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| number = ML071550459
| number = ML071550459
| issue date = 05/09/2007
| issue date = 05/09/2007
| title = Sequoyah April/May 2007 Exam Nos. 05000327-07-301, 05000328-07-301 - Final JPMs (Part 3 of 3). (Section 1 of 4)
| title = April/May 2007 Exam Nos. 05000327-07-301, 05000328-07-301 - Final JPMs (Part 3 of 3). (Section 1 of 4)
| author name =  
| author name =  
| author affiliation = NRC/RGN-II
| author affiliation = NRC/RGN-II
Line 14: Line 14:
| page count = 134
| page count = 134
}}
}}
See also: [[followed by::IR 05000327/2007301]]
See also: [[see also::IR 05000327/2007301]]


=Text=
=Text=
{{#Wiki_filter:Final Submittal(BluePaper)
{{#Wiki_filter:Final Submittal
SEQUOYAH APRIL/MAY2007EXAMEXAMNOS.05000327/2007301AND05000328/2007301
                          (Blue Paper)
APRIL9-11,2007 ANDMAY9,2007 (written)1.Administrative
              SEQUOYAH APRIL/MAY 2007 EXAM
JPMs2.In-plantJPMs3.ControlRoomJPMs(simulatorJPMs)
                  EXAM NOS. 05000327/2007301
                    AND 05000328/2007301
(PR EPARED!REVISEDBY:VALIDATEDBY:
                    APRIL 9 - 11, 2007 AND
APPROVED BY:*JPM 8.1.a Page1o f 10Rev0 SEQUOYAH N UCLEA RPLANT JOB PERFORMANCE M EASURE B.1.a Raise Power to 10-3%O r iginalS ignatures onFile Date!Date!Date!(Operation s T raining Manage r)CO NCURRED:**(Operat ions Representative)
                      MAY 9, 2007 (written)
Date!/*Validationnot
1. Administrative JPMs
required fo r mi nor enhancements
2. In-plant JPMs
, procedure Rev changes t hat do notaffectthe JPM,or individual
3. Control Room JPMs (simulator JPMs)
s tep changesthatdono t affect t he flow of t he JPM.**Operations Concurrence requiredfor
 
new JPMsan d changes tha t affectthe flow o f the JPM(ifnotdrivenbya procedure revision).
 
/(JPM B.1.a Page2o f 1 0 RevO NU CLEAR T RAINING REVIS ION/USAGE LOG Revis i on Descrip tion Pages Prepared/NumberOfRevis ionVD ate Affected Revised Bv: 0 Initialissue
                                                                                        JPM 8 .1 .a
Y 3/08/07 AliRHEvans I I i I v-Specifyif the JPMchange willrequireanother vali dation (Y o r N).Seecove r sheetforcriteria.
                                                                                        Page 1 of 10
JPMB.1.aPage3of10Rev0 (SEQUOYAHNUCLEARPLANT
                                                                                        Rev 0
RO/SRO JOB PERFORMANCE
                  SEQUOYAH NUCLEARPLANT
MEASURE Task: Ra iseReactorPowerto10
                  JOB PERFORM ANCE MEASURE
.3%JAITA task#: 0010190101
                                              B.1.a
,OperatetheControlRodDrive Systemtobringthereactorcritical
                            Raise Power to 10-3 %
0010100101
(
,ManuallyopentheReactorTripBreakerfromtheControiRoom3110140601,Re
                                      Original Signatures on File
spondtoContinuousRodWithdrawalperAOP-C.01
  PREPARED!
KiA Ratings:192008K1.08
  REVISED BY:                                                              Date!
001K5.18 001A3.08 001AK1.01 001AA2.05 3.5/3.6 4.2/4.3 3.9/4.0 3.4'/3.7 4.4/4.6 Task Standard:Reactoristrippedinre
  VALIDATED BY: *                                                          Date!
sponsetouncontrolledrodwithdrawal.In-Pl ant_x Evaluat ion Method: Simulator===================================================================
  APPROVED BY:                                                              Date!
===============
                                (Operations Training Manager)
=(Performer:
  CONCURRED:    **                                                          Date!
NAMEStartTime Performance
                                (Operations Representative)
Rating:SATUNSATPerformanceTimeFinishTime
                * Validation not required fo r minor enha nceme nts, procedure Rev changes that
Evaluator:
                do not affec t the JP M, or individual step changes that do not affect the flow of
/SIGNATURE DATE================================================================================
                the J PM.
===COMMENTS
                ** Operations Concurrence required for new JPMs and changes that affect the
(JPMB.1.a Page 4of10Rev0 SPECIA L INSTRUCTIONSTOEVALUATOR:1.Sequenced stepsidentifiedb
                flow of the JPM (if not driven by a procedure revision).
y a n" s"2.Any UNS AT r equ ire s comments 3.Ensureoperator performsthefollow in g requ ired act ions fo r SELF-CHECKING;
/
a.Identifiesthecorrectunit,train, componen t , et c.b.Reviewsthe intendedact
 
ionande xpected response.c.Comparestheactua l respon setothee xpected response.4.In itialize simulatortoIC-9 1 5.Ensure Aud io-Count RateMult iplierisseto n t he'x t'scale6.Acknow ledgeanyassociatedalarms.
                                                                                                JPM B.1.a
Initi a l izeSimulatortoIC-91 Validation Time: CR.21min s Loca l ToolS/Equ ipm ent/Proce dures Needed: 0-GO-2Mark Up , 0-S O-B5-1 Mark Up , Counts Doublingtab l e , 1 1M Plot References'
                                                                                                Page 2 of 10
Reference Title Rev N o.A.0-GO-2 U nit Startup f romHotSt andbvtoReactor Critical 26 B.0-50*85*1 Contr olRodDrive S vstem 3 2 C.A OP-C.O lRodControl S ystem Malfunction
                                                                                                RevO
1 6READTOOPERATOR
/
DIRECTIONSTOTRAINE E: Iwillex p la inthe initialconditions,andstate t he tasktob e performed.Allcontrolroomstep
                                                NUCLEAR TRAINING
s shallbeperformedforthi s JP M.I willprovideini
                                                REVISION/USAGE LOG
t ialing cue s a nd reportsonotheractionswhend
  Revision                        Desc rip tion                                        Pages      Prepared/
irec tedbyyou.Wh enyoucomp let ethetasks uccessfully , theobject ive fort h i sjobperforman cemea sure willbesat isf ied.Ensureyo u indi catetomewhenyou understa nd y our ass ignedtask.To i nd icate thatyou havecompleted yo ur a ssigned taskreturnthe
  Number                          Of Revis ion                      V        Date    Affected  Revised Bv:
handoutsheet I p ro videdy ou.INITIAL CONDITIONS:Areactor s t artupisin progress in accordance
      0        Initial issue                                        Y      3/08/07      Ali      RH Evans
w ith 0-GO-2, Reactor Startup.The following condit ions e xist:*All shutdow n bank rodsa re fully withdrawn.*Control Bank" 0"isat127steps.*T h e es tima ted cri tica l positioni s 155s teps on Control Bank" 0".*Most rece nt 1 1 M predicts 150 steps o n C ontrolBank0*You areatthe e" doubling o f source range cou nts.*Allpre cautions , lim itations , p rer equ isites and pre ceding steps for perfo rmanceofthe task have been met o r successfull
                                                                                    I
y performed.INITIATING C UES: The U n i t Supervisord
(                                                                  i
irectsyouto cont inue w ith the reactor startup and withdraw control rods t o critical ity and increase power to take critica l data i n accor dance with 0-GO-2, Unit Startup from Hot Standby to Reactor Critical, section 5.2, beginning atStep 55, and 0-SO-85-1 section6.3,s tep 41.You are t o notify th e Unit Supervisorwhen c riticaldata has been taken.
                                                                          I
STEP 1.:[55]((JobPerformance Checklist: STEP/STANDARDIfICRRplottrend indicatesacceptableECC,Theninitiater od withdrawal usingS O-85-1 t o seventhdoubling range(App.C)o r criticality.
              I
STANDARD: Candidate d e ter m ines that 7'''dou bling isapp r o x imat e ly 2400 CPS on eachSRchannel.Determine s that ICRR in dicate s acceptab le ECC (+/-1000 p cm o f e st imated).Initiates rodwithdrawalbyplacing IN-HOLD*OUTswitch1-HS-85-5111 tot heOUTposition.NOTE: Refer to jpm step 3 for critical step on determining
  v - Specify if the JPM change will require another validation (Y or N).
reactoris critical.COMMENTS: Procedure note prior to step 56: Steps5.3(56)th rough 5.3(58)maybe repeated as necessaryifrod motion is stopped prior to reaching doublingrangeor criticality.
      See cover sheet for criteria.
STEP2.[56]Whe nanyofthefollowing conditionsa
 
re met:*SRcountrate reachesorexceedsseventh doublingr ange determined inAppe ndixCo r*B a n k 0 rod s reachfully withdrawnpo
                                                                                                JPM B.1.a
sition or*Operatorso r Reactor Engineer determine that rod motions houl dbestoppedTHENSTOPoutwardrodmotion STAND ARD: Thi sstepwillNOTbeapplicablea
                                                                                                Page 3 of 10
t this time COMMENTS: JP M B.1.a Page5o f 10 RevO SATIUNSAT_S AT_UNSA T St art Tim e__Critical Step_SAT_UNS A T Note: Candidate may stop rod withdrawal
                                                                                                Rev 0
whenP*6is received.WhenP*6is received , action willbetakenper
                                          SEQUOYAH NUCLEAR PLANT
procedure step 62 of D-GO*2
                                                      RO/SRO
STEP3.[57]If Reactor i s critical,thengotoste
(                                        JOB PERFORMANCE MEASURE
p 5.2(59)(NAS tep 5.2(58).-SAT STANDARD: Pe rf ormer determ ine s t he reactor is criticalby observinga stab le-UNS AT startup rat e with n o addition o f positive reactivity prior t o rea ching 10--3%p owerand procedure s tep 58w illbeNA.Cue: If necessary, a sk operatorIf the reactor Is c r itical.Cr itical Step NOTE: If app licant states that the react orIsNOT crit ical,t his i s co nsidered UNSAT performance
  Task:
.CO M MENTS:STEP4.[59]Ifan y o fthefollowing condit ions exist:-SAT*Criticai conditionscannotbe
        Raise Reactor Power to 10.3%
achievedwi thinthe+/-75 0 p cm-UNSAT termination
  JAITA task # :
band o r*Criticalconditionscannotbe achievedwithinthe+
                0010190101, Operate the Control Rod Drive System to bring the reactor critical
/-1000p cm-allowablelimit
                0010100101, Manually open the Reactor Trip Breaker from the Controi Room
s o r,*Criticalco
                3110140601, Respond to Continuous Rod Withdrawal per AOP-C.01
nditions cannot be achievedabo
  KiA Ratings:
verodinsert ionlimitor*Reactor startupmu st beabortedforotherreasons,Thenperfo rmthefollowingtoabort reactor startup:*STOProdwithdrawal*INITIATE insert ion o f controlbanks*PERFORMAppendix D,Actions if reactorstartupmust beaborted*DONOTcontinuethissection STANDARD: Candidate determinesth
                  192008 K1.08    3.5/3.6
is stepdoesNOTapply CO M MENTS:STEP5.[6 0]If reactorissubcritica l with rod s at f u lly withdrawnposit ion,the n-S AT performAppendixEActionsif reactorsubcritical
                001K5.18        4.2/4.3
withrodsfully UNSAT with drawn.-STANDARD: Candidate determ ines th atthisstep is NA COMMENTS: ((---
                001A3.08        3.9/4.0
                001AK1.01        3.4'/3.7
                  001AA2.05      4.4/4.6
  Task Standard :
        Reactor is tripped in response to uncontrolled rod withdrawal.
  Evaluation Method:                    x
                          Simulator _--!O-_~      In-Plant        _
  ===================================================================================
  Performer:
(                                  NAME                                                Start Time
  Performance Rating: SAT              UNSAT          Performance Time                Finish Time
  Evaluator:                                                /
                                  SIGNATURE                  DATE
  ===================================================================================
                                                    COMMENTS
 
                                                                                                                                    JPM B.1.a
                                                                                                                                      Page 4 of 10
                                                                                                                                      Rev 0
  SPECIAL INSTR UCTIONS TO EVALUATOR:
  1. Sequenced steps identified by an "s"
  2. Any UNSAT requires comments
  3. Ensure operator performs the following required actions for SELF-CHECKING;
      a. Identifies the correct unit, train, component, etc.
      b. Reviews the intended action and expected response.
      c. Compares the actual response to the expected response.
  4. Initialize simulator to IC-91
  5. Ensure Audio-Count Rate Multiplier is set on the 'xt ' scale
  6. Acknowledge any associated alarms.
  Initialize Simulator to IC-91
  Val idation Time: CR. 21 mins                          Loca l
  To ol S/Equ ipment/Procedures Needed:
            0-GO-2 Mark Up, 0-SO-B5-1 Mark Up, Counts Doubling table, 11M Plot
  Referenc es'
                            Reference                                                    Title                                          Rev No.
  A.      0-GO-2                                            Unit Startup from Hot Standbv to Reactor Critical                              26
  B.      0-50*85*1                                        Control Rod Drive Svstem                                                        32
  C.      AOP-C.O l                                          Rod Control System Malfunction                                                16
  = = == = = == == = = = = = = = ~ = = = = = == = = == ==== = = = = = === = = = = === === == = = = = = = = = = = = = = = = = = = = = = = = =
                                                            READ TO OPERATOR
  DIRECTIONS TO TRAINEE:
(
            I will explain the initial conditions, and state the task to be performed. All control room steps shall
            be performed for this JPM. I will provide initialing cues and reports on other actions when directed
            by you. When you complete the task successfully, the objective for this job performance measure
            will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate
            that you have completed your assigned task return the handout sheet I provided you.
  INITIAL CONDITIONS:
            A rea ct or startup is in progress in accordance with 0-GO-2 , Reactor Startup. T he following
            conditions exist:
                  *    All shutdown bank rods a re fully withdrawn .
                  *    Co nt rol Bank "0 " is at 127 ste ps .
                  *    T he estimated critical pos ition is 155 steps on Co ntrol Bank "0".
                  *    Most rece nt 11M predicts 150 steps o n Cont rol Bank 0
                  *    You are at the        e" doubling of source range cou nts .
                  *    All pre cautions , lim itations , prerequisites and preceding steps for performance of the
                        task have been met or successfully performed .
    INITIATING CUES:
              The U nit Supervisor directs you to continue with the reactor startup and withdraw control
              rods to criticality and increase power to take critical data in accordance with 0-GO-2,
              Unit Startup from Hot Standby to Reactor Critical, section 5 .2, beginning at Step 55, and
              0- SO-85-1 sectio n 6.3, step 41 .
              You are to notify th e Unit Supervisor whe n critical data has been taken.
 
                                                                                                JPM B.1 .a
                                                                                                Page 5 of 10
                                                                                                RevO
  Job Performance Checklist:
                                            STEP/STANDARD                                      SATIUNSAT
( STEP 1.: [55]    If ICRR plot trend indicates acceptable ECC, Then initiate rod withdrawal  _SAT
                    using SO-85-1 to seventh doubling range (App. C) or criticality.
                                                                                                _    UNSAT
    STANDARD: Candidate determines that 7''' doubling is approximately 2400 CPS on
                    each SR channel. Determines that ICRR indicates acceptable ECC (+/-
                    1000 pcm of estimated). Initiates rod withdrawal by placing IN-HOLD*
                    OUT switch1 -HS-85-5111 to the OUT position.
                                                                                              Start Time_ _
  NOTE: Refer to jpm step 3 for critical step on determining reactor is critical.            Critical Step
  COMM ENT S:
  Procedure note prior to step 56:
  Steps 5.3(56) th rough 5.3(58) may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range or criticality.
  STEP 2. [56]    Whe n any of the following conditions are met:                              _    SAT
                        * SR count rate reaches or exceeds seventh doubling range              _    UNSAT
                          determined in Appendix C or
(                        * Bank 0 rods reach fully withdrawn position or
                        * Operators or Reactor Engineer determine that rod motion should
                          be stopped
                    THEN STOP outward rod motion
    STANDARD : This step will NOT be applicable at this time
      COMMENTS:
  Note :            Candidate may stop rod withdrawal when P*6 is received.
                    When P*6 is received, action will be taken per procedure step 62 of
                    D-GO*2
 
  --------                  -  ._- -_. -    _._--
                                                                                                    JPM B.1.a
                                                                                                    Page 6 of 10
                                                                                                    RevO
  Job Performance Checklist :
                                                  STEP/STANDARD                                    SATIU NSAT
(
  STEP 3. [57]      If Reactor is critical, then go to step 5.2(59) (NA Step 5.2(58).              -    SAT
    STANDARD: Perf ormer determ ines the reacto r is cr itic al by obse rv ing a stable            -    UNSAT
                    startup rat e with no addition of positive reac tiv ity prio r to rea ching
                    10--3%power and procedure step 58 will be NA.
  Cue:      If necessary, ask operator If the reactor Is critical.                                Cr itical Step
  NOTE:    If applicant states that the reactor Is NOT critical , t his is co nsidered UNSAT
            performance.
    CO MMENTS:
  STEP 4. [59]      If any of the following conditions exist:                                      -    SAT
                          *    Criticai conditions cannot be achieved within the +/- 750 pcm        -    UNSAT
                                termination band or
                          * Critical cond itions cannot be achieved within the +/- 1000 pcm
                              - allowable limit s or,
                          * Critical conditions can not be achieved above rod insert ion limit or
                          * Reactor startup must be aborted for other reasons,
(                    Then perfo rm the fo llowing to abort reactor startup:
                            *  STOP rod withdrawa l
                            *    INITIATE insertion of control banks
                            *    PERFORM Appendi x D, Actions if reactor startup must be aborted
                            *    DO NOT cont inue this section
      STA NDARD : Cand idate determines this step does NOT apply
      CO MMENTS:
    STEP 5. [6 0]      If reactor is subcritical with rods at fully withdrawn position, then          -    SAT
                      perform Append ix E Actions if reactor subcritical with rods fully
                      withdrawn.                                                                      -    UNSAT
      STANDARD: Candidate determ ines that this step is NA
      COMMENTS:
 
                                                                                                JPM B.1.a
                                                                                                Page 7 of 10
                                                                                                Rev 0
  Job Performance Checklist:
                                                STEP/STANDARD                                    SAT/UNSAT
( STEP 6. [61]      If the reactor is critical with SUR less than 0.3 DPM, and                        SAT
                                                          4                                    -
                    Intermediate Range NIS <P-6 (1E* %), then perform the following:
                                                                                                -    UNSAT
                          *  If Bank D control Rods are BELOW the fully withdrawn position,
                                then operate control rods to establish a positive SUR of
                                approximately 0.3 DPM.
    STANDARD: Candidate evaluates IR SUR and if necessary, withdraws control
                    bank D to establish a 0.3 DPM SUR
    COMMENTS:
  Procedure not es prior to step 62:
  1. Blo cki ng t he SRM tr ip wi th HS*92-5001 and HS-92-5002 will disable the detector
    outputs and rem ove t he audio count rate signa l
  2. Step 5.3(62) may be performed at time of criti cality , if re~u ired, Sourc e Range
    reactor trip must be BLOCKED before trip set po int of 10 CPS
                              -
  STEP 7. [62]      When annunciator window XA-55*4A, window D-2 is iit, then                  -    SAT
(                          *  Record both Source Range readings                                  -    UNSAT
                          *  Record both Intermediate Range readings
                                                                                              4
                          *  Verify a minimum of 1 IRM channel greater than or equal to 1F %
                              RTP.
                                                                                                Crit ical Step
                          *  Block source range reactor trip by momentar ily placing HS-92-
                              5001 and HS-92-5002 SRM TRIP RESET-BLOCK handswitches
                              to BLOCK.
                          *  Verify annunciator window XA-55-4A, C-1, is lit
                          *  Select NR-45 to record 1 IR and 1 PR channel
                          *  Adjust NR-45 chart speed as desired.
    STANDARD: Acknowledge P*6 annunciator; Record SR and IR indications on MCB,
                      and verify IR indication > 1E,4%.
                      Places both switches in BLOCK, and observes annunciator XA-55-4A-C1
                      Selects one IR and one PR indication on NR-45
  Cue:              If the candidate reports t hat Sour ce Range High Flu x Tri ps have
                      been blocked, ackn owledge and prov ide direction t o raise reac to r
                                        3
                      power t 01x1 0* % p ower t o o bt ain c riti cal data
      COMMENTS:
 
                                                                                                JPM B.l.a
                                                                                                Page 8 of 10
                                                                                                RevO
  Job Performance Checklist:
                                              STEP/STANDARD                                      SAT/UNSAT
  STEP 8. [63]      Ensure PA announcement made to notify plant personnel when                  -    SAT
                    the reactor is critical.
                                                                                                -    UNSAT
    STA NDARD: Announces criticality over the PA system
    COMMENTS:
  Note prior to step 64:
  Whe n T-avg is less t han 551 degrees F and Tavg-Tref dev iation alarm Is lit, SR
  4.1.1.4.b req uires ver ifying lowest T-AVG greater than or equ al to 541 deg rees F at
  least once eve ry 30 minutes.
  STEP 9. [64]      If Tavg-Tref alarm (M-5A window C-6) is lit, and Tavg is less than          -  SAT
                    551 degrees F, Then perform 0-SI-SXX-068-127.0 to satisfy SR
                    4.1 .1.4.b, Minimum Temperature for Criticality.                            -  UNSAT
    STANDARD : Candidate verifies Tavg is 547 degrees F.
  Cue: Another operator_will perform the surveillance
    COMMENTS :
(
  Booth Ins tructor: Insert malf unc tion IMF RD01 f:48 k:1 at t he next rod moti on.
                        Ind ication on 1-M-4, Rod Motion Red or Green Light.
  STEP 10. [65]      RAISE reactor power to approximately 1 X 10.3%:                              -  SAT
                      [65.1] If Bank 0 rods are below fUlly withdrawn position, then operate      -  UNSAT
                              control rods to establish a positive SUR of approximately 0.5 DPM
                              (not to exceed 1 DPM)
    STANDARD: Initiates rod withdrawal by placing IN-HOLD-OUT switch 1-HS-85-                  Critical Step
                      5111 to the OUT position. Ensures SUR is <1 DPM
    COMMENTS :
 
                                                                                        JPM B.1.a
                                                                                        Page 9 of 10
                                                                                        Rev O
  Job Performance Checklist:
                                          STEP/STANDARD                                  SAT/UNSAT
  STE P 11.      Determines that Bank 0 Group 1 is stepping after releasing IN-          -    SAT
                HOLD-OUT switch
                                                                                          -    UNSAT
    STAND ARD : Candidate reports rod movement to SRO or attempts to insert
                Bank 0 rods . Determines rod movement does not stop
  Cue :            /f candidate reports to SRO, acknowledge the report. D/rect
                  the candidate to recommend an action
    COMM ENTS:
  STEP 12.:      Trip the reactor in response to inappropriate continuous rod motion.    -    SAT
    STAN DARD: Cand idate trips the reactor in response to inappropriate continuous rod  -    UNSAT
                  motion.
  Note: Candidate may refer to AOP C.01 for tripping reactor                            Critical Step
    COMM ENTS:
                          -
(
                                                    End of JPM
 
                                        CANDIDATE CUE SHEET
                (TO BE RETURNED TO EXAMI NER UPON COMPLETION OF TASK)
DIRECT ION TO TRAINEE:
      I will explain the initial conditions, and state the task to be performed. All control room
      steps shall be performed for this JPM, including any required communications. I will
      provide initiating cues and reports on other actions when directed by you. Ensure you
      indicate to me when you understand your assigned task. To indicate that you have
      completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
        A reac tor start up is in progress in accordance with 0-GO-2, Reactor Startup. The
        following conditions exist:
            *  All shutdown bank rods are fully withd rawn .
            *  Con trol Bank "D" is at 127 steps.
            *  Th e estimated critical position is 155 steps on Control Bank "D". .
            *  Most Lecent 11M predicts 150 steps on Control Bank D
                                    th
            *  You are at the 6 doubling of source range counts.
            *  All precautions, limitations, prerequisites and preceding steps for perfo rmance of
                the task have bee n met or successfully performed.
INITIATING CUES:
        The Un it Supervisor directs you to continue with the reactor startup and
        withdraw control rods to criticality and increase power to take critical data
        in accordance with 0-GO -2, Un it Startup from Hot Standby to Reactor
        Critical, section 5.2, beginning at Step 55, and 0-50-85-1 section 6.3, step
        41.
        You are to notify the Unit Supervisor when critical data has been t aken.
 
            - - - - -,,-._-,--_..              __._._-_    ..
                                  Sequoyah Nuclear Plant
(
                                            Unit 0
                              General Operat ing Instructions
                                            O-GO-2
          UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL
                                        Revision 0026
                                      Quality Related
                              Level of Use: Continuous
}}
}}

Latest revision as of 05:40, 23 November 2019

April/May 2007 Exam Nos. 05000327-07-301, 05000328-07-301 - Final JPMs (Part 3 of 3). (Section 1 of 4)
ML071550459
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 05/09/2007
From:
NRC/RGN-II
To:
References
50-327/07-301, 50-328/07-301
Download: ML071550459 (134)


See also: IR 05000327/2007301

Text

{{#Wiki_filter:Final Submittal

                          (Blue Paper)
              SEQUOYAH APRIL/MAY 2007 EXAM
                 EXAM NOS. 05000327/2007301
                    AND 05000328/2007301
                    APRIL 9 - 11, 2007 AND
                     MAY 9, 2007 (written)

1. Administrative JPMs 2. In-plant JPMs 3. Control Room JPMs (simulator JPMs)


                                                                                       JPM 8 .1 .a
                                                                                       Page 1 of 10
                                                                                       Rev 0
                  SEQUOYAH NUCLEARPLANT
                 JOB PERFORM ANCE MEASURE
                                              B.1.a
                            Raise Power to 10-3 %

(

                                     Original Signatures on File
 PREPARED!
 REVISED BY:                                                               Date!
 VALIDATED BY: *                                                           Date!
 APPROVED BY:                                                              Date!
                                (Operations Training Manager)
 CONCURRED:    **                                                           Date!
                                (Operations Representative)
               * Validation not required fo r minor enha nceme nts, procedure Rev changes that
               do not affec t the JP M, or individual step changes that do not affect the flow of
               the J PM.
               ** Operations Concurrence required for new JPMs and changes that affect the
               flow of the JPM (if not driven by a procedure revision).

