoverthepastseveralyears.ANFhasinvestedmanythousands ofdollarsandmanyman-months ofeffortindeveloping thedebris-resistant lowertieplaterevealedintheDocument.
| |
| Assumingacompetitor hadavailable thesamebackground dataandincentives asANF,thecompetitor might,ataminimum,developtheinformation forthesameexpenditure ofmanpowerandmoneyasANF.THATthestatements madehereinabove are,tothebestofmyknowledge, information, andbelief,truthfulandcomplete.
| |
| FURTHERAFFIANTSAYETHNOT.SWORNTOANDSUBSCRIBED beforemethis8~~dayof1987.,noTARy,,PujLIC l~4!14/g6*/
| |
| ADVANCEDNUCLEARFUELSCORPORATION 2101HORNRAPIDSROAD,POBOX130,RICHlAND.
| |
| WA993524130 I509I3758100TELEX:15.2878FUELENGINEERING 8TECHNICAL SERVICESAugust25,1987DAA:014:87DonaldC.CookNuclearPlantNo.2DocketNo.50-316LicenseNo.DPR-74TRANSMITTAL OFANF-87-91(P),,REV.
| |
| 1,DCCOOK2DEBRIS-RESISTANT LOWERTIEPLATEPRESSUREDROPTESTREPORTU.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555 | |
|
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|
| ==DearSir:== | | ==Dear Sir:== |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Transmittal ofDonaldC.CookUnit2Debris-Resistant LowerTiePlatePressureDropTestReportEnclosedaretencopieseachoftheAdvancedNuclearFuelsCorporation (ANF)technical reportANF-87-91(P), | | Transmittal of Donald C. Cook Unit 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report Enclosed are ten copies each of the Advanced Nuclear Fuels Corporation (ANF) technical report ANF-87-91(P), Rev. 1, entitled "DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report," which supports operation of the D.C. Cook Unit 2 Nuclear Plant. At the request of American Electric Power Service Company (AEPSC), this report is being transmitted directly by ANF. |
| Rev.1,entitled"DCCook2Debris-Resistant LowerTiePlatePressureDropTestReport,"whichsupportsoperation oftheD.C.CookUnit2NuclearPlant.AttherequestofAmericanElectricPowerServiceCompany(AEPSC),thisreportisbeingtransmitted directlybyANF.Thedocumenttransmitted viathisletterreflectschangesandanalysisofthelowertieplateusedinthemanufacture ofthereloadfueldesignated XN-4whichwillbeloadedinthereactorinApril1988.Thedocumentshowsanalysesandtestsperformed onthedebris-resistant tieplatedesign.ResultsoftheanalysesshowthattheCycle7reloadfueliscompatible withtheexistingANFfuelintheplant.ANFconsiders information contained intheenclosedtechnical reporttobeproprietary. | | The document transmitted via this letter reflects changes and analysis of the lower tie plate used in the manufacture of the reload fuel designated XN-4 which will be loaded in the reactor in April 1988. The document shows analyses and tests performed on the debris-resistant tie plate design. |
| TheAffidavit enclosedprovidesthenecessary information toallowthewithholding oftheproprietary versionfrompublicdisclosure asrequiredby10CFR2.790(b).
| | Results of the analyses show that the Cycle 7 reload fuel is compatible with the existing ANF fuel in the plant. |
| ANAfflLIAIE OfKRAf11VERK VNIOhlQwKitU U.S.NuclearRegulatory Commission DAA:014:87 August25,1987Ifyouhaveanyquestions regarding thistransmittal, pleasecontactMr.JamesG.Feinstein ofAEPSCat(614)233-2040.
