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| {{#Wiki_filter:k'H.j.MML'. | | {{#Wiki_filter:k'H.j.MML'. |
| 'Y(ACCELERATED BIDSPROCESSIREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9407150239 DOC.DATE: | | 'Y (ACCELERATED BIDS P ROCESSI REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9407150239 DOC.DATE: 94/07/11 NOTARIZED: |
| 94/07/11NOTARIZED: | | NO DOCKET FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2 Niagara Moha 05000410 AUTH.NAME AUTHOR AFFILIATION MCCORMICK,M. |
| NODOCKETFACIL:50-410 NineMilePointNuclearStation,Unit2NiagaraMoha05000410AUTH.NAMEAUTHORAFFILIATION MCCORMICK,M.
| | Niagara Mohawk Power Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| NiagaraMohawkPowerCorp.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards"NineMilePointUnit2EALsRevBasedonNUMARCNESP-007." | | Forwards"Nine Mile Point Unit 2 EALs Rev Based on NUMARC NESP-007." Upgrade project involved listed plants.DISTRIBUTION CODE: AO45D COPIES RECEIUED: LTR 2 ENCL/SIZE:&400 TITLE: OR Submittal: |
| Upgradeprojectinvolvedlistedplants.DISTRIBUTION CODE:AO45DCOPIESRECEIUED:
| | Emergency Preparedness Plans, Implement'g Proce ures, C NOTES:License Exp date in accordance with 10CFR2,2.109(12/22/72). |
| LTR2ENCL/SIZE:&400TITLE:ORSubmittal:
| | 05000237 License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| Emergency Preparedness Plans,Implement'g Proceures,CNOTES:License Expdateinaccordance with10CFR2,2.109(12/22/72). | | 05000244 RECIPIENT ID CODE/NAME PD1-1 PD PD1-3 PD BRINKMAN, D.STANG,J JOHNSON.,A INTERNAL: AEOD/DOA/IRB NUDOCS-ABSTRACT EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RE PIENT CO NAME BRINKMAN,D MENNING,J CONICELLA,N. |
| 05000237LicenseExpdateinaccordance with10CFR2,2.109(9/19/72).
| | NRI~RSSg PEPB REG~~LE)01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 g Qu/@ex NOTE TO ALL"RIDS'ECIPIENTS: |
| 05000244RECIPIENT IDCODE/NAME PD1-1PDPD1-3PDBRINKMAN, D.STANG,JJOHNSON.,A INTERNAL:
| | PLEASE HELP US TO REDUCE XYASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXI: 504-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 |
| AEOD/DOA/IRB NUDOCS-ABSTRACT EXTERNAL: | |
| NRCPDRCOPIESLTTRENCL1111111111111111REPIENTCONAMEBRINKMAN,D MENNING,J CONICELLA,N.
