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| {{#Wiki_filter:~~~i43'k~ROCHESTER GASANDENCLOSURE | | {{#Wiki_filter:~~~i 43'k~ROCHESTER GAS AND ENCLOSURE'4.l*2 j~~llktf'LECTRIC CORPORATION |
| '4.l*2j~~llktf'LECTRICCORPORATION | | ~89 EAST AVENUE, ROCHESTER, N.Y.1484&0001 ROGER W.KOBER WCC PRC%OKNT CIXCTlOC O 5TEAM PROOUCTlON TCLKPHONC ABACA COOC%le 546.2700 Dr.Thomas E.Murley, Regional Administrator U.S.Nuclear Regulatory Commission Region I 631 Park Avenue I October.28, 1986 King of Prussia, Pennsylvania 19406 Subject: RG&E Response to Systematic Assessment of.Licensee Performance (SALP)Report No.50-244/85-99 |
| ~89EASTAVENUE,ROCHESTER, N.Y.1484&0001 ROGERW.KOBERWCCPRC%OKNTCIXCTlOCO5TEAMPROOUCTlON TCLKPHONC ABACACOOC%le546.2700Dr.ThomasE.Murley,RegionalAdministrator U.S.NuclearRegulatory Commission RegionI631ParkAvenueIOctober.28,1986KingofPrussia,Pennsylvania 19406Subject:RG&EResponsetoSystematic Assessment of.Licensee Performance (SALP)ReportNo.50-244/85-99 | |
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| ==DearDr.Murley:== | | ==Dear Dr.Murley:== |
| InresponsetoyourSeptember 18,1986letter.transmitting theSALP,Report 85-99andasaresultofourOctober7,1986meetinginRochester, weareproviding writtencomments.
| | In response to your September 18, 1986 letter.transmitting the SALP,Report 85-99 and as a result of our October 7, 1986 meeting in Rochester, we are providing written comments.In general, we agree with the report and appreciate the opportunity to discuss our performance over the SALP period with you.We note your assessment that our performance demonstrates a strong commitment to safe and efficient plant operations. |
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| Ingeneral,weagreewiththereportandappreciate theopportunity todiscussourperformance overtheSALPperiodwithyou.Wenoteyourassessment thatourperformance demonstrates astrongcommitment tosafeandefficient plantoperations.
| | Regarding strengthening.of our Quality Assurance Program, we have been accelerating completion of our initiatives. |
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| Regarding strengthening
| | These have been discussed with you and members of your staff and we will continue to keep you informed of,our progress.We believe the issue of"informality with regard to station activities" is more properly addressed as an issue of"control of activities."'!Two types of comments are provided.First, comments on the SALP-Board Observations regarding"an apparent attitude of informality at Ginna Station" are provided in Attachment A"RG&E Comments on Control of Activities." Second, specific comments on specific pages in'he report are included in Attachment B-"RG&E Comments on SALP Report 50-244/85-99." This discussion should provide you with assurance that the staff at RG&E is continuously striving for excellence in perform-ance.Ro r W.Kober Attachment |
| .ofourQualityAssurance Program,wehavebeenaccelerating completion ofourinitiatives. | | /Copies: Document Control Desk c'W fR pf I ll' |
| | 'RQfE Response to SAXP Report No.50-2li/85-99 Page ATTACHMENT A ATTACHMENT A t&o e so o o c 8 We believe the issue of"informal versus formal"" attitude to be one of<<control of activities." It is necessary to review some of the formal programs already in place or in progress which are designed to improve ouZ"control of activities." There are two modes that naturally apply when controlling activities. |
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| Thesehavebeendiscussed withyouandmembersofyourstaffandwewillcontinuetokeepyouinformedof,ourprogress.
| | A reactive mode, logically entered for events such as plant trips or emergency maintenance, and a pro-active mode for pre-planning of activities. |
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| Webelievetheissueof"informality withregardtostationactivities" ismoreproperlyaddressed asanissueof"controlofactivities."
