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| {{#Wiki_filter:ATTACHMENTARevisetheTechnicalSpecificationpagesasfollows:Remove6.5-9Insert6.5-9i.;,9102250,111...9.10215",'PDR,ADOCK050002444P--PDR REVIEW(Continued)h.Anyindicationofanunanticipateddeficiencyinsomeaspectofdesignoroperationofsafetyrelated3~structures,systems,orcomponents.ReportsandmeetingminutesofthePlantOperationsReviewCommittee.AUDITS6.5.2.8TheNSARBshalldirecttheestablishmentofanauditprogramandevaluateauditsperformed'oensuresafefacilityoperation.Auditsshallencompass:a~b.c~TheconformanceoffacilityoperationtoallprovisionscontainedwithintheTechnicalSpecificationsandapplicablelicenseconditionsatleastonceperyear.Theperformance,trainingandqualificationsoftheoperatingandtechnicalstaffatleastonceayear.Theresultsofallactionstaken.tocorrectdeficienciesoccurringinfacilityequipment,structures,systemsormethodofoperationthataffectnuclearsafetyatleastoncepersixmonths.d.TheperformanceofallactivitiesrequiredbytheQualityAssuranceProgramforR.E.GinnaNuclearPowerPlanttomeetthecriteriaofAppendixB,10CFR50,atleastoncee.per24months.TheRadiationEmergencyPlanandimplementingproceduresatleastatthefrequencyrequiredby10CFR50.54(t).TheStationSecurityPlanand.implementingproceduresatleastatthefrequencyrequiredby10CFR73.40(d).6.5-9Proposed. | | {{#Wiki_filter:ATTACHMENT A Revise the Technical Specification pages as follows: |
| IOEl AttachmentBThepurposeoftheproposedamendmentistoprovideclarificationofwhichqualityassuranceactivitiesaresubjecttoauditconsiderations,throughreferencetotheNuclearRegulatoryCommission(NRC)endorsedQualityAssuranceProgramforR.E.GinnaNuclearPowerPlant.Theproposedamendmentalsochangestheauditfrequency,describedinTechnicalSpecification6.5.2.8d,from"atleastonceperyear"to"atleastonceper24months."TheproposedchangetoprovideclarificationtoSpecification6.5.2.8disconsidered.tobeanadministrativechange.Sincetheproposedchangeonlyprovidesclarification,noreductionofthelevelofauthorityandresponsibilitythereof,wouldresultfromtheadministrativechange.Theproposedchangetotheauditfrequencyfrom"atleastonceperyear"to"atleastonceper24months"wouldnotreducethe.overalleffectivenesstoensurethatallprograms/activitiesrequired.bytheQualityAssuranceProgrammeetthecriteriaofAppendixB,10CFR50.TheproposedchangefacilitatesGinna.'sauditandassessmentplanningprocesswhichisbasedongroupperformanceandmanagementconcerns.The-purpose,ofassessmentsperformed.aspartof.thequalityprogramistoassistmanagementinevaluatingtheperformanceofstationactivitiesand.theeffectiveness,ofmanagementcontrols.andprograms.TheauditprogramatGinnahasbeenintransitionoverthepast'eartofacilitatetheconductofperformance.basedauditsandassessments.Theseimprovementsarebeingincorporatedinto-theGinnaQualityAssuranceProgramsubmittal..Furthermore,implementationoftheproposed.amendmentwil1continue.toprovidemanagementwithtimelyandrelevantinformationregardingperformanceandcomplianceofallactivitiestomeetthecriteriaofAppendix"B",10CFRPart50.Theproposed.amendmentpermitsmoreefficientuseofresourceswhichineffectwillenabletheconductofmoreassessments,bothspecialanddiagnostic.Thisapproach,i.e.,groupperformance.basedassessments,isencouragedinNUREG-0800,Revision0,StandardReviewPlan,datedAugust,1990.Consistentwiththeabove,selectionofanassessmentfrequencyshould.bebasedontheimportanceoftheactivityforsafeandreliablestationoperation,pastperformance,suspectedweakareas,andregulatoryrequirementsratherthanaschedule.predicatedbytheabrupt12monthrequirement.TheoveralleffectivenesstomeetthecriteriaofAppendix.B,10CFR50willnotbereduced.since:(1)personnelresponsibleforcarryingoutself-assessmentfunctions,includingsafetycommitteeactivities(PORCandNSARB)andcontinuingQualityAssuranceauditsarecognizantofday-to-dayactivitiesand (2)actinamanagementadvisoryfunctiontoidentifyand,alleviateanomalousperformanceandprecursorsofpotentialproblems.Further,theproposedamendmentisconsistentwiththerequiredauditfrequencyof24monthsidentifiedinNUREG-0452,"StandardTechnicalSpecificationsforWestinghousePressurizedWaterReactors."10CFR50.92EVALUATIONTheproposedchangeintheGinnaTechnicalSpecificationsdoesnotinvolveasignificanthazardconsideration.Thebasisforthisdeterminationisasfollows:~Thereisnosignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluatedbecauseaccidentconditionsand.assumptionsarenotaffectedbytheproposedTechnicalSpecificationchange.Thepossibilityofanewordifferentkindofaccident.fromanyaccidentpreviouslyevaluatedisnotcreated.Inmattersrelated.tonuclearsafety,allaccidentsareboundedbypreviousanalysis.Theproposedchangedoesnotaddormodifyanyequipmentorsystemdesignnordoesitinvolveanychangesintheoperationofanyplantsystem.Theabsenceofahardwarechangemeansthattheaccidentinitiatorsremainunaffected,sonouniqueaccidentprobabilityiscreated.TheproposedamendmentdoesnotinvolveasignificantreductioninthemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationbecausetheproposedamendmentwillcontinuetoensurethat(1)performancebased.auditsandassessmentsshallbeinsufficientdepth,(2).participatingmembersaresatisfiedthatitemsunderreviewdonototherwiseconstituteaconcernand(3)allactivitiesrequiredbytheQualityAssuranceProgrammeetthecriteriaofAppendixB,10CFR50.Further,theproposedamendmentpermitsmoreefficientuseofresourceswhichineffectwillenabletheconductofmoreassessments,bothspecialand.diagnostic.Inadditiontotheabove,thisproposedamendmentisconsistentwiththerequiredauditfrequencyof24monthsidentifiedinNUREG-0452,"Standard.TechnicalSpecificationsforWestinghousePressurizedWaterReactors."Therefore,theproposedchangetotheoperatinglicensedoesnotinvolveasignificantreductioninthemarginofsafetyasdefinedinthebasisforanyTechnicalSpecification.CONCLUSIONOnthebasisoftheabove,RG&Ehasdetermined.thattheamendmentrequestdoes,notinvolveasignificanthazardsconsideration.}}
| | Remove Insert 6.5-9 6.5-9 |
| | .;,9102250,1 1 1...9.10215 |
| | ",'PDR, ADOCK 05000244-i 4P - PDR |
| | |
| | REVIEW (Continued) |
| | : h. Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components. |
| | 3 ~ Reports and meeting minutes of the Plant Operations Review Committee. |
| | AUDITS 6.5.2.8 The NSARB shall direct the establishment of an audit program and evaluate audits performed'o ensure safe facility operation. Audits shall encompass: |
| | a ~ The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year. |
| | : b. The performance, training and qualifications of the operating and technical staff at least once a year. |
| | c ~ 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. |
| | : d. The performance of all activities required by the Quality Assurance Program for R. E. Ginna Nuclear Power Plant to meet the criteria of Appendix B, 10 CFR 50, at least once per 24 months. |
| | : e. The Radiation Emergency Plan and implementing procedures at least at the frequency required by 10 CFR 50.54(t). |
| | The Station Security Plan and. implementing procedures at least at the frequency required by 10 CFR 73.40(d). |
| | 6.5-9 Proposed. |
| | |
| | IO E |
| | l |
| | |
| | Attachment B The purpose of the proposed amendment is to provide clarification of which quality assurance activities are subject to audit considerations, through reference to the Nuclear Regulatory Commission (NRC) endorsed Quality Assurance Program for R. E. Ginna Nuclear Power Plant. The proposed amendment also changes the audit frequency, described in Technical Specification 6.5.2.8d, from "at least once per year" to "at least once per 24 months." |
| | The proposed change to provide clarification to Specification 6.5.2.8d is considered. to be an administrative change. Since the proposed change only provides clarification, no reduction of the level of authority and responsibility thereof, would result from the administrative change. |
| | The proposed change to the audit frequency from "at least once per year" to "at least once per 24 months" would not reduce the. overall effectiveness to ensure that all programs/activities required. by the Quality Assurance Program meet the criteria of Appendix B, 10 CFR 50. |
| | The proposed change facilitates Ginna.'s audit and assessment planning process which is based on group performance and management concerns. The -purpose, of assessments performed. as part of. the quality program is to assist management in evaluating the performance of station activities and. the effectiveness, of management controls. and programs. |
| | The audit program at Ginna has been in transition over the to facilitate the conduct of performance. based audits and past'ear assessments. These improvements are being incorporated into- the Ginna Quality Assurance Program submittal.. Furthermore, implementation of the proposed. amendment wil1 continue. to provide management with timely and relevant information regarding performance and compliance of all activities to meet the criteria of Appendix "B", 10 CFR Part 50. |
| | The proposed. amendment permits more efficient use of resources which in effect will enable the conduct of more assessments, both special and diagnostic. This approach, i.e., group performance. |
| | based assessments, is encouraged in NUREG-0800, Revision 0, Standard Review Plan, dated August, 1990. |
