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{{#Wiki_filter:AttachmentA1.ReplaceTechnicalSpecificationpages6.2-7and6.3-1withtheenclosedpages.8507260038850719PDRADOCK05000244P:PDR m'~'i<
{{#Wiki_filter:Attachment  A
R.E.GINNASTATIONOPERATIONSANDTECHNICALSECTIONSGROUPORGANIZATIONSOPERATIONSMANAGERTECHNICALMANAGEROPERATIONSSUPERVISOR(SRO)RESULTSANDTESTSUPERVISORREACTORENGINEERTECHNICALPROJECTSSUPERVISORENGINEER(S)SHIFTSUPERVISORI/SHIFT(SRO)TECHNICIANS8REPAIRMENTECHNICALCOMPUTERSYSTEMSANALYSTHEADCONTROLOPERATORI/SHIFT(RO)CONTROLOPERATORI/SHIFT(RO)AUXILIARYOPERATORS2/SHIFTCOMPUTERTECHNICIANSFIGURE6.2-5RGSEREV.54$pcf42S C"1I~'
: 1. Replace Technical Specification pages 6.2-7 and 6.3-1 with the enclosed pages.
6.3STATIONSTAFFQUALIFICATIONS6.3.1EachmemberofthefacilityshallmeetorexceedtheminimumqualificationsofANSIStandardN18.1-1971,"SelectionandTrainingofNuclearPowerPlantPersonnel"<assupplementedbyRegulatoryGuide1.8>September1975iforcomparablepositions<exceptfortheShiftTechnicalAdvisoriandexceptfortheOperations1ManagerwhoshallhaveheldanNRCsenioroperatorlicenseforGinna.References1Ltr.J.Maier(RG6E)toD.Crutchfield(NRC)idatedDecember30'980.6.3-1PROPOSED r4f AttachmentBTheproposedchangewoulddeletetherequirementthatthestationOperationsManagercurrrentlyholdanNRCsenioroperatorlicenseandreplaceitwiththerequirementthattheindividualmusthaveheldanNRCsenioroperatorlicenseforGinna.TheOperationsSupervisor<towhomtheShiftSupervisorsandoperatingpersonnelreport<willstillberequiredtomaintainanNRCsenioroperatorlicense.Thus<anindividualonthemanagementchainwillstillberequiredtomaintainalicense.TheANSIN18.1-1971requirementisonlythattheOperationsManagershouldhavealicenseonlyatthetimeofassumingtheposition.Theproposedrequirementswouldmeetorexceedtheintentoftherequirement.TheadvantagesoftheproposedchangearethattheOperationsManagerwillhavemoretimetodevotetomanagingtheoperatingorganizationduetoareducedtrainingcommitment.InadditionsthebaseofpersonnelwhocouldfilltheOperationsManagerpositionwillbebroadenedtoincludenotonlythosecurrentlyholdingalicensebutalsothosewhohaveheldalicense.TheproposedchangeisacceptablesinceitwillretainthenecessarymanagementknowledgeandcontrolswhileimprovingtheabilityoftheOperationsManagertomanagetheoperatingorganization.Inaccordancewith10CFR50.91<theproposedchangetotheTechnicalSpecificationshasbeenevaluatedagainstthreecriteriatodetermineiftheoperationofthefacilityinaccordancewiththeproposedamendmentwould:1.involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or2.3.createthepossibilityofanewordifferentkindofaccidentfrom'anyaccidentpreviously"evaluated;,or~~involveasig'nificantreductionin"a'margino'fsafety.Theproposedchangewillnothaveanadverseimpactasjudgedagainstthesecriteria.TheproposedTechnicalSpecificationchangeconformstotheintentofregulatoryguidanceandmeetstheCommission'sexample(vi)ofamendmentsthatdonotinvolveasignificanthazardsconsiderationbecausetheresultsofthechangearewithinallacceptablecriteriaestablishedbyregulatoryguidance.Theproposedamendmentdoesnotinvolveanyirreversibleconsequences.Therefore<thereisnounduerisktopublichealthandsafetyandafindingofnosignificanthazardsiswarrantedfortheproposedTechnicalSpecificationchange.
8507260038 850719 PDR  ADOCK 05000244 P              :PDR
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R. E. GINNA STATION OPERATIONS AND TECHNICAL SECTIONS GROUP ORGANIZATIONS OPERATIONS                                        TECHNICAL MANAGER                                        MANAGER OPERATIONS        RESULTS              REACTOR            TECHNICAL AND TEST                                  PROJECTS  ENGINEER(S)
SUPERVISOR (SRO)   SUPERVISOR            ENGINEER            SUPERVISOR SHIFT      TECHNICIANS            TECHNICAL SUPERVISOR                            COMPUTER I /SHIFT (SRO)   8 REPAIRMEN        SYSTEMS ANALYST HEAD CONTROL OPERATOR                            COMPUTER I/SHIFT (RO)
TECHNICIANS CONTROL OPERATOR I/SHIFT (RO)
AUXILIARY OPERATORS 2/ SHIFT FIGURE  6.2-5 RGSE REV. 54$ pcf 42 S
 
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6.3        STATION STAFF QUALIFICATIONS 6.3.1      Each member  of the  facility shall  meet or exceed  the minimum  qualifications of  ANSI Standard    N18.1-1971, "Selection and Training of Nuclear    Power  Plant Personnel"< as supplemented    by Regulatory Guide 1.8>
September  1975i for  comparable positions< except    for the Shift Technical Advisori 1  and except  for the Operations Manager who  shall  have held an  NRC  senior operator license for Ginna.
References 1
Ltr. J. Maier (RG6E) to D. Crutchfield   (NRC) i  dated December 30'980.
6.3-1              PROPOSED
 
