Similar Documents at Cook |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999
Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5611999-10-11011 October 1999
Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal
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Proposed Tech Specs Re Containment Recirculation Sump Water Inventory
ML17326A1591999-09-23023 September 1999
Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project
ML17326A1461999-09-17017 September 1999
Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality
ML17326A1181999-09-10010 September 1999
Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
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Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
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Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2.
ML17325B6061999-05-21021 May 1999
Proposed Tech Specs Revising Limitations on Positive Reactivity Additions
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5551999-04-19019 April 1999
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ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A3581998-12-0303 December 1998
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ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
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Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
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ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
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ML17335A2341998-09-14014 September 1998
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Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4701996-02-0808 February 1996
In-Service Pump Test Plan, Units 1 & 2
ML17334B5661995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class,1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 1, Final Plan
ML17334B5671995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class 1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 2, Final Plan
ML17332A2521994-08-0303 August 1994
Rev 3 to Plant Manager Procedure (PMP) 12 PMP 3150 PCP.100, Radwaste Pcp.
ML17332A2491994-08-0303 August 1994
Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm.
ML20063K0631994-02-11011 February 1994
Change Sheet 1 to Rev 5 to Plant Manager Procedure (PMP) 12 PMP 6010 RPP.304, Use of HEPA Vacuum Cleaners. W/ Updated Index,Page 14
ML17331B0441993-11-0909 November 1993
Rev 15 to Emergency Response Manual. W/931109 Ltr
ML17334B4851993-08-0909 August 1993
Rev 14 to Emergency Response Manual. W/930809 Ltr
ML17334B4821993-04-0202 April 1993
Rev 3 of Pump Inservice Test Program.
ML17329A5431992-06-11011 June 1992
Change Sheet 7 to Rev 6 to Procedure PMP 2080 EPP.107, Notification of Plant Personnel.
ML20077S7281991-03-14014 March 1991
Rev 3 to PMP 6010.OSD.001, Odcm
ML17325B3791990-03-0101 March 1990
Change Sheet 1 to Rev 3 to Procedure PMP 2080 EPP.106, Initial Offsite Notification.
ML17334B3551990-02-0505 February 1990
Rev 2 to DC Cook Nuclear Plant Units 1 & 2 Inservice Testing Pump Program.
ML17334B3561990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML17334B3571990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML20246M2191989-03-21021 March 1989
Procedure MS-3.2.1.9-1B, Maint & Surveillance Ite Medium Voltage Switchgear Equipment
ML17325B0511988-12-0909 December 1988
Interim Acceptance Criteria for Safety-Related Piping Sys.
ML17334B1491987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML17334B1501987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML20212A3191986-10-0202 October 1986
Rev 1 to Procedure 12 PMP 4021 TRP.001, Reactor Trip Review
ML17324A9301986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.001, Maint Procedure for Repowering RHR Pump.
ML17324A9321986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.003, Maint Procedure for Repowering Pressurizer Backup Heaters.
ML17324A9331986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.005, Maint Procedure for Repowering Containment Valves.
ML17324A9341986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.304, Pressurizer PORV Cable Repair.
ML17324A9351986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.305, App R Post-Fire Repowering of In-Containment Valves.
ML17334A9711986-05-22022 May 1986
Rev 0 to Procedure 12-OHP 4023.100.001, Unit 1 Emergency Remote Shutdown.
ML20213F6011986-05-15015 May 1986
Rev 1 to Procedure PMP 6010.OSD.001, Offsite Dose Calculation Manual
ML17324A9001986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Iv,Training for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8991986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Ii,Writers Guide for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8971986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part I,Specific Technical Guidelines for Donald C Cook Nuclear Plant.