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| NRI~RSSgPEPBREG~~LE)01NSICCOPIESLTTRENCL11111111111111gQu/@exNOTETOALL"RIDS'ECIPIENTS: | |
| PLEASEHELPUSTOREDUCEXYASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXI:504-2083)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDITOTALNUMBEROFCOPIESREQUIRED:
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| LTTR15ENCL15
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| tTNIAGARAUMOHAWKONEAS1LEPONTNUCLEARTRANNGCENTERIRD01,BOX1481OSWEGO
| | t T NIAGARA U MOHAWK ONE AS1LE PONT NUCLEAR TRANNG CENTER I RD 01, BOX 1481OSWEGO |
| ~NEWYORK13126/TELEPHONE (315)349-2080UnitedStatesNuclearRegulatory Commission DocumentControlDeskWashington, DC20555NineMilePointNudearPowerStationUnit2DocketNo,50-410LicenseNo.NPF-69July11,1994NMP2L1482 | | ~NEW YORK 13126/TELEPHONE (315)349-2080 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Nine Mile Point Nudear Power Station Unit 2 Docket No, 50-410 License No.NPF-69 July 11, 1994 NMP2L 1482 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NineMilePointUnit2Emergency ActionLevelsRevisionBasedonNUMARCNESP-007Inaccordance withtheguidanceprovidedbytheNRCstaffatrecentNEImeetings, NiagaraMohawkissubmitting forreviewandapprovaltheenclosedEmergency ActionLevels(EALs)forNineMilePointNudearStationUnit2.NiagaraMohawk,inaccordance with10CFR50,54 (q),hasreviewedtheseEALsanddetermined thattheyrepresent anenhancement totheNineMlePointEmergency Plan,TheEALshavebeenrevisedconsistent withtheNUMARCNESP407methodology, andweredeveloped aspartofajointprojectwithallnudearutilities withinNewYorkState.Inordertoassistyourreviewwehaveincludedanumberofdevelopmental documents intheendosedEALGeneration Package.TheEALGeneration Packageconsistsofthefollowing:
| | Nine Mile Point Unit 2 Emergency Action Levels Revision Based on NUMARC NESP-007 In accordance with the guidance provided by the NRC staff at recent NEI meetings, Niagara Mohawk is submitting for review and approval the enclosed Emergency Action Levels (EALs)for Nine Mile Point Nudear Station Unit 2.Niagara Mohawk, in accordance with 10CFR50,54 (q), has reviewed these EALs and determined that they represent an enhancement to the Nine Mle Point Emergency Plan, The EALs have been revised consistent with the NUMARC NESP407 methodology, and were developed as part of a joint project with all nudear utilities within New York State.In order to assist your review we have included a number of developmental documents in the endosed EAL Generation Package.The EAL Generation Package consists of the following: |
| ~Plant-Specific EALGuideline | | ~Plant-Specific EAL Guideline~EAL Technical Bases~Fission Product Barrier Evaluation |
| ~EALTechnical Bases~FissionProductBarrierEvaluation | | ~Emergency Action Level Matrix~EAL Binning Document~Validation and Verification Report Attachment 1 provides an explanation of the contents of the EAL Generation Package.These EALs were developed as a joint project with the New York Power Authority, Consolidated Edison, Rochester Gas and Electric, and Niagara Mohawk.This process ensures consistent emergency classification between all New York State nuclear utilities to the greatest extent possible, limited only by plant design differences. |
| ~Emergency ActionLevelMatrix~EALBinningDocument~Validation andVerification ReportAttachment 1providesanexplanation ofthecontentsoftheEALGeneration Package.TheseEALsweredeveloped asajointprojectwiththeNewYorkPowerAuthority, Consolidated Edison,Rochester GasandElectric, andNiagaraMohawk.Thisprocessensuresconsistent emergency classification betweenallNewYorkStatenuclearutilities tothegreatestextentpossible, limitedonlybyplantdesigndifferences. | | We believe that a coordinated review of all the New York State nuclear utility EAL revisions will promote this consistency and will result in the most advantageous use of time and resources. |
| Webelievethatacoordinated reviewofalltheNewYorkStatenuclearutilityEALrevisions willpromotethisconsistency andwillresultinthemostadvantageous useoftimeandresources.
