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| +TEN(RIBS)ACCESSION NBR:7903140460 DOC~DATE:79/03/09NOTARIZED'O DOCKETFACIL:50"244 ROBERTEMMETGINNANUCLEARPLANTEUNIT1eROCHESTER G05000?44AUTH.NAMEAUTHORAFFILIATION NHITEELeD~ROCHESTER GAS8ELECTRICCORP'ECIP~NAMERECIPIENT AFFILIATION ZIEMANNE0~L~OPERATING REACTORSBRANCH2 | | +TEN (RIBS)ACCESSION NBR:7903140460 DOC~DATE: 79/03/09 NOTARIZED'O DOCKET FACIL:50"244 ROBERT EMMET GINNA NUCLEAR PLANTE UNIT 1 e ROCHESTER G 05000?44 AUTH.NAME AUTHOR AFFILIATION NHITEE L e D~ROCHESTER GAS 8 ELECTRIC CORP'EC IP~NAME RECIPIENT AFFILIATION ZIEMANNE 0~L~OPERATING REACTORS BRANCH 2 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| RESPONDSTO790208REQUEST&FORNAROSADDLINFOREREVISIONTOSUPPL4OFFULL-TERM LICENSEAPPLICATION
| | RESPONDS TO 790208 REQUEST&FORNAROS ADDL INFO RE REVISION TO SUPPL 4 OF FULL-TERM LICENSE APPLICATION |
| ~DISTRIBUTION CODE:ASSISCOPIESRECEIVED:LTR | | ~DISTRIBUTION CODE: ASSIS COPIES RECEIVED:LTR |
| $ENCLjSIZE:~TITLE:GENERALDISTRIBUTION FORAFTERISSUANCEOFOPERATING LIC+~i5o+NOTES:3f'MA+~8.CZ"RECIPIENT IDCODE/NAME ACTION:05BCINTERNAL: | | $ENCL j SIZE:~TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC+~i 5o+NOTES: 3 f'MA+~8.CZ" RECIPIENT ID CODE/NAME ACTION: 05 BC INTERNAL: REG 1 LE 15 CORE PERF BR 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS EXTERNAL: 03 LPDR 23 ACRS COPIES ENCL 7 7 1 1 2'1 1 1 1 1 1 1 1 1 16 16 RECIPIENT ID CODE/NAME 02 NRC PDR 14 TA/EDO 16 AD SYS/PROJ 18 REAC SFTY BR 20 EEB 22 BR INKMAN 04 NSIC COPIES LTTR ENCL TOTAI NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38 ee f I Htf f Hd I".arch 9, 1979 tlr.Dennis L.Ziemann, Chief Operating Reactors Branch 52 Division of Operating Reactors U.S.Nuclear Regulatory Commission |
| REG1LE15COREPERFBR17ENGRBR19PLANTSYSBR21EFLTTRTSYSEXTERNAL:
| | <iashington, D.C.20555 |
| 03LPDR23ACRSCOPIESENCL77112'1111111111616RECIPIENT IDCODE/NAME 02NRCPDR14TA/EDO16ADSYS/PROJ18REACSFTYBR20EEB22BRINKMAN04NSICCOPIESLTTRENCLTOTAINUMBEROFCOPIESREQUIRED:
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| LTTR38ENCL38 eefIHtffHd I".arch9,1979tlr.DennisL.Ziemann,ChiefOperating ReactorsBranch52DivisionofOperating ReactorsU.S.NuclearRegulatory Commission
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| <iashington, D.C.20555 | |
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| ==Deariver.Ziemann:== | | ==Dear iver.Ziemann:== |
| Enclosed, asrequested, is'copyoftheadditional information regarding Revision4toSupplement XVoftheFull-Term LicenseApplication fortheR.E.GinnaNuclearPowerPlantrequested byyourletterofFebruary8,1979.Asindicated intheenclosure, supplement ZVwillbefurtherrevisedinthenearfuturetoreflectinformation submitted withthisletter.Sincerely, ma4)lrf~,LeonD.K?hit,Jr.CRA:dmaOEnclosure | | Enclosed, as requested, is'copy of the additional information regarding Revision 4 to Supplement XV of the Full-Term License Application for the R.E.Ginna Nuclear Power Plant requested by your letter of February 8, 1979.As indicated in the enclosure, supplement ZV will be further revised in the near future to reflect information submitted with this letter.Sincerely, ma 4)lrf~, Leon D.K?hit , Jr.CRA:dmaO Enclosure |
| ~~( | | ~~( |
| Enclosure RESPONSETOREUESTFORADDITIONAL INFORMATION GINNANUCLEARPOWERPLANTNRCComment1OneofthepurposesofRevision4ofSupplement IVtotheTechnical Supplement Accompanying Application foraFull-Term Operating Licenseistoendorsethe"currentNRCRegulatory Guidesassociated withqualityassurance ANSIStandards." | | Enclosure RESPONSE TO RE UEST FOR ADDITIONAL INFORMATION GINNA NUCLEAR POWER PLANT NRC Comment 1 One of the purposes of Revision 4 of Supplement IV to the Technical Supplement Accompanying Application for a Full-Term Operating License is to endorse the"current NRC Regulatory Guides associated with quality assurance ANSI Standards." The list of guides beginning on page IV-3 of Revision 4 should be revised as noted below to accomplish this purpose.Document Revision Shown Revision Should Be.Regulatory Regulatory Regulatory Regulatory Regulatory Pegulatory Regulatory Regulatory Regulatory Reaulatory Regulatory.Regulatory ANSI N45.2.Guide Guide Guide Guide Guide Guide Guide Guide Guide Guide Guide Guide 12 1.30 1.33 1.37 1.38 1.39 1.58 1.64 1.74 1.88 1.94 1.116 1.123 None None None None'None None None None None (Not Listed)None None None Rev.0 Rev.2 Rev.0 Rev.2 Rev.2 Rev.0 Rev.2 Rev.0 Rev.2 Rev.1 Rev.0-R Rev.1 D3, R4, 2/74 RGGE Clarification 1 It was not intended, as inferred in the statement of purposes, to provide an endorsement of all the"current NFC Regulatory Guides associated with quality assurance ANSI Standards." Since the endorsement of a portion of the listing was intended, clarification will be made in the statement of stated purposes through deletion of the term"current". |
| Thelistofguidesbeginning onpageIV-3ofRevision4shouldberevisedasnotedbelowtoaccomplish thispurpose.DocumentRevisionShownRevisionShouldBe.Regulatory Regulatory Regulatory Regulatory Regulatory Pegulatory Regulatory Regulatory Regulatory Reaulatory Regulatory
