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{{#Wiki_filter:Appendix D Scenario Outline Form ES-D-1 Facilit y: Call a w a y Scenar io No.: 1 Op T e st No.: NRC Exam in e r s:   O p e r a t o r s:             Initial C ond itio ns: 100% po w e r, BOL. RE-52, Blo w d o w n Disch arg e Pumps Disc har ge Mon i tor, is OOS.
{{#Wiki_filter:Appendix D                                           Scenario Outline                                 Form ES-D-1 Facility:           Callaway                          Scenario No.:           1   Op Test No.:       NRC Examiners:                                                       Operators:
BB-PCV-45 5A PORV Leaka g e - Block Valv e Clos ed. Motor Driven AFW Pump 'A' OOS.
Initial Conditions:       100% power, BOL.
T u rnover: Red u ce p o w e r to less than 9 0% at 1% per mi nute to remov e Cond ens ate Pump 'A' from service d ue to a seal l eak  Critical T a sk: Start EDG 'A' to ener gize Em erge nc y B u s pr ior to initi a tion of ECA 0.0 cop i ng steps.
RE-52, Blowdown Discharge Pumps Discharge Monitor, is OOS.
Manu all y Start 'A' HHSI pum p prior to e x it from EOP Attachment 1.
BB-PCV-455A PORV Leakage - Block Valve Closed.
Event No.
Motor Driven AFW Pump A OOS.
Malf. No.
Turnover:                 Reduce power to less than 90% at 1% per minute to remove Condensate Pump A from service due to a seal leak Critical Task:           Start EDG A to energize Emergency Bus prior to initiation of ECA 0.0 coping steps.
Event T y pe* Event Description 1 R - RO N - BOP, SRO R e du ce po w e r I - BOP, SRO SG level transmitter failure.
Manually Start A HHSI pump prior to exit from EOP Attachment 1.
2 F W M02A T S - SRO C - ALL 4KV Bus NB0 2 Normal F e e d e r Breaker trip.
Event No.     Malf. No. Event Type*                                 Event Description 1                     R - RO         Reduce power N - BOP, SRO 2                      I - BOP,       SG level transmitter failure.
3 EPS05B T S - SRO 4 P R S 0 2 A  I - RO, SRO T S - SRO Pressuriz e r Level T r ansmitter fails lo w  C - RO, SRO RCS Le ak req u irin g reactor tr ip. 5 RCS0 6 C  6 BAT M - ALL Loss of off-site po w e r, SBLOCA.
FWM02A      SRO TS - SRO 3                      C - ALL         4KV Bus NB02 Normal Feeder Breaker trip.
7 E P S 0 6 B KJS012 C - BOP 'B' DG T r ips - 'A' DG fails to AUT O Start. MANUAL Start requ ired. 8 SBI008C C - RO 'A' HHSI pum p fails to AUT O Start - MANUAL Start requir ed. * (N)ormal,   (R)eactivit y ,   (I)n strument,    (C) o mp onent,    (M)ajor Scenario Event Description NRC Scena rio 1 The crew will assume th e shift at 10 0% power with instructio ns to reduce power due to a Condensate Pump seal leak.
EPS05B TS - SRO 4         PRS02A      I - RO, SRO     Pressurizer Level Transmitter fails low TS - SRO 5                      C - RO,         RCS Leak requiring reactor trip.
At approximately 95% power, a Steam Generator Lev el transmitter will d r ift low, requ iring the crew to take manual control of the fe edwater regulating valve for the affected steam generator in accordance with OTO-AE-2. The SRO will also refer to Technical Speci f ications for the appropriate action requir e ments. When technical specifica t ions have been addressed, 4KV Vital Bus NB02 normal feeder breaker will trip. 'B' EDG will automatically start and energize bus NB02. The crew will respond in accordan ce with alar m response procedures, OTO-NB-00 002  and OTO-SA-1 to st op AFW flow and secure unnecessary equipment started b y the Shutdown Sequencer. The SRO will refer to tech nical spe c ifications.
RCS06C      SRO 6                     M - ALL         Loss of off-site power, SBLOCA.
When the pl ant is stab le , a Pressurizer Level Transmitter will fail low, cau s ing Letdow n isolation
BAT 7         EPS06B      C - BOP         B DG Trips - A DG fails to AUTO Start. MANUAL Start required.
. The crew will restore letd own in acco rdance with OTO-BG-1.
KJS012 8                     C - RO         A HHSI pump fails to AUTO Start - MANUAL Start required.
The SRO will address T e chnical Specificatio ns. An RCS lea k will develo p when Letdown is place d in service, requiring th e crew to determine that the reactor must be tripped.
SBI008C
When the reactor is tri p p ed, a loss of off-site pow er will occur.
      *   (N)ormal,   (R)eactivity, (I)nstrument,    (C)omponent,    (M)ajor Scenario Event Description NRC Scenario 1 The crew will assume the shift at 100% power with instructions to reduce power due to a Condensate Pump seal leak.
The RCS leak will prog ress to a SBLOCA. Diesel Generator 'B' trip s and canno t be started.
At approximately 95% power, a Steam Generator Level transmitter will drift low, requiring the crew to take manual control of the feedwater regulating valve for the affected steam generator in accordance with OTO-AE-2. The SRO will also refer to Technical Specifications for the appropriate action requirements.
Diesel Generator 'A' fails to automatically start, and must be manually started and aligned in accordan ce with E-0 or ECA-0.0.
When technical specifications have been addressed, 4KV Vital Bus NB02 normal feeder breaker will trip. B EDG will automatically start and energize bus NB02. The crew will respond in accordance with alarm response procedures, OTO-NB-00002 and OTO-SA-1 to stop AFW flow and secure unnecessary equipment started by the Shutdown Sequencer. The SRO will refer to technical specifications.
HHSI pump 'A' fails to automatically st art, a nd must be manually started.
When the plant is stable, a Pressurizer Level Transmitter will fail low, causing Letdown isolation.
The crew will restore letdown in accordance with OTO-BG-1. The SRO will address Technical Specifications.
An RCS leak will develop when Letdown is placed in service, requiring the crew to determine that the reactor must be tripped.
When the reactor is tripped, a loss of off-site power will occur. The RCS leak will progress to a SBLOCA.
Diesel Generator B trips and cannot be started. Diesel Generator A fails to automatically start, and must be manually started and aligned in accordance with E-0 or ECA-0.0. HHSI pump A fails to automatically start, and must be manually started.
The scenario may be terminated upon entry to ES-1.2, Post LOCA Cooldown and Depressurization.
The scenario may be terminated upon entry to ES-1.2, Post LOCA Cooldown and Depressurization.
EOP flow pa th: E-0, ECA-0.0, E-0, E-1, ES-1.2
EOP flow path: E-0, ECA-0.0, E-0, E-1, ES-1.2 Scenario 1 Scenario Malfunction List
: 1)  Initialize at IC-20.
: 2)  Run Batch File "iltone.txt", and verify the actions on the following page are loaded correctly.
: 3)  Ensure Immediate Boration Timer is reset.
: 4)  Check RX trip switch has a RED flag.
: 5)  Ensure NIS indicates 100%
: 6)  Ensure step counters for Control Bank D are set at 215 steps and all other step counters are set for 228.
: 7)  Ensure the digital display is selected to REP0480A and RET0499A.
: 8)  Ensure AE-LT-519 is selected
: 9)  Ensure BB-LT-459 is selected
: 10) Hang hold off tags on the "A" MDAFP.
: 11) Ensure Decrease Loading Rate Button is ON.
: 12) Update status board for B Protected Train week. Record "A" MDAFP, LCO 3.7.5, 72 hours.
: 13) Place Letdown orifi A and B in service with a caution tag on C
: 14) White board has the following boron concentrations:
    * "A" MDAFP T/S 3.7.5, Action C.1. 72 Hours. OOS @ 0500 Today
    * 'A' CCP "5 days ago" 1107 ppm
    * 'B' CCP "two weeks ago" 1135 ppm
: 15) Supply turnover and log sheets and OTG-ZZ-00004.
: 16) Ensure the RM-11 is on the training system.
: 17) Microphones available for each person being evaluated and a video tape is in the VCR.
: 18) Ensure chart recorders are "rolled forward".
: 19) Ensure copies of the following procedures are in the file drawers:
* OTO-AE-00002                  OTG-ZZ-00004
* OTO-NB-00002                  OTN-AD-00001
* OTO-SA-00001                  OTN-BG-00001, Addendum 4
* OTO-BG-00001                  OTN-EC-00001
* ECA-0.0
* E-0
* E-1                    E-2 Scenario 1 Scenario Malfunction List File:                iltone.TXT
>Author: S. P. Aufdemberge
>Date:                20050504
>=============SCENARIO SETUP ITEMS===========================================
>TAGOUT "A" MDAFW PUMP
> FILE: AL01A.TXT
> Red lights stay on the ESFAS Panel bat al01a.txt
>Simulates de-energization of "A" PORV Block valve due to PORV Leakage ior bbhis8000a_ic (-1 0) 0 irf bbs014 (-1 0) 0
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT A
>'A' S/G lev xmttr fails to 0 psig over 60 sec from trigger #1 (MANUAL) imf fwm02a (1) 0 60
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT B
>Loss of NB02 normal feeder breaker, from trigger #2 (MANUAL) imf eps05b (2)
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT C
>Pressurizer Level Transmitter Fails Low, from trigger #3 (MANUAL) imf prs02a (3) 0 60
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT D
>RCS leak requiring Reactor trip,Grows to 600gpm over 10 minutes from Manual Trigger #5 imf rcs06c (5) 600 600
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT E
>Loss of Off-Site Power, from Manual trigger #6
> Incoming Lines imf eps03a (6 0) imf eps03b (6 3) imf eps03c (6 20) imf eps03g (6 5)
>Incoming Line lights irf msb006 (6 0) 0 irf msb007 (6 5) 0 irf msb008 (6 3) 0
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT F
>"B" EDG trips and "A" EDG will fail to automatically start. "B" EDG fails on the loss of off-site power imf eps06b (7)
>Loss of off-site power "sensed" by green light on RCP control switch trgset 7 "x21o115g.eq.0"
>Disable Automatic start of "A" EDG irf kjs012 (-1 0) 1
>============================================================================
>=======================EVENT PRELOAD========================================
>EVENT G
> "A" CCP fails to auto start, manual will be successful irf sbi008c (-1 0) 1
>end of file Scenario 1 Crew Turnover Separate Turnover sheets provided Appendix D                              Operator Action                          Form ES-D-2 Op Test No.:        1    Scenario #    1    Event #      1                Page 6  of 36 Event
 
== Description:==
Reduce Power Time          Position                        Applicants Actions or Behavior SRO      Refer to OTO-MA-00008, Rapid Load Reduction CREW        Determine amount of boric acid to reduce reactor power to 90%
CREW        Record rate of turbine load change Discuss amount and rate of turbine load change and boric acid SRO addition with crew SRO      Notify Load Dispatcher SRO      Notify Chemistry, Health Physics, and Radwaste Initiate boron equalization
* Energize at least 1 group of backup heaters RO
* Place the PZR Master Controller in MAN
* Lower PZR Master Controller output to 38% to 42%
* Place the PZR Master Controller in AUTO 6
 
Appendix D                              Operator Action                          Form ES-D-2 Op Test No.:      1      Scenario #    1    Event #      1                Page 7  of 36 Event
 
== Description:==
Reduce Power Time          Position                        Applicants Actions or Behavior Borate from the BAST using any of the following:
* Emergency Boration o  Start at least 1 Boric Acid Transfer Pump o  Open Emergency Boration to Charging Pump suction BG HIS-8104 o  Check Emergency Borate flow is greater than 30 GPM on BG FI-183A
* Borate to the VCT RO o  Place RCS Makeup Control to STOP (BG HS-26) o  Place RCS Makeup Control Selector to BORATE (BG HS-25) o  Reset Boric Acid counter to 000 (BG FY-110B) o  Set BG FY-110B for the desired galloons of boric acid to be added o  Place BG HS-26 in RUN RO        Place Rod Control in AUTO Reduce turbine load at less than or equal to 5% per minute using any of the following:
o  Reduce turbine load using the Load Limit potentiometer o  Reduce turbine load using the %/min loading rate o  Rotate Load Limit Set potentiometer clockwise until both of the following are met:
BOP Load Limit light extinguished At Set Load - LIT o  Set Loading Rate Limit %/min to desired value o  Select Decrease Loading Rate - ON o  Lower load set MW toward desired load using DECREASE LOAD pushbutton 7


Scenario 1 Scenario Malfunction L i st  1) Initialize at I C-20. 2) Run Batch File "iltone.t x t", and verify the actions on the following page are loaded correctly. 3) Ensure Immediate Boration Timer is reset. 4) Check RX trip switch ha s a RED flag.
Appendix D                            Operator Action                        Form ES-D-2 Op Test No.:       1     Scenario #  1   Event #     1               Page 8  of 36 Event
: 5) Ensure NIS indicates 10 0% 6) Ensure step counters for Control Bank "D" are set at 215 step s and all oth e r step coun ters are set for 2
 
: 28. 7) Ensure the digital displa y is selected to REP048 0A and RET 0499A. 8) Ensure AE-LT-519 is se lected 9) Ensure BB-LT-459 is se lected 10) Hang hold off tags on th e "A" MDAF P. 11) Ensure Decrease Loadin g Rate Button is "ON".
== Description:==
: 12) Update status board for "B" Protected Train week. Record " A" MDAFP, LCO 3.7.5, 72 hours. 13) Place Letdo wn orifi A and B in service with a cau t ion tag on C 14) White board has the following boron concentrations:  "A" MDAFP T/S 3.7.5, Action C.1. 7 2 Hours. OOS @ 0500 Today  'A' CCP "5 d a ys ago" 1107 ppm  'B' CCP "t wo weeks ag o" 1135 ppm
Reduce Power Time          Position                    Applicants Actions or Behavior BOP      Check MFP Turbine Speed control in AUTO When power has been reduced approximately 5%, or at Lead Evaluators discretion, proceed to Event 2 8
: 15) Supply turnover and log sheets and OTG-ZZ-00 004. 16) Ensure the RM-11 is on the training system. 17) Microphones available f o r each person being evaluated and a video tape is in the VC R. 18) Ensure char t recorders are "rolled f o rward". 19) Ensure copies of the following procedures are in the file draw ers: OTO-AE-00 002  OTG-ZZ-00 004  OTO-NB-00 002  OTN-AD-00 001  OTO-SA-00 001  OTN-BG-00 001, Addendum 4  OTO-BG-00 001  OTN-EC-00 001  ECA-0.0  E-0  E-1     E-2 Scenario 1 Scenario Malfunction L i st  File:  iltone.TXT
>Author: S. P. Aufdember ge >Date:  20050504 > >=========
====SCENARIO SE TUP ITEMS====
==========
=============
=============
=== >TAGO U T "A" M D AFW PUMP >  FILE:  AL01A.
T XT  > Red lights stay on the ESFAS P anel bat al01a.txt
>Simulates de-energization of "A" PO RV Block valve due to PORV Leakage ior bbhis8000a_ic (-1 0) 0 irf bbs014 (-
1 0) 0 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT A >'A' S/G lev xmtt r fails to 0 psig over 60 sec from t r igger #1 (MANU A L) imf fw m02 a (1) 0 60 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT B >Loss of NB02 normal feeder bre a ker, from t r igger #2 (MANUAL
) imf eps05b (2) 
>=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT C >Pressurizer Level Transmitter F a ils Low , from t r ig ger #3 (M ANUAL) imf prs02a (3) 0 60 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT D >RCS leak requir i ng Reactor trip, G ro w s to 600gp m over 10 minut es from Manual Trigger #5 imf rcs06c (5) 60 0 600 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT E >Loss of Off-Site Power, fr om Ma nual trigger #6
> Incoming Lines imf eps03a (6 0) imf eps03b (6 3) imf eps03c (6 20) imf eps03g (6 5)
>Incoming Line lights irf msb006 (6 0
) 0 irf msb007 (6 5
) 0 irf msb008 (6 3
) 0 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT F >"B" EDG tr ips and "A" EDG w ill fail to automatical ly star t.  "B" E D G fails on the loss of off-site pow e r imf eps06b (7)
>Loss of off-site po w e r "sensed" b y gr een light on RCP control s w itch trgset 7 " x 21o11 5g.eq.0" >Disable Automatic start of "A" ED G irf kjs012 (-1 0) 1
>=========
=============
=============
=============
=============
=============
== >=========
=============
=E VENT PREL O A D===========
==========
=============
====== >EVENT G > "A" CCP fails to auto star t, manual w ill be successful irf sbi008c (-1 0) 1 > > >end of file


Scenario 1 Crew Turno ver    Separate Turnover sheets provided
Appendix D                              Operator Action                              Form ES-D-2 Op Test No.:        1    Scenario #    1     Event #        2                Page 9  of 36 Event


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 1 Page 6 of 36          Event Descri p ti on: Red u ce Po w e r  T i me Positio n Appl icant's Acti ons or Beh a vi o r    SRO Refer to OT O-MA-0000 8, Rapid Load Reductio n    CREW Determine a m ount of boric acid to re duce reactor power to 90%
== Description:==
CREW Record rate of turbine lo ad change SRO Discuss am ount and rat e of turbine load change and boric acid addition with crew    SRO Notify Load Dispatcher SRO Notify Che m istry, Health Physics, an d Radwaste RO Initiate boro n equalizat ion  Energize at least 1 group of backup h eaters  Place the PZR Master Controller in MAN  Lower PZR Master Controller output to 38% to 4 2%  Place the PZR Master Controller in AUTO    6 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 1 Page 7 of 36          Event Descri p ti on: Red u ce Po w e r  T i me Positio n Appl icant's Acti ons or Beh a vi o r      RO Borate from the BAST using any of the following:  Emergency Boration o Start at least 1 Boric Acid Transfer Pump o Open Emergency Boration to Charging Pump suction BG HIS-8104 o Check Emergency Borate flow is gre a ter than 30 GPM on BG FI-183A  Borate to the VCT o Place RCS Makeup Control to STOP (BG HS-
SG Level Transmitter Failure Time          Position                          Applicants Actions or Behavior Booth Operator Instructions:
: 26) o Place RCS Makeup Control Selecto r to BORATE (BG HS-25) o Reset Boric Acid counter to 000 (BG FY-110B) o Set BG FY-110B for the desired galloons of boric acid to be added o Place BG HS-26 in RUN RO Place Rod Control in AUTO BOP Reduce turbine load at less than or equal to 5%
per minute using any of the followin g: o Reduce turbine load using the Load Limit potentiometer o Reduce turbine load using the %/min loading rat e o Rotate Load Limit Set potentiometer clockwise until both of the following are met:  Load Limit light extinguished  At Set Load - LIT o Set Loading Rate Limit %/min to desired value o Select Decrease Loadin g Rate - ON o Lower load set MW toward desired load using DECREASE LOAD push button 7 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 1 Page 8 of 36          Event Descri p ti on: Red u ce Po w e r  T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP Check MFP Turbine Speed control in AUTO    When po w e r has been reduced approximately 5%, or at Lead Evaluator's discretion, proceed to Event 2 8
Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 2 Page 9 of 36          Event Descri p ti on: SG Level T r ansmitter F a ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
When directed, insert command for SG Level Transmitter failure Indications available:
When directed, insert command for SG Level Transmitter failure Indications available:
REACT O R PARTIAL T R IP, annunciator 83C SG A LEV DEV, annunciator 108C SG A LEV LO, Annunciator 108B SRO Refer to OT O-AE-00002 for level malfunction BOP IDENTIFY f a iled chann el (LT-519) by comparin g steam generator le vel indicator
REACTOR PARTIAL TRIP, annunciator 83C SG A LEV DEV, annunciator 108C SG A LEV LO, Annunciator 108B SRO       Refer to OTO-AE-00002 for level malfunction IDENTIFY failed channel (LT-519) by comparing steam BOP generator level indicators.
: s. BOP SELECT alt e rnate level channel LT-551. BOP STABILIZE steam generator level at its programmed level (4 5-55%). BOP WHEN stea m generator level is retu rned to programmed le vel and IF place d in "MANUAL" during the transient, PLACE feedwater regulating valve to automatic control.
BOP       SELECT alternate level channel LT-551.
SRO Refer to T/S LCO 3.3.1 TAB 3.3.1-1 Item 14 and T/S LCO 3.
STABILIZE steam generator level at its programmed level (45-BOP 55%).
3.2 TAB 3.3.2-1 Item 5 and 6 and ENSURE compliance with requirement for minimu m operable channels an d action statements.
WHEN steam generator level is returned to programmed level BOP      and IF placed in MANUAL during the transient, PLACE feedwater regulating valve to automatic control.
o TS 3.3.1 and 3.3.2 apply (72 Hour Action)     SRO Refer to T/S LCO 3.3.4 and T/S LCO 3.3.3 and ENSURE compliance.
Refer to T/S LCO 3.3.1 TAB 3.3.1-1 Item 14 and T/S LCO 3.3.2 TAB 3.3.2-1 Item 5 and 6 and ENSURE compliance with SRO      requirement for minimum operable channels and action statements.
o   TS 3.3.1 and 3.3.2 apply (72 Hour Action)
Refer to T/S LCO 3.3.4 and T/S LCO 3.3.3 and ENSURE SRO compliance.
When Tech Specs have been identified, proceed to Event 3.
When Tech Specs have been identified, proceed to Event 3.
9 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 3 Page 10 of 36           Event Descri p ti on: 4KV Bus NB0 2 Normal F e e d e r Breaker T r ip  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
9
When directed, insert command for Bus NB0 2 breaker trip Indications available:
 
DG B sta r ts and supplies NB02 SHUTDOW N SEQUENCER ACTUATED TRAI N B Annun ciator 21C DIESEL GE NERAT OR NE02 TROUBLE Annu nciator 23D NB01 BREAKER NOT OPERABL E Annunciator 18F SRO Refer to OT O-NB-0000 2, Loss of P o wer to NB0 2      RO Check 4160 VAC Bus NB02 ENERGIZED R O Check E D G B-R u n n i n g    BOP Check ESW Flow Aligned to EDG B BOP Check ESW Train A Properly Aligned RO Check Reactor Power less than 100
Appendix D                             Operator Action                           Form ES-D-2 Op Test No.:       1     Scenario #   1     Event #     3               Page 10 of 36 Event
%    BOP Check SG NR Level trending to or within 45 -55
 
%    BOP Check TDAFP Secured o Throttle CLOSE TDAF P discharge FCVs     BOP Check M D AFP Secured Throttle Closed MDAFP B Discharge FCVs RO Check Pressurizer Level at or trending to program level 10 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 3 Page 11 of 36           Event Descri p ti on: 4KV Bus NB0 2 Normal F e e d e r Breaker T r ip  T i me Positio n Appl icant's Acti ons or Beh a vi o r  RO Check Pressurizer Pressure at or tr ending to 22 20 - 2250 p s ig    BOP Check CCW Pump B or D running RO Check only one chargin g pump running. Stop one ch arging pump RO Check RCP Seal Injectio n Flow between 8 -13 gpm/pump Crew Check any Service Air Compressors running BOP Check Panel PN08 Transferred to n o rmal source RO/BOP Check SFP Cooling in service BOP Check CR (A or B) and Class IE (A and B) AC u n its running BOP Check busses PK02 and PK04 RO Go to OTA-RL-RK021, Attachment C, and verify automatic LSELS actuations o Ensure equipment is in normal alignment SRO Refer to Attachment G f o r guidance concerning possible T e ch Spec action statements o TS 3.8.1 applies SRO If desired, cr oss-tie PK0 2 and PK04 to functional battery chargers in accordance with OTN-PK-00001 11 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 3 Page 12 of 36           Event Descri p ti on: 4KV Bus NB0 2 Normal F e e d e r Breaker T r ip  T i me Positio n Appl icant's Acti ons or Beh a vi o r  SRO If Swing Charger (NK26
== Description:==
) is available
4KV Bus NB02 Normal Feeder Breaker Trip Time          Position                        Applicants Actions or Behavior Booth Operator Instructions:
, refer to OTN-NK-00001 and, as requ ired, charge batteries NK12 and NK14 RO/BOP Ensure "A" Control Room Air Condit i oner is runn ing    SRO Ensure "A" Class 1E Air Conditioner is running a nd take action in accordan ce with FSAR 16.7.13.1 for the inope rable "B" Class 1E Air Conditioner When TDAFP and MDAFP flow is throttled, plant is stable, and Tech Specs have been addressed, or at Lead Examiner's discretion, proceed to Event 4 12 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 4 Page 13 of 36           Event Descri p ti on: PZ R Level T r ansmitter fails lo
When directed, insert command for Bus NB02 breaker trip Indications available:
: w. PZ R LCV fails clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
DG B starts and supplies NB02 SHUTDOWN SEQUENCER ACTUATED TRAIN B Annunciator 21C DIESEL GENERATOR NE02 TROUBLE Annunciator 23D NB01 BREAKER NOT OPERABLE Annunciator 18F SRO       Refer to OTO-NB-00002, Loss of Power to NB02 RO       Check 4160 VAC Bus NB02 ENERGIZED RO        Check EDG B-Running BOP       Check ESW Flow Aligned to EDG B BOP       Check ESW Train A Properly Aligned RO       Check Reactor Power less than 100%
When directed, insert command for Pressuri z er Level transmitter failure Indications available:
BOP       Check SG NR Level trending to or within 45 -55%
PRESSURI ZER LOW L EVEL DEVI ATION Ann unciator 32C LETDOW N HEAT EXCHANGER DISCHARGE FLOW HIGH LOW Ann unciator 39E Letdow n is olates    CREW Identify the cause of the loss of letd own. CREW Determine t hat PZR LVL INST FAIL URE occurred. (LT-459)
Check TDAFP Secured BOP o   Throttle CLOSE TDAFP discharge FCVs Check MDAFP Secured BOP Throttle Closed MDAFP B Discharge FCVs RO       Check Pressurizer Level at or trending to program level 10
RO Select altern ate Pressurizer Level Control Channel (LT-461)
 
RO Isolate letdo w n by closing all orifice isolation valves. (Already closed)     RO Reduce cha r ging flow to minimum re quired for RCP seal injection a s f o llows:     RO If the CCP is in service, SLOWLY CLOSE BH HC-182 while reducing ch arging flow using BG FK-121. Maintain approximate l y 8 GPM to each RCP seal.
Appendix D                               Operator Action                           Form ES-D-2 Op Test No.:       1     Scenario #     1     Event #       3               Page 11 of 36 Event
RO ENSURE BG-HC-182 is FULL CLOSED.
 
RO Verify Reactor Makeup Control System set in automatic for the correct boro n concentrat i ons and is maintaining VCT level.
== Description:==
RO STABILIZE pressurizer level as follo ws:       13 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 4 Page 14 of 36           Event Descri p ti on: PZ R Level T r ansmitter fails lo
4KV Bus NB02 Normal Feeder Breaker Trip Time          Position                        Applicants Actions or Behavior RO       Check Pressurizer Pressure at or trending to 2220 - 2250 psig BOP       Check CCW Pump B or D running Check only one charging pump running.
: w. PZ R LCV fails clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  CREW Restore normal letdown per OTO-BG-00001, Pressurizer Le vel Control Malfunctions.
RO
RO Ensure Letdown system containment isolation valves are open BG HIS-815 2  BG HIS-816 0    RO Ensure RCS Letdown to Regenerative Heat Exch anger Valves are open BG HIS-459 BG HIS-460     RO Throttle Charging Header back Pressure Control Valve to establish 85-90 GPM BG HIS-182     RO Place Letdo wn HX Outl et Pressure Controller in Manual and RAISE setp oint to great er than 75% open BG PK-131     RO Open Orifice Isolation V a lve(s) to establish de sir ed letdown flow BG HIS-814 9AA  BG HIS-814 9BA  BG HIS-814 9CA    RO Adjust Letdo wn HX Outl et Pressure Controller to maintain between 300 psig and 3 50 psig and place in Aut o matic  BG PK-131     RO Adjust Charging flow as necessary t o maintain Pressurizer level 14 Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 4 Page 15 of 36           Event Descri p ti on: PZ R Level T r ansmitter fails lo
* Stop one charging pump RO       Check RCP Seal Injection Flow between 8 -13 gpm/pump Crew       Check any Service Air Compressors running BOP       Check Panel PN08 Transferred to normal source RO/BOP       Check SFP Cooling in service BOP       Check CR (A or B) and Class IE (A and B) AC units running BOP       Check busses PK02 and PK04 Go to OTA-RL-RK021, Attachment C, and verify automatic RO      LSELS actuations o   Ensure equipment is in normal alignment Refer to Attachment G for guidance concerning possible Tech SRO      Spec action statements o   TS 3.8.1 applies If desired, cross-tie PK02 and PK04 to functional battery SRO chargers in accordance with OTN-PK-00001 11
: w. PZ R LCV fails clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r        When Letdow n is restored, proceed to Event 5 15 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 16 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
 
Appendix D                             Operator Action                         Form ES-D-2 Op Test No.:       1     Scenario #   1     Event #     3               Page 12 of 36 Event
 
== Description:==
4KV Bus NB02 Normal Feeder Breaker Trip Time          Position                      Applicants Actions or Behavior If Swing Charger (NK26) is available, refer to OTN-NK-00001 SRO and, as required, charge batteries NK12 and NK14 RO/BOP       Ensure A Control Room Air Conditioner is running Ensure A Class 1E Air Conditioner is running and take action SRO      in accordance with FSAR 16.7.13.1 for the inoperable B Class 1E Air Conditioner When TDAFP and MDAFP flow is throttled, plant is stable, and Tech Specs have been addressed, or at Lead Examiners discretion, proceed to Event 4 12
 
Appendix D                               Operator Action                             Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       4               Page 13 of 36 Event
 
== Description:==
PZR Level Transmitter fails low. PZR LCV fails closed Time          Position                          Applicants Actions or Behavior Booth Operator Instructions:
When directed, insert command for Pressurizer Level transmitter failure Indications available:
PRESSURIZER LOW LEVEL DEVIATION Annunciator 32C LETDOWN HEAT EXCHANGER DISCHARGE FLOW HIGH LOW Annunciator 39E Letdown isolates CREW       Identify the cause of the loss of letdown.
CREW       Determine that PZR LVL INST FAILURE occurred. (LT-459)
RO       Select alternate Pressurizer Level Control Channel (LT-461)
Isolate letdown by closing all orifice isolation valves. (Already RO closed)
Reduce charging flow to minimum required for RCP seal RO injection as follows:
If the CCP is in service, SLOWLY CLOSE BH HC-182 while RO        reducing charging flow using BG FK-121. Maintain approximately 8 GPM to each RCP seal.
RO       ENSURE BG-HC-182 is FULL CLOSED.
Verify Reactor Makeup Control System set in automatic for the RO correct boron concentrations and is maintaining VCT level.
RO       STABILIZE pressurizer level as follows:
13
 
Appendix D                               Operator Action                             Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       4               Page 14 of 36 Event
 
== Description:==
PZR Level Transmitter fails low. PZR LCV fails closed Time          Position                          Applicants Actions or Behavior Restore normal letdown per OTO-BG-00001, Pressurizer Level CREW Control Malfunctions.
Ensure Letdown system containment isolation valves are open RO
* BG HIS-8152
* BG HIS-8160 Ensure RCS Letdown to Regenerative Heat Exchanger Valves are open RO
* BG HIS-459
* BG HIS-460 Throttle Charging Header back Pressure Control Valve to RO        establish 85-90 GPM
* BG HIS-182 Place Letdown HX Outlet Pressure Controller in Manual and RO        RAISE setpoint to greater than 75% open
* BG PK-131 Open Orifice Isolation Valve(s) to establish desired letdown flow RO
* BG HIS-8149AA
* BG HIS-8149BA
* BG HIS-8149CA Adjust Letdown HX Outlet Pressure Controller to maintain RO        between 300 psig and 350 psig and place in Automatic
* BG PK-131 Adjust Charging flow as necessary to maintain Pressurizer RO level 14
 