/

                                                                                               JPM B.1.a
                                                                                               Page 2 of 10
                                                                                               RevO

/

                                                NUCLEAR TRAINING
                                               REVISION/USAGE LOG
 Revision                        Desc rip tion                                         Pages      Prepared/
 Number                          Of Revis ion                       V        Date     Affected   Revised Bv:
     0         Initial issue                                        Y       3/08/07      Ali      RH Evans
                                                                                    I

( i

                                                                          I
             I
  v - Specify if the JPM change will require another validation (Y or N).
      See cover sheet for criteria.
                                                                                               JPM B.1.a
                                                                                               Page 3 of 10
                                                                                               Rev 0
                                          SEQUOYAH NUCLEAR PLANT
                                                     RO/SRO

( JOB PERFORMANCE MEASURE

 Task:
        Raise Reactor Power to 10.3%
 JAITA task # :
                0010190101, Operate the Control Rod Drive System to bring the reactor critical
                0010100101, Manually open the Reactor Trip Breaker from the Controi Room
                3110140601, Respond to Continuous Rod Withdrawal per AOP-C.01
 KiA Ratings:
                 192008 K1.08    3.5/3.6
                001K5.18         4.2/4.3
                001A3.08         3.9/4.0
                001AK1.01        3.4'/3.7
                 001AA2.05       4.4/4.6
 Task Standard :
        Reactor is tripped in response to uncontrolled rod withdrawal.
 Evaluation Method:                    x
                         Simulator _--!O-_~       In-Plant        _
 ===================================================================================
 Performer:

( NAME Start Time

 Performance Rating: SAT              UNSAT           Performance Time                 Finish Time
 Evaluator:                                                /
                                  SIGNATURE                   DATE
 ===================================================================================
                                                    COMMENTS
                                                                                                                                    JPM B.1.a
                                                                                                                                     Page 4 of 10
                                                                                                                                     Rev 0
 SPECIAL INSTR UCTIONS TO EVALUATOR:
 1. Sequenced steps identified by an "s"
 2. Any UNSAT requires comments
 3. Ensure operator performs the following required actions for SELF-CHECKING;
      a. Identifies the correct unit, train, component, etc.
      b. Reviews the intended action and expected response.
      c. Compares the actual response to the expected response.
 4. Initialize simulator to IC-91
 5. Ensure Audio-Count Rate Multiplier is set on the 'xt ' scale
 6. Acknowledge any associated alarms.
 Initialize Simulator to IC-91
 Val idation Time: CR. 21 mins                          Loca l
 To ol S/Equ ipment/Procedures Needed:
            0-GO-2 Mark Up, 0-SO-B5-1 Mark Up, Counts Doubling table, 11M Plot
 Referenc es'
                            Reference                                                     Title                                           Rev No.
 A.       0-GO-2                                             Unit Startup from Hot Standbv to Reactor Critical                              26
 B.       0-50*85*1                                         Control Rod Drive Svstem                                                        32
 C.       AOP-C.O l                                          Rod Control System Malfunction                                                 16
 = = == = = == == = = = = = = = ~ = = = = = == = = == ==== = = = = = === = = = = === === == = = = = = = = = = = = = = = = = = = = = = = = =
                                                            READ TO OPERATOR
  DIRECTIONS TO TRAINEE:

(

            I will explain the initial conditions, and state the task to be performed. All control room steps shall
            be performed for this JPM. I will provide initialing cues and reports on other actions when directed
            by you. When you complete the task successfully, the objective for this job performance measure
            will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate
            that you have completed your assigned task return the handout sheet I provided you.
  INITIAL CONDITIONS:
            A rea ct or startup is in progress in accordance with 0-GO-2 , Reactor Startup. T he following
            conditions exist:
                  *    All shutdown bank rods a re fully withdrawn .
                  *    Co nt rol Bank "0 " is at 127 ste ps .
                  *    T he estimated critical pos ition is 155 steps on Co ntrol Bank "0".
                  *    Most rece nt 11M predicts 150 steps o n Cont rol Bank 0
                  *    You are at the         e" doubling of source range cou nts .
                  *    All pre cautions , lim itations , prerequisites and preceding steps for performance of the
                       task have been met or successfully performed .
   INITIATING CUES:
             The U nit Supervisor directs you to continue with the reactor startup and withdraw control
             rods to criticality and increase power to take critical data in accordance with 0-GO-2,
             Unit Startup from Hot Standby to Reactor Critical, section 5 .2, beginning at Step 55, and
             0- SO-85-1 sectio n 6.3, step 41 .
             You are to notify th e Unit Supervisor whe n critical data has been taken.
                                                                                               JPM B.1 .a
                                                                                               Page 5 of 10
                                                                                               RevO
 Job Performance Checklist:
                                            STEP/STANDARD                                      SATIUNSAT

( STEP 1.: [55] If ICRR plot trend indicates acceptable ECC, Then initiate rod withdrawal _SAT

                   using SO-85-1 to seventh doubling range (App. C) or criticality.
                                                                                               _    UNSAT
   STANDARD: Candidate determines that 7 doubling is approximately 2400 CPS on
                   each SR channel. Determines that ICRR indicates acceptable ECC (+/-
                   1000 pcm of estimated). Initiates rod withdrawal by placing IN-HOLD*
                   OUT switch1 -HS-85-5111 to the OUT position.
                                                                                             Start Time_ _
  NOTE: Refer to jpm step 3 for critical step on determining reactor is critical.            Critical Step
  COMM ENT S:
 Procedure note prior to step 56:
 Steps 5.3(56) th rough 5.3(58) may be repeated as necessary if rod motion is stopped
 prior to reaching doubling range or criticality.
  STEP 2. [56]     Whe n any of the following conditions are met:                               _    SAT
                        * SR count rate reaches or exceeds seventh doubling range               _    UNSAT
                          determined in Appendix C or

( * Bank 0 rods reach fully withdrawn position or

                        * Operators or Reactor Engineer determine that rod motion should
                          be stopped
                    THEN STOP outward rod motion
    STANDARD : This step will NOT be applicable at this time
     COMMENTS:
  Note :            Candidate may stop rod withdrawal when P*6 is received.
                    When P*6 is received, action will be taken per procedure step 62 of
                    D-GO*2
 --------                   -  ._- -_. -    _._--
                                                                                                    JPM B.1.a
                                                                                                    Page 6 of 10
                                                                                                    RevO
  Job Performance Checklist :
                                                  STEP/STANDARD                                     SATIU NSAT

(

  STEP 3. [57]      If Reactor is critical, then go to step 5.2(59) (NA Step 5.2(58).               -     SAT
    STANDARD: Perf ormer determ ines the reacto r is cr itic al by obse rv ing a stable             -     UNSAT
                    startup rat e with no addition of positive reac tiv ity prio r to rea ching
                    10--3%power and procedure step 58 will be NA.
  Cue:      If necessary, ask operator If the reactor Is critical.                                Cr itical Step
  NOTE:     If applicant states that the reactor Is NOT critical , t his is co nsidered UNSAT
            performance.
    CO MMENTS:
  STEP 4. [59]       If any of the following conditions exist:                                       -    SAT
                          *     Criticai conditions cannot be achieved within the +/- 750 pcm        -     UNSAT
                                termination band or
                          * Critical cond itions cannot be achieved within the +/- 1000 pcm
                              - allowable limit s or,
                          * Critical conditions can not be achieved above rod insert ion limit or
                          * Reactor startup must be aborted for other reasons,

( Then perfo rm the fo llowing to abort reactor startup:

                            *   STOP rod withdrawa l
                            *    INITIATE insertion of control banks
                            *    PERFORM Appendi x D, Actions if reactor startup must be aborted
                            *    DO NOT cont inue this section
     STA NDARD : Cand idate determines this step does NOT apply
     CO MMENTS:
   STEP 5. [6 0]      If reactor is subcritical with rods at fully withdrawn position, then           -     SAT
                      perform Append ix E Actions if reactor subcritical with rods fully
                      withdrawn.                                                                       -    UNSAT
     STANDARD: Candidate determ ines that this step is NA
     COMMENTS:
                                                                                                JPM B.1.a
                                                                                                Page 7 of 10
                                                                                                Rev 0
 Job Performance Checklist:
                                               STEP/STANDARD                                    SAT/UNSAT

( STEP 6. [61] If the reactor is critical with SUR less than 0.3 DPM, and SAT

                                                          4                                     -
                    Intermediate Range NIS <P-6 (1E* %), then perform the following:
                                                                                                -     UNSAT
                         *   If Bank D control Rods are BELOW the fully withdrawn position,
                               then operate control rods to establish a positive SUR of
                               approximately 0.3 DPM.
    STANDARD: Candidate evaluates IR SUR and if necessary, withdraws control
                    bank D to establish a 0.3 DPM SUR
   COMMENTS:
 Procedure not es prior to step 62:
 1. Blo cki ng t he SRM tr ip wi th HS*92-5001 and HS-92-5002 will disable the detector
    outputs and rem ove t he audio count rate signa l
 2. Step 5.3(62) may be performed at time of criti cality , if re~u ired, Sourc e Range
    reactor trip must be BLOCKED before trip set po int of 10 CPS
                              -
  STEP 7. [62]       When annunciator window XA-55*4A, window D-2 is iit, then                   -     SAT

( * Record both Source Range readings - UNSAT

                          *   Record both Intermediate Range readings
                                                                                             4
                          *   Verify a minimum of 1 IRM channel greater than or equal to 1F %
                              RTP.
                                                                                               Crit ical Step
                          *   Block source range reactor trip by momentar ily placing HS-92-
                              5001 and HS-92-5002 SRM TRIP RESET-BLOCK handswitches
                              to BLOCK.
                          *   Verify annunciator window XA-55-4A, C-1, is lit
                          *   Select NR-45 to record 1 IR and 1 PR channel
                          *   Adjust NR-45 chart speed as desired.
    STANDARD: Acknowledge P*6 annunciator; Record SR and IR indications on MCB,
                     and verify IR indication > 1E,4%.
                     Places both switches in BLOCK, and observes annunciator XA-55-4A-C1
                     Selects one IR and one PR indication on NR-45
  Cue:               If the candidate reports t hat Sour ce Range High Flu x Tri ps have
                     been blocked, ackn owledge and prov ide direction t o raise reac to r
                                       3
                     power t 01x1 0* % p ower t o o bt ain c riti cal data
     COMMENTS:
                                                                                                JPM B.l.a
                                                                                                Page 8 of 10
                                                                                                RevO
 Job Performance Checklist:
                                             STEP/STANDARD                                      SAT/UNSAT
 STEP 8. [63]      Ensure PA announcement made to notify plant personnel when                   -    SAT
                   the reactor is critical.
                                                                                                -    UNSAT
   STA NDARD: Announces criticality over the PA system
   COMMENTS:
 Note prior to step 64:
 Whe n T-avg is less t han 551 degrees F and Tavg-Tref dev iation alarm Is lit, SR
 4.1.1.4.b req uires ver ifying lowest T-AVG greater than or equ al to 541 deg rees F at
 least once eve ry 30 minutes.
 STEP 9. [64]       If Tavg-Tref alarm (M-5A window C-6) is lit, and Tavg is less than           -   SAT
                   551 degrees F, Then perform 0-SI-SXX-068-127.0 to satisfy SR
                    4.1 .1.4.b, Minimum Temperature for Criticality.                             -   UNSAT
    STANDARD : Candidate verifies Tavg is 547 degrees F.
  Cue: Another operator_will perform the surveillance
    COMMENTS :

(

  Booth Ins tructor: Insert malf unc tion IMF RD01 f:48 k:1 at t he next rod moti on.
                       Ind ication on 1-M-4, Rod Motion Red or Green Light.
  STEP 10. [65]      RAISE reactor power to approximately 1 X 10.3%:                              -   SAT
                     [65.1] If Bank 0 rods are below fUlly withdrawn position, then operate       -   UNSAT
                             control rods to establish a positive SUR of approximately 0.5 DPM
                             (not to exceed 1 DPM)
    STANDARD: Initiates rod withdrawal by placing IN-HOLD-OUT switch 1-HS-85-                  Critical Step
                     5111 to the OUT position. Ensures SUR is <1 DPM
    COMMENTS :
                                                                                        JPM B.1.a
                                                                                        Page 9 of 10
                                                                                        Rev O
 Job Performance Checklist:
                                         STEP/STANDARD                                  SAT/UNSAT
 STE P 11.      Determines that Bank 0 Group 1 is stepping after releasing IN-          -     SAT
                HOLD-OUT switch
                                                                                         -    UNSAT
   STAND ARD : Candidate reports rod movement to SRO or attempts to insert
                Bank 0 rods . Determines rod movement does not stop
 Cue :            /f candidate reports to SRO, acknowledge the report. D/rect
                 the candidate to recommend an action
   COMM ENTS:
 STEP 12.:       Trip the reactor in response to inappropriate continuous rod motion.    -    SAT
   STAN DARD: Cand idate trips the reactor in response to inappropriate continuous rod   -    UNSAT
                 motion.
 Note: Candidate may refer to AOP C.01 for tripping reactor                            Critical Step
   COMM ENTS:
                         -

(

                                                    End of JPM
                                       CANDIDATE CUE SHEET
                (TO BE RETURNED TO EXAMI NER UPON COMPLETION OF TASK)

DIRECT ION TO TRAINEE:

      I will explain the initial conditions, and state the task to be performed. All control room
      steps shall be performed for this JPM, including any required communications. I will
      provide initiating cues and reports on other actions when directed by you. Ensure you
      indicate to me when you understand your assigned task. To indicate that you have
      completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

       A reac tor start up is in progress in accordance with 0-GO-2, Reactor Startup. The
       following conditions exist:
           *   All shutdown bank rods are fully withd rawn .
            *  Con trol Bank "D" is at 127 steps.
            *  Th e estimated critical position is 155 steps on Control Bank "D". .
            *  Most Lecent 11M predicts 150 steps on Control Bank D
                                    th
            *  You are at the 6 doubling of source range counts.
            *  All precautions, limitations, prerequisites and preceding steps for perfo rmance of
               the task have bee n met or successfully performed.
INITIATING CUES:
        The Un it Supervisor directs you to continue with the reactor startup and
        withdraw control rods to criticality and increase power to take critical data
        in accordance with 0-GO -2, Un it Startup from Hot Standby to Reactor
        Critical, section 5.2, beginning at Step 55, and 0-50-85-1 section 6.3, step
        41.
        You are to notify the Unit Supervisor when critical data has been t aken.
            - - - - -,,-._-,--_..              __._._-_     ..
                                 Sequoyah Nuclear Plant
(
                                            Unit 0
                              General Operat ing Instructions
                                           O-GO-2
         UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL
                                       Revision 0026
                                      Quality Related
                              Level of Use: Continuous Use

(

  Effective Date:  12-10-2006
  Responsible Organization:     OPS, Operations
  Prepared By:    O. A. Porter
  Approved By:    W. T. Leary
                                 Current Revision Description
  Revised to resolve interface problem with 0-RT-NUC-000-003.0 (PER 115799). Added
  contingency actions if Control Bank 0 reaches full out position. Incorporated various other
  enhancements.
                       THIS PROCEDURE IMPACTS REACTIVITY

(

        SQN           UNIT STARTUP FROM HOT STANDBY 0-GO-2
        Unit 0                TO REACTOR CRITICAL           Rev. 0026

\ Paae 2 of 85

                                        Table of Contents
   1.0  FIRST SECTION                                                     3
   1.1  Purpose                                                           3
   1.2  Scope                                                             3
   2.0  REFERENCES                                                        3
   2.1  Performance References                                            3
   2.2  Developmental References                                          5
   3.0   PRECAUTIONS AND LIMITATIONS                                      6
   3.1   PRECAUTIONS                                                      6
   3.2   LIMITATIO NS                                                     8
   4.0   PREREQUiSiTES                                                    9
   5.0   INSTRUCTIONS                                                    12
   5.1   Actions to be performed prior to a reactor startup              12
 ( 5.2   Reactor Startup after a refueling outage                        21
   5.3   Reactor Startup after a non-refueling outage                    45
   6.0   RECORDS                                                         69
   Appendix A:      DELETED                                              70
   Append ix B:     MODE 3 TO MODE 2,1 REVIEW AND APPROVAL               71
   Ap pendi x C:    DETERMING SOURCE RANGE COUNT RATE DOUBLI NG          79
    Appendix D:     ACTIONS IF REACTOR STARTUP MUST BE ABORTED           80
    Appendix E:     ACTIONS IF BANK D RODS REACH FULL OUT POSITION
                    PRIOR TO CRITICALITY                                 81
                    Source Notes                                         83
      SON            UNIT STARTUP FROM HOT STANDBY               0-GO-2
      Unit 0                TO REACTOR CRITICAL                  Rev. 0026

\"

                                                                 Page 3 of 85
  1.0   FIRST SECTION
  1.1   Purpose
        This General Operating (GO) Instruction provides necessary actions to perform a
        unit startup from hot standby (Mode 3) to reactor critical (Mode 2) following a reactor
        shutdown or initial startup after refueling.
  1.2   Scope
        A.    This GO contains the following sections:
              1.   5.1 Actions to perform prior to commencing reactor startup.
              2.   5.2 Reactor startup after a refueling outage.
              3.   5.3 Reactor startup after a non-refueling outage.
        This instruction also provides guidance for the control of reactivity associated with
        Xenon while the reactor is in a hot standby condition.
( 2.0   REFERENCES
  2.1   Performance References
        A.    0-RT-NUC-000-003.0, Low Power Physics Testing
         B.   0-SI-OPS-000-004.0, Surveillance Requirements Petiormed on Increased
              Frequency with No Specific Frequency
         C.   0-SO-30-5, Lower Compartment Cooling Units
         D.   0-SI-SXX-068-127.0, RCS and Pressurizer Temperature and Pressure Limits
         E.   0-SO-30-6, Control Rod Drive Cooling Units
         F.    1-PI-OPS-000-021 .1 , Mode 1-4 Control Room Operator MCR Duty Station Shift
               Relief and Syst em Status Checklist
         G.    2-PI-OPS-000-023.1 , Mode 1-4 Control Room Operator MCR Duty Station Shift
               Relief and System Status Checklists
         H.    1, 2-S0-3-2, Auxiliary Feedwater System
         I.    1,2-SI-ICC-092-N41.1, Channel Calibration of Power Range Nuclear
               Instrumentation System, Channel N4 1
                                                       ---- -        --
      SQ N           UNIT STARTUP FROM HOT STANDBY               0-GO-2
      Unit 0                TO REACTOR CRITICAL                  Rev . 0026

\. Paqe 4 of 85

  2.1   Performance References (continued)
        J.   1, 2-SI-ICC-092-N42.2, Channel Calibration of Power Range Nuclear
             Instrumentation System, Channel N42
        K.   1, 2-SI-ICC-092-N43 .3, Channel Calibration of Power Range Nuclear
             Instrumentation System, Channel N43
        L.   1,2-SI-ICC-092-N44.4, Channel Calibration of Power Range Nuclear
             Instru mentation System, Channel N44
        M.   0-SI-NUC-000-001.0, Estimated Critical Conditions
        N.   0-SI-NU C-000-038.0, Shutdown Margin
        O.   1, 2-SO-68-2, Reactor Coolant Pumps
        P.   1-PI-OPS-057-001.0, Functional Testing of Low Voltage Bus Cooling Oil Pumps
        Q.    Core-Operating Limit Report
        R.    0-PI-OPS-000-001.0, Initial Startup System Parameter Log

( S. 0-PI-OPS-301-001.0, Plant Computer Point Disablement

        T.    OPDP-4, Ann unciat or Disablement
        U.    SI-53, Specific Iodine Isotopic Activity Concentration and/or DE 1-131
              Determination
        V.    SI-407.2, Radioactive Gaseous Waste Effluent Particulate and Iodine Dose
              Rates from Shield and Auxiliary Building Exhausts (Weekly/ Special) and
              Condenser Vacuum Exhaust (Special)
         W. 0-SI-CEM-030-415 .0, Gaseous Effluent Requirements (Gross Alpha Noble Gas
              and Tritium)
         X.   0-SO-62-7, Boron Concentration Control
         Y.   0-SO-85-1, Control Rod Drive and Rod Position Indication System
         Z.   OPDP-1, Conduct of Operations
         AA. SPP-10.0, Plant Operations Standard Program
         BB. SPP-3.1 , Corrective Action Program
         CC. Technical Requirements Manual, 3.4.7
         DO. Technical Specifications, SR 4.1.1 .4.a
      SQN           UNIT STARTUP FROM HOT STANDBY            0-GO-2
      Unit 0                TO REACTOR CRITICAL               Rev, 0026

( Page 5 of 85

  2.1   Performance References (continued)
        EE. Technical Specifications, SR 4.1.1A.b
  2.2   Developmental References
        A,   GO I-1, Plant Startup from Cold Shutdown to Hot Standby
        B.   GO I-2, Plant Startup from Hot Standby to Minimum Load
        C,   O-GO-2-1, Plant Startup from Hot Standby to Reactor Critical
        D,   FSAR Section 13,5
        E,   SPP-10 A , Reactivity Management Program

( \,

     SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0                  TO REACTOR CRITICAL                    Rev. 0026

( Pa~e 6 of 85

 3.0   PRECAUTIONS AND LIMITATIONS
 3.1   PRECAUTIONS
       A.   Steps of this procedure must be performed sequentially , unless specifically
            stated otherw ise.
       B.   Criticality is indicated by a positive stable startup rate (SUR) with no rod motion.
            Anticipate criticality anytime reactivity changes are being made. Nuclear
            instrumentation shall be monitored very closely in anticipation of unplanned
            reactivity rate of change.
       C.   During the hot standby period, observe the source and intermediate range
            instruments as the Xenon transient progresses to assure that an inadvertent
            return to criticality does not occur.
       D.   Reactor Engineering should be contacted for guidance on core operating
            recommendations during unusual power maneuvers such as startup at end of
            coreJife. [C.8]
       E.    If reactor startup is anticipated prior to reaching the Xenon-free condition, the

( reactor coolant temperature, rod position, and boron concentration may be used

            to account for time dependent changes in Xenon concentration. Conditions
             should be close ly monitored to ensure that shutdown margin requirements of
             0-SI-NUC-000- 038.0 are maintained at all times. If desired, shutdown rods may
             be withdrawn in accordance with COLR specifications to provide immediate
             insertion poison for a reactivity excursion. [C.12]
       F.    To preserve the life of 20 AST and 20 ET, power must be removed from the
             turbine trip Bus A and trip bus B if unit startup is extended.
        G.   During the approach to criticality Operators shall not be distracted by activities
             such as shift turnover and surveillance testing . [SQ99 0136PER]
        H.    US / SRO Oversight for control rod manipulation shall include :
              1.   Prior to Rod Movemen t
                   a.    Ensure RPI's within T.S. range (+ or - 12 steps)
                   b.    Verify on target with Rx Eng reactivity balance sheet
                         or withi n limits of Estimated Critical Condition (as appli cable)
                   c.    Ensure procedural requirements met.
                   d.    Ensure no simultaneous reactivity manipulations in progress.

\


_.

      SQN          UNIT STARTUP FROM HOT STANDBY                0-GO-2
      Unit 0              TO REACTOR CRITICAL                   Rev. 0026

( Page 7 of85

  3.1   PRECAUTIONS (continued)
             2. During Rod Movement
                a.   Ensure RO has peer check
                b.   Ensure RO is following procedure
                c.   Ensure RO understands criteria for stopping rod motion (based upon
                     number of steps and/or nuclear instrument response)
                d.   Watch performance of rod manipulation while listening to audible
                     indication of rod step
                e.   Ensure peer checking meets expectations (OPDP-1)
                f.   Re-verify items of initial evaluation (on previous page)
                g.   Monitor plant for expected response

(

     SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0                 TO REACTOR CRITICAL                   Rev. 0026

( Page 8 of 85

 3.2   LIMITATIONS
       A.   Simultaneous reactivity addition by rod withdrawal and dilution is NOT allowed
            while in the source range.
       B.   If at any point during the approach to criticality , ONE of the two source range
            dete ctors shows an unexplained increase in count rate equal to or greater than
            a factor of 5, or if BOTH source range detectors show an unexplained increase
            in count rate equal to or greater than a factor of 2, the approach to criticality
            shall be SUSPENDED IMMEDIATELY (i.e., all rod withdrawals and/or boron
            dilutions shall be terminated). Further positive reactivity changes shall not be
            resumed until an evaluation is performed and the Shift Manager authorizes a
            resumption in the approach to criticality.
       C.   After refue ling operations, the NIS indications may be inaccurate until
            calibration at higher power levels. The NIS calibration procedures will adjust
            the PRM trip set points to ensure that the excore detectors do not contribute to
             an overpower condition. Prior to startup , the PRM high range flux trip setpoint
            will be adjusted from 109 to 60%, with the rod stop (C-2) remaining at 103%.
             [C.3j -                        .
       D.    Whil e in Mode 3, maintain the Reactor Coolant System boron concentration in

( accordan ce with 0-SI-NUC -000-038.0, Shutdown Margin requirements.