| | Please contact Ms.Coleen Ware, Director of Emergency Preparedness, at 349-2066 should you have any questions or require additional information regarding this matter.Very truly yours, c MJM/JDJ/bh M.McCormick, Jr.Vice President-Nudear Safety Assessment and Support CC: Mr.B.S.Norris, Senior Resident Inspector Mr.M.L.Boyle, Acting Director, Project Directorate I-1, NRR Mr.D.S.Brinkman, Sr.Project Manager, NRR Mr.T.T.Martin, Regional Administrator, Region 1 9407 250239 9407>>1 PDR ADOCK 05000410 P P'DP pgyg (() |
| PleasecontactMs.ColeenWare,DirectorofEmergency Preparedness, at349-2066shouldyouhaveanyquestions orrequireadditional information regarding thismatter.Verytrulyyours,cMJM/JDJ/bh M.McCormick, Jr.VicePresident-Nudear SafetyAssessment andSupportCC:Mr.B.S.Norris,SeniorResidentInspector Mr.M.L.Boyle,ActingDirector, ProjectDirectorate I-1,NRRMr.D.S.Brinkman, Sr.ProjectManager,NRRMr.T.T.Martin,RegionalAdministrator, Region194072502399407>>1PDRADOCK05000410PP'DPpgyg(()
| | ATTACHMENT 1 NINE MILE POINT NUCLEAR STATION UNIT 2 EAL GENERATION PACKAGE CONTENT |
| ATTACHMENT 1NINEMILEPOINTNUCLEARSTATIONUNIT2EALGENERATION PACKAGECONTENTSUMMARYINTRODUCTION Priortotheacceptance bytheNRCofNUMARC/NESP-007 "Methodology forDevelopment ofEmergency ActionLevels"asanacceptable alternative totheNUREG0654EALguidance, thefournuclearutilities intheStateofNewYorkdecidedtoperformajointimplementation ofthenewmethodology. | | |
| Thisupgradeprojectinvolvedthefollowing plants:NineMilePointUnit1(NMP1)-NiagaraMohawkPowerCorporation NineMilePointUnit2(NMP2)-NiagaraMohawkPowerCorporation JamesA.FitzPatrick NuclearPowerPlant-NewYorkPowerAuthority IndianPointStation2-Consolidated EdisonIndianPoint3NuclearPowerStation-NewYorkPowerAuthority R.E.GinnaNuclearPowerStation-Rochester GasandElectricWhiletheresulting upgradedEALsaresitespecific, anobjective oftheupgradeprojectwastoensureconformity andconsistency betweenthesitestotheextentpossible.
| | ==SUMMARY== |
| Thefollowing paragraphs describethesitespecificEALdevelopmental documents whichareincludedintheEALreviewpackage.~~1ThePEGistheNMP2Interpretation oftheNUMARCmethodology fordeveloping EALs.ThePEGidentifies deletions fromtheNUMARCmethodology bystrikingoutwordsandphrasesthatarenotapplicable, additions areidentified byunderlining newwordsandphrases.Thedocuments whichprovidethebasisforthesechangesfromNUMARCmethodology arelistedinthereferences sectionofthePEG.inPB'rvliTheFPBEcontainstheevaluation oftheNUMARCexampleEALsforeachofthethreefissionproductbarriers.
| | INTRODUCTION Prior to the acceptance by the NRC of NUMARC/NESP-007"Methodology for Development of Emergency Action Levels" as an acceptable alternative to the NUREG 0654 EAL guidance, the four nuclear utilities in the State of New York decided to perform a joint implementation of the new methodology. |
| Theresultofthisevaluation isadiscretesetofquantifiable EALswhichrepresent theNUMARCfissionproductbarrierlossmatrices.
| | This upgrade project involved the following plants: Nine Mile Point Unit 1 (NMP1)-Niagara Mohawk Power Corporation Nine Mile Point Unit 2 (NMP2)-Niagara Mohawk Power Corporation James A.FitzPatrick Nuclear Power Plant-New York Power Authority Indian Point Station 2-Consolidated Edison Indian Point 3 Nuclear Power Station-New York Power Authority R.E.Ginna Nuclear Power Station-Rochester Gas and Electric While the resulting upgraded EALs are site specific, an objective of the upgrade project was to ensure conformity and consistency between the sites to the extent possible.The following paragraphs describe the site specific EAL developmental documents which are included in the EAL review package.~~1 The PEG is the NMP2 Interpretation of the NUMARC methodology for developing EALs.The PEG identifies deletions from the NUMARC methodology by striking out words and phrases that are not applicable, additions are identified by underlining new words and phrases.The documents which provide the basis for these changes from NUMARC methodology are listed in the references section of the PEG.i nP B'r vl i The FPBE contains the evaluation of the NUMARC example EALs for each of the three fission product barriers.The result of this evaluation is a discrete set of quantifiable EALs which represent the NUMARC fission product barrier loss matrices. |
| ,~ | | ,~ |
| BasedonthenumberoexampleEALs,andthenumberoossandpotential lossconditions, thesetofconditions thatcanyieldagivenemergency classification canbedetermined.