Appendix D                               Operator Action                             Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       4               Page 15 of 36 Event
 
== Description:==
PZR Level Transmitter fails low. PZR LCV fails closed Time          Position                          Applicants Actions or Behavior When Letdown is restored, proceed to Event 5 15
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 16   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time        Position                          Applicants Actions or Behavior Booth Operator Instructions:
When directed, insert commands for remaining events as sequenced Indications available:
When directed, insert commands for remaining events as sequenced Indications available:
PROCESS RADI ATION HIGH Ann unciator 61B Rising trend on Iodine and Particulate Channels 31, 32 If RMS has not been reset from previous failure, the follow i n g alarms w ill also indicate an RCS leak:
PROCESS RADIATION HIGH Annunciator 61B Rising trend on Iodine and Particulate Channels 31, 32 If RMS has not been reset from previous failure, the following alarms will also indicate an RCS leak:
PRES SURI ZER LOW L EVEL DE VI ATION, 32C PRES SURI ZER PR ES SURE L O W HEATE R S ON, 33C     CREW DETERMINE the approximate size of the leak.
PRESSURIZER LOW LEVEL DEVIATION, 32C PRESSURIZER PRESSURE LOW HEATERS ON, 33C DETERMINE the approximate size of the leak. Should CREW determine greater than 50 GPM leak NOTE:       The plant computer group tabular time trend GT-SG17 can be used to approximate the leak size.
Should determine greater than 50 GPM lea k    NOTE: The plant computer group tabular time trend GT-SG17 can be used to approximate the leak size.
USE trends of VCT level (20 GAL/%) and/or PZR level RO (60 GAL/%).
RO USE trends of VCT level (20 GAL/%) and/or PZR level (60 GAL/%).
NOTE:       Only one charging pump should be in operation until PZR level is increased for the plant cooldown.
NOTE: Onl y one c harging pump should be in operation until PZR level is increased for the plant cooldo w n. RO COMPARE Charging and Letdown flow rates. Crew should determine that PZR level CANNOT b e maintained.
COMPARE Charging and Letdown flow rates. Crew should RO determine that PZR level CANNOT be maintained.
SRO Direct Reactor Trip RO CHEC K Re actor Trip:
SRO       Direct Reactor Trip RO       CHECK Reactor Trip:
Rod Bottom Lights - ALL LIT   Reactor Trip and Bypass Breakers -
* Rod Bottom Lights - ALL LIT
OPEN    Neutron Flux - LOWERI NG 16 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 17 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP CHECK Turbine Trip:
* Reactor Trip and Bypass Breakers - OPEN
All turbine S t op valves - CLOSED.
* Neutron Flux - LOWERING 16
CREW CHECK Po wer to AC Emergency Buses:
 
AC emerge ncy buses - AT LEAST ONE E N E R GIZED    NB01(NO)
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 17   of   36 Event
O R    NB02(NO)
 
SRO DIRECT S Go to ECA-0.
== Description:==
0, Loss of All AC Power, Step 1. RO CHEC K Re actor Trip:
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior BOP       CHECK Turbine Trip:
Reactor Trip and Bypass Breakers -
All turbine Stop valves - CLOSED.
OPEN    Neutron Flux - LOWERI NG    BOP CHECK Turbine Trip:
CREW       CHECK Power to AC Emergency Buses:
All Turbine Stop valves  
AC emergency buses - AT LEAST ONE ENERGIZED
- CLOSED. RO CHECK if RCS is Isolat ed:     a. PZR PORV s - CLOSE D    BB HIS-455 A    BB HIS-456 A      b. Letdown Isolation Valves - CLOSED 17 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 18 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    1. Letdown Orifice Isolation valves:   BG HIS-814 9AA    BG HIS814 9BA    BG HIS-814 9CA      2. RCS Letdo wn to Regen HX val v es:   BG HIS-459   BG HIS-460     c. RCS to Excess Letdow n HX val v es - CLOSED BG HIS-815 3A    BG HIS-815 4A    BG HIS-815 3B    BG HIS-815 4B    RO CLOSE valve(s) as nece ssary.       d. Reactor Head Vent Valves - CLOSED BB HIS-800 1A    BB HIS-800 2A    BB HIS-800 1B    BB HIS-800 2B    BOP CHECK AF W Flow - GREATER T H AN 300,00 0 LBM/HR     CREW TRY to Restore Power to Any AC Emergency Bus:
* NB01(NO)
: a. ENERGIZE AC emerge ncy bus with diesel gene rator:   18 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 19 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r  CRITIC A L TA S K  1. START D G (s):   KJ HS-8A -
OR
DG - "A"
* NB02(NO)
: 2. CHECK AC emergency buses - AT LEAST ONE ENERGIZE D    NB01 - ENERGIZED O R    NB02 - NOT ENERGIZ E D    CREW b. CHECK AC emergency buses - AT LEAST ONE ENERGIZE D    NB01 - YES BOP c. CHECK ESW Pump associated wit h energized AC emergency bus(es) - RUNNI NG    EF HIS-55A (NB01) - YES
SRO       DIRECTS Go to ECA-0.0, Loss of All AC Power, Step 1.
: d. Return to procedure and step in effe ct and IMPLEMENT Functional Restoration Procedures as necessar y. Crew will review CSF Status Trees.
RO       CHECK Reactor Trip:
None currently required for implementat ion    SRO DIRECT S re turn to E-0.
* Reactor Trip and Bypass Breakers - OPEN
R O CHEC K S I S t a t u s:     a. CHECK is SI is actuated
* Neutron Flux - LOWERING BOP       CHECK Turbine Trip:
:    Any SI annu nciator 88A through 88D - LIT O R    SB069 SI Actuate RED light - LIT O R 19 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 20 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    LOCA Sequ encer annun ciators 30A or 31A - LIT
All Turbine Stop valves - CLOSED.
: b. CHECK bot h Trains of SI - ACTUATED LOCA Sequ encer annun ciator 30A -
RO       CHECK if RCS is Isolated:
LIT    LOCA Sequ encer annun ciator 31A -
: a. PZR PORVs - CLOSED
NOT LIT   SB069 SI Actuate RED light - LIT S O LID (NOT blinking)
* BB HIS-455A
Note: A tta ch me n t A co nt a i ns a Critical T ask BOP PERF O RM Attachment A, Automati c Action Ver i fication, while continuing w i th this pro c edure. (Actions for Attachment A begin on page 32 of t h is guide)
* BB HIS-456A
RO CHECK Ge nerator Output Breakers - OPEN MA ZL-3A (V55)
: b. Letdown Isolation Valves - CLOSED 17
MA ZL-4A (V53)
 
RO CHECK Fee dwater Isola t ion:     a. Main Feedwater Pumps - TRIPPED Annunciator 120A, MFP A Trip - LIT Annunciator 123A, MFP B Trip - LIT
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 18   of   36 Event
: b. Main Feedwater Reg Valves - CLOSED AE ZL-510 (SG A)
 
AE ZL-520 (SG B)
== Description:==
AE ZL-530 (SG C)
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
AE ZL-540 (SG D)
: 1. Letdown Orifice Isolation valves:
: c. Main Feedwater Reg Bypass Valves - CLOSED AE ZL-550 (SG A) 20 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 21 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    AE ZL-560 (SG B)
* BG HIS-8149AA
AE ZL-570 (SG C)
* BG HIS8149BA
AE ZL-580 (SG D)
* BG HIS-8149CA
: d. Feedwater Isolation Valves - CLOSED AE HIS-39 (S G A)   AE HIS-40 (S G B)   AE HIS-41 (S G C)   AE HIS-42 (S G D)     RO CHEC K AF W Pumps:     a. MD AFW Pumps - BOT H RUNNING   AL HIS-23A   AL HIS-22A     b. TD AFW Pu mp - RUNNING IF NE CESSA RY    RO CHECK AF W Valves - PROPER E M ERGE NCY ALIGNME N T    MD AF P Flow Control Valves - THROTTLED AL HK-7A   AL HK-9A   AL HK-11A   AL-HK-5A TD AFP Flow Control Valves - FULL OPEN AL HK-8A   AL HK-10A   AL HK-12A   AL HK-6A 21 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 22 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r      RO CHECK Tot al AFW Flow - GREAT E R THAN 3 00,000 LBM/HR RO CHECK PZ R PORVs and Spray Va lves:     a. PZR PORV s - CLOSE D    BB HIS-455 A    BB HIS-456 A      b. PZR PORV s - BOTH I N AUT O    BB HIS-455 A    BB HIS-456 A      c. PORV Block Valves - BOTH OPEN   BB HIS-800 0A    BB HIS-800 0B      d. Normal PZR Spray Valves - CLOSED BB ZL-455B   BB ZL-455C     RO CHECK If RCPs Should Be Stopped:
: 2. RCS Letdown to Regen HX valves:
: a. RCPs - AN Y RUN NIN G (N O)     SRO Go to Step 13.
* BG HIS-459
RO CHECK RCS Temperat ures:   NO RCPs ru nning - RCS COL D LE G TE MPERATURE S STABLE AT 557°F OR TRENDI NG TO 557°F 22 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 23 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r      CREW CHECK If any SG Is Fa ulted:     a. CHECK pressures in all SGs:   ANY S G PRESSURE L O WERI NG I N AN UNC ONT R OLLED MA NNER    O R    ANY S G COMPLETEL Y DEPRESS URIZED    SRO Go to Step 15.
* BG HIS-460
CREW CHECK If SG Tubes Are Intact:
: c. RCS to Excess Letdown HX valves - CLOSED
Levels in all SGs:       NO S G NA RROW RAN G E LEV E L RISIN G IN AN UNC ONT R OLLED MA NNER      SG Stea mline N16 radiation - NORMAL N16 161 (SG A)
* BG HIS-8153A
N16 162 (SG B)
* BG HIS-8154A
N16 163 (SG C)
* BG HIS-8153B
N16 164 (SG D)
* BG HIS-8154B RO             CLOSE valve(s) as necessary.
Condenser Air Remo val radiation -
: d. Reactor Head Vent Valves - CLOSED
NORMAL BEFORE ISOLATI O N    GEG 925       SG Blowdo wn and Sample radiation
* BB HIS-8001A
- NORMAL BEFORE ISOLATI O N    BML 256   SJL 026 23 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 24 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r        SG ASD rad i ation - NORMAL AB RIC 111 (SG A)   AB RIC 112 (SG B)   AB RIC 113 (SG C)   AB RIC 114 (SG D)       Turbine Driven Auxiliary Feedwater Pump exha ust radiation -
* BB HIS-8002A
NORMAL    FC RIC 385 RO CHECK If RCS Is Intact:
* BB HIS-8001B
Containmen t Pressure -
* BB HIS-8002B BOP       CHECK AFW Flow - GREATER THAN 300,000 LBM/HR CREW       TRY to Restore Power to Any AC Emergency Bus:
NORMAL (NO)
: a. ENERGIZE AC emergency bus with diesel generator:
GN PI-934   GN PI-935   GN PI-936   GN PI-937   GN PR-934       Containmen t Normal Su mp Level -
18
NORMAL    EJ LI-8   EJ LI-7   EJ LR-6       Containmen t Normal sump Level -
 
NORMAL    LF LI-9   LF LI-10   24 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 25 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    Containmen t Radiation  
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 19   of   36 Event
- NORMAL BEFORE ISOLATION GTG 313   GTG 323   GTA 591   GTA 601     SRO Go To E-1, Loss of Rea c tor or Seco ndary Coola n t, Step 1.
 
NOTE: Seal injection flo w sho uld be maintained to all RCPs.
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior CRITICAL TASK                              1. START DG(s):
* KJ HS-8A - DG - A
: 2. CHECK AC emergency buses - AT LEAST ONE ENERGIZED
* NB01 - ENERGIZED OR
* NB02 - NOT ENERGIZED
: b. CHECK AC emergency buses - AT LEAST ONE CREW ENERGIZED
* NB01 - YES
: c. CHECK ESW Pump associated with energized AC BOP emergency bus(es) - RUNNING
* EF HIS-55A (NB01) - YES
: d. Return to procedure and step in effect and IMPLEMENT Functional Restoration Procedures as necessary.
* Crew will review CSF Status Trees. None currently required for implementation SRO       DIRECTS return to E-0.
RO        CHECK SI Status:
: a. CHECK is SI is actuated:
* Any SI annunciator 88A through 88D - LIT OR
* SB069 SI Actuate RED light - LIT OR 19
 
Appendix D                                 Operator Action                            Form ES-D-2 Op Test No.:       1     Scenario #     1     Event #       5, 6, 7, & 8     Page 20   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time        Position                          Applicants Actions or Behavior
* LOCA Sequencer annunciators 30A or 31A - LIT
: b. CHECK both Trains of SI - ACTUATED
* LOCA Sequencer annunciator 30A - LIT
* LOCA Sequencer annunciator 31A - NOT LIT
* SB069 SI Actuate RED light - LIT SOLID (NOT blinking)
Note:                   PERFORM Attachment A, Automatic Action Verification, while Attachment        BOP      continuing with this procedure.
A contains a Critical Task                (Actions for Attachment A begin on page 32 of this guide)
RO       CHECK Generator Output Breakers - OPEN
* MA ZL-3A (V55)
* MA ZL-4A (V53)
RO       CHECK Feedwater Isolation:
: a. Main Feedwater Pumps - TRIPPED
* Annunciator 120A, MFP A Trip - LIT
* Annunciator 123A, MFP B Trip - LIT
: b. Main Feedwater Reg Valves - CLOSED
* AE ZL-510 (SG A)
* AE ZL-520 (SG B)
* AE ZL-530 (SG C)
* AE ZL-540 (SG D)
: c. Main Feedwater Reg Bypass Valves - CLOSED
* AE ZL-550 (SG A) 20
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 21   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
* AE ZL-560 (SG B)
* AE ZL-570 (SG C)
* AE ZL-580 (SG D)
: d. Feedwater Isolation Valves - CLOSED
* AE HIS-39 (SG A)
* AE HIS-40 (SG B)
* AE HIS-41 (SG C)
* AE HIS-42 (SG D)
RO       CHECK AFW Pumps:
: a. MD AFW Pumps - BOTH RUNNING
* AL HIS-23A
* AL HIS-22A
: b. TD AFW Pump - RUNNING IF NECESSARY RO       CHECK AFW Valves - PROPER EMERGENCY ALIGNMENT
* MD AFP Flow Control Valves - THROTTLED
* AL HK-7A
* AL HK-9A
* AL HK-11A
* AL-HK-5A
* TD AFP Flow Control Valves - FULL OPEN
* AL HK-8A
* AL HK-10A
* AL HK-12A
* AL HK-6A 21
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 22   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior RO       CHECK Total AFW Flow - GREATER THAN 300,000 LBM/HR RO       CHECK PZR PORVs and Spray Valves:
: a. PZR PORVs - CLOSED
* BB HIS-455A
* BB HIS-456A
: b. PZR PORVs - BOTH IN AUTO
* BB HIS-455A
* BB HIS-456A
: c. PORV Block Valves - BOTH OPEN
* BB HIS-8000A
* BB HIS-8000B
: d. Normal PZR Spray Valves - CLOSED
* BB ZL-455B
* BB ZL-455C RO       CHECK If RCPs Should Be Stopped:
: a. RCPs - ANY RUNNING (NO)
SRO       Go to Step 13.
RO       CHECK RCS Temperatures:
* NO RCPs running - RCS COLD LEG TEMPERATURES STABLE AT 557°F OR TRENDING TO 557°F 22
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 23   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior CREW       CHECK If any SG Is Faulted:
: a. CHECK pressures in all SGs:
* ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR
* ANY SG COMPLETELY DEPRESSURIZED SRO       Go to Step 15.
CREW       CHECK If SG Tubes Are Intact:
* Levels in all SGs:
* NO SG NARROW RANGE LEVEL RISING IN AN UNCONTROLLED MANNER
* SG Steamline N16 radiation - NORMAL
* N16 161 (SG A)
* N16 162 (SG B)
* N16 163 (SG C)
* N16 164 (SG D)
* Condenser Air Removal radiation - NORMAL BEFORE ISOLATION
* GEG 925
* SG Blowdown and Sample radiation - NORMAL BEFORE ISOLATION
* BML 256
* SJL 026 23
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 24   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
* SG ASD radiation - NORMAL
* AB RIC 111 (SG A)
* AB RIC 112 (SG B)
* AB RIC 113 (SG C)
* AB RIC 114 (SG D)
* Turbine Driven Auxiliary Feedwater Pump exhaust radiation - NORMAL
* FC RIC 385 RO       CHECK If RCS Is Intact:
* Containment Pressure - NORMAL (NO)
* GN PI-934
* GN PI-935
* GN PI-936
* GN PI-937
* GN PR-934
* Containment Normal Sump Level - NORMAL
* EJ LI-8
* EJ LI-7
* EJ LR-6
* Containment Normal sump Level - NORMAL
* LF LI-9
* LF LI-10 24
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 25   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
* Containment Radiation - NORMAL BEFORE ISOLATION
* GTG 313
* GTG 323
* GTA 591
* GTA 601 SRO       Go To E-1, Loss of Reactor or Secondary Coolant, Step 1.
NOTE:       Seal injection flow should be maintained to all RCPs.
CHECK If RCPs Should Be Stopped:
CHECK If RCPs Should Be Stopped:
Loss of Power, already - TRIPPED BOP CHECK If Any SG Is Fa ulted:     CHECK pressures in all SGs:   ANY S G PRESSURE L O WERI NG I N AN UNC ONT R OLLED MA NNER    O R    ANY S G COMPLETEL Y DEPRESS URIZED (NO)
Loss of Power, already - TRIPPED BOP       CHECK If Any SG Is Faulted:
CHECK pressures in all SGs:
* ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR
* ANY SG COMPLETELY DEPRESSURIZED (NO)
Go to Step 3.
Go to Step 3.
BOP CHECK Intact SG Level s:     a. Narrow rang e levels - GREATER T H AN 7% [25%]     b. CONT ROL f eed flow to maintain narrow range levels between 7% [25%] and 50% 25 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 26 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP CHECK Sec ondary Radi ation - NORMAL
BOP       CHECK Intact SG Levels:
: a. PERF O RM the following:
: a. Narrow range levels - GREATER THAN 7% [25%]
PERF O RM EOP Adden dum 11, Re storing SG Sampling After SI Actuation DIRECT Ch emistry to periodically sample all SGs for activity.
: b. CONTROL feed flow to maintain narrow range levels between 7% [25%] and 50%
DIRECT He alth Physics to survey steamlines in Auxiliary Bui l ding Area 5 as necessa ry      b. CHECK unisolated se condary radiation monitors:
25
SG Sa mple radiation:
 
SJL 026   SG ASD rad i ation:   AB RIC 111 (SG A)   AB RIC 112 (SG B)   AB RIC 113 (SG C)   AB RIC 114 (SG D)   Turbine Driven Auxiliary Feedwater Pump Exha ust radiation:
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 26   of   36 Event
FC RIC 385
 
: c. Secondary radiation - N O RMAL    RO CHECK PZ R PORVs and Block Valves:
== Description:==
: a. Power to Block Valves  
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior BOP       CHECK Secondary Radiation - NORMAL
- AVAILABL E    BB HIS-800 0A (NO)   BB HIS-800 0B    26 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 27 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    b. PZR PORV s - CLOSE D    BB HIS-455 A    BB HIS-456 A      c. Block Valves - BOTH OPEN BB HIS-800 0A (NO)   BB HIS-800 0B    Crew CHECK If ECCS Flow Should Be Reduced:
: a. PERFORM the following:
* PERFORM EOP Addendum 11, Restoring SG Sampling After SI Actuation
* DIRECT Chemistry to periodically sample all SGs for activity.
* DIRECT Health Physics to survey steamlines in Auxiliary Building Area 5 as necessary
: b. CHECK unisolated secondary radiation monitors:
* SG Sample radiation:
* SJL 026
* SG ASD radiation:
* AB RIC 111 (SG A)
* AB RIC 112 (SG B)
* AB RIC 113 (SG C)
* AB RIC 114 (SG D)
* Turbine Driven Auxiliary Feedwater Pump Exhaust radiation:
* FC RIC 385
: c. Secondary radiation - NORMAL RO       CHECK PZR PORVs and Block Valves:
: a. Power to Block Valves - AVAILABLE
* BB HIS-8000A (NO)
* BB HIS-8000B 26
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 27   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
: b. PZR PORVs - CLOSED
* BB HIS-455A
* BB HIS-456A
: c. Block Valves - BOTH OPEN
* BB HIS-8000A (NO)
* BB HIS-8000B Crew       CHECK If ECCS Flow Should Be Reduced:
: a. RCS subcooling - GREATER THAN 30°F
: a. RCS subcooling - GREATER THAN 30°F
: b. Secondary heat sink:
: b. Secondary heat sink:
Narrow rang e level in at least one int a ct SG - GREATER THAN 7% [2 5%]   O R    Total feed flow to intact SGs - GREATER THAN 300,00 LBM/HR
* Narrow range level in at least one intact SG -
: c. RCS pressure - STABL E OR RISING     d. PZR level - GREATER THAN 9% [2 9%] (NO)     RO CHECK If Containment Spray should Be Stopped:
GREATER THAN 7% [25%]
: a. Spray Pu mp s - ANY RUNNING SRO Go to Step 8. OBSERVE CAUTI O NS prior to Step 8.
OR
27 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 28 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r  CAUTI O N: If RCS pres sure low e rs in an uncontrolled manner to less than 325 PSIG, the RHR pumps must be manuall y resta r ted to suppl y w a ter to the RCS. RO CHECK If RHR Pu mps Should Be Stopped:
* Total feed flow to intact SGs - GREATER THAN 300,00 LBM/HR
: a. CHEC K RC S pressure:
: c. RCS pressure - STABLE OR RISING
: 1. Pressure -
: d. PZR level - GREATER THAN 9% [29%] (NO)
GREATER THAN 325 PSIG       2. Pressure -
RO       CHECK If Containment Spray should Be Stopped:
STABLE OR RISING
: a. Spray Pumps - ANY RUNNING SRO       Go to Step 8. OBSERVE CAUTIONS prior to Step 8.
: b. RHR Pu mps - ANY RU NNIN G WIT H SUCTI O N ALIGNE D TO RWST     c. RESET SI if necessary:
27
SB HS-42A   SB HS-43A     d. STOP RHR Pumps and PLACE in standby:
 
EJ HIS-1   EJ HIS-2     e. MONITOR R C S p r e s s u r e    CREW CHECK SG and RCS Pressures:
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 28   of   36 Event
CHECK pre ssure in all SGs - STABLE OR RI SING    CHECK RCS pressure  
 
- STABLE OR LOWERING CREW CHECK If Di esel Generators Should Be Stopped:
== Description:==
28 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 29 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    a. AC emerge ncy buses -
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior CAUTION:         If RCS pressure lowers in an uncontrolled manner to less than 325 PSIG, the RHR pumps must be manually restarted to supply water to the RCS.
ENERGIZED BY OFF S I T E POWE R    NB01 (NO)   NB02 (NO)     TRY to restore offsite p o wer to AC emergency buses using EOP Adden dum 7, Restoring Offsite Power.     b. RESET SI if necessary:
RO       CHECK If RHR Pumps Should Be Stopped:
SB HS-42A   SB HS-43A     c. LOAD equip m ent on AC emergency bus(es) as n e cessary using EOP Addendum 8, Loading Equipment on AC emergency Buses.
: a. CHECK RCS pressure:
CREW INITIATE Evaluation of P l ant Status:
: 1. Pressure - GREATER THAN 325 PSIG
: a. CHECK cold leg recircu l ation capab ility:   Train A - AVAILABLE RHR Pu mp A (EJ HIS-1
: 2. Pressure - STABLE OR RISING
)    CCW Pu mp A (EG HI S-2 1) or CCW Pump C (EG HIS-23)
: b. RHR Pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST
RWST To RHR Pu mp A Suction (BN HIS-8812A)
: c. RESET SI if necessary:
Containmen t Recirc Su mp to RHR Pump A Suc t ion (EJ HIS-8811A)
* SB HS-42A
CCW to RHR HX A (EG HIS-101)
* SB HS-43A
Train B - AVAILABLE RHR Pu mp B (EJ HIS-2
: d. STOP RHR Pumps and PLACE in standby:
)    CCW Pu mp B (EG HI S-2 2) or CCW Pump D (EG HIS-24)
* EJ HIS-1
RWST To RHR Pu mp B Suction (BN HIS-8812B) 29 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 30 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    CCW to RHR HX B (EG HIS-102)
* EJ HIS-2
: b. CHECK Auxiliary Buildin g radiation -
: e. MONITOR RCS pressure CREW       CHECK SG and RCS Pressures:
NORMAL    Aux Building Process Ra diation monitor:
* CHECK pressure in all SGs - STABLE OR RISING
GLP 604   Aux Building Area Radiation monitors TRY to identify and isolat e leakage:
* CHECK RCS pressure - STABLE OR LOWERING CREW       CHECK If Diesel Generators Should Be Stopped:
DIRECT He alth Physics and Chemistry to assist in the evaluation as necessary.
28
IF the cause is a loss of RCS invent ory outside containment, THEN Go To ECA-1.2, LOCA Outside Containment, Step 1.
 
: c. O B T A I N sam p l e s:   1. DIRECT Ch emistry to initiate post a ccident sampling:
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 29   of   36 Event
RCS boron concentratio n    RCS activity   Containmen t atmosphere
 
: 2. PLACE Hyd r ogen Analyzers in Service using EOP Addendum 16, Placing Hydrogen Analyzers In Service. 3. CONSULT Plant Engineering Staff for assessin g additional sampling requirements for fuel damage.
== Description:==
: d. EVALUAT E plant equipment for long term recovery as necessary:
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
Hydrogen Recombiners Radwaste systems   Radiation monitoring Post accide nt monitoring Operating safeguards e quipment:
: a. AC emergency buses - ENERGIZED BY OFFSITE POWER
30 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 1 Event # 5, 6, 7, & 8 Page 31 of 36           Event Descri p ti on: RCS Le ak - Lo ss of Off-Site Po w e r - SBLOC A - DG T r ip - HHSI Pump Fa ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    CCPs   SI Pumps   RHR Pu mps    CS Pu mps    ESW Pump s    CCW Pu mp s    Containmen t Cooler Fans Containmen t Hydrogen Mixing Fans AFW Pump s    Control Room ventilation Auxiliary Bui l ding ventilat i on    Fuel Buildin g ventilation
* NB01 (NO)
: e. START additional plant equipment to assist in r e covery as directed by SS/CRS CREW CHECK If RCS Cooldown And Depressurizat i on Is Required
* NB02 (NO)
: a. RCS pressure - GREAT ER THAN 3 25 PSIG     b. Go to ES-1.
TRY to restore offsite power to AC emergency buses using EOP Addendum 7, Restoring Offsite Power.
2, Post LOCA Cooldown And Depressurization, Step 1   Scenario ma y be termi nated on transition to ES-1.2, or w hen all cri t ical tasks are complete and at Lead Examiner discretion 31 ATTAC H MENT A Automatic Action Veri fication  BOP CHECK Ch arging Pumps:
: b. RESET SI if necessary:
CRITIC A L TA S K BOP a. CCPs - BOTH RUN NIN G    BG HI S-1A (Must man uall y start HHSI Pump 'A')   BG HIS-2 A    B O P b. S T O P NCP:   BG HIS-3     BOP CHEC K SI And RHR P u mps    SI Pumps -
* SB HS-42A
BOTH RUN NING (N O)   EM HI S-4     EM HI S-5   RHR Pu mps - BOTH R UNNI NG    EJ HIS-1   EJ HIS-2     BOP CHECK ECCS Flow:
* SB HS-43A
BOP a. CCPs to Boron Inj Header - FLOW INDICAT E D    EM FI-917A   EM FI-917B     BOP b. RCS pressure - LESS T H AN 1700 PSIG BOP c. SI Pump Dis c harge - FL OW INDI CATED    EM FI-918   EM FI-922     BOP d. RCS pressure - LESS T H AN 325 PSIG 32 ATTAC H MENT A Automatic Action Veri fication  BOP e. RHR To Acc u mulator Injection Loop  
: c. LOAD equipment on AC emergency bus(es) as necessary using EOP Addendum 8, Loading Equipment on AC emergency Buses.
- FLOW INDICATED EJ FI-618   EJ FI-619   CAUTI O N: If offsite pow er is lost after SI res e t, manual action ma y be required to restart s a feguards equipment.
CREW       INITIATE Evaluation of Plant Status:
BOP CHECK ES W Pumps - BOTH RUNNING   EF HIS-55A   EF HIS-56A     BOP CHEC K CC W Alignment:
: a. CHECK cold leg recirculation capability:
BOP a. CCW Pu mp s - ONE RU NNIN G IN E A CH TR AIN    Red Train:   EG HIS-21 or EG HIS-2 3    Yellow Train   EG HIS-22 or EG HIS-2 4    BOP b. CCW Service Loop Supply and Return valves for one operating CCW pump -
* Train A - AVAILABLE
OPEN    EG ZL-15 AND EG ZL-53 O R    EG ZL-16 AND EG ZL-54 BOP CHECK Co ntainment Cooler Fans -
* RHR Pump A (EJ HIS-1)
RUNNING I N SLOW SPEE D    GN HI S-9   GN HI S-17   GN HI S-5   GN HI S-13     BOP CHECK Co ntainment Hydrogen Mi xing Fans -
* CCW Pump A (EG HIS-21) or CCW Pump C (EG HIS-23)
RUNNING I N SLOW SP E E D 33 ATTAC H MENT A Automatic Action Veri fication    GN HI S-2   GN HI S-4   GN HI S-1   GN HI S-3     BOP CHECK If Containment Spray Shoul d Be Actuated:
* RWST To RHR Pump A Suction (BN HIS-8812A)
* Containment Recirc Sump to RHR Pump A Suction (EJ HIS-8811A)
* CCW to RHR HX A (EG HIS-101)
* Train B - AVAILABLE
* RHR Pump B (EJ HIS-2)
* CCW Pump B (EG HIS-22) or CCW Pump D (EG HIS-24)
* RWST To RHR Pump B Suction (BN HIS-8812B) 29
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 30   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
* CCW to RHR HX B (EG HIS-102)
: b. CHECK Auxiliary Building radiation - NORMAL
* Aux Building Process Radiation monitor:
* GLP 604
* Aux Building Area Radiation monitors TRY to identify and isolate leakage:
* DIRECT Health Physics and Chemistry to assist in the evaluation as necessary.
IF the cause is a loss of RCS inventory outside containment, THEN Go To ECA-1.2, LOCA Outside Containment, Step 1.
: c. OBTAIN samples:
: 1. DIRECT Chemistry to initiate post accident sampling:
* RCS boron concentration
* RCS activity
* Containment atmosphere
: 2. PLACE Hydrogen Analyzers in Service using EOP Addendum 16, Placing Hydrogen Analyzers In Service.
: 3. CONSULT Plant Engineering Staff for assessing additional sampling requirements for fuel damage.
: d. EVALUATE plant equipment for long term recovery as necessary:
* Hydrogen Recombiners
* Radwaste systems
* Radiation monitoring
* Post accident monitoring
* Operating safeguards equipment:
30
 
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     1       Event #       5, 6, 7, & 8     Page 31   of   36 Event
 