| | ANF considers information contained in the enclosed technical report to be proprietary. The Affidavit enclosed provides the necessary information to allow the withholding of the proprietary version from public disclosure as required by 10 CFR 2.790(b). |
| Yoursverytruly,DAA:llhEnclosures D.A.Adkisson, ActingManagerReloadLicensing cc:Mr.M.P.Alexich(AEPSC)Mr.T.Georgantis (AEPSC)Mr.D.L.Wiggington (NRC)(w/Enclosures)}}
| | AN AfflLIAIEOf KRAf11VERK VNIOhl Qw KitU |
| | |
| | U.S. Nuclear Regulatory DAA:014:87 Commission August 25, 1987 If you have any questions regarding this transmittal, please contact Mr. James G. Feinstein of AEPSC at (614) 233-2040. |
| | Yours very truly, D. A. Adkisson, Acting Manager Reload Licensing DAA:llh Enclosures cc: Mr. M. P. Alexich (AEPSC) |
| | Mr. T. Georgantis (AEPSC) |
| | Mr. D. L. Wiggington (NRC) (w/Enclosures)}} |
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ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML20205P0591999-04-14014 April 1999
Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view]
Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML17328A3091990-06-20020 June 1990
Requests That Proprietary WCAP-12623 & Rev 4-P to CEN-313-P, Steam Generator Sleeving Rept & Steam Generator Tube Repair Using Leak Tight Sleeves, Respectively,Be Withheld from Public Disclosure (Ref 10CFR2.790)
ML20043C0771990-05-14014 May 1990
Requests That Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Be Withheld (Ref 10CFR2.790)
ML17326B4001988-07-22022 July 1988
Forwards Listed Topical Repts,Providing Fuel Storage Facility Thermal Hydraulic & Criticality Analysis Results. W/O Stated Encls
ML17334B1281987-08-25025 August 1987
Forwards Proprietary Version of Rev 1 to ANF-87-91(P), DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Rept, Supporting Operation of Facility.Rept Withheld (Ref 10CFR2.790(b))
ML17325A1271987-05-29029 May 1987
Forwards Proprietary XN-NF-87-31(P), Steamline Break Analysis for DC Cook Unit 2, Addressing Asymmetric Thermal Hydraulic & Neutronic Core Characteristics Resulting from Event.Rept Withheld (Ref 10CFR2.790)
ML20215D4081987-05-15015 May 1987
FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1
NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986
Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P
ML17324A7991986-04-24024 April 1986
Forwards Rev 1 to Proprietary XN-NF-85-68(P), DC Cook Unit 2 Limiting Break Loca/Eccs Analysis,10% Steam Generator Tube Plugging & K(Z) Curve. Rev Reflects Changes to Reflood Correlation Per NRC Concerns
ML17324A7731986-04-17017 April 1986
Forwards Proprietary Responses to NRC Questions 4 & 5 Re Rev 1 to XN-NF-85-64(P) Plant Transient Analysis for DC Cook Unit 2 w/10% Steam Generator Tube Plugging. Responses Withheld (Ref 10CFR2.790)
ML17326B2241986-04-14014 April 1986
Forwards Response to 860108 Question 10 Re XN-NF-85-28, DC Cook Unit 2 Sar. Info Provided Re Calculated Coolant Pressure Rise & DNBR During Rod Ejection Accident
ML17326B2111986-03-21021 March 1986
Forwards Proprietary Suppl 1 to Rev 1 to XN-NF-85-64(P), Plant Transient Analysis for DC Cook,Unit 2 W/10% Steam Generator Tube Plugging, Providing Revised Boron Dilution Analysis.Suppl Withheld (Ref 10CFR2.790(b))
ML17324A7201986-03-14014 March 1986
Forwards Proprietary Responses to NRC 860108 Questions 6,8 & 10 Re XN-NF-85-64(P) & Rev 1 to XN-NF-85-64(P), Plant Transient Analysis for DC Cook Unit 2 W/10% Steam Generator Tube.... Encls Withheld (Ref 10CFR2.790(b))
ML17324A6721986-03-0505 March 1986
Forwards Proprietary Responses to NRC Questions 1-4,7 & 11 Re XN-NF-85-64(P), Plant Transient...Steam Generator Tube Plugging. Addl Responses Expected by 860314.Proprietary XN-NF-84-69 Also Encl.Encls Withheld (Ref 10CFR2.790)
ML17324A7511986-02-20020 February 1986