| | In addition, consistent with your current practice pages IV-3 and IV-4 are being revised to reflect the revision levels of the NRC Regulatory Guides and ANSI Standards to which the program conforms.NRC Comment 2 Fevision 4 deleted the position of Quality Assurance Enaineer, QA Program.Please show who has the responsi-bility formerly assigned to tnis position.RGGE Clarification 2 This position never did evolve into a full time posi-tion as originally perceived. |
| .Regulatory ANSIN45.2.GuideGuideGuideGuideGuideGuideGuideGuideGuideGuideGuideGuide121.301.331.371.381.391.581.641.741.881.941.1161.123NoneNoneNoneNone'NoneNoneNoneNoneNone(NotListed)NoneNoneNoneRev.0Rev.2Rev.0Rev.2Rev.2Rev.0Rev.2Rev.0Rev.2Rev.1Rev.0-RRev.1D3,R4,2/74RGGEClarification 1Itwasnotintended, asinferredinthestatement ofpurposes, toprovideanendorsement ofallthe"currentNFCRegulatory Guidesassociated withqualityassurance ANSIStandards." | | The duties, primarily admin-istrative in nature, are assigned on a rotational basis to QA Group non key staff personnel. |
| Sincetheendorsement ofaportionofthelistingwasintended, clarification willbemadeinthestatement ofstatedpurposesthroughdeletionoftheterm"current".
| | This part time function has been retitled within the QA Group procedures as gA Group Administrator with duties performed internittently to en-sure schedules, reports and revised procedures are issued when necessary. |
| Inaddition, consistent withyourcurrentpracticepagesIV-3andIV-4arebeingrevisedtoreflecttherevisionlevelsoftheNRCRegulatory GuidesandANSIStandards towhichtheprogramconforms.
| | Group training, a duty formerly assigned to the deleted position, is assumed by the Manager, Quality Assurance. |
| NRCComment2Fevision4deletedthepositionofQualityAssurance
| | The description of the Quality Assurance Manager on page IV-6 will be revised to provide this clarification. |
| : Enaineer, QAProgram.Pleaseshowwhohastheresponsi-bilityformerlyassignedtotnisposition.
| | NRC Comment 3 Revision 4 deleted the responsibilities of the Super-intendent, General Maintenance to train personnel who support his activities and for administrative direction of nondestructive examination personnel. |
| RGGEClarification 2Thispositionneverdidevolveintoafulltimeposi-tionasoriginally perceived.
| | Please show who has these responsibilities. |
| Theduties,primarily admin-istrative innature,areassignedonarotational basistoQAGroupnonkeystaffpersonnel.
| | RGSE Clarification 3 Training of General Maintenance personnel for Ginna Station Support activities is coordinated by the General Maintenance Quality Control Coordinator as described on page IV-8 and by the Welding and NDE Engineer as described on page IV-6.Page IV-2 also describes training respon-sibilities for which each department is responsible. |
| ThisparttimefunctionhasbeenretitledwithintheQAGroupprocedures asgAGroupAdministrator withdutiesperformed internittently toen-sureschedules, reportsandrevisedprocedures areissuedwhennecessary.
| | Although the administrative direction for nondestructive examination |
| Grouptraining, adutyformerlyassignedtothedeletedposition, isassumedbytheManager,QualityAssurance.
| | 'personnel has not changed, this alignment to General Maintenance is under review.Realignment, if and when it occurs, would involve the consolidation of admin-istrative and functional responsibility under the Welding and Nondestructive Examination Engineer.The description of responsibilities will be revised to further clarify that functional guidance and direction is also provided, when necessary, during the conduct of examinations for those methods for which the Nelding and Nondestructive Engineer is a aualified Level III.In addition, the responsibilities of the General Maintenance Quality Control Coordinator described on page IV-S, include coordinating the performance of veri-fication activities |
| Thedescription oftheQualityAssurance ManageronpageIV-6willberevisedtoprovidethisclarification.
| | {nondestructive examination included)for General Maintenance activities. |
| NRCComment3Revision4deletedtheresponsibilities oftheSuper-intendent, GeneralMaintenance totrainpersonnel whosupporthisactivities andforadministrative direction ofnondestructive examination personnel.
| | The clarified descrip-tions and related organization charts is considered detail sufficient to"provide organization charts and functional responsibility descriptions that denote the line of respon-sibility and areas of authority within each of the major organizations in a project." NRC Comment 4 The third paragraph on page IV-l0 of Revision 4 has added"Significant" in front of"errors and deficiencies". |
| Pleaseshowwhohastheseresponsibilities.
| | Describe the controls which assure that errors and defi-ciencies which are not significant are corrected. |
| RGSEClarification 3TrainingofGeneralMaintenance personnel forGinnaStationSupportactivities iscoordinated bytheGeneralMaintenance QualityControlCoordinator asdescribed onpageIV-8andbytheWeldingandNDEEngineerasdescribed onpageIV-6.PageIV-2alsodescribes trainingrespon-sibilities forwhicheachdepartment isresponsible.