== Description:==
RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time          Position                          Applicants Actions or Behavior
* CCPs
* SI Pumps
* RHR Pumps
* CS Pumps
* ESW Pumps
* CCW Pumps
* Containment Cooler Fans
* Containment Hydrogen Mixing Fans
* AFW Pumps
* Control Room ventilation
* Auxiliary Building ventilation
* Fuel Building ventilation
: e. START additional plant equipment to assist in recovery as directed by SS/CRS CREW       CHECK If RCS Cooldown And Depressurization Is Required
: a. RCS pressure - GREATER THAN 325 PSIG
: b. Go to ES-1.2, Post LOCA Cooldown And Depressurization, Step 1 Scenario may be terminated on transition to ES-1.2, or when all critical tasks are complete and at Lead Examiner discretion 31
 
ATTACHMENT A Automatic Action Verification BOP CHECK Charging Pumps:
CRITICAL TASK    BOP a. CCPs - BOTH RUNNING
* BG HIS-1A (Must manually start HHSI Pump A)
* BG HIS-2A BOP b. STOP NCP:
* BG HIS-3 BOP CHECK SI And RHR Pumps
* SI Pumps - BOTH RUNNING (NO)
* EM HIS-4
* EM HIS-5
* RHR Pumps - BOTH RUNNING
* EJ HIS-1
* EJ HIS-2 BOP CHECK ECCS Flow:
BOP a. CCPs to Boron Inj Header - FLOW INDICATED
* EM FI-917A
* EM FI-917B BOP b. RCS pressure - LESS THAN 1700 PSIG BOP c. SI Pump Discharge - FLOW INDICATED
* EM FI-918
* EM FI-922 BOP d. RCS pressure - LESS THAN 325 PSIG 32
 
ATTACHMENT A Automatic Action Verification BOP       e. RHR To Accumulator Injection Loop - FLOW INDICATED
* EJ FI-618
* EJ FI-619 CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
BOP       CHECK ESW Pumps - BOTH RUNNING
* EF HIS-55A
* EF HIS-56A BOP       CHECK CCW Alignment:
BOP       a. CCW Pumps - ONE RUNNING IN EACH TRAIN
* Red Train:
* EG HIS-21 or EG HIS-23
* Yellow Train
* EG HIS-22 or EG HIS-24
: b. CCW Service Loop Supply and Return valves for one BOP operating CCW pump - OPEN
* EG ZL-15 AND EG ZL-53 OR
* EG ZL-16 AND EG ZL-54 CHECK Containment Cooler Fans - RUNNING IN SLOW BOP SPEED
* GN HIS-9
* GN HIS-17
* GN HIS-5
* GN HIS-13 CHECK Containment Hydrogen Mixing Fans - RUNNING IN BOP SLOW SPEED 33
 
ATTACHMENT A Automatic Action Verification
* GN HIS-2
* GN HIS-4
* GN HIS-1
* GN HIS-3 BOP CHECK If Containment Spray Should Be Actuated:
BOP a. CHECK the following:
BOP a. CHECK the following:
Containmen t pressure -
* Containment pressure - GREATER THAN 27 PSIG OR
GREATER THAN 27 PSIG O R    GN PR-934 indicates co ntainment pressure - HAS BEEN GRE A TER THA N 27 PSIG     O R    Annunciator 59A CSAS - LIT     O R    Annunciator 59B CISB -
* GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR
LIT     BOP b. Containmen t Spray Pu mps - BOTH RUNNING   EN HIS-3   EN HIS-9     BOP c. ESFAS stat us panels C SAS sections:
* Annunciator 59A CSAS - LIT OR
SA066 X W H ITE lights  
* Annunciator 59B CISB - LIT BOP b. Containment Spray Pumps - BOTH RUNNING
- ALL LIT SA066Y W H ITE lights  
* EN HIS-3
- ALL LIT BOP d. ESFAS stat us panels CI SB sections:
* EN HIS-9 BOP c. ESFAS status panels CSAS sections:
SA066 X W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT SA066Y W H ITE lights  
* SA066Y WHITE lights - ALL LIT BOP d. ESFAS status panels CISB sections:
- ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:
* SA066X WHITE lights - ALL LIT
* SA066Y WHITE lights - ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:
BOP a. CHECK for any of the following:
BOP a. CHECK for any of the following:
Containmen t pressure -
* Containment pressure - GREATER THAN 17 PSIG 34
GREATER THAN 17 PSIG 34 ATTAC H MENT A Automatic Action Veri fication    O R    GN PR-934 indicates co ntainment pressure - HAS BEEN GRE A TER THA N 17 PSIG     O R    Steamline pressure - LESS THAN 615 PSIG     O R    AB PR-514 or PR-535 indicates ste a mline pressure -
 
HAS BEEN LESS THAN 615 PSIG BOP b. CHECK MSI V s and Byp a ss valves - CLOSED BOP CHECK ECCS Valves -
ATTACHMENT A Automatic Action Verification OR
PROP ER E M ERGE NCY ALIGNME N T    BOP a. ESFAS stat us panels SI S sections:
* GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 17 PSIG OR
SA066 X W H ITE lights  
* Steamline pressure - LESS THAN 615 PSIG OR
- ALL LIT SA066Y W H ITE lights  
* AB PR-514 or PR-535 indicates steamline pressure -
- ALL LIT BOP CHECK Co ntainment Isolation Phase A:
HAS BEEN LESS THAN 615 PSIG BOP       b. CHECK MSIVs and Bypass valves - CLOSED BOP       CHECK ECCS Valves - PROPER EMERGENCY ALIGNMENT BOP       a. ESFAS status panels SIS sections:
BOP a. ESFAS stat us panels CI SA sections:
* SA066X WHITE lights - ALL LIT
SA066 X W H ITE lights  
* SA066Y WHITE lights - ALL LIT BOP       CHECK Containment Isolation Phase A:
- ALL LIT SA066Y W H ITE lights  
BOP       a. ESFAS status panels CISA sections:
- ALL LIT BOP CHECK SG Blowdown Isolation:
* SA066X WHITE lights - ALL LIT
BOP ESFAS stat us panels S G BSIS sections:
* SA066Y WHITE lights - ALL LIT BOP       CHECK SG Blowdown Isolation:
SA066 X W H ITE lights  
BOP       ESFAS status panels SGBSIS sections:
- ALL LIT SA066Y W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT CAUTI O N: If offsite pow er is lost after SI res e t, manual action ma y be required to restart s a feguards equipment.
* SA066Y WHITE lights - ALL LIT CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
BOP CHECK Bot h Trains of control Room Ventilation I s olation:   35 Appendix D Scenario Outline Form ES-D-1 F a c i l i t y: C a l l a w a y S c e n a r i o No.: 2 Op Test No.:
BOP       CHECK Both Trains of control Room Ventilation Isolation:
NRC E x a m i n e r s:   O p e r a t o r s:             Initial Conditi ons: 50% power, BOL. RE-5 2, Blowd o wn Disch a rg e Pumps Discha rge M onit o r, is OOS.
35
BB-PCV-455A PORV Leak a ge - Block Valve Closed.
 
Motor Driven AFW Pump 'A' OOS.
Appendix D                                     Scenario Outline                               Form ES-D-1 Facility:         Callaway                      Scenario No.:         2   Op Test No.:     NRC Examiners:                                                 Operators:
Turn over: Maintain sta b l e plant co ndi tions  Critical Ta sk: Insert n egative rea c tivity by insert in g co n t rol rod s or ini t iating emerg ency bo ration prio r to the end of step 4 o f FR-S.1. Isolate AFW t o faulted SG prio r to occurren ce of an O R ANGE con d i tion on the Integrity CSF Status Tre
Initial Conditions:   50% power, BOL.
: e. Event No. Malf. No. Event Type* E v e n t Description I - RO, SRO Pressu rizer p r essu re in stru ment fails hig h 1 T+10 PRS01A TS - SRO 2 T+25 FWM0 3B C - BOP, SRO  'B' Feedwater Control Valv e fails clo s e d in automatic I - ALL Turbi ne First Stage Pressu re Tran smitter fails low 3 T+35 PCS02B TS - SRO   4 T+50 CRF04_52 CRF04_53 M - ALL Multiple Drop ped Rod s - requires rea c t o r trip 5 CRF 13 C - ALL ATWS 6 MSS14A C - BOP Stuck o pen safety valve.  
RE-52, Blowdown Discharge Pumps Discharge Monitor, is OOS.
* (N)ormal,    (R)eactivity,    (I)nstrument,   (C)omp onent,   (M)ajor
BB-PCV-455A PORV Leakage - Block Valve Closed.
Motor Driven AFW Pump A OOS.
Turnover:             Maintain stable plant conditions Critical Task:         Insert negative reactivity by inserting control rods or initiating emergency boration prior to the end of step 4 of FR-S.1.
Isolate AFW to faulted SG prior to occurrence of an ORANGE condition on the Integrity CSF Status Tree.
Event          Malf. Event                                        Event No.         No.       Type*                                     Description 1                    I - RO,       Pressurizer pressure instrument fails high T+10       PRS01A     SRO TS - SRO 2                   C - BOP,       B Feedwater Control Valve fails closed in automatic T+25      FWM03B      SRO 3                    I - ALL       Turbine First Stage Pressure Transmitter fails low T+35       PCS02B     TS - SRO 4       CRF04_52   M - ALL       Multiple Dropped Rods - requires reactor trip T+50        CRF04_53 5                   C - ALL       ATWS CRF13 6                   C - BOP       Stuck open safety valve.
MSS14A
    *   (N)ormal,    (R)eactivity,    (I)nstrument,     (C)omponent,       (M)ajor Scenario Event Description NRC Scenario 2 The crew will assume the shift with instructions to maintain present plant conditions The controlling pressurizer pressure transmitter will fail high, requiring the crew to select an alternate pressure channel to control heaters and spray in accordance with OTO-BB-6. The SRO will also determine the appropriate technical specification action requirements.
When the plant is stable, a Feedwater Control Valve will fail closed in automatic, requiring manual operation to restore SG level.
When SG level is restored, PT-506 will fail low, requiring the RO to place Rod Control in manual to stop rod motion, the BOP to select PT-505 for control, reset C-7, and place steam dumps in the Steam Pressure mode in accordance with OTO-AC-3. The SRO will also address Technical Specifications.
Multiple control rods will drop. A reactor trip is required but an ATWS occurs. The crew must take action to initiate RCS emergency boration and de-energize rod drive MG sets. A SG safety valve will stick open, requiring the crew to isolate AFW flow to the SG and attempt isolation.
The scenario may be terminated when the crew transitions to ES-1.1, SI Termination.
EOP Flow Path: E-0, FR-S.1, E-0, E-2, ES-1.1 Scenario 2 Scenario Malfunction List
: 1)  Initialize at IC-17, 50%.
: 2)  Run Batch File ilttwo.txt and verify the actions on the following page are loaded correctly.
: 3)  Ensure immediate boration timer is reset.
: 4)  Ensure BB PT-455 is selected as the controlling pressure channel.
: 5)  Ensure First Stage Pressure Transmitter PT-506 is selected for control
: 6)  Ensure NIS indicates 50% power.
: 7)  Check Rx Trip switch has a red flag.
: 8)  Ensure step counters for Control Bank "D" are set at 150 steps and all other step counters are set at 228 steps.
: 9)  Ensure the digital display is selected to REP0480A and RET0499A.
: 10) Place 'A' MDAFP in PTL and hand a Hold Off tag on handswitch ALHIS23A.
: 11) Ensure Decrease Loading Rate Button is "ON".
: 12) Update the status board for "B" train week.
: 13) Update Status Board - 'A' MDAFP, TS 3.7.5, Condition C, 72 hrs. Current outage time is 16 hours.
: 14) Ensure Letdown orifi A and B are in service, and a caution tag placed on C
: 15) Ensure AEHV38 is appropriately throttled
: 16) White board has the following boron concentrations:
    *    "A" CCP 5 days ago 1105 ppm
    *    "B" CCP 15 days ago 1132 ppm
* RCS boron = 1090
* PZR boron = 1093
: 17) Ensure chart recorders are "rolled forward".
: 18) Microphones are available for each person being evaluated and a videotape is in the VCR.
: 19) Ensure the RM-11 is on the training system.
: 20) Ensure turnover sheets and log sheets are on the desks.
: 21) Ensure copies of the following procedures are in the file drawers:
* OTO-BB-00006
* OTO-AE-00001
* OTO-AC-00003
* E-0
* FR-S.1
* E-2
* ES-1.1 Scenario 2 Scenario Malfunction List File:                ilttwo.TXT
>Author: S. P. Aufdemberge
>Date:                20050504
>=============SCENARIO SETUP ITEMS===========================================
>Remove 'A' MDAFP from service
>FILE AL01A.TXT
>Simulates tag out of the MD AFP A in the Pull-to-lock position bat al01a.txt
>Simulates de-energization of "A" PORV Block valve due to PORV Leakage ior bbhis8000a_ic (-1 0) 0 irf bbs014 (-1 0) 0
>===========================================================================
>=============EVENT PRELOAD=================================================
>EVENT 1
>Pressurizer Pressure Channel BBPT0455 fails to 2500 over 60 seconds
>Manually Input Event 1 imf prs01a (1 0) 2500 60
>===========================================================================
>=============EVENT PRELOAD=================================================
>EVENT 2
>"B" Feed Reg Valve fails closed in Automatic over 90 seconds
>Manually Input Event 2 imf fwm03b (2 0) 0 90
>===========================================================================
>=============EVENT PRELOAD=================================================
>EVENT 3
>ACPT0506 fails low over 60 second ramp
>Manually Input Event 3 imf pcs02b (3 0) 0 60
>===========================================================================
>=============EVENT PRELOAD=================================================
> EVENT 4
>Multiple Dropped Rods
>Manually Input Event 4 imf crf04_52 (4) imf crf04_53 (4)
>===========================================================================
>=============EVENT PRELOAD=================================================
>EVENT 5
>PROTECTIVE SYSTEM FAILURE (ATWS) Preloaded into scenario. No Manual Input >required imf crf13 (-1 0) both
>===========================================================================
>=============EVENT PRELOAD=================================================
>EVENT 6
>Main Steam Safety Valve Fails 100% Open, with a 10 sec delay, and a 1 sec >ramp from trigger #6 (CONDITIONAL) trgset 6 "sac.le.10" imf mss14a (6 10) 100 1
>===========================================================================
>end of file Scenario 2 Crew Turnover Separate Turnover Sheets provided Appendix D                                Operator Action                            Form ES-D-2 Op Test No.:        1    Scenario #      2      Event #      1                Page 6  of 28 Event
 
== Description:==
Pressurizer Pressure Instrument Failure Time          Position                          Applicants Actions or Behavior Booth Operator Instructions:
When directed, insert command for PT-455 failure HIGH Indications Available:
PRESSURIZER HIGH PRESSURE DEVIATION Annunciator 33B PRESSURIZER PRESSURE LOW HEATERS ON Annunciator 33C REACTOR PARTIAL TRIP Annunciator 83C PT-455 indicates high Refer to OTO-BB-0006, Pressurizer Pressure Control System SRO Instrument Failures RO      Select an alternate channel (457/456)
RO      Check PZR pressure 2200 - 2250 psig RO      Check P-11 correct state (Not Lit)
BOP      Select recorder to valid channel SRO      Direct I&C to trip the affected bistables SRO      Refer to Tech Specs
* 3.3.1, Condition E, M
* 3.3.2 Condition D, L
* 3.3.4 Item 3
* 3.4.1 (DNB)
After Technical Specifications have been addressed, proceed to Event 2


Scenario Event Description NRC Scena rio 2  The crew will assume th e shift with i n struction s t o maintain present plant conditions The controlli ng pressurizer pressure transmitter will fail h i gh, requiring th e crew to se lect an alternate pr essure chan nel to contro l heaters an d spray in accordance with OTO-BB-6. The SRO will also determine the appropri a te technica l specif icatio n action req u irements.
Appendix D                              Operator Action                            Form ES-D-2 Op Test No.:       1     Scenario #    2      Event #        2               Page 7  of 28 Event
When the pl ant is stab le , a Feedwater Control Valve will fail closed in au tomatic, requiring manual operation to rest ore SG level
. When SG level is restor ed, PT-506 will fail l o w, requiring the RO to place Rod Control in manual to stop rod motion, the BOP to select PT-505 for control, reset C-7, and place steam dumps in the Steam Pressure mode in accorda n ce with OTO-AC-3. Th e SRO will a l so address Technical Specificatio ns. Multiple con t rol rods will drop. A reactor trip is re quired but a n ATWS occurs. The cr ew must take action t o initiate RCS emergency boration and de-energize rod drive MG sets. A SG safety valve will stick open, req u iring the cr ew to isolate AFW flow to the SG and attempt isolation.
The scenario may be terminated when the crew transitions t o ES-1.1, SI Termination.
EOP Flow Path: E-0, FR-S.1, E-0, E-2, ES-1.1


Scenario 2 Scenario Malfunction L i st  1) Initializ e at IC-17, 50%.
== Description:==
: 2) Run Batch F i l e iltt w o.t x t and v e rif y th e action s on the foll o w i ng pa ge ar e lo ade d correctl
B Feedwater Control Valve fails closed in automatic Time          Position                          Applicants Actions or Behavior Booth Operator Instructions:
: y. 3) Ensure imm edi ate borati on ti mer is reset.
When directed, insert command for Feedwater Control Valve failure Indications Available:
: 4) Ensure BB PT
B FRV failing closed Feedwater flow to B SG Lowering STEAM GENERATOR B FLOW MISMATCH Annunciator 109D BOP        Determines SG B level is lowering.
-455 is se lecte d as the controll i ng press u re ch ann el. 5) Ensure F i rst Stage Press u re T r ansmitter PT
Place AE-FK-520, SG B MFW Reg Valve Control, in BOP MANUAL, and restore SG level.
-506 is se lecte d for control
SRO        Refer to OTO-AE-0001, Feedwater System Malfunctions.
: 6) Ensure NIS indicates 50% pow e r. 7) Check R x T r ip s w itc h has a re d flag. 8) Ensure step c o unters for Cont rol Bank "D" ar e set at 150 steps an d al l oth e r step count er s are set at 228 steps.
RO        Place Rod Control in AUTO BOP        Check Main Feed Pump tripped (NO)
: 9) Ensure the dig i tal disp la y is se lected to REP 0 480A a nd RET 049 9A. 10) Place 'A' MDAFP in P T L and hand a Hold Off tag on hands w i tc h ALHIS23A.
BOP        Check Main Feed Pump Speed controlling in auto and stable Check Main Feed Reg Valves controlling in Auto (NO)
: 11) Ensure D e crea se Loa di ng Rat e Button is "ON".
BOP
: 12) Upd a te the status boar d for "B" train w e ek. 13) Upd a te Status Board - '
* Ensure Manual control
A' MDAF P, T S 3.7.5, Cond ition C, 7 2 hrs. Current outag e time is 16 ho urs. 14) Ensure L e tdo w n orifi A and B are in serv ice, and a ca utio n tag pl ace d on C 15) Ensure AEHV 3 8 is appr opri a tel y t h rottled 16) W h ite boar d ha s the follo w i ng boro n conc entr a tions:    "A" CCP 5 d a y s ago 11 05 p p m "B" CCP 15 da ys a go 11 32 p p m RCS bor on = 1090 PZ R boron = 1 093 17) Ensure ch art record ers are "r olle d for w ar d". 18) Microph on es a r e avai lab l e for each pers on b e in g eval uate d and a vi de otap e is in the VCR
* Check Main Feed Reg Bypass Valves in service (NO)
. 19) Ensure the RM
BOP
-11 is on the tr aini ng s y stem. 20) Ensure turn ove r sheets and l o g sheets are o n the desks.
* Check Condensate Pump operation
: 21) Ensure co pi es of the follo w i n g pr oced ures ar e in the file dra w e r s:  OT O-BB-0000 6  OT O-AE-0000 1  OT O-AC-0000 3  E-0  FR-S.1  E-2  ES-1.1 Scenario 2 Scenario Malfunction L i st  F ile:  ilttw o.T X T >Author: S. P. Aufdember ge >Date:  20050504 > > >=========
* Check Heater Drain Pump operation BOP        Verify SG NR level trend 45 - 55% and maintain RO        Monitor or operate rod control to maintain Tave/Tref +/- 5 °F
====SCENARIO SE TUP ITEMS====
==========
=============
=============
=== >Remove 'A' M D AFP from service
>FILE  AL01A.T XT  >Simulates tag out of the MD A F P A in the Pull-to-lock position bat al01a.txt
>Simulates de-energization of "A" PO RV Block valve due to PORV Leakage ior bbhis8000a_ic (-1 0) 0 irf bbs014 (-
1 0) 0 >=========
=============
=============
=============
=============
=============
= >=========
====EVENT PRELOAD==========
==========
=============
=============
=== >EVENT 1 >Pressurizer Pre ssure Channel B BPT0455 fails to 2500 over 60 sec onds >Manually Input Event 1 imf prs01a (1 0
) 2500 60 >=========
=============
=============
=============
=============
=============
= >=========
====EVENT PRELOAD==========
==========
=============
=============
=== >EVENT 2 >"B" Feed Reg V a lve fails closed in Automatic over 90 seconds
>Manually Input Event 2 imf fw m03 b (2 0) 0 90 >=========
=============
=============
=============
=============
=============
= >=========
====EVENT PRELOAD==========
==========
=============
=============
=== >EVENT 3 >ACPT0506 fails low ove r 60 second ramp
>Manually Input Event 3 imf pcs02b (3 0) 0 60 >=========
=============
=============
=============
=============
=============
= >=========
====EVENT PRELOAD==========
==========
=============
=============
=== > EVENT 4
>Multiple Droppe d Rods >Manually Input Event 4 imf crf04_52 (4) imf crf04_53 (4) >=========
=============
=============
=============
=============
=============
= >=========
====EVENT PRELOAD==========
==========
=============
=============
=== >EVENT 5 >PROTEC T IVE S Y STEM FAILU R E (ATWS) P r eloaded into scena rio. No Manual I nput >require d imf crf13 (-1 0
) b o th >=========
=============
=============
=============
=============
=============
= >=========
====EVENT PRELOAD==========
==========
=============
=============
=== >EVENT 6 >Main Steam Safet y Valve Fails 100%
Open, w i th a 10 sec dela y , a nd a 1 sec >ram p from trigge r #6 (CONDITI ONA L) trgset 6 "sac.le.1 0" imf mss14a (6 10) 100 1 >=========
=============
=============
=============
=============
=============
= >end of file


Scenario 2 Crew Turno ver    Separate Turnover Shee ts provided
Appendix D                              Operator Action                            Form ES-D-2 Op Test No.:        1    Scenario #    2      Event #        2               Page 8  of 28 Event


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 1 Page 6 of 28           Event Descri p ti on: Pressuriz e r Pressure Instrum ent Failur e  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
== Description:==
When directed, insert command for PT-455 failure HIGH Indications Available:
B Feedwater Control Valve fails closed in automatic Time          Position                          Applicants Actions or Behavior BOP        Check MFP Oil Pressure normal SRO        Perform communications per Ops Communications-01 SRO        Verify Power change less than 15% in 1 hour When the plant is stable, proceed to Event 3
PRESSURI ZER HI GH PRESSURE DEVIATI O N Annunciator 33B PRESSURI ZER PRESSURE L O W HEATERS ON Annunc iator 33C REACT OR PARTIAL T R IP Annun ciator 83C PT-455 indicates high SRO Refer to OT O-BB-0006, Pressurizer Pressure Control System Instrument Failures RO Select an alt e rnate chan nel (457/456)    RO Check PZR pressure 22 00 - 2250 p s ig    RO Check P-11 correct state (Not Lit)
 
BOP Select recor der to valid channel SRO Direct I&C to trip the aff e cted bistab les    SRO Refer to Tech Specs 3.3.1, Condition E, M  3.3.2 Condition D, L  3.3.4 Item 3  3.4.1 (DNB)    After Techn ical Specifications have been addressed, proceed to Event 2
Appendix D                                 Operator Action                           Form ES-D-2 Op Test No.:       1     Scenario #       2     Event #       3                Page 9  of 28 Event


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 2 Page 7 of 28          Event Descri p ti on: "B" F eed w a ter Contro l Valve f a ils clos ed i n a u tomatic  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
== Description:==
When directed, insert command for Feedw at er Control Valve failure Indications Available:  
Turbine First Stage Pressure Transmitter Fails Low Time          Position                          Applicants Actions or Behavior Booth Operator Instructions:
'B' FRV faili ng closed Feed w a ter flow to "B" SG Low ering STEAM GENERAT OR B FLOW MI SMAT CH Annunciator 109D BOP Determines SG "B" level is lowering.
When directed, insert command for First Stage Pressure Channel PT-506 failing low Indications Available:
BOP Place AE-FK-520, SG "B" MFW Re g Valve Con t rol, in MANUAL, a nd restore SG level.
PT-506 indication failing low Control Rods stepping in if in auto Rx Deviation alarm Refer to OTO-AC-00003, Turbine Impulse Pressure Channel SRO Failure RO       Place Rod Control in MANUAL Identify the failed channel by comparing meter indications and BOP identifying alarmed annunciators. (PT-506)
SRO Refer to OT O-AE-0001, Feedwater System Malfunctions.
Select the alternate impulse pressure channel by utilizing the BOP Impulse Pressure selector switch AC PS-505Z.
RO Place Rod Control in AUTO BOP Check Main Feed Pump tripped (NO)
RO      Check Tave within 1.5°F of Tref (When restored, then maintain)
BOP Check Main Feed Pump Speed controlling in au t o and stable BOP Check Main Feed Reg Valves contro lling in Auto (NO) Ensure Manual control BOP  Check Main Feed Reg Bypass Valves in service (NO)  Check Condensate Pump operation  Check Heater Drain Pump operation BOP Verify SG NR level trend 45 - 55%
Check Rod Control in AUTO RO
and maintain RO Monitor or operate rod control to maintain Tave/Tref +/- 5 °F
* Will place in AUTO if directed by SRO and Tave and Tref are matched Maintain Tavg at the corresponding Tref value for existing plant RO power. Ensure RX power is less than 3565 MWth.
Place the Steam Dump Interlock Selector switches (AB-HS-64 BOP and AB-HS-63) to the OFF/RESET position.


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 2 Page 8 of 28           Event Descri p ti on: "B" F eed w a ter Contro l Valve f a ils clos ed i n a u tomatic  T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP Check MFP Oil Pressure normal SRO Perform communications per Ops Communications-01 SRO Verify Powe r change less than 15% in 1 hour When the plant is stable, proceed to Event 3
Appendix D                                 Operator Action                           Form ES-D-2 Op Test No.:       1     Scenario #       2     Event #       3                Page 10  of 28 Event


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 3 Page 9 of 28          Event Descri p ti on: T u rbine F i rst Stage Pressur e T r ansmitter F a i l s Lo w  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
== Description:==
When directed, insert command for First Sta ge Pressure Channel PT-506 failing low  Indications Available:
Turbine First Stage Pressure Transmitter Fails Low Time          Position                          Applicants Actions or Behavior BOP      Check C-7, Load Loss Stm Dump Armed - Extinguished Transfer Steam Dumps to the Steam Pressure Mode:
PT-506 indication failing lo w Control Ro ds stepping in if in au to Rx Deviation alarm SRO Refer to OT O-AC-0000 3, Turbine I m pulse Pressure Channel Failure    RO Place Rod Control in MANUAL BOP Identify the failed chann el by comparing meter indications an d identifying alarmed annunciators. (P T-506)     BOP Select the al ternate impulse pressure channel by utilizing the Impulse Pressure sele ct or switch A C PS-505Z. RO Check Tave within 1.5°F of Tref (When restored, then maintain)
* Set the AB PK-507, Steam Header Pressure controller BOP for 7.28 turns (1092 psig)
RO Check Rod Control in AUTO  Will pla c e in AUTO if directed by SRO and Tave and Tref are matched RO Maintain Tavg at the corresponding Tref value for existing plant power. Ensure RX power is less th an 3565 MWth.
* Place the Steam Dump Select to STEAM PRESS BOP       Place the Steam Dump Bypass Interlock switches to ON Check the following permissives are in their correct state within 1 hour of the channel failure per Attachment B, permissives:
BOP Place the Steam Du mp Interlock Selector switch es (AB-HS-64 and AB-HS-
CREW
: 63) to the OFF/RESET position.
* P-7 (LIT)
* P-13 (LIT)
Direct an RO to Place SW12 for PT-506 at AMSAC SRO      Test/Bypass Panel and place SW11, Bypass toggle switch, to the right hand position Refer to T/S LCO 3.3.1 (Improved T/S LCO 3.3.1) to ensure SRO      compliance with the requirements for minimum channels.
* Condition T RO       Restore Rod Control to Manual if directed Note:
10 minutes after the failure, ATWS System Trouble Alarm, 83F, will annunciate.
(No consequence)
When Tech Specs have been addressed, proceed to Event 4


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 3 Page 10 of 28          Event Descri p ti on: T u rbine F i rst Stage Pressur e T r ansmitter F a i l s Lo w  T i me Positio n Appl icant's Acti ons or Beh a vi o r  BOP Check C-7, Load Loss S t m Du mp Armed - Extin guished    BOP Transfer Steam Du mps to the Steam Pressure Mode: Set the AB PK-507, Ste a m Header Pressure co ntroller for 7.28 turns (1092 psig)  Place the Steam Du mp Select to STEAM P R ES S    BOP Place the Steam Du mp Bypass Interlock swit che s to ON    CREW Check the f o llowing per missives are in their corr ect state wit h in 1 hour of th e channel fa ilure per Att a chment B, permissives:  P-7 (LIT)  P-13 (LIT)    SRO Direct an RO to Place SW12 for PT-506 at AMSAC Test/Bypass Panel and place SW11 , Bypass toggle switch, t o the right han d position SRO Refer to T/S LCO 3.3.1 (Improved T/
Appendix D                                 Operator Action                             Form ES-D-2 Op Test No.:       1     Scenario #     2       Event #     4,5,6            Page 11  of  28 Event
S LCO 3.3.1
) to ensure compliance with the requirements for minimum c hannels. Condition T    RO Restore Rod Control to Manual if directed Not e: 10 minutes a fter the failure, ATWS Sy s t em Trouble Alarm, 83F, w i ll a nnun ciate.  (No c onse q u e nce)    When Tech Specs have been addressed, proceed to Event 4


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 11 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Instructor Instructions:
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior Booth Instructor Instructions:
When directed, insert commands to initiate remainder of events as sequenced Indications Available:
When directed, insert commands to initiate remainder of events as sequenced Indications Available:
Tw o dropped control rods Rod Botto m lights Multiple annunciators CREW Recognizes more than one control ro d dropped.
Two dropped control rods Rod Bottom lights Multiple annunciators CREW       Recognizes more than one control rod dropped.
SRO Directs reactor trip.
SRO       Directs reactor trip.
RO Attempts to trip reactor.
RO       Attempts to trip reactor. Reactor will not trip.
Reactor will not trip.
SRO       Directs entry to FR-S.1 RO       CHECK Reactor Trip:
SRO Directs entr y to FR-S.1 RO CHEC K Re actor Trip:
* Rod Bottom Lights - ALL LIT (NO)
Rod Bottom Lights - ALL LIT (NO)
* Reactor Trip and Bypass Breakers -OPEN (NO)
Reactor Trip and Bypass Breakers -
* Neutron Flux - LOWERING (Possible, if Control Rod insertion is in progress))
O PEN (NO)   Neutron Flux - LOWERI NG (Possible, if Control Rod insertion is in progress))
Manually TRIP Reactor:
Manually T R IP Reactor:
* SB HS-1
SB HS-1   SB-HS-42 (B OP)     IF reactor will NOT trip, THEN PERFORM the following:
* SB-HS-42 (BOP)
CRITIC A L TA S K RO a. Manuall y I N SERT control rods w h e n AUTO slo w s  belo w 48 SPM, or inse rt manuall y continuousl
IF reactor will NOT trip, THEN PERFORM the following:
: y.
CRITICAL                    a. Manually INSERT control rods when AUTO slows TASK              RO below 48 SPM, or insert manually continuously.
Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 12 of 28           Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP b. OPEN supply breakers to PG19 and PG20:
 