ML18005A0161986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part III, Verification/Validation for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML20195C5361986-03-15015 March 1986
Public Version of Emergency Response Manual for DC Cook Nuclear Plant
ML20141D7121986-02-28028 February 1986
Rev 0 to Master Insp Plan
ML20137J6061985-12-17017 December 1985
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 2 to Erp 2.07, Outside Agency Liaison, Rev 1 to Erp 2.08, Initial Assessment Group Runner & Rev 2 to Erp 5.01.W/860117 Release Memo
ML17334A9441985-11-0505 November 1985
Change Sheet 1 of Rev 9 to Spec DCCFP101QCN, Matl & Application Spec - Initial & Repair Installations, Revising App D Silicon Foam Scope of Work to Identify New Fire Barriers & for Cross Referencing Fire Zones
ML17334A9191985-10-15015 October 1985
Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept
1999-05-07
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Text
ATTACHMENT TOAEP:NRC:0773Q PROCEDURES GENERATION PACKAGEPARTIIIVERIFICATION/VALIDATION FORDONALDC.COOKNUCLEARPLANTEMERGENCY OPERATING PROCEDURES REVISION1MAY1,1986 1li"1IJ0 EOPVERIFICATION/VALIDATION PROGRAMOverviewVerification/Validation (V&V)ofEOPsistheevaluation performed todetermine thattheactionsspecified intheprocedure canbecarriedoutbytheoperatortomanageemergency conditions effectively.
Thisevaluation willbecarriedoutintwophases.Thefirstphase,TableTopReview,willaddressobjectives thataregearedtowardverifying theTechnical adequacyoftheEOPs.Thesecondphase,ControlRoomWalk-Through, willaddressobjectives focusedonthehumanengineering aspectsofthewrittendocument's usability.
Problemareas(hereafter referredtoasdiscrepancies) identified bytheV&Vprocesswillbedocumented, investigated, andresolved.
Itistheintention ofD.C.CooktoperformV&Vofallsignificant modification totheEOP'safterinitialimplementation.
AportionoftheDetailedControlRoomRevieweffortwillbeperformed concurrently withtheV&Vprocesstoaddressthehumanengineering aspectsoftheEOP-operator-hardware interface.
OBJECTIVES Thescopeoftheevaluation accomplished byV&Vwillbedefinedbyaddressing severalcriteria.
Thesecriteriaorobjectives arepresented asfollows,listedundertheprogramphaseduringwhichtheyareaddressed:
TableToReviewThattheEOP'saretechnically correct,i.e.,theyaccurately reflecttheTechnical Guidelines (including sourcedocuments andEOPDocumentation Form).ThattheEOPsarewrittencorrectly, i.e.,theyaccurately reflectthewritersguide.Thatthelanguageandlevelofinformation presentation intheEOP'siscompatible withtheminimumnumber,qualification,
- training, andexperience oftheoperating staff.
ControlRoomWalk-Throu h(Validation)
ThattheEOPsareusable,i.e.,theycanbeunder-stoodandfollowedwithoutconfusion, delays,errors,etc.Thatthereisacorrespondence betweentheEOPsandthecontrolroom/plant
- hardware, i.e.,control/equipment/indications thatarereferenced areavail-able(insideandoutsideofthecontrolroom),usethesamedesignation, usethesameunitsofmeasure,andoperateasspecified intheEOPs.Thatthereisahighlevelofassurance thattheEOPswillwork,i.e.,theprocedure guidestheoperatorinmitigating transients andaccidents.
NOTE:SincetheD.C.CookEOP'swillbebasedonthegenericWesting-houseOwnersGroupEmergency ResponseGuidelines (ERGs)andagenericvalidation hasbeenperformed ontheERGs,thiscriteriawillnotbespecifically addressed.
However,aselectedsetofplantspecificEOPswillbeexercised attheSNUPPSsimulator inZion,Illinois.
Inthisway,anindependent checkofthegenericprogramcanbemadetoinsuretheplantspecificconversion didnotdetractfromtheoverallworkability of.theEOP's.TheEOP'schosenforsimulator validation mettheselection criteriawhichcomplieswiththerecommenda-tionsofNUREG0700(Section3.4.2.2)aswellasthoseneededtoaddresstheimportant areasofemergency operations (eg.,eventdiagnosis, criticalsafetyfunctionmonitoring, highriskeventsequences, etc.)forsystemreviewandtaskanalysispurposes.