| | ~4~RG&E Clarification 4 A field change system and design verification are the routine methods utilized to correct non significant errors and deficiencies. |
| Althoughtheadministrative direction fornondestructive examination
| | Page IV-9 describes control of design changes, including field changes in addition to design verification. |
| 'personnel hasnotchanged,thisalignment toGeneralMaintenance isunderreview.Realignment, ifandwhenitoccurs,wouldinvolvetheconsolidation ofadmin-istrative andfunctional responsibility undertheWeldingandNondestructive Examination Engineer. | | Clarification of the methods for correcting the non significant errors and deficiencies will be pro-vided in revised page IV-10.NRC Comment 5 Revision 4 does not indicate that the Manager, Quality Assurance reviews and approves deviations from quality standards as was indicated in Revision 3.Please show who has these responsibilities. |
| Thedescription ofresponsibilities willberevisedtofurtherclarifythatfunctional guidanceanddirection isalsoprovided, whennecessary, duringtheconductofexaminations forthosemethodsforwhichtheNeldingandNondestructive Engineerisaaualified LevelIII.Inaddition, theresponsibilities oftheGeneralMaintenance QualityControlCoordinator described onpageIV-S,includecoordinating theperformance ofveri-ficationactivities
| | RG&E Clarification 5 The Manager of Quality Assurance retains the respon-sibility for review and approving deviations from quality standards. |
| {nondestructive examination included) forGeneralMaintenance activities. | | The deletion from Revision 4 was inadvertent and will be rectified in revised'age IV-10.NRC Comment 6 The changes to Table IV-1 need justification or elimination as they appear to down grade the quality assurance program.RG&E Clarification 6 The changes to Table IV-1 were not intended to down grade the program.The intent was to regroup the items in the format, groupings of ANSI N45.2.13 which was not avail-able when the initial Table IV-1 listing was prepared.In the process of reformation a few of the significant items were inadvertently omitted and are being incorporated into a revised Table.The cross reference of incorporation of previous Table items into the new Table format is as follows.Table IV 4-1 Rev.3 4 5 6 7 8 9 10 11 12 13 14 Table IV 4-1 Rev.5 1 2 deleted as stated but covered by 2 2 2 2 2 3 4 4 4, 5, 6 2 6 Table IV 4-1 Rev.3 15 Table IV 4-1 Rev.5 deleted as this is redundant with the other factors of N45.2.13 NRC Comment 7 The last paragraph on page IV-12 of Revision 4 assigns some responsibilities to Engineering for major modification. |
| Theclarified descrip-tionsandrelatedorganization chartsisconsidered detailsufficient to"provideorganization chartsandfunctional responsibility descriptions thatdenotethelineofrespon-sibilityandareasofauthority withineachofthemajororganizations inaproject."
| | Please indicate the assignment of these responsibilities for minor modifications. |
| NRCComment4Thethirdparagraph onpageIV-l0ofRevision4hasadded"Significant" infrontof"errorsanddeficiencies".
| | Also, the same paragraph no longer contains the commitment that"installation requirements" will be provided for modification. |
| Describethecontrolswhichassurethaterrorsanddefi-ciencieswhicharenotsignificant arecorrected.
| | Please justify or eliminate this change.RGGE Clarification 7 Page IV-12 is being revised to clarify to what extent Engineering is responsible for providing drawings and specifications for minor modifications. |
| ~4~RG&EClarification 4Afieldchangesystemanddesignverification aretheroutinemethodsutilizedtocorrectnonsignificant errorsanddeficiencies. | | Engineering in-stallation requirements are not issued separately but are provided in drawings and specifications. |
| PageIV-9describes controlofdesignchanges,including fieldchangesinadditiontodesignverification.
| | The sentence con-cerning"installation requirements" is describing the types of documents distributed by Engineering and the deletion was to clarify the inconsistent, grammar.Page IV-12 provides a description of typical departmental responsibilities associated with the types of documents being.provided and activities for which they are typically used.NRC Comment 8 The last paragraph on page IV-13 and the third para-graph on page IV-20, of Revision 4 no longer require Quality Control review of operating procedures as was required in Revision 3.RG&E Clarification 8 Operating procedures, unlike maintenance, repair, modification and refueling procedures, do not involve quality assurance requirements and therefore are of little interest to departmental quality representatives. |
| Clarification ofthemethodsforcorrecting thenonsignificant errorsanddeficiencies willbepro-videdinrevisedpageIV-10.NRCComment5Revision4doesnotindicatethattheManager,QualityAssurance reviewsandapprovesdeviations fromqualitystandards aswasindicated inRevision3.Pleaseshowwhohastheseresponsibilities. | | Examples of Quality Assurance requirements characteristic of the other procedures include calibrated tools, inspection and test requirements, witness points, quantitative and qualitative acceptance criteria etc.Operating procedures typically just provide"how to" instructions and precautions to the station operating personnel for system line up and operation. |
| RG&EClarification 5TheManagerofQualityAssurance retainstherespon-sibilityforreviewandapproving deviations fromqualitystandards. | | As described in the same paragraph of page IV-13, the Plant Operations Review Committee to which the Station Quality Control Engineer is now a member has review respon-sibility for all Ginna Station procedures which include the operating procedures. |
| ThedeletionfromRevision4wasinadvertent andwillberectified inrevised'age IV-10.NRCComment6ThechangestoTableIV-1needjustification orelimination astheyappeartodowngradethequalityassurance program.RG&EClarification 6ThechangestoTableIV-1werenotintendedtodowngradetheprogram.Theintentwastoregrouptheitemsintheformat,groupings ofANSIN45.2.13whichwasnotavail-ablewhentheinitialTableIV-1listingwasprepared.
| | NRC Comment 9 The second paragraph of IV-7 except suppliers of stand-ard off-the-shelf items from the commitment that suppliers must be on an approved suppliers list.Please indicate the controls for suppliers of standard off-the-shelf items.RGKE Clarification 9 Addition of a supplier to the qualified suppliers list is based on satisfactory evaluation of the suppliers capa-bility by Quality Assurance, Purchasing and/or other depart-ments responsible for the procurement of safety related items as described in IV.7.Procurement planning involves determining to what extent the acceptance of off-the-shelf items is to be based upon source inspection, certificate of conformance, receipt inspection and post installation test.For off-the-shelf items, procured from suppliers required to have a quality assurance program and for which item acceptance is based on other than receipt inspection, the supplier must be on an approved suppliers list or in the process of being added to the list.Other off-the-shelf items, that are manufactured to industry standards, are typically utilized in applications other than nuclear and for which item acceptance is based exclusively on receipt inspection may be purchased from sources other than the approved suppliers list.With the exception of the supplier selection method, the controls for all procurements are identical with regard to planning;preparation, review, approval and processing of documents; and item receipt and acceptance. |
| Intheprocessofreformation afewofthesignificant itemswereinadvertently omittedandarebeingincorporated intoarevisedTable.Thecrossreference ofincorporation ofpreviousTableitemsintothenewTableformatisasfollows.TableIV4-1Rev.34567891011121314TableIV4-1Rev.512deletedasstatedbutcoveredby222223444,5,626 TableIV4-1Rev.315TableIV4-1Rev.5deletedasthisisredundant withtheotherfactorsofN45.2.13NRCComment7Thelastparagraph onpageIV-12ofRevision4assignssomeresponsibilities toEngineering formajormodification.