| | Consistent with the above, selection of an assessment frequency should. be based on the importance of the activity for safe and reliable station operation, past performance, suspected weak areas, and regulatory requirements rather than a schedule. predicated by the abrupt 12 month requirement. |
| | The overall effectiveness to meet the criteria of Appendix. B, 10 CFR 50 will not be reduced. since: |
| | (1) personnel responsible for carrying out self-assessment functions, including saf ety committee activities (PORC and NSARB) and continuing Quality Assurance audits are cognizant of day-to-day activities and |
| | |
| | (2) act in a management advisory function to identify and, alleviate anomalous performance and precursors of potential problems. |
| | Further, the proposed amendment is consistent with the required audit frequency of 24 months identified in NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors." |
| | 10 CFR 50.92 EVALUATION The proposed change in the Ginna Technical Specifications does not involve a significant hazard consideration. The basis for this determination is as follows: |
| | ~ There is no significant increase in the probability or consequences of an accident previously evaluated because accident conditions and. assumptions are not affected by the proposed Technical Specification change. |
| | The possibility of a new or different kind of accident. from any accident previously evaluated is not created. In matters related. to nuclear safety, all accidents are bounded by previous analysis. The proposed change does not add or modify any equipment or system design nor does it involve any changes in the operation of any plant system. The absence of a hardware change means that the accident initiators remain unaffected, so no unique accident probability is created. |
| | The proposed amendment does not involve a significant reduction in the margin of safety as defined in the basis for any Technical Specification because the proposed amendment will continue to ensure that (1) performance based. audits and assessments shall be in sufficient depth , (2). participating members are satisfied that items under review do not otherwise constitute a concern and (3) all activities required by the Quality Assurance Program meet the criteria of Appendix B, 10 CFR 50. Further, the proposed amendment permits more efficient use of resources which in effect will enable the conduct of more assessments, both special and. diagnostic. In addition to the above, this proposed amendment is consistent with the required audit frequency of 24 months identified in NUREG-0452, "Standard. Technical Specifications for Westinghouse Pressurized Water Reactors." Therefore, the proposed change to the operating license does not involve a significant reduction in the margin of safety as defined in the basis for any Technical Specification. |
| | CONCLUSION On the basis of the above, RG&E has determined. that the amendment request does, not involve a significant hazards consideration.}} |
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Category:TECHNICAL SPECIFICATIONS
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ML17262B1191992-12-17017 December 1992 Proposed Tech Specs Sections 3.2 & 3.3 Re Acid Storage Tank Boron Concentration Reduction Study ML17309A5021992-11-30030 November 1992 Proposed Tech Specs Reflecting Removal of Table of Containment Isolation Valves ML17262B0441992-10-0808 October 1992 Proposed TS 3.7.1 Re Auxiliary Electrical Sys ML17262B0211992-09-15015 September 1992 Proposed Tech Specs Sections 3.1.1.4,3.1.1.6 & 4.3.4, Addressing GL 90-06, Resolution of Generic Issue 70, 'Porv & Block Valve Reliability' & Generic Issues 94, 'Addl LTOP for Lwrs.' ML17262A9141992-06-22022 June 1992 Proposed TS 4.3.1 Re Reactor Vessel Matl Surveillance Testing ML17262A8321992-04-23023 April 1992 Proposed Tech Specs Re Snubber Visual Insp Schedule ML17262A8221992-04-21021 April 1992 Proposed Tech Specs Re Fire Protection Program ML17262A7871992-03-23023 March 1992 Proposed Tech Spec Revising Section 6.5.1 Re Plant Operations Review Committee Function ML17262A7911992-03-20020 March 1992 Proposed Tech Specs Revising 6.9.1.2 & 6.9.2.5 1999-06-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. 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W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements 1999-06-28
[Table view] |
Text
ATTACHMENT A Revise the Technical Specification pages as follows:
Remove Insert 6.5-9 6.5-9
.;,9102250,1 1 1...9.10215
",'PDR, ADOCK 05000244-i 4P - PDR
REVIEW (Continued)
- h. Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
3 ~ Reports and meeting minutes of the Plant Operations Review Committee.