        E.   The stepping or tripping of the Control Rod during periods when coolant crud
             level are high should be kept to a minimum. This will limit the possibil ity of
             CRDM mis-stepping due to crud contamination of CRDM latch assemblies.
        SQN            UNIT STARTUP FROM HOT STANDBY             0-GO-2
       Unit 0                 TO REACTOR CRITICAL                Rev. 0026

( Paae 9 of 85

'"
          STARTUP No.       leo'                  Unit   I                      Date ~cIay
   4.0    PREREQUISITES
                                              NOTES
    1) Throughout this Instruction where an IF/THEN statement exists, the step should be
       N/A'd if the condition does not exist.
    2) Prerequisites may be completed in any order.
    3) Management oversight is required for a Reactor Startup after a non-refueling outage.
       A Reactor Startup after a refueling outage is a CIPTE.
          [1 ]    ENSURE Instruction to be used is the latest copy of effective
                  version .
          [2]     R~VIEW    Precautions and Limitations.
                  INDICATE below which instruction this 80

( [3]

                  is being entered from:
                  *    0-GO-1 (cold shutdown to hot standby)
                  *    0-80-6 (30% reactor power to hot standby)
                  *    0-80-7 (hot standby to cold shutdown)
                  *    0-80-5 (normal power operation)
           [4]     MAINTAIN pressurizer pressure within the normal operating
                   band by use of the pressurizer heaters and spray valves .
           [5]     MAINTAIN pressurizer level greater than or equal to 25%.
           SQN                 UNIT STARTUP FROM HOT STANDBY                O-GO-2
           Unit 0                     TO REACTOR CRITICAL                   Rev. 0026
                                                                            Page 10 of 85
              STARTUP No.           Iill                   Unit    I
     4.0      PREREQUISITES (co ntinued)
                                                       NOTE
      Due to instrument inaccuracies the steam dump or SG atmospheric relief valve setpoint of
      84% or 1005 psig may be +/- 1% or +/- 12 psig off.
              [6]       MAINTAIN TAVG stable at 547°F with steam dumps
                        in pressure mode or with SG atmospheric relief valves.
              [7]       MAINTAIN SG levels within the normal operating range
                        using Auxiliary Feedwater.
              [8]        ENSURE all reactor coolant pumps are in operation in
                        aceordance with 1,2-S0 -68-2, Reactor Coolant Pumps. [C.12]

( [9] IF the reactor vessel head has been removed,

                        THEN
                         ENSURE conditional performance of 0-SI-SXX-085-043.0,
                         Rod Drop Time Measurements, has been performed
                         to comply with SR 4.1.3.4.a.
               [10]      REQUEST Periodic Test Coordinate to confirm that the
                         followi ng checklists have been distributed:
                    [10.1]      Mode 3 to Mode 2, 1, Surveillance Checklist
                                 (NA if previously performed for this startup).
                    [1 0.2]      Reactor Trip Breaker Checklist (NA if previously
                                 performed for this startup).
                [11]      ENSURE East Valve Vault Room Vent Chute dampers OPEN.
                          (inside door near SPING Room, Ref. PER 03-002446-000).
                [1 2]     NOTIFY MIG to re-scale LR-3-43A and LR-3-98A, Steam
                          Generator Wide Range Level Recorders, to 80% - 90%.

\. ..

      SQN             UNIT STARTUP FROM HOT STANDBY 0*GO*2
      Unit 0                 TO REACTOR CRITICAL             Rev. 0026

( Paqe 11 of 85

        STARTUP No . /0/                     Unit   I                      Date~
  4.0   PREREQUISITES (continued)
        [13]      ENSURE each performer documents their name and initials:
               Print Name           Initials          Print Name            Initials
         :>. .t. f.I tt>-        J'.m/"
                t
                    -

(

                                      END OF TEXT

\.

       SON             UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                 TO REACTOR CRITICAL                 Rev. 0026

( Paae 12 of 85

         STARTUP No.        11821                Unit     I                     Date Tudry
 5.0     INSTRUCTIONS
 5.1     Actions to be performed prior to a reactor startup
         [1]     ENSURE Section 4.0. Prerequisites complete.
                                              NOTE
  Steps 5.1[2] through 5.1[11] may be performed in any order.
         [2]     INTIATE Appendix B, * Mode 3 to Mode 2,1 Review And
                 Approval while continuing with this instruction.
          [3]    OBTAIN assistance from Systems Engineering to complete
                 Appendix B steps associated with Pressurizer Spray line
                 bypass valves.

(

                                              NOTE
  Steps for MFPT startup may be performed in parallel with other activities. The MFPT trip
  busses shall be energized prior to entering Mode 2 (LCO 3.3.2.1 or 3.3.2) except as
  allowed by LCO 3.0.4. [C.1]
          [4]     INITIATE applicable section(s) of 1, 2-S0-2/3-1 to prepare
                  at least one MFP for startup. while continuing with this
                  instruction. (N/A if no MFPT available)
           [5]    ENSURE TDAFW LCVs are in NORMAL.
                                                                                2fK     AfIdP
                                                                                 1st       IV
        SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                   TO REACTOR CRITICAL                 Rev. 0026

( Page 13 of 85

         STARTUP No.          /at::t                U n it~/<--_                   Date ~
 5.1     Actions to be performed prior to a reactor startup (conti nued)
                                              CAUTION
  Rapid changes in pressurizer enclosure temperatu re may result in pressurizer safety
  valve simmer.
          [6]      IF lower compartment coolers are not in service.
                   THE N
               [6.1]      ALIGN lower compartment coolers to maintain
                          pressurizer enclosure temperature less than 110°F
                          in accordance with 0-SO-30-5 .
               [6.2]      MONITOR Pressurizer enclosure temperature
                       _ using Plant Computer pt. T1001A.

( [7] IF control rod drive coolers are not in service,

                   THEN
               [7.1 ]     ALIGN control rod drive coolers to maintain
                          shroud enclosure temperature less than 164°F
                          in accordance with 0-SO-30-6.
               [7.2]       MONITOR Reactor Cavity Air temperature
                           using Plant Computer pt. T1014A.
                                                 NOTE
   New analysis is not required for this startup. Routine analysis is sufficient unless there is
   reason to suspect chemistry has been changed.
           [8]      NOTIFY Chemistry Supervisor that mode change from 3 to 2
                    requires sampling in accordance with 0-SI-CEM-000-050.0.
                    0-SI-CEM-030-407.2, and 0-SI-CEM-030-415.0 requirements.
        SQN            UNIT STARTUP FROM HOT STANDBY 0-GO*2
       Unit 0                   TO REACTOR CRITICAL                Rev. 0026

( Paae 14 of 85

          STARTUP No.         /4c:f               Unit ~/,---_                     Date   7<<IA.{
 5.1      Actions to be performed prior to a reactor startup (continued)
                                              NOTE
  To prese rve the life of 20 AST and 20 ET, power must be removed from turbine trip bus A
  and trip bus B if unit startup is extended.
           [9]    ENERGIZE main turbine trip buses by CLOSING
                  the following breakers (NA breakers not applicable):
  UNIT       TRA IN          BREAKER            250V DC      POSITION             INITIA LS
          TRA IN A       1-BKRD-47-KA/516      BAIT Bd 1      CLOSED
                                                                             RIle
                                                                               1st
                                                                                           buR
                                                                                            CV
     1
                                                                             i lK          IfW?
           TRAIN B l- 1-BKRD-47-KB/516         BAITBd 2       CLOSED
                                                                             * 1st          CV
                                                                             llh:-         At",;

( 2

           TRAIN A       2-BK RD-47-KA/519     BAIT Bd 1      CLOSED            1st         CV
                                                                              ,;,nr
           TRAIN B       2-BKRD-47-KB/519      BAITBd 2       CLOSED            1st
                                                                                          -*
                                              NOTE
   Step 5.1[10] may be marked N/A if not required.
            [10]   PERFORM 0-PI-OPS-047-723.0, 20/AS T, 20/ET, 20-1/0PC,
                   and 20-210 PC Operability Verification (N/A if not performed).
        SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                 TO REACTOR CRITICAL                  Rev. 0026

( "

                                                                   Page 15 of 85
          STARTUP No.       IMI                   Unit      1                      Date~
 5.1     Actions to be performed prior to a reactor startup (con ti nued)
                                            CAUTIO N
  Operation of t he H ic pumps w ithout the t urbin e being reset w ill result in
  overheating of the EHC fluid and pu mps.
                                               NOTE
  Startup of EHC and turbine reset may be postponed until later in startup, (N/A if
  postponed )
          [11]   ENSURE EHC system in service in accordance with
                 1,2-5 0 -47-2 (NA if previously performed),
          [12]   IF 1'\0 MFPT is ready for start up per 1,2-8 0-2/3-1 ,
                 THEN
                 GO TO Section 5,1[18].

(

          [1 3J  ENSURE MFPT designated for startup has been tested
                 and ready for start up per 1, 2-80-2/3-1
                 PRIOR to proceeding with the next step ,
                                                                         J
                                                      'll~
                                                      sa<<             /1Xf &c+----   61n le-£
                                                     Initials           Datr           Time
        SQN           UNIT STARTUP FROM HOT STANDBY 0-GO*2
       Unit 0               TO REACTOR CRITICAL                   Rev. 0026

( Page 16 of 85

          STARTUP No. / tA:I                     Unit     I                       Date  7 m411:\
 5.1      Actions to be perform ed prior to a reac to r start up (cont in ued)                 I
                                             NOTES
  1)  Steps for MFPT startup may be performed in parallel with other activities. The MFPT
      trip busses shall be energized prior to entering Mode 2 (LCO 3.3.2.1 or 3.3.2) except
      as allowed by LCO 3.0.4. [C.1]
  2)  Power is placed on only ONE MFPT trip bus in Step 5.1[14] to prevent inadvertent
      AFW P start .
          [14]  ENSURE power restored to ONLY ONE of MFPT trip busses
                on the applicable unit: (N/A breakers not applicable.) [C.1]
                                          ELECTRICAL        BREAKER
      PUMP            BREAKER NO.                                                INITIALS
                                             BOARD          POSITION
                                             250v DC                         MId         Zj/tr
     MFPT 1A        1-BKRD-46-KN523        Battery Bd I      CLOSED            1st        CV

(

                                                                             ~st
                                             250v DC                                       'P
     MFPT 1B        1-BKRD-46-KN524         Battery Bd I     CLOSED                       CV
                                             250v DC                                       ;,-
     MFPT 2A        2-BKRD-46-KB/523       Battery Bd 2      CLOSED
                                                                               At/"
                                                                               1s         CV
                                             250v DC                                      'b
     MFPT 2B        2-BKRD-46-KB/524       Battery Bd 2      CLOSED            Ht         CV
              --_._--                -
         SQN            UNIT STARTUP FROM HOT STANDBY             0-GO-2
        Unit 0                  TO REACTOR CRITICAL               Rev. 0026

( Paae 17 of 85

           STARTUP No.       1(;(;)(               Unit    I                      Date  ~
 5.1       Actions to be performed prior to a reac tor startup (continued)
                                             CAUTION
  Failure to rese t a MFPT prior to energizing t he remaining MFPT trip buss will in itiate
  an ESF actuation.
                                                NOTE
  If 51 signal or Hi/Hi stea m generator level has occurred, Reactor Trip Breakers will have to
  be cycled .
           [15]    RESET MFPT energized in step 5.1[14] above.
                                                                             ~odtrx. 7rley
                                                           1st               Time          Date
                                                           CV

(

                                                NOTE
   IF the remaining NON-running MFPT is not available, THEN N/A step 5.1[16] and 5.1[17]
            [16]   RESTORE power to remaining MFPT Trip Bus
                   on applicable unit. (N/A breakers not applicable)
                                             ELECTRICAL        BREAKER
       PUMP           BREAKER NO.                                                 INITIALS
                                                BOARD          POSITION
     MFPT 1A        1-BKRD-46-KA/523
                                            250v DC Battery
                                                  Bd I          CLOSED
                                                                              AJ{#
                                                                                 st
                                                                                           '9>
                                                                                           CV
                                            250v DC Battery                   /'4'       -II/f(£
     MFPT 1B        1-BKRD-46-KA/524              Bd I          CLOSED          1st        CV
      MFPT 2A       2-BKRD -46-KB/523
                                            250v DC Battery
                                                  Bd 2          CLOSED
                                                                               /1/11
                                                                                1~t
                                                                                             '9
                                                                                           CfJ
                                            250v DC Battery
      MFPT 2B       2-BKRD- 46-KB/524             Bd 2          CLOSED          1st        OV
        SQN             UNIT STARTUP FROM HOT STANDBY             0-GO-2
       Unit 0                   TO REACTOR CRITICAL               Rev. 0026

( Page 18 of 85

          STARTUP No. /(D I                        Unit    I                    Date 7dJ~
 5.1      Ac tions to be performed prior to a reactor startup (continued)
          [17]     RESET MFPT energized in step 5.1 [16] above.
                                                  _--Ji'M:'----_ _ &A1ti!q
                                                           1st              Time      'fJ~7
                                                                                       Date
                                                           CV
                                                                           00In
                                                                            Time
          [18]     SELECT one source range channel and one intermediate
                   range channel with the highest readings to record on NR 45.
          [19]     ENSURE audio count rate channel is in operation and selected
                   for source range channel with highest reading. [C.1 1]
          [20]     ENSURE all reactor first out alarms reset.

(

                                                NOTE
  Refer to 1-PI-OPS-000-021.1 (Unit 1) or 2-PI-OPS-000-023.1 (Unit 2) for updating the Plant
  Computer.
           [21]    IF ICS is available.
                   THEN
                    ENSURE Plant Computer is reset and updating
                    (NA if previously performed). [C.5]
                                                NOTE
   Closing of the RTB's for performance of 0-SI-OPS-085-01 1.0 (SR 4.1.3.3) is addressed in
   Licensing and NRC TelephoneNisit Report RIMs # S10 960521 800.
           [22]     IF 0-SI-OPS-085-011.0 is out-of-frequency,
                    THEN
                [22.1]     CLOSE RTB's provided Group Demand counters have
                           no known deficiencies.                                       Q""'"
                [22.2]     PERFORM 0-SI-OPS-085-011.0 (NA if above step
                           cannot be performed).
       saN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                  TO REACTOR CRITICAL               Rev. 0026

( Page 19 of 85

         STARTUP No. /Ql)1                        Unit   I                      Date~
 5.1     Actions to be periormed prior to a reactor startup (continued)
         [23]     IF control rods were withdrawn 5 steps to prevent thermal
                  lockup during RCS heatup,
                  THEN
                  INSERT control rods in accordance with 0-SO-85-1.
         [24]     ENSURE Rod Bank Update completed
                  by performing the following:
             [24.1]      DEPRESS NSSS and BOP button on ICS main screen.
             [24.2]      DEPRESS ROD BANK UPDATE Button
                         AND
                         ENSURE all bank positions are zero.
              [24.3] _ DEPRESS F3 to save these rod bank positions.
          [25]    VERIFY Rod Bank Update status by performing the following:

(

              [25.1]     DEPRESS NSSS and BOP button on ICS main screen.
              [25.2]     DEPRESS ROD INSERTION LIMIT DISPLAY Button.
              [25.3]     VERIFY Rod Bank Update Status indicates "UPDATED"
                         in green letters.
                                               NOTE
  TI-28 defines fully withdrawn position.
          [26]     IF shutdown rods are inserted.
                   THEN
                   PERFORM the following :
               [26.1]    VERIFY sufficient shutdown reactivity exists
                          USING 0-SI-NUC-000-038.0, Shutdown Margin.
               [26.2]     WITHDRAW Shutdown Rods to fully withdrawn position
                          in accordance with 0-SO-85-1.
                                                                              1st   CV
   FROM : SEQUC YAH OPERATOR TRA I NI NG          PHONE NO.       423 843 4339            Hpr-, 04 2007 02 : 00PM P3

( saN UNIT STARTUP FROM HOT STANDBY 0-GO-2

.r --,             UnitO                    TO REACTOR CRITICAL                   Rev. 0026
                                                                                  PaCle 26 of 85
                     STARTUP No. /()c) I                          Uni t '                        Date~
            5.2      Reactor Startup after a refueling outage (continued)
            I                                              CAUTION
            ~) NOT exceed a steady startup rate of +1 DPM.
                                                                                                                I
            ~                                                 NOTE
            l~l1e unit enters Mode 2 when the control banks are first withdrawn.
                                                                                                                II
                      [17]     INITIATE a reactor startup by performing the following:
                          [17.1]    . RECORD both source range readings
                                      for ICRR base counts.
                                   N-31 .2~ CPS                        N-32   /1   CPS              Lk
                                                                                                    Initials

( [17.2] RECORD intermediate range readings.

                                   N-35/..3X(~~10                      N-36Plxt,*f,                -2IIIL-
                                                                                                    Initials
                           [1 7,3J     CALCULATE initial source range count doubling value
                                       USING Appendix C.
                                                             MODE 2
                            [17.4]     INITIATE withdrawal of control banks in accordance
                                       with o-SO-85-1 t o first stop' point:
                                    _    CONTROL
                                            _ _-    BANK -A- - I            128 STEPS      .J
                            [17.5]     ENSURE Mode 2 entry is logged
                                       (log entry may be performed out of sequence late-) ,                 o
 *'
          SQN               UNIT STARTUP FROM HOT STANDBY               0-GO-2

( Unit 0 TO REACTOR CRITICAL Rev. 0026

                                                                        Pa!le 26 of 85
            STARTUP No. ,/()p{                          Unit      /
    5.2     Reactor Startup after a refuel ing outage (continued)
                                                 CAUTION
     Do NOT exceed a steady startup rate of +1 DPM.
                                                    NOTE
     The unit enters Mode 2 when the cont rol banks are first withdrawn.
             [17]     INITIATE a react or startup by perform ing the following :
                 [17.1]      RECORD both source range readings
                             for ICRR base co unts.
                           N-31{.27~CP5                     N-32/$oc)CP5                .?/Ie:
                                                                                       Initials
                  [17.2]     RECORD inte rmediate range readings .

(

                           N-35 t 3k ~~fo                    N-36 t4",rfo                &tr
                                                                                       Initials
                  [17 .3]    CALCULATE initial source range count doubling value
                              USING Append ix C.
                                                   MODE 2
                  [17.4]      INITIATE withdrawal of control banks in acco rdance
                              with 0-50-85-1 to first stop point:
                                CONTROL BANK A                   128 STEPS
                   [17 .5]    ENSURE Mode 2 entry is logged
                              (log entry may be performed out of sequence later),              o
       SQN            UNIT STARTUP FROM HOT STANDBY 0*GO-2
      Unit 0                  TO REACTOR CRITICAL                  Rev. 0026
                                                                   Page 27 of 85
         STARTUP No. IIXJ!                        Unit_-s-_I                     Date~
 5.2     Reactor Startup afte r a refueling outage (continued)
         [18]    WHEN control bank A is at 128 steps,
                 THEN
                 PERFORM the following:
             [18.1]    STOP rod withdrawal.
             [1 8.2]   WAIT for approximately two minutes.
             [18.3]     NOTIFY Rx Engineering to perform ICRR calculation
                        in accordance with 0-RT-NUC-000-003.0. [C.11]
                                            CAUTIO N
  Lowest loop T*avg mus t be verified greater than or equ al to 541°F
  using 0*SI-SXX*068-127.0 within 15 minutes prior to achieving cr iticality.

( NOTES

   1) Approximately five to seven count doublings are expected to result in criticality.
      However, criticality should be anticipated at any time.
   2) Proper bank overlap must be verified using 0-80-85-1 as each successive rod bank
      is withdrawn.
          [19]    WHEN concurrence obtained from Rx Engineering,
                  THEN
                  INITIATE rod withdrawa l to first count doubling
                  (determined in App. C) USING 0-80-85-1.
            SQN               UNIT STARTUP FROM HOT STANDBY 0-GO-2
           Unit 0                      TO REACTOR CRITICAL               Rev. 0026
                                                                         Pace 28 of 85

\ ..

              STARTUP No. /<<';1                                    I
                                                           Unit_--L.._                 Date~
    5.2       Reactor Startup afte r a refuel ing outage (con tinued)
                                                       NOTE
     Steps 5.2[20] and 5.2[21] may be repeated as necessary if rod motion is stopped
     prior to reaching doubling value.
              [20]     WHEN any of the following conditions are met:
                       *      Source range count rate is approximately equal to
                              first doubling value determined in Appendix C
                              OR
                       *      Control bank being withdrawn reaches 128 steps
                              (requires verifying overlap in 0-SO-85-1 )
                              OR
                       *      Operators or Rx Engineer determine that rod motion
                              should be stopped
(                      THEN
                       STOP outward rod motion.
               [21]    IF rod motion was stopped prior to reaching doubling range
                       AND Unit Supervisor concurrence is obtained to resume,
                       THEN
                        RESUME rod withdrawal to first count doubling
                        USING 0-8 0-85-1.
               [22]     IF source range count rate has reached or exceeded
                        first doubling,
                        THEN
                        PERFORM the following:
                    [22.1]       ENSURE rod motion STOPPED.                               nrti
                                                                                          *
                    [22.2]       WAIT approximately 2-3 minutes
                                 to allow count rate to rise.
                    [22.3]       NOTIFY Rx Engineering to perform ICRR calculations in
                                 accordance with O-RT-NUC-000-003.0. [C.11]
                    [22.4]       DETERMINE new count doubling range
                                  USING Appendix C.
        SQN           UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Uni t 0                 TO REACTOR CRITICAL                    Rev. 0026
                                                                      Page 29 of 85
          STARTUP No.       ,Ity;(                  Unit_.L-_ I                     Date~
 5.2      Reactor Startup after a refueling outage (continued)
          [23]   IF IGRR plot indicates criticality will fall outside
                 +/- 1000 pcm EGG termination band,
                 THEN
              [23.1 ]   NOTIFY SM and Duty Plant Manager.
              [23.2]    EVALUATE if EGG should be recalculated
                        prior to continuing startup.
              [23.3]    IF startup must be aborted,
                        THEN                                                           ~
                        PERFORM Appendix D, Actions if Reactor Startup Must
                        Be Aborted.                                                    ' '-J
                                                                                         f-1
           [24]   WI:IEN concurrence obtained from Rx Engineering,
                  THEN
                  INITIATE rod withdrawal to second doubling range

( (determined in App. G) USING 0-SO-85-1.

                                                NOTE
  Steps 5.2[25] and 5.2[26] may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range.
           [25]   WHEN any of the following conditions are met:
                  *    Source range count rate reaches or exceeds
                       second doubling range determined in Appendix G
                       OR
                   *   Control bank being withdrawn reaches 128 steps
                       (requires verifying overlap in 0-SO-85-1)
                       OR
                   *   Operators or Rx Engineer determine that rod motion
                       should be stopped
                   THEN
                   STOP outward rod motion.
       SQN              UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                   TO REACTOR CRITICAL

c Rev. 0026

                                                                        Page 30 of 85
         STARTUP No. /          cal                  Unit_4-_    I
   5.2   Reactor Startup after a refueli ng outage (continued)
         [26]     IF rod motion was stopped prior to reaching doubling range
                  AND Unit Supervisor concurrence is obtained to resume,
                  THEN
                  RESUME rod withdrawal to second doubling range
                  USING 0-SO-85-1.
         [27]     IF source range count rate has reached or exceeded
                  second doubling range,
                  THEN
                  PERFORM the following:
              [27.1]     ENSURE rod motion STOPPED.                                   WE
                                                                                      *
              [27.2]     WAIT approximately 2-3 minutes
                       _ to allow count rate to rise.
              [27.3]     NOTIFY Rx Engineering to perform ICRR calculations in

c [27.4]

                          accordance with 0-RT-NUC-000-003.0. [C.11]
                          DETERMINE new count doubling range
                          USING Appendix C.
          [28]     IF ICRR plot indicates criticality will fall outside
                   +/- 1000 pcm ECC termination band,
                   THEN
               [28.1]     NOTIFY SM and Duty Plant Manager.
               [28.2]     EVALUATE if ECC should be recalculated
                          prior to continuing startup.
               [28.3]     IF startup must be aborted,
                          THEN
                          PERFORM Appendix D, Actions if Reactor Startup Must
                          Be Aborted.
           [29]     IF ICRR plot trend indicates acceptable ECC,
                   THEN
                    INITIATE rod withdrawal to third doubling range
                    (determined in App. C) USING 0-SO-85-1.

\..

         SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
        Unit 0                    TO REACTOR CRITICAL               Rev. 0026

( Page 31 of 85

           STARTUP No.          IfX;JI                 Unit   I
 5.2       Reactor Startup after a refueling outage (continued)
                                                   NOTE
  Steps 5.2[30] and 5.2[31] may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range.
           [30]     WHEN any of the following conditions are met:
                    *    Source range count rate reaches or exceeds
                         third doubling range dete rmined in Appendix C
                         OR
                    *     Control bank being withdrawn reaches 128 steps
                          (requires verifying overlap in 0-SO-85-1)
                          OR
                    *     Operators or Rx Engineer determine that rod motion
                          should be stopped

( THEN

                    STOP outward rod motion.
            [31]    IF rod motion was stopped prior to reaching doubling range
                    AND Unit Supervisor concurrence is obtained to resume,
                    THEN
                    RESUME rod withdrawal to third doub ling range
                     USING 0-SO-85-1 .
            [32]     IF source range count rate has reached or exceeded
                    third doubling range,
                    THEN
                     PERFORM the following:
                 [32.1]     ENSURE rod motion STOPPED.
                 [32.2]     WAIT approximately 2-3 minutes
                            to allow count rate to rise.
                 [32.3]     NOTIFY Rx Engineering to perform le RR calculations in
                            accordance with 0-RT-NUC-000-003.0. [C.11]
                 [32.4]     DETERMINE new count doubling range
                            USING Appendix C.
        SQN              UNIT STARTUP FROM HOT STANDBY 0-GO-2
        Unit 0                     TO REACTOR CRITICAL                 Rev. 0026

( Paqe 32 of 85

          STARTUP No.          --I..Od.-               Unit    I
                                                               *
 5.2      Reactor Startup after a refueling outage (continued)
           [33]   IF ICRR plot indicates criticality will fall outside
                  +/- 1000 pcm ECC termination band,
                  THEN
               [33.1]       NOTIFY SM and Duty Plant Manager.
               [33.2]       EVALUATE if ECC should be recalculated
                            prior to continuing startup.
               [33.3]       IF startup must be aborted,
                            THEN
                            PERFORM Appendix D, Actions if Reactor Startup Must       if'
                            Be Aborted.                                               r:!
           [34]    IF ICRR plot trend indicates acceptable ECC,
                   THEN
                   INITIATE rod withdrawal USING 0-SO-85-1
                   to fourth doubling range (App. C) or criticality.