| | Sections IV.4 and IV.7 will be reviewed and revised to reflect the above cl'arification. |
| Pleaseindicatetheassignment oftheseresponsibilities forminormodifications.
| | NRC Comment 10 Please explain the significance of adding"verification" to modify"inspections" in the first two paragraphs of IV-10 of Revision 4.RG&E Clarification 10 The modifier is to clarify the applicability of inspec-tion controls to the quality assurance function inspections as distinguished from preventative maintenance inspections performed by plant maintenance personnel. |
| Also,thesameparagraph nolongercontainsthecommitment that"installation requirements" willbeprovidedformodification. | | Page IV-10 is being revised to provide this clarification. |
| Pleasejustifyoreliminate thischange.RGGEClarification 7PageIV-12isbeingrevisedtoclarifytowhatextentEngineering isresponsible forproviding drawingsandspecifications forminormodifications.
| | NRC Comment 11 Revision 4 does not indicate that Engineering is respon-sible for including inspection requirements in specification as was indicated in Revision 3.Please show who now has that responsibility. |
| Engineering in-stallation requirements arenotissuedseparately butareprovidedindrawingsandspecifications. | | RGGE Clarification 11 Quality Assurance is responsible for the inclusion of inspection requirements in specifications. |
| Thesentencecon-cerning"installation requirements" isdescribing thetypesofdocuments distributed byEngineering andthedeletionwastoclarifytheinconsistent, grammar.PageIV-12providesadescription oftypicaldepartmental responsibilities associated withthetypesofdocuments being.providedandactivities forwhichtheyaretypically used.NRCComment8Thelastparagraph onpageIV-13andthethirdpara-graphonpageIV-20,ofRevision4nolongerrequireQualityControlreviewofoperating procedures aswasrequiredinRevision3.RG&EClarification 8Operating procedures, unlikemaintenance, repair,modification andrefueling procedures, donotinvolvequalityassurance requirements andtherefore areoflittleinteresttodepartmental qualityrepresentatives.
| | Page IV-20 is being revised to clarify this responsibility. |
| ExamplesofQualityAssurance requirements characteristic oftheotherprocedures includecalibrated tools,inspection andtestrequirements, witnesspoints,quantitative andqualitative acceptance criteriaetc.Operating procedures typically justprovide"howto"instructions andprecautions tothestationoperating personnel forsystemlineupandoperation.
| | NRC Comment 12 Please explain the significance of the changes made to the last paragraph of IV-11.RG&E Clarification 12 Quality Assurance now assists Engineering in assuring required tests for modifications are included in specifi-cations.Najor modification clarifies scope for which Engineering and Quality Assurance share responsibility for design test requirements. |
| Asdescribed inthesameparagraph ofpageIV-13,thePlantOperations ReviewCommittee towhichtheStationQualityControlEngineerisnowamemberhasreviewrespon-sibilityforallGinnaStationprocedures whichincludetheoperating procedures.
| | The change in Engineering assistance for test procedure preparation is to clarify that Engineering assistance is not always necessary and especially for minor modification for which they have minimal involvement. |
| NRCComment9Thesecondparagraph ofIV-7exceptsuppliers ofstand-ardoff-the-shelf itemsfromthecommitment thatsuppliers mustbeonanapprovedsuppliers list.Pleaseindicatethecontrolsforsuppliers ofstandardoff-the-shelf items.RGKEClarification 9Additionofasuppliertothequalified suppliers listisbasedonsatisfactory evaluation ofthesuppliers capa-bilitybyQualityAssurance, Purchasing and/orotherdepart-mentsresponsible fortheprocurement ofsafetyrelateditemsasdescribed inIV.7.Procurement planninginvolvesdetermining towhatextenttheacceptance ofoff-the-shelf itemsistobebaseduponsourceinspection, certificate ofconformance, receiptinspection andpostinstallation test.Foroff-the-shelf items,procuredfromsuppliers requiredtohaveaqualityassurance programandforwhichitemacceptance isbasedonotherthanreceiptinspection, thesuppliermustbeonanapprovedsuppliers listorintheprocessofbeingaddedtothelist.Otheroff-the-shelf items,thataremanufactured toindustrystandards, aretypically utilizedinapplications otherthannuclearandforwhichitemacceptance isbasedexclusively onreceiptinspection maybepurchased fromsourcesotherthantheapprovedsuppliers list.Withtheexception ofthesupplierselection method,thecontrolsforallprocurements areidentical withregardtoplanning; preparation, review,approvalandprocessing ofdocuments; anditemreceiptandacceptance.
| | Section IV.11, Test Control, is being revised to provide clarification for test respon-sibility associated with minor modifications. |
| SectionsIV.4andIV.7willbereviewedandrevisedtoreflecttheabovecl'arification.
| | NRC Comment 13 The last paragraph of IV-14 in Revision 4, does not indicate that Quality Control establishes the procedures for implementing inspection status sheets during maintenance, repair, and modification as was indicated in Revision 3.Please show who now has that responsibility. |
| NRCComment10Pleaseexplainthesignificance ofadding"verification" tomodify"inspections" inthefirsttwoparagraphs ofIV-10ofRevision4.RG&EClarification 10Themodifieristoclarifytheapplicability ofinspec-tioncontrolstothequalityassurance functioninspections asdistinguished frompreventative maintenance inspections performed byplantmaintenance personnel.