AUDITS 6.5.2.8 The NSARB shall direct the establishment of an audit program and evaluate audits performed'o ensure safe facility operation. Audits shall encompass:
a ~ The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
- b. The performance, training and qualifications of the operating and technical staff at least once a year.
c ~ 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.
- d. The performance of all activities required by the Quality Assurance Program for R. E. Ginna Nuclear Power Plant to meet the criteria of Appendix B, 10 CFR 50, at least once per 24 months.
- e. The Radiation Emergency Plan and implementing procedures at least at the frequency required by 10 CFR 50.54(t).
The Station Security Plan and. implementing procedures at least at the frequency required by 10 CFR 73.40(d).
6.5-9 Proposed.
IO E
l
Attachment B The purpose of the proposed amendment is to provide clarification of which quality assurance activities are subject to audit considerations, through reference to the Nuclear Regulatory Commission (NRC) endorsed Quality Assurance Program for R. E. Ginna Nuclear Power Plant. The proposed amendment also changes the audit frequency, described in Technical Specification 6.5.2.8d, from "at least once per year" to "at least once per 24 months."
The proposed change to provide clarification to Specification 6.5.2.8d is considered. to be an administrative change. Since the proposed change only provides clarification, no reduction of the level of authority and responsibility thereof, would result from the administrative change.
The proposed change to the audit frequency from "at least once per year" to "at least once per 24 months" would not reduce the. overall effectiveness to ensure that all programs/activities required. by the Quality Assurance Program meet the criteria of Appendix B, 10 CFR 50.
The proposed change facilitates Ginna.'s audit and assessment planning process which is based on group performance and management concerns. The -purpose, of assessments performed. as part of. the quality program is to assist management in evaluating the performance of station activities and. the effectiveness, of management controls. and programs.
The audit program at Ginna has been in transition over the to facilitate the conduct of performance. based audits and past'ear assessments. These improvements are being incorporated into- the Ginna Quality Assurance Program submittal.. Furthermore, implementation of the proposed. amendment wil1 continue. to provide management with timely and relevant information regarding performance and compliance of all activities to meet the criteria of Appendix "B", 10 CFR Part 50.
The proposed. amendment permits more efficient use of resources which in effect will enable the conduct of more assessments, both special and diagnostic. This approach, i.e., group performance.
based assessments, is encouraged in NUREG-0800, Revision 0, Standard Review Plan, dated August, 1990.
Consistent with the above, selection of an assessment frequency should. be based on the importance of the activity for safe and reliable station operation, past performance, suspected weak areas, and regulatory requirements rather than a schedule. predicated by the abrupt 12 month requirement.
The overall effectiveness to meet the criteria of Appendix. B, 10 CFR 50 will not be reduced. since:
(1) personnel responsible for carrying out self-assessment functions, including saf ety committee activities (PORC and NSARB) and continuing Quality Assurance audits are cognizant of day-to-day activities and
(2) act in a management advisory function to identify and, alleviate anomalous performance and precursors of potential problems.
Further, the proposed amendment is consistent with the required audit frequency of 24 months identified in NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors."
10 CFR 50.92 EVALUATION The proposed change in the Ginna Technical Specifications does not involve a significant hazard consideration. The basis for this determination is as follows:
~ There is no significant increase in the probability or consequences of an accident previously evaluated because accident conditions and. assumptions are not affected by the proposed Technical Specification change.
The possibility of a new or different kind of accident. from any accident previously evaluated is not created. In matters related. to nuclear safety, all accidents are bounded by previous analysis. The proposed change does not add or modify any equipment or system design nor does it involve any changes in the operation of any plant system. The absence of a hardware change means that the accident initiators remain unaffected, so no unique accident probability is created.
The proposed amendment does not involve a significant reduction in the margin of safety as defined in the basis for any Technical Specification because the proposed amendment will continue to ensure that (1) performance based. audits and assessments shall be in sufficient depth , (2). participating members are satisfied that items under review do not otherwise constitute a concern and (3) all activities required by the Quality Assurance Program meet the criteria of Appendix B, 10 CFR 50. Further, the proposed amendment permits more efficient use of resources which in effect will enable the conduct of more assessments, both special and. diagnostic. In addition to the above, this proposed amendment is consistent with the required audit frequency of 24 months identified in NUREG-0452, "Standard. Technical Specifications for Westinghouse Pressurized Water Reactors." Therefore, the proposed change to the operating license does not involve a significant reduction in the margin of safety as defined in the basis for any Technical Specification.
CONCLUSION On the basis of the above, RG&E has determined. that the amendment request does, not involve a significant hazards consideration.