| | Based on the number o example EALs, and the number o oss and potential loss conditions, the set of conditions that can yield a given emergency classification can be determined. |
| Anevaluation ofeachcondition orsetofconditions wasmadetodetermine ifitproperlydefinestheappropriate threshold forthedassification.
| | An evaluation of each condition or set of conditions was made to determine if it properly defines the appropriate threshold for the dassification. |
| Ifacondition orsetofconditions wasappropriate, acommentreflecting thisconclusion wasrecordedinthisdocument, Ifacondition orsetofconditions isdetermined tobeinappropriate, itislinedoutandthereasonforthisconclusion issimilarly recorded.
| | If a condition or set of conditions was appropriate, a comment reflecting this conclusion was recorded in this document, If a condition or set of conditions is determined to be inappropriate, it is lined out and the reason for this conclusion is similarly recorded.P2E LB Since the format presented in NUMARC/NESP-007 is inadequate for implementation; the EALs.defined-by-the.PEG-and FPBE-must be binned into categories and subcategories which support ease of use.The binning document identifies where each PEG/FPBE Initiating Conditions (IC)is addressed within the presentation scheme, NMP2 EAL Technical Bases Document The EAL Technical Bases Document provides an explanation and rationale for each of the emergency action level (EALs)included in the EAL Upgrade Program.It is also intended to facilitate the review process of the NMP2 EALs and provide historical documentation for future reference. |
| P2ELBSincetheformatpresented inNUMARC/NESP-007 isinadequate forimplementation; theEALs.defined-by-the.PEG-and FPBE-must bebinnedintocategories andsubcategories whichsupporteaseofuse.Thebinningdocumentidentifies whereeachPEG/FPBEInitiating Conditions (IC)isaddressed withinthepresentation scheme,NMP2EALTechnical BasesDocumentTheEALTechnical BasesDocumentprovidesanexplanation andrationale foreachoftheemergency actionlevel(EALs)includedintheEALUpgradeProgram.Itisalsointendedtofacilitate thereviewprocessoftheNMP2EALsandprovidehistorical documentation forfuturereference.
| | This document is also intended to be used by those individuals responsible for implementation of the NMP2 dassification procedure as a technical reference and aid in EAL interpretation. |
| Thisdocumentisalsointendedtobeusedbythoseindividuals responsible forimplementation oftheNMP2dassification procedure asatechnical reference andaidinEALinterpretation.
| | NMP2 Emer en A ion Level Matrix The Emergency Action Level Matrix is the user level result of the EAL development project.This matrix will be incorporated in the Emergency Plan Implementing Procedures and is used directly by operations personnel to classify an event.P2V r'li i The NMP2 Verification and Validabon Report documents the process conducted to verify and to validate the site specific EALs and supporting documentation, This document also includes the comments received during validation along with comment resolutions. |
| NMP2EmerenAionLevelMatrixTheEmergency ActionLevelMatrixistheuserlevelresultoftheEALdevelopment project.Thismatrixwillbeincorporated intheEmergency PlanImplementing Procedures andisuseddirectlybyoperations personnel toclassifyanevent.P2Vr'liiTheNMP2Verification andValidabon Reportdocuments theprocessconducted toverifyandtovalidatethesitespecificEALsandsupporting documentation, Thisdocumentalsoincludesthecommentsreceivedduringvalidation alongwithcommentresolutions.