| | Addressing the reactive mode, there are several formal processes.already in place," in which the plant staff is quite proficient, which demonstrate control of activities. |
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| '!Twotypesofcommentsareprovided. | | These processes include: o Post Trip Review (A-25.4)o Emergency Maintenance Procedures o Corrective Action System o Morning Priority Action Required (MOPAR)o Emergency Operating Procedures (EOPs)Recovery from plant trips is accomplished by the plant staff safely and effectively in a formal fashion.Emergency Maintenance is planned in a well thought out manner and is formally approved by the Plant Operations Review Committee (PORC).Our control of operationa events has improved.The upgraded EOP's coupled with the newly installed simulator has strengthened our response to off-normal ev'ents.However, we have identified additional areas to be evaluated which could improve our"control of activities." These are: o Root Cause Identification o Troubleshooting 1~The plant staff will review these areas and will implement those aspects which can improve our control of activities. |
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| First,commentsontheSALP-Board Observations regarding
| | In the pro-active mode, the following programs/processes are in place to control activities. |
| "anapparentattitudeofinformality atGinnaStation"areprovidedinAttachment A"RG&ECommentsonControlofActivities."
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| Second,specificcommentsonspecificpagesin'hereportareincludedinAttachment B-"RG&ECommentsonSALPReport50-244/85-99."
| | o PORC o QA/QC Sub-Committee o ALARA Committee o.MOPAR' |
| | t f'I 4 RGfE Response to 8ALP Report No.50-2ii/85-99 Page 2 ATTACHMENT A You are aware of these committees and have commented on them as strengths so no further elaboration is recpxired here.The following programs are being.developed and implemented: |
| | o Accreditation o Maintenance Procedure Upgrade (stressing acceptance criteria)o Maintenance Information System (MIS)o Objective Based Management Program (OBM)These programs will improve our control of activities at all levels within the plant.Several other areas will be evaluated by the plant staff to determine aspects.which can improve our control of activities. |
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| Thisdiscussion shouldprovideyouwithassurance thatthestaffatRG&Eiscontinuously strivingforexcellence inperform-ance.RorW.KoberAttachment
| | 0 0 0 0 Concurrent Activity Identification and Control Non QA Work Activity Control OBM Planning Conduct of Meetings In reviewing performance"at the plant, review of concurrent activities, can be improved with the objective of identifying and eliminating potential conflicts. |
| /Copies:DocumentControlDesk c'WfRpfIll'
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| 'RQfEResponsetoSAXPReportNo.50-2li/85-99 PageATTACHMENT AATTACHMENT At&oesoooc8Webelievetheissueof"informal versusformal""attitudetobeoneof<<controlofactivities."
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| Itisnecessary toreviewsomeoftheformalprogramsalreadyinplaceorinprogresswhicharedesignedtoimproveouZ"controlofactivities."
| | This concept has already been included in the MOPAR meetings and will continue to be stressed.This discussion should provide you with assurance that the staff at Ginna is continuously striving for excellence in perfonnance. |
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| Therearetwomodesthatnaturally applywhencontrolling activities.
| | Pa RG&E Response to SALP Report No.50-2ii/85-99 Page 1 ATTACHMENT B Attachment B Specific Comments RO&E Response to Systematic Assessment of License Performance (SALP)Report No.50-2ii/85-99 The following provides comments to specific pages for the purposes of clarification, updating information, and/or points of disagree-ment.Page 9, 2nd paragraph regarding 1985 Reactor'rips on Steam-.Generator Levels (S/G).This is provided, for clarification and updating of the situation. |
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| Areactivemode,logically enteredforeventssuchasplanttripsoremergency maintenance, andapro-active modeforpre-planning ofactivities.