| | RG&E Clarification 13 Since inspection status sheets are not utilized during maintenance, repair and modification, the need for a governing procedure is not necessary. |
| PageIV-10isbeingrevisedtoprovidethisclarification.
| | Inspection status sheets, as described in IV.14, indicates a separate form prepared and utilized by Quality Control to track the status of inspection activity (i.e.inservice inspection) which typically involves several inspections during an annual outage.Inspection status for maintenance, repair and modification activities is indicated on job travelers, data sheets, and procedure step sign off locations. |
| NRCComment11Revision4doesnotindicatethatEngineering isrespon-sibleforincluding inspection requirements inspecification aswasindicated inRevision3.Pleaseshowwhonowhasthatresponsibility.
| | This is not clear in the second to the last paragraph and page IV-24 will be revised to provide this clarification. |
| RGGEClarification 11QualityAssurance isresponsible fortheinclusion ofinspection requirements inspecifications.
| | NRC Comment 14 The third paragraph on page IV-26 of Revision 4 assigns some responsibilities for major design changes.Indicate the assignment of these responsibilities for minor design changes.RG&E Clarification 14 This paragraph is being clarified to reflect the review by the cognizant design organization (i.e.Engi-neering or Ginna Station as appropriate). |
| PageIV-20isbeingrevisedtoclarifythisresponsibility.
| | NRC Comment 15 The commitment in Revision 3 to audit each activity"at least annually" has been changed in Revision 4 to audit each activity"at the required frequency". |
| NRCComment12Pleaseexplainthesignificance ofthechangesmade tothelastparagraph ofIV-11.RG&EClarification 12QualityAssurance nowassistsEngineering inassuringrequiredtestsformodifications areincludedinspecifi-cations.Najormodification clarifies scopeforwhichEngineering andQualityAssurance shareresponsibility fordesigntestrequirements.
| | Revision 4 does not appear to be auditable in this respect.Please clarify. |
| ThechangeinEngineering assistance fortestprocedure preparation istoclarifythatEngineering assistance isnotalwaysnecessary andespecially forminormodification forwhichtheyhaveminimalinvolvement.
| | RG&E Clarification 15 Required audit frequencies, as defined in Technical Specifications 6.0, vary from six months to two years with the majority requiring an annual audit.A six month frequency is specified, for the activity associated with the results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.A two year frequency is specified for the Station Security Plan and implementing procedures.. |
| SectionIV.11,TestControl,isbeingrevisedtoprovideclarification fortestrespon-sibilityassociated withminormodifications.
| | Table IV 18-1 and the audit schedule include more than just the activities associated with 10CFR50 Appendix B activities which require an audit at least once per year.Page IV-28 is being revised to make reference to Technical Specifications 6.0.t1RC Comment 16 In Revision 4, Table IV 18-1,"Audit List," please justify these omissions or replace the items in the table.RG&E Clarification 16 With an exception of an inadvertent deletion from the General Haintenance listing, deletions from Revision 3 are to correct some inconsistencies in the listing of activities to be audited with activities for which a department has responsibility. |
| NRCComment13Thelastparagraph ofIV-14inRevision4,doesnotindicatethatQualityControlestablishes theprocedures forimplementing inspection statussheetsduringmaintenance, repair,andmodification aswasindicated inRevision3.Pleaseshowwhonowhasthatresponsibility.
| | The justification for the deletions are described as follows: sibility of this Organization. |
| RG&EClarification 13Sinceinspection statussheetsarenotutilizedduringmaintenance, repairandmodification, theneedforagoverning procedure isnotnecessary. | | It is listed in General Haintenance. |
| Inspection statussheets,asdescribed inIV.14,indicates aseparateformpreparedandutilizedbyQualityControltotrackthestatusofinspection activity(i.e.inservice inspection) whichtypically involvesseveralinspections duringanannualoutage.Inspection statusformaintenance, repairandmodification activities isindicated onjobtravelers, datasheets,andprocedure stepsignofflocations. | | Purchasin and General Haintenance |
| Thisisnotclearinthesecondtothelastparagraph andpageIV-24willberevisedtoprovidethisclarification.
| | -Deletion of records is to recognize that these departments have chosen to utilize Engineering and Ginna Station for the storage of the records.Auditors are instructed to include record submittals are part of the audit of the other activities. |
| NRCComment14Thethirdparagraph onpageIV-26ofRevision4assignssomeresponsibilities formajordesignchanges.Indicatetheassignment oftheseresponsibilities forminordesignchanges.RG&EClarification 14Thisparagraph isbeingclarified toreflectthereviewbythecognizant designorganization (i.e.Engi-neeringorGinnaStationasappropriate).
| | General Haintenance a.Fabrication Control was substituted for Inspection and Surveillance. |
| NRCComment15Thecommitment inRevision3toauditeachactivity"atleastannually" hasbeenchangedinRevision4toauditeachactivity"attherequiredfrequency".
| | Fabrication activities for Ginna Station have been minimal for the past couple of years.Inspection and Surveillance is primarily associated with shop fabrication and will be audited commensurate with fabrication control.b.Pandling, Storage and Shipping was inadvertently deleted and will be reinserted in Table IV.18-1.}} |
| Revision4doesnotappeartobeauditable inthisrespect.Pleaseclarify.
| |
| RG&EClarification 15Requiredauditfrequencies, asdefinedinTechnical Specifications 6.0,varyfromsixmonthstotwoyearswiththemajorityrequiring anannualaudit.Asixmonthfrequency isspecified, fortheactivityassociated withtheresultsofallactionstakentocorrectdeficiencies occurring infacilityequipment, structures, systemsormethodofoperation thataffectnuclearsafetyatleastoncepersixmonths.Atwoyearfrequency isspecified fortheStationSecurityPlanandimplementing procedures.. | |
| TableIV18-1andtheauditscheduleincludemorethanjusttheactivities associated with10CFR50AppendixBactivities whichrequireanauditatleastonceperyear.PageIV-28isbeingrevisedtomakereference toTechnical Specifications 6.0.t1RCComment16InRevision4,TableIV18-1,"AuditList,"pleasejustifytheseomissions orreplacetheitemsinthetable.RG&EClarification 16Withanexception ofaninadvertent deletionfromtheGeneralHaintenance listing,deletions fromRevision3aretocorrectsomeinconsistencies inthelistingofactivities tobeauditedwithactivities forwhichadepartment hasresponsibility.