| | The verification process was performed to ensure the NMP2 EALs and classification procedures are technically correct.The NMP2 EAL verification was conducted prior to the EAL validation exercises. |
| Theverification processwasperformed toensuretheNMP2EALsandclassification procedures aretechnically correct.TheNMP2EALverification wasconducted priortotheEALvalidation exercises.
| | The technical accuracy of the upgraded EALs were verified through tabletop reviews. |
| Thetechnical accuracyoftheupgradedEALswereverifiedthroughtabletopreviews.
| | , 0 The validation process sures that the NMP2 EALs and c assification procedures are usable and correct, and ensures that emergency response personnel are able to arrive at consistent interpretations of EALs under similar conditions. |
| ,0 Thevalidation processsuresthattheNMP2EALsandcassification procedures areusableandcorrect,andensuresthatemergency responsepersonnel areabletoarriveatconsistent interpretations ofEALsundersimilarconditions. | | The EALs were validated through observation of emergency response organization personnel responding to simulated emergency events.The group of EALs selected for validation were sufficiently representative of all the EALs. |
| TheEALswerevalidated throughobservation ofemergency responseorganization personnel responding tosimulated emergency events.ThegroupofEALsselectedforvalidation weresufficiently representative ofalltheEALs.
| | OSSI 93-402A-10-NMP2 Docket f,'~-'ft~Accession 8 a z uz>Date~Of Lti'eguiatol I Do;l:.-t Filo ew or a e mer enc c ion eve ra e roec Nine Mile Point 1&2 Niagara Mohawk Power Corporation Nine Mile Point Unit 2 Generation Package Operations Support Services, Inc.233 Water Street 2nd Floor Plymouth, MA 02360 1t$r I ggqf't'ii w I$4+l+Pl II ,'.~ch I l'U~~~r}} |
| OSSI93-402A-10-NMP2 Docketf,'~-'ft~
| |
| Accession 8azuz>Date~OfLti'eguiatol IDo;l:.-tFiloeworaemerenccioneveraeroecNineMilePoint1&2NiagaraMohawkPowerCorporation NineMilePointUnit2Generation PackageOperations SupportServices, Inc.233WaterStreet2ndFloorPlymouth, MA02360 1t$rIggqf't'iiwI$4+l+PlII,'.~chIl'U~~~r}} | |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999
Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies
ML20217G1291999-10-15015 October 1999
Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend
ML20217K2831999-10-14014 October 1999
Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001
ML20217H3211999-10-0808 October 1999
Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls
ML20212K8601999-10-0606 October 1999
Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2
ML20216J9311999-09-30030 September 1999
Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
ML20212J4651999-09-30030 September 1999
Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl
ML18040A3701999-09-30030 September 1999
Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs
ML20212K8641999-09-30030 September 1999
Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam
ML20212J8831999-09-30030 September 1999
Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant
ML20212E9801999-09-23023 September 1999
Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03
ML20216F7101999-09-17017 September 1999
Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed
ML20212B2821999-09-14014 September 1999
Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable
ML20212D8981999-09-14014 September 1999
Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl
ML20212B2581999-09-10010 September 1999
Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List
ML20211P5771999-09-10010 September 1999
Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld
ML20212A1341999-09-0707 September 1999
Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f
ML20211K8141999-09-0101 September 1999
Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met
ML20211L9221999-09-0101 September 1999
Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC
ML20211J6461999-08-30030 August 1999
Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity
ML20211K3001999-08-30030 August 1999
Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1
ML20211K5031999-08-30030 August 1999
Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999
ML20211H1921999-08-26026 August 1999
Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML20211P5161999-08-26026 August 1999
Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied
ML20211G4921999-08-26026 August 1999
Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to
ML20211D7731999-08-20020 August 1999
Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630
ML20211B9371999-08-18018 August 1999
Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based
ML18040A3691999-08-16016 August 1999
Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys.