PG HIS-16   PG HIS-18       WHEN react o r is tripped, THEN CL OSE supply breakers to PG19 and PG20.
Appendix D                                   Operator Action                                Form ES-D-2 Op Test No.:       1     Scenario #       2     Event #     4,5,6           Page   12     of 28 Event
BOP CHECK Turbine trip:
 
All Turbine Stop valves  
== Description:==
- CLOSED     BOP CHECK AF W Pumps Running:
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior BOP       b. OPEN supply breakers to PG19 and PG20:
: a. MD AFW Pumps - BOT H RUNNING (Must start "B" MDAFW Pu mp)   AL HIS-23A   AL HIS-22A     b. TD AFW Pu mp - RUNNING IF NE CESSA RY  (May need t o start)   CRITIC A L TA S K RO INITIATE Emergenc y Boration of RCS:
* PG HIS-16
Note:   If SI is actuated, HHSI w i ll b e pro v iding b o ration fl o w v i a the RWST
* PG HIS-18 WHEN reactor is tripped, THEN CLOSE supply breakers to PG19 and PG20.
: a. CHECK charging pumps - AT LEAST ONE RUNNING   CCP(s):   BG HIS-1 A    BG HIS-2 A    O R Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 13 of 28           Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r    NCP:   BG HIS-3     RO b. ALIGN e m ergency boration flow path:
BOP       CHECK Turbine trip:
: 1. START Bori c Acid Transfer Pumps:
All Turbine Stop valves - CLOSED BOP       CHECK AFW Pumps Running:
BG HIS-5 A    BG HIS-6 A      2. OPEN Emergency Borate to Charging Pump Suc t ion valve:   BG HIS-810 4      3. CHECK Emergency Boration Flow -
: a. MD AFW Pumps - BOTH RUNNING (Must start B MDAFW Pump)
GREAT ER THAN 30 GPM BG FI-183A       4. MAINT A IN charging flow - GREAT ER THAN EME R GENCY BORATI ON FLOW     c. CHECK PZ R Pressure - LESS THAN 2335 PSIG CREW CHECK Co ntainment Purge Isolatio n:     a. ESFAS stat us panels C P IS sections:
* AL HIS-23A
SA066 X W H ITE lights  
* AL HIS-22A
- ALL LIT SA066Y W H ITE lights  
: b. TD AFW Pump - RUNNING IF NECESSARY (May need to start)
- ALL LIT RO CHECK If the Following Trips Have Occurred:  
CRITICAL TASK              RO       INITIATE Emergency Boration of RCS:
Note:
If SI is actuated, HHSI will be providing boration flow via the RWST
: a. CHECK charging pumps - AT LEAST ONE RUNNING
* CCP(s):
* BG HIS-1A
* BG HIS-2A OR
 
Appendix D                                 Operator Action                            Form ES-D-2 Op Test No.:       1     Scenario #     2       Event #     4,5,6           Page 13   of 28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
* NCP:
* BG HIS-3 RO       b. ALIGN emergency boration flow path:
: 1. START Boric Acid Transfer Pumps:
* BG HIS-5A
* BG HIS-6A
: 2. OPEN Emergency Borate to Charging Pump Suction valve:
* BG HIS-8104
: 3. CHECK Emergency Boration Flow - GREATER THAN 30 GPM
* BG FI-183A
: 4. MAINTAIN charging flow - GREATER THAN EMERGENCY BORATION FLOW
: c. CHECK PZR Pressure - LESS THAN 2335 PSIG CREW       CHECK Containment Purge Isolation:
: a. ESFAS status panels CPIS sections:
* SA066X WHITE lights - ALL LIT
* SA066Y WHITE lights - ALL LIT RO       CHECK If the Following Trips Have Occurred:
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:        1    Scenario #      2      Event #      4,5,6            Page 14  of  28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
: a. Reactor trip:
* Rod Bottom Lights - ALL LIT (YES)
* Reactor Trip and Bypass Breakers - OPEN (NO)
* Neutron Flux - LOWERING (YES)
BOP      b. Turbine trip:
* All Turbine Stop Valves - CLOSED RO      CHECK If Reactor Is Subcritical:
: a. Power Range channels - LESS THAN 5% (POST ACCIDENT PR - LESS THAN 5%)
: b. Intermediate Range channels - NEGATIVE STARTUP RATE (POST ACCIDENT PR - STABLE OR LOWERING)
Go to Step 16. OBSERVE CAUTION prior to Step 16.
SRO Directs entry to E-0.
RO      CHECK Reactor Trip:
* Rod Bottom Lights - ALL LIT (YES)
* Reactor Trip and Bypass Breakers - OPEN (NO) o    Dispatch AO to Open RTBs
* Neutron Flux - LOWERING (YES)
BOP      CHECK Turbine Trip:
: a. All turbine Stop Valves - CLOSED BOP      CHECK Power to AC Emergency Buses:
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 15  of  28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
: a. AC emergency buses - AT LEAST ONE ENERGIZED
* NB01 OR
* NB02
: b. AC emergency buses - BOTH ENERGIZED CREW        CHECK SI Status:
: a. CHECK if SI is actuated:
* Any SI annunciator 88A through 88D - LIT OR
* SB069 SI Actuate RED light - LIT OR
* LOCA Sequencer annunciators 30A or 31A - LIT
: b. CHECK both Trains of SI - ACTUATED
* LOCA Sequencer annunciator 30A - LIT
* LOCA Sequencer annunciator 31A - LIT
* SB069 SI Actuate RED light - LIT SOLID (NOT blinking)
PERFORM Attachment A, Automatic Action Verification, while BOP continuing with this procedure.
BOP      CHECK Generator Output Breakers - OPEN
* MA ZL-3A (V55)
* MA ZL-4A (V53)
BOP      CHECK Feedwater Isolation:
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 16  of  28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior BOP      a. Main Feedwater Pumps - TRIPPED
* Annunciator 120A, MFP A Trip - LIT
* Annunciator 123A, MFP B Trip - LIT BOP      b. Main Feedwater Reg Valves - CLOSED
* AE ZL-510 (SG A)
* AE ZL-520 (SG B)
* AE ZL-530 (SG C)
* AE ZL-540 (SG D)
BOP      c. Main Feedwater Reg Bypass Valves - CLOSED
* AE ZL-550 (SG A)
* AE ZL-560 (SG B)
* AE ZL-570 (SG C)
* AE ZL-580 (SG D)
BOP      d. Feedwater Isolation Valves - CLOSED
* AE HIS-39 (SG A)
* AE HIS-40 (SG B)
* AE HIS-41 (SG C)
* AE HIS-42 (SG D)
BOP      CHECK AFW Pumps:
: a. MD AFW Pumps - BOTH RUNNING (B MDAFW Pump is running. A MDAFW Pump is OFF)
* AL HIS-23A
* AL HIS-22A
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 17  of  28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
: b. TD AFW Pump - RUNNING IF NECESSARY BOP      CHECK AFW Valves - PROPER EMERGENCY ALIGNMENT
* MD AFP Flow Control Valves - THROTTLED
* AL HK-7A
* AL HK-9A
* AL HK-11A
* AL HK-5A
* TD AFP Flow Control Valves - FULL OPEN (May isolate to BOP faulted SG)
* AL HK-8A
* AL HK-10A
* AL HK-12A
* AL HK-6A BOP      CHECK total AFW Flow - GREATER THAN 300,000 LBM/HR RO        CHECK PZR PORVs and Spray Valves:
RO        a.        PZR PORVs - CLOSED
* BB HIS-455A
* BB HIS-456A RO        b.        PZR PORVs - BOTH IN AUTO
* BB HIS-455A
* BB HIS-456A RO        c. PORV Block Valves - BOTH OPEN (NO)
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 18  of  28 Event


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 14 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r    a. R e a c t o r trip:    Rod Bottom Lights - ALL LIT (YES)
== Description:==
Reactor Trip and Bypass Breakers -
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
OPEN (NO)
* BB HIS-8000A (CLOSED)
Neutron Flux - LOWERI NG (YES)    B O P b. T u r b i n e trip:    All Turbine Stop Valves - CLOSED RO CHECK If Reactor Is Su bcritica l:     a. Power Rang e channels
* BB HIS-8000B RO        d. Normal PZR Spray Valves - CLOSED
- LESS THAN 5% (POST ACCIDENT PR - LESS THAN 5%)      b. Intermediate Range channels - NEGATIVE ST ARTUP RATE (POST ACCIDENT PR - STABLE OR L O WERING)     SRO  Go to Step 16. OBSERVE CAUTION prior to Step 16.
* BB ZL-455B
Directs entr y to E-0. RO CHEC K Re actor Trip:
* BB ZL-455C NOTE:        Seal injection flow should be maintained to all RCPs.
Rod Bottom Lights - ALL LIT (YES)
RO       CHECK If RCPs Should Be Stopped:
Reactor Trip and Bypass Breakers -
RO        a. RCPs - ANY RUNNING RO        b. ECCS Pumps - AT LEAST ONE RUNNING
OPEN (NO) o Dispatch A O to Open RTBs    Neutron Flux - LOWERI NG (YES)    BOP CHECK Turbine Trip:
* CCP OR
: a. All turbine S t op Valves - CLOSED BOP CHECK Po wer to AC Emergency Buses:  
* SI Pump RO        c. RCS pressure - LESS THAN 1425 PSIG (NO)
CREW        CHECK RCS Temperatures:
* Any RCP running - RCS TAVG STABLE AT 557°F OR TRENDING TO 557°F (NO)
If TEMPERATURE IS LESS THAN 557°F and LOWERING, then perform THE FOLLOWING:
BOP       a. STOP dumping steam.
: b. IF cooldown continues, THEN CONTROL total feed flow:


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 15 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r    a. AC emerge ncy buses - AT LEAST ONE E N E R GIZED    NB01    O R    NB02      b. AC emerge ncy buses -
Appendix D                                 Operator Action                            Form ES-D-2 Op Test No.:       1     Scenario #     2       Event #      4,5,6           Page 19   of  28 Event
BOTH ENERGIZED C R E W CHEC K S I S t a t u s:     a. CHECK if SI is actuated:
Any SI annu nciator 88A through 88D - LIT O R    SB069 SI Actuate RED light - LIT O R    LOCA Sequ encer annun ciators 30A or 31A - LIT
: b. CHECK bot h Trains of SI - ACTUATED LOCA Sequ encer annun ciator 30A -
LIT    LOCA Sequ encer annun ciator 31A -
LIT    SB069 SI Actuate RED light - LIT S O LID  (NOT blinking)
BOP PERF O RM Attachment A, Automati c Action Ver i fication, while continuing w i th this pro c edure. BOP CHECK Ge nerator Output Breakers - OPEN MA ZL-3A (V55)
MA ZL-4A (V53)
BOP CHECK Fee dwater Isola t ion:
Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 16 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve   T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP a. Main Feedwater Pumps - TRIPPED Annunciator 120A, MFP A Trip - LIT Annunciator 123A, MFP B Trip - LIT BOP b. Main Feedwater Reg Valves - CLOSED AE ZL-510 (SG A)
AE ZL-520 (SG B)
AE ZL-530 (SG C)
AE ZL-540 (SG D)
BOP c. Main Feedwater Reg Bypass Valves - CLOSED AE ZL-550 (SG A)
AE ZL-560 (SG B)
AE ZL-570 (SG C)
AE ZL-580 (SG D)
BOP d. Feedwater Isolation Valves - CLOSED AE HIS-39 (S G A)    AE HIS-40 (S G B)    AE HIS-41 (S G C)    AE HIS-42 (S G D)    BOP CHECK AF W Pumps:      a. MD AFW Pumps - BOT H RUNNING  (B MDAFW Pump is running. A MDAFW Pump is OFF)    AL HIS-23A    AL HIS-22A Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 17 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r      b. TD AFW Pu mp - RUNNING IF NE CESSA RY    BOP CHECK AF W Valves - PROPER E M ERGE NCY ALIGNME N T    MD AF P Flow Control Valves - THROTTLED AL HK-7A    AL HK-9A    AL HK-11A    AL HK-5A  BOP TD AFP Flow Control Valves - FULL OPEN (May isolate to faulted SG)
AL HK-8A    AL HK-10A    AL HK-12A    AL HK-6A    BOP CHECK total AFW Flow - GREAT ER THAN 30 0,000 LBM/
HR    RO CHECK PZ R PORVs and Spray Va lves:    RO a. PZR PORV s - CLOSED BB HIS-455 A    BB HIS-456 A    RO b. PZR PORV s - BOTH I N AUT O    BB HIS-455 A    BB HIS-456 A    RO c. PORV Block Valves - BOTH OPEN (NO)
Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 18 of 28           Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r    BB HIS-800 0A (CLOSED)
BB HIS-800 0B    RO d. Normal PZR Spray Valves - CLOSE D    BB ZL-455B    BB ZL-455C    NOTE: Seal injection flo w sho uld be maintained to all RCPs.
RO CHECK If RCPs Should Be Stopped:
RO a. RCPs - AN Y RUN NIN G    RO b. ECCS Pumps - AT LEAST ON E R UNNI NG    CCP    O R    SI Pump    RO c. RCS pressure - LESS T H AN 1425 PSIG (NO)
CREW CHECK RCS Temperat ures:    Any RCP ru nning - RCS TAVG ST ABLE AT 55 7°F OR TRENDI NG TO 557°F (NO)
If TEMPERATURE IS L ESS THAN 557°F and LOWERI NG, then perform THE F O L L OWING:    BOP a. STOP du mp ing steam.
: b. IF cooldown continues, THEN CONTROL total feed flow:


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 19 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r    MAINT A IN t o tal feed flo w greater than 300,000 LBM/HR until narrow range level is g r eater than 7%
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
* MAINTAIN total feed flow greater than 300,000 LBM/HR until narrow range level is greater than 7%
[25%] in at least one SG.
[25%] in at least one SG.
BOP c. IF cooldown continues, THEN FAST CLOSE all MSIVs and Bypass valves: (May ha ve been performed)
: c. IF cooldown continues, THEN FAST CLOSE all MSIVs and BOP Bypass valves: (May have been performed)
AB HS-79   AB HS-80     BOP CHECK If Any SG Is Fa ulted:     a. CHECK pressures in all SGs:   ANY S G PRESSURE L O WERI NG I N AN UNC ONT R OLLED MA NNER ("A" SG)   O R    ANY S G COMPLETEL Y DEPRESS URIZED    SRO b. Go To E-2, Faulted Steam Generat or Isolation, Step 1. CAUTI O NS: At least one SG must be maintained available for RCS c ooldow n. An y faulted SG or seco ndary brea k should remain isolated during subsequent recovery actions unless needed for RCS co oldo w n. BOP CHECK MSI V s and Byp a ss Valves -
* AB HS-79
CLOSED     BOP CHECK If Any SG Secondary Pressure Boundary Is Intact:
* AB HS-80 BOP       CHECK If Any SG Is Faulted:
: a. CHECK pre ssures in all SGs - ANY STABLE OR RISING BOP IDENTIFY F aulted SG(s):  
: a. CHECK pressures in all SGs:
* ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER (A SG)
OR
* ANY SG COMPLETELY DEPRESSURIZED SRO       b. Go To E-2, Faulted Steam Generator Isolation, Step 1.
CAUTIONS:         At least one SG must be maintained available for RCS cooldown.
Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
BOP       CHECK MSIVs and Bypass Valves - CLOSED BOP       CHECK If Any SG Secondary Pressure Boundary Is Intact:
: a. CHECK pressures in all SGs - ANY STABLE OR RISING BOP       IDENTIFY Faulted SG(s):
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 20  of  28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior BOP      a. CHECK pressures in all SGs:
* ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER (A)
OR
* ANY SG COMPLETELY DEPRESSURIZED BOP      ISOLATE Faulted SG(s):
CRITICAL TASK              BOP      a. ISOLATE AFW flow to faulted SG(s):
* CLOSE associated MD AFP Flow Control Valve(s):
* AL HK-7A (SG A)
* CLOSE associated TD AFP Flow Control Valve(s):
* AL HK-8A (SG A)
BOP      b. CHECK ASD from faulted SG(s) - CLOSED
* AB PIC-1A (SG A)
: c. Locally CLOSE TDAFP Steam Supply From Main steam Loop Manual Isolation valve from faulted SG(s):
* ABV0085 (SG B)
* ABV0087 (SB C)
: d. CHECK Main Feedwater valves to faulted SG(s) -
BOP CLOSED
* Main Feedwater Reg Valves:
* AE ZL-510 (SG A)
* Main Feedwater Reg Valves:
* AE ZL-550 (SG A)
* Feedwater Isolation Valve:
* AE HIS-39 (SG A)
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 21  of  28 Event
 
== Description:==
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior
: e. CHECK SG Blowdown containment Isolation Valve from BOP faulted SG(s) - CLOSED
* BM HIS-1A (SG A)
: f. CLOSE Steamline Low Point Drain valve from faulted BOP SG(s):
* AB HIS-9 (SG A)
CHECK CST To AFP Suction Header Pressure - GREATER BOP THAN 2.7 PSIG CREW        CHECK Secondary Radiation:
: a. PERFORM EOP Addendum 11, Restoring SG Sampling BOP/SRO After SI Actuation
* PERFORM EOP Addendum 11, Restoring SG Sampling After SI Actuation
* DIRECT Chemistry to periodically sample all SGs for activity
* DIRECT Health Physics to survey steamlines in Auxiliary Building Area 5 as necessary CREW        b. CHECK unisolated secondary radiation monitors:
* SG Sample radiation:
* SJL 026
* SG ASD radiation:
* AB RIC 111 (SG A)
* AB RIC 112 (SG B)
* AB RIC 113 (SG C)
* AB RIC 114 (SG D)
* Turbine Driven Auxiliary Feedwater Pump Exhaust
 
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:        1    Scenario #      2      Event #      4,5,6            Page 22  of  28 Event


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 20 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r  BOP a. CHECK pressures in all SGs:    ANY S G PRESSURE L O WERI NG I N AN UNC ONT R OLLED MA NNER ("A")    O R    ANY S G COMPLETEL Y DEPRESS URIZED    BOP ISOLATE F aulted SG(s):
== Description:==
CRITIC A L TA S K BOP a. ISOLATE AFW flow to faulted SG(s):
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior radiation:
CLOSE associated MD AFP Flow Control Val ve(s):    AL HK-7A (S G A)    CLOSE associated TD AFP Flow C ontrol Valve(s):
* FC RIC 385
AL HK-8A (S G A)    BOP b. CHECK ASD from faulted SG(s) - CLOSED AB PIC-1A (S G A)      c. Locally CLOSE TDAFP Steam Supp ly From Main steam Loop Manual Isolatio n valve from faulted SG(s):
: c. Secondary radiation - NORMAL CREW       CHECK If ECCS Flow Should Be Reduced:
ABV0085 (SG B)
ABV0087 (SB C)
BOP d. CHECK Mai n Feedwater valves to faulted SG(s) -
CLOS ED    Main Feedwater Reg Valves:
AE ZL-510 (SG A)
Main Feedwater Reg Valves:
AE ZL-550 (SG A)
Feedwater Isolation Valve:
AE HIS-39 (S G A)
Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 21 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r      BOP e. CHECK SG Blowdown containment Isolation Valve from faulted SG(s) - CLOSED BM HI S-1A (SG A)    BOP f. CLOSE Ste a mline Low Point Drain valve fro m faulted SG(s):    AB HIS-9 (S G A)    BOP CHECK CST To AFP Suction Head er Pressure
- GREAT ER THAN 2.7 PSIG CREW CHECK Sec ondary Radi ation:    BOP/S R O a. PERF O RM EOP Adden dum 11, Re storing SG Sampling After SI Actuation PERF O RM EOP Adden dum 11, Re storing SG Sampling After SI Actuation DIRECT Ch emistry to periodically sample all SGs for activity    DIRECT He alth Physics to survey steamlines in Auxiliary Bui l ding Area 5 as necessa ry    CREW b. CHECK unisolated se condary radiation monitors:
SG Sa mple radiation:
SJL 026    SG ASD rad i ation:    AB RIC 111 (SG A)    AB RIC 112 (SG B)    AB RIC 113 (SG C)    AB RIC 114 (SG D)    Turbine Driven Auxiliary Feedwater Pump Exha ust Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 22 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r  radiation:
FC RIC 385
: c. Secondary radiation - N O RMAL    CREW CHECK If ECCS Flow Should Be Reduced:
: a. RCS subcooling - GREATER THAN 30°F
: a. RCS subcooling - GREATER THAN 30°F
: b. Secondary heat sink:
: b. Secondary heat sink:
Narrow rang e level in at least one int a ct SG - GREATER THAN 7% [2 5%]     O R    Total feed flow to intact SGs - GREATER THAN 300,000 LBM/HR
* Narrow range level in at least one intact SG -
: c. RCS pressure - STABL E OR RISING     d. PZR level - GREATER THAN 9% [2 9%]     R O R E S E T S I:   SB HS-42A   SB HS-43A     RO STOP All B u t One CCP:   BG HIS-1 A    O R    BG HIS-2 A    SRO Go To ES-1.
GREATER THAN 7% [25%]
1, SI Termination, Step
OR
: 3.
* Total feed flow to intact SGs - GREATER THAN 300,000 LBM/HR
Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 2 Event # 4,5,6 Page 23 of 28          Event Descri p ti on: Multipl e dro p p ed rods, AT W S , Stuck Open Main Steam S a fet y Va lve  T i me Positio n Appl icant's Acti ons or Beh a vi o r    Scenario ma y be termi nated upon transition to ES-1.1, or at Lead Examiner's discretion after all critical tasks a r e complete
: c. RCS pressure - STABLE OR RISING
: d. PZR level - GREATER THAN 9% [29%]
RO        RESET SI:
* SB HS-42A
* SB HS-43A RO       STOP All But One CCP:
* BG HIS-1A OR
* BG HIS-2A SRO       Go To ES-1.1, SI Termination, Step 3.


ATTAC H MENT A Automatic Action Veri fication  BOP CHECK Ch arging Pumps:
Appendix D                                  Operator Action                            Form ES-D-2 Op Test No.:      1      Scenario #      2      Event #      4,5,6            Page 23  of  28 Event
BOP a. CCPs - BOTH RUN NIN G    BG HIS-1 A    BG HIS-2 A    B O P b. S T O P NCP:   BG HIS-3     BOP CHEC K SI And RHR P u mps    SI Pumps -
 
BOTH RUN NING    EM HI S-4   EM HI S-5   RHR Pu mps - BOTH R UNNI NG    EJ HIS-1   EJ HIS-2     BOP CHECK ECCS Flow:
== Description:==
BOP a. CCPs to Boron Inj Header - FLOW INDICAT E D    EM FI-917A   EM FI-917B     BOP b. RCS pressure - LESS T H AN 1700 PSIG BOP c. SI Pump Dis c harge - FL OW INDI CATED    EM FI-918   EM FI-922     BOP d. RCS pressure - LESS T H AN 325 PSIG BOP e. RHR To Acc u mulator Injection Loop  
Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time          Position                          Applicants Actions or Behavior Scenario may be terminated upon transition to ES-1.1, or at Lead Examiners discretion after all critical tasks are complete
- FLOW INDICATED EJ FI-618 ATTAC H MENT A Automatic Action Veri fication    EJ FI-619   CAUTI O N: If offsite pow er is lost after SI res e t, manual action ma y be required to restart s a feguards equipment.
 
BOP CHECK ES W Pumps - BOTH RUNNING   EF HIS-55A   EF HIS-56A     BOP CHEC K CC W Alignment:
ATTACHMENT A Automatic Action Verification BOP CHECK Charging Pumps:
BOP a. CCW Pu mp s - ONE RU NNIN G IN E A CH TR AIN    Red Train:   EG HIS-21 or EG HIS-2 3    Yellow Train   EG HIS-22 or EG HIS-2 4    BOP b. CCW Service Loop Supply and Return valves for one operating CCW pump -
BOP a. CCPs - BOTH RUNNING
OPEN    EG ZL-15 AND EG ZL-53 O R    EG ZL-16 AND EG ZL-54 BOP CHECK Co ntainment Cooler Fans -
* BG HIS-1A
RUNNING I N SLOW SPEE D    GN HI S-9   GN HI S-17   GN HI S-5   GN HI S-13     BOP CHECK Co ntainment Hydrogen Mi xing Fans -
* BG HIS-2A BOP b. STOP NCP:
RUNNING I N SLOW SP E E D    GN HI S-2   GN HI S-4 ATTAC H MENT A Automatic Action Veri fication    GN HI S-1   GN HI S-3     BOP CHECK If Containment Spray Shoul d Be Actuated:
* BG HIS-3 BOP CHECK SI And RHR Pumps
* SI Pumps - BOTH RUNNING
* EM HIS-4
* EM HIS-5
* RHR Pumps - BOTH RUNNING
* EJ HIS-1
* EJ HIS-2 BOP CHECK ECCS Flow:
BOP a. CCPs to Boron Inj Header - FLOW INDICATED
* EM FI-917A
* EM FI-917B BOP b. RCS pressure - LESS THAN 1700 PSIG BOP c. SI Pump Discharge - FLOW INDICATED
* EM FI-918
* EM FI-922 BOP d. RCS pressure - LESS THAN 325 PSIG BOP e. RHR To Accumulator Injection Loop - FLOW INDICATED
* EJ FI-618
 
ATTACHMENT A Automatic Action Verification
* EJ FI-619 CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
BOP       CHECK ESW Pumps - BOTH RUNNING
* EF HIS-55A
* EF HIS-56A BOP       CHECK CCW Alignment:
BOP       a. CCW Pumps - ONE RUNNING IN EACH TRAIN
* Red Train:
* EG HIS-21 or EG HIS-23
* Yellow Train
* EG HIS-22 or EG HIS-24
: b. CCW Service Loop Supply and Return valves for one BOP operating CCW pump - OPEN
* EG ZL-15 AND EG ZL-53 OR
* EG ZL-16 AND EG ZL-54 CHECK Containment Cooler Fans - RUNNING IN SLOW BOP SPEED
* GN HIS-9
* GN HIS-17
* GN HIS-5
* GN HIS-13 CHECK Containment Hydrogen Mixing Fans - RUNNING IN BOP SLOW SPEED
* GN HIS-2
* GN HIS-4
 
ATTACHMENT A Automatic Action Verification
* GN HIS-1
* GN HIS-3 BOP CHECK If Containment Spray Should Be Actuated:
BOP a. CHECK the following:
BOP a. CHECK the following:
Containmen t pressure -
* Containment pressure - GREATER THAN 27 PSIG OR
GREATER THAN 27 PSIG O R    GN PR-934 indicates co ntainment pressure - HAS BEEN GRE A TER THA N 27 PSIG     O R    Annunciator 59A CSAS - LIT     O R    Annunciator 59B CISB -
* GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR
LIT     BOP b. Containmen t Spray Pu mps - BOTH RUNNING   EN HIS-3   EN HIS-9     BOP c. ESFAS stat us panels C SAS sections:
* Annunciator 59A CSAS - LIT OR
SA066 X W H ITE lights  
* Annunciator 59B CISB - LIT BOP b. Containment Spray Pumps - BOTH RUNNING
- ALL LIT SA066Y W H ITE lights  
* EN HIS-3
- ALL LIT BOP d. ESFAS stat us panels CI SB sections:
* EN HIS-9 BOP c. ESFAS status panels CSAS sections:
SA066 X W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT SA066Y W H ITE lights  
* SA066Y WHITE lights - ALL LIT BOP d. ESFAS status panels CISB sections:
- ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:
* SA066X WHITE lights - ALL LIT
* SA066Y WHITE lights - ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:
BOP a. CHECK for any of the following:
BOP a. CHECK for any of the following:
Containmen t pressure -
* Containment pressure - GREATER THAN 17 PSIG OR
GREATER THAN 17 PSIG O R    GN PR-934 indicates co ntainment pressure - HAS  
* GN PR-934 indicates containment pressure - HAS


ATTAC H MENT A Automatic Action Veri fication BEEN GRE A TER THA N 17 PSIG     O R    Steamline pressure - LESS THAN 615 PSIG     O R    AB PR-514 or PR-535 indicates ste a mline pressure -
ATTACHMENT A Automatic Action Verification BEEN GREATER THAN 17 PSIG OR
HAS BEEN LESS THAN 615 PSIG BOP b. CHECK MSI V s and Byp a ss valves - CLOSED BOP CHECK ECCS Valves -
* Steamline pressure - LESS THAN 615 PSIG OR
PROP ER E M ERGE NCY ALIGNME N T    BOP a. ESFAS stat us panels SI S sections:
* AB PR-514 or PR-535 indicates steamline pressure -
SA066 X W H ITE lights  
HAS BEEN LESS THAN 615 PSIG BOP       b. CHECK MSIVs and Bypass valves - CLOSED BOP       CHECK ECCS Valves - PROPER EMERGENCY ALIGNMENT BOP       a. ESFAS status panels SIS sections:
- ALL LIT SA066Y W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT BOP CHECK Co ntainment Isolation Phase A:
* SA066Y WHITE lights - ALL LIT BOP       CHECK Containment Isolation Phase A:
BOP a. ESFAS stat us panels CI SA sections:
BOP       a. ESFAS status panels CISA sections:
SA066 X W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT SA066Y W H ITE lights  
* SA066Y WHITE lights - ALL LIT BOP       CHECK SG Blowdown Isolation:
- ALL LIT BOP CHECK SG Blowdown Isolation:
BOP       ESFAS status panels SGBSIS sections:
BOP ESFAS stat us panels S G BSIS sections:
* SA066X WHITE lights - ALL LIT
SA066 X W H ITE lights  
* SA066Y WHITE lights - ALL LIT CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
- ALL LIT SA066Y W H ITE lights  
BOP       CHECK Both Trains of control Room Ventilation Isolation:
- ALL LIT CAUTI O N: If offsite pow er is lost after SI res e t, manual action ma y be required to restart s a feguards equipment.
BOP       a. ESFAS status panels CRVIS sections:
BOP CHECK Bot h Trains of control Room Ventilation I s olation:     BOP a. ESFAS stat us panels C R VIS sections:
* SA066X WHITE lights - ALL LIT
SA066 X W H ITE lights  
- ALL LIT  


ATTACHMENT A Automatic Action Verification SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:
ATTACHMENT A Automatic Action Verification
* SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:
BOP a. ESFAS status panels CPIS sections:
BOP a. ESFAS status panels CPIS sections:
SA066X WHITE lights - ALL LIT SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
* SA066X WHITE lights - ALL LIT
Manual actions taken Failed Equipment Attachment A, Automatic Action Verification, completed  
* SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
* Manual actions taken
* Failed Equipment
* Attachment A, Automatic Action Verification, completed


ATTACHMENT A Automatic Action Verification 36  BOP a. ESFAS status panels CRVIS sections:
ATTACHMENT A Automatic Action Verification BOP a. ESFAS status panels CRVIS sections:
SA066X WHITE lights - ALL LIT SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:
* SA066X WHITE lights - ALL LIT
* SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:
BOP a. ESFAS status panels CPIS sections:
BOP a. ESFAS status panels CPIS sections:
SA066X WHITE lights - ALL LIT SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
* SA066X WHITE lights - ALL LIT
Manual actions taken Failed Equipment Attachment A, Automatic Action Verification, completed  
* SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
* Manual actions taken
* Failed Equipment
* Attachment A, Automatic Action Verification, completed 36