| | After close operations supervision of the startup following the 1986 outage, we have concluded that the subject trips had a root cause of equipment failure.This is based on the following: |
| | 1.Z&C calibration of the Steam Dump Control System resulted in being able to operate in manual-auto during the startup with proper response obtained.2.The feedwater flow transmitters were checked and recalibrated with the lower output set exactly at 10 millianps. |
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| Addressing thereactivemode,thereareseveralformalprocesses
| | While still somewhat inaccurate at very.low power levels, their response was better than in previous'ears. |
| .alreadyinplace,"inwhichtheplantstaffisquiteproficient, whichdemonstrate controlofactivities. | |
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| Theseprocesses include:oPostTripReview(A-25.4)oEmergency Maintenance Procedures oCorrective ActionSystemoMorningPriorityActionRequired(MOPAR)oEmergency Operating Procedures (EOPs)Recoveryfromplanttripsisaccomplished bytheplantstaffsafelyandeffectively inaformalfashion.Emergency Maintenance isplannedinawellthoughtoutmannerandisformallyapprovedbythePlantOperations ReviewCommittee (PORC).Ourcontrolofoperationa eventshasimproved.
| | 'Page 12, regarding SALP Board Recommendation on housekeeping. |
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| TheupgradedEOP'scoupledwiththenewlyinstalled simulator hasstrengthened ourresponsetooff-normalev'ents.However,wehaveidentified additional areastobeevaluated whichcouldimproveour"controlofactivities."
| | We agree with recommendation and will'institute a formal housekeeping program.The program will consist of three phases: defining the standards, performing an education program, and implementating. |
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| Theseare:oRootCauseIdentification oTroubleshooting 1~Theplantstaffwillreviewtheseareasandwillimplement thoseaspectswhichcanimproveourcontrolofactivities.
| | k RGSE Response to SALP Report No.50-244/85-99 Page 2 ATTACHMENT B Page 13,.bottom paragraph regarding SWP clarification The following is provided for as an update: A procedure is currently being developed which will describe the purpose of each section of a work permit.This procedure will also outline the generally accepted interpretation for common work permit entries.This should reduce the chance of misinterpretatXori'f the meaning of work permit require-ments.-Page 14, 1st paragraph regarding ALARA policy: A number of formal mechanisms have been and continue to be in place.to ensure that radiation exposure is maintained ALARA and additional formal mechanisms are being developed. |
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| Inthepro-active mode,thefollowing programs/processes areinplacetocontrolactivities.
| | A Corporate ALARA Policy was issued by Francis E.Drake, Jr., the Corporate Chairman of the Board in 1978 and was updated by Paul W.Briggs, Chairman of the Board, in 1984.A.much more detailed policy was issued in 1986.Plant ALARA procedures have been in place for a number of years and govern all activities at the plant, including modifications. |
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| oPORCoQA/QCSub-Committee oALARACommittee o.MOPAR'
| | After requirements for ALARA review of modification designs were added to Engineering Department procedures on November 1, 1985.A detailed checklist to assist in compliance with this review requirement is being prepared.Page 14, 1st paragraph regarding'Corporate Health Physicists gob description: |
| tf'I4 RGfEResponseto8ALPReportNo.50-2ii/85-99 Page2ATTACHMENT AYouareawareofthesecommittees andhavecommented onthemasstrengths sonofurtherelaboration isrecpxired here.Thefollowing programsarebeing.developed andimplemented:
| | The Corporate Health Physicist position description and list of duties was prepared and issued in November 1980.The position description and list of duties was revised in July 1985.Page 15, 3rd paragraph regarding TLD correction factor: The following is provided for update: Our environmental TLD badges were submitted to the DOE for irradiation and subsequent readout at our facility.We have received verbal verification that our system is within normally acceptable range, but the official report has not yet been received. |
| oAccreditation oMaintenance Procedure Upgrade(stressing acceptance criteria)
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| oMaintenance Information System(MIS)oObjective BasedManagement Program(OBM)Theseprogramswillimproveourcontrolofactivities atalllevelswithintheplant.Severalotherareaswillbeevaluated bytheplantstafftodetermine aspects.whichcanimproveourcontrolofactivities.