( NOTE

  Steps 5.2[35] through 5.2[37] may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range or criticality.
            [35]   WHEN any of the following conditions are mel:
                   *      Source range count rate reaches or exceeds
                          fourth doubling range determined in Appendix C
                          OR
                    *     Control bank being withdrawn reaches 128 steps
                          (requires verifying overlap in 0-SO-85-1 )
                          OR
                    *     Bank D rods reach fully withdrawn position
                          OR
                    *   . Operators or Rx Engineer determine that rod motion
                           should be stopped
                    THEN
                    STOP outward rod motion.
     - - -         - - --
       SON              UNIT STARTUP FROM HOT STANDBY 0-GO-2
      Unit 0                    TO REACTOR CRITICAL                Rev. 0026

( Page 33 of 85

        STARTUP No. ~                                Unit     I                   Date /(; " " ;
 5.2    Reactor Startup after a refueling outage (continued)
        [36]     IF reactor is critical,
                 THEN
                 GO TO Step 5.2[59] (N/A Steps 5.2[37] through 5.2[58]).
        [37]     IF ALL of the following conditions are met:
                 *      rod motion was stopped prior to reaching
                        doubling range or criticality
                 *      Bank D rods are below fully withdrawn position
                 *      Unit Supervisor concurrence is obtained to resume,
                 THEN
                 RESUME rod withdrawal USING 0-SO-85-1
                 to fourth doubling range or criticality (whichever comes first).    ~D    0 0

( [38] IF source range count rate has reached or exceeded

                  fourth doubling range,
                  THEN
                  PERFORM the following:
             [38.1]       ENSURE rod motion STOPPED.
             [38.2]       WAIT approximately 2-3 minutes
                          to allow count rate to rise.
             [38.3]        NOTIFY Rx Engineering to perform ICRR calculations in
                           accordance with 0-RT-NUC-000-003 .0. [C.11]
              [38.4]       DETERMINE new count doubling range
                           USING Appendix C.
          [39]     IF reactor is subcritical with Bank D rods
                   at fully withdrawn position,
                   THEN
                   PERFORM Appendix E, Actions if Reactor is Subcritical with
                                                                                         ~
                                                                                         ~0
                   Rods Fully Withdrawn.
         SQN              UNIT STARTUP FROM HOT STANDBY 0-GO-2
        Unit 0                      TO REACTOR CRITICAL                 Rev. 0026

( Page 34 of 85

           STARTUP No.           /0l?I                  Unit    I                     Date~
 5.2       Reactor Sta rtup after a refue li ng ou tage (continued)
           [40]    IF ICRR plot indicates criticality will fall outside
                   +/- 1000 pcm ECC termination band,
                   THEN
                [40.1]       NOTIFY SM and Duty Plant Manager.
                [40.2]       EVALUATE if ECC should be recalculated
                             prior to continuing startup.
                [40.3]       IF startup must be aborted,
                             THEN
                             PERFORM Append ix D, Actions if Reactor Startup Must
                             Be Aborted.
           [41]     IF I.9RR plot trend indicates acceptable ECC,
                    THEN
                    INITIATE rod withdrawal USING 0-SO-85-1

( to fifth doubling range (App. C) or criticality.

                                                     NOTE
  Steps 5.2[42] through 5.2[44] may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range or criticality .
            [42]    WHEN any of the following conditions are met:
                    *      Source range count rate reaches or exceeds
                           fifth doubling range determined in Appendix C
                           OR
                     *     Bank D rods reach fully withdrawn position
                           OR
                     *     Operators or Rx Engineer determine that rod motion
                           should be stopped
                     THEN
                     STOP outward rod motion.
             [43]    IF reactor is critical,
                     THEN
                     GO TO Step 5.2[59] (N/A Steps 5.2[44] through 5.2[58]).
     SQN              UNIT STARTUP FRO M HOT STANDBY               0-GO-2
     UnitO                     TO REACTOR CRITICAL                 Rev. 0026

( Pace 35 of 85

       STARTUP No.          / cht                  Unit     I                    Date /do"7
 5.2   Reactor Startup after a refuel ing outage (continued)
       [44]    IF ALL of the following conditions are met:
               *      rod motion was stopped prior to reaching
                      doubling range or criticality
               *      Bank D rods are below fully withdrawn position
               *      Unit Supervisor concurrence is obta ined to resume,
               THEN
               RESUME rod withdrawal USING 0-SO-85-1
               to fifth doubling range or criticality (whicheve r comes first).
       [45]    IF source range count rate has reached or exceeded
               fifth doubling range,
               THEN
                PERFORM the following:
           [45.1]       ENSURE rod motion STOPPED.

( [45.2] WAIT approximately 2-3 minutes

                        to allow count rate to rise.
            [45.3]      NOTIFY Rx Engineering to perfo rm leRR calculations in
                        accordan ce with 0-RT-NUC-000 -003 .0. [C.11]
            [45.4]      DETERMINE new count doub ling range
                        USING Appendix C.
        [46]    IF reactor is subcritical with Bank D rods
                at fully withdrawn position,
                THEN
                PERFORM Appendi x E, Actions if Reactor is Subcritical with
                Rods Fully Withdrawn .
         SQN             UNIT STARTUP FROM HOT STANDBY                  0-GO-2
        Unit 0                    TO REACTOR CRITICAL                   Rev. 0026

( Page 36 of 85

 5.2
          STARTUP No. L@_                             Unit
           Reactor Startup after a refueling outage (continued)
                                                                 I                    Date 4
           [47]    IF IGRR plot indicates criticality will fall outside
                   +/- 1000 pcm EGG termination band,
                   THEN
                [47.1]     NOTIFY SM and Duty Plant Manager.
                [47.2]     EVALUATE if EGG should be recalculated
                           prior to continuing startup.
                [47.3]     IF startup must be aborted,
                           THEN
                           PERFORM Appendix D, Actions if Reactor Startup Must
                           Be Aborted .
            [48]    IF IGRR plot trend indicates acceptable EGG,
                    THEN
                    INITIATE rod withdrawal USING 0-SO-85-1
                    to sixth doubling range (App. C) or criticality.

( NOTE

  Steps 5.2[49] through 5.2[51] may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range or criticality .
            [49]    WHEN any of the following conditions are met:
                    *     Source range count rate reaches or exceeds
                          sixth doubling range determined in Appendix C
                          OR
                     *    Bank D rods reach fully withdraw n position
                          OR
                     *    Operators or Rx Engineer determine that rod motion
                          should be stopped
                     THEN
                     STOP outward rod motion.
             [50]    IF reactor is critical,
                     THEN
                     GO TO Step 5.2[59] (N/A Steps 5.2[51]through 5.2[58]).
     SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0                   TO REACTOR CRITICAL                Rev. 0026

( Page 37 of 85

       STARTUP No. / t?i'J1                       Unit    I                    Date /dcla
 5.2   Reactor Startup after a refueling outage (continued)
                                                                                         i
       [51)    IF ALL of the following conditions are met:
               *     rod motion was stopped prior to reaching
                     doubling range or criticality
               *     Bank D rods are below fully withdrawn position
               *     Unit Supervisor concurrence is obtained to resume,
               THEN
               RESUME rod withdrawal USING 0-SO-85-1
               to sixth doubling range or criticality (whichever comes first).
       [52)    IF source range count rate has reached or exceeded
                sixth doubling range,
                THEN
                PERFORM the following:
            [52.1]     ENSURE rod motion STOPPED.
            [52.2]     WAIT approximately 2-3 minutes
                       to allow count rate to rise.
            [52.3]     NOTIFY Rx Engineering to perform ICRR calculations in
                       accordance with 0-RT-NUC-000-003.0. [C.11)
            [52.4)      DETERMINE new count doubling range
                        USING Appendix C.
        [53)    IF reactor is subcritical with Bank D rods
                at fully withdrawn position,
                THEN
                 PERFORM Appendix E, Actions if Reactor is Subcritical with
                 Rods Fully Withdrawn.
        SQN              UNIT STARTUP FROM HOT STANDBY                  0-GO-2
       UnitO                      TO REACTOR CRITICAL                   Rev. 0026

( Pace 38 of 85

          STARTUP No.            [(J()(               Unit       I
 5.2       Reactor Startup after a refuel ing outage (co ntinued)
           [54]    IF IGRR plot indicates criticality will fall outside
                   +/- 1000 pcm EGG termination band,
                   THEN
                [54.1]     NOTIFY SM and Duty Plant Manager.
                [54.2]     EVALUATE if EGG should be recalculated
                           prior to continuing startup.
                [54.3]     IF startup must be aborted, THEN
                           PERFORM Appendix D, Actions if Reactor Startup Must
                           Be Abo rted.
           [55]     IF IGRR plot trend indicates acceptable EGG,
                    THE N
                    INITIATE rod withdrawal USING 0-SO-85- 1
                    to seventh doubling range (App. C) or criticality.                 o

( NOTE

  Steps 5.2[56] through 5.2[58] may be repeated as necessary if rod motion is stopped
  prior to reaching doubling range or criticality.
            [56]    WHEN any of the following conditions are met:
                    *     Source range count rate reaches or exceeds
                          seventh doubling range determined in Appendix G
                          OR
                     *    Bank D rods reach fully withdrawn position
                          OR
                     *    Operators or Rx Engineer determine that rod motion
                          should be stopped
                     THEN
                     STOP outward rod motion.                                         DODD
             [57]    IF reacto r is critical,
                     THEN
                     GO TO Step 5.2[59] (N/A Step 5.2[58]).
     SQN            UNIT STARTUP FROM HOT STANDBY               0-GO-2
     Unit 0                  TO REACTOR CRITICAL                Rev. 0026

( Page 39 of 85

       STARTUP No.              _                Unit      _                     Date      _
 5.2   Reactor Startup aft er a refuel ing outage (continued)
       [58]    IF ALL of the following conditions are met:
               *    rod motion was stopped prior to reaching
                    doubling range or criticality
               *    Bank D rods are below fully withdrawn position
               *    Unit Supervisor concurrence is obtained to resume,
               THEN
               RESUME rod withdrawal USING 0-SO-85-1
               to seventh doubling range or criticality (whichever comes first).    0 0 0 0
       [59]    IF any of the following conditions exist:
                * - critical conditions cannot be achieved
                    within the +/-1000 pcm allowable limits
                    OR
                *   critical conditions cannot be achieved above
                     rod insertion limit
                    OR
                *    reactor startup must be aborted for other reasons,
                THEN
                PERFORM the following to abort reactor startup: [C.11]
            [59.1]     STOP rod withdrawal.
            [59.2]     INITIATE insertion of control banks.
            [59.3]     PERFORM Appendix D, Actions if Reactor Startup
                       Must Be Aborted.                                                 o
            [59.4]     DO NOT CONTINUE this section.
          SQN              UNIT STARTUP FROM HOT STANDBY              0-GO-2
          Unit 0                   TO REACTOR CRITICAL                Rev. 0026

( Paqe 40 of 85

            STARTUP No.                                Unit       _                 Date   _
      5.2   Reactor Startup after a refueling outage (continued)
            [60]     IF reactor is subcritical with Bank D rods
                     at fully withdrawn position,
                     THEN
                     PERFORM Appendix E, Actions if Reactor is Subcritical with
                     Rods Fully Withdrawn.                                               0
            [61]     IF reactor is critical with SUR less than 0.3 DPM
                     AND intermediate range NIS is less than P-6 (1 X 10.4 %),
                     THEN
                     PERFORM the following:
                 [61.1]      IF Bank D control rods are BELOW
                          - fully withdrawn position,
                             THEN
                             OPERATE control rods to establish a positive SUR
                             of approximately 0.3 DPM.
                 [61 .2]     IF Bank 0 rods have reached fully withdrawn position
                             AND Rx Engineering concurs with RCS dilution,
                             THEN
                             PERFORM RCS dilution (as recommended by Rx Eng)
                             to establish positive SUR of approx. 0.3 DPM
                             USING 0-SO-62-7.
c....
      SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
      Unit 0                 TO REACTOR CRITICAL                  Rev. 0026

( Page 41 of 85

         STARTUP No.            _               Unit         _                  Date          _
 5.2     Reactor Startup after a refueling ou tage (continued)
         IStart of Critical Step(s)
                                           NOTES
  1) Blocking the SRM reactor trip with [HS-92-50011 and [HS-92-50021 will disable the
     detect or outputs and remove the audio count rate signal.
  2) Step 5.2[62) may be performed at time of criticalit¥. if required. Source range reactor
     trip must be BLOCKED before trip setpoints of 10 cps.
         [62)    WHEN annunciator XA-55-4A, window 0 -2
                                     P-6
                               INTERMEDIATE
                                   RANGE             is LIT, THEN [C.2)
                                 PERMISSIVE
             [62.1)    RECORD both source range readings.
                N-31         CPS               N-32,         CPS
                                                                                  Initials
             [62.2)    RECORD both intermediate range readings.
                 N-35        %RTP              N-36          %RTP
                                                                                  Initials
              [62.3)   VERIFY a minimum of one IRM channel
                       greater than or equal to 1 X 10 -4 % RTP.                            o
              [62.4]   BLOCK source range reactor trip by momentarily
                       placing [HS-92-50011 and [HS-92-50021 SRM TRIP
                       RESET-BLOCK P-6 handswitches to BLOCK.
                                                    Initials            Date              Time
          SQN           UNIT STARTUP FROM HOT STANDBY 0-GO-2
         Unit 0                 TO REACTOR CRITICAL                Rev. 0026

(.. Page 42 of 85

            STARTUP No.            _                Unit       _                  Date           _
   5.2      Reac tor Startup after a refuel ing outage (continued)
                [62.5]   VERIFY annunciator XA-55-4A, window C-1
                                 SOURCE RANGE
                                TRAINS A & B TRIP
                                      BLOCK            is LIT.
                                                                                           o
            IEnd of Critica l Step(s)
                [62.6]   SELECT NR 45to record one intermediate range
                         channel and one power range channel.
                [62.7]   ADJUST NR 45 chart speed as desired.
                          (N/A is no change needed.)                                        o
            [63]    ENSURE PA announcement made to notify plant personnel
                    when the reactor is critical.                                           o
                                                  NOTE
    Wh en T-avg is less than 551°F and Tavg - Tref deviation alarm is lit, SR 4.1.1.4.b requires
    verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes.
             [64]   IF Tavg - Tref deviation alarm [M-5A window C-6] is LIT
                    AND T-avg is less than 551°F,
                    THEN
                    PERFORM 0-SI-SXX-068-127.0 to satisfy SR 4.1.1.4.b,
                    Minimum Temperature For Criticality.
(
     SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0                   TO REACTOR CRITICAL                 Rev. 0026

( Page 43 of 85

       STARTUP No .               _               Unit        _                 Date      _
 5.2   Reactor Startup after a refueling outage (continued)
       [65)    RAISE reactor power to approximately 1 X 10-3% :
           [65.1)      IF Bank 0 control rods are BELOW
                       fully withdrawn position,
                       THEN
                       OPERATE control rods to establish a positive SUR
                       of approximately 0.5 OPM (not to exceed 1 OPM).
           [65 .2)     IF Bank 0 rods have reached fully withdrawn position
                       AND Rx Engineering concurs with RCS dilution,
                       THEN
                       PERFORM RCS dilution (as recommended by Rx Eng)
                       to establish positive SUR of approx. 0.5 DPM
                       USING 0-SO-62-7.
            [65.3]     WHEN intermediate range Nls indicate
                        appro ximately 1 X 10.3 %,
                       THEN
                        PERFORM the following:
                [65.3.1)     STABILIZE reactor power using control rods.
                [65.3.2)     RECORD critical data indicated below.
               Power Level:             N-35_ _ %RTP                N-36_ _ %RTP
               Rod Position:                                RCS Boron concentration
                                     Bank       Step                                 ppm
                                               1               2            3          4
                                                     Initials          Date          Time
        [66J     MAINTAIN reactor power stable with control banks
                 above low insertion limit USING rod movement or
                 boration /dilution to compensate for Xenon.                           o
     SQN             UNIT STARTUP FROM HOT STANDBY              0-GO-2
     Unit 0                    TO REACTOR CRITICAL              Rev. 0026

( Pane 44 of 85

       STARTUP No.                _              Unit      _                  Date _
 5.2   Reactor Startup after a refue ling outage (continued)
       [67]    IF start up is to continue with one or both MFPTs available,
               THE N
           [67.1]      ENSURE Steps 5.1 [13] through 5.1[15] have been
                       comp leted for applicable pump(s).
           [67.2]     VERIFY other applicable actions Section 5.2 completed
                       or initiated .
           [67.3]      GO TO 0-GO-3, Power Ascension From Reactor Critical
                       to Less Than 5% Reactor Power.
       [68]     IF start up is to continue with NO MFPT available,
               THEN
            [68.1]     MARK Steps 5.1[13] through 5.1[17] as 'O N/A".
            [68.2]     VERIFY other applicable actions in Section 5.2
                       completed or initiate d.
            [68.3]     GO TO 0-GO-3 , Power Ascension From Reactor Critical
                       to Less Than 5% Reactor Power.
        [69]    IF startup is to be discontinued ,
                THEN
                GO TO 0-GO-6, Power Reduction From 30% Reactor Power to
                Hot Standby.
                                          END OF TEXT
       SQN               UNIT STARTUP FROM HOT STANDBY               0-GO-2

c Unit 0

         STARTUP No .
                                  TO REACTOR CRITICAL
                                     _              Unit       _
                                                                      Rev. 0026
                                                                      Paae 45 of 85
                                                                                    Date    _
 5.3     Reactor Startup after a non-refueling outage
         [1]       VERIFY applicable actions in Section 5.1 completed or
                   initiated.
                                               NOTE
  Steps 5.3[3] through 5.3[8] may be performed out of sequence.
         [2]       IF any MFPT trip buss is NOT energized ,
                   THEN
               [2.1]       ENSURE requirements of LCO 3.0.4 are satisfied .
               [2.2]       NOTI FY Unit SRO that LCO 3.3.2.1 (3.3.2) action 20
                           will apply when Mode 2 is entered .
          [3]       ENSURE Appendix B, Mode 3 to Mode 2, 1 Review and

( Approval has been completed to ensure all restraints to

                    Mode 2, 1 entry have been resolved and appro vals for mode
                    change gra nted.
                                                                                         SM
          [4]       BLOCK Source Range High Flux At Shutdown alarm:
                [4.1]      PLACE BOTH HI FLUX AT SHUTDOWN switches
                           on M-13 to the BLOCK positio n.
                [4.2]      VERIFY annun ciator XA-55-4 B window C-1,
                                   SOURCE RANGE
                                   HIGH SHUTDOWN
                                      FLUX ALARM        is L1T.[C.2].
                                         CLOCK
                                                                                          o
           [5]      VERIFY greater than or equal to 0.5 cps
                    on the highest reading SR instrument.                                 o
         SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
        Unit 0                  TO REACTOR CRITICAL                Rev. 0026

( Paae 46 of 85

           STARTUP No.              _               Uni t     _                  Date         _
  5.3      Reac to r Startup after a non -ref ueli ng outage (continued)
                                                 NOTE
   The following count rates may be used as a reference during the approach to criticality .
           [6]    RECORD SR count rates from two of the following:
                  [C.2) (N/A instruments not used)
                              XI-92-5001A        (N31)                   cps
                              XI-92-5002A         (N32)                  cps
                                                          OR
                              XI-92-5001B         (N31)        _ _ _ cps
                              XI-92-5002B         (N32)        _ _ _ _cps
                                                                       Time              Date

( [7) IF conditions exist which could cause Power Range NIS

                   indicatio ns to be non-conservative,
                  THE N
                   ENSURE Power Range high flux trip setpoints reduced to 60%
                   in accordance with the following: [C.3)
                   *    1,2-SI-ICC-092-N41 .1                                               0
                   *    1,2-SI-ICC-092-N42.2                                                0
                   *     1,2-SI-ICC-092-N43.3                                               0
                    *    1,2-SI-ICC-092-N44.4                                               0
                                      Instrument Maintenance            Date             Time
(
       SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                  TO REACTOR CRITICAL                    Rev. 0026

( Page 47 of 85

         STARTUP No .             _                 Unit       _                    Date   _
   5.3   Reactor Startup after a non-refueling outage (con tinued)
         [8)     VERIFY the estimated critical position calculated in
                  accordance with 0-8 1-NUC-000-001.0, Estimated Critical
                  Conditions.
          Estimated critical position:                      steps on bank
          Assumed boron concentration:                      ppm
                                                             Initials             Time   Date
                                                              8TA                 Time   Date
          [9]     VERIFY Steps 5.3[1] through 5.3[8) completed.
          [10]    IF estimated critical boron concentration does NOT
                  approximate ly equal actual boron concentration,
                  THEN
              [10.1)     DETERMINE the appropriate boration/dilution
                         requirements to achieve criticality within acceptable
                         limits.                                                         D
              [10.2)     DILUTE/BORATE in accordance with 0-80-62-7
                         to the estimated critical boron concentration. [C.12]           D
              [10.3)     OPERATE pressurizer heaters/spray as necessary
                         to equalize boron concentration (within 50 ppm) between
                         reactor coolant loops and the pressurizer. [C.12]               D
               [10.4]    WHEN sufficient mixing has occurred,
                         THEN
                          OBTAIN a new boron sample.                                     D
               [10.5]     ENSURE actual boron concentration is approximately
                          equal to the estimated critical boron concentration.
 (
          saN          UNIT STARTUP FROM HOT STANDBY 0-GO-2
         Unit 0               TO REACTOR CRITICAL                   Rev. 0026

( Page 48 of 85

           STARTUP No .          _               Unit        _                    Date      _
  5.3      Reac to r Startup after a non-refueling outage (continued)
                                              NOTE
   Termination limits are associated with +/- 750 pcm tolerance band. These values are within
   minimum and maximum rod positions corresponding to Tech Spec limit of +/- 1000 pcm
   (Minimum and Maximum Allowable Limits). Termination limits shall be used by Reactor
   Engineering and Operations to determine whether approach to criticality should be
   termi nated and a new ECC calculated . ECC must be terminated if Minimum or Maximum
   Allowable Limits (correspo nding to Tech Spec limit of +/- 1000 pcm) are approached.
            [11]  RECORD upper and lower rod positio n limits correspondi ng to
                  +/- 750 pcm Termination Band as determined by
                  0-SI-N UC-000-001 .0. Estimated Critical Conditions .
         Upper termination rod position                      steps on bank
         Lower termination rod position                      steps on bank

( Initials Time Date

            [12]  RECORD minimum and maximum rod positions correspo nding
                  to +/- 1000 pcm ALLOWAB LE LIMITS (Tech Spec Limit)
                  determined by 0-SI-NUC-000 -001.0, Estimated Critical
                  Conditions. [C.11]
   Minimum allowable rod position                  steps on bank
   Maximum allowable rod positio n                 steps on bank
                                                              Initials        Time      Date
             [13]  VERIFY all shutdown rods are fully withdrawn in accordance
                   with 0-SI-OPS-000-004.0. Surveillence Requirements
                   Performed on Increased Frequency with no Specific
                   Frequency, within 15 minutes prior to withdrawing control rods.
                                                                                   Time   Date
(
          SON            UNIT STARTUP FROM HOT STANDBY 0-GO-2
         Unit 0                   TO REACTOR CRITICAL                    Rev. 0026

( Page 49 of 85

           STARTUP No.                _                Unit       _                    Date _---'__
 5.3       Reactor Startup afte r a no n-refue ling outage (co nti nued)
                                                    NOTE
  SR 4.1.1.4.a requires verifying lowest T-avg greater than or equal to 541°F
  withi n 15 minutes prior to achieving criticality.
            [14]    IF O-SI-SXX-068-127.0 is NOT in progress,
                    THEN
                    INITIATE applicable sections of O-SI-SXX-068-127.0
                    to satisfy SR 4.1.1.4.a., Minimum Temperature For Criticality.
            [15]    NOTIFY onsite personnel of reactor startup over PIA system.                0
                                                  CAUTION
  Avoid operatio ns tha t could produce sudden changes of temperatu re or unplanned
  boron con cen tration changes du ring approach to cr iticality or low power.
                                                   NOTES
  1)     Nuclear instrumentation shall be monitored very closely for indications of unplanned
         reactivity rate of change. [C.11]
  2)    Activities that can distract operators and supervisors involved with reactor startup,
         such as shift turnover and surveillance testing during approach to criticality,
         SHALL BE avoided. [C.12]
   3)    ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for
         monitoring NIS indications.
             [16]    MONITOR nuclear instruments during approach to criticality:
                 [16.1]     MONITOR source range and intermediate range NIS
                            to identify potential reactivity anomalies . [C.11]                o
                 [16.2]     IF desired to place NR-45 recorder in fast speed,
                            THEN
                            ADJUST chart speed to high.
         SQN              UNIT STARTUP FROM HOT STANDBY               0-GO-2
        Unit 0                    TO REACTOR CRITICAL                 Rev. 0026

( Paqe 50 of 85

           STARTUP No.               _                Unit       _                  Date          _
   5.3     Reactor Startup aft er a no n-refueli ng ou tage (continued)
                                               CAUTION
    Do NOT exceed a steady sta rtup rat e of +1 DPM.
                                                  NOTE
    The unit ente rs Mode 2 when the control banks are first withdrawn.
            [17]     INITIATE a reactor startup by performing the following:
                [17.1]     RECORD both source range readings
                           for leRR base counts.
                         N-31_ _CPS                       N-32,_ _CPS
                                                                                        Initials
                [17.2]     RECORD intermedi ate range readings.
                         N-35           %                 N-36          %
                                                                                        Initials
                 [17.3]    CALCULATE initial source range count doub ling value
                            USING Appendix C.
                                                 MODE2
                 [17.4]     INITIATE withdrawal of control banks in acco rdance
                            with 0-SO-85-1 to first stop point:
                              CONTROL BANK A                   128 STEPS
                  [17.5]    ENSURE Mode 2 entry is logged
                            (log entry may be performed out of sequence later).                 o
 (
        SQN           UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Uni tO                  TO REACTOR CRITICAL                Rev. 0026

( Pane 51 of 85

          STARTUP No.             _               Uni t      _                   Date        _
 5.3      Reactor Startup after a non-refueling outage (continued)
          [18]   WHEN control bank A is at 128 steps,
                 THEN.
                 PERFORM the following:
              [18.1]    STOP rod withdrawal.
              [18.2]    WAIT for approximately two minutes.
              [18.3]     NOTIFY Rx Engineering to perform ICRR calculation
                        in accordance with 0-81-NUC-000-001.0. [C.11]
                                             CAUTION
  Lowest loop T-avg must be ver ified greater t han or equal to 541 °F
  us ing 0-SI-SXX-068-127.0 withi n 15 minutes prior to achieving criticality.
                                               NOTES
   1)  Appro ximately five to seven count doublings are expected to result in criticality.
       However , criticality should be anticipated at any time.
  2)   Proper bank overlap must be verified using 0-80-85-1 as each successive rod bank
       is withdrawn .
           [19]   WHEN concurrence obtained from Rx Engineering,
                  THE N
                  INITIATE rod withdrawal to first count doubling
                  (dete rmined in App. C) USING 0-80-85-1.                                 o
          SQN               UNIT STARTUP FROM HOT STANDBY              0-GO-2
         UnitO                       TO REACTOR CRITICAL               Rev . 0026