ML20210Q0031999-08-11011 August 1999
Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr
ML20210R6661999-08-10010 August 1999
Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2
ML20210R8101999-08-10010 August 1999
Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b)
ML20210L5321999-08-0606 August 1999
Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue
ML18041A0711999-07-30030 July 1999
Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed
ML20210J9351999-07-29029 July 1999
Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage
ML20216E1491999-07-26026 July 1999
Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206
ML20210E9151999-07-23023 July 1999
Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied
ML20209G7911999-07-12012 July 1999
Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions
ML20209G3711999-07-12012 July 1999
Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1
ML20209G2001999-07-0909 July 1999
Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01)
ML20209F8561999-07-0606 July 1999
Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4
ML20211K5071999-07-0606 July 1999
Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857
ML20196J6421999-06-30030 June 1999
Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110
ML20209B7071999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl
ML20211P5271999-06-29029 June 1999
Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted
ML20196K6461999-06-29029 June 1999
Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV
ML20209B3501999-06-25025 June 1999
Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs
ML20212J4431999-06-25025 June 1999
Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity
ML20209B3531999-06-25025 June 1999
Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment
ML20196F5721999-06-23023 June 1999
Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl
ML20196G1461999-06-23023 June 1999
Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed
1999-09-07
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999
Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001
ML20217H3211999-10-0808 October 1999
Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls
ML18040A3701999-09-30030 September 1999
Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs
ML20216J9311999-09-30030 September 1999
Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
ML20212E9801999-09-23023 September 1999
Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03
ML20216F7101999-09-17017 September 1999
Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed
ML20212D8981999-09-14014 September 1999
Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl
ML20212B2581999-09-10010 September 1999
Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List
ML20211P5771999-09-10010 September 1999
Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld
ML20212A1341999-09-0707 September 1999
Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f
ML20211K8141999-09-0101 September 1999
Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met
ML20211L9221999-09-0101 September 1999
Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC
ML20211K3001999-08-30030 August 1999
Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1
ML20211J6461999-08-30030 August 1999
Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity
ML20211H1921999-08-26026 August 1999
Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML20211D7731999-08-20020 August 1999
Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630
ML20211B9371999-08-18018 August 1999
Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based
ML18040A3691999-08-16016 August 1999
Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys.
ML20210R6661999-08-10010 August 1999
Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2
ML20210R8101999-08-10010 August 1999
Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b)
ML18041A0711999-07-30030 July 1999
Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed
ML20210J9351999-07-29029 July 1999
Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage
ML20209G3711999-07-12012 July 1999
Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1
ML20209G7911999-07-12012 July 1999
Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions
ML20209G2001999-07-0909 July 1999
Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01)
ML20209F8561999-07-0606 July 1999
Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4
ML20211K5071999-07-0606 July 1999
Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857
ML20209B7071999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl
ML20211P5271999-06-29029 June 1999
Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted
ML20209B3501999-06-25025 June 1999
Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs
ML20209B3531999-06-25025 June 1999
Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment
ML20196G1461999-06-23023 June 1999
Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed
ML20196F5721999-06-23023 June 1999
Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl
ML20209B2951999-06-22022 June 1999
Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226
ML20196E9231999-06-21021 June 1999
Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor
ML18040A3651999-06-0707 June 1999
Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission
ML18040A3661999-06-0404 June 1999
Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr
ML20195C9751999-06-0101 June 1999
Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods
ML20195C9601999-05-28028 May 1999
Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr
ML20207F1811999-05-24024 May 1999
Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns
ML20195B1861999-05-21021 May 1999
Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl
ML20207D1541999-05-21021 May 1999
Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld
ML20207D5331999-05-21021 May 1999
Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790
ML20206S2621999-05-16016 May 1999
Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date
ML20195D5911999-05-13013 May 1999
Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411
ML20206P1981999-05-11011 May 1999
Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2
ML20206R6941999-05-10010 May 1999
Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate
ML20206N0291999-05-0707 May 1999
Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28
ML20206G8121999-04-30030 April 1999
Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083
ML20206F7731999-04-22022 April 1999
Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2
1999-09-07
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'Y (ACCELERATED BIDS P ROCESSI REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9407150239 DOC.DATE: 94/07/11 NOTARIZED:
NO DOCKET FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2 Niagara Moha 05000410 AUTH.NAME AUTHOR AFFILIATION MCCORMICK,M.