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| 0000Concurrent ActivityIdentification andControlNonQAWorkActivityControlOBMPlanningConductofMeetingsInreviewing performance
| | A r~4 ROSE Response to 8ALP Report No.50-2ii/85-99 Page 3 ATTACHMENT B Page 18, 2nd paxagraph regarding all Balance of Plant (BOP)instrumentation: |
| "attheplant,reviewofconcurrent activities, canbeimprovedwiththeobjective ofidentifying andeliminating potential conflicts.
| | This is to clarify that it is our intent to provide controls and procedures for selective BOP instrumentation and not all.Page 20, 2nd paragraph regarding{}C backshift covexage: RGRE will implement QC backshift'overage of selected preplanned safety related operations activities. |
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| ThisconcepthasalreadybeenincludedintheMOPARmeetingsandwillcontinuetobestressed.
| | Page 22,-bottom of page: We assume the word"none" was omitted regarding the Board" Recommendation for the Licensee and NRC.Page 28, 2nd paragraph regarding fuel consolidation: |
| | I , The discussion of fuel consolidation activities does not completely reflect all the circumstances surrounding that licensing issue.The NRC licensing issues involved vere stxaight forward and did not involve the actual consolidation technicpxes.. |
| | The initial recgxest for license amendment and responses to'RC cpxestions were submitted in a timely fashion.However, largely due to doubts within governmental organizations as to the likelihood that consolidation would actually take place, certain key NRC licensing milestones wexe delayed.All safety issues were resolved as required by the schedule and fuel consolidation was actually performed. |
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| Thisdiscussion shouldprovideyouwithassurance thatthestaffatGinnaiscontinuously strivingforexcellence inperfonnance.
| | RG&E kept the NRC apprised of all activities during the licensing process.Page 34, bottom of page regarding the Board recommendation: |
| | Since the end of the SALP review period, we have met with you and provided you with an update of our plans and progress.We will continue to keep you informed. |
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| Pa RG&EResponsetoSALPReportNo.50-2ii/85-99 Page1ATTACHMENT BAttachment BSpecificCommentsRO&EResponsetoSystematic Assessment ofLicensePerformance (SALP)ReportNo.50-2ii/85-99 Thefollowing providescommentstospecificpagesforthepurposesofclarification, updatinginformation, and/orpointsofdisagree-
| | I'L A V<<>> |
| ment.Page9,2ndparagraph regarding 1985Reactor'rips onSteam-.Generator Levels(S/G).Thisisprovided, forclarification andupdatingofthesituation.
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| Aftercloseoperations supervision ofthestartupfollowing the1986outage,wehaveconcluded thatthesubjecttripshadarootcauseofequipment failure.Thisisbasedonthefollowing:
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| 1.Z&Ccalibration oftheSteamDumpControlSystemresultedinbeingabletooperateinmanual-autoduringthestartupwithproperresponseobtained.
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| 2.Thefeedwater flowtransmitters werecheckedandrecalibrated withtheloweroutputsetexactlyat10millianps.
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| Whilestillsomewhatinaccurate atvery.lowpowerlevels,theirresponsewasbetterthaninprevious'ears.
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| 'Page12,regarding SALPBoardRecommendation onhousekeeping.
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| Weagreewithrecommendation andwill'institute aformalhousekeeping program.Theprogramwillconsistofthreephases:definingthestandards, performing aneducation program,andimplementating.