( Pace 52 of 85

            STARTUP No.                 _                 Un it   _                  Date     _
  5.3       Reacto r Startup after a non-refueling outage (continued)
                                                     NOTE
   Steps 5.3[20) and 5.3[21) may be repeated as necessary if rod motion is stopped
   prior to reaching doubling value.
            [20]     WHEN any of the following condit ions are met:
                     *      Source range count rate is approximate ly equal to
                            first doubling value determined in Appendix C
                            OR
                     *      Control bank being withdrawn reaches 128 steps
                            (requires verifying overlap in 0-SO-85 -1)
                            OR
                     *      Operators or Rx Engineer determine that rod motion
                            should be stopped
                     THEN
                     STOP outward rod motion.                                            DODD
             [21)     IF rod motion was stopped prior to reaching doubling range
                     AND Unit Supervisor concu rrence is obtai ned to resume,
                     THEN
                      RESUME rod withdrawal to first count doubling
                      USING 0-SO-85-1 .                                                   DO DD
             [22]     IF source range count rate has reached or exceeded
                      first doubling,
                      THEN
                      PERFORM the following:
                 [22.1]        ENSURE rod motion STOPPED.
                 [22.2]        WAIT approximately 2-3 minutes
                               to allow count rate to rise .
                 [22.3)        NOTIFY Rx Engineering to perform ICRR calculations in
                               acco rdance with 0-SI-NUC-000-001 .0. [C.1 1]                0
                  [22.4)       DETERMINE new count doubling range
                               USING Appendix C.
(
         SQN            UNIT STARTUP FROM HOT STANDBY O-GO -2
        Unit 0                   TO REACTOR CRITICAL                   Rev. 0026

( Page 53 of 85

           STARTUP No .             _                Unit         _                  Date    _
  5.3      Reactor Startup after a non-refueling outage (continued)
           [23)   IF ICRR plot indicates criticality will fall outside
                  +/- 750 pcm ECC termination band,
                  THEN
               [23.1)     NOTIFY SM and Duty Plant Manager.
               [23.2)     EVALUATE if ECC should be recalculated
                          prior to continuing startup.
               [23.3]     IF startup must be aborted,
                         THEN
                          PERFORM Appendix D, Actions if Reactor Startup Must
                          Be Aborted.                                                      0
            [24)   WHEN concurrence obtained from Rx Engineering,
                   THE;.N
                   INITIATE rod withdrawal to second doubling range
                   (determined in App. C) USING 0-SO-85-1.                                 o
                                                  NOTE
   Steps 5.3[25) and 5.3[26] may be repeated as necessary if rod motion is stopped
   prior to reaching doubling range.
            [25)   WHEN any of the following conditions are met:
                   *    Source range count rate reaches or exceeds
                        second doubling range determined in Appendix C
                        OR
                   *    Control bank being withdrawn reaches 128 steps
                        (requires verifying overlap in 0-SO-85-1)
                        OR
                    *    Operators or Rx Engineer determine that rod motion
                        should be stopped
                    THEN
                    STOP outward rod motion.                                              000 0
(
     SQN              UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Un itO                   TO REACTOR CRITICAL                     Rev. 0026

( Page 54 of 85

       STARTUP No.                _                Unit         _                   Date    _
 5.3   Reactor Startup after a non-refueling outage (continued)
       [26]     IF rod motion was stopped prior to reaching doubling range
                AND Unit Supervisor concurrence is obtained to resume,
                THEN
                RESUME rod withdrawal to second doubling range
                USING 0-SO-85-1.                                                       0000
       [27]     IF source range count rate has reached or exceeded
                second doubling range,
                THEN
                PERFORM the following:
            [27.1]     ENSURE rod motion STOPPED.
            [27.2]     WAIT approximately 2-3 minutes
                       to allow count rate to rise.
            [27.3]     NOTIFY Rx Engineering to perform ICRR calculations in
                       accordance with 0-SI-NUC-000-001.0. [C.11]                        0
            [27.4]     DETERMINE new count doubling range
                        USING Appendix G.
        [28]     IF IGRR plot indicates criticality will fall outside
                 +/- 750 pcm EGG termination band,
                 THEN
             [28.1]     NOTIFY SM and Duty Plant Manager.
             [28.2]     EVALUATE if EGG should be recalculated
                        prior to continuing startup.
             [28.3]     IF startup must be aborted,
                        THEN
                        PERFORM Appendix D, Actions if Reactor Startup Must
                        Be Aborted.                                                      0
         [29]     IF IGRR plot trend indicates acceptable EGG,
                  THEN
                  INITIATE rod withdrawal to third doubling range
                  (determined in App. G) USING 0-SO-85-1.                                 o
             SON              UNIT STARTUP FROM HOT STANDBY 0-GO-2
            Unit 0       -            TO REACTOR CRITICAL               Rev. 0026

(-. Page 55 of 85

               STARTUP No .              _                Unit      _                 Date    _
     5.3       Reactor Startup after a non-refueling outage (conti nued)
                                                      NOTE
      Steps 5.3[30] and 5.3[31] may be repeated as necessary if rod motion is stopped
      prior to reaching doubling range.
               [30]    WHEN any of the following conditions are met:
                        *     Source range count rate reaches or exceeds
                              third doubling range determined in Appendix C
                              OR
                        *     Control bank being withdrawn reaches 128 steps
                              (requires verifying overlap in 0-SO-85-1)
                              OR
                        *     Operators or Rx Engineer determine that rod motion
                              should be stopped
                        THEN
                        STOP outward rod motion.                                          DODD
                [31]    IF rod motion was stopped prior to reaching doubling range
                        AND Unit Supervisor concurrence is obtained to resume,
                        THEN
                         RESUME rod withdrawal to third doubling range
                         USING 0-8 0-85-1.                                                0000
                [32]     IF source range count rate has reached or exceeded
                         third doubling range,
                         THEN
                         PERFORM the following:
                    [32.1]      ENSURE rod motion STOPPED.
                    [32.2]      WAIT approximately 2-3 minutes
                                to allow count rate to rise.
                     [32.3]      NOTIFY Rx Engineering to perform ICRR calculations in
                                accordance with 0-SI-NUC-000-001.0. [C.11]                  0
                     [32.4]      DETERMINE new count doubling range
                                 USING Appendix C.
   (
          SQN             UNIT STARTUP FROM HOT STANDBY                  0-GO-2
          Unit 0                   TO REACTOR CRITICAL                   Rev. 0026

('.

                                                                         Page 56 of 85
            STARTUP No.               _                Unit         _                  Date    _
   5.3      Reac tor Startup after a non-refueling outage (co ntinued)
             [33]   IF ICRR plot indicates criticality will fall outside
                    +/- 750 pcm ECC termination band,
                    THEN
                 [33.1]     NOTIFY SM and Duty Plant Manager.
                 [33.2]     EVALUATE if ECC should be recalculated
                            prior to continuing startup.
                 [33.3]     IF startup must be aborted,
                            THEN
                            PERFORM Appendix D, Actions if Reactor Startup Must
                            Be Aborted.                                                      0
             [34]    IF ICRR plot trend indicates acceptable ECC,
                     TH_EN
                     INITIATE rod withdrawal USING 0-SO-85-1
                     to fourth doubling range (App. C) or criticality.                       o
                                                    NOTE
    Steps 5.3[35] through 5.3[37] may be repeated as necessary if rod motion is stopped
    prior to reaching doubling range or criticality.
              [35]   WHEN any of the following conditions are met:
                     *    Source range count rate reaches or exceeds
                          fourth doubling range determined in Appendix C
                           OR
                      *    Control bank being withdrawn reaches 128 steps
                           (requires verifying overlap in 0-SO-85-1)
                           OR
                      *    Bank D rods reach fully withdrawn position
                           OR
                      *    Operators or Rx Engineer determine that rod motion
                           should be stopped
                      THEN
                      STOP outward rod motion.                                              0000
     SQN               UNIT STARTUP FROM HOT STANDBY               O-GO-2
     Unit 0                    TO REACTOR CRITICAL                 RevoOO26

( Paqe 57 of 85

       STARTUP No,                _                 Unit      _                   Date   _
 503   Reactor Startup after a non-refueling outage (continued)
       [36]     IF reactor is critical,
               THEN
                GO TO Step 5.3[59] (N/A Steps 5.3[37] through 5.3[58]).
       [37]     IF ALL of the following conditions are met:
                *      rod motion was stopped prior to reaching
                       doubling range or criticality
                *      Bank D rods are below fully withdrawn position
                *      Unit Supervisor concurrence is obtained to resume,
                THEN
                 RESUME rod withdrawal USING 0-SO-85-1
                 to fourth doubling range or criticality (whichever comes first).    0000
        [38]     IF source range count rate has reached or exceeded
                 fourth doubling range,
                 THEN
                 PERFORM the following:
            [38.1]       ENSURE rod motion STOPPED.
            [38.2]       WA IT approximately 2-3 minutes
                         to allow count rate to rise.
            [38.3]       NOTIFY Rx Engineering to perform ICRR calculations in
                         accordance with 0-SI-NUC-000-001.0. [C011]                    0
             [38.4]       DETERMINE new count doubling range
                          USING Appendix C.
         [39]     IF reactor is subcritical with Bank D rods
                  at fully withdrawn position,
                  THEN
                  PERFORM Appendix E, Actions if Reactor is Subcritical with
                  Rods Fully Withdraw n.                                               0
         SQN                UNIT STARTUP FROM HOT STANDBY 0-GO-2

c Unit 0

           STARTUP No.
                                      TO REACTOR CRITICAL
                                                          Unit       _
                                                                          Rev. 0026
                                                                          Page 58 of 85
                                                                                        Date    _
 5.3       Reactor Startup after a non-refueling outage (continued)
           [40]      IF IGRR plot indicates criticality will fall outside
                     +/- 750 pcm EGG termination band,
                     THEN
                 [40.1]       NOTIFY SM and Duty Plant Manager.
                 [40 .2]       EVALUATE if ECG should be recalculated
                               prior to continuing startup.
                 [40.3]        IF startup must be aborted,
                              THEN
                               PERFORM Appendix D, Actions if Reactor Startup Must
                               Be Aborted.                                                    0
            [41]      IF IGRR plot trend indicates acceptable EGG,
                      TH_EN
                      INITIATE rod withdrawal USING 0-SO-85-1
                      to fifth doubling range (App . G) or criticality.                       o
                                                       NOTE
   Steps 5.3[42] thro ugh 5.3[44] may be repeated as necessary if rod motion is stopped
   prior to reaching doubling range or criticality;
             [42]     WHEN any of the following conditions are met:
                      *      Source range count rate reaches or exceeds
                             fifth doubling range determined in Appendix G
                             OR
                       *     Bank D rods reach fully withdrawn position
                             OR
                       *     Operators or Rx Engineer determine that rod motion
                             should be stopped
                       THEN
                       STOP outward rod motion.                                              DODD
              [43]     IF reactor is critical,
                       THEN
                       GO TO Step 5.3[59] (N/A Steps 5.3[44] through 5.3[58]).
      SQN              UNIT STARTUP FROM HOT STANDBY 0-GO-2
      Unit 0                   TO REACTOR CRITICAL                 Rev. 0026

( Paqe 59 of 85

        STARTUP No.               _                 Unit      _                  Date    _
  5.3   Reactor Startu p after a non-refu eling outage (continued)
        [44)    IF ALL of the following conditions are met:
                *      rod motion was stopped prior to reaching
                       doubling range or criticality
                *      Bank D rods are below fully withdrawn position
                *      Unit Supervisor concur rence is obtained to resume,
                THEN
                RESUME rod withdrawal USING 0-80-85-1
                to fifth doubling range or criticality (whichever comes first).      0000
         [45)    IF source range count rate has reached or exceeded
                 fifth doubling range,
                 THEN
                 PERFORM the following:
             [45.1)      ENSURE rod motion STOPPED.
             [45.2)      WAIT approximately 2-3 minutes
                         to allow count rate to rise.
             [45.3]      NOTIFY Rx Engineering to perform ICRR calculations in
                         accordance with 0-SI-NUC-000-001 .0. [C.11]                   0
             [45.4)       DETERMINE new count doubling range
                          USING Appendix C.
          (46)    IF reactor is subcritical with Bank D rods
                  at fully withdrawn position,
                  THEN
                  PERFORM Appendix E, Actions if Reactor is Subcritical with
                  Rods Fully Withdrawn.                                                o
l
          SON               UNIT STARTUP FROM HOT STANDBY                   0-GO-2
         Unit 0                      TO REACTOR CRITICAL                    Rev. 0026

( Page 60 of 85

            STARTUP No .                                  Unit         _                  Date    _
   5.3       Reactor Startup after a non-refueling ou tage (continued)
             [47]     IF ICRR plot indica tes criticality will fall outside
                      +/- 750 pcm ECC termination band ,
                      THEN
                  [47 .1]     NOTIFY SM and Duty Plant Manager.
                  [47 .2]     EVALUATE if ECC should be recalculated
                              prior to continuing startup.
                  [47 .3]     IF startup must be aborted ,
                              THEN
                              PERFORM Ap pendix D, Actions if Reactor Startup Must
                              Be Aborted .                                                      0
              [48]     IF ICRR plot trend indicates acceptable ECC,
                       THE N
                       INITIATE rod withd rawa l USING 0-SO-85- 1
                       to sixth doubling range (App. C) or criticality.                         o
                                                      NOTE
    Steps 5.3[49] through 5.3[51] may be repeated as necessary if rod motion is stopped
    prior to reaching doubling range or criticality .
              [49]     WHEN any of the following conditions are met:
                       *     Source range count rate reaches or exceeds
                             sixth doublin g range determined in Appe ndix C
                             OR
                        *    Bank D rods reac h fully withdrawn position
                             OR
                        *    Operators or Rx Engineer determ ine that rod motion
                             should be stopped
                        THEN
                        STOP outward rod moti on.                                              0000
               [50]     IF reactor is critical,
                        THEN
                        GO TO Step 5.3[59] (N/A Steps 5.3[51] through 5.3[58]).
(,
      SQN             UNIT STARTUP FROM HOT STANDBY                0-GO-2
      Unit 0                   TO REACTOR CRITICAL                 Rev. 0026

( PaQe 61 of 85

        STARTUP No.              _                 Unit      _                   Date      _
  5.3   Reactor Startup afte r a non-refueling outage (continued)
        [51]    IF ALL of the following conditions are met:
                *     rod motion was stopped prior to reaching
                      doubling range or criticality
                *     Bank D rods are below fully withdrawn position
                *     Unit Supervisor concurrence is obtained to resume,
                THEN
                RESUME rod withdrawal USING 0-SO-85-1
                to sixth doubling range or criticality (whichever comes first).     D D D D
        [52]    IF source range count rate has reached or exceeded
                 sixth doubling range,
                THEN
                 PERFORM the following:
             [52.1]     ENSURE rod motion STOPPED.
             [52.2]     WAIT approximately 2-3 minutes
                        to allow count rate to rise.
             [52.3]      NOTIFY Rx Engineering to perform ICRR calculations in
                         accordance with O-SI-NUC-OOO-001.0. [C.11]                     D
             [52.4]      DETERMINE new count doubling range
                         USING Appendix C.
         [53]    IF reactor is subcritical with Bank D rods
                 at fully withdrawn position,
                 THEN
                 PERFORM Appendix E, Actions if Reactor is Subcritical with
                  Rods Fully Withdrawn.                                                 D
(
                                                                                             -  ---   - - -
          SQN              UNIT STARTUP FROM HOT STANDBY                 0-GO-2
         UnitO                      TO REACTOR CRITICAL                  Rev. 0026

( Page 62 of 85

            STARTUP No.                _                Unit        _                  Date         _
  5.3       Reactor Startup afte r a non-refueli ng outage (continued)
            [54]    IF ICRR plot indicates criticality will fall outside
                    +/- 750 pcm EGG termination band,
                    THE N
                 [54.1]      NOTIFY SM and Duty Plant Manager.
                 [54.2]      EVALUATE if EGC should be recalculated
                             prior to continuing startup.
                 [54.3]      IF startup must be aborted ,
                             THEN
                             PERFORM Appendix D, Actions if Reactor Startup Must
                             Be Aborted.                                                       D
             [55]    IF IGRR plot trend indicates acceptable EGG,
                     Tf-i!:N
                     INITIATE rod withdrawal USING 0-SO-85-1
                     to seventh doubling range (App. G) or criticality.                        D
                                                     NOTE
   Steps 5.3[56] through 5.3[58] may be repeated as necessary if rod motion is stopped
    prior to reaching doubling range or criticality.
             [56)    WHEN any of the following conditions are met:
                      *    Source range count rate reaches or exceeds
                           seventh doubling range determined in Appendix G
                           OR
                      *    Bank D rods reach fully withdrawn position
                           OR
                      *    Operators or Rx Engineer determine that rod motion
                            should be stopped
                      THEN
                      STOP outward rod motion.                                              D D D D
              [57)    IF reactor is critical,
                      THEN
                       GO TO Step 5.3[59] (N/A Step 5.3[58]).
(
      SQN             UNIT STARTUP FROM HOT STANDBY               0-GO-2
      Unit 0                    TO REACTOR CRITICAL               Rev. 0026

( Paqe 63 of 85

        STARTUP No.                _               Unit      _                    Date      _
  5.3   Reactor Startup aft er a non-refueling outage (contin ued)
        [58]     IF ALL of the following conditions are met:
                 *    rod motion was stopped prior to reaching
                      doubling range or criticality
                 *    Bank D rods are below fully withdrawn position
                 *    Unit Supervisor concurrence is obtained to resume,
                 THEN
                 RESUME rod withdrawal USING 0-SO-85-1
                 to seventh doubling range or criticality (whichever comes first).   0 0 0 0
         [59)    IF any of the following conditions exist:
                  * - critical conditions cannot be achieved
                      within the +/-750 pcm termination band
                      OR
                  *    critical conditions cannot be achieved
                       within the +/-1000 pcm allowable limits
                       OR
                  *    critical conditions cannot be achieved above
                       rod insertion limit
                       OR
                  *    reactor startup must be aborted for other reasons,
                  THEN
                   PERFORM the following to abort reactor startup: [C.11]
              [59.1)     STOP rod withdrawal.
              [59.2)     INITIATE insertion of control banks.
              [59.3)     PERFORM Appendix 0 , Actions if Reactor Startup
                         Must Be Aborted.                                                o
              [59.4)     DO NOT CONTINUE this section.
l
     SQN             UNIT STARTUP FROM HOT STANDB Y 0-GO-2
     Unit 0                   TO REACTOR CRITICAL                Rev. 0026

( Page 64 of 85

       STARTUP No.               _               Unit       _                  Date   _
 5.3   Reactor Startup after a non-refueling outage (continued)
       [60]    IF reactor is subcritical with Bank 0 rods
               at fully withdrawn position,
               THEN
               PERFORM Appendix E, Actions if Reactor is Subcritical with
               Rods Fully Withdrawn.                                                0
       [61]    IF reactor is critical with SUR less than 0.3 DPM
               AND intermediate range NIS is less than P-6 (1 X 10-4 %),
               THEN
               PERFORM the following:
            [61.1]     IF Bank 0 control rods are BELOW
                       fully withdrawn position,
                       THEN
                       OPERATE control rods to establish a positive SUR
                       of approximately 0.3 DPM.
            [61.2]     IF Bank 0 rods have reached fully withdrawn position
                       AND Rx Engineering concurs with RCS dilution,
                       THEN
                       PERFORM RCS dilution (as recommended by Rx Eng)
                       to establish positive SUR of approx. 0.3 DPM
                        USING 0-SO-62-7.
      SQN            UNIT STARTUP FROM HOT STANDBY 0*GO-2
     Unit 0                  TO REACTOR CRITICAL                   Rev. 0026

c Page 65 of 85

         STARTUP No.                            Unit         _                   Date         _
 5.3     Reactor Startup afte r a non-refueling outage (continued)
         ISta rt of Critical Step(s)
                                            NOTES
  3) Blocking the SRM reactor trip with [HS-92 -50011 and [HS-92-5002] will disable the
     detector outputs and remove the audio count rate signal.
  4) Step 5.3[62] may be performed at time of criticality, if required. Source range reactor
     trip must be BLOCKED before trip setpoint of 105 cps.
         [62]    WHEN annunciator XA-55-4A , window D-2
                           P-6 INTERMEDIATE
                                  RANGE
                               PERMISSIVE         is LIT, THEN [C.2]
             [62.1]    RECORD both source range readings.
                     N-31_    _   CPS                  N-32           CPS
                                                                                     Initials
             [62.2]    RECORD both intermediate range readings.
                     N-35,        %RTP                N-36            %RTP
                                                                                     Initials
              [62.3]   VERIFY a minimum of one IRM channel greater than or
                        equal to 1 X 10.4 % RTP.                                            0
              [62.4]    BLOCK source range reactor trip by momentarily
                        placing [HS-92-5001] and [HS-92-5002] SRM TRIP
                        RESET-BLOCK P-6 handswitches to BLOCK.
                                                             Initials        Time            Date
        SQN            UNIT STARTUP FROM HOT STANDBY O-GO-2
        UnitO                 TO REACTOR CRITICAL                 Rev. 0026

( Paqe 66 of 85

          STARTUP No.             _               Unit       _                  Date          _
 5.3      Reactor Startup after a non-refueling outage (continued)
              [62.5]    VERIFY annunciator XA-55-4A, window C-1
                                   SOURCE RANGE
                                  TRAINS A & B TRIP
                                        BLOCK             is LIT.
                                                                                         o
          IEnd of Critical Step(s)
              [62.6]    SELECT NR 45 to record one intermediate range
                        channel and one power range channel.                             o
              [62.7]    ADJUST NR 45 chart speed as desired.
                     _  (N/A if no change needed).                                       o
          [63]    ENSURE PA announcement made to notify plant personnel
                  when the reactor is critical.                                          o
                                                NOTE
  When T-avg is less than 551°F and Tavg - Tref deviation alarm is lit, SR 4.1.1.4.b requires
  verifying lowest T-avg greater than or equal to 541 °F at least once per 30 minutes.
           [64]   IF Tavg - Tref deviation alarm [M-5A window C-6] is LIT
                  AND T-avg is less than 551°F,
                  THEN
                  PERFORM 0-SI-SXX-068-127.0 to satisfy SR 4.1 .1.4.b,
                  Minimum Temperature For Criticality.
     SQN             UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0                  TO REACTOR CRITICAL                  Rev. 0026

( Paae 67 of 85

       STARTUP No.               _               Unit      _                    Date   _
 5.3   Reactor Startup after a non-refueling outage (continued)
       [65)    RAISE reactor power to approximately 1 X 10.3 'Yo:
           [65.1)     IF Bank D control rods are BELOW
                      fully withdrawn position,
                      THEN
                      OPERATE control rods to establish a positive SUR
                      of approximately 0.5 DPM (not to exceed 1 DPM).
           [65.2)     IF Bank 0 rods have reached fully withdrawn position
                      AND Rx Engineering concu rs with RCS dilution,
                      THEN
                       PERFORM RCS dilution (as recommended by Rx Eng)
                      to establish positive SUR of approx. 0.5 DPM
                       USING 0-SO-62-7.
            [65.3] _ WHEN intermediate range NIS indicate
                       approximately 1 X 10.3 'Yo,
                       THEN
                       PERFORM the following :
               [65 .3.1)    STABILIZE reactor power using control rods.
                [65.3.2]    RECORD critical data indicated below.
       Powe r Level:         N-35          %RTP         N-36         %RTP
      Rod Position:                             RCS Boron concentration
                            Bank        Step                                 ppm
        Loop TAVG;
                                    1              2              3           4
                                                            Initials        Time     Date
        [66]     VERIFY control rods above rod insertion limit
                 USING 1,2-SI-OPS-000-002.0, Shift Log.                              o
        [67)     MAINTAIN reactor power stable with control banks
                 abo ve low insertion limit USING rod movement or
                 boration/dilution to compen sate for Xenon.                         o
     SQN              UNIT STARTUP FROM HOT STANDBY             0-GO-2
     Un it 0                  TO REACTOR CRITICAL               Rev. 0026

( Page 68 of 85

       STARTUP No.                _               Unit      _                 Date _
 5.3   Reacto r Startup after a non-refuel ing outage (continued)
       [68)     IF start up is to continue with one or both MFPTs available,
                THEN
            [68.1)     ENSURE Steps 5.1[13] throug h 5.1[15) have been
                       completed for applicable pump(s).
            [68.2]     VERIFY other applicable actions in Section 5.3
                       completed or initiated .
            [68.3]     GO TO 0-GO-3, Power Ascension From Reactor Critical
                       to Less Than 5% Reactor Power.
       [69)     IF start up is to continue with NO MFPT available ,
                THEN
             [69.1]     MARK Steps 5.1[13) through 5.1[1 7] as "N/A".
             [69.2]    VERIFY other applicable actions in Section 5.3
                        compl eted or initiated .
             [69.3)     GO TO 0-GO-3, Power Ascension From Reactor Critical
                        to Less Than 5% Reactor Power.
        [70]     IF startup is to be discontinued,
                 THE N
                 GO TO 0-GO-6, Power Reduction From 30 %
                 Reactor Power to Hot Standby.
                                            END OF TEXT
     saN          UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0             TO REACTOR CRITICAL                  Rev. 0026

( Page 69 of 85

 6.0   RECORDS
       Completed copies shall be transmitted to the Operations Superintendent's
       Secretary.
       SQN       UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0          TO REACTOR CRITICAL     Rev. 0026

( Page 70 of 85

                                Appendix A
                                (Page 1 of 1)
                                 DELETED
   1.0   DELETED
 (
           SQN             UNIT STARTUP FROM HOT STANDBY                0-GO-2
          Unit 0                    TO REACTOR CRITICAL                 Rev. 0026