Requests That Proprietary WCAP-11080, DC Cook Unit 2 Rdf Resistance Temp Detector Installation Safety Evaluation, Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl
ML17321A9561985-11-15015 November 1985
Forwards Proprietary XN-NF-85-64(P), Plant Transient Analysis for DC Cook Unit 2 W/10% Steam Generator Tube Plugging. Rept Withheld (Ref 10CFR2.790(h))
ML17326B0081985-10-15015 October 1985
Forwards XN-NF-85-28, DC Cook Unit 2,Cycle 6 SAR & Proprietary Suppl 1 to XN-NF-85-28(P), DC Cook Unit 2, Cycle 6 Sar:Disposition of Srp.... Proprietary Suppl Withheld (Ref 10CFR2.790(b))
ML17326B0011985-10-0303 October 1985
Forwards Proprietary XN-NF-85-68(P), DC Cook Unit 2 Limiting Break Loca/Eccs Analysis,10% Steam Generator Tube Plugging & K(Z) Curve. Affidavit Encl.Rept Withheld (Ref 10CFR2.790)
ML17321A9001985-09-30030 September 1985
Notifies of Error in 10CFR50.46 LOCA Analyses Performed for Facilities.Input Error in TOODEE2 Code Used to Calculate Fuel Rod Heatup Resulted in Rod Decay Heat Power Too Low & Subsequent Underpredicted Cladding Temp.Part 21 Related
ML17321A7851985-08-0909 August 1985
Requests That Proprietary Safety Evaluation for Resistance Temp Detector Operability & Cross Calibr Be Withheld (Ref 10CFR2.790)
ML17321A7861985-08-0606 August 1985
Requests That Proprietary Safety Evaluation for Increased Rdf Resistance Temp Detector Uncertainty Installation Be Withheld (Ref 10CFR2.790)
ML20134P6651985-07-22022 July 1985
FOIA Request for Nonproprietary Version of Exxon Nuclear Co, Inc Rept XN-NF-739 Re Seismic Evaluation of Nuclear Fuel
ML17321A6711985-06-10010 June 1985
Forwards Proprietary Slides Entitled, Cycle 6 Safety Analysis Status Review, Presented at 850530 Meeting W/Nrc & Util.Rb Stout Affidavit Also Encl.Slides Withheld (Ref 10CFR2.790)
ML17321A5141985-04-0303 April 1985
Forwards Proprietary XN-NF-85-20(P), Mod of Exem/Pwr Flecht Based Reflood Quench & Heat Transfer Correlations for DC Cook Unit 2. Affidavit Encl.Rept Withheld (Ref 10CFR2.790)
ML17321A5191985-04-0303 April 1985
Forwards Proprietary Draft DC Cook Unit 2 Cycle 5 5% Steam Generator Tube Plugging Limiting Break LOCA-ECCS Analysis:K(Z) Curve. Rept Withheld
ML17321A4991985-03-21021 March 1985
Discusses 850315 Telcon Re Incorrect Expression for Multiplier on Heat Transfer Coefficient Used in TOODEE2, Which Affected LOCA-ECCS Analyses for Several Pwrs.Analyses Redone
ML17326B1311984-08-0707 August 1984
Forwards Nonproprietary Version of Rev 2 to XN-NF-84-21, DC Cook,Unit 2,Cycle 5,5% Steam Generator Tube Plugging Limiting Break Loca/Eccs Analysis, Per American Electric Power Svc Co Request
ML17326B1241984-07-27027 July 1984
Forwards Proprietary Rev 2 to XN-NF-84-21 (P), DC Cook Unit 2,Cycle 5 5% Steam Generator Tube Plugging Limiting Break Loca/Eccs Analysis, Per American Electric Power Svc Co Request.Rept Withheld (Ref 10CFR2.790)
ML17320B0671984-05-21021 May 1984
Forwards Nonproprietary Info Re Cycle 5 LOCA ECCS Analysis, Per 840507 Ltr & Proprietary Page 1 of Response 4, Inadvertently Omitted from Ref Ltr Submittal.Proprietary Info Withheld (Ref 10CFR2.790)
ML17320B0311984-05-0707 May 1984
Forwards Proprietary Addl Info Re DC Cook Unit 2 Cycle 5 LOCA ECCS Analysis,Per 840302 Ltr.Info Withheld (Ref 10CFR2.790)
ML20081C9821984-03-13013 March 1984
Forwards Nonproprietary Version of XN-NF-82-90(NP),Suppl 1, Potential Radiological Consequences of Incidents Involving High Exposure Fuel, Which Supports Application for Tech Spec Changes for Cycle 5 Reload
ML17334A5161984-03-0202 March 1984
Forwards Proprietary & Nonproprietary Info Supporting Application for Tech Spec Changes for Cycle 5 Reload. Proprietary Repts Withheld
ML17320A8441983-10-11011 October 1983
Forwards Affidavit AW-78-23 & RB Stout 831011 Affidavit Requesting Withholding XN-NF-739(P), Seismic Evaluation of Exxon Nuclear 17x17 Assemblies in Westinghouse Pwrs.