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Attachment    B The proposed    change would delete the requirement that the station Operations      Manager currrently hold an NRC senior operator license and replace      it with the requirement that the individual must have held an NRC senior operator license for Ginna. The Operations Supervisor< to whom the Shift Supervisors and operating personnel report<     will still be required to maintain an NRC senior operator license. Thus< an individual on the management chain will still be required to maintain a license. The ANSI have      N18.1-1971 requirement is only that the Operations Manager should              a license only at the time of assuming the position. The proposed requirements would meet or exceed the intent of the requirement.
The advantages of the proposed change are that the Operations Manager will have more time to devote to managing the operating organization due to a reduced training commitment. In additions the base of personnel who could position  will  be  broadened  to fill include the Operations Manager not only those currently holding  a  license  but  also  those  who  have held a license.
The proposed change is acceptable since knowledge        controls it while will retain the improving the necessary management                  and ability of the Operations Manager to manage the operating organization.
In accordance with 10 CFR 50.91< the proposed change to the Technical Specifications has been evaluated against three criteria to determine    if  the operation of the facility in accordance with the proposed amendment would:
: 1. involve  a  significant increase in    the probability or consequences    of an accident previously evaluated; or
: 2. create the possibility of a new or different kind of accident from'any accident previously" evaluated;,or~~
: 3. involve a sig'nificant reduction in" a'margin o'f safety.
The proposed    change  will not  have an adverse  impact as judged against these    criteria.
The proposed Technical Specification change conforms to the intent of regulatory guidance and meets the Commission's example (vi) of amendments that do not involve a significant hazards consideration because the results of the change are within all acceptable criteria established by regulatory guidance. The proposed amendment does not involve any irreversible consequences.
Therefore< there is no undue risk to public health and safety and a finding of no significant hazards is warranted for the proposed Technical Specification change.
 
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Latest revision as of 11:41, 4 February 2020

Proposed Tech Spec Changes,Revising Requirements for Station Operations Manager to Hold Senior Operator License
ML17254A450
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/19/1985
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17254A449 List:
References
NUDOCS 8507260038
Download: ML17254A450 (8)
v • d • e


Text

Attachment A

1. Replace Technical Specification pages 6.2-7 and 6.3-1 with the enclosed pages.

8507260038 850719 PDR ADOCK 05000244 P :PDR

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R. E. GINNA STATION OPERATIONS AND TECHNICAL SECTIONS GROUP ORGANIZATIONS OPERATIONS TECHNICAL MANAGER MANAGER OPERATIONS RESULTS REACTOR TECHNICAL AND TEST PROJECTS ENGINEER(S)

SUPERVISOR (SRO) SUPERVISOR ENGINEER SUPERVISOR SHIFT TECHNICIANS TECHNICAL SUPERVISOR COMPUTER I /SHIFT (SRO) 8 REPAIRMEN SYSTEMS ANALYST HEAD CONTROL OPERATOR COMPUTER I/SHIFT (RO)

TECHNICIANS CONTROL OPERATOR I/SHIFT (RO)

AUXILIARY OPERATORS 2/ SHIFT FIGURE 6.2-5 RGSE REV. 54$ pcf 42 S

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6.3 STATION STAFF QUALIFICATIONS 6.3.1 Each member of the facility shall meet or exceed the minimum qualifications of ANSI Standard N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel"< as supplemented by Regulatory Guide 1.8>

September 1975i for comparable positions< except for the Shift Technical Advisori 1 and except for the Operations Manager who shall have held an NRC senior operator license for Ginna.

References 1

Ltr. J. Maier (RG6E) to D. Crutchfield (NRC) i dated December 30'980.

6.3-1 PROPOSED

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Attachment B The proposed change would delete the requirement that the station Operations Manager currrently hold an NRC senior operator license and replace it with the requirement that the individual must have held an NRC senior operator license for Ginna. The Operations Supervisor< to whom the Shift Supervisors and operating personnel report< will still be required to maintain an NRC senior operator license. Thus< an individual on the management chain will still be required to maintain a license. The ANSI have N18.1-1971 requirement is only that the Operations Manager should a license only at the time of assuming the position. The proposed requirements would meet or exceed the intent of the requirement.

The advantages of the proposed change are that the Operations Manager will have more time to devote to managing the operating organization due to a reduced training commitment. In additions the base of personnel who could position will be broadened to fill include the Operations Manager not only those currently holding a license but also those who have held a license.

The proposed change is acceptable since knowledge controls it while will retain the improving the necessary management and ability of the Operations Manager to manage the operating organization.

In accordance with 10 CFR 50.91< the proposed change to the Technical Specifications has been evaluated against three criteria to determine if the operation of the facility in accordance with the proposed amendment would:

1. involve a significant increase in the probability or consequences of an accident previously evaluated; or
2. create the possibility of a new or different kind of accident from'any accident previously" evaluated;,or~~
3. involve a sig'nificant reduction in" a'margin o'f safety.

The proposed change will not have an adverse impact as judged against these criteria.

The proposed Technical Specification change conforms to the intent of regulatory guidance and meets the Commission's example (vi) of amendments that do not involve a significant hazards consideration because the results of the change are within all acceptable criteria established by regulatory guidance. The proposed amendment does not involve any irreversible consequences.

Therefore< there is no undue risk to public health and safety and a finding of no significant hazards is warranted for the proposed Technical Specification change.

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