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| k RGSEResponsetoSALPReportNo.50-244/85-99 Page2ATTACHMENT BPage13,.bottomparagraph regarding SWPclarification Thefollowing isprovidedforasanupdate:Aprocedure iscurrently beingdeveloped whichwilldescribethepurposeofeachsectionofaworkpermit.Thisprocedure willalsooutlinethegenerally acceptedinterpretation forcommonworkpermitentries.ThisshouldreducethechanceofmisinterpretatXori'f themeaningofworkpermitrequire-ments.-Page14,1stparagraph regarding ALARApolicy:Anumberofformalmechanisms havebeenandcontinuetobeinplace.toensurethatradiation exposureismaintained ALARAandadditional formalmechanisms arebeingdeveloped.
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| ACorporate ALARAPolicywasissuedbyFrancisE.Drake,Jr.,theCorporate ChairmanoftheBoardin1978andwasupdatedbyPaulW.Briggs,ChairmanoftheBoard,in1984.A.muchmoredetailedpolicywasissuedin1986.PlantALARAprocedures havebeeninplaceforanumberofyearsandgovernallactivities attheplant,including modifications.
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| Afterrequirements forALARAreviewofmodification designswereaddedtoEngineering Department procedures onNovember1,1985.Adetailedchecklist toassistincompliance withthisreviewrequirement isbeingprepared.
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| Page14,1stparagraph regarding'Corporate HealthPhysicists gobdescription:
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| TheCorporate HealthPhysicist positiondescription andlistofdutieswaspreparedandissuedinNovember1980.Thepositiondescription andlistofdutieswasrevisedinJuly1985.Page15,3rdparagraph regarding TLDcorrection factor:Thefollowing isprovidedforupdate:Ourenvironmental TLDbadgesweresubmitted totheDOEforirradiation andsubsequent readoutatourfacility.
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| Wehavereceivedverbalverification thatoursystemiswithinnormallyacceptable range,buttheofficialreporthasnotyetbeenreceived.
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| Ar~4 ROSEResponseto8ALPReportNo.50-2ii/85-99 Page3ATTACHMENT BPage18,2ndpaxagraph regarding allBalanceofPlant(BOP)instrumentation:
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| Thisistoclarifythatitisourintenttoprovidecontrolsandprocedures forselective BOPinstrumentation andnotall.Page20,2ndparagraph regarding
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| {}Cbackshift covexage:
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| RGREwillimplement QCbackshift
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| 'overageofselectedpreplanned safetyrelatedoperations activities.
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| Page22,-bottomofpage:Weassumetheword"none"wasomittedregarding theBoard"Recommendation fortheLicenseeandNRC.Page28,2ndparagraph regarding fuelconsolidation:
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| I,Thediscussion offuelconsolidation activities doesnotcompletely reflectallthecircumstances surrounding thatlicensing issue.TheNRClicensing issuesinvolvedverestxaightforwardanddidnotinvolvetheactualconsolidation technicpxes..
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| Theinitialrecgxestforlicenseamendment andresponses to'RCcpxestions weresubmitted inatimelyfashion.However,largelyduetodoubtswithingovernmental organizations astothelikelihood thatconsolidation wouldactuallytakeplace,certainkeyNRClicensing milestones wexedelayed.Allsafetyissueswereresolvedasrequiredbythescheduleandfuelconsolidation wasactuallyperformed.
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| RG&EkepttheNRCapprisedofallactivities duringthelicensing process.Page34,bottomofpageregarding theBoardrecommendation:
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| SincetheendoftheSALPreviewperiod,wehavemetwithyouandprovidedyouwithanupdateofourplansandprogress.
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| Wewillcontinuetokeepyouinformed.