ML17320A6921983-09-16016 September 1983
Requests Expedited Review of Creep Collapse Criteria Presented in XN-NF-82-06(P) Qualification of Exxon Nuclear Fuel for Extended Burnup. to Support Cycle 5 Operation, Approval of Creep Collapse by 831231 Requested
ML17320A6751983-08-24024 August 1983
Authorizes Use of Encl Affidavit AW-78-23 Re Request for Withholding Proprietary Info Concerning Optimized Fuel Assemblies Transition Reload Review
ML17320A3581983-02-0303 February 1983
Requests Generic Review of PTS-PWR2 Plant Transient Simulator Code Be Reactivated,Due to Difficulty Encountered in DC Cook Unit 2 Cycle 4 Review
ML17320A2831983-01-0404 January 1983
Forwards Proprietary Responses to Issues Raised by NRC at 821202 Meeting W/American Electric Power Re Cycle 4 Operation.Affidavit Supporting Withholding from Public Disclosure Encl.Responses Withheld (Ref 10CFR2.790)
ML17320A2621982-12-20020 December 1982
Forwards Table 1 Providing Reactivity Parameters for Unit 2, Consistent W/Parameters Used in FSAR Issued in Jul 1982
ML20070C7631982-12-10010 December 1982
Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested
ML17320A2331982-12-0909 December 1982
Responds to Question Re Basis for Full ECCS Flow Used in LOCA-ECCS Analysis in XN-NF-82-35,Suppl 1,per 821208 Telcon
ML17334A4501982-11-24024 November 1982
Forwards Suppl 1 to XN-NF-82-35, DC Cook Unit 2 Cycle 4 Limiting Break LOCA-ECCS Analysis Using Exem/Pwr.
ML17319B6681982-11-24024 November 1982
Forwards DC Cook Unit 2 Potential Radiological Consequences of Incidents Involving High Exposure Fuel. Util Will Be Referencing Rept in Future Correspondence Re Cycle 4 Operation
ML17319B5731982-10-0808 October 1982
Forwards Proprietary Users Manual for PTSPWR2-FORTRAN Program for Simulation of PWR Plant Transients & Suppl 1 to Manual.Affidavit Supporting Proprietary Classification of Documents Encl.Manuals Withheld (Ref 10CFR2.790)
ML17319B5761982-10-0808 October 1982
Forwards Revision 1 to XN-NF-82-32(P), Plant Transient Analysis for DC Cook Unit 2 Reactor at 3,425 Mwt, Including DNB Analysis Method Changes to Support Cycle 4 Operation. Revision Withheld (Ref 10CFR2.790)
ML17319B5671982-09-29029 September 1982
Forwards Proprietary Suppl 1 to XN-NF-82-37(P), DC Cook Unit 2,Cycle 4 SAR,Thermal-Hydraulic Analysis, Providing Addl Analysis of steady-state Thermal Margins During Cycle 4 Operation.Rept Withheld (Ref 10CFR2.790)
ML17319B4091982-06-30030 June 1982
Forwards XN-NF-82-37, DC Cook Unit 2,Cycle 4 SAR, XN-NF-82-35, DC Cook Unit 2 LOCA ECCS Analysis Using Exem/ PWR Large Break Results, & XN-NF-82-32(P), Plant Transient Analysis... XN-NF-82-32(P) Withheld (Ref 10CFR2.790)
ML20038C0241981-10-29029 October 1981
Requests Withholding of Proprietary Version of Clasix Computer Program for Analysis of Reactor Plant Containment Response to Hydrogen Release & Deflagration, (Ref 10CFR2.790)
ML17331A8011981-07-23023 July 1981
Forwards Affidavit for Withholding Proprietary Facility Conceptual Design Description for Technical Support Ctr & Emergency Operations Facilities. Affidavit Corrects CAW-80-75 Submitted 800613
ML19340C1081980-11-0404 November 1980
Forwards Corrections to XN-NF-77-57,Suppl 1,Exxon Nuclear Power Distribution Control for Pwrs:Phase 2, June 1979. Revisions Do Not Change Intent of Related PDC-2 Procedure But Clarify Requirements
ML17317B5371979-09-11011 September 1979
Forwards Proprietary & Nonproprietary Versions of XN-NS-TP-009, Fuel Storage Racks Corrosion Program, Boral-Stainless Steel. Proprietary Version Withheld (Ref 10CFR2.790)