Theeventsequences are:Spurioussafetyinjection Lossofreactorcoolant(smallbreakapproximately 1"diameter)
Lossofreactorcoolant(smallbreakapproximately 4"diameter)
Lossofreactorcoolant(largebreak)Lossofsecondary coolantCombinedlossofreactorandsecondary coolantSteamgenerator tuberupture(designbasis)Steamgenerator tuberupture(multiple rupturesinonegenerator)
Anticipated transient withoutscramInadequate corecooling(resulting fromfailuresinemergency corecoolingsystemInadequate corecooling(resulting fromlossofsecondary heatsink)Pressurized thermalshock.
Alloftheeventsequences abovearewithinthecapabilities andlimitations oftheSNUPPSsimulator whenprogrammed withD.C.CookPlantspecificsoftware.
PROGRAMDESCRIPTION EachEOPwillbeexaminedandevaluated stepbystepforcompliance withtheobjectives presented above.Theobjectives arebrokendownintospecificitemstocreateasystematic checklist.
Inorderforanobjective tobesatisfied, eachspecificitemmustbeacharacteristic oftheEOP.Eachobjective isbrokendownasfollows:ThattheEOPsaretechnically correct,i.e.,theyaccurately reflecttheTechnical Guidelines (including sourcedocuments andEOPDocumentation Form).-Areentryconditions orsymptomscorrectly stated?Isthearrangement andcontentofsteps,cautions, andnotessupported byinformation fromsourcedocuments?
-Arecalculated ortranslated quantitative valuescorrect?Istheplant,hardwareidentified bytheEOPavailable fortheoperatortouse?ThattheEOPsarewrittencorrectly, i.e.,accurately reflectthewritersguide.-AretheEOPslegible,i.e.,aregraphsandtablesclearlyreadable, isprintedmaterialvisiblewithinthebordersonallpages?Istheformatconsistent throughout theprocedure set?IsEOPidentification completeandcorrect?Aresteps,cautions, andnotesclearlyandconsistently presented, understandable, anddistinguishable fromeachother?Aretransitions withintheEOPsconsistent andincompliance withtherulesofreferencing andbranching contained inthewritersguide?
That.thelanguageandlevelofinformation presentactionintheEOPsiscompatible withtheminimumnumber,qualification,
- training, andexperience oftheoperating staffwhenwalkthrough andsimulator exercises areconducted withtheminimum(orless)controlroomstaffsizerequiredbyD.C.Cooktechnical specifications.
-AretheEOPsincompatible with.shift,manninglevelsandpolicies?
0ThattheEOPsareusable,i.e.,theycanbeunderstood andfollowedwithoutconfusion, delays,errors,etc.-DotheEOPscontainsufficient information, consistent withtraining, toenabletheoperatortoproperlyexecutetheEOPinstructions?
-Doestheoperatorcomprehend theinformation presented intheEOPs?0Thatthereisacorrespondence betweentheprocedures andthecontrolroom/plant
- hardware, i.e.,control/equipment/indications thatarereferenced available (insideandoutsidetheofcontrolroom),usethesamedesignation, usethesameunitsofmeasure,andoperateasspecified intheEOPs.-AretheEOPscompatible withplanthardwareandplantresponse?
0Thatthereisahighlevelofassurance thattheEOP'swillwork,i.e.,theprocedures guidetheoperatorinmitigating transients andaccidents.
-Again,sincetheD.C.CookplantEOP'sarebasedontheWestinghouse GroupERG's,credit.istakenforvalidation/verification ofthisobjective basedonthegenericERGvalidation.
D.C.Cookwillcheckthisobjective byusingaselectedsetofplantspecificprocedures attheSNUPPSsimulator inZion,Illinois.