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| I'LAV<<>>
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| }} | | }} |
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[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] |
Inspection Report - Ginna - 1985099 |
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Text
~~~i 43'k~ROCHESTER GAS AND ENCLOSURE'4.l*2 j~~llktf'LECTRIC CORPORATION
~89 EAST AVENUE, ROCHESTER, N.Y.1484&0001 ROGER W.KOBER WCC PRC%OKNT CIXCTlOC O 5TEAM PROOUCTlON TCLKPHONC ABACA COOC%le 546.2700 Dr.Thomas E.Murley, Regional Administrator U.S.Nuclear Regulatory Commission Region I 631 Park Avenue I October.28, 1986 King of Prussia, Pennsylvania 19406 Subject: RG&E Response to Systematic Assessment of.Licensee Performance (SALP)Report No.50-244/85-99
Dear Dr.Murley:
In response to your September 18, 1986 letter.transmitting the SALP,Report 85-99 and as a result of our October 7, 1986 meeting in Rochester, we are providing written comments.In general, we agree with the report and appreciate the opportunity to discuss our performance over the SALP period with you.We note your assessment that our performance demonstrates a strong commitment to safe and efficient plant operations.
Regarding strengthening.of our Quality Assurance Program, we have been accelerating completion of our initiatives.
These have been discussed with you and members of your staff and we will continue to keep you informed of,our progress.We believe the issue of"informality with regard to station activities" is more properly addressed as an issue of"control of activities."'!Two types of comments are provided.First, comments on the SALP-Board Observations regarding"an apparent attitude of informality at Ginna Station" are provided in Attachment A"RG&E Comments on Control of Activities." Second, specific comments on specific pages in'he report are included in Attachment B-"RG&E Comments on SALP Report 50-244/85-99." This discussion should provide you with assurance that the staff at RG&E is continuously striving for excellence in perform-ance.Ro r W.Kober Attachment
/Copies: Document Control Desk c'W fR pf I ll'
'RQfE Response to SAXP Report No.50-2li/85-99 Page ATTACHMENT A ATTACHMENT A t&o e so o o c 8 We believe the issue of"informal versus formal"" attitude to be one of<<control of activities." It is necessary to review some of the formal programs already in place or in progress which are designed to improve ouZ"control of activities." There are two modes that naturally apply when controlling activities.
A reactive mode, logically entered for events such as plant trips or emergency maintenance, and a pro-active mode for pre-planning of activities.
Addressing the reactive mode, there are several formal processes.already in place," in which the plant staff is quite proficient, which demonstrate control of activities.
These processes include: o Post Trip Review (A-25.4)o Emergency Maintenance Procedures o Corrective Action System o Morning Priority Action Required (MOPAR)o Emergency Operating Procedures (EOPs)Recovery from plant trips is accomplished by the plant staff safely and effectively in a formal fashion.Emergency Maintenance is planned in a well thought out manner and is formally approved by the Plant Operations Review Committee (PORC).Our control of operationa events has improved.The upgraded EOP's coupled with the newly installed simulator has strengthened our response to off-normal ev'ents.However, we have identified additional areas to be evaluated which could improve our"control of activities." These are: o Root Cause Identification o Troubleshooting 1~The plant staff will review these areas and will implement those aspects which can improve our control of activities.
In the pro-active mode, the following programs/processes are in place to control activities.
o PORC o QA/QC Sub-Committee o ALARA Committee o.MOPAR'
t f'I 4 RGfE Response to 8ALP Report No.50-2ii/85-99 Page 2 ATTACHMENT A You are aware of these committees and have commented on them as strengths so no further elaboration is recpxired here.The following programs are being.developed and implemented:
o Accreditation o Maintenance Procedure Upgrade (stressing acceptance criteria)o Maintenance Information System (MIS)o Objective Based Management Program (OBM)These programs will improve our control of activities at all levels within the plant.Several other areas will be evaluated by the plant staff to determine aspects.which can improve our control of activities.
0 0 0 0 Concurrent Activity Identification and Control Non QA Work Activity Control OBM Planning Conduct of Meetings In reviewing performance"at the plant, review of concurrent activities, can be improved with the objective of identifying and eliminating potential conflicts.
This concept has already been included in the MOPAR meetings and will continue to be stressed.This discussion should provide you with assurance that the staff at Ginna is continuously striving for excellence in perfonnance.