| |
| Thejustification forthedeletions aredescribed asfollows:sibilityofthisOrganization.
| |
| ItislistedinGeneralHaintenance.
| |
| Purchasin andGeneralHaintenance | |
| -Deletionofrecordsistorecognize thatthesedepartments havechosentoutilizeEngineering andGinnaStationforthestorageoftherecords.Auditorsareinstructed toincluderecordsubmittals arepartoftheauditoftheotheractivities. | |
| GeneralHaintenance a.Fabrication Controlwassubstituted forInspection andSurveillance.
| |
| Fabrication activities forGinnaStationhavebeenminimalforthepastcoupleofyears.Inspection andSurveillance isprimarily associated withshopfabrication andwillbeauditedcommensurate withfabrication control.b.Pandling, StorageandShippingwasinadvertently deletedandwillbereinserted inTableIV.18-1.}} | |
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Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
IR 05000244/19990081999-10-14014 October 1999
Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
IR 05000244/19992011999-09-24024 September 1999
Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999
Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L4481990-09-18018 September 1990
Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21)
ML17309A4491990-09-13013 September 1990
Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld
ML17262A1331990-09-11011 September 1990
Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion
ML17261B1511990-08-29029 August 1990
Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively
ML17261B1481990-08-28028 August 1990
Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant
IR 05000244/19880261990-08-20020 August 1990
Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented
ML17261B1501990-08-20020 August 1990
Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented
ML17261B1371990-08-17017 August 1990
Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant.
ML17309A4481990-08-16016 August 1990
Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records
ML17261B1351990-08-15015 August 1990
Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function
ML17261B1361990-08-14014 August 1990
Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts
ML17261B1331990-08-13013 August 1990
Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002
ML17261B1261990-07-30030 July 1990
Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days
ML20055H9291990-07-23023 July 1990
Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21
ML17261B1091990-07-20020 July 1990
Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp
ML17309A4471990-07-17017 July 1990
Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b)
ML17261B0881990-07-13013 July 1990
Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability.
ML17261B0921990-07-11011 July 1990
Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723
ML20044B0481990-07-10010 July 1990
Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs
ML17309A4461990-07-0909 July 1990
Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions
ML17261B0931990-07-0909 July 1990
Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs
ML17261B0901990-07-0909 July 1990
Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion
ML17250B2151990-06-29029 June 1990
Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries
ML17261B0851990-06-28028 June 1990
Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21
ML17250B1991990-06-0808 June 1990
Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983
ML17250B1951990-06-0505 June 1990
Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept
ML17250B1851990-06-0101 June 1990
Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs
ML17261B0691990-06-0101 June 1990
Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear
ML17250B1811990-05-31031 May 1990
Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21)
ML17250B1801990-05-29029 May 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity
ML17250B1841990-05-29029 May 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined
ML17261B0961990-05-29029 May 1990
Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred
ML17250B1721990-05-18018 May 1990
Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage
ML20042G8931990-05-0808 May 1990
Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3
ML17261B0611990-04-26026 April 1990
Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements
ML17261B0591990-04-17017 April 1990
Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur
ML17261B0461990-04-12012 April 1990
Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys
ML17262A1431990-04-12012 April 1990
Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys
ML17250B1451990-04-0606 April 1990
Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed
ML17250B1441990-04-0505 April 1990
Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion
ML17261B0401990-03-30030 March 1990
Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501
ML17261B0321990-03-28028 March 1990
Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp
ML17261B0331990-03-28028 March 1990
Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date
ML17261B0231990-03-26026 March 1990
Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated
ML17261B0281990-03-23023 March 1990
Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods
ML17261B0221990-03-22022 March 1990
Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828
ML17261B0411990-03-20020 March 1990
Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4)
ML17261B0151990-03-19019 March 1990
Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses
ML17261B0101990-03-15015 March 1990
Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies
ML20012D2831990-03-14014 March 1990
Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl
1990-09-18
[Table view] |
Text
REGULATORNFORMAT ION DISTRIBUTION
+TEN (RIBS)ACCESSION NBR:7903140460 DOC~DATE: 79/03/09 NOTARIZED'O DOCKET FACIL:50"244 ROBERT EMMET GINNA NUCLEAR PLANTE UNIT 1 e ROCHESTER G 05000?44 AUTH.NAME AUTHOR AFFILIATION NHITEE L e D~ROCHESTER GAS 8 ELECTRIC CORP'EC IP~NAME RECIPIENT AFFILIATION ZIEMANNE 0~L~OPERATING REACTORS BRANCH 2
SUBJECT:
RESPONDS TO 790208 REQUEST&FORNAROS ADDL INFO RE REVISION TO SUPPL 4 OF FULL-TERM LICENSE APPLICATION
~DISTRIBUTION CODE: ASSIS COPIES RECEIVED:LTR
$ENCL j SIZE:~TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC+~i 5o+NOTES: 3 f'MA+~8.CZ" RECIPIENT ID CODE/NAME ACTION: 05 BC INTERNAL: REG 1 LE 15 CORE PERF BR 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS EXTERNAL: 03 LPDR 23 ACRS COPIES ENCL 7 7 1 1 2'1 1 1 1 1 1 1 1 1 16 16 RECIPIENT ID CODE/NAME 02 NRC PDR 14 TA/EDO 16 AD SYS/PROJ 18 REAC SFTY BR 20 EEB 22 BR INKMAN 04 NSIC COPIES LTTR ENCL TOTAI NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38 ee f I Htf f Hd I".arch 9, 1979 tlr.Dennis L.Ziemann, Chief Operating Reactors Branch 52 Division of Operating Reactors U.S.Nuclear Regulatory Commission
<iashington, D.C.20555
Dear iver.Ziemann:
Enclosed, as requested, is'copy of the additional information regarding Revision 4 to Supplement XV of the Full-Term License Application for the R.E.Ginna Nuclear Power Plant requested by your letter of February 8, 1979.As indicated in the enclosure, supplement ZV will be further revised in the near future to reflect information submitted with this letter.Sincerely, ma 4)lrf~, Leon D.K?hit , Jr.CRA:dmaO Enclosure
~~(
Enclosure RESPONSE TO RE UEST FOR ADDITIONAL INFORMATION GINNA NUCLEAR POWER PLANT NRC Comment 1 One of the purposes of Revision 4 of Supplement IV to the Technical Supplement Accompanying Application for a Full-Term Operating License is to endorse the"current NRC Regulatory Guides associated with quality assurance ANSI Standards." The list of guides beginning on page IV-3 of Revision 4 should be revised as noted below to accomplish this purpose.Document Revision Shown Revision Should Be.Regulatory Regulatory Regulatory Regulatory Regulatory Pegulatory Regulatory Regulatory Regulatory Reaulatory Regulatory.Regulatory ANSI N45.2.Guide Guide Guide Guide Guide Guide Guide Guide Guide Guide Guide Guide 12 1.30 1.33 1.37 1.38 1.39 1.58 1.64 1.74 1.88 1.94 1.116 1.123 None None None None'None None None None None (Not Listed)None None None Rev.0 Rev.2 Rev.0 Rev.2 Rev.2 Rev.0 Rev.2 Rev.0 Rev.2 Rev.1 Rev.0-R Rev.1 D3, R4, 2/74 RGGE Clarification 1 It was not intended, as inferred in the statement of purposes, to provide an endorsement of all the"current NFC Regulatory Guides associated with quality assurance ANSI Standards." Since the endorsement of a portion of the listing was intended, clarification will be made in the statement of stated purposes through deletion of the term"current".