Appendix D Scenario Outline Form ES-D-1 F a c i l i t y: C a l l a w a y S c e n a r i o No.: 3 Op Test No.:
Appendix D                                       Scenario Outline                               Form ES-D-1 Facility:         Callaway                        Scenario No.:         3   Op Test No.:       NRC Examiners:                                                   Operators:
NRC E x a m i n e r s:   O p e r a t o r s:             Initial Conditi ons: 5 - 10% power, BOL.
Initial Conditions:     5 - 10% power, BOL.
RE-5 2, Blowd o wn Disch a rg e Pumps Discha rge M onit o r, is OOS.
RE-52, Blowdown Discharge Pumps Discharge Monitor, is OOS.
BB-PCV-455A PORV Leak a ge - Block Valve Closed.
BB-PCV-455A PORV Leakage - Block Valve Closed.
Turn over: Incre a se po wer to 100% at 3% per hou r  Critical Ta sk: Isolate ru ptur ed SG in step 3 of E-3.
Turnover:               Increase power to 100% at 3% per hour Critical Task:           Isolate ruptured SG in step 3 of E-3.
Establish and Maintain RCS temperatu r e bel o w that required for d epre s su rization of the ruptu r ed SG. Event No. Malf. No. Event Type* E v e n t Description R - RO Rai s e po we r. 1 T+0 N - BOP, SRO I - ALL Powe r Ra nge NI failure.
Establish and Maintain RCS temperature below that required for depressurization of the ruptured SG.
2 T+10 NIS03D TS - SRO I - BOP, Steam Dump pres sure s e tpoint failure.
Event          Malf.      Event                                        Event No.         No.       Type*                                   Description 1                    R - RO         Raise power.
3 T+30 MSS13B S R O  4 T+40 BBV001 C - RO, SRO TS - SRO RCP hig h vibration.
T+0                     N - BOP, SRO 2                    I - ALL       Power Range NI failure.
5 T+60 RCS0 2 A M - ALL SGTR. Rea c tor trip re quired. 6 MSS07A C - BOP Atmosph e ri c dump valve fails op en, req u iring m anual isolation.
NIS03D T+10                     TS - SRO 3                    I - BOP,       Steam Dump pressure setpoint failure.
7 Component Override KAHIS29 C - RO Instrum ent air to containme n t fails clo s ed , requiri ng alt e rnate RCS depressu ri zat i on. * (N)ormal,   (R)eactivity,   (I)nstrument,   (C)omp onent,   (M)ajor
MSS13B T+30                     SRO 4                     C - RO,       RCP high vibration.
T+40        BBV001      SRO TS - SRO 5                    M - ALL       SGTR. Reactor trip required.
RCS02A T+60 6                     C - BOP       Atmospheric dump valve fails open, requiring manual isolation.
MSS07A 7       Component     C - RO         Instrument air to containment fails closed, requiring alternate RCS Override                  depressurization.
KAHIS29
    *   (N)ormal,     (R)eactivity,   (I)nstrument,     (C)omponent,     (M)ajor Scenario Event Description NRC Scenario 3 The crew will assume the shift with instructions to raise reactor power in preparation for returning the unit to full power.
When the power ascension is in progress, a power range instrument will fail high, requiring the crew to respond in accordance with OTO-SE-1. The crew will manually control feedwater bypass flow and remove the failed channel from service. The SRO will also determine the appropriate technical specification action requirements.
When the plant is stable and technical specifications have been addressed, a steam dump pressure setpoint failure will require the crew to place steam dumps in off/reset and control reactor power and Tave manually in accordance with OTO-AB-1 and OTO-AB-4.
When the plant is stable, increasing RCP vibration will require the crew to enter OTO-BB-2 to determine that the RCP must be stopped in accordance with OTN-BB-3. The crew will stop the affected RCP after determining reactor power is below P-8. Actions of OTO-BB-4 will also be performed to defeat Loop Delta T and Tave inputs. The SRO will also determine the appropriate technical specification action requirements.
When the plant is stable, a SGTR develops, requiring the crew to trip the reactor and initiate Safety Injection. An atmospheric dump valve will fail open in automatic and require manual closure. Instrument Air to containment will fail closed, requiring alternate RCS depressurization.
The scenario may be terminated when ECCS pumps are stopped in E-3, Steam Generator Tube Rupture.
EOP Flow Path: E-0, E-3 SCENARIO SETUP GUIDE                                        EXAM #:      ILT-1 Scenario Malfunction List
: 1)  Initialize at IC-67. password = redsox, MONITOR CAF20(4) equal 1.0
: 2)  Run Batch File "iltthree.txt", and verify the actions on the following page are loaded correctly.
: 3)  Ensure Immediate Boration Timer is reset.
: 4)  Check RX trip switch has a RED flag.
: 5)  Ensure NIS indicates 10%
: 6)  Ensure step counters for Control Bank D are set at 114 steps and all other step counters are set for 228.
: 7)  Ensure the digital display is selected to REP0480A and RET0499A.
: 8)  Ensure Decrease Loading Rate Button is ON.
: 9)  Update status board for B Protected Train week.
: 10) Place Letdown orifi A and B in service with a caution tag on C
: 11) White board has the following boron concentrations:
    * 'A' CCP "5 days ago" 1107 ppm
    * 'B' CCP "two weeks ago" 1135 ppm
: 12) Supply turnover and log sheets, Xe Predict, Dilution/Boration calculation and OTG-ZZ-00003.
: 13) Ensure the RM-11 is on the training system.
: 14) Microphones available for each person being evaluated and a video tape is in the VCR.
: 15) Ensure chart recorders are "rolled forward".
: 16) Ensure copies of the following procedures are in the file drawers:
* OTO-SE-00001
* OTO-AB-00004
* OTO-AB-00001
* OTO-BB-00002
* OTN-BB-00003
* E-0
* E-3 Scenario 3
>File:                iltthree.txt
>Author: S. P. Aufdemberge
>Date:                20050517
>=============SCENARIO SETUP ITEMS===========================================
>Simulates de-energization of "A" PORV Block valve due to PORV Leakage irf bbs014 (-1 0) 0
>BMRE52 OOS Pre-Setup imf rms6_08 (-1 0)
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT A
>Fail N44 to full scale high imf nis03d (1 0) 200 10
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT B
>Steam Dump Pressure Setpoint Failure imf mss13b (2 0) 1500 100
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT C
>RCP Hi Vibration irf bbv001 (3 0) 6.1 30
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT D
>SGTR A Leak grows from 0 to 300 over 100 seconds AUTOMATICALLY inserted when >BBHIS37 taken to stop or PTL.
trgset 4 x21i115s imf rcs02a (4 120) 300 100
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT E
> A ASD fails open requiring manual isolation trgset 5 x04o9o imf mss07a (5 0)
>============================================================================
>========================EVENT PRELOAD=======================================
>EVENT F
>Instrument Air Fails closed requiring Alternate RCS Depressurization trgset 6 jstsisa.eq.1 ior kahis29_ic (6) on ior kahis29_io (6) off ior kahis29_og (6) on ior kahis29_or (6) off
>================================================================================
==============================================================================
To FAST CLOSE A MSIV ONLY:
SAS013A set to OFF SAS013B set to OFF SAS013C set to OFF SAS017 set to ENABLE SAS018A set to FC
>end of file Scenario 3 Crew Turnover Separate Turnover sheets provided Appendix D                                Operator Action                          Form ES-D-2 Op Test No.:        1    Scenario #      3    Event #      1                Page 6  of 31 Event


Scenario Event Description NRC Scena rio 3 The crew will assume th e shift with i n struction s t o raise react o r power in preparation for returning th e unit to full power. When the power ascen s ion is in pr ogress, a po wer range instrument will fail high, re quiring the crew to resp ond in accor dance with OTO-SE-1.
== Description:==
The crew will manually control feedwater bypass flow and remove the failed ch annel from service. The SRO will also determine the appropriate technical sp ecificat ion a c tion require ments. When the plant is stab le and technical spec if ications have been addresse d, a steam dump pressure set point failure will require t he crew to place steam dumps in off/reset and control reactor power and Tave manually in accordance with OTO-AB-1 and OT O-AB-4. When the pl ant is stab le , increasin g RCP vibration will requi re the crew to enter OTO-BB-2 to determine that the RCP must be stopped in accordance wit h OTN-BB-3. The crew will stop the affected RCP after determining reactor power is below P-8. Actions of OTO-BB-4 will also be performed to defeat Loo p Delta T and Tave inputs. The SRO will also det ermine the appropriate technical sp ecificat ion a c tion require ments. When the plant is stab le , a SGTR de velops, requiring the cre w to trip the reactor and initiate Safety Injection. An atmospheric du mp val v e will fail open in automatic and require manual closure. In strument Air to containment will fail cl osed, requiri ng alternate RCS depres surization.
Raise Power Time          Position                          Applicants Actions or Behavior Refer to OTG-ZZ-0003, Plant Startup Hot Zero Power to 30%
The scenario may be terminated when ECCS pu mps are stopped in E-3, Steam Gen e rator Tube Rupture.
SRO Power, section 6.3 Perform a Pre-Job Brief of power ascension:
EOP Flow Path:  E-0, E-3   
* General strategy for proceeding to 30% Power.
* Any items not completed as expected to this point.
* Applicable Precautions and Limitations
* Activities that can be performed at any time during the next CREW              sections(s) of this procedure such as Stroking MFRV's and Placing Reboiler in service.
* MFP and MFRV control status
* Extraction Steam Line Drain and FW Preheating status
* Steam Dump strategy Discuss the use of Optional Parameter Alarms as an aid to avoid undesired challenges to legal or system requirements BOP      Initiate a 3% per hour loading rate RO      Commence raising reactor power When power is >10%, verify P-7 and P-10 permissives are RO illuminated When control of the plant is demonstrated during startup, proceed to the next event


SCENARIO SETUP GUI D E  EXAM #:  ILT-1  Scenario Malfunction List
Appendix D                             Operator Action                            Form ES-D-2 Op Test No.:       1     Scenario #    3     Event #      2               Page 7   of 31 Event
: 1) Initialize at IC-67. pa sswo rd = re dsox, M O NITO R CA F20(4) eq ual 1.0 2) Run Batch Fil e "iltthree.
tx t", and verify the action s o n the followin g page a r e lo aded corre c tl y. 3) Ens u re Immediate Boration Timer is reset. 4) Che c k RX tri p swit ch ha s a RED flag.
: 5) Ensu re NIS indicates 1 0% 6) Ensu re ste p counters fo r Control Ban k "D" a r e set at 114 ste p s a n d all other ste p cou n ters are set for 228. 7) Ensu re the di gital displ a y is sel e cte d to REP048 0A and RET0 499 A. 8) Ensu re Decre a se L oadi ng Rate Button is "O N". 9) Upd a te statu s boa rd for "B" Prote c ted Train we ek. 10) Place Letd o wn orifi A and B in service with a ca ution tag on C
: 11) White bo ard has the follo wing boron con c entration s: 'A' CCP "5 da ys ago" 110 7 ppm  'B' CCP "two wee k s ago" 1 135 ppm 12) Supply turnov er and lo g sh eets, Xe Pred ict, Dilution/Boration cal c ul ation and OTG-ZZ-000
: 03. 13) Ensu re the RM-11 i s on th e training system. 14) Microph one s available for each perso n being evalu a t ed and a vide o tape is in th e VCR. 15) Ensu re chart recorders a r e "rolled forwa r d". 16) Ensu re copie s of the following pro c e d u r e s are in the fil e dra w e r s:  OTO-SE-00 0 01  OTO-AB-00 0 04  OTO-AB-00 0 01  OTO-BB-00 0 02  OTN-BB-00003  E-0  E-3 Scenario 3  
>File:  iltthree.txt
>Author: S. P. Aufdember ge >Date:  20050517 > >=========
====SCENARIO SE TUP ITEMS====
==========
=============
=============
=== >Simulates de-energization of "A" PO RV Block valve due to PORV Leakage irf bbs014 (-
1 0) 0 >BMRE52 OOS Pre-Setup imf rms6_08 (-1
: 0) >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT A >Fail N44 to full scale high imf nis03d (1 0) 200 10 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT B >Steam Dump P r essure Setpoint Failure imf mss13b (2 0) 1500 100
>=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT C 
>RCP Hi Vibration irf bbv001 (3 0
) 6.1 30 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT D >SGTR A L eak g r o w s from 0 t o 3 00 over 100 seco nds AUTO MA TI CALL Y inser t ed w h en >BBHIS37 taken to stop or PTL. trgset 4 "
x 21i115 s" imf rcs02a (4 12
: 0) 300 10 0 >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT E > "A" ASD fails open requiring m a nual isolation trgset 5 "
x 04o9 o" imf mss07a (5 0)
   >=========
=============
=============
=============
=============
=============
== >=========
=============
==E VENT PREL O A D===========
==========
=============
===== >EVENT F >Instrument Air Fails closed requiri ng Alternate R C S Depressuriza tion trgset 6 "jstsisa.eq.1" ior kahis29_ic (6) on ior kahis29_io (6) off ior kahis29_og (6) on ior kahis29_or (6) off >=========
=============
=============
=============
=============
=============
====== ==========
=============
=============
=============
=============
=============
=== To FAST CL O SE "A" MSIV O N L Y: SAS013A set to "
O F F" SAS013B set to "
O F F" SAS013C set to "OFF" SAS017 set to "E NABLE" SAS018A set to "
F C" >end of file


Scenario 3 Crew Turno ver      Separate Turnover sheets provided
== Description:==
Power Range NI Failure Time          Position                        Applicants Actions or Behavior Booth Instructor Instructions:
When directed, insert command for Power Range NI failure Indications Available:
PRNI N-44 failing HIGH Annunciators 78A, 78E, 82A for Power Range Channel deviation REACTOR PARTIAL TRIP Annunciator 83C BOP      Refer to Annunciator Response procedures SRO      Refer to OTO-SE-00001, Nuclear Instrument Malfunction Check Power Range Instruments normal.
RO
* N-44 is failing high RO        Ensure Rod Control is in MANUAL BOP      Place SG Main Feed Reg Bypass valves in MANUAL BOP      Control SG levels from 45 - 55%
BOP      Stop any Main Turbine load changes (None in progress)
RO        Maintain Tave/Tref within 1.5°F using manual rod control Check the following permissives are in their required state
* P-7 CREW
* P-8
* P-9
* P-10 CREW        Select an operable channel on the NI Recorder


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 1 Page 6 of 31          Event Descri p ti on: Raise P o w e r  T i me Positio n Appl icant's Acti ons or Beh a vi o r     SRO Refer to OT G-ZZ-0003, Plant Startup Hot Zero Power to 30%
Appendix D                             Operator Action                           Form ES-D-2 Op Test No.:       1     Scenario #    3     Event #     2               Page 8  of 31 Event
Power, section 6.3 CREW Perform a Pre-Job Brief of power ascension:
General strategy for proceeding to 30
% Power. Any items n o t completed as expected to this po int. Applicable P r ecautions a nd Limitatio n s  Activities th at can be pe rformed at any time duri ng the next sections(s) of this proce dure such a s Stroking MFRV's and Placing Reboiler in service. MFP and MFRV control status  Extraction Steam Line Drain and FW Preheating status  Steam Du mp strategy Discuss the use of Optional Parameter Alarms as an aid to avoid undesired challen ges to legal or system requirements BOP Initiate a 3%
per hour lo ading rate RO Commence raising react o r power    RO When power is >10%, verify P-7 and P-10 permissives are illuminated When control of the plant is demonstrated during startup, proceed to the next event Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 2 Page 7 of 31           Event Descri p ti on: Po w e r R ang e NI F a ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Instructor Instructions:
When directed, insert command for Pow e r Range NI failure Indications Available:
PRNI N-44 f a iling HIGH Annunciators 78A, 78E, 82A for Po w e r Range Channel deviation REACT OR PARTIAL T R IP Annun ciator 83C BOP Refer to Annunciator R e sponse pro c edures    SRO Refer to OT O-SE-00001 , Nuclear In strument Ma lfunction RO Check Power Range Instruments normal. N-44 is failin g high    RO Ensure Rod Control is in MANUAL    BOP Place SG Main Feed Reg Bypass va lves in MANUAL BOP Control SG levels from 45 - 55%
BOP Stop any Main Turbine load change s (None in p r ogress)    RO Maintain Tave/Tref within 1.5°F usin g manual rod control CREW Check the f o llowing per missives are in their requ ired state  P-7  P-8  P-9  P-10    CREW Select an op erable chan nel on the NI Recorder


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 2 Page 8 of 31          Event Descri p ti on: Po w e r R ang e NI F a ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r      CREW Bypass the malfunctioning channel at the Detector Current Comparator Drawer Place UPPER SECTI ON switch to N-44 Place LOWER SECTION switch to N-44 Place ROD STOP B Y P ASS switch to N-44 Place POWER MI SMATCH BY PAS S switch to N-44     CREW At the Comp arator and Rate drawer, place Comparator Channel Defeat switch to N-44     CREW Ensure the following ann unciator win dows are extinguished: 78A, PR CH ANNEL DE V  78B, PR UP PER DETE CTOR FL UX DEV 78C, PR LOWER DET E CTOR FL UX DEV 82A, PR OV ER PWR ROD ST OP    RO Check Rod Control in AUTO Rod Control is in MANUAL BOP Return Feed Reg Bypas s valves to automatic operation as required by the SRO BOP Control SG levels at 45 - 55%
== Description:==
CREW Check Reactor Power >10% (NO) Perform Att a chment B, Low Power Trips Enabled, within the ti me limit specified in TS SRO Refer to applicable Te ch Specs TS 3.3.1 Condition D, E, S  
Power Range NI Failure Time          Position                        Applicants Actions or Behavior Bypass the malfunctioning channel at the Detector Current Comparator Drawer
* Place UPPER SECTION switch to N-44 CREW
* Place LOWER SECTION switch to N-44
* Place ROD STOP BYPASS switch to N-44
* Place POWER MISMATCH BYPASS switch to N-44 At the Comparator and Rate drawer, place Comparator CREW Channel Defeat switch to N-44 Ensure the following annunciator windows are extinguished:
* 78A, PR CHANNEL DEV CREW
* 78B, PR UPPER DETECTOR FLUX DEV
* 78C, PR LOWER DETECTOR FLUX DEV
* 82A, PR OVER PWR ROD STOP Check Rod Control in AUTO RO
* Rod Control is in MANUAL Return Feed Reg Bypass valves to automatic operation as BOP required by the SRO BOP       Control SG levels at 45 - 55%
Check Reactor Power >10% (NO)
CREW
* Perform Attachment B, Low Power Trips Enabled, within the time limit specified in TS Refer to applicable Tech Specs SRO
* TS 3.3.1 Condition D, E, S


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 2 Page 9 of 31           Event Descri p ti on: Po w e r R ang e NI F a ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r    When Tech Specs have been identified, proceed to Event 3
Appendix D                             Operator Action                           Form ES-D-2 Op Test No.:       1     Scenario #     3     Event #     2               Page 9   of 31 Event


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 3 Page 10 of 31           Event Descri p ti on: Steam Dump P r essure Setp oi nt F a ilure  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Instructor Instructions:
== Description:==
Power Range NI Failure Time          Position                        Applicants Actions or Behavior When Tech Specs have been identified, proceed to Event 3
 
Appendix D                               Operator Action                         Form ES-D-2 Op Test No.:       1     Scenario #     3     Event #     3               Page 10 of 31 Event
 
== Description:==
Steam Dump Pressure Setpoint Failure Time          Position                        Applicants Actions or Behavior Booth Instructor Instructions:
When directed, insert command for the Steam Dump pressure transmitter failure Indications Available:
When directed, insert command for the Steam Dump pressure transmitter failure Indications Available:
Steam Dum ps start to open SRO Refers to OTO-AB-000 04, Steam Header Pressure Channel Failure     BOP Check Steam header pressure indicator AB PI-5 07 indicatin g significantly different tha n SG pressure indicators BOP Check Feed Pump Spee d Changing due to failed channel Must control feed pump speed using GE potentiometers with speed controller in manual, due to PT-507 failure Restore programmed DP     BOP Check Steam Du mp Co ntrol in Pressure Mode BOP Place Steam Header Pressure Controller in MANUAL BOP Check stea m dumps re sponding in MANUAL     BOP Manually control SG pressure to the desired value SRO Initiate act i o n s to repair f a iled transmitter SRO Perform notifications per OPS-Communications-01 When steam pressure is under manual control, proceed to the next event  
Steam Dumps start to open Refers to OTO-AB-00004, Steam Header Pressure Channel SRO Failure Check Steam header pressure indicator AB PI-507 indicating BOP significantly different than SG pressure indicators Check Feed Pump Speed Changing due to failed channel
* Must control feed pump speed using GE potentiometers BOP with speed controller in manual, due to PT-507 failure
* Restore programmed DP BOP       Check Steam Dump Control in Pressure Mode BOP       Place Steam Header Pressure Controller in MANUAL BOP       Check steam dumps responding in MANUAL BOP       Manually control SG pressure to the desired value SRO       Initiate actions to repair failed transmitter SRO       Perform notifications per OPS-Communications-01 When steam pressure is under manual control, proceed to the next event


Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 4 Page 11 of 31           Event Descri p ti on: RCP Hig h Vibr ation  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Booth Operator Instructions:
Appendix D                               Operator Action                         Form ES-D-2 Op Test No.:       1     Scenario #     3   Event #       4               Page 11 of 31 Event
 
== Description:==
RCP High Vibration Time          Position                        Applicants Actions or Behavior Booth Operator Instructions:
When directed, insert command to initiate RCP high vibration Indications Available:
When directed, insert command to initiate RCP high vibration Indications Available:
RCP VI B DANGER An nunciator 70A RCP VI B/SYS ALERT Annunciator 70B NOTE: In Modes 1 & 2 when a RCP is stopped, the idle loop RTD channel is IN OPERABLE and the actions of OTO-BB-00004, RTD Chann el Failures, should be p e rformed. SRO Refer to OT O-BB-00002 , Reactor Coolant Pump Off-Normal R O Check R C P V i b r a t i o n s      a. RCP Vibrati on level; ALL RCPs L e ss than 5 MILS on the frame   A N D    ALL RCPs L e ss than 20 MILS on the shaft (at RP312, B YI-471) (See cue shee t posted beh ind back bo ards)     IF Reactor power LESS THAN 48%   (P-8 extinguished on SB069)
RCP VIB DANGER Annunciator 70A RCP VIB/SYS ALERT Annunciator 70B NOTE:
RO SECURE th e affected RCP IAW OT N-BB-00003. (Will stop pump in a subsequent step)
In Modes 1 & 2 when a RCP is stopped, the idle loop RTD channel is INOPERABLE and the actions of OTO-BB-00004, RTD Channel Failures, should be performed.
RO Continue to MONITOR RCP para m eters for all RCPs. SRO REFER to OTG-ZZ-00004, Power Op erations, to shutdown the plant.
SRO       Refer to OTO-BB-00002, Reactor Coolant Pump Off-Normal RO      Check RCP Vibrations
Appendix D Operator Action Form ES-D-2 Op T e st No.: 1 Scenar io # 3 Event # 4 Page 12 of 31           Event Descri p ti on: RCP Hig h Vibr ation  T i me Positio n Appl icant's Acti ons or Beh a vi o r  SRO Refer to T/S LCO 3.3.1, T/S LCO 3.3
: a. RCP Vibration level;
.2, and T/S LCO 3.4.4.
* ALL RCPs Less than 5 MILS on the frame AND
CREW Verify that permissive P8 is extinguished.
* ALL RCPs Less than 20 MILS on the shaft (at RP312, B YI-471) (See cue sheet posted behind back boards)
CAUTI O N: Consider the effects of securing the RCP WIL L have on S/G level and Pzr Pre ssure control. The FRV in Auto should handle the transient but will later need to be closed and the FRV Bypass placed in service to prevent a high level Turbine Trip. If the "D" RCP is secured, Pzr Press con trol is accomplished by c y cling h eaters. RO STOP the Reactor Coolant Pump.
IF Reactor power LESS THAN 48%
CREW In Modes 1, and 2, when a RCP is stopped, the idle loop RT D channel is I N OPERABL E. PERF O RM actions of OTO-BB-00004, RTD CHANNEL FAILURES, for the INOPERABLE RT D channel and refer to T/S LCO 3.3.1, T/S LCO 3.3
(P-8 extinguished on SB069)
.2, T/S LCO 3.4.4 and CARS 19960 1236. CREW GO T O OT G-ZZ-00005, Plant Shutdown 20% Power to Ho t Standby.       The next event is initiated on a trigger from RCP trip  
SECURE the affected RCP IAW OTN-BB-00003. (Will stop RO pump in a subsequent step)
RO       Continue to MONITOR RCP parameters for all RCPs.
REFER to OTG-ZZ-00004, Power Operations, to shutdown the SRO plant.
 
Appendix D                               Operator Action                         Form ES-D-2 Op Test No.:       1     Scenario #     3   Event #     4               Page 12 of 31 Event
 
== Description:==
RCP High Vibration Time          Position                      Applicants Actions or Behavior SRO       Refer to T/S LCO 3.3.1, T/S LCO 3.3.2, and T/S LCO 3.4.4.
CREW       Verify that permissive P8 is extinguished.
CAUTION:         Consider the effects of securing the RCP WILL have on S/G level and Pzr Pressure control. The FRV in Auto should handle the transient but will later need to be closed and the FRV Bypass placed in service to prevent a high level Turbine Trip. If the D RCP is secured, Pzr Press control is accomplished by cycling heaters.
RO       STOP the Reactor Coolant Pump.
In Modes 1, and 2, when a RCP is stopped, the idle loop RTD channel is INOPERABLE. PERFORM actions of OTO-BB-CREW        00004, RTD CHANNEL FAILURES, for the INOPERABLE RTD channel and refer to T/S LCO 3.3.1, T/S LCO 3.3.2, T/S LCO 3.4.4 and CARS 199601236.
GO TO OTG-ZZ-00005, Plant Shutdown 20% Power to Hot CREW Standby.
The next event is initiated on a trigger from RCP trip
 
Appendix D                                Operator Action                              Form ES-D-2 Op Test No.:        1    Scenario #    3    Event #      5, 6, 7          Page 13      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior Indications Available:
PRESSURIZER LOW LEVEL DEVIATION Annunciator 32C PRESSURIZER PRESSURE LOW HEATERS ON Annunciator 33C RO        Determines PZR level dropping rapidly.
SRO      Directs Reactor Trip and Safety Injection actuation.
RO        CHECK Reactor Trip:
* Rod Bottom Lights - ALL LIT
* Reactor Trip and Bypass Breakers - OPEN
* Neutron Flux - LOWERING BOP      CHECK Turbine Trip:
: a. All Turbine Stop valves - CLOSED CREW        CHECK Power To AC Emergency Buses:
RO/BOP      a. AC emergency buses - AT LEAST ONE ENERGIZED
* NB01 OR
* NB02
: b. AC emergency buses - BOTH ENERGIZED CHECK SI Status:
 
Appendix D                                Operator Action                              Form ES-D-2 Op Test No.:      1      Scenario #    3    Event #      5, 6, 7          Page 14      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior RO        a. CHECK if SI is actuated:
* Any SI annunciator 88A through 88D - LIT OR
* SB069 SI Actuate RED light - LIT OR
* LOCA Sequencer annunciators 30A or 31A - LIT RO        b. CHECK both Trains of SI - ACTUATED
* LOCA Sequencer annunciator 30A - LIT
* LOCA Sequencer annunciator 31A - LIT
* SB069 SI Actuate RED light - LIT SOLID (NOT blinking)
PERFORM Attachment A, Automatic Action Verification, while BOP continuing with this procedure.
BOP      CHECK Generator Output Breakers - OPEN
* MA ZL-3A (V55)
* MA ZL-4A (V53)
BOP      CHECK Feedwater Isolation:
BOP      a. Main Feedwater Pumps - TRIPPED
* Annunciator 120A, MFP A Trip - LIT
* Annunciator 123A, MFP B Trip - LIT BOP      b. Main Feedwater Reg Valves - CLOSED
* AE ZL-510 (SG A)
* AE ZL 520 (SG B)
* AE ZL 530 (SG C)
 
Appendix D                                Operator Action                                Form ES-D-2 Op Test No.:      1      Scenario #    3      Event #      5, 6, 7          Page 15      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior
* AE ZL 540 (SG D)
BOP      c. Main Feedwater Reg Bypass Valves - CLOSED
* AE ZL-550 (SG A)
* AE ZL 560 (SG B)
* AE ZL 570 (SG C)
* AE ZL 580 (SG D)
BOP      d. Feedwater Isolation valves - CLOSED
* AE HIS-39 (SG A)
* AE HIS-40 (SG B)
* AE HIS-41 (SG C)
* AE HIS-42 (SG D)
BOP      CHECK AFW Pumps:
: a. MD AFW Pumps - BOTH RUNNING
* AL HIS-23A
* AL-HIS-22A
: b. TD AFW Pumps - RUNNING IF NECESSARY BOP      CHECK AFW Valves - PROPER EMERGENCY ALIGNMENT
* MD AFP Flow Control Valves - THROTTLED
* AL HK-7A
* AL HK-9A
* AL HK-11A
* AL HK-5A
* TD AFP Flow Control Valves - FULL OPEN
 
Appendix D                                Operator Action                                Form ES-D-2 Op Test No.:      1      Scenario #    3      Event #      5, 6, 7          Page 16      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior
* AL HK-8A
* AL HK-10A
* AL HK-12A
* AL HK-6A BOP      CHECK Total AFW Flow - GREATER THAN 300,00 LBM/HR RO        CHECK PZR PORVs and Spray Valves:
: a. PZR PORVs - CLOSED
* BB HIS-455A
* BB-HIS-456A
: b. PZR PORVs - BOTH IN AUTO
* BB HIS-455A
* BB-HIS-456A
: c. PORV Block Valves - BOTH OPEN (NO)
* BB HIS-8000A (Closed)
* BB-HIS-8000A
: d. Normal PZR Spray Valves - CLOSED
* BB ZL-455A
* BB-ZL-456A RO        CHECK If RCPs Should Be Stopped:
: a. RCPs - ANY RUNNING
 
Appendix D                                Operator Action                                Form ES-D-2 Op Test No.:      1      Scenario #    3      Event #      5, 6, 7          Page 17      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior
: b. ECCS Pumps - AT LEAST ONE RUNNING
* CCP OR
* SI Pump
: c. RCS pressure - LESS THAN 1425 PSIG RO        CHECK RCS Temperatures:
* Any RCP running - RCS TAVG STABLE AT 557°F OR TRENDING TO 557°F RO        CHECK If Any SG Is Faulted:
: a. CHECK pressures in all SGs:
* ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER (NO)
OR
* ANY SG COMPLETELY DEPRESSURIZED RO        CHECK If SG Tubes Are Intact:
* Levels in all SGs:
* NO SG NARROW RANGE LEVEL RISING IN AN UNCONTROLLED MANNER
* SG Steamline N16 radiation - NORMAL
* N16 161 (SGA)
* N16 162 (SGB)
* N16 163 (SGC)
* N16 164 (SGD)
* Condenser Air Removal radiation - NORMAL BEFORE ISOLATION
* GEG 925
 