Niagara Mohawk Power Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards"Nine Mile Point Unit 2 EALs Rev Based on NUMARC NESP-007." Upgrade project involved listed plants.DISTRIBUTION CODE: AO45D COPIES RECEIUED: LTR 2 ENCL/SIZE:&400 TITLE: OR Submittal:
Emergency Preparedness Plans, Implement'g Proce ures, C NOTES:License Exp date in accordance with 10CFR2,2.109(12/22/72).
05000237 License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-1 PD PD1-3 PD BRINKMAN, D.STANG,J JOHNSON.,A INTERNAL: AEOD/DOA/IRB NUDOCS-ABSTRACT EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RE PIENT CO NAME BRINKMAN,D MENNING,J CONICELLA,N.
NRI~RSSg PEPB REG~~LE)01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 g Qu/@ex NOTE TO ALL"RIDS'ECIPIENTS:
PLEASE HELP US TO REDUCE XYASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXI: 504-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15
t T NIAGARA U MOHAWK ONE AS1LE PONT NUCLEAR TRANNG CENTER I RD 01, BOX 1481OSWEGO
~NEW YORK 13126/TELEPHONE (315)349-2080 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Nine Mile Point Nudear Power Station Unit 2 Docket No, 50-410 License No.NPF-69 July 11, 1994 NMP2L 1482
SUBJECT:
Nine Mile Point Unit 2 Emergency Action Levels Revision Based on NUMARC NESP-007 In accordance with the guidance provided by the NRC staff at recent NEI meetings, Niagara Mohawk is submitting for review and approval the enclosed Emergency Action Levels (EALs)for Nine Mile Point Nudear Station Unit 2.Niagara Mohawk, in accordance with 10CFR50,54 (q), has reviewed these EALs and determined that they represent an enhancement to the Nine Mle Point Emergency Plan, The EALs have been revised consistent with the NUMARC NESP407 methodology, and were developed as part of a joint project with all nudear utilities within New York State.In order to assist your review we have included a number of developmental documents in the endosed EAL Generation Package.The EAL Generation Package consists of the following:
~Plant-Specific EAL Guideline~EAL Technical Bases~Fission Product Barrier Evaluation
~Emergency Action Level Matrix~EAL Binning Document~Validation and Verification Report Attachment 1 provides an explanation of the contents of the EAL Generation Package.These EALs were developed as a joint project with the New York Power Authority, Consolidated Edison, Rochester Gas and Electric, and Niagara Mohawk.This process ensures consistent emergency classification between all New York State nuclear utilities to the greatest extent possible, limited only by plant design differences.
We believe that a coordinated review of all the New York State nuclear utility EAL revisions will promote this consistency and will result in the most advantageous use of time and resources.
Please contact Ms.Coleen Ware, Director of Emergency Preparedness, at 349-2066 should you have any questions or require additional information regarding this matter.Very truly yours, c MJM/JDJ/bh M.McCormick, Jr.Vice President-Nudear Safety Assessment and Support CC: Mr.B.S.Norris, Senior Resident Inspector Mr.M.L.Boyle, Acting Director, Project Directorate I-1, NRR Mr.D.S.Brinkman, Sr.Project Manager, NRR Mr.T.T.Martin, Regional Administrator, Region 1 9407 250239 9407>>1 PDR ADOCK 05000410 P P'DP pgyg (()
ATTACHMENT 1 NINE MILE POINT NUCLEAR STATION UNIT 2 EAL GENERATION PACKAGE CONTENT
SUMMARY
INTRODUCTION Prior to the acceptance by the NRC of NUMARC/NESP-007"Methodology for Development of Emergency Action Levels" as an acceptable alternative to the NUREG 0654 EAL guidance, the four nuclear utilities in the State of New York decided to perform a joint implementation of the new methodology.