( Paqe 71 of 85

'.
                                                   Appendix B
                                                  (Page 1 of 8)
                            MODE 3 TO MODE 2,1 REVIEW AND APPROVAL
             STARTUP No.                                Unit      _                    Date    _
   1.0       MODE 3 TO 2,1 REVIEW AND APPROVAL
                                                     NOTE
    Steps in this Appendix may be performed out of sequence, except for those steps that
    pertain to the Operations Superintendent Hold Point.
             [1]     PRIOR to entering Mode 2, 1, an SRO shall review the
                     follo wing:
                                                      NOTE
    Mode 3 to Mode 2, 1 Checklist and Reactor Trip Breaker Checklist are to be attached to
    this instruction .
                     A.     Mode 3 to Mode 2,1 Checklists from the respo nsible
                            sections and DETERMINE that the requi red surveillance
                            testing for Mode 2 entry has been comp leted .
                                                                                   Time     Date
                      B.    Reactor Trip Breaker Closure Checkl ists from the
                            responsible sections and DETERMINE that required
                            surveillance testi ng for mode change has been
                            comp leted .
                                                                                   Time     Date
                      C.    Active clearances for mode change restraints. [C .10].
                                                                                   Time     Date
                       D.    TACF Books for outstanding alternations on systems prior
                             to declaring a T .S. system or compo nent operable . [C.10]
                                                                                    Time    Date
     SQN        UNIT STARTUP FROM HOT STANDBY 0-GO-2
     Unit 0             TO REACTOR CRITICAL                    Rev. 0026

( Paae 72 of 85

                                      Appendix B
                                     (Page 2 of 8)
       STARTUP No.                          Unit         _                   Date      _
 1.0   MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)
            E.  O-TI -EXX-OOO-001.0, Electrical Jumper Control Log to
                determine if any potential T . S. restriction exists
                which would prevent a mode change.
                                                                         Time     Date
            F.  Active Procedures Book to determine equipment status
                that may be abnormal.
                                                                         Time     Date
            G.  OPDP-4, Annunciator Disablement Log for alarms
                affecting operability of equipment required for mode
                change .
                                                                         Time     Date
            H.  O-PI-OPS-301-001.0 Plant Computer Point Disablement
                 Log for alarms affecting operability of equipment required
                for mode change.
                                                                         Time     Date
            I.   Board walkdown is completed to verify proper equipment
                 alignment.
                 (Refer to appropriate CRO and OATe Pis for guidance)
                 [C.10]
                                                                          Time    Date
                                        -    ---  ---------
       SQN           UNIT STARTUP FROM HOT STANDBY 0-GO-2

c Unit 0 TO REACTOR CRITICAL

                                           Appendix B
                                                                Rev. 0026
                                                                Page 73 of 85
                                          (Page 3 of 8)
         STARTUP No.                             Unit      _                  Date       _
 1.0     MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)
                                              NOTE
  Tech Spec and T RM LCO 3.0.4 govern entering Mode 2 if any LCO requirement applicable
  in Mode 2 is not met. Therefore , mode change is not allowed while in a Tech Spec or
  TRM action UNLESS the exceptions and/or allowances stated in LeO 3.0.4 can be applied.
                 J.  REVIEW all Tech Spec and TRM Actions which have
                     been entered on the affected unit and common equipment
                     to verify that mode change is acceptab le.
                                                            SRO            Time        Date
                                                            SRO            Time        Date
      SQN           UNIT STARTUP FROM HOT STANDBY 0*GO-2
      UnitO                 TO REACTOR CRITICAL              Rev. 0026

( Page 74 of 85

                                        Append ix B
                                       (Page 4 of 8)
        STARTUP No.                           Unit       _                   Date    _
  2.0   DEPARTMENT MANAGERS REVIEW
  2.1   Period ic Tes t Coordinator:
        [1]    ENSURE that all surveillance requirements for mode 2 entry
               are updated and included within the mode change check list.
                                           Periodic Test Coordinator       Time   Date
        [2]    ENSURE that all surveillance requirements for Reactor Trip
               Breaker Closure Checklist are updated and included within the
               checkl ist. [C.9)
                                           Periodic Test Coordinator       Time   Date
  2.2   Instrument Maintenance:
        [1]    ENSURE Wide Range SG Level Recorders [LR-3-43A) and
               [LR-3 -98A) are OPERABLE and SET to a range requested by
               the operator. (Recommended range between 80 and 90% of
               scale). [C.6]
                                            Instrument Maintenance         Time   Date
  2.3    Fire Ops Section:
         [1]    ENSURE limitations as stated in 0-TI-SXX-000-016.0 are not
                exceeded .
                                           Fire Manager or Designee        Time   Date
l
        SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                  TO REACTOR CRITICAL                  Rev. 0026

( Paae 75 of 85

                                             Appendix B
                                            (Pag e 5 of 8)
          STARTUP No .             _                Unit       _                  Date      _
 2.4      Systems Engineering Section:
          [1)    REVIEW of mode change checklist is complete and all
                 surveillance requirements have met their acceptance criteria
                 for Mode 2 entry.
                                                       Shift Manager            Time    Date
          [2)    REVIEW of Reactor Trip Breaker Closure Checklist is
                 complete, all surveillance requirements have met their
                 accep tance criteria , and all open items that affect mode
                 change have been closed .
                                                       Shift Manager            Time    Date
                                                 NOTE
  Th e evaluation made by the Systems Engineer in the next step will prevent thermal shock
  to the PZR spray nozzle.
           [3]    ENSURE PZR spray line bypass valves are throttled to
                  maintain acceptable spray line temperature in accordance with
                  0-SO-68-3 .
                                                    System Engineering         Time    Date
           [4)    IF startup is following a refueling outage ,
                  THEN
                  ENSURE Present Cycle Core Operating Limit Report are
                  inserted in the unit's Technical Specification Binder. [C.7)
                                                         Licensing or designee    Time   Date
       SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
       Unit 0                 TO REACTOR CRITICAL                 Rev. 0026

( Paqe 76 of 85

                                           Appe ndix B
                                          (Page 6 of 8)
          STARTUP No.            _                 Unit      _                  Date      -r-
 2.5      Maintenance Section:
          [1 ]  REVIEW of mode change checklist is complete and all
                surveillance requirements have met their acceptance criteria
                for Mode 2 entry.
                                                          Shift Manager         Time   Date
          [2]   REVIEW of Reactor Trip Breaker Closure Checkiist is
                complete, all surveillance requirements have met their
                acceptance criteria, and all open items that affect mode
                change have been closed.
                                                          Shift Manager         Time   Date
 2.6       Chemistry Sect io n:
                                               NOTE
  The following step does not require a new analysis to be performed for this startup.
  Routine analysis is sufficient unless there is reason to suspect chemistry has been
  changed .
           [1]   ENSURE reactor coolant chemistry within limits of Technical
                 Requirements Manual 3.4.7 as determined by the Chemical
                 Shift Supervisor.
                                                   Chemical Shift Supervisor     Time  Date
                                          - ------             ----
       SQN           UNIT STARTUP FROM HOT STANDBY                 0-GO-2
       UnitO                TO REACTOR CRITICAL                    Rev. 0026

( Page 77 of 85

                                          Appendix B
                                         (Page 7 of 8)
         STARTUP No.                             Un it         _                   Date      _
   3.0   SHIFT MANAGER (SM) HOLD POINT
         [1)   ENSURE Tech Spec and non-Tech Spec work related
              activities are completed or will not prohibit entry or impact
               co ntinued operatio n in Mode 2.
                                                               SM              Time     Date
         [2]   ENSURE no open DCN/ECNs that wou ld prohibit a mode
               change . (SM concurrence with the Modifications Manager or
               des ignee).
                                                                SM             Time     Date
         [3]   REVIEW all open work activities relative to the unit for the
               purpose of iden tifyi ng mainte nance act ivities that could affect
               system ope rability prior to mode change
                                                                8M             Time     Date
          [4]  IF any potential Tech Spec. mode constraint exists ,
               THEN
               OBTAIN Operations Superintendent reso lution prior to
               proceeding with the mode change
                                                                8M             Time     Date
 l
     SQN           UNIT STARTUP FROM HOT STANDBY                0-GO-2
     Unit 0                TO REACTOR CRI TICAL                  Rev. 0026

( Page 78 of 85

                                         Appendix B
                                        (Page 8 of 8)
       STARTUP No.                              Un it       _                  Date     _
 3.0   SHIFT MANAGER (SM) HOLD POI NT (continued)
       [5]   IF th e startup follows a reactor trip or an eme rgency shutdown,
             T HEN
             A.    ENSURE cause of the trip/shutdown has been determined
                   and will not im pact Mod e 2 entry.
                                                            SM             Time       Date
              B.   ENSURE Reactor trip report is comp lete.
                   (O-T I-QXX-OOO-001.0 , Event Critique, Post Trip Report,
                 _ Equipment Root Cause and Outage Milestone PER
                   Evaluation)
                                                             SM            Time       Dat e
              C.    ENSURE O-GO-12 , Realignment of Secondary Equipment
                    Following Reactor TripfTurbine Trip/Em ergency
                    shutdown, is comp lete.
                                                             SM            Time       Date
 4.0    OPERATIONS SUPERINTENDENT HOLD POINT
        Operations Superintendent or his designee con cur s and grant s approval to
        proceed to Mode 2, 1.
                                              Operations Superintend ent        T ime  Date
      SQN            UNIT STARTUP FROM HOT STANDBY                 0-GO-2
     UnitO                    TO REACTOR CRITICAL                  Rev. 0026

( Paae 79 of 85

                                               Appendix C
                                              (Page 1 of 1)
                 DETERMING SOURCE RANGE COUNT RATE DOUBLING
 1.0    Calculating Doubling Range
                                                 NOTES
  1) Source rang e reading shall be allowed to stabilize for approximate ly 3 minutes
     after each reactivity change prior to determining new stable count rate.
  2) The highest reading channel should be used when determining stable count rate.
     Digital indication on shutdown monitor [M-13] is preferred.
  3) Doubling range is used to determine when rod motion should be stopped during
     approach to criticality. Criticality is expected in about 5 to 7 count rate doublings.
  4) This appendix may be performed and IV'd by operators, STA, or Rx Engineers.
      STABLE              COUNT RATE DOUBLING RANGE                            INITIALS
  COUNT RATE (CR)          CR X 1.75 =               CR X 2.0 =          1st              IV
                         (Lower value not used
                            for first doubling)
                                              End of Section
           SQN              UNIT STARTUP FROM HOT STANDBY 0-GO-2
           Unit 0                   TO REACTOR CRITICAL                    Rev. 0026

( Paqe 80 of 85

                                                  Appendix D
                                                 (Page 1 of 1)
                          ACTIONS IF REACTOR STARTUP MUST BE ABORTED
             STARTUP No.               _                 Unit _---..,_                  Date     _
    1.0      Operator Actions
                                                   CAUTION
     If reactor t rip is required, E-O should be performed inste ad of th is appe ndix.
             [1 ]      ENSURE all control bank rods FULLY INSERTED
                       in accordance with 0-SO-85-1 .
             [2]       LOG Mode 3 entry in narrative log.
             [3]       VERIFY adequate shutdown margin in accordance with
                       0-SI-NUC-000-038 .0.
                                                                    Initials         Time    Date
              [4]       DETERMINE and CORRECT cause of the discrepancy.                      o
              [5]      WHEN reactor startup is to resume,
                       THEN
                        PERFORM the following:
                   [5.1]      RECALCULATE estimated critical conditions in
                             accordance with 0-RT-NUC-000-003.0 (Startup
                             after refueling) or 0-SI-NUC-000-001.0 (Startup
                              after non-refueling outage).
                   [5.2]      DILUTE/BORATE in accordance with 0-SO-62-7
                              to the estimated critical boron concentration. [C.12]
                   [5.3]      EQUALIZE boron concentration (within 50 ppm)
                              between reactor coolant loops and pressurizer
                              by operating pzr heaters and spray. [C.12]
                    [5.4]     RE-INITIATE 0-GO-2.
                                               End of Document
 \.
                                                             ---- ~--=-=::----------
        SQN               UNIT STARTUP FROM HOT STANDBY               0-GO-2
        Unit 0                   TO REACTOR CRITICAL                  Rev. 0026

( Pane 81 of 85

                                                Appe nd ix E
                                               (Page 1 of 2)
    ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY
 1.0      Operator Actions
                                                   NOTE
  Allowabl e upper limit for critical posit ion may be above the fully withdrawn position on
  Bank D. If Reactor Engineering determines that core response is within acceptable limits,
  this app endix allows RCS dilution to assist in achieving criticality.
           [1]      CONSULT Reactor Engineering to determine
                    if core response is within acceptable limits.                            D
           [2]      IF projected critical rod position exceeds +1000 pcm limit
                    OR startup will be aborted due to failing to achieve criticality,
                    THEN
                [2.1]      PERFORM Appen dix D, Actions if Reactor Startup Must
                           Be Aborted.                                                       D
                [2.2]      DO NOT CONTINUE this appendi x.                                   D
           [3]       ENSURE contro l bank 0 inserted to less than or equal to
                     estimated critical position determined in
                     0-RT-NUC-000 -003.0 (Startup after refueling)
                     or 0-SI-NU C-000-001 .0 (Startup afte r non-refueling outage ).
            [4]      DETERMINE dilution volume to increase core reactivity
                     by 100 pcm OR as recommended by Rx Engineering.
                                                                                         Rx Engineer
                   _ _ __ _ gallons
                                                                                             IV
       SQN           UNIT STARTUP FROM HOT STANDBY                 0-GO-2
       Unit 0                TO REACTOR CRITICAL                    Rev. 0026

( Paqe 82 of 85

                                           Appendix E
                                          (Page 2 of 2)
         STARTUP No.            _                 Unit        _                   Date   _
 1.0     Operator Actions (continued)
                                            CAUTION
  NIS indications should be carefully monitored during and following dilution .
         [5]    PERFORM specified dilutio n USING 0-SO-62-7.                           o
         [6]    WHEN at least 30 minutes has elapsed for ReS mixing
                AND Rx Engineer concurs with resumin g startup,
                TH EN
                RETURN to appropriate step (based on number of doublings)
                in Sect. 5.2 (Startup after refueling ) or Section 5.3 (Startup
                after non-refueling outage ).                                          o
                                       End of Documen t
           SQN            UNIT STARTUP FROM HOT STANDBY 0-GO-2
          Unit 0                 TO REACTOR CRITICAL              Rev. 0026

( Page 83 of 85

                                           Source Notes
                                            (Page 1 of 3)
                                                                               Implementing
          Requirements Statement                   Source Document               Statement
  Verify MFWP trip bus energized before              LER 328 /88-014                C.1
  entry into Mode 2.
  Revise GOI-2 to require verification of           NCO 89011800 2                  C.2
  intermediate range (IR) status at                  LER 328/89006
  approximately 20 and 25 percent,                   S53890531 844
  verify source range (SR) status and                  JRB to NRC
  channel check at I ~wer power , monitor
  core delta Ts at low-power levels and
  during power escalation and compare
  with NIS response, and verify that the
  IR rod stop and trip bistables come in
  at the appropriate power level during
  power ascens ion.
   Following refueling operations                     SOER-90-003                    C.3
   relocation of NIS or modifications                NCO 900107009
   affecting the NIS response , provide               NER 1187001
   adequate reductions of trip setpoint             LER 327/90011 R1
   and limitations of reactor power until
   accuracy of the NIS is verified. Also ,
   provide alternate indications of power
   independent of calorimetric
   calculations during power ascens ions.
   Decommitted 3/12 /99                                                              C.4
   Assu rance that TSC computer is reset       Verbal commitment to NRC at           C.5
   prior to startup ; defines "reset" and         SNP Meeting 10104/90
   "updating". (Modified C.5 permitting
   relaxing requirement.)
    Provis ions to ensure that enhanced              NCO 890097004                   C.6
    steam generator level recorders are               L44 890505 805
(   operable in the main control room prior
    to entering mode 2.
          SQN          UNIT STARTUP FROM HOT STANDBY 0-GO-2
          Unit 0               TO REACTOR CRITICAL                 Rev. 0026

( Page 84 of 85

                                            Source Notes
                                            (Page 2 of 3)
                                                                                Implementing
          Requirements Statement                   Source Document                Statement
 Based upon the requiremen ts of the             PORC Minutes #50880                 C.7
 May 6, 1991 PORC meeting this                      5/06/91T/S 91-08
 verification has been added to
 implem ent the referenced Technical
 Specification chang e for the Core
 Operating Limits Report.
 Consult Reactor Engineering for                      NER 89 0794                    C.8
 guidan ce during evolutions of unusual               OER 89 3497
 power maneuvers at end of core life.
 Provide reactor trip breake r closure            U1C5 Outage Critique                C.9
 checklists to ensure all surveillan ce                     item
 requirem ents for reactor trip breaker
 closure are satisfied.
  Revise GOI-2 to include a step signoff                II S-92-045                  C.10
  with the TACF review, hold order
  review etc. section of GOI , for the Duty
  SOS to ensure a board walkdown to
  verify proper alignm ent is performed by
  a designated SRO prior to mode
  change.
  Operations startup procedures should:                SOER 88-02                    C.11
  1) Stress conservative actions and                  NER 88047400
  complian ce with written procedures
  when repositioning control rods ,
  2) Guidance on actions when criticality
  will be achieved outside the ECC
  toleran ce band ,
  3) Avoid activities which dist ract the
  operators ,
  4) Directions to use pertinent
  instrumentation to monitor approach to
   criticality ,
   5) Periodic pauses during rod
   withdrawal.
             SQN           UNIT STARTUP FROM HOT STANDBY 0-GO-2
            Unit 0                TO REACTOR CRITICAL            Rev. 0026

(-, Page 85 of 85

                                            Source Notes
                                            (Page 3 of 3)
                                                                              Implementing
            Req ui reme nts Statement               So urce Document            Statement
    Operator Controls and monitoring               INPO SOER 94-002                C.12
    activities involving possible boron
    concentration reduction which could
    result in unplanned reactivity changes.
    Procedures that do NOT contain               TRO I NCO 970071001               C.13
    app ropriate verification requirements
    will be revised. (This item is NOT
    annotated within the procedure, since
    the entire procedu re must meet the
    verification program requirements .
 c.
 (

I ~

                                                                       .--
       SQN             UNIT STARTUP FROM HOT STANDBY                a-GO-2 )
       Unit a                   TO REACTOR CRITICAL                 Rev. 0025
                                                                    Page 79 of 85
                                                 Appendix C
                                                (Page 1 of 1)
                  DETERMING SOURCE RANGE COUNT RATE DOUBLING
  1.0    Calculating Doubling Range
                                                   NOTES
   1) Source range reading shall be allowed to stabilize for aporoximately 3 minutes
      after each rea ctivity change prior to determining new stable count rate.
   2) The highest reading channel should be used when determining stable count rate.
      Digital indication on shutdown monitor [M-13] is preferred .
   3) Doubling range is used to determ ine when rod motion should be stopped during
      approach to criticality. Criticality is expected in about 5 to 7 count rate doublings.
   4) This appendix may be performed and IVd by operators, STA, or Rx Engineers.
                     --
       STABLE               COUNT RATE DOUBLING RANGE                           INITIALS

c , COUNT RATE (CR) CR X 1.75 =

                          (Lower valu e not used
                                                      CR X 2.0 =           1st              IV
        ZD                   for first doubling)         t.f:6           CY--         r;2-
       4:0                         70                     I?O            rtL           ~
       00                          13~                   IS9             c..          ~
      I S~                         2 7f                  ]('(           2-              <>::
      3 1~                          5'50                 4?3)           2-              {.--
      (j3 5                       I {( (                 /270             ~                ~
      (2- 7 D                     2 Z2-7.----         2 SZiO               W'----         ur-
                                               End of Section
    SON               ESTIMATED CRITICAL CONDITIONS                         0-SI -NUC-000-001 .0

c 0 Rev 5"::::::::-

                                                                            Page 35 of 42
                                                APPENDIXC
                                                Page 8 of 10
                      MONITORING THE APPROACH TO CRITICALITY
                                            DATA SHEET C-1
                ICRR DURING ROD WITHD RAWAL FOR CHANNEL N-32
 UNIT    \            CYCLE                                                     DATE ,...-ro Oo')'
     ECC:- -'PPM \.5"~ STEPS                                                                            T
                                                                        .
                                                      . I
                                                                        I
                                                                        I   "'.
                             ,l,"                   ' I
                              I
                                                                        :     :
     ..
                                                        :               :
     "
                                                                :                       :
     e
                                                                        :     :
                                                        :       :       :     :
                                                        :               :     :
     "
                               :                                 :       :              :
     'A
                                                         :               :
                               :                                 :                      :
     o                                                   :               :
                               :
     "
                   '"
                                    ,,,
                                                     "'I      .          "'I                ...
                 COUNT            SECS            Cr;      BANK       STEPS     ICRR           INITIALS
          CRO     iq -                                                           1.00             /"-"
          CR 1    3 '1                                                             .'1if           r-/
          CR2      7 "\'                                                         ;Z-L/         A/
          CR3      /,5                                                           . ,,1-       .........
          CR4
           CR5
                   -';o g' _
                  6 / '<;'
                                                                                  , t lo
                                                                                 . u)         ---
                                                                                              "--
                                                                                                -../'
          CR6     12.7U                                                          . ciS
           CR7
           CR8
           CR9
           REVIEWED BY - --            -=:-:-::=-=-=0-==-- -       DATE                     _
                                        REACTOR ENGR

( l

( TENNESSEE VALLEY AUTHOR ITY

                      SEQUOYAH NUCLEAR PLANT
                  SYSTEM OPERATING INSTRUCTION
                                   0-50-85-1
                     CONTROL ROD DRIVE SYSTEM
                                  Revision 32
                              QUALITY RELATED
 PREPARED BY:                  JENNIFER REGAN
 RESPONSIBLE ORGANIZATION:         OPERATIONS
 APPROVED BY:                W. T. LEARY
                                                EFFECTIVE DATE:       1211112006
 LEVEL OF USE: CONTINUOUS USE
 REVISION
 DESCRIPTION:  Revised to incorporate the new reactor breaker close control switch,
               2-HS-99-7, per DCN D21843A.
  PERFORMANCE OF THIS PROCEDURE COULD IMPACT REACTIVITY

l

      SQN                     CONTROL ROD DRIVE SYSTEM                                              0-SO-85-1
       1,2                                                                                          Rev 32

( Page 2 of 77

                                              TABLE OF CONTENTS
                                                         Page 1 of 2
 Section Title                                                                                                                    Page
 1.0       INTRODUCTION                                                                                                              4
 1.1       Purpose                                                                                                                   4
 1.2       Scope ................................................................................................................    4
 2.0       REFERENCES..................................................................................................              4
 2.1       Performance References                                                                                                    4
 2.2       Developmental References...............                                                                                   4
 3.0       PRECAUTIONS AND LIMITATIONS... .............................................................                              6
 4.0        PREREQtJlSITE ACTIONS                                                                                                    9
 5.0       STARTUP/STANDBYREADINESS.................................................................                                10
 5.1        Placing MG Set(s) in Standby Readiness.........................................................                         10
 5.1.1      Placing MG Set A In Service With MG Set B NOT Operating                                                                 12
 5.1 .2     Placing MG Set B In Service With MG Set A NOT Operating                                                                 15
 5.2        ReseUClose Reactor Trip Breakers                                                                                        18
 6.0        NORMAL OPERATION                                                                                                        21
 6.1        Placing MG Set A In Service With MG Set B Operating                                                                     21
 6.2        Placing MG Set B In Service With MG Set A Operating                                                                     30
 6.3        Manual Operation of Rod Control System Below 15 Percent Power                                                           39
 6.4        Transferring from Manual to Auto Rod Control..... ............................................                          52
  6.5       Transferring from Auto to Manual Rod Control. ................................................                          53
  7.0       SHUTDOWN.....................................................................................................           54
  7.1       Removing the MG Set A From Service                                                                                      54
  7.2       Removing the MG Set B From Service                                                                                      55
       SQN                  CONTROL ROD DRIVE SYSTEM                0-SO-85-1
        1,2                                                         Rev 32

( Page 3 of 77

                                        TABLE OF CONTENTS
                                               Page 2 of 2
  Sect ion Title                                                                    Page
  8.0       INFREQUENT OPERATION                                                  .   56
  8. 1      Alternate Method of Paralleling MG Set A                             ..   56
  8.2       Alt ern ate Method of Paralleling MG Set B                           ..   58
  8.3       Resetting Step Counters After Withdrawing Rods Above 23 1 Steps      ..   60
  8.4       Resetting Step Counters After Inserting Rods Below 0 Steps           ..   61
  8.5       Placin g MG Set A In Service for Maintenance                         ..   62
  8.6       Placin g MG Set B In Service for Mainte nance                        ..   69
  9.0       RECORDS                                                               .   76
            SOURCE NOTES                                                              77
            ATTACHMENTS
            ATTACHMENT 1:         CONTROL ROD DRIVE SYSTEM
                                  POWER CHECKLIST 1-85-1 .01
            ATTACHMENT 2:         CONTROL ROD DRIVE SYSTEM
                                  POWER CHECKLIST 2-85-1.01
(
 --- ---------             ---------
         SQN                 CONTROL ROD DRIVE SYSTEM                     0-SO-85-1

c 1,2 Rev 32

                                                                          Page 4 of 77
    1.0       INTRODUCTION
    1.1       Purpose
              This instruction provides the steps necessary for the operation of the Control Rod
              Drive System.
    1.2       Scope
              This instru ction provides detailed steps for the following operations:
              Placing Control Rod Drive MG Sets in Service
              Removing Control Rod Drive MG Sets from Service
              Parallel Operation of Control Rod Drive MG Sets
               Manual Operation of the Control Rod Drive System
              Transferring Rod Control from Manual to Auto
              Transferring Rod Control from Auto to Manual
    2.0        REFERENCES
    2.1        Performance References
               A.   Procedures
                    1.   0-SI-NUC-000-038. 0, Shutdown Margin
                    2.   1,2-PI-IFT-099-0P4.0, Verification of P4 Contacts
               B.   Tech Specs
                    1. 3.4.1.2
               C.   Westinghouse Tech. Bulletin
                     NSD-TB-92-05RO
     2.2       Developmental References
               A.   Tech Specs
                    1.   3.1.3.1
                    2.   3.1.3.2
                    3.   3.1.3.4
                    4.   3.1.3.5
                    5.   3.1.3.6
       SQN             CONTROL ROD DRIVE SYSTEM 0-80-85-1

( 1,2 Rev 32

'.                                              Page 5 of 77
   2.0      REFERENCES (Continued)
            B. Technical Requirements Manual
               1.   TR 3.1.3.3
            C. F8AR
               1.   7.7.1.2.1
            D. TVA Drawings
               1.   45N699 -1
               2.   45N777-3
               3.   45N703-1, 2, 3,4
               4.   45N1646 -4
               5.   45N2646-4
               6. _ 45N1624 -1, 2, 3,4, 5, 8
                7.  45N2624-1, 2, 3,4 , 5, 8
                8.  617F619

c

     SQN                CONTROL ROD DRIVE SYSTEM                     0-SO-85-1
      1.2                                                            Rev 32

( Page 6 of??