Appendix D                                Operator Action                              Form ES-D-2 Op Test No.:        1    Scenario #    3    Event #      5, 6, 7          Page 18      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior
* SG Blowdown and Sample radiation - NORMAL BEFORE ISOLATION
* BML 256
* SJL 026
* SG ASD radiation - NORMAL
* AB RIC 111 (SG A) (NO)
* AB RIC 112 (SG B)
* AB RIC 113 (SG C)
* AB RIC 114 (SG D)
* Turbine Driven Auxiliary Feedwater Pump Exhaust Radiation - NORMAL
* FC RIC 385 SRO      Go To E-3, Steam Generator Tube Rupture, Step 1 RO        CHECK If RCPs Should Be Stopped:
: a. RCPs - ANY RUNNING
: b. ECCS pumps - AT LEAST ONE RUNNING
* CCP OR
* SI Pump
: c. RCS pressure - LESS THAN 1425 PSIG CREW        IDENTIFY Ruptured SG(s):
* Unexpected rise in any SG narrow range level (A SG)
OR
* High radiation from any SG sample
 
Appendix D                                Operator Action                              Form ES-D-2 Op Test No.:      1      Scenario #    3    Event #      5, 6, 7          Page 19      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior OR
* High radiation from any SG steamline OR
* High radiation from any SG Blowdown line sample CRITICAL TASK              BOP      ISOLATE Flow From Ruptured SG(s):
: a. ADJUST ruptured SG(s) ASD controller setpoint to 1160 PSIG:
* AB PIC-1A (SG A)
: b. CHECK ruptured SG(s) ADS - CLOSED
* AB PIC-1A (SG A)
IF SG ASD is NOT closed, THEN PLACE SG ASD controller BOP in MANUAL and CLOSE SGT ASD.
: c. Locally CLOSE TDAFP Steam Supply From Main Steam Loop Manual Isolation valve from ruptured SG(s):
* ABV0085 (SG B)
* ABV0087 (SG C)
: d. CHECK SG Blowdown and Sample Isolation valves from ruptured SG(s) - CLOSED
* Blowdown Containment Isolation Valve:
* BM HIS-1A (SG A)
* Upper Sample Inner Containment Isolation valve:
* BM HIS-19 (SG A)
: e. CLOSE Steamline Low Point Drain valve from ruptured
 
Appendix D                                Operator Action                                Form ES-D-2 Op Test No.:      1      Scenario #    3      Event #      5, 6, 7          Page 20      of  31 Event
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior SG(s):
* AB HIS-9 (SG A)
: f. CHECK if C-9 interlocks - LIT Cue:
When Logic Channel Toggle Switches are placed in OFF during the next step, the associated FAIL light comes ON (Back Board Mockup)
: g. CLOSE MSIV and MSIV Bypass valve from ruptured SG(s):
* CLOSE ruptured SG(s) MSIV (preferred order):
* FAST CLOSE using EOP Addendum 35, MSIV Fast Closure, at MSFIS cabinets SA075A and SA075B OR
* CLOSE all MSIV Bypass valves (preferred order):
* USE Main Steamline Isolation Bypass Valves Controller AB HIK-15 OR
* Locally ISOLATE MSIV Bypass valve(s) as necessary CREW        CHECK Ruptured SG(s) Level:
: a. Narrow range level - GREATER THAN 7% [25%]
Stop Feed flow to the ruptured SG
* Close MDAFP flow control valve AL-HK-7A
* Close TDAFP flow control valve AL-HK-8A


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 13 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  Indications Available:
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     3     Event #     5, 6, 7         Page 21      of  31 Event
PRESSURI ZER LOW L EVEL DEVI ATION Ann unciator 32C PRESSURI ZER PRESSURE L O W HEATERS ON Annunc iator 33C RO Determines PZR level dropping rapid l y. SRO Directs Reactor Trip an d Safety Injection actuat ion. RO CHEC K Re actor Trip:
Rod Bottom Lights - ALL LIT    Reactor Trip and Bypass Breakers -
OPEN    Neutron Flux - LOWERI NG    BOP CHECK Turbine Trip:
: a. All Turbine Stop valves
- CLOSED    CREW CHECK Po wer To AC Emergency Buses:    RO/B OP a. AC emerge ncy buses - AT LEAST ONE E N E R GIZED    NB01    O R    NB02      b. AC emerge ncy buses -
BOTH ENERGIZED C H E C K S I S t a t u s:
Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 14 of 31           Event Descri p ti on: SGT R;  Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  RO a. CHECK if SI is actuated:
Any SI annu nciator 88A through 88D - LIT O R    SB069 SI Actuate RED light - LIT O R    LOCA Sequ encer annun ciators 30A or 31A - LIT RO b. CHECK bot h Trains of SI - ACTUATED LOCA Sequ encer annun ciator 30A -
LIT    LOCA Sequ encer annun ciator 31A -
LIT    SB069 SI Actuate RED light - LIT S O LID (NOT blinking)
BOP PERF O RM Attachment A, Automati c Action Ver i fication, while continuing w i th this pro c edure. BOP CHECK Ge nerator Output Breakers - OPEN MA ZL-3A (V55)
MA ZL-4A (V53)
BOP CHECK Fee dwater Isola t ion:    BOP a. Main Feedwater Pumps - TRIPPED Annunciator 120A, MFP A Trip - LIT Annunciator 123A, MFP B Trip - LIT BOP b. Main Feedwater Reg Valves - CLOSED AE ZL-510 (SG A)
AE ZL 520 (SG B)
AE ZL 530 (SG C)


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 15 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    AE ZL 540 (SG D)
== Description:==
BOP c. Main Feedwater Reg Bypass Valves - CLOSED AE ZL-550 (SG A)
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior CHECK Ruptured SG(s) Pressure - GREATER THAN 340 BOP PSIG BOP      INITIATE RCS Cooldown:
AE ZL 560 (SG B)
: a. CHECK RCS pressure - LESS THAN 1970 PSIG
AE ZL 570 (SG C)
* P-11 light - LIT
AE ZL 580 (SG D)
: b. BLOCK Steamline Pressure SI:
BOP d. Feedwater Isolation valves - CLOSED AE HIS-39 (S G A)    AE HIS-40 (S G B)    AE HIS-41 (S G C)    AE HIS-42 (S G D)     BOP CHECK AF W Pumps:     a. MD AFW Pumps - BOT H RUNNING    AL HIS-23A    AL-HIS-22A
* SB HS-9
: b. TD AFW Pu mps - RUNNING IF NE CESS ARY    BOP CHECK AF W Valves - PROPER E M ERGE NCY ALIGNME N T    MD AF P Flow Control Valves - THROTTLED AL HK-7A    AL HK-9A    AL HK-11A    AL HK-5A    TD AFP Flow Control Valves - FULL OPEN
* SB-HS-10 CRITICAL TASK            CREW        c. DETERMINE required core exit temperature: (variable)
: d. DUMP steam to condenser from intact SG(s) at maximum BOP rate:
: 1. CHECK condenser - AVAILABLE
* C-9 interlocks - LIT
* MSIVs - ANY OPEN
: 2. PLACE Steam Header Pressure Controller in MANUAL and ZERO OUTPUT:
* AB PK-507
: 3. PLACE Steam Dump Select switch in STM PRESS position:
* AB US-500Z
: 4. ADJUST Steam Header Pressure Controller in STM PRESS mode to achieve maximum cooldown rate:


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 16 of 31          Event Descri p ti on: SGT R;  Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    AL HK-8A   AL HK-10A    AL HK-12A    AL HK-6A    BOP CHECK Tot al AFW Flow - GREAT E R THAN 3 00,00 LBM/
Appendix D                               Operator Action                                Form ES-D-2 Op Test No.:       1     Scenario #    3      Event #     5, 6, 7           Page 22      of  31 Event
HR    RO CHECK PZ R PORVs and Spray Va lves:     a. PZR PORV s - CLOSE D    BB HIS-455 A    BB-HIS-456 A      b. PZR PORV s - BOTH I N AUT O    BB HIS-455 A    BB-HIS-456 A     c. PORV Block Valves - BOTH OPEN (NO)    BB HIS-800 0A (Closed)
BB-HIS-800 0A      d. Normal PZR Spray Valves - CLOSE D    BB ZL-455A    BB-ZL-456A RO CHECK If RCPs Should Be Stopped:
: a. RCPs - AN Y RUN NIN G Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 17 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    b. ECCS Pumps - AT LEAST ON E R UNNI NG    CCP    O R    SI Pump      c. RCS pressure - LESS T H AN 1425 PSIG RO CHECK RCS Temperat ures:    Any RCP ru nning - RCS TAVG ST ABLE AT 55 7°F OR TRENDI NG TO 557°F    RO CHECK If Any SG Is Fa ulted:      a. CHECK pressures in all SGs:    ANY S G PRESSURE L O WERI NG I N AN UNC ONT R OLLED MA NNER (N O)    O R    ANY S G COMPLETEL Y DEPRESS URIZED    RO CHECK If SG Tubes Are Intact:
Levels in all SGs:    NO S G NA RROW RAN G E LEV E L RISIN G IN AN UNC ONT R OLLED MA NNER    SG Stea mline N16 radiation - NORMAL N16 161 (SGA)
N16 162 (SGB)
N16 163 (SGC)
N16 164 (SGD)
Condenser Air Remo val radiation -
NORMAL BEFORE ISOLATI O N    GEG 925 Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 18 of 31           Event Descri p ti on: SGT R;  Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    SG Blowdo wn and Sample radiation
- NORMAL BEFORE ISOLATI O N    BML 256    SJL 026    SG AS D rad i ation - NORMAL AB RIC 111 (SG A) (NO)
AB RIC 112 (SG B)    AB RIC 113 (SG C)    AB RIC 114 (SG D)    Turbine Driven Auxiliary Feedwater Pump Exha ust Radiation -
NORMAL    FC RIC 385 SRO Go To E-3, Steam Gen e rator Tube Rupture, Step 1 RO CHECK If RCPs Should Be Stopped:
: a. RCPs - AN Y RUN NIN G      b. ECCS pu mp s - AT LEAST ONE RUNNING CCP    O R    SI Pump      c. RCS pressure - LESS T H AN 1425 PSIG CREW IDENTIFY Ruptured SG(s):
Unexpected rise in any SG narrow range level ("A" SG)
O R    High radiation from any SG sample


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 19 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    O R    High radiation from any SG steamline O R    High radiation from any SG Blowdo wn line sample CRITIC A L TA S K BOP ISOLATE Fl ow From Ruptured SG(s):
== Description:==
: a. ADJUST ru ptured SG(s) ASD con troller setpoint to 1160 PSIG:
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior
AB PIC-1 A (SG A)      b. CHEC K rup t ured SG(s)
* AB PK-507
ADS - CL OSED    AB PIC-1 A (SG A)    BOP IF SG ASD i s NOT clos ed, THEN PLACE SG ASD controll er in MANUAL and CLOSE SGT ASD.
: e. Core exit TCs - LESS THAN REQUIRED RO TEMPERATURE BOP       f. STOP RCS cooldown
: c. Locall y CL OSE TDAF P Steam Su ppl y From Main Steam Loop Manual Isolation valve from ruptured SG(s):   ABV0085 (SG B)
: g. MAINTAIN core exit TCs - LESS THAN REQUIRED BOP TEMPERATURE BOP      CHECK Intact SG Levels:
ABV0087 (SG C)
: a. Narrow range levels - GREATER THAN 7% [25%]
: d. CHECK SG Blow do wn and Sample Isolation valves from ruptured SG(s) -
: b. CONTROL feed flow to maintain narrow range levels between 27% and 50%
CLOSED    Blow do wn Containment Isolation Valve:
RO        CHECK PZR PORVs And Block Valves:
BM HI S-1A (SG A)    Upper Sam p le Inner Containment Isolation valve:
: a. Power to Block Valves - AVAILABLE
BM HI S-19 (S G A)      e. CLOSE Ste a mline Lo w Point Drai n valve from ruptured
* BB HIS 8000A
* BB HIS 8000B
: b. PZR PORVs - CLOSED
* BB HIS 455A
* BB HIS 456B
: c. Block Valves - AT LEAST ONE OPEN
* BB HIS 8000A
* BB HIS 8000B


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 20 of 31           Event Descri p ti on: SGT R;  Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  SG(s):    AB HIS-9 (S G A)      f. CHECK if C-9 interlocks - LIT Cue: When Logic Channel Toggle Sw i t ches are placed in OFF during the next step, the associated FAIL light comes ON (Back Board Mockup)    g. CLOSE MSI V and MSIV By pass val ve from ruptured SG(s):    CLOSE rup t ured SG(s) MSIV (preferred order):
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     3     Event #       5, 6, 7         Page 23      of 31 Event
FAST CL OSE using EOP Addend um 35, MSI V Fast Closure, at MSFIS cabinets SA075A and SA075B      O R    CLOSE all MSIV By pa ss valves (preferred order):    USE Main Steamline Isolation By p ass Valves Controller AB HIK-15      O R    Locall y ISOLATE MSIV By pass val ve(s) as necessary    CREW CHECK Ru ptured SG(s) Level:
: a. Narrow rang e level - GREATER T H AN 7% [25%]
Stop Feed flow to the ruptured SG  Close MDAFP flow control valve AL-HK-7A  Close TDAFP flow control valve AL-HK-8A


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 21 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  BOP CHECK Ru ptured SG(s) Pressure -
== Description:==
GREAT ER THAN 340 PSIG    BOP INITIATE RCS Cooldown:
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior RO        RESET SI:
: a. CHECK RCS pressure
* SB HS-42A
- LESS THAN 1970 PSIG P-11 light -
* SB HS-43A RO        RESET Containment Isolation Phase A and Phase B
LIT      b. BLOCK Ste a mline Pressure SI:
* Phase A (CISA):
SB HS-9    SB-HS-10 CRITIC A L TA S K CREW c. DETERMINE required core exit temperature: (variable)
* SB HS-53
BOP d. DUMP steam to condenser from intact SG(s) at maxi mum rate:       1. CHECK condenser - AVAILABLE C-9 interlocks - LIT MSIVs - ANY OPE N      2. PLACE Ste a m Header Pressure Controller in MANUAL and ZERO OUTPUT:   AB PK-507      3. PLACE Ste a m Du mp S e lect switch in STM PRE SS position:
* SB HS-56
AB US-500 Z      4. ADJUST St eam Header Pressure Controller in STM PRESS mo de to achieve maxi mum cooldown rate:
* Phase B (CISB):
* SB HS-52
* SB HS-55 RO        ESTABLISH Instrument Air To Containment:
: a. CHECK if ESW To Air Compressor valves - OPEN
* EF HIS-43
* EF HIS-44
: b. START Air Compressor(s):
* KA HIS-3C
* KA HIS-2C
: c. OPEN Instrument Air Supply Containment Isolation valve:
* KA HIS-29 (will not open)
PERFORM the following:
IF valve CANNOT be opened, THEN locally OPEN valve.
(2000 Aux South piping pen room, P-30) (Will NOT open)


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 22 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    AB PK-507    RO e. Core exit TCs - LESS THAN R E QUIRED TEMP ERAT URE    B O P f. STOP R C S cooldo w n    BOP g. MAINT A IN core exit TCs - LESS THAN R E QUIRED TEMP ERAT URE    BOP CHECK Intact SG Level s:      a. Narrow rang e levels - GREATER T H AN 7% [25%]      b. CONT ROL f eed flow to maintain narrow range levels between 27% and 50%
Appendix D                               Operator Action                                Form ES-D-2 Op Test No.:       1     Scenario #   3     Event #     5, 6, 7           Page 24      of  31 Event
RO CHEC K PZ R PORVs A nd Block Valves:
: a. Power to Block Valves - AVAILABL E    BB HIS 800 0A    BB HIS 800 0B      b. PZR PORV s - CLOSED BB HIS 455 A    BB HIS 456 B      c. Block Valves - AT LEAST ONE OP EN    BB HIS 800 0A    BB HIS 800 0B Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 23 of 31           Event Descri p ti on: SGT R;  Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r      R O R E S E T S I:    SB HS-42A    SB HS-43A    RO RESET Containment Isolation Phase A and Phase B Phase A (CISA):
SB HS-53    SB HS-56    Phase B (CISB):
SB HS-52    SB HS-55    RO ESTABLISH Instrument Air To Containment:
: a. CHECK if ESW To Air Compressor valves - OPEN EF HIS-43    EF HIS-44      b. START Air C o m p r e s s o r (s):    KA HIS-3C    KA HIS-2C      c. OPEN Instrument Air Supply Containment Isolation valve:
KA HIS-29 (w i ll not ope n)      PERF O RM the following:
IF valve CANNOT be o pened, THEN locally OPEN val v e.  (2000 Aux South piping pen room, P-30) (Will NOT open)


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 24 of 31          Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  RO CHECK If RHR Pu mps Should Be Stopped:
== Description:==
: a. RHR Pu mps - ANY RU NNIN G WIT H SUCTI O N ALIGNE D TO RWST     b. RCS pressure - GREAT ER THAN 3 25 PSIG     c. STOP RHR Pumps and PLACE in standby:
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                        Applicants Actions or Behavior RO       CHECK If RHR Pumps Should Be Stopped:
EJ HIS-1   EJ HIS-2     d. MONITOR R C S p r e s s u r e    BOP CHECK If RCS Cooldown Should Be Stopped:
: a. RHR Pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST
: a. Core exit TCs - LESS THAN REQUIRED T E MPERAT URE    b. STOP R C S c o o l d o w n    CREW c. MAINT A IN  core exit TCs - LESS THAN R E QUIRED TEMP ERAT URE    BOP CHECK Ru ptured SG(s) Pressure - STABLE OR RISING RO CHECK RCS Subcoolin g - GREAT ER THAN 5 0°F     DEPRESSURIZE RCS To minimize Break Flow And Refill PZR:     a. Normal PZR spray - AV AILABLE (NO)  
: b. RCS pressure - GREATER THAN 325 PSIG
: c. STOP RHR Pumps and PLACE in standby:
* EJ HIS-1
* EJ HIS-2
: d. MONITOR RCS pressure BOP       CHECK If RCS Cooldown Should Be Stopped:
: a. Core exit TCs - LESS THAN REQUIRED TEMPERATURE
: b. STOP RCS cooldown
: c. MAINTAIN core exit TCs - LESS THAN REQUIRED CREW TEMPERATURE BOP       CHECK Ruptured SG(s) Pressure - STABLE OR RISING RO       CHECK RCS Subcooling - GREATER THAN 50°F DEPRESSURIZE RCS To minimize Break Flow And Refill PZR:
: a. Normal PZR spray - AVAILABLE (NO)


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 25 of 31           Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r  RO DEPRESS URIZE RCS Using PZR PORV To Minimize Break Flow And Refill PZR:
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     3     Event #       5, 6, 7         Page 25     of 31 Event
: a. PZR PORV - AT LEAST ONE A VAIL ABLE    BB HIS-455 A    O R    BB HIS-456 A      b. OPEN one PZR PORV until any of the following conditions satisfied:   Both of the following:
 
: 1. RCS pressure - LESS T H AN RUPT URED SG(s) PRES SURE    2. PZR level - GREATER THAN 9% [2 9%]   O R    PZR level - GREATER THAN 74% [
== Description:==
64%]   O R    RCS subcooling LESS THAN 30°F
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                          Applicants Actions or Behavior DEPRESSURIZE RCS Using PZR PORV To Minimize Break RO Flow And Refill PZR:
: c. CLOS E PZ R PORV:   BB HIS-455 A    BB HIS-456 A    RO CHEC K RC S Pressure - RISING CREW CHECK If ECCS Flow Should Be Terminated:
: a. PZR PORV - AT LEAST ONE AVAILABLE
* BB HIS-455A OR
* BB HIS-456A
: b. OPEN one PZR PORV until any of the following conditions satisfied:
* Both of the following:
: 1. RCS pressure - LESS THAN RUPTURED SG(s)
PRESSURE
: 2. PZR level - GREATER THAN 9% [29%]
OR
* PZR level - GREATER THAN 74% [64%]
OR
* RCS subcooling LESS THAN 30°F
: c. CLOSE PZR PORV:
* BB HIS-455A
* BB HIS-456A RO       CHECK RCS Pressure - RISING CREW       CHECK If ECCS Flow Should Be Terminated:
: a. RCS subcooling - GREATER THAN 30°f
: a. RCS subcooling - GREATER THAN 30°f
: b. Secondary heat sink:  
: b. Secondary heat sink:


Appe ndi x D Operator Actio n F o rm ES-D-2 Op T e st No.: 1 Scenar io # 3 Ev ent # 5, 6, 7 Page 26 of 31           Event Descri p ti on: SGT R; Reactor T r ip Requ ired , ADV F a ils Open, IA to C T MT F a ils Clos ed  T i me Positio n Appl icant's Acti ons or Beh a vi o r    Narrow rang e level in at least one int a ct SG - GREATER THAN 7% [2 5%]     O R    Total feed flow to SG(s)  
Appendix D                                 Operator Action                              Form ES-D-2 Op Test No.:       1     Scenario #     3     Event #       5, 6, 7         Page 26     of 31 Event
- GREAT ER THAN 30 0,000 LBM/HR     c. RCS pressure - STABL E OR RISING     d. PZR level - GREATER THAN 9% [2 9%]     RO STOP ECCS Pumps An d Place In Standby:
 
== Description:==
SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time          Position                          Applicants Actions or Behavior
* Narrow range level in at least one intact SG -
GREATER THAN 7% [25%]
OR
* Total feed flow to SG(s) - GREATER THAN 300,000 LBM/HR
: c. RCS pressure - STABLE OR RISING
: d. PZR level - GREATER THAN 9% [29%]
RO       STOP ECCS Pumps And Place In Standby:
: a. Both SI Pumps:
: a. Both SI Pumps:
EM HI S-4   EM HI S-5     b. All but one CCP:   BG HIS-1 A    O R    BG HIS-2 A    Scenario ma y be termi nated w hen ECCS pum ps are stopped, or at Lead Examiner's discretion w hen all cri t ical tasks have been met.  
* EM HIS-4
* EM HIS-5
: b. All but one CCP:
* BG HIS-1A OR
* BG HIS-2A Scenario may be terminated when ECCS pumps are stopped, or at Lead Examiners discretion when all critical tasks have been met.
 
ATTACHMENT A Automatic Action Verification BOP CHECK Charging Pumps:
BOP a. CCPs - BOTH RUNNING
* BG HIS-1A
* BG HIS-2A BOP b. STOP NCP:
* BG HIS-3 BOP CHECK SI And RHR Pumps
* SI Pumps - BOTH RUNNING
* EM HIS-4
* EM HIS-5
* RHR Pumps - BOTH RUNNING
* EJ HIS-1
* EJ HIS-2 BOP CHECK ECCS Flow:
BOP a. CCPs to Boron Inj Header - FLOW INDICATED
* EM FI-917A
* EM FI-917B BOP b. RCS pressure - LESS THAN 1700 PSIG BOP c. SI Pump Discharge - FLOW INDICATED
* EM FI-918
* EM FI-922 BOP d. RCS pressure - LESS THAN 325 PSIG BOP e. RHR To Accumulator Injection Loop - FLOW INDICATED


ATTAC H MENT A Automatic Action Veri fication    BOP CHECK Ch arging Pumps:
ATTACHMENT A Automatic Action Verification
BOP a. CCPs - BOTH RUN NIN G    BG HIS-1 A    BG HIS-2 A    B O P b. S T O P NCP:   BG HIS-3    BOP CHEC K SI And RHR P u mps    SI Pumps -
* EJ FI-618
BOTH RUN NING    EM HI S-4    EM HI S-5    RHR Pu mps - BOTH R UNNI NG    EJ HIS-1    EJ HIS-2    BOP CHECK ECCS Flow:
* EJ FI-619 CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
BOP a. CCPs to Boron Inj Header - FLOW INDICAT E D    EM FI-917A    EM FI-917B    BOP b. RCS pressure - LESS T H AN 1700 PSIG BOP c. SI Pump Dis c harge - FL OW INDI CATED    EM FI-918    EM FI-922    BOP d. RCS pressure - LESS T H AN 325 PSIG BOP e. RHR To Acc u mulator Injection Loop
BOP       CHECK ESW Pumps - BOTH RUNNING
- FLOW INDICATED
* EF HIS-55A
* EF HIS-56A BOP        CHECK CCW Alignment:
BOP       a. CCW Pumps - ONE RUNNING IN EACH TRAIN
* Red Train:
* EG HIS-21 or EG HIS-23
* Yellow Train
* EG HIS-22 or EG HIS-24
: b. CCW Service Loop Supply and Return valves for one BOP operating CCW pump - OPEN
* EG ZL-15 AND EG ZL-53 OR
* EG ZL-16 AND EG ZL-54 CHECK Containment Cooler Fans - RUNNING IN SLOW BOP SPEED
* GN HIS-9
* GN HIS-17
* GN HIS-5
* GN HIS-13 CHECK Containment Hydrogen Mixing Fans - RUNNING IN BOP SLOW SPEED
* GN HIS-2


ATTAC H MENT A Automatic Action Veri fication    EJ FI-618    EJ FI-619    CAUTI O N: If offsite pow er is lost after SI res e t, manual action ma y be required to restart s a feguards equipment.
ATTACHMENT A Automatic Action Verification
BOP CHECK ES W Pumps - BOTH RUNNING    EF HIS-55A    EF HIS-56A    BOP CHEC K CC W Alignment:
* GN HIS-4
BOP a. CCW Pu mp s - ONE RU NNIN G IN E A CH TR AIN    Red Train:    EG HIS-21 or EG HIS-2 3    Yellow Train    EG HIS-22 or EG HIS-2 4     BOP b. CCW Service Loop Supply and Return valves for one operating CCW pump -
* GN HIS-1
OPEN    EG ZL-15 AND EG ZL-53 O R    EG ZL-16 AND EG ZL-54 BOP CHECK Co ntainment Cooler Fans -
* GN HIS-3 BOP CHECK If Containment Spray Should Be Actuated:
RUNNING I N SLOW SPEE D    GN HI S-9    GN HI S-17    GN HI S-5    GN HI S-13    BOP CHECK Co ntainment Hydrogen Mi xing Fans -
RUNNING I N SLOW SP E E D    GN HI S-2 ATTAC H MENT A Automatic Action Veri fication    GN HI S-4    GN HI S-1    GN HI S-3     BOP CHECK If Containment Spray Shoul d Be Actuated:
BOP a. CHECK the following:
BOP a. CHECK the following:
Containmen t pressure -
* Containment pressure - GREATER THAN 27 PSIG OR
GREATER THAN 27 PSIG O R    GN PR-934 indicates co ntainment pressure - HAS BEEN GRE A TER THA N 27 PSIG     O R    Annunciator 59A CSAS - LIT     O R    Annunciator 59B CISB -
* GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR
LIT     BOP b. Containmen t Spray Pu mps - BOTH RUNNING   EN HIS-3   EN HIS-9     BOP c. ESFAS stat us panels C SAS sections:
* Annunciator 59A CSAS - LIT OR
SA066 X W H ITE lights  
* Annunciator 59B CISB - LIT BOP b. Containment Spray Pumps - BOTH RUNNING
- ALL LIT SA066Y W H ITE lights  
* EN HIS-3
- ALL LIT BOP d. ESFAS stat us panels CI SB sections:
* EN HIS-9 BOP c. ESFAS status panels CSAS sections:
SA066 X W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT SA066Y W H ITE lights  
* SA066Y WHITE lights - ALL LIT BOP d. ESFAS status panels CISB sections:
- ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:
* SA066X WHITE lights - ALL LIT
* SA066Y WHITE lights - ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:
BOP a. CHECK for any of the following:
BOP a. CHECK for any of the following:
Containmen t pressure -
* Containment pressure - GREATER THAN 17 PSIG OR
GREATER THAN 17 PSIG O R ATTAC H MENT A Automatic Action Veri fication    GN PR-934 indicates co ntainment pressure - HAS BEEN GRE A TER THA N 17 PSIG     O R    Steamline pressure - LESS THAN 615 PSIG     O R    AB PR-514 or PR-535 indicates ste a mline pressure -
 
HAS BEEN LESS THAN 615 PSIG BOP b. CHECK MSI V s and Byp a ss valves - CLOSED BOP CHECK ECCS Valves -
ATTACHMENT A Automatic Action Verification
PROP ER E M ERGE NCY ALIGNME N T    BOP a. ESFAS stat us panels SI S sections:
* GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 17 PSIG OR
SA066 X W H ITE lights  
* Steamline pressure - LESS THAN 615 PSIG OR
- ALL LIT SA066Y W H ITE lights  
* AB PR-514 or PR-535 indicates steamline pressure -
- ALL LIT BOP CHECK Co ntainment Isolation Phase A:
HAS BEEN LESS THAN 615 PSIG BOP       b. CHECK MSIVs and Bypass valves - CLOSED BOP       CHECK ECCS Valves - PROPER EMERGENCY ALIGNMENT BOP       a. ESFAS status panels SIS sections:
BOP a. ESFAS stat us panels CI SA sections:
* SA066X WHITE lights - ALL LIT
SA066 X W H ITE lights  
* SA066Y WHITE lights - ALL LIT BOP       CHECK Containment Isolation Phase A:
- ALL LIT SA066Y W H ITE lights  
BOP       a. ESFAS status panels CISA sections:
- ALL LIT BOP CHECK SG Blowdown Isolation:
* SA066X WHITE lights - ALL LIT
BOP ESFAS stat us panels S G BSIS sections:
* SA066Y WHITE lights - ALL LIT BOP       CHECK SG Blowdown Isolation:
SA066 X W H ITE lights  
BOP       ESFAS status panels SGBSIS sections:
- ALL LIT SA066Y W H ITE lights  
* SA066X WHITE lights - ALL LIT
- ALL LIT CAUTI O N: If offsite pow er is lost after SI res e t, manual action ma y be required to restart s a feguards equipment.
* SA066Y WHITE lights - ALL LIT CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
BOP CHECK Bot h Trains of control Room Ventilation I s olation:     BOP a. ESFAS stat us panels C R VIS sections:  
BOP       CHECK Both Trains of control Room Ventilation Isolation:
BOP       a. ESFAS status panels CRVIS sections:


ATTACHMENT A Automatic Action Verification SA066X WHITE lights - ALL LIT SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:
ATTACHMENT A Automatic Action Verification
* SA066X WHITE lights - ALL LIT
* SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:
BOP a. ESFAS status panels CPIS sections:
BOP a. ESFAS status panels CPIS sections:
SA066X WHITE lights - ALL LIT SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
* SA066X WHITE lights - ALL LIT
Manual actions taken Failed Equipment Attachment A, Automatic Action Verification, completed  
* SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
* Manual actions taken
* Failed Equipment
* Attachment A, Automatic Action Verification, completed


Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
Appendix C                                   Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                  Task No.:
: Determine t he volume a nd RMCS controls sett ings for raising RWST level. JPM No.: 2005 NRC RO/SRO A1-2     K/A Referen c e: 2.1.25 (2.8)
Task
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
 
Date: Method of testing:
==Title:==
This J P M can be performed in an y settin g with the required references available.
Determine the volume and RMCS             JPM No.:     2005 NRC RO/SRO controls settings for raising RWST                    A1-2 level.
Simulated Performance:
K/A  
Actual Performance:
 
X C l a s s r o o m X S i m u l a t o r  P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: The unit is coming out of a refueling outage. A significa nt leak occurred during th e refuel pool draindown process. RWST level is 92%. RWST Boro n Concentration is 2375 PPM. BAST concentration is 7000 ppm Task Stand ard: Volume addition and con t rols sett ing s within the specified ra nge. Required Materials: Straight Edge Calculator General  
==Reference:==
2.1.25 (2.8)
Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing: This JPM can be performed in any setting with the required references available.
Simulated Performance:                                       Actual Performance:       X Classroom          X     Simulator            Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
* The unit is coming out of a refueling outage.
* A significant leak occurred during the refuel pool draindown process.
* RWST level is 92%.
* RWST Boron Concentration is 2375 PPM.
* BAST concentration is 7000 ppm Task Standard:             Volume addition and controls settings within the specified range.
Required Materials:
* Straight Edge
* Calculator General  


==References:==
==References:==
OTN-BG-00002, REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM, Rev. 020 Handouts:
* OTN-BG-0002
* RWST Level/Volume Curve Initiating Cue:            You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM Time Critical Task:        No Validation Time:            10 Minutes NUREG 1021, Revision 9, Supplement 1
Appendix C  Job Performance Measure              Form ES-C-1 Worksheet SIMULATOR SETUP N/A NUREG 1021, Revision 9, Supplement 1
Appendix C                                    Page 3 of 6                    Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a )
Evaluator Note:            There is no required sequence of steps. The candidate may first refer to OTN-BG-00002.
Performance Step: 1        Determine the volume to be added.
Standard:                  Refers to RWST Level/Volume Curve and determines  23,500 gallons but  25,500 must be added.
Comment:
Evaluator Cue:              Provide a copy of the RWST Level/Volume Curve if the book is not available where the JPM is performed or the existing document cannot be marked.
Performance Step: 2        Locate/review the applicable procedure.
Standard:                  Locates OTN-BG-00002 and determines that Section 5.5 -
MANUAL MODE OF RMCS OPERATION applies.
Comment:
Evaluator Cue:              Provide OTN-BG-00002, Section 5.5.
NUREG 1021, Revision 9, Supplement 1


OTN-BG-00 002, REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM, Re
Appendix C                             Page 4 of 6                           Form ES-C-1 PERFORMANCE INFORMATION Procedure NOTES
: v. 0 20  Handouts:  OTN-BG-00 02  RWST Leve l/Volume Cu rve    Initiating Cu e: You have b een directed to determine the volume addition re quired to establish th e RWST level to 98% an d the Reactor Makeup Control System settings to maintain RWST boron concen tration at it's current value with a makeup flow rate of 90 GPM Time Critical Task:
* If the makeup water is to be blended for use somewhere preceding the step:        other than the Chemical and Volume Control System, ensure that the VCT level is sufficient for expected plant operating conditions.
No  Validation Time:
* If makeup is required to the Spent Fuel Pool refer to OTN-EC-00001 Performance Step: 3 Determine the desired boric acid and makeup water flow rates, for blended flow using Figure 7-2.
10 Minutes NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP  N/A  NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 3 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Critical Steps with a )  Evaluator Note:
Standard:           Refers to Figure 7-2 and determines by interpolation:
There is no required sequence of steps. The candidate ma y first refer to OTN-BG-00002.
* Boric Acid flow =30.54 GPM.
Performanc e Step: 1 Determine t he volume t o be added.
* Makeup Water flow = 59.46 GPM Evaluator Cue:     Assume that adequate supply capacity is available to perform the evolution.
S t a n d a r d: Refers to RWST Level/Volume Curve and determines  23,500 gallons but  25,500 mu st be added.
Performance Step: 4 Determines RMCS settings based upon required blended flow rates Standard:           Refers to Figure 7-2 and determines:
C o m m e n t:  Evaluator Cue:
* Boric Acid flow BG-FK-111 potentiometer setting 5.63.
Provide a cop y of the RWST Level/Volume Curve if the book is not available w here the JPM is performed or the existing document cannot be marked.
* Blended flow BG-FK-110 potentiometer setting 7.63.
Performanc e Step: 2 Locate/review the applicable proced ure. S t a n d a r d: Locates OTN-BG-0000 2 and determines that Section 5.5 -
Evaluator Cue:     Assume that adequate supply capacity is available to perform the evolution.
MAN U AL MODE OF R M CS OPE R ATION applies.      C o m m e n t:  Evaluator Cue:
Terminating Cue:       After the controls settings are determined, this JPM is complete.
Provide OT N-BG-0000 2, Section 5.5.
NUREG 1021, Revision 9, Supplement 1
NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 4 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    P r o c e d u r e N O T E S preceding the step:  If the makeup water is to be blended for use somewhere other than t he Chemical and Volume Control System, ensure that t he VCT leve l is suf f icien t for expected plant operating co nditions. If makeup is required to the Spent Fuel Pool ref e r to OTN-EC-00 001    Performanc e Step: 3 Determine t he desired b o ric acid a n d makeup water flow rates, for blended f l ow using Figure 7-2.
 