In addition, consistent with your current practice pages IV-3 and IV-4 are being revised to reflect the revision levels of the NRC Regulatory Guides and ANSI Standards to which the program conforms.NRC Comment 2 Fevision 4 deleted the position of Quality Assurance Enaineer, QA Program.Please show who has the responsi-bility formerly assigned to tnis position.RGGE Clarification 2 This position never did evolve into a full time posi-tion as originally perceived.
The duties, primarily admin-istrative in nature, are assigned on a rotational basis to QA Group non key staff personnel.
This part time function has been retitled within the QA Group procedures as gA Group Administrator with duties performed internittently to en-sure schedules, reports and revised procedures are issued when necessary.
Group training, a duty formerly assigned to the deleted position, is assumed by the Manager, Quality Assurance.
The description of the Quality Assurance Manager on page IV-6 will be revised to provide this clarification.
NRC Comment 3 Revision 4 deleted the responsibilities of the Super-intendent, General Maintenance to train personnel who support his activities and for administrative direction of nondestructive examination personnel.
Please show who has these responsibilities.
RGSE Clarification 3 Training of General Maintenance personnel for Ginna Station Support activities is coordinated by the General Maintenance Quality Control Coordinator as described on page IV-8 and by the Welding and NDE Engineer as described on page IV-6.Page IV-2 also describes training respon-sibilities for which each department is responsible.
Although the administrative direction for nondestructive examination
'personnel has not changed, this alignment to General Maintenance is under review.Realignment, if and when it occurs, would involve the consolidation of admin-istrative and functional responsibility under the Welding and Nondestructive Examination Engineer.The description of responsibilities will be revised to further clarify that functional guidance and direction is also provided, when necessary, during the conduct of examinations for those methods for which the Nelding and Nondestructive Engineer is a aualified Level III.In addition, the responsibilities of the General Maintenance Quality Control Coordinator described on page IV-S, include coordinating the performance of veri-fication activities
{nondestructive examination included)for General Maintenance activities.
The clarified descrip-tions and related organization charts is considered detail sufficient to"provide organization charts and functional responsibility descriptions that denote the line of respon-sibility and areas of authority within each of the major organizations in a project." NRC Comment 4 The third paragraph on page IV-l0 of Revision 4 has added"Significant" in front of"errors and deficiencies".
Describe the controls which assure that errors and defi-ciencies which are not significant are corrected.
~4~RG&E Clarification 4 A field change system and design verification are the routine methods utilized to correct non significant errors and deficiencies.
Page IV-9 describes control of design changes, including field changes in addition to design verification.
Clarification of the methods for correcting the non significant errors and deficiencies will be pro-vided in revised page IV-10.NRC Comment 5 Revision 4 does not indicate that the Manager, Quality Assurance reviews and approves deviations from quality standards as was indicated in Revision 3.Please show who has these responsibilities.
RG&E Clarification 5 The Manager of Quality Assurance retains the respon-sibility for review and approving deviations from quality standards.
The deletion from Revision 4 was inadvertent and will be rectified in revised'age IV-10.NRC Comment 6 The changes to Table IV-1 need justification or elimination as they appear to down grade the quality assurance program.RG&E Clarification 6 The changes to Table IV-1 were not intended to down grade the program.The intent was to regroup the items in the format, groupings of ANSI N45.2.13 which was not avail-able when the initial Table IV-1 listing was prepared.In the process of reformation a few of the significant items were inadvertently omitted and are being incorporated into a revised Table.The cross reference of incorporation of previous Table items into the new Table format is as follows.Table IV 4-1 Rev.3 4 5 6 7 8 9 10 11 12 13 14 Table IV 4-1 Rev.5 1 2 deleted as stated but covered by 2 2 2 2 2 3 4 4 4, 5, 6 2 6 Table IV 4-1 Rev.3 15 Table IV 4-1 Rev.5 deleted as this is redundant with the other factors of N45.2.13 NRC Comment 7 The last paragraph on page IV-12 of Revision 4 assigns some responsibilities to Engineering for major modification.
Please indicate the assignment of these responsibilities for minor modifications.
Also, the same paragraph no longer contains the commitment that"installation requirements" will be provided for modification.
Please justify or eliminate this change.RGGE Clarification 7 Page IV-12 is being revised to clarify to what extent Engineering is responsible for providing drawings and specifications for minor modifications.
Engineering in-stallation requirements are not issued separately but are provided in drawings and specifications.