This upgrade project involved the following plants: Nine Mile Point Unit 1 (NMP1)-Niagara Mohawk Power Corporation Nine Mile Point Unit 2 (NMP2)-Niagara Mohawk Power Corporation James A.FitzPatrick Nuclear Power Plant-New York Power Authority Indian Point Station 2-Consolidated Edison Indian Point 3 Nuclear Power Station-New York Power Authority R.E.Ginna Nuclear Power Station-Rochester Gas and Electric While the resulting upgraded EALs are site specific, an objective of the upgrade project was to ensure conformity and consistency between the sites to the extent possible.The following paragraphs describe the site specific EAL developmental documents which are included in the EAL review package.~~1 The PEG is the NMP2 Interpretation of the NUMARC methodology for developing EALs.The PEG identifies deletions from the NUMARC methodology by striking out words and phrases that are not applicable, additions are identified by underlining new words and phrases.The documents which provide the basis for these changes from NUMARC methodology are listed in the references section of the PEG.i nP B'r vl i The FPBE contains the evaluation of the NUMARC example EALs for each of the three fission product barriers.The result of this evaluation is a discrete set of quantifiable EALs which represent the NUMARC fission product barrier loss matrices.
,~
Based on the number o example EALs, and the number o oss and potential loss conditions, the set of conditions that can yield a given emergency classification can be determined.
An evaluation of each condition or set of conditions was made to determine if it properly defines the appropriate threshold for the dassification.
If a condition or set of conditions was appropriate, a comment reflecting this conclusion was recorded in this document, If a condition or set of conditions is determined to be inappropriate, it is lined out and the reason for this conclusion is similarly recorded.P2E LB Since the format presented in NUMARC/NESP-007 is inadequate for implementation; the EALs.defined-by-the.PEG-and FPBE-must be binned into categories and subcategories which support ease of use.The binning document identifies where each PEG/FPBE Initiating Conditions (IC)is addressed within the presentation scheme, NMP2 EAL Technical Bases Document The EAL Technical Bases Document provides an explanation and rationale for each of the emergency action level (EALs)included in the EAL Upgrade Program.It is also intended to facilitate the review process of the NMP2 EALs and provide historical documentation for future reference.
This document is also intended to be used by those individuals responsible for implementation of the NMP2 dassification procedure as a technical reference and aid in EAL interpretation.
NMP2 Emer en A ion Level Matrix The Emergency Action Level Matrix is the user level result of the EAL development project.This matrix will be incorporated in the Emergency Plan Implementing Procedures and is used directly by operations personnel to classify an event.P2V r'li i The NMP2 Verification and Validabon Report documents the process conducted to verify and to validate the site specific EALs and supporting documentation, This document also includes the comments received during validation along with comment resolutions.
The verification process was performed to ensure the NMP2 EALs and classification procedures are technically correct.The NMP2 EAL verification was conducted prior to the EAL validation exercises.
The technical accuracy of the upgraded EALs were verified through tabletop reviews.
, 0 The validation process sures that the NMP2 EALs and c assification procedures are usable and correct, and ensures that emergency response personnel are able to arrive at consistent interpretations of EALs under similar conditions.
The EALs were validated through observation of emergency response organization personnel responding to simulated emergency events.The group of EALs selected for validation were sufficiently representative of all the EALs.
OSSI 93-402A-10-NMP2 Docket f,'~-'ft~Accession 8 a z uz>Date~Of Lti'eguiatol I Do;l:.-t Filo ew or a e mer enc c ion eve ra e roec Nine Mile Point 1&2 Niagara Mohawk Power Corporation Nine Mile Point Unit 2 Generation Package Operations Support Services, Inc.233 Water Street 2nd Floor Plymouth, MA 02360 1t$r I ggqf't'ii w I$4+l+Pl II ,'.~ch I l'U~~~r