 3.0      PRECAUTIONS AND LIMITATIONS
          A.  Rod thermal lock-up is NOT a concern when the reactor trip breakers are
              OPEN. If reactor trip breakers are CLOSED and an RCS cooldown of
              greater than 50°F is planned , the shutdown and control banks should be
              withdrawn at least 5 steps each . This will limit the possibility of "thermal lock-
              up" of the rods. This does not apply if performing sections 8.5 or 8.6.
          B.  If both MG sets are to be shutdown, the control rods and shutdown rods shall
              be insert ed in the core and the reactor trip breakers OPEN prior to shutting
              down the MG sets.
          C.  Reactor Trip Breakers shall NOT be closed while in Mode 3 unless in
              compliance with LCO 3.4.1 .2.
          D.  Failure to perform 1,2-PI-IFT-099-0P4.0, Verification of P4 Contact s could
              resu lt in the prevention of AUTO SI if required.
          E.  Under normal conditions , the control rod banks must be withdrawn and
              inserted in the prescribed sequence. For withd rawal the sequence is
              Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown
              Bank D, Control Bank A, Control Bank B, Control Bank C, and Control Bank
              D. The insertion sequence is the reverse of the withdrawal sequence .
          F.   For manual bank sequencing , the prescribed withdrawal and insertion
               sequence should be followed . Rod motion of the correct bank should be
               monitored by observing the group step counters and the rod position
               indicators.
          G.   During Control Rod withdrawal , the Controi Banks should be monitored for
               bank overlap .
          H.   The control banks must be maintained above their respective insertion limits
               (Low-Low Alarm to ensure adequate shutdown in the event of a reactor trip , to
               ensure that maximum possible ejected rod reactivity limits are maintained and
                to ensure acceptable core power distributions.
           I.   Before withdra wing any rod bank from the fully inserted position, the group
                step counters and the rod position indicators for that bank must be at zero
                steps .
     SQN               CONTROL ROD DRIVE SYSTEM                        0-SO-85-1

c 1,2 Rev 32

                                                                       Page 7 of 77
 3.0      PRECAUTIONS AND LIMITATIONS (Continued)
              J.    Deleted
          K.  The Control Rods shall NOT be stepped or tripped unless the RCS pressure
              is at least 100 psig.
          L. RPl s and step counters shall be maintained within limits
             per TS 3.1.3.1 and 3.1.3.2.
          M. Continuous rod motion shall comply with these restrictions:
              CRDM OUTLET                      ROD MOTION LIMITS
             TE MPERATURE
                   " 190°F           10 minutes ON           20 minutes OFF
                   " 200°F            6 minutes ON           24 minutes OFF
             Tim e limitations are due to a lower air flow rate of 48 ,000 cfm across the
             shroud combined with a higher temperature (Reference TSIR-97-BOP-30-636
             and We stinghouse Letters RIM's #B38931005806, B38930920800, and
             8 38931 005803).
          N. The following failures will render the rod control system incapable of
             automatic and / or manual motion without any annunciation or indicatio n:
             1) Hand switch failure; 2) relay failure, and 3) failure of both 100v DC power
             supplies (PS3 and PS6) simultaneously.
          O. Defeating or restoring Tavg/Delta T or NIS chan nel may cause step change in
             input to rod control. A delay of at least 3 minutes prior to returning rod control
             to auto matic will allow lead/lag signal to decay off.
     SON                CONTROL ROD DRIVE SYSTEM                        0-SO-85-1
      1,2                                                               Rev 32

( Page 8 of 77

 3.0      PRECAUTIONS AND LIMITATIONS (Continued)
          P. Directiona l Overcurrent Relay Targ ets are reset by depressing the Relay
             Target Reset Pushbutton on the panel to break the target coil seal in circuit
             and th en lifting the mechanical reset at the bottom of the relay cover.
          Q.  US I SRO Oversight for control rod manipulation shall include :
              1.   Prior to Rod Movement
                   a.     Ensure RPI's within T.S. range (+ or - 12 steps)
                   b.     Ensure delta flux will not be adversely affected
                   c.     Ensure Ta vg and Rx Thermal power will not be adversely affected
                   d.     Verify on target with Rx Eng reactivity balance sheet
                    e.    Verify power chan ge will not exceed hourly rate
                    f.     Ensure no simultaneous reactivity manipulations in progres s
                           (Le.: borations, dilutions or turbine load change s)
              2.    During Rod Movement
                    a.     Ensure RO has peer check
                    b.     Ensure RO is following procedu re
                    c.     Ensure RO under stands how many steps they are moving rods
                    d.     Ensure RO has checked all the above mentioned items
                    e.     Watch performance of rod manipulation while listening to audib le
                           indication of rod step
                    f.     Ensure peer check is doing their job
                    g.     Re-verify steps a - d of initial evalua tion
                     h.     Ensure procedure is follo wed placing rods back to auto
                           (Tavg - Tref mismatch)
                     L      Monitor plant for expected response

---====----"==~ .== = = =='----._----

         SQN               CONTROL ROD DRIVE SYSTEM                     0-SO-85-1

(' 1,2 Rev 32

                                                                        Page 39 of 77
    Unit        (                                                                Date 'tH~
    6.3       Manual Operation of Rod Control System Below 15 Percent Power
              CAUTION        If reactor trip breakers are CLOSED and an RCS cooldown of
                             greater than 50°F is planned, the shutdown and control banks
                             should be withdrawn at least 5 steps each. This will limit the
                             possibility of "thermal lock-up" of the rods. Thermal lock-up is
                             NOT a concern during unit heatup.
              NOTE        Continuous rod motion shall comply with these restrictions :
                       CRDM OUTLET                 ROD MOTION LIMITS
                      TEMPERATURE
                           <190°F            10 minutes ON       20 minutes OFF
                           <200°F             6 minutes ON       24 minutes OFF
              [1]  ENSURE Section 5.2, Reset/Close Reactor Trip
                   Breakers has been compieted.
              [2]  IF the shutdown and control rods were withdrawn 5 steps
                   to prevent thermal lockup during an RCS cooldown ,
                   THEN
                   ENSURE rods are fully inserted prior to withdrawal.                 ,Itt. 1MM5-
                                                                                         1st   cv
              NOTE            ROD CONTROL STARTUP STEP COUNTER
                              RESET (SUS on M-4) Resets:
                               A.     All GROUP STEP COUNTERS on the Control Board.
                               B.     The master cycler reversible counter.
                               C.     All slave cycler counters.
                                D.    The bank overlap counter.
                                E.    All internal memory and alarm circuits.
                                F.    All pulse-to-analog converters in the Rod Position
                                       Indication System.
               CAUTION         ROD CONTROL STARTUP STEP COUNTER RESET
                               (SUS on M-4) should never be held in STARTUP position for any
                               extended period of time. Holding this switch in STARTUP
                               position may cause damage to the counters.
c.             [3]  MOMENTARILY PLACE [SUS], Rod Control Startup
                    Step Counter Reset to the STARTUP position to reset
                    Control Rod Drive System.
       SQN              CONTROL ROD DRIVE SYSTEM                   0-SO-85-1
        1,2                                                        Rev 32

( Page 40 of 77

  Unit                                                                      Date J1l/)"'1
  6.3       Manual Operation of Rod Control System Below 15 Percent Power (Continued)
            CAUTION .     Before withdrawing any rod from the fully inserted position , all
                         Group Step Counters and all Rod Position indicators must be at
                         zero steps.
            [4]  ENSURE all Full Length Rod step counters reset to zero.
            [5]  VERIFY rod control IN-OUT direction lights are NOT LIT .
            [6]  DEPRESS [RCAS] , Rod Urgent Failure Alarm Reset.
            [7]  RESET Window 6 (A-6), ROD CONTROL SYSTEM
                 URGENT FAILURE alarm on panel [XA*55-4B] using
                 [XS-55-4A] , Annunciator RESET/ACKITEST Switch.
             [8] VERIFY the following rod control system alarms on panel
                 [XA-55-4B] are NOT LIT:
                                    WINDOW         NOT LIT
                                     NUMBER        N)
                                      5 (A5)          IB'
                                      6 (A6)          ~
                                      11 (B4)         IE"'
                                      12 (B5)         10"
                                      13(B6)          iW
                                      18 (C4)         Il:i1
                                      19(C5)           ~
                                      27 (06)          &r
                                      34 (E6)          1!6
                                                                                  11/
(
      SQN                   CONTROL ROD DRIVE SYSTEM                        0-50-85-1
       1,2                                                                  Rev 32

( Page 41 of 77

 Unit          I                                                                     Date 110"1
 6.3       Manual Operation of Rod Control System Below 15 Percent Power
           (Contin ued )
           [9] ENSURE Plan t computer points for rod ban k position are
                 ZERO using th e following computer points :
                 COMPUTER PT                  ROD BANK                 -,J
                        U0049                  Control A              [JJ'"
                        U0050                  Con trol B             lit"
                        U0051                  Control C              Ii;1(
                        U0052                  Control D              [B'"
                        U0053                 Shutdown A              I!2f
                        U0054                 Sh utdown B             IB'"
                        U0055                 Shutdown C              IB"
                                                                       ~
                      - U0056                 Shutd own D
            [10] MONITOR Control Rod position USING Rod Position Indicators
                   ICS screen 30 minute trend during SD & Control Ban ks
                   with drawal to aid in det ectin g rod misalignm ent.
            [11] IF Individual Rod Pos ition Indicatio n does not indicat e proper rod
                  po sition d uring withdraw al of SD Ban ks , THEN
                  [a]   STOP rod withdrawa l.                                                   f.Zi f?
                  [b] ENSURE subcriticality.                                                    k!jJ:J
                  [e] CONTACT MIG
                        AND
                         INITIATE troubleshooting.                                              I!jlt
                  [d]    IF troubleshooting does not resolve the problem ,
                         OR
                         sub criticality can NOT be verifie d ,
                         THEN
                         INITIATE Rea ctor TRIP .                                               iliff
             [12] IF Individual Rod Position Indication does not ind icate pro per rod
                   po sition during withdraw al of Control Ban ks , THEN
                   GO TO AOP-C.01 se ction 2.6 Rod Pos ition Indicator (RPI)
                   Malfunction - Modes 1 or 2.                                                  ~A
       SQN              CONTROL ROD DRIVE SYSTEM                     0-SO-85-1
        1,2                                                           Rev 32

( Page 42 of 77

 Unit.         (
              -'-     _                                                          Date TIJ0'1
 6.3        Manual Ope ration of Rod Cont rol System Below 15 Percent Powe r
            (Continued)
            CAUTION      Unde r normal co nditions control rod banks mus t be withdrawn
                          and inserted in t he prescribed sequence. For w ithdrawal, the
                          sequence is Shutdown Bank A, Shutdown Bank B, Shutdown
                          Bank C, Shutdown Bank D, Control Bank A, Control Bank B,
                          Control Bank C, Control Bank D. The insertion sequence is the
                          reve rse of the withdrawal seq uence.
            NOTE 1        Startup rate, Source range, Intermediat e range , Nuclear
                          Instrumentation recorders, Group Step Counters and the
                          Rod Position Indicators should be monitored during each
                          bank withdrawal.
             NOTE 2      The following failures will render the rod control system incapable
                         of automatic and / or manual motion without any annunciation or
                         indication: 1) Hand switch failure; 2) relay failure, and
                         3) simultaneous failure of both 100v DC power supplies (PS3 and
                         PS6)
             [13] PLA CE [HS*S5-51101, Rod Control Mode Selector to the
                  SBA position.                                                      1lL 1 ~
                                                                                      1st    CV
             [14] VERIFY Rod Speed Indicator [SI-412]. indicates
                  64 Steps/minute.                                                   1!I£. / ~
                                                                                      1st    CV
       SQN                CONTROL ROD DRIVE SYSTEM                      0-SO-85-1
        1,2                                                             Rev 32

( Page 43 of 77

  Unit        --:(___                                                            Da te-L=~_
  6.3       Manual Operation of Rod Control System Below 15 Percent Powe r
            (Continued)
            NOTE            Monitor Group Step Counters, Rod Position Indicator
                            and the "IN-OUT" status lights to ensure anticipated
                            motion as each bank is being withdrawn. Rod speed
                            indicator should be reading 64 steps per minute.
            [15] ENSURE Shutdown Bank A demand position counters
                 operational by performing the following: [C.2]
                 [a]  BUMP [HS-85-5111] , Rod Control Switch to withdraw Shutdown Bank A
                      one-half step at a time, for one full step.
                                                                                      ~ I /11M(
                                                                                       1st  cv
                  [b] CHECK group demand position counters advance properly .
                 [c]  BUMP [HS-85-5111] to withdraw Shutdown Bank A
                      one-half step at a time, for the second full step.
                                                                                      JJ1L /~
                                                                                       1st  CV
                  [d] VERIFY group demand position counters advance properly.
                  [e] IF group demand position counters do NOT advance properly,
                      THEN
                      A.      STOP rod withdrawal.                                            .Q2>>.
                       B.     INITIATE WO to have counter repaired.                           fi[1r
                      C.      WHEN counter is repaired , THEN
                              1.      ENSURE Shutdown Bank A fully INSERTED.                   ~
                              2.      RETURN to beginning of this step.                       ,fjd-
             NOTE            The fully withdrawn position for shutdown and
                             control rods is defined by TI-28, Atl. 6.
             [16] WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN
                   position using [HS-85-5111] .                                      ~ /IIIW
                                                                                        1st  CV
(
       SQN                 CONTROL ROD DRIVE SYSTEM                         0-SO-85-1
        1,2                                                                 Rev 32

( Page 44 of 77

 Unit.       1                                                                       Date'--L"""'"tDJ-_
 6.3        Manual Operation of Rod Control System Below 15 Percent Power
            (Continued)
            [17] PLACE IHS-85-5110], Rod Control Mode Selector to the
                  SBB position.                                                            ,( /t( I /UW{
                                                                                            1st      CV
            [18] VERIFY Rod Speed Indicator [51-412], indicates
                   64 Steps/minute.
            NOTE             The following failures will render the rod control syste m incapable
                             of automatic and / or manu al motion without any annunciation or
                             indication: 1) Hand switch failure; 2) relay failure, and
                             3) simultaneous failure of both 100v DC power supplies (PS3 and
                             PS6).
            [19] ENSURE Shutdown Bank B demand position co unte rs
                 o pera tional by perf orming the followin g: [C.2]
                 [a]  BUMP [HS-85 -5111], Rod Control Switch to withdraw Shutdown Bank B
                      one-ha lf step at a time , for one full step .
                                                                                          .iJtL I AlI'i.
                                                                                             1st     cv
                  [b] CHECK group demand position counters advance properly.
                 [c]   BUMP [HS-85-5111] to withdraw Shutdown Bank B
                       one -ha lf step at a time , for the second full step .
                                                                                           d If!- I 1I'fJ-'i
                                                                                             1st      cv
                  [d] VERIFY group demand position cou nters advance properly .
                  [e]  IF g roup demand pos ition counters do NOT advance properly,
                       THEN
                       A.       STOP rod withdrawa l.
                       B.       INITIATE W O to have counter repaired .
                       C.       WHEN counte r is repaired, THEN
                                1.     ENSURE Shutdown Bank B fully INSERTED and
                                2.     RETURN to beginning of this ste p.
             [20] WITHDRAW Shutdown Bank B to the FULLY WITHDRAWN
                   position usi ng [HS-85-5111] .                                          ~ /~
                                                                                              1st     CV
        SQN                CONTROL ROD DRIVE SYSTEM                       0-SO-85-1
         1,2                                                              Rev 32

( Page 45 of 77

  Unit.        --'-{___                                                               Date--l.-=-""=f-_
  6.3        Manual Operation of Rod Control System Below 15 Percent Power
             (Continued)
             [21] PLACE [HS-85-5110], Rod Control Mode Selector to the
                   SBC position.                                                         ~ I MfI"l.
                                                                                            1st      CV
             [22] VERIFY Rod Speed Indicator [SI-412], indicates
                    o Steps/minute .                                                       AJ.<, /~
                                                                                            1st      CV
             NOTE            The following failures will render the rod control system incapable
                             of automatic and / or manual motion    without any annunciation or
                             indication: 1) Hand switch failure; 2) relay failure , and
                             3) simultaneous failure of both 100v   DC power supplies (PS3 and
                             PS6).
             [23] ENSURE Shutdown Bank C demand position counters
                  operational by performing the following : [C.2]
                  [a]   BUMP [HS-85-5111], Rod Control Switch to withdraw
                       Shutdown Bank C one full step.                                     !JtL I MJVI..
                                                                                            1st      CV
                   [b] CHECK group demand position counter advances properly.
                  [c]   BUMP [HS-85-5111] to withdraw Shutdown Bank C
                        a second full step.                                                "-It<
                                                                                             1st
                                                                                                  I  ~
                                                                                                     CV
                   [d] VERIFY group demand position counter advanced properly.
                   tel IF group demand position counters do NOT advance properly,
                        THEN
                        A.      STOP rod withdrawal.
                        B.      INITIATE WO to have counter repaired.
                        C.      WHEN counter is repaired , THEN
                                1.     ENSURE Shutdown Bank C fully INSERTED and
                                2.     RETURN to beginning of this step .
              [24] WITHDRAW Shutdown Bank C to the FULLY WITHDRAWN
                    position using [HS-85-5111].                                          ;flf(    I  MWJ2
                                                                                              1st     CV
(
      SQN                  CONTROL ROD DRIVE SYSTE M                       0-SO-85-1

c 1,2 Rev 32

                                                                           Page 46 of ??
 Unit          I                                                                       Date       7Tf{Jtry
 6.3       Manual Operation of Rod Control System Below 15 Percent Power
           (Continued)
           [25] PLACE [HS-85-511 OJ, Rod Control Mode Selector to the
                  SBD position.                                                           .llt..i- I 111M
                                                                                              1st        CV
           [26] VERIFY Rod Speed Indicato r [SI-412] , indicates
                   o Steps/minute.                                                          I't /I<. I ...!J!..1!!l
                                                                                              1st        CV
            NOTE             The following failures will render the rod control system incapable
                             of automatic and / or manual motion without any annunciation or
                             indication: 1) Hand switch failure ; 2) relay failure , and
                             3) simultaneous failure of both 100v DC power supplies (PS3 and
                             PS6).
            [27] ENSURE Shutdown Bank 0 demand position counters
                 operational by performing the following: [C.2]
                 [a]   BUMP [HS-85-511 1] , Rod Control Switch to withdraw
                       Shutdown Bank 0 one full step.                                      J!.l!:S..- I ~
                                                                                              1st         CV
                  [b] CHECK group demand position counter advan ces properly.
                 [c ]  BUMP [HS-85-5111] to withdraw Shutdown Bank 0
                       a seco nd full step.                                                 ~ l tHJIL
                                                                                               1st        CV
                  [d] VERIFY group demand position counter advanced properly.
                  [e]  IF group demand position counters do NOT advance properly,
                       THEN
                       A.       STOP rod withdrawal.
                       B.       INITIATE WO to have counte r repai red.
                        C.      WHEN counter is repaired, THEN
                                1.     ENSURE Shutdown Bank 0 fully INSERTED and
                                2.     RETURN to beginning of this step.
             [28] WITHDRAW Shutdown Bank D to the FULLY WITHDRAWN
                   posi tion using [HS-85-5111].                                              I!ft
                                                                                                1st
                                                                                                       I   AI
                                                                                                           CV
                                                                                                              W   '
      SQN                 CONTROL ROD DRIVE SYSTEM                     0-SO-85-1
       1,2                                                              Rev 32

( Page 47 of 77

 Unit        )                                                                     Date     !7If'1
 6.3       Manu al Operation of Rod Control System Below 15 Percent Power
           (Continued )
           NOTE            Remainder of this section performed in conjunction
                           with 0-GO-2 or 0-RT-NUC-OOO-003.0.
           [29] PLACE [HS-85-5110], Rod Control Mode Selector to the
                  MANUAL position.                                                     Jl/f( , AIM.
                                                                                         1st     cv
            [30] VERIFY Rod Speed Indicator [SI-412] , indicates
                   48 Steps/minute.                                                     11 #<. , Awl
                                                                                         t st    CV
            NOTE           The following failures will render the rod control system incapable
                           of automatic and / or manual motion without any annunciation or
                           indication: 1) Hand switch failure; 2) relay failure, and
                           3) simultaneous failure of both 100v DC power supplies (PS3 and
                           PS6).
            [31] ENSURE Control Bank A demand position counters
                 operational by performing the following: [C.2]
                 [a]  BUMP [HS-85-5111], Rod Control Switch to withdraw
                      Control Bank A one-half step at a time, for one full step.       !1J.ti.. IAtr
                                                                                          l si   CV
                 [b] CHECK group demand position counters advance properly.
                 [c]  BUMP [HS-85-5111] to withdraw Control Bank A
                      one-half step at a time, for the second full step.                AIIf.. , ~
                                                                                          1st     CV
                  [d] VERIFY group demand position counters advance properly.                        QV
                  tel IF group demand position counters do NOT advance properly,
                       THEN
                       A.     STOP rod withdrawal.                                                  ~
                       B.     INITIATE WO to have counter repaired.                                 f/'P-
                       C.     WHEN counter is repaired, THEN
                              1.     ENSURE Control Bank A fully INSERTED and                       Af1J}
                              2.     RETURN to beginning of this step.                              ~
      saN              CONTROL ROD DRIVE SYSTEM                    0-SO-85-1
       1,2                                                          Rev 32

( Page 48 of 77

 Unit         (                                                              Date 1vl?o9-!p
 6.3       Manual Operation of Rod Control System Below 15 Percent Power
           (Continued)
           [32] CONTINUE withdrawal of Control Bank A using [HS-85-5111] ,         IJ lL(
                Rod Control Switch to 128 steps or next doubling.                 "'F,
           NOTE          When Control Bank A is above 20 steps. alarm FULL
                         LENGTH RODS AT BOnOM light on [XA-55-4B]
                         should clear. When Control Bank A gets above 20
                         steps and rods are driven back in, the alarm will come
                         back in. When Control Banks B, C, and 0 get above 35
                         steps, then drop below 20 steps, the alarm will come
                         back in.
           [33] WHEN Control Bank A is above 20 steps, THEN
                ENSURE Window 28 (0 -7). FULL LENGTH RODS
                RODS AT BOnOM alarm on panel [XA-55-4B]
                CLEARS.
        SQN                 CONTROL ROD DRIVE SYSTEM                      0-50-85-1
         1,2                                                              Rev 32

( Page 49 of 77

   Unit         I                                                                   Date     iWA-y
   6.3       Manual Operation of Rod Control System Below 15 Percent Power
             (Continued)
             CAUTION         When Control Bank A is reaches 128 steps, Control Bank B
                              should begin to move. Each successive bank should begin to
                              move when the previous bank reaches 128 steps.
             [34] WHEN Control Bank A is withdrawn to 128 steps, THEN
                  ENSURE Control Bank B demand position counters
                  operational by performing the following: [C.2]
                  [a]    BUMP [HS-85-5111J, Rod Control Switch to withdraw
                         Control Bank B one-half step at a time, for one full step.     "#1st
                                                                                                f AW t..
                                                                                                   cv
                   [b] - CHECK group demand position counters advance properly.
                  [e]    BUMP [HS-85-5111] to withdraw Control Bank B
                         one-half step at a time, for the second full step.             .!:!I:L f M CI't
                                                                                          t st     cv
                   [d] VERIFY group demand position counters advance properly.
                   [e] IF group demand position counters do NOT advance properly ,
                         THEN
                         A.     STOP rod withdrawal.
                         B.     INITIATE WO to have counter repaired.
                         C.     WHEN counter is repaired, THEN
                                1.     ENSURE Control Bank B fully INSERTED and
                                2.     RETURN to beginning of this step.
              [35] CONTINUE withdrawal of Control Bank Busing [HS-85-5111]
                    to 128 steps or next doubling .
c.
      SQN                  CONTROL ROD DRIVE SYSTEM                      0-SO-85-1
       1,2                                                               Rev 32

( Page 50 of 77

 Unit        {                                                                    Da~        WR~
 6.3       Manual Operation of Rod Control System Below 15 Percent Power
           (Continued)
           [36] WHEN Control Bank B is withdrawn to 128 steps, THEN
                ENSURE Control Bank C demand position counters
                operational by performing the following: [C.2]
                [a]    BUMP [HS-85-5111] , Rod Control Switch to withdraw
                      Control Bank C one-half step at a time , for one full step.      t1.JfL , IIJ-ld-
                                                                                         1st     CV
                 [b] CHE CK group demand position counters advance properl y.
                [c]    BUMP [HS-85-5111] to withdraw Control Bank C
                       one-half step at a time, for the second full step.              m , cvMWI-
                                                                                         1st
                 [d] _ VERIFY group demand position counters advan ce properl y.
                 [e]   IF group demand position counters do NOT advance properly,
                       THEN
                       A.      STOP rod withdrawal.                                                R)f
                       B.      INITIATE WO to have counter repaired.                               ~
                       C.      WHEN counter is repaired , THEN
                               1.    ENSURE Control Bank C fully INSERTED and                       ~
                               2.    RETURN to beginning of this step.                              ~
            [37] CONTINUE wit hdrawal of Control Bank C using [HS-85-5111]
                  to 128 steps or next doubling.                                           I. It {
            NOTE         Three steps are added to the low-lo w insertion limit (110
                          steps @ zero power) until LEFM is availabl e.
            [38] WHEN Control Bank C is '" 113 Steps, THEN
                  ENSURE Window 14 (B-7), ROD CONTROL BANKS
                  LIMIT LOW-LOW alarm on panel [XA-55-4B]
                  CLEARS.                                                                    LIf(
      SQN                 CONTROL ROD DRIVE SYSTEM                      0-SO-85-1
       1,2                                                              Rev 32