The sentence con-cerning"installation requirements" is describing the types of documents distributed by Engineering and the deletion was to clarify the inconsistent, grammar.Page IV-12 provides a description of typical departmental responsibilities associated with the types of documents being.provided and activities for which they are typically used.NRC Comment 8 The last paragraph on page IV-13 and the third para-graph on page IV-20, of Revision 4 no longer require Quality Control review of operating procedures as was required in Revision 3.RG&E Clarification 8 Operating procedures, unlike maintenance, repair, modification and refueling procedures, do not involve quality assurance requirements and therefore are of little interest to departmental quality representatives.
Examples of Quality Assurance requirements characteristic of the other procedures include calibrated tools, inspection and test requirements, witness points, quantitative and qualitative acceptance criteria etc.Operating procedures typically just provide"how to" instructions and precautions to the station operating personnel for system line up and operation.
As described in the same paragraph of page IV-13, the Plant Operations Review Committee to which the Station Quality Control Engineer is now a member has review respon-sibility for all Ginna Station procedures which include the operating procedures.
NRC Comment 9 The second paragraph of IV-7 except suppliers of stand-ard off-the-shelf items from the commitment that suppliers must be on an approved suppliers list.Please indicate the controls for suppliers of standard off-the-shelf items.RGKE Clarification 9 Addition of a supplier to the qualified suppliers list is based on satisfactory evaluation of the suppliers capa-bility by Quality Assurance, Purchasing and/or other depart-ments responsible for the procurement of safety related items as described in IV.7.Procurement planning involves determining to what extent the acceptance of off-the-shelf items is to be based upon source inspection, certificate of conformance, receipt inspection and post installation test.For off-the-shelf items, procured from suppliers required to have a quality assurance program and for which item acceptance is based on other than receipt inspection, the supplier must be on an approved suppliers list or in the process of being added to the list.Other off-the-shelf items, that are manufactured to industry standards, are typically utilized in applications other than nuclear and for which item acceptance is based exclusively on receipt inspection may be purchased from sources other than the approved suppliers list.With the exception of the supplier selection method, the controls for all procurements are identical with regard to planning;preparation, review, approval and processing of documents; and item receipt and acceptance.
Sections IV.4 and IV.7 will be reviewed and revised to reflect the above cl'arification.
NRC Comment 10 Please explain the significance of adding"verification" to modify"inspections" in the first two paragraphs of IV-10 of Revision 4.RG&E Clarification 10 The modifier is to clarify the applicability of inspec-tion controls to the quality assurance function inspections as distinguished from preventative maintenance inspections performed by plant maintenance personnel.
Page IV-10 is being revised to provide this clarification.
NRC Comment 11 Revision 4 does not indicate that Engineering is respon-sible for including inspection requirements in specification as was indicated in Revision 3.Please show who now has that responsibility.
RGGE Clarification 11 Quality Assurance is responsible for the inclusion of inspection requirements in specifications.
Page IV-20 is being revised to clarify this responsibility.
NRC Comment 12 Please explain the significance of the changes made to the last paragraph of IV-11.RG&E Clarification 12 Quality Assurance now assists Engineering in assuring required tests for modifications are included in specifi-cations.Najor modification clarifies scope for which Engineering and Quality Assurance share responsibility for design test requirements.
The change in Engineering assistance for test procedure preparation is to clarify that Engineering assistance is not always necessary and especially for minor modification for which they have minimal involvement.
Section IV.11, Test Control, is being revised to provide clarification for test respon-sibility associated with minor modifications.
NRC Comment 13 The last paragraph of IV-14 in Revision 4, does not indicate that Quality Control establishes the procedures for implementing inspection status sheets during maintenance, repair, and modification as was indicated in Revision 3.Please show who now has that responsibility.
RG&E Clarification 13 Since inspection status sheets are not utilized during maintenance, repair and modification, the need for a governing procedure is not necessary.
Inspection status sheets, as described in IV.14, indicates a separate form prepared and utilized by Quality Control to track the status of inspection activity (i.e.inservice inspection) which typically involves several inspections during an annual outage.Inspection status for maintenance, repair and modification activities is indicated on job travelers, data sheets, and procedure step sign off locations.
This is not clear in the second to the last paragraph and page IV-24 will be revised to provide this clarification.
NRC Comment 14 The third paragraph on page IV-26 of Revision 4 assigns some responsibilities for major design changes.Indicate the assignment of these responsibilities for minor design changes.RG&E Clarification 14 This paragraph is being clarified to reflect the review by the cognizant design organization (i.e.Engi-neering or Ginna Station as appropriate).
NRC Comment 15 The commitment in Revision 3 to audit each activity"at least annually" has been changed in Revision 4 to audit each activity"at the required frequency".
Revision 4 does not appear to be auditable in this respect.Please clarify.
RG&E Clarification 15 Required audit frequencies, as defined in Technical Specifications 6.0, vary from six months to two years with the majority requiring an annual audit.A six month frequency is specified, for the activity associated with the results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.A two year frequency is specified for the Station Security Plan and implementing procedures..
Table IV 18-1 and the audit schedule include more than just the activities associated with 10CFR50 Appendix B activities which require an audit at least once per year.Page IV-28 is being revised to make reference to Technical Specifications 6.0.t1RC Comment 16 In Revision 4, Table IV 18-1,"Audit List," please justify these omissions or replace the items in the table.RG&E Clarification 16 With an exception of an inadvertent deletion from the General Haintenance listing, deletions from Revision 3 are to correct some inconsistencies in the listing of activities to be audited with activities for which a department has responsibility.
The justification for the deletions are described as follows: sibility of this Organization.
It is listed in General Haintenance.
Purchasin and General Haintenance
-Deletion of records is to recognize that these departments have chosen to utilize Engineering and Ginna Station for the storage of the records.Auditors are instructed to include record submittals are part of the audit of the other activities.
General Haintenance a.Fabrication Control was substituted for Inspection and Surveillance.
Fabrication activities for Ginna Station have been minimal for the past couple of years.Inspection and Surveillance is primarily associated with shop fabrication and will be audited commensurate with fabrication control.b.Pandling, Storage and Shipping was inadvertently deleted and will be reinserted in Table IV.18-1.