ML17317B3001979-06-26026 June 1979
Advises That Westdyn Computer Code Analysis of Benchmark Problems Will Be Completed by 790731
1990-06-20
[Table view] |
Text
l REGULATORY )FORMATION DISTRIBUTION SY M (R IDS)
~ a ACCESSIQN NBR: 87083i 0058 DOC. DATE: 87/08/25 NOTARIZED: YES DOCKET FACIL: 50-3i6 Donald C. Cook Nuclear Power Plant. Unit 2. Indiana 5 050003i6 AUTH. NAME AUTHOR AFFILIATION ADKISSQNp D.*. Advanced Nuclear Fuels Corp. (formerly Exxon Nuclear Co. p I RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
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AQVANCEDNUCLEAHFUELS CORPORATION 2101 HORN RAPIDS ROAD, PO BOX 130, RICHLAND, WA 993524130 FUEL ENGINEERING a (509) 375-8100 TELEX: 15-2878 TECHNICAL SERVICES August 25, 1987 DAA: 014:87 87083i0058 050003%6 870825'DR ADOCH P PDR Donald C. Cook Nuclear Plant No. 2 Docket No. 50-316 License No. DPR-74 TRANSMITTAL OF ANF-87-91(P), REV. 1, DC COOK 2 DEBRIS-RESISTANT LOWER TIE PLATE PRESSURE DROP TEST REPORT U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Dear Sir:
Subject:
Transmittal of Donald C. Cook Unit 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report Enclosed are ten copies each of the Advanced Nuclear Fuels Corporation (ANF) technical report ANF-87-91(P), Rev. 1, entitled "DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report," which supports operation of the D.C. Cook Unit 2 Nuclear Plant, At the request of American Electric Power Service Company (AEPSC), this report is being transmitted directly by ANF.
The document transmitted via this letter reflects changes and analysis of the lower tie plate used in the manufacture of the reload fuel designated XN-4 which will be loaded in the reactor in April 1988. The document shows analyses and tests performed on the debris-resistant tie plate design.
Results of the analyses show that the Cycle 7 reload fuel is compatible with the existing ANF fuel in the plant.
ANF considers information contained in the enclosed technical report to be proprietary. The Affidavit enclosed provides the necessary information to allow the withholding of the proprietary version from public disclosure as required by 10 CFR 2.790(b) ~
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)d AN AFFILIATEOF KRAFTWERK UNION Q~ KSVU
U.S. Nuclear Regulatory DAA:014:87 Commission August 25, 1987 If you have any questions regarding this transmittal, please contact Hr. James G. Feinstein of AEPSC at (614) 233-2040.
Yours very truly, D. A. Adkisson, Acting Hanager Reload Licensing DAA:llh Enclosures cc: Hr. H. P. Alexich (AEPSC)
Hr. T. Georgantis (AEPSC)
Hr. D. L. Wiggington (NRC) (w/Enclosures)
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AFFIDAVIT STATE OF WASHINGTON )
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COUNTY OF BENTON )
I, H. E. Williamson being duly sworn, hereby say and depose:
- l. I am Manager, Licensing and Safety Engineering, for Advanced Nuclear Fuels Corporation, ("ANF"), and as such I am authorized to execute this Affidavit.
- 2. I am familiar with ANF's detailed document control system and policies which govern the protection and control of information.
- 3. I am familiar with the document ANF-87-91(P), Revision 1, entitled "Donald C. Cook Unit 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report," referred to as "Document." Information contained in this Document has been classified by ANF as proprietary in accordance with the control system and policies established by ANF for the control and protection of information.