S t a n d a r d: Refers to Figure 7-2 and determines by interpolation: Boric Acid flow =30.54 GPM. Makeup Water flow = 59.46 GPM Evaluator Cue:
Appendix C                             Page 5 of 6                   Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO/SRO A1-2 Examinees Name:
Assume that adequate suppl y cap acity is available to perform the evolution.
Performanc e Step: 4 Determines RMCS settings based u pon require d blended flow rates     S t a n d a r d: Refers to Figure 7-2 and determines: Boric Acid flow BG-FK-111 potentio meter setting 5.63. Blended flo w BG-F K-110 potentiometer setting 7.63.     Evaluator Cue:
Assume that adequate suppl y cap acity is available to perform the evolution.
Terminating Cue:
After the co ntrols sett in gs are deter mined, this JPM is complete.
NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 5 of 6 Form ES-C-1 VERIFICATI O N OF COMPLETI ON    Job Performance Measure No.:
2005 NRC RO/SRO A1-2   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 945: Line 1,727:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:     NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 6 of 6 Form ES-C-1 JPM CUE S H EET    INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
The unit is coming out of a refueling outage. A significa nt leak occurred during th e refuel pool draindown process. RWST level is 92%. RWST Boro n Concentration is 2375 PPM. BAST concentration is 7000 ppm INITIATING CUE: You have b een directed to determine the volume addition re quired to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boro n concentrat i on at its current v a lue with a makeup flow rate of 90 GPM.
NUREG 1021, Revision 9, Supplement 1
NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
 
: Determine t he volume a nd RMCS controls sett ings for raising RWST level. JPM No.: 2005 NRC RO/SRO A1-2     K/A Referen c e: 2.1.25 (2.8)
Appendix C                           Page 6 of 6                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
* The unit is coming out of a refueling outage.
Date: Method of testing:
* A significant leak occurred during the refuel pool draindown process.
This J P M can be performed in an y settin g with the required references available.
* RWST level is 92%.
Simulated Performance:
* RWST Boron Concentration is 2375 PPM.
Actual Performance:
* BAST concentration is 7000 ppm INITIATING CUE:     You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM.
X C l a s s r o o m X S i m u l a t o r  P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: The unit is coming out of a refueling outage. A significa nt leak occurred during th e refuel pool draindown process. RWST level is 92%. RWST Boro n Concentration is 2375 PPM. BAST concentration is 7000 ppm Task Stand ard: Volume addition and con t rols sett ing s within the specified ra nge. Required Materials: Straight Edge Calculator General  
NUREG 1021, Revision 9, Supplement 1
 
Appendix C                                   Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                  Task No.:
Task
 
==Title:==
Determine the volume and RMCS             JPM No.:     2005 NRC RO/SRO controls settings for raising RWST                    A1-2 level.
K/A  
 
==Reference:==
2.1.25 (2.8)
Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing: This JPM can be performed in any setting with the required references available.
Simulated Performance:                                       Actual Performance:       X Classroom          X     Simulator            Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
* The unit is coming out of a refueling outage.
* A significant leak occurred during the refuel pool draindown process.
* RWST level is 92%.
* RWST Boron Concentration is 2375 PPM.
* BAST concentration is 7000 ppm Task Standard:             Volume addition and controls settings within the specified range.
Required Materials:
* Straight Edge
* Calculator General  


==References:==
==References:==
OTN-BG-00002, REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM, Rev. 020 Handouts:
* OTN-BG-0002
* RWST Level/Volume Curve Initiating Cue:            You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM Time Critical Task:        No Validation Time:            10 Minutes NUREG 1021, Revision 9, Supplement 1
Appendix C  Job Performance Measure              Form ES-C-1 Worksheet SIMULATOR SETUP N/A NUREG 1021, Revision 9, Supplement 1
Appendix C                                    Page 3 of 6                    Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a )
Evaluator Note:            There is no required sequence of steps. The candidate may first refer to OTN-BG-00002.
Performance Step: 1        Determine the volume to be added.
Standard:                  Refers to RWST Level/Volume Curve and determines  23,500 gallons but  25,500 must be added.
Comment:
Evaluator Cue:              Provide a copy of the RWST Level/Volume Curve if the book is not available where the JPM is performed or the existing document cannot be marked.
Performance Step: 2        Locate/review the applicable procedure.
Standard:                  Locates OTN-BG-00002 and determines that Section 5.5 -
MANUAL MODE OF RMCS OPERATION applies.
Comment:
Evaluator Cue:              Provide OTN-BG-00002, Section 5.5.
NUREG 1021, Revision 9, Supplement 1
Appendix C                            Page 4 of 6                          Form ES-C-1 PERFORMANCE INFORMATION Procedure NOTES
* If the makeup water is to be blended for use somewhere preceding the step:        other than the Chemical and Volume Control System, ensure that the VCT level is sufficient for expected plant operating conditions.
* If makeup is required to the Spent Fuel Pool refer to OTN-EC-00001 Performance Step: 3 Determine the desired boric acid and makeup water flow rates, for blended flow using Figure 7-2.
Standard:          Refers to Figure 7-2 and determines by interpolation:
* Boric Acid flow =30.54 GPM.
* Makeup Water flow = 59.46 GPM Evaluator Cue:      Assume that adequate supply capacity is available to perform the evolution.
Performance Step: 4 Determines RMCS settings based upon required blended flow rates Standard:          Refers to Figure 7-2 and determines:
* Boric Acid flow BG-FK-111 potentiometer setting 5.63.
* Blended flow BG-FK-110 potentiometer setting 7.63.
Evaluator Cue:      Assume that adequate supply capacity is available to perform the evolution.
Terminating Cue:      After the controls settings are determined, this JPM is complete.
NUREG 1021, Revision 9, Supplement 1


OTN-BG-00 002, REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM, Re
Appendix C                             Page 5 of 6                   Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO/SRO A1-2 Examinees Name:
: v. 0 20  Handouts:  OTN-BG-00 02  RWST Leve l/Volume Cu rve    Initiating Cu e: You have b een directed to determine the volume addition re quired to establish th e RWST level to 98% an d the Reactor Makeup Control System settings to maintain RWST boron concen tration at it's current value with a makeup flow rate of 90 GPM Time Critical Task:
No  Validation Time:
10 Minutes NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP  N/A  NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 3 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Critical Steps with a )  Evaluator Note:
There is no required sequence of steps. The candidate ma y first refer to OTN-BG-00002.
Performanc e Step: 1 Determine t he volume t o be added.
S t a n d a r d: Refers to RWST Level/Volume Curve and determines  23,500 gallons but  25,500 mu st be added.
C o m m e n t:  Evaluator Cue:
Provide a cop y of the RWST Level/Volume Curve if the book is not available w here the JPM is performed or the existing document cannot be marked.
Performanc e Step: 2 Locate/review the applicable proced ure. S t a n d a r d: Locates OTN-BG-0000 2 and determines that Section 5.5 -
MAN U AL MODE OF R M CS OPE R ATION applies.      C o m m e n t:  Evaluator Cue:
Provide OT N-BG-0000 2, Section 5.5.
NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 4 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    P r o c e d u r e N O T E S preceding the step:  If the makeup water is to be blended for use somewhere other than t he Chemical and Volume Control System, ensure that t he VCT leve l is suf f icien t for expected plant operating co nditions. If makeup is required to the Spent Fuel Pool ref e r to OTN-EC-00 001    Performanc e Step: 3 Determine t he desired b o ric acid a n d makeup water flow rates, for blended f l ow using Figure 7-2.
S t a n d a r d: Refers to Figure 7-2 and determines by interpolation:  Boric Acid flow =30.54 GPM. Makeup Water flow = 59.46 GPM Evaluator Cue:
Assume that adequate suppl y cap acity is available to perform the evolution.
Performanc e Step: 4 Determines RMCS settings based u pon require d blended flow rates    S t a n d a r d: Refers to Figure 7-2 and determines:  Boric Acid flow BG-FK-111 potentio meter setting 5.63. Blended flo w BG-F K-110 potentiometer setting 7.63.      Evaluator Cue:
Assume that adequate suppl y cap acity is available to perform the evolution.
Terminating Cue:
After the co ntrols sett in gs are deter mined, this JPM is complete.
NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 5 of 6 Form ES-C-1 VERIFICATI O N OF COMPLETI ON    Job Performance Measure No.:
2005 NRC RO/SRO A1-2   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 987: Line 1,803:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:     NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 6 of 6 Form ES-C-1 JPM CUE S H EET    INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
The unit is coming out of a refueling outage. A significa nt leak occurred during th e refuel pool draindown process. RWST level is 92%. RWST Boro n Concentration is 2375 PPM. BAST concentration is 7000 ppm INITIATING CUE: You have b een directed to determine the volume addition re quired to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boro n concentrat i on at its current v a lue with a makeup flow rate of 90 GPM.
NUREG 1021, Revision 9, Supplement 1
NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
 
Callaway Pl ant Task No.:
Appendix C                           Page 6 of 6                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Task Title
* The unit is coming out of a refueling outage.
: Determine isolation po ints for a tagging requ est JPM No.: 2005 NRC RO A2     K/A Referen c e: 2.2.13 (3.6)
* A significant leak occurred during the refuel pool draindown process.
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
* RWST level is 92%.
Date: Method of testing:
* RWST Boron Concentration is 2375 PPM.
Simulated Performance:
* BAST concentration is 7000 ppm INITIATING CUE:     You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM.
Actual Performance:
NUREG 1021, Revision 9, Supplement 1
X C l a s s r o o m X S i m u l a t o r  P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Containmen t Spray Pu mp "A" flow element EN F E-5 is leakin g on the high side ta
 
: p. A job has be en initiated t o drain the a ssociate d piping and rep a ir the flow element Task Stand ard: Tagging bou ndaries are identified to provide minimum isolation of EN FE-5   Required Materials:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway Plant                            Task No.:
ODP-ZZ-00 310, Workmen's Protection Assurance M-22BN01, M-22EN01, E-23EN01 General  
Task
 
==Title:==
Determine isolation points for a         JPM No.:     2005 NRC RO A2 tagging request K/A  
 
==Reference:==
2.2.13 (3.6)
Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom          X     Simulator            Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.
A job has been initiated to drain the associated piping and repair the flow element Task Standard:             Tagging boundaries are identified to provide minimum isolation of EN FE-5 Required Materials:         ODP-ZZ-00310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 General  


==References:==
==References:==
ODP-ZZ-0310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 Initiating Cue:            You have been directed to identify the tagging boundaries to allow work to be performed on flow element EN FE-5.
Time Critical Task:        NO Validation Time:            15 Minutes Callaway 2005 NRC RO A2                                                    NUREG 1021, Revision 9


ODP-ZZ-03 10, Workmen's Protectio n Assurance M-22BN01, M-22EN01, E-23EN01 Initiating Cu e: You have b een directed to identify t he tagging b oundaries to allow work to be performed on flow element EN FE-5.
Appendix C               Job Performance Measure         Form ES-C-1 Worksheet SIMULATOR SETUP None Required Callaway 2005 NRC RO A2                         NUREG 1021, Revision 9
Time Critical Task:
 
NO  Validation Time:
Appendix C                                   Page 3 of 6                         Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
15 Minutes Callaway 20 05 NRC R O A2  NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP   None Required Callaway 20 05 NRC R O A2 NURE G 102 1, Revision 9 Appendix C Page 3 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
START TIME:
START TI ME:         Performanc e Step: 1 Obtains required drawings S t a n d a r d: Locates prin t rack and id entifies requ ired drawings Evaluator Note:
Performance Step: 1     Obtains required drawings Standard:               Locates print rack and identifies required drawings Evaluator Note:         Isolation points may be identified in any order Comment:
Isolation points ma y b e identified in an y orde r    C o m m e n t:       Performanc e Step: 2 EN HV-1, Containment Recirc Sump Supply val v e will be cl osed  S t a n d a r d: Locates and marks EN HV-1 closed C o m m e n t:       Performanc e Step: 3 EN HV-6, Containment Spray "A" di scharge to Containment will be closed S t a n d a r d: Locates and marks EN HV-6 closed C o m m e n t:       Performanc e Step: 4 EN V-24, Recirculat ion valve to RW ST, will be closed S t a n d a r d: Locates and marks EN V-24 closed C o m m e n t:   Callaway 20 05 NRC R O A2 NURE G 102 1, Revision 9 Appendix C Page 4 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 5 BN HV-4, RWST suctio n supply to Containmen t Spray Pu mp "A", will be clo s e d  S t a n d a r d: Locates and marks BN HV-4 closed C o m m e n t:       Performanc e Step: 6 EITHER ONE of EN V-9 0 , EN V-92 or EN V-67, Containmen t Spray line drain or vent valves, will be open S t a n d a r d: Locates and marks any of EN V-90, EN V-92, or EN V-67 op en    Comment: More than 1 valve is a cceptable Performanc e Step: 7 Pump breaker may be o pened and e l ectrica lly isolated S t a n d a r d: Identifies iso l ation of Co ntainment Spray Pu mp "A" electrical circuit brea ker    Comment: Ma y also tag breakers for MOVs, but not required Terminating Cue:
Performance Step: 2     EN HV-1, Containment Recirc Sump Supply valve will be closed Standard:               Locates and marks EN HV-1 closed Comment:
When the applicant has determined the isolation boundaries for the w o r k to be performed.
Performance Step: 3     EN HV-6, Containment Spray A discharge to Containment will be closed Standard:               Locates and marks EN HV-6 closed Comment:
STOP TI ME:     Callaway 20 05 NRC R O A2 NURE G 102 1, Revision 9 Appendix C Page 5 of 6 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Performance Step: 4     EN V-24, Recirculation valve to RWST, will be closed Standard:               Locates and marks EN V-24 closed Comment:
2005 NRC RO A2   Exa m inee's Name:
Callaway 2005 NRC RO A2                                               NUREG 1021, Revision 9
 
Appendix C                               Page 4 of 6                     Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 BN HV-4, RWST suction supply to Containment Spray Pump A, will be closed Standard:           Locates and marks BN HV-4 closed Comment:
Performance Step: 6 EITHER ONE of EN V-90, EN V-92 or EN V-67, Containment Spray line drain or vent valves, will be open Standard:           Locates and marks any of EN V-90, EN V-92, or EN V-67 open Comment:           More than 1 valve is acceptable Performance Step: 7 Pump breaker may be opened and electrically isolated Standard:           Identifies isolation of Containment Spray Pump A electrical circuit breaker Comment:           May also tag breakers for MOVs, but not required Terminating Cue:       When the applicant has determined the isolation boundaries for the work to be performed.
STOP TIME:
Callaway 2005 NRC RO A2                                         NUREG 1021, Revision 9
 
Appendix C                             Page 5 of 6               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO A2 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,020: Line 1,857:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   Callaway 20 05 NRC R O A2 NURE G 102 1, Revision 9 Appendix C Page 6 of 6 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Containmen t Spray Pu mp "A" flow element EN F E-5 is leakin g on the high sid e tap. A job has be en initiated t o drain the a ssociate d piping and rep a ir the flow ele m ent    INITIATING CUE: You have b een directed to identify t he tagging b oundaries to allow work to be performed.
Callaway 2005 NRC RO A2                                 NUREG 1021, Revision 9
Callaway 20 05 NRC R O A2 NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
 
Callaway Pl ant Task No.:
Appendix C                               Page 6 of 6                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:     Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.
Task Title
A job has been initiated to drain the associated piping and repair the flow element INITIATING CUE:         You have been directed to identify the tagging boundaries to allow work to be performed.
: Review a ta gging reque st for approval JPM No.: 2005 NRC SRO A2     K/A Referen c e: 2.2.13 (3.6)
Callaway 2005 NRC RO A2                                         NUREG 1021, Revision 9
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
 
Date: Method of testing:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway Plant                            Task No.:
Simulated Performance:
Task
Actual Performance:
 
X C l a s s r o o m X S i m u l a t o r  P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Containmen t Spray Pu mp "A" flow element EN F E-5 is leakin g on the high side ta
==Title:==
: p. A job has be en initiated t o drain the a ssociate d piping and rep a ir the flow element Task Stand ard: Tagging bou ndaries are identified to provide minimum isolation of EN FE-5. WPA not approved due to 2 d e ficiencies Required Materials:
Review a tagging request for             JPM No.:   2005 NRC SRO A2 approval K/A  
ODP-ZZ-00 310, Workmen's Protection Assurance M-22BN01, M-22EN01, E-23EN01 General  
 
==Reference:==
2.2.13 (3.6)
Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom          X     Simulator            Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.
A job has been initiated to drain the associated piping and repair the flow element Task Standard:             Tagging boundaries are identified to provide minimum isolation of EN FE-5. WPA not approved due to 2 deficiencies Required Materials:         ODP-ZZ-00310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 General  


==References:==
==References:==
ODP-ZZ-0310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 Initiating Cue:            You have been directed to review the WPA for approval to allow work to be performed on flow element EN FE-5.
Time Critical Task:        NO Validation Time:            15 minutes Callaway 2005 NRC SRO A2                                                    NUREG 1021, Revision 9
Appendix C                Job Performance Measure          Form ES-C-1 Worksheet SIMULATOR SETUP None Required Callaway 2005 NRC SRO A2                          NUREG 1021, Revision 9
Appendix C                                    Page 3 of 6                        Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtains required drawings Standard:                Locates print rack and identifies required drawings Evaluator Note:          Isolation points may be identified in any order Comment:
Performance Step: 2      Reviews WPA to determine appropriate isolation points for Containment Spray Pump A flow element FE-5 Standard:                Reviews tag listing Comment:
Performance Step: 3      Determines that BN HV-4, RWST suction supply to Containment Spray Pump A must be closed and tagged Standard:                Identifies deficiency on tagging request. Local handwheel must be tagged as part of valve isolation Comment:
Performance Step: 4      Determines that Containment Spray Pump A breaker must be tagged Standard:                Identifies that the Containment Spray Pump A breaker is not tagged and requires tagging Comment:
Callaway 2005 NRC SRO A2                                              NUREG 1021, Revision 9


ODP-ZZ-03 10, Workmen's Protectio n Assurance M-22BN01, M-22EN01, E-23EN01 Initiating Cu e: You have b een directed to review the WPA for approval to allow work to be performed on flow element EN F E-5. Time Critical Task:
Appendix C                             Page 4 of 6                     Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5  Return the WPA without approval Standard:           Determines that WPA cannot be approved Comment:
NO  Validation Time:
Terminating Cue:         When the applicant has provided disposition of the WPA, this JPM is complete STOP TIME:
15 minutes Callaway 20 05 NRC S R O A2  NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP    None Required Callaway 20 05 NRC S R O A2  NURE G 102 1, Revision 9 Appendix C Page 3 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
Callaway 2005 NRC SRO A2                                   NUREG 1021, Revision 9
START TI ME:        Performanc e Step: 1 Obtains required drawings S t a n d a r d: Locates prin t rack and id entifies requ ired drawings Evaluator Note:
 
Isolation points ma y b e identified in an y orde r    C o m m e n t:        Performanc e Step: 2 Reviews W PA to determine appropriate isolat io n points for Containmen t Spray Pu mp "A" flow element FE-5 S t a n d a r d: Reviews tag listing    C o m m e n t:        Performanc e Step: 3 Determines that BN HV-4, RWST suction supp ly to Containment Spray Pu mp "A" must be closed and tagged  S t a n d a r d: Identifies de ficiency on t agging requ est. Local h andwheel must be tagged a s part of valve isolation C o m m e n t:        Performanc e Step: 4 Determines that Containment Spray Pump "A" breaker must be tagged  S t a n d a r d: Identifies th at the Containment Spray Pu mp "A" breaker is n o t tagged and requires tag g ing    C o m m e n t:    Callaway 20 05 NRC S R O A2 NURE G 102 1, Revision 9 Appendix C Page 4 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 5 Return the WPA without approval S t a n d a r d: Determines that WPA cannot be app roved    C o m m e n t:     Terminating Cue:
Appendix C                             Page 5 of 6               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO A2 Examinees Name:
When the applicant has provided disposition of the WPA, this JPM is complete   STOP TI ME:     Callaway 20 05 NRC S R O A2 NURE G 102 1, Revision 9 Appendix C Page 5 of 6 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC RO A2   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,051: Line 1,906:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   Callaway 20 05 NRC S R O A2 NURE G 102 1, Revision 9 Appendix C Page 6 of 6 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Containmen t Spray Pu mp "A" flow element EN F E-5 is leakin g on the high sid e tap. A job has be en initiated t o drain the a ssociate d piping and rep a ir the flow ele m ent    INITIATING CUE: You have b een directed to review the WPA for approval to allow work to be performed on flow element EN FE-5.
Callaway 2005 NRC SRO A2                                 NUREG 1021, Revision 9
Callaway 20 05 NRC S R O A2 NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
 
Callaway Pl ant Task No.:
Appendix C                               Page 6 of 6                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:     Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.
N/A     Task Title: Determine Maxi mum Allowable Stay Time JPM No.: 2005 NRC RO A3     K/A Referen c e: 2.3.2 (2.5)
A job has been initiated to drain the associated piping and repair the flow element INITIATING CUE:         You have been directed to review the WPA for approval to allow work to be performed on flow element EN FE-5.
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
Callaway 2005 NRC SRO A2                                         NUREG 1021, Revision 9
Date: Method of testing:
 
Simulated Performance:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway Plant                            Task No.:   N/A Task
Actual Performance:
 
X C l a s s r o o m  S i m u l a t o r  P l a n t X READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Conditions:
==Title:==
A job is being performed on RHR Pu mp "A" that r equires isolating and draining system piping.
Determine Maximum Allowable Stay         JPM No.:   2005 NRC RO A3 Time K/A  
You have b een directed to open RHR Pump "A" drain valve EJ V-148 and route a hose to the local floor dr ain  Task Stand ard: Correct RWP is selecte d and stay time identifie d as 30 minutes based upon exceeding maximum dose Required Materials:
 
RWPs, Survey Maps General  
==Reference:==
2.3.2 (2.5)
Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator            Plant        X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         A job is being performed on RHR Pump A that requires isolating and draining system piping.
You have been directed to open RHR Pump A drain valve EJ V-148 and route a hose to the local floor drain Task Standard:             Correct RWP is selected and stay time identified as 30 minutes based upon exceeding maximum dose Required Materials:         RWPs, Survey Maps General  


==References:==
==References:==
RWPs, Survey Maps Initiating Cue:            Identify the appropriate RWP for entry and determine maximum allowable stay time before a dosimeter limit is exceeded.
Time Critical Task:        NO Validation Time:            8 Minutes Callaway 2005 NRC RO/SRO A3                                                NUREG 1021, Revision 9


RWPs, Survey Maps Initiating Cu e: Identify the appropriate RWP for entry and determine ma ximum allowable st ay time befo r e a dosimeter limit is exceeded.
Appendix C                   Job Performance Measure         Form ES-C-1 Worksheet SIMULATOR SETUP None Required Callaway 2005 NRC RO/SRO A3                         NUREG 1021, Revision 9
Time Critical Task:
 
NO  Validation Time:
Appendix C                                 Page 3 of 5                         Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
8 Minutes Callaway 20 05 NRC R O/SRO A3  NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP None Required Callaway 20 05 NRC R O/SRO A3 NURE G 102 1, Revision 9 Appendix C Page 3 of 5 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
START TIME:
START TI ME:         Performanc e Step: 1 Determine RWP required for task p e rformed  S t a n d a r d: Selects RWP 500501WPA C o m m e n t:       Performanc e Step: 2 Determines stay time based upon do simeter setting S t a n d a r d: Determines dosimeter setting is 10 mr total dose and 100 mr/hr dose rate.
Performance Step: 1     Determine RWP required for task performed Standard:               Selects RWP 500501WPA Comment:
S t a n d a r d: Selects surv ey map #11 11, RHR Pu mp "A" roo m  S t a n d a r d: Determines dose rate in the area of t he work is 2 0 mr/hr S t a n d a r d: Determines maxi mum st ay time at 2 0 mr/hr is 30 minutes to avoid exceeding 10 mr total dose.
Performance Step: 2     Determines stay time based upon dosimeter setting Standard:               Determines dosimeter setting is 10 mr total dose and 100 mr/hr dose rate.
C o m m e n t:     Terminating Cue:
Standard:               Selects survey map #1111, RHR Pump A room Standard:               Determines dose rate in the area of the work is 20 mr/hr Standard:               Determines maximum stay time at 20 mr/hr is 30 minutes to avoid exceeding 10 mr total dose.
When the candidate indicates stay time for the w o rk performed, this JPM is complete   STOP TI ME:     Callaway 20 05 NRC R O/SRO A3 NURE G 102 1, Revision 9 Appendix C Page 4 of 5 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Comment:
2005 NRC RO A3   Exa m inee's Name:
Terminating Cue:             When the candidate indicates stay time for the work performed, this JPM is complete STOP TIME:
Callaway 2005 NRC RO/SRO A3                                         NUREG 1021, Revision 9
 
Appendix C                             Page 4 of 5               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO A3 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,084: Line 1,951:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   Callaway 20 05 NRC R O/SRO A3 NURE G 102 1, Revision 9 Appendix C Page 5 of 5 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
A job is being performed on RHR Pu mp "A" that r equires isolating and draining system piping.
Callaway 2005 NRC RO/SRO A3                             NUREG 1021, Revision 9
You have b een directed to open RHR Pump "A" drain valve EJ V-148 and route a hose to the local f l o o r drain     INITIATING CUE: Identify the appropriate RWP for entry and determine ma ximum allowable st ay time befo r e a dosimeter limit is exceeded.
 
Callaway 20 05 NRC R O/SRO A3 NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
Appendix C                               Page 5 of 5                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:     A job is being performed on RHR Pump A that requires isolating and draining system piping.
: Evaluate plant condition s, upgrade the emergency classif i cation and mak e a PA R. JPM No.: 2005 NRC SRO A4     K/A Referen c e: 2.4.44 (4.0)
You have been directed to open RHR Pump A drain valve EJ V-148 and route a hose to the local floor drain INITIATING CUE:         Identify the appropriate RWP for entry and determine maximum allowable stay time before a dosimeter limit is exceeded.
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
Callaway 2005 NRC RO/SRO A3                                     NUREG 1021, Revision 9
Date: Method of testing:
 
Simulated Performance:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
Actual Performance:
Task
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: A large break LOCA is in progress. Attempts to initiate Cont ainment Spray have failed. A Site Emergency was declared 20 minutes ago based on lo ss of the RCS subcooling an d radiation monitor GT-RE-59 reading 3.1E+3 R/hr. One minute ago contain m ent pressure lowered rapidly and now continues to lower at a slower rate. Wind speed is 5 Miles/Hr. Wind direction is from 218° The outside temperature is 88  
 
ûF. Task Stand ard: Upgrades classification and makes a PAR.
==Title:==
Required Materials:
Evaluate plant conditions, upgrade     JPM No.:     2005 NRC SRO A4 the emergency classification and make a PAR.
SENTRY Computer General  
K/A  
 
==Reference:==
2.4.44 (4.0)
Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator        X   Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
* A large break LOCA is in progress.
* Attempts to initiate Containment Spray have failed.
* A Site Emergency was declared 20 minutes ago based on loss of the RCS subcooling and radiation monitor GT-RE-59 reading 3.1E+3 R/hr.
* One minute ago containment pressure lowered rapidly and now continues to lower at a slower rate.
* Wind speed is 5 Miles/Hr.
* Wind direction is from 218°
* The outside temperature is 88 F.
Task Standard:             Upgrades classification and makes a PAR.
Required Materials:         SENTRY Computer General  


==References:==
==References:==
EIP-ZZ-00101, CLASSI FICATION OF EMERGENCIES, Re
* EIP-ZZ-00101, CLASSIFICATION OF EMERGENCIES, Rev.
: v. 032 EIP-ZZ-00102, EMERGENCY I M PL EMENTING ACTIONS, Rev. 034 EIP-ZZ-00212, PROTECTIVE ACTI ON RECOMMENDATI ONS, Rev. 021   Handouts:
032
EIP-ZZ-00101, EIP-ZZ-00102, EIP-ZZ-00212 Initiating Cu e: Reevaluate the Emerge ncy Classification and pe rform required follow up actions requ ired of the Emergency Coordinator.
* EIP-ZZ-00102, EMERGENCY IMPLEMENTING ACTIONS, Rev.
Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task:
034
Yes   Validation Time:
* EIP-ZZ-00212, PROTECTIVE ACTION RECOMMENDATIONS, Rev. 021 Handouts:                   EIP-ZZ-00101, EIP-ZZ-00102, EIP-ZZ-00212 Initiating Cue:             Reevaluate the Emergency Classification and perform required follow up actions required of the Emergency Coordinator.
24 Minutes Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP   N/A   JPM Setup:
Callaway SRO NRC JPM A4                                     NUREG 1021, Revision 9, Supplement 1
Ensure SENTRY Screen is called up on computer with plant 'WIND SECTOR" data d e leted, then minimize screen pr ior to JPM performance Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 4 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Critical Steps with a )   Performanc e Step: 1 Review cha nging condit i ons. S t a n d a r d: Enters EIP-ZZ-00101 Reviews Group 2 (Fission Product Barrier) EAL
 
's  Declares General Emerg ency based on uncontrolled depressurization of cont ainment. C o m m e n t:   Performanc e Step: 2 Enters EIP-ZZ-00102 S t a n d a r d: Announces GE and rea s on to contr o l room personnel.
Appendix C                     Job Performance Measure               Form ES-C-1 Worksheet Time Critical Task: Yes Validation Time:   24 Minutes Callaway SRO NRC JPM A4                     NUREG 1021, Revision 9, Supplement 1
Comment: The candidate ma y w o rk through the next several steps using EIP-ZZ-00102, ATTACHMENT 5 (flow c harted procedure steps).
 