Pa RG&E Response to SALP Report No.50-2ii/85-99 Page 1 ATTACHMENT B Attachment B Specific Comments RO&E Response to Systematic Assessment of License Performance (SALP)Report No.50-2ii/85-99 The following provides comments to specific pages for the purposes of clarification, updating information, and/or points of disagree-ment.Page 9, 2nd paragraph regarding 1985 Reactor'rips on Steam-.Generator Levels (S/G).This is provided, for clarification and updating of the situation.
After close operations supervision of the startup following the 1986 outage, we have concluded that the subject trips had a root cause of equipment failure.This is based on the following:
1.Z&C calibration of the Steam Dump Control System resulted in being able to operate in manual-auto during the startup with proper response obtained.2.The feedwater flow transmitters were checked and recalibrated with the lower output set exactly at 10 millianps.
While still somewhat inaccurate at very.low power levels, their response was better than in previous'ears.
'Page 12, regarding SALP Board Recommendation on housekeeping.
We agree with recommendation and will'institute a formal housekeeping program.The program will consist of three phases: defining the standards, performing an education program, and implementating.
k RGSE Response to SALP Report No.50-244/85-99 Page 2 ATTACHMENT B Page 13,.bottom paragraph regarding SWP clarification The following is provided for as an update: A procedure is currently being developed which will describe the purpose of each section of a work permit.This procedure will also outline the generally accepted interpretation for common work permit entries.This should reduce the chance of misinterpretatXori'f the meaning of work permit require-ments.-Page 14, 1st paragraph regarding ALARA policy: A number of formal mechanisms have been and continue to be in place.to ensure that radiation exposure is maintained ALARA and additional formal mechanisms are being developed.
A Corporate ALARA Policy was issued by Francis E.Drake, Jr., the Corporate Chairman of the Board in 1978 and was updated by Paul W.Briggs, Chairman of the Board, in 1984.A.much more detailed policy was issued in 1986.Plant ALARA procedures have been in place for a number of years and govern all activities at the plant, including modifications.
After requirements for ALARA review of modification designs were added to Engineering Department procedures on November 1, 1985.A detailed checklist to assist in compliance with this review requirement is being prepared.Page 14, 1st paragraph regarding'Corporate Health Physicists gob description:
The Corporate Health Physicist position description and list of duties was prepared and issued in November 1980.The position description and list of duties was revised in July 1985.Page 15, 3rd paragraph regarding TLD correction factor: The following is provided for update: Our environmental TLD badges were submitted to the DOE for irradiation and subsequent readout at our facility.We have received verbal verification that our system is within normally acceptable range, but the official report has not yet been received.
A r~4 ROSE Response to 8ALP Report No.50-2ii/85-99 Page 3 ATTACHMENT B Page 18, 2nd paxagraph regarding all Balance of Plant (BOP)instrumentation:
This is to clarify that it is our intent to provide controls and procedures for selective BOP instrumentation and not all.Page 20, 2nd paragraph regarding{}C backshift covexage: RGRE will implement QC backshift'overage of selected preplanned safety related operations activities.
Page 22,-bottom of page: We assume the word"none" was omitted regarding the Board" Recommendation for the Licensee and NRC.Page 28, 2nd paragraph regarding fuel consolidation:
I , The discussion of fuel consolidation activities does not completely reflect all the circumstances surrounding that licensing issue.The NRC licensing issues involved vere stxaight forward and did not involve the actual consolidation technicpxes..
The initial recgxest for license amendment and responses to'RC cpxestions were submitted in a timely fashion.However, largely due to doubts within governmental organizations as to the likelihood that consolidation would actually take place, certain key NRC licensing milestones wexe delayed.All safety issues were resolved as required by the schedule and fuel consolidation was actually performed.
RG&E kept the NRC apprised of all activities during the licensing process.Page 34, bottom of page regarding the Board recommendation:
Since the end of the SALP review period, we have met with you and provided you with an update of our plans and progress.We will continue to keep you informed.
I'L A V<<>>