( Page 51 of 77

 Unit        I                                                                    Date     ]uO""1
 6.3       Manual Operation of Rod Con tro l System Below 15 Perce nt Power
           (Continued)
           NOTE         Three steps are added to the low insertion limit (120
                        steps @ zero power) until LEFM is available.
           [39] WHEN Control Bank C is '" 123 steps. THEN
                ENSURE Window 7 (A-7). ROD CONTROL BANKS
                LIMIT LOW alarm on panel [XA-55-4B] CLEARS .
           [40] WHEN Control Bank C is withdrawn to 128 steps. THEN
                ENSURE Control Bank D demand position counters
                operational by performing the following: [C.2]
                [a]    BUMP [HS-85-5111] . Rod Control Switch to withdraw
                     - Control Bank D one-half step at a time, for one full step.      JlIf( I NtJil.
                                                                                        1st    cv
                 [b] CHECK group demand position counters advance properly.                        [i}
                [c]    BUMP [HS-85-5111] to withdraw Control Bank D
                       one-half step at a time, for the second full step.             ~ I /J(if/.
                                                                                        1st     CV
                 [d] VERIFY group demand position counters advance properly.                       [)"
                 [e]   IF group demand position counters do NOT advance properly.
                       THEN
                       A.     STOP rod withdrawal.                                                i!1.4
                       B.     INITIATE WO to have counter repaired.                               If/JI
                       C.     WHEN counter is repaired, THEN
                              1.     ENSURE Control Bank D fully INSERTED and                     ~
                              2.     RETURN to beginning of this step.                             ~
            [41] CONTINUE withdrawal of Control Bank D using [HS-85 -5111]
                  to next doubli ng or criticality.
                                        End of Section 6.3

l

                            ROD CONTROL SYSTEM MALFUNCTIONS                       AOP-C.01
       SQN
                                                                                  Rev. 16
(
  I STEP I       ACTION/EXPECTED RESPONSE                   RESPONSE NOT OBTAINED
    2.1     Continuous Rod Bank Movement
    1.   CHECK rod control:
         a.  ENSURE rod control in MAN.
         b.  CHECK rod motion STOPPED.                  b. TRIP the reactor, and
                                                           GO TO E-O, Reactor Trip or Safety
                                                           Injection.
                                                            --~.--
        CAUTION:      -  Control Rods should NOT be manually withdrawn during a plant
                         transient.
    2.   CHECK for steam line or feedwater line
         break:
         a.   CHECK for rising reactor power            a. GO TO Step 3 .
              with dropping T- avg .
          b.  GO TO AOP-S.05 , Steam Line or
              Feedwater Line Break/Leak.
               --~.--

(

                                              Page 5 of 62
                                                                                      JPM B.1 .b
                                                                                      Page 1 of 14
                                                                                      Rev. 11
                   SEQUOVAHNUCLEARPLANT

( JOB PERFORMANCE MEASURE

                               B.1.b JPM 77-2AP
               Perform DIG Load Test on 1B-B DIG
                                     (with low oil press)

(

 PREPAREDI
 REVISED BY:                                                              Date/
 VALIDATED BY: *                                                           Datel
 APPROVED BY:                                                             Datel
                               (Operations Training Manager)
 CONCURRED:    **                                                          Date/
                               (Operations Repres entative)
               * Validation not required for minor enhancements, procedure Rev changes that
               do not affect the JPM , or individual step changes that do not affect the flow of
               the JPM .
               ** Operations Concurrence required for new JPMs and changes that affect the
               flow of the JPM (if not driven by a procedure revision ).
                                                                                              JPM B.1.b
                                                                                              Page 2 of 14
                                                                                              Rev. 11
                                                  NUCL EAR TRAININ G
                                                 REV IS ION/U SAGE LOG
  R EVISION                  DESCRIPT ION OF                    V      DATE      PAGES     PREPARED/
  NUMBER                          REV ISION                                     AFFECTED  REVISED BY:
       7         Revised to reflect revision changes in SI-     N    10/14/99       All    SR TAYLOR
                 7B, changed critical steps for consistency
                 with JPM 77-5AP reviewed/approved
                 4/20/99, corrected typos and incorporated
                 comments from 1999 cycle 5 requal
                 perfo rmances of JPM 77-2AP. Flow of
                 the J PM is not affected .
    penlink      Deleted step 20 based on rev 20 of O-AR*       N      8/9/00      5,12     SR Taylor
                 M26-B , Updated rev level
    penli nk     SO-82 rev update only                          N     8/17/00        4      SR Tay lor
    penlin k     0-AR-M26-B rev chg only                        N     8/28/00        4      SR Taylor
    penli nk     0-SI-OPS-082-007.B rev chg only                N     6/21/01        4     W R Ramsey
    pen/in k     1-SI-O PS-082-007.B rev 25 Update minor        N    09/07/01      ALL     WR Ram sey
                 chang es related to stopwatch usage

( 8 Incorporated pen/ink changes ; updated to

                 recent revisions of references; no impact
                                                                N     8/20/02       All    J P Kearney
                 on JPM flow
       9         Revised remote funct ions used to conform      N   12/0 1/2003   4,8, 10  JJ Tricoglou
                 to new simutator configuration
      10         Updated to curre nt revisions and IC.          N     8/11/04       All    MG Croteau
      11         Updated to current revisions . Minor format    N    01/3 1/07      All     RH Evans
                 chan ges
   v - Specify if the J PM change will require another validation (Y or N).
       See cover sheet for criteria.

(,

                                                                                                   JPM B.1.b
                                                                                                   Page 3 of 14
                                                                                                   Rev. 11
                                           SEQUOYAH NUCLEAR PLANT
                                                      ROISRO
                                          JOB PERFORMANCE MEASURE

(

  Task:
          Perform DIG Load Test on 18-B DIG
  JAITA tas k # :
          0640020101      0640040101       0640060101      (RO)
  KIA Rati ngs:
          064A4.01 (4 .0/4.3)              064A1.01 (2.0/3.1)
          064A4.02 (3.3/3.4)               064A4.03 (3.213.3)
          064A2.09 (3.1/3.3)               064A3.06 (3.3/3.4)
  Task Stand ard :
          Perform DIG Operability Test per 1-SI-OPS-082-007.B. specifically manually start the DIG. Open
          alternate ERCW supply valve and emergency stop DIG on low oil pressure annunciator.
  Eva luation Method :     Simulator _ -!:
                                        X,--_     In-Plant       _
  ============== =========================== ==================================== ======
  Performer:
                                   NAME                                                    Start Time

( Performance Rating: SAT UNSAT Performance Time Finish Time

  Evaluato r:                                                  I
                                  SIGNATURE                        DATE
  ====================================================================================
                                                   COMMENTS

('

                                                                                               JPM B.1.b
                                                                                               Page 4 of 14
                                                                                               Rev. 11
 SPECIAL INSTRUCTIONS TO EVALUATOR :
 1.  Sequenced steps identified by an "s"

( 2. Any UNSAT requires comments

 3.  Acknowledge any associated alarms.
 4.  Initialize Simulator to IC-16.
 5.  A Console operator will be required to enter overrides and play role of AUO on Radio.
 6.  When operator starts step #19, insert IMF AN_OV_946 f :2.
 7.  An extra simulator operator will be needed at step 5 for timing the D/G.
 8.  Ensure operator performs the following required actions for SELF-CHECKING;
     a. Identifies the correct unit, train, component, etc.
     b. Reviews the intended action and expected response.
     c. Compares the actual response to the expected response.
 Validation Time: CR        13 minutes       Local            _
 Tools/Equipment/P rocedures Needed :
          Marked up portions of 1-SI*OPS-082-007.B:
           * Section 4;
           * Section 6.1; and,
           * Appendix "C".
           O-AR-M26-B window B-4
 References'
                      Reference                                         Tille                    Rev No.
 1.     1-SI-OPS-082-007.B                       Electrical Power System Diesel Generator 1B-B      39
 2.     O-AR-M26-B                               Annunciator O-XA-55-26B                            27

(

                                                                                                         JPM B.1.b
                                                                                                         Page 5 of 14
                                                                                                         Rev. 11

(

 ================= ======== =====================================================
                                                    READ TO OPERATOR
 Directions to Trainee:
         I will explain the initial conditions , and state the task to be performed. All control room steps shall
         be performed for this JPM. I will provide initiating cues and reports on other actions when directed
         by you. Whe n you comp lete the task successfully, the objective for this job performance measure
         will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate
         that you have completed your assigned task return the handout sheet I provided you.
 INITIAL CONDITIONS:
         1.    Both units are at 100% RTP.
         2.    All systems are OPERABLE, except for the 1B-B DIG , 0-GO -16 has been completed on all the A train
               equ ipment.
         3.    Maintenance has been completed on the 1B-B DIG and the clearance has been removed.
         4.    The DIG has been rolled and is in standby alignment using 0-SO-82-2.
         5.    The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082 *007.B and all parameters
               are within limits.
         6.    The U1 Control Room AUO has verified breaker 1934 is removed.
         7.    SI-166.36 is NOT required.

( 8.

         9.
               D/G-DAQ has been installed.
               Room fire protection is in service.
         10.   Sect ion 4.0 of 1-SI-OPS-082-007.B is complete.
 INITIATING CUES :
         1.    The U1 US/SRO has reviewed the comple ted work package for the 1B-B DIG , all that remains is to
               perform 1-SI-OPS-082-007 .B for the PMT.
         2. You are an extra unit operator and have been assigned to perform the operability run of DIG 1B-B per
               SI-OPS-08 2-007 .B.
          1. T he PMT requires the AMB IENT MANUAL START method for testing.
          3. Notify the US when the test is comp lete.
                                                                                           JPM B.1.b
                                                                                            Page 6 of 14
                                                                                            Rev. 11
 Job Pertormance Checklist:
                                         STEP/STANDARD                                      SATIUNSAT

( STEP 1.: Operator obtains a copy of the appropriate procedure. - SAT

   NOTE:        Initial conditions cover steps up to transition to App "C" .              -     UNSAT
 STANDARD:      Operator obtains a copy of 1-SI-OPS*082-007.B. Pertormance of task      Start T ime-  -
                will start with AppendiX C.
 COMMENTS:
 STEP 2.:   [1) ENSURE [D-HS*82-48) . 1B-B D/G mode selector switch in the UNIT           -     SAT
                position.
                                                                                          -     UNSAT
 STANDARD :     O-HS-82-48 in UNIT position on O-M-26. Green light ON.
 COMMENTS:
 STEP 3.:   [2)  Place [1*HS*57*74). D/G 1B-B Synchronize Switch in the SYN position.     -      SAT
   NOTE:        O*EI*82*35 and O*XI*82*33 will indicate running voltage & frequency.      -     UNSAT

( STANDARD: 1-HS-57-74 in "SYN" position on O-M-26. This step is cr itical to allow

                to allow DIG to be synchronized to the Shutdown Bd.                     Critical Step
 COMMENTS:

(

                                                                                            JPM B.1.b
                                                                                            Page 7 of 14
                                                                                            Rev. 11
 Job Performance Checklist:
                                          STEPISTANDARD                                     SAT/UNSAT

( STEP 4. [3] PERFORM the following to initiate the DIG start signal: - SAT

                 [a]     IF the D/G-DAQ is to be used, THEN NOTIFY D/G-DAQ                 -    UNSAT
                         Operator to
                         START the D/G -DAQ
     NOTE:      Operator should coo rd inate t he start of the D/G-DA Q just prior to
                DIG st art actu ation.
     Cue         Console operator Play ro le o f DIG-DAQ operator: DI G-DAQ
                 computer is running.
 STANDARD:      Operator notifies the DIG-DAQ operator to start the DIG-DAQ.
 COMMENTS:
 STEP 5.:        [b]     PROCEED with the countdown: 3,2,1, START.                         -    SAT
                 [c]     DEPRESS [0-HS-82-46A] . DG 1B-B Emergency Start Switch            -    UNSAT
                         AND START stopwatch.

c [d] WHEN voltage >6800 volts AND frequency >58.8 Hz, THEN

                         STOP stopwatch.
                                                                                         Critical Step
     CUE:       An ext ra ope rato r with stop wat ch is sta nding by .
 STANDARD :     D-HS-82-46A mo me ntaril y depr essed . Green light will go "out" and
                 red li ght will com e "on" abo ve DIG mimic. [Not critical: DIG running
                aiarm will ANN to indicate DIG> 40 rpm. Incoming voltage and
                frequency are verified on 0-EI-82-34 and 0-XI-82-32. Portions of this
                step is crit ical to start t he DIG.
 COMMENTS:
 STEP 6.:   [4] ENSURE [1-FCV-67-67] , ERCW cooling water supply valve is OPEN.            -    SAT
                                                                                           -    UNSAT
 STANDA RD:      ERCW valve 1-FCV-67-67 is verified open.
 COMMENTS:
                                                                                                   JPM B.1.b
                                                                                                    Page 8 of 14
                                                                                                    Rev. 11
 Job Performance Checklist:
                                          STEPISTANDARD                                             SAT/UNSAT

( ST EP 7.: [5] RECORD the steady state values for the following: - SAT

                 A. [O-EI-82-34] . DG 1B-B incoming Voltage.
                 B. rO-XI-82-321, DG 1B-B incoming Frequency.                                     -    UNSAT
                 C. Time from Stopwatch (es):
                        Seco nds            Stopw atch ID Number
                        Seconds             Stopwatch 10 Number
   CUE:          Time from s top wat ch . = 9.48 seconds
 STANDARD:       Operator records parameters as directed and verifies acceptance criteria
                 met. DIG voltage (as indicated on INC Voltage Gen 1B-B 0-EI-34) is;::
                 6800 but :s. 7260 volts and freq uency (as indicated on INC Freq Gen 1B-B
                 0-XI-82-32) is ;:: 58.8 Hz and s 61.2 Hz
 COMMENTS:
 ACCEPTANCE CRITERIA: DIG 1B-B achieves steady state generator voltage of ;::6800 and            ~7260   volts and
                               frequency of ;::58.8 Hz and :s. 61.2 Hz.

( STEP 8.: [6] RECORD Voltage Regul ator Control Current. - SAT

      Cue:       Voltage Regulator Control Current Is 1.8 dc amps.                                 -   UNSAT
 STAN DAR D:     Operator records Voltage Regulator Control Current.
 COMM ENTS :
 ACCEPTANCE CRITERIA: Voltage Regulator Control Curren t between 1.0 - 2.5 dc amps. The Voltage
                               regulator card must be functioning properly to conside r DG operable.
 STEP 9.: [7]   ENSURE DIG 1B*B [86 LOR] red light NOT ILLUMINATED, at DIG local                   -   SAT
                 relay panel.
                                                                                                   -    UNSAT
      Cue:       Role Playas DIG operator - 86 LOR local red light Is not
                 Illuminated.
 STANDARD        Operator request DIG operator to verify red light on 86 LOR at DIG is not
                 illuminated.
 COMMENTS:
                                                                                             JPM B.1.b
                                                                                             Page 9 of 14
                                                                                             Rev. 11
 Job Performance Checklist:
                                         STEP/STANDARD                                       SATIUNSAT

( Booth operator: to reset 86LOR, IRF EGR08 f:1 ;

                    then notify operator 86 LOR Is reset.
 NOTE            Do not hold [86 LOR] in RESET position if it does not latch on the first
                 attempt. Coil failure may result if relay is held in RESET position.
 STEP 10.:  [8] RESET [86 LOR] Lockout Relay. on DIG local relay panel.                     -    SAT
   NOTE:         When requested of DIG AUO. reset 86LOR                                     -    UNSAT
                 [Booth operator: IRF EGR08 f:1 to reset 86LOR ;
                 then no tify operator 86 LOR is reset)
                                                                                          Critical Step
 STANDARD:       86 LOR is reset. This step is critical to allow paralleling the D/G to
                 the Shutdown Bd.
 COMMENT S:
 STEP 11.:  [9] VERIFY [86LOR] is reset by amber light [0-XI-82-49] ILLUMINATED on
                 0-M-26.
 STANDARD:       86 LOR amber light on 0-M-26 is verified lit

( COMMENTS:

 STEP 12.: [10] IF the D/G-DAQ was used. THEN                                               -    SAT
                 RECORD from the time required to achieve :2: 6800 Volts and z 58.8 HZ      -    UNSAT
                 from the D/G*DAQ computer:
                                       Seconds
      Cue:       Time was 9.5 seconds for D/G*DAQ.
 STANDARD:       Operator ensures the DG accelerates to at least 900 rpm (58.8 - 61.2 Hz)
                 and Voltage and frequency are within limit within the required 10
                 seconds. (Evaluator can sign for Tech Support)
 COMMENTS:

(

                                                                                           JPM B.l.b
                                                                                            Page 10 of 14
                                                                                            Rev. 11
 Job Performance Checklist:
                                         STEP/STANDARD                                      SAT/UNSAT

c ACCEPTANCE CRITERIA: D/G lB-B start from ambient condition achieves in less than or equal to 10

                              seconds generator voltage 2: 58.8 Hz.
 STEP 13.: [11] RECORD start as ambient in 0-SI*OPS-082-007 .M.                            -   SAT
     Cue:        Another operato r w ill recor d st art.                                   -   UNSAT
 STANDARD:       Operator logs (addresses logging) the start in 0*SI-OPS-082-007.M.
 COMMENTS :
 ST EP 14.: [12] RETURN to Section 6.1, Step [9] of this instruction.                      -   SAT
 STANDARD:       Operator returns to the appropriate section and step of the procedure.    -   UNSAT
                 (Exits Appendix C)
 COMMENTS:
 EVALU ATOR NOTE: Followina steps evaluate procedure section 6.1.

( STEP 15.: [9] PERFORM the following to wipe the Automatic Voltage Control Rheostat: - SAT

                 [a]     RECORD voltage from [D-EI-82-34].                                 -    UNSAT
                 [b]     ENSURE [O-HS-82-42] DG lA-A Voltage Regulator Switch in the
                                 PULL-P-AUTO position
                 [c]     DECREASE voltage to 6700 volts on [O-EI-82-34) USING [D-HS-
                         82-42]
                 [d]     INCREASE voltage to 7300 volts on [O-EI-82-34] USING [O-HS-
                         82-42]
                 [e]     RETURN voltage to value recorded in [9Ile].
 STANDAR D:      Operator uses 0-HS-82-42 to decrease voltage to 6700 volts and
                 increase voltage to 7300 volts, then return voltage to the value recorded
                 in step [glle].
 COMMENTS:

(

                                                                                            JP M B.1.b
                                                                                             Page 11 of 14
                                                                                             Rev. 11
 Job Perform ance Checklist:
                                          STEPISTANDARD                                      SAT/UNSAT

( STEP 16.: [10] PLACE [D-HS-82-48] , Mode Selector Switch in PARALLEL position. - SAT

                                                                                           -    UNSAT
 STANDARD:       0-HS*82-48 rotated to the PARALLEL position. Red light "on" & green
                 light "off". This step is critical to place speed droop circuit in      Critical Step
                 service.
 COMM ENTS:
 STE P 17.: [11] ADJUST [0-HS-82-431. DG 1B-B Speed Control Switch to obtain a             -    SAT
                 synchroscope indication of slowly rotating in [FAST] direction.
                                                                                           -    UNSAT
 STANDARD :      Operator adjusts speed control hand switch 0-HS-82-43 such that
                 synchrosco pe (XI-82-31) is moving slowly in the fast direction (slowly
                 clockwise) .
 COMM ENTS:
 STEP 18.: [12] ENSURE [0-HS-82-42] . DG 1B-B Voltage Regulator Low-Raise Switch in         -   SAT

( the PULL-P-AUTO position. AND

                                                                                            -    UNSAT
                  ADJUST to match incoming voltage with running voltage.
 STANDARD :       Operator ensures HS-82-42 in PULL-P-AUTO and adjusts DIG voltage       Critical Step
                  such that incoming voltage (EI-82-34) and running voltage (EI-82-35)
                  are approximately equal. Only the bold portion of t hi s standard is
                  critical.
                  This is critical to match voltage of the DIG w ith the voltage on the
                  Shutdown Bd.
 COMMENTS:
                                                                                                JPM B.l .b
                                                                                                 Page 12 of 14
                                                                                                 Rev. 11
 Job Performance Checklist:
                                           STEP/STANDARD                                         SAT/UNSAT

( Booth operator: INSERT the following IMF AN_OV_946 1:2 when operator begins

                 discussing the step to close DIG Bkr.
 STEP 19.: [13] WHEN the synchroscope DG 1B-B [o-SI-82-31] indicates 12 O'Clock                -     SAT
                 position, THEN
                        CLOSE breaker [1914] via [l -HS-57-73Aj, 1914 DG lB-B to SO            -     UNSAT
                        BD lB-B, AND
                 START stopwatch.
   NOTE:         Whe n operator begins disc ussing t he step to close DIG Bkr, insert
                 override IMF AN_OV_946 f:2 .
 STANDA RD:      Operator discusses closing DIG 1B*B breaker 191 4, but should stop due
                 to annunciator.
 COMMENTS:
 STEP 20.:       Respond to annuciator panel 0-M-26B window B-4.                                -    SAT
 STANDARD:       Operator pulls AR 0-M26-B and consults page for window B-4 or TAKES            -    UNSAT
                 PRUDENT ACTION TO EMERGENCY STOP DIG.

( COMMENTS :

 EVALUATOR NOTE: The next Performance Step is from the ARP Corrective Actions.
 STEP 21.:   [1] IF DIG running with no valid accident (blackout or SI) signal present,         -    SAT
                 THEN,
                 ENSURE DIG shutdown by depressing emergency stop pushbutton 0-                 -    UNSAT
                 HS-82-47A.
      Cue:       If contacted, EDG AUO reports Engine 1 LO Pressure is 15 psig and
                 decreasing.                                                                  Critical Step
 STANDARD:       Oper ato r init iates action [w ithin 2 mi nutes] after determining no valid
                 accident signal, lube oil pressure low by depressing emergency stop
                 button for Diesel Generator 1B-B.
                 This step is critical to prevent damage to th e D/G due to low lube oil
                 pressure.
 COMMENTS:
                                                                                        JPM B.1.b
                                                                                        Page 13 of 14
                                                                                        Rev. 11
 Job Performance Checkl ist:
                                      STEP/STANDARD                                     SAT/UNSAT

c STEP 22.: Inform US/SRO of Emergency stop of Diesel Generator 1B-B. SAT

                 US/SRO instructs opera tor to standby for further instructions.            UNSAT
 STANDARD :      Operator informs US/SRO of Emergency stop of Diesel Generator 1B-B.
 COMMENTS :                                                                          Stop T ime__

FROM : SEQU[ YRH OPERRTOR TRR INING PHONE NO. 423 843 4339 '"pr. 04 2007 02 : OOPM P4

                                         CANDIDATE CUE SHEET
                    (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
      DIRECTION TO TRAINEE:
             I will explain the initial conditions, and state the task to be performed. All control
             room steps shall be performed for this JPM, including any required
             communications. I will provide initiating cues and reports on other actions when
             directed by you . Ensure you indicate to me when you understa nd your assigned
             task. To indicate that you have completed your assigned task return the handout
             sheet I provided you.
      INITI,~L CONDITIONS:
             Both units are at 100% RTP.
             All systems are OPERABLE, except for the 1B-B DIG , 0-GO-16 has been completed on
             all the A train equipment.
             Mainten ance has been completed on the 1B-B DIG and the clearance has been
             removed .
             The DIG has-been rolled and Is in standby alignment using 0-80-82-2.
             The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082-007.B and all
              parameters are within limits.
             The Ul Contro l Room AUO has verified breaker 1934 is removed.
              SI-166 .36 is NOT required.
              D/G-DAQ has been Installed.
              Room fire protection is in service.
              Section 4.0 of 1-SI-OPS-082-007.B is complete.
      INITIATING CUES:
              The U1 US/SRO has reviewed the completed work package for the 18-8 DIG, all .
              that remains is to perform 1-SI-OPS-082-007.B for the PMT.
              You are an extra unit operator and have been assigned to perform the operability.
              run of DIG 1B-B per SI-OPS-082-o07.B.
              The PMT requires the AMBIENT MANUAL START method for testing.
              Notify the US when the test is complete.
                                  CANDIDATE CUE SHEET
            (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

     I will ex plain the initial co nditio ns, and state th e task to be performed . All control
     roo m steps sh all be perform ed for this JP M , including any require d
     comm un ications. I will prov ide init iatin g cues and reports on other actions when
     directed by you. Ensure you indicate to me when you understand your assigned
     tas k. To indicate that you have compl eted your assigned task return the handout
     sh eet I provided you .

INITIAL CONDITIONS:

     Both units are at 100% RTP.
     All systems are OPERABLE, except for the 1B-B DIG , 0-GO-1 6 has been completed on all the
     A train equipment.
     Maintenance has been completed on the 1B-B DIG and the clearance has been removed.
     The DIG has been rolled and is in standby alignment using 0-SO-82-2.
     The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082-007.B and all
     parameters are- within limits.
     The U1 Control Room AUO has verified breaker 1934 is in the Disconnect position.
     SI-166.36 is NOT required.
      D/G-DAQ has been installed.
      Applicable steps of Appendix J, Monitoring the DIG Starting Air System, compl
      Room fire protection is in service.                                                     l'.
      Section 4.0 of 1-SI-OPS-082-007.B is complete.

INITIATING CUES:

      The U1 US/SRO has reviewed the completed work package for the 1B-B
      remains is to perform 1-SI-OPS-082*007.B for the PMT.
      You are an extra unit operator and have been assigned t o perform the operability run of
      DIG 1B-B per SI-OPS-082-007.B.
      The PMT requires the AMBIENT MANUAL START method for testing.
      Notify the US when the test is complete.

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