Theverification andvalidation processshallbeconducted ontheentiresetofUnitoneEOPs.Duringthegeneration oftheUnittwosetofEOPs,areaswheresignificant differences betweentheunitsresultedindifferent operatorinstructions willbenoted.Theseareaswillthenbesubjected totheentireverification/validation processasdescribed above.
RESPONSIBILITIES TheOperations Department Superintendent (O.S.)willhavetheresponsibility forimplementing theVGVprogramatD.C.Cook.TheOperations Department Procedure Coordinator (P.C)willhavetheresponsibility forconducting theVGVprogram.Department engineers, procedure coordinator andlicensedoperators willtakepartineveryfacetoftheprocess.Theengineers willparticipate (asteammember)inthetabletopreviewsegmentofthereview.Licensedoperators, bothSROandRO,willparticipate (asteammembers)inthetabletopreviewandwalkthroughsegmentsofthereview.TheProcedure Coordinator (SROlicensed) willconducttheVandVprogramassessment andbeateammemberforboththetablereviewandcontrolroomwalkthroughsegments.
Inaddition, wheneverpossible, depart-mentengineers withhumanfactorsbackground willpartici-pateasteammembersforthetabletopreviewandcontrolroomwalkthrough.
Thereviewteamswillberesponsible forverifying objectives aremetanddiscrepancies aredocu-mented.ThePlantNuclearSafetyReviewCommittee (PNSRC)isresponsible forfinalapprovaloftheEOPs.Additional taskresponsibilities areasfollows:TheP.CwilltrainthereviewteamsintheuseoftheV6Uprocedure.
TheP.C.willinterface withtheDetailedControl-Room DesignReviewCoordinator.
TheO.S.andP.C.willresolvealldiscrepancies.
(TheP.Cwillensurethatallresolutions areincorporated asnecessary intotheEOPs.)DISCREPANCY IDENTIFICATION TheultimategoaloftheV&VprogramistoidentifyareaswheretheplantspecificEOPsmaydeviatefromthegenericprocedures, criteriainthewriterguide,andtechnical guidelines, and/orplantcharacteristics orpolicies.
Itistheresponsibility ofthereviewteams,throughtheuseoftheV&Vprocedure, toensurethatobjectives aremet,and/ordiscrepancies documented.
Thereviewteamsshouldalsomakerecommendations toresolvediscrepancies whenappropriate.
6.DISCREPANCY RESOLUTION Onceadiscrepancy isidentified anddocumented, aresolu-tionmustbedeveloped.
Thesolutionwhichresolvesthediscrepancy maytakeanyofvariousforms,e.g.,procedure change,increased operatortraining, hardwaremodification, etc.Inallcases,theresolution willbedocumented.
Whenachangetoaprocedure orhardwareismadetoresolveadiscrepancy, adetermination mustbemadetoindicatewhetherornotthesechangesshouldbereverified orrevalidated.
Thecriteriausedtodetermine thiswillbewhetherornotthechangehasamajorimpactonitemsonthechecklist.
Ifthechangehadamajorimpactonthechecklist itemtheareaoftheprocedure affectedbythechangewillberevalidated/reverified.
Forexample,ifitisdetermined thatasetpointisincorrect, thenthenewsetpointshouldberevalidated toensureitmeetsthewalkthroughchecklist criteriawhichrequires"instrument ranges/scales/units andtolerances" tobe"consistent withtheinstrument valuesstated".Changesthathaveaminorimpact(eg.,typo's,spellingerrors,etc.)onchecklist itemswillnotberevalidated/reverified.
TheV&VonanygivenEOPwillnotbeconsidered complete.
untilalldiscrepancies applicable toitareresolved.
Proposedchangeswillbeevaluated fortheirimpactonotheremergency responsecapabilities.
7.RECORDRETENTION Alldocumentation formsgenerated duringtheV&Vprogramwillbeconsidered partoftheEmergency Procedures andretainedinaccordance withPlantManagersInstruction-2130,PlantRecords.