- 4. The Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by ANF and not made available to the public. Based on my experience, I am aware that other companies- regard information of the kind contained in the Document as
.pr'opriejyry .and confidential.
- 5. -The Document has been made available to the U.S. Nuclear Regulatory Commission in confidence, with the request that the information 4 t contained in the Document will not be disclosed or divulged.
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- 6. The Document contains information which is vital to a competitive advantage of ANF and would be helpful to competitors of ANF when competing with ANF.
- 7. The information contained in the Document is considered to be proprietary by ANF because it reveals certain distinguishing aspects of debris-resistant lower tie plate which secure competitive advantage to ANF for fuel design optimization and marketability, and includes information utilized by ANF in its business which affords ANF an opportunity to obtain a competitive advantage over its competitors who do not or may not know or use the information contained in the Document,
- 8. The disclosure of the proprietary information contained in the Document to a competitor would permit the competitor to reduce its expenditure of money and manpower and to, improve its competitive position by giving it extremely valuable insights into debris-resistant lower tie plate and would result in substantial harm to the competitive position of ANF.
- 9. The Document contains proprietary information which is held in confidence by ANF and is not available in public sources.
- 10. In accordance with ANF's policies governing the protection and control of information, proprietary information contained in the Document has been made available, on a limited basis, to others outside ANF only as required and under suitable agreement providing for nondisclosure and limited use of the information.
ll. ANF policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 12. This Document provides information which reveals the debris-resistant lower tie plate developed by ANF over the past several years. ANF has invested many thousands of dollars and many man-months of effort in developing the debris-resistant lower tie plate revealed in the Document.
Assuming a competitor had available the same background data and incentives as ANF, the competitor might, at a minimum, develop the information for the same expenditure of manpower and money as ANF.
THAT the statements made hereinabove are, to the best of my knowledge, information, and belief, truthful and complete.
FURTHER AFFIANT SAYETH NOT.
SWORN TO AND SUBSCRIBED before me this 8~~day of 1987.
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ADVANCEDNUCLEARFUELS CORPORATION 2101 HORN RAPIDS ROAD, PO BOX 130, RICHlAND. WA 993524130 FUEL ENGINEERING 8 I509I 375 8100 TELEX: 15.2878 TECHNICAL SERVICES August 25, 1987 DAA: 014: 87 Donald C. Cook Nuclear Plant No. 2 Docket No. 50-316 License No. DPR-74 TRANSMITTAL OF ANF-87-91(P),,REV. 1, DC COOK 2 DEBRIS-RESISTANT LOWER TIE PLATE PRESSURE DROP TEST REPORT U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Dear Sir:
Subject:
Transmittal of Donald C. Cook Unit 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report Enclosed are ten copies each of the Advanced Nuclear Fuels Corporation (ANF) technical report ANF-87-91(P), Rev. 1, entitled "DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report," which supports operation of the D.C. Cook Unit 2 Nuclear Plant. At the request of American Electric Power Service Company (AEPSC), this report is being transmitted directly by ANF.
The document transmitted via this letter reflects changes and analysis of the lower tie plate used in the manufacture of the reload fuel designated XN-4 which will be loaded in the reactor in April 1988. The document shows analyses and tests performed on the debris-resistant tie plate design.
Results of the analyses show that the Cycle 7 reload fuel is compatible with the existing ANF fuel in the plant.
ANF considers information contained in the enclosed technical report to be proprietary. The Affidavit enclosed provides the necessary information to allow the withholding of the proprietary version from public disclosure as required by 10 CFR 2.790(b).
AN AfflLIAIEOf KRAf11VERK VNIOhl Qw KitU
U.S. Nuclear Regulatory DAA:014:87 Commission August 25, 1987 If you have any questions regarding this transmittal, please contact Mr. James G. Feinstein of AEPSC at (614) 233-2040.
Yours very truly, D. A. Adkisson, Acting Manager Reload Licensing DAA:llh Enclosures cc: Mr. M. P. Alexich (AEPSC)
Mr. T. Georgantis (AEPSC)
Mr. D. L. Wiggington (NRC) (w/Enclosures)