Mark the ti me of the GE announcement: __________.
Appendix C                           Job Performance Measure               Form ES-C-1 Worksheet SIMULATOR SETUP N/A JPM Setup:
ATTACHMENT 4, OFF SITE NOTI FICATION FORM, must be provided to the communicator w i thin 15 minutes from this time. Performanc e Step: 3 Manually initiate ERFIS.
Ensure SENTRY Screen is called up on computer with plant WIND SECTOR data deleted, then minimize screen prior to JPM performance Callaway SRO NRC JPM A4                             NUREG 1021, Revision 9, Supplement 1
S t a n d a r d: Locates ERFIS button.
 
C o m m e n t:   Evaluator Cue:
Appendix C                                     Page 4 of 8                     Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a )
ERFIS w as actuated when the Site Emergenc y w as decl ared. Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 5 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Performanc e Step: 4 Notify On-site personnel S t a n d a r d: Completes ATTACH ME NT 1 Sounds plan t emergency alarm. Makes the scripted anno uncement and repeats.
Performance Step: 1       Review changing conditions.
C o m m e n t:   Evaluator Cue:
Standard:
For the purpose of examination security
* Enters EIP-ZZ-00101
, dire ct the candidate to simulate the alarm actuation and announcement.
* Reviews Group 2 (Fission Product Barrier) EALs
Performanc e Step: 5 Have SAS a c tivate the callout.
* Declares General Emergency based on uncontrolled depressurization of containment.
S t a n d a r d: Acknowledges cue.
Comment:
C o m m e n t:   Evaluator Cue:
Performance Step: 2       Enters EIP-ZZ-00102 Standard:                 Announces GE and reason to control room personnel.
SAS w as a c tivated w h en the Site Emergenc y was declared.
Comment:                   The candidate may work through the next several steps using EIP-ZZ-00102, ATTACHMENT 5 (flowcharted procedure steps).
Performanc e Step: 6 Complete the SENTRY screen or fill out ATTACHMENT 4.
Mark the time of the GE announcement: __________.
S t a n d a r d: Completes the SENTRY screen. Critical task dat a: GE Release in p r ogress  Wind speed and directio n  PAR - Evacuate 2 miles all around a nd 5 miles in downwind sectors B, C, and D C o m m e n t:   Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 6 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Performanc e Step: 7 Provide ATT A CHMENT 4 to the communicator.
ATTACHMENT 4, OFF SITE NOTIFICATION FORM, must be provided to the communicator within 15 minutes from this time.
S t a n d a r d: Provides ATTACHMENT 4 to the co mmunicator within 15 minutes after the GE declaration.
Performance Step: 3       Manually initiate ERFIS.
Comment: Mark the ti me that ATTACHMENT 4 is provided to the communicator: __________.
Standard:                 Locates ERFIS button.
Terminating Cue:
Comment:
After ATTACHMENT 4 is provided to the communicator, this JPM is com plete. Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 7 of 8 Form ES-C-1 VERIFICATI O N OF COMPLETI ON    Job Performance Measure No.:
Evaluator Cue:             ERFIS was actuated when the Site Emergency was declared.
2005 NRC SRO A4   Exa m inee's Name:
Callaway SRO NRC JPM A4                               NUREG 1021, Revision 9, Supplement 1
 
Appendix C                             Page 5 of 8                     Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Notify On-site personnel Standard:
* Completes ATTACHMENT 1
* Sounds plant emergency alarm.
* Makes the scripted announcement and repeats.
Comment:
Evaluator Cue:     For the purpose of examination security, direct the candidate to simulate the alarm actuation and announcement.
Performance Step: 5 Have SAS activate the callout.
Standard:           Acknowledges cue.
Comment:
Evaluator Cue:     SAS was activated when the Site Emergency was declared.
Performance Step: 6 Complete the SENTRY screen or fill out ATTACHMENT 4.
Standard:           Completes the SENTRY screen. Critical task data:
* GE
* Release in progress
* Wind speed and direction
* PAR - Evacuate 2 miles all around and 5 miles in downwind sectors B, C, and D Comment:
Callaway SRO NRC JPM A4                         NUREG 1021, Revision 9, Supplement 1
 
Appendix C                             Page 6 of 8                   Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Provide ATTACHMENT 4 to the communicator.
Standard:           Provides ATTACHMENT 4 to the communicator within 15 minutes after the GE declaration.
Comment:           Mark the time that ATTACHMENT 4 is provided to the communicator: __________.
Terminating Cue:       After ATTACHMENT 4 is provided to the communicator, this JPM is complete.
Callaway SRO NRC JPM A4                       NUREG 1021, Revision 9, Supplement 1
 
Appendix C                             Page 7 of 8                   Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC SRO A4 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,135: Line 2,045:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Page 8 of 8 Form ES-C-1 JPM CUE S H EET    INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
A large break LOCA is in progress. Attempts to initiate Cont ainment Spray have failed. A Site Emergency was declared 20 minutes ago based on loss of the R C S subcooling and radia t ion monitor GT-RE-59 reading 3
Callaway SRO NRC JPM A4                       NUREG 1021, Revision 9, Supplement 1
.1E+3 R/hr. One minute ago contain m ent pressure lowered rapidly and now continu e s to lower at a slower r a te. Wind speed is 5 Miles/Hr Wind direction is from 218° The outside temperature is 88  
 
ûF. INITIATING CUE: Reevaluate the Emerge ncy Classification and pe rform required follow up act i ons require d of the Emergency Coordinator.
Appendix C                               Page 8 of 8                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Callaway SRO NRC JPM A4 NUREG 102 1, Revision 9, Supplement 1 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
* A large break LOCA is in progress.
: Borate RCS During Cooldown Outside the Control Room JPM No.: 2005 NRC J P M P1     K/A Referen c e: 068 EA 1.11 3.9 / 4.1 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
* Attempts to initiate Containment Spray have failed.
Date: Method of testing:
* A Site Emergency was declared 20 minutes ago based on loss of the RCS subcooling and radiation monitor GT-RE-59 reading 3.1E+3 R/hr.
Simulated Performance:
* One minute ago containment pressure lowered rapidly and now continues to lower at a slower rate.
X Actual Performance:
* Wind speed is 5 Miles/Hr
C l a s s r o o m  S i m u l a t o r  P l a n t X READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: The control room is damaged beyond use and systems are aligned as per OTO-ZZ
* Wind direction is from 218°
-00001, Control Room Inaccessibility. The plant is shutdown with control fro m the Aux S/D Panel due to a fire.
* The outside temperature is 88 F.
The plant is in Mode 3 at normal operating temperature and pressure. Pr essurizer level is 25%, RCS boron concentration is 1000 p p m, and all shutdown and control r ods are fully inserted. C o re burnup is 295 EFPD. The "B" CCP is in service.
INITIATING CUE:         Reevaluate the Emergency Classification and perform required follow up actions required of the Emergency Coordinator.
Task Stand ard: RCS boratio n from outside the contr o l room has been completed Required Materials:
Callaway SRO NRC JPM A4                           NUREG 1021, Revision 9, Supplement 1
OTS-ZZ-00 001, Cooldown From Outside the Co ntrol Room, Revision 13 Curve Book Table 1-8 Figure 7-3 General  
 
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
Task
 
==Title:==
Borate RCS During Cooldown               JPM No.:     2005 NRC JPM P1 Outside the Control Room K/A  
 
==Reference:==
068 EA 1.11     3.9 / 4.1 Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing:
Simulated Performance:             X                         Actual Performance:
Classroom                Simulator            Plant        X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         The control room is damaged beyond use and systems are aligned as per OTO-ZZ-00001, Control Room Inaccessibility. The plant is shutdown with control from the Aux S/D Panel due to a fire. The plant is in Mode 3 at normal operating temperature and pressure. Pressurizer level is 25%, RCS boron concentration is 1000 ppm, and all shutdown and control rods are fully inserted. Core burnup is 295 EFPD. The B CCP is in service.
Task Standard:             RCS boration from outside the control room has been completed Required Materials:         OTS-ZZ-00001, Cooldown From Outside the Control Room, Revision 13 Curve Book Table 1-8 Figure 7-3 General  


==References:==
==References:==
OTS-ZZ-00001, Cooldown From Outside the Control Room, Revision 13 Initiating Cue:            You have been directed by the Shift Supervisor to perform Section 4.1 of OTS-ZZ-00001 to borate the RCS from the Boric Acid Tanks.
Time Critical Task:        NO Validation Time:            39 minutes 2005 NRC JPM P1                                                            NUREG 1021, Revision 9
Appendix C                                  Page 2 of 7                        Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtain a controlled copy of OTS-ZZ-00001, Cooldown From Outside the Control Room.
Standard:                Operator should obtain procedure copy.
Comment:
Step 2.0 Performance Step: 2      Review the Precautions and Limitations of OTS-ZZ-00001.
Standard:                Operator should review all precautions and limitations.
Comment:
Evaluators Cue:          All Precautions and Limitations are satisfied.
Performance Step: 3      Review the Initial Conditions of OTS-ZZ-00001.
Standard:                Operator should review all Initial Conditions.
Comment:
Evaluators Cue:          All Initial Conditions are satisfied.
Ask if the Operator understands the Initial Conditions and Initiating Cues.
Step 4.1 Performance Step: 4      Borate the RCS to Xenon-Free Cold Shutdown as follows.
Standard:                Operator should determine to borate the RCS to Cold Xenon-Free Shutdown.
Comment:
2005 NRC JPM P1                                                      NUREG 1021, Revision 9


OTS-ZZ-00 001, Cooldown From Outside the Co ntrol Room, Revision 13 Initiating Cu e: You have b een directed by the Shift Supervisor to perform Section 4.1 of OTS-ZZ-00 001 to borat e the RCS from the Boric Acid Tanks.
Appendix C                            Page 3 of 7                        Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.1 Performance Step: 5 Determine the required boron concentration for cold shutdown using Curve Book Table 1-8.
Time Critical Task:
Standard:          Operator should determine required boron concentration is approximately 1100 - 1200 ppm.
NO  Validation Time:
Comment:
39 minutes 2005 NRC J P M P1 NUREG 102 1, Revision 9  
Step 4.1.1.1 Performance Step: 6 Determine the number of gallons of 4 WT % boric acid from the BAT required to achieve the boron concentration in Step 4.1.1 using Figure 7-3 of the Curve Book.
Standard:          Operator should calculate 1567 +/- 200 GAL.
If nomograph is used, then 1350 - 1400 gallons will be the volume indicated 515676              7000-1000 VB                      In  (                )
8.33                7000-1150 Comment:            Nomograph indicates approximately 1350 -1400 gallons Cue:                If requested, Boric Acid Tank concentration is 7000 ppm Step 4.1.2.1 Performance Step: 7 Start a Boric Acid Transfer Pump A or B with local control switch or with the pushbutton on the associated breaker pump A(B) NG01AHF4 (NG02AAF4).
Standard:          Operator should start A or B Boric Acid Pump.
Evaluators Cue:    Direct the candidate to use the local HIS for the Boric Acid Pump Comment:
Evaluators Cue:   The Boric Acid Transfer Pump is running.
2005 NRC JPM P1                                                 NUREG 1021, Revision 9


Appendix C Page 2 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
Appendix C                             Page 4 of 7                       Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.2.2 Performance Step: 8 Open the Immediate Boration valve BGHV8104.
START TI ME:        Performanc e Step: 1 Obtain a controlled cop y of OTS-ZZ
Standard:           Operator goes to A SI Pump Room and manually OPENS BG-HV-8104.
-00001, Cooldown From Outside the Control Room.
Comment:
S t a n d a r d: Operator should obtain procedure copy.
Evaluators Cue:     BGHV8104 is OPEN.
C o m m e n t:      Step 2.0  Performanc e Step: 2 Review the Precautions and Limitations of OTS-ZZ-00001.
Step 4.1.2.3 Performance Step: 9 Monitor boric acid flow on Local Indicator BGFI183B.
S t a n d a r d: Operator should review all precautio ns and limit ations. C o m m e n t:  Evaluator's Cue:
Standard:           Operator should monitor boric acid flow on BGFI183B.
All Precauti ons and Limitations are satisfied.
Comment:             BGFI183B is outside the room Evaluators Cue:     Local Indicator shows 100 GPM.
Performanc e Step: 3 Review the I n itial Conditions of OTS-ZZ-00001.
Step 4.1.4 Performance Step: 10 Determine the boration time required by dividing the gallons of acid by the flow rate indicated.
S t a n d a r d: Operator should review all Initia l Conditions.
Standard:              1567 GAL
C o m m e n t:  Evaluator's Cue:
                                            = 16 MIN (+/- 3 MIN) 100 GPM Comment:
All Initial Conditions are satisfied.
Evaluators Cue:     The required time has elapsed.
Ask if the Operator understands the Initial Conditions and Initiating Cues.
Step 4.1.5.1 Performance Step: 11 When the required time has elapsed, stop the Boric Acid Transfer Pump.
Step 4.1  Performanc e Step: 4 Borate the RCS to X e n on-Free Cold Shutdown as follows.
Standard:           Operator should secure A or B Boric Acid Pump with the local control switch or the pushbutton on the breaker A - NG01AHF4 B - NG02AAF4 Comment:
S t a n d a r d: Operator should determine to borate the RCS to Cold X enon-Free Shutdown.
Evaluators Cue:     The Boric Acid Transfer Pump is STOPPED.
C o m m e n t:  2005 NRC J P M P1  NUREG 102 1, Revision 9 Appendix C Page 3 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.1  Performanc e Step: 5 Determine t he required boron conce n tration for cold shutdow n using Curve Book Table 1-8. S t a n d a r d: Operator should determine required boron conce n tration is approximate l y 1100 - 1200 ppm.
2005 NRC JPM P1                                                 NUREG 1021, Revision 9
C o m m e n t:      Step 4.1.1.1  Performanc e Step: 6 Determine t he number of gallons of 4 WT % boric acid from the BAT required to achieve the boron concentration in Step 4.1.
 
1 using Figure 7-3 of the Curve Book.
Appendix C                           Page 5 of 7                         Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.5.2 Performance Step: 12 CLOSE BGHV8104.
S t a n d a r d: Operator should calcu l at e 1567 +/- 200 GAL.
Standard:           Operator should CLOSE BGHV8104.
If nomograph is used, th en 1350 - 1 400 gallons will be the volume indicated 5 1 5 6 7 6 7 0 0 0-1 0 0 0    V B 8.33 In ( 7000-1150 )    Comment: Nomograp h indicates approximatel y 1350 -1 400 gallons Cue: If requested, Boric Aci d Tank concentration is 7000 ppm Step 4.1.2.1  Performanc e Step: 7 Start a Boric Acid Transf e r Pump "A" or "B" with local contro l switch or wit h the pushb utton on the associat ed breaker pu mp A(B) NG01AHF4 (NG02 AAF4). S t a n d a r d: Operator should start "A
Comment:
" or "B" Boric Acid Pump.
Evaluators Cue:     BGHV8104 is CLOSED.
Evaluator's Cue:
Step 4.1.7 Performance Step: 13 Have the RCS sampled to ensure the required SDM has been obtained.
Direct the candidate to use the local HIS for the Boric Ac id Pump  C o m m e n t:  Evaluator's Cue:
Standard:           Operator should call for Chemistry to sample RCS for boron.
The Boric Acid Transfer Pump is running.
Comment:
2005 NRC J P M P1  NUREG 102 1, Revision 9 Appendix C Page 4 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.2.2  Performanc e Step: 8 Open the Immediate Boration valve BGHV8104.
Evaluators Cue:     When called, Hot Lab Chem Tech will sample RCS for boron.
S t a n d a r d: Operator goes to "A" SI Pump Roo m and manually OPENS BG-HV-810 4. C o m m e n t:   Evaluator's Cue:
Terminating Cue:       When boration of the RCS has been performed, this JPM is complete.
BGHV8104 is OPEN.
STOP TIME:
Step 4.1.2.3 Performanc e Step: 9 Monitor boric acid flow on Local Indicator BGFI183B.
2005 NRC JPM P1                                               NUREG 1021, Revision 9
S t a n d a r d: Operator should monitor boric acid flow on BGFI 183B. Comment: BGFI183B i s outside the room Evaluator's Cue:
 
Local Indicator show s 100 GPM. Step 4.1.4 Performanc e Step: 10 Determine t he boration t i me required by dividing the gallons o f acid by the flow rate indicated.
Appendix C                             Page 6 of 7               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM P1 Examinees Name:
1567 GAL S t a n d a r d: 100 GPM = 16 MIN (+/-
3 MIN)     C o m m e n t:   Evaluator's Cue:
The required time has elapsed.
Step 4.1.5.1 Performanc e Step: 11 When the required time has elapsed , stop the B o ric Acid Transfer Pump.
S t a n d a r d: Operator should secure "A" or "B"  Boric Acid Pu mp with the local control switch or the pushbutton on t he breaker A - NG01AHF4 B - NG02AAF4 C o m m e n t:   Evaluator's Cue:
The Boric Acid Transfer Pump is STOPPED.
2005 NRC J P M P1 NUREG 102 1, Revision 9 Appendix C Page 5 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.5.2 Performanc e Step: 12 CLOSE BGHV8104.
S t a n d a r d: Operator should CLOSE BGHV8104. C o m m e n t:   Evaluator's Cue:
BGHV8104 is CLOSED.
Step 4.1.7 Performanc e Step: 13 Have the RCS sampled to ensure th e required SDM has been obtained.
S t a n d a r d: Operator should call for Chemistry t o sample RCS for boron.
C o m m e n t:   Evaluator's Cue:
When called, Hot Lab Chem Tech will sampl e RCS for b o ron. Terminating Cue:
When boration of the RCS has been performe d , this JPM is complete.
STOP TI ME:     2005 NRC J P M P1 NUREG 102 1, Revision 9 Appendix C Page 6 of 7 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC J P M P1   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,210: Line 2,146:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M P1 NUREG 102 1, Revision 9 Appendix C Page 7 of 7 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
The control room is damaged beyond use and systems are aligned as p e r OTO-ZZ-00001, Control Room In accessibility. The plant is shut down with control from the Aux S/D Panel due to a fire. The pla n t is in Mod e 3 at normal operating temperature and pressure. P r essurizer le vel is 25%, RCS boron concentratio n is 1000 ppm, and all shutd o wn and control rods ar e fully insert ed. Core burnup is 295 EFPD. The "B" CCP is in service.
2005 NRC JPM P1                                         NUREG 1021, Revision 9
INITIATING CUE: You have b een directed by the Shift Supervisor to perform Section 4.1 of OTS-ZZ-00001 to borate the RCS fro m the Boric Acid Tanks. 2005 NRC J P M P1 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
 
: Locally Close Valves for CIS-B JPM No.: 2005 NRC J P M P2     K/A Referen c e: 103 A2.03 3.5 / 3.8 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
Appendix C                           Page 7 of 7                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The control room is damaged beyond use and systems are aligned as per OTO-ZZ-00001, Control Room Inaccessibility. The plant is shutdown with control from the Aux S/D Panel due to a fire. The plant is in Mode 3 at normal operating temperature and pressure. Pressurizer level is 25%, RCS boron concentration is 1000 ppm, and all shutdown and control rods are fully inserted.
Date: Method of testing:
Core burnup is 295 EFPD. The B CCP is in service.
Simulated Performance:
INITIATING CUE:     You have been directed by the Shift Supervisor to perform Section 4.1 of OTS-ZZ-00001 to borate the RCS from the Boric Acid Tanks.
X Actual Performance:
2005 NRC JPM P1                                             NUREG 1021, Revision 9
C l a s s r o o m  S i m u l a t o r  P l a n t X READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant was at 100% power when a Loss of All AC Power occurred. T he Control Room entered emergency procedure ECA-0.0, Loss of All A C Power. A containment spray signa l has been r e ceived and require d valve positions can not be performed from the Control Room. Task Stand ard: Upon completion of this JPM, val v es associa t ed with Penetrations 74, 75, and 76 will be clo s e d or verified closed.
 
Required Materials:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                  Task No.:
None   General  
Task
 
==Title:==
Locally Close Valves for CIS-B           JPM No.:   2005 NRC JPM P2 K/A  
 
==Reference:==
103 A2.03       3.5 / 3.8 Examinee:                                                     NRC Examiner:
Facility Evaluator:                                           Date:
Method of testing:
Simulated Performance:           X                           Actual Performance:
Classroom                Simulator            Plant        X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant was at 100% power when a Loss of All AC Power occurred. The Control Room entered emergency procedure ECA-0.0, Loss of All AC Power. A containment spray signal has been received and required valve positions can not be performed from the Control Room.
Task Standard:             Upon completion of this JPM, valves associated with Penetrations 74, 75, and 76 will be closed or verified closed.
Required Materials:         None General  


==References:==
==References:==
ECA-0.0, Loss of All AC Power, Revision 5 Initiating Cue:            The Control Room supervisor has directed you to perform Local Operator Actions of Step 21B RNO (CISB Outer Containment Valves),
of ECA-0.0. Reposition any required valves and inform him when done.
Time Critical Task:        NO Validation Time:            10 minutes 2005 NRC JPM P2                                                            NUREG 1021, Revision 9
Appendix C                                      Page 2 of 9                        Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Evaluator Note: All valves will be in the normal positions as stated in the JPM Performance Step: 1          Obtain a verified working copy of ECA-0.0, Loss of All AC Power.
Standard:                    Operator should obtain ECA-0.0 copy.
Comment:
Evaluators Cue:            Provide operator with copy of ECA-0.0.
Performance Step: 2          Go to the Aux Building North Piping Penetration Room #1323.
Standard:                    Operator should go to the North Piping Penetration Room #1323.
NOTE:                        Operator should go thru HP Access.
Comment:
Performance Step: 3          Verify CLOSED EG-HV-58, CCW to RCS outer CTMT ISO.
Standard:                    Operator should demonstrate knowledge of how to verify a motor-operated valve OPEN/CLOSED.
NOTE:                        Pen 74, valves in Steps 3 through 8 can be operated in any order.
Comment:
Evaluator Cue:              EG-HV-58 is open 2005 NRC JPM P2                                                        NUREG 1021, Revision 9
Appendix C                            Page 3 of 9                        Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 CLOSE EG-HV-58, CCW to RCS Outer CTMT ISO.
Standard:          Operator should CLOSE EG-HV-58.
NOTE:              Operator should be able to describe how to CLOSE a limitorque valve.
Standard:          Valves in Steps 3 through 8 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-58 is now CLOSED.
Performance Step: 5 Verify CLOSED EG-HV-71, CCW to RCS Outer CTMT ISO.
Standard:          Operator should verify position of EG-HV-71.
NOTE:              Pen 74 Standard:          Valves in Steps 3 through 8 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-71 is OPEN.
2005 NRC JPM P2                                              NUREG 1021, Revision 9
Appendix C                            Page 4 of 9                        Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Operator should CLOSE EG-HV-71, CCW to RCS Outer CTMT ISO.
Standard:          Operator should CLOSE EG-HV-71.
NOTE:              Pen 74 Standard:          Valves in Steps 3 through 8 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-71 is now CLOSED.
Performance Step: 7 Verify CLOSED EG-HV-126, CCW to RCS CTMT Bypass.
Standard:          Operator should verify CLOSED EG-HV-126, CCW to RCS CTMT Bypass.
NOTE:              Pen 74 Standard:          Valves in Steps 3 through 8 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-126 is CLOSED.
2005 NRC JPM P2                                              NUREG 1021, Revision 9
Appendix C                            Page 5 of 9                        Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8  Verify CLOSED EG-HV-127, CCW to RCS CTMT Bypass.
Standard:            Operator should verify CLOSED EG-HV-127, CCW to RCS CTMT Bypass.
NOTE:                Pen 74 Standard:            Valves in Steps 3 through 8 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-127 is CLOSED.
Performance Step: 9  Verify CLOSED EG-HV-59, CCW from RCS Outer CTMT ISO.
Standard:            Operator should verify position of EG-HV-59.
NOTE:                Pen 75 Standard:            Valves in Steps 9 through 11 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-59 is OPEN.
Performance Step: 10 CLOSE EG-HV-59, CCW from Outer CTMT ISO.
Standard:            Operator should CLOSE EG-HV-59.
NOTE:                Pen 75 Standard:            Valves in Steps 9 through 11 can be operated in any order.
Comment:
Evaluators Cue:    EG-HV-59 is now CLOSED.
2005 NRC JPM P2                                                NUREG 1021, Revision 9


ECA-0.0, Lo ss of All AC Power, Re vision 5  Initiating Cu e: The Control Room supervisor has dir e cted you to perform Local Operator Actions of Step 21B RNO (CISB Outer Containmen t Valves), of ECA-0.0.
Appendix C                             Page 6 of 9                       Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 11 Verify CLOSED EG-HV-131, CCW from RCS CTMT Bypass.
Reposition any required valves and inform him when done.
Standard:           Operator should verify CLOSED EG-HV-131.
Time Critical Task:
NOTE:               Pen 75 Standard:           Valves in Steps 9 through 11 can be operated in any order.
NO  Validation Time:
Comment:
10 minutes 2005 NRC J P M P2  NUREG 102 1, Revision 9 Appendix C Page 2 of 9 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
Evaluators Cue:     EG-HV-131 is CLOSED.
START TI ME:  Evaluator Note:  All valves will be in the normal positions as stated in the JPM      Performanc e Step: 1 Obtain a verified working copy of ECA-0.0, Loss of All AC Power.
Performance Step: 12 Verify CLOSED EG-HV-61, CCW from RCS Outer CTMT ISO.
S t a n d a r d: Operator should obtain ECA-0.0 copy.
Standard:           Operator should verify position of EG-HV-61.
C o m m e n t:  Evaluator's Cue:
NOTE:               Pen 76 Standard:           Valves in Steps 12 through 14 can be operated in any order.
Provide operator w i th cop y of ECA-0.0.
Comment:
Performanc e Step: 2 Go to the Aux Building North Piping Penetration Room #132
Evaluators Cue:     EG-HV-61 is OPEN.
: 3. S t a n d a r d: Operator should go to th e North Piping Penetration Room #1 323. NOTE: Operator s hould go thru HP Acce ss. C o m m e n t:        Performanc e Step: 3 Verify CLOS ED EG-HV-58, CCW to RCS outer CTMT ISO. S t a n d a r d: Operator should demonstrate knowledge of how to verify a motor-opera t ed valve OPEN/CL O SED. NOTE: Pen 74, valves in Steps 3 through 8 can be operated in an y order. C o m m e n t:  Evaluator Cue:
Performance Step: 13 CLOSE EG-HV-61, CCW from RCS Outer CTMT ISO.
EG-HV-58 is open 2005 NRC J P M P2  NUREG 102 1, Revision 9 Appendix C Page 3 of 9 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 4 CLOS E EG-H V-58, CC W to RCS Outer CTMT I S O. S t a n d a r d: Operator should CLOSE EG-HV-58.
Standard:           Operator should CLOSE EG-HV-61, CCW from RCS Outer CTMT ISO.
NOTE: Operator s hould be able to describe how to CLOSE a limitorque valve.
NOTE:               Pen 76 Standard:           Valves in Steps 12 through 14 can be operated in any order.
S t a n d a r d: Valves in Steps 3 throug h 8 can be o perated in a n y order.        C o m m e n t:  Evaluator's Cue:
Comment:
EG-HV-58 is no w CLOSED.      Performanc e Step: 5 Verify CLOS ED EG-HV-71, CCW to RCS Outer CTMT ISO.
Evaluators Cue:     EG-HV-61 is now CLOSED.
S t a n d a r d: Operator should verify position of E G-HV-71. N O T E: Pen 7 4    S t a n d a r d: Valves in Steps 3 throug h 8 can be o perated in a n y order. C o m m e n t:  Evaluator's Cue:
2005 NRC JPM P2                                               NUREG 1021, Revision 9
EG-HV-71 is OPEN.
 
2005 NRC J P M P2  NUREG 102 1, Revision 9 Appendix C Page 4 of 9 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 6 Operator should CLOSE EG-HV-71, CCW to RCS Outer CT MT ISO. S t a n d a r d: Operator should CLOSE EG-HV-71.
Appendix C                             Page 7 of 9                       Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 14 Verify CLOSED EG-HV-133, CCW from RCS CTMT BYPASS.
N O T E: Pen 7 4    S t a n d a r d: Valves in Steps 3 throug h 8 can be o perated in a n y order. C o m m e n t:  Evaluator's Cue:
Standard:           Operator should verify CLOSED EG-HV-133.
EG-HV-71 is no w CLOSED.      Performanc e Step: 7 Verify CLOSED EG-HV-126, CCW to RCS CT MT Bypass.
NOTE:               Pen 76 Standard:           Valves in Steps 12 through 14 can be operated in any order.
S t a n d a r d: Operator should verify CLOSED EG-HV-126, CCW to RCS CTM T By pass. N O T E: Pen 7 4    S t a n d a r d: Valves in Steps 3 throug h 8 can be o perated in a n y order. C o m m e n t:  Evaluator's Cue:
Comment:
EG-HV-126 is CLOSED.
Evaluators Cue:     EG-HV-133 is CLOSED.
2005 NRC J P M P2  NUREG 102 1, Revision 9 Appendix C Page 5 of 9 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 8 Verify CLOSED EG-HV-127, CCW to RCS CT MT Bypass.
Performance Step: 15 Standard:           Operator should inform Control Room Supervisor Local Operator Action is completed to Isolated CIS-B Valves.
S t a n d a r d: Operator should verify CLOSED EG-HV-127, CCW to RCS CTM T By pass. N O T E: Pen 7 4    S t a n d a r d: Valves in Steps 3 throug h 8 can be o perated in a n y order. C o m m e n t:  Evaluator's Cue:
Comment:
EG-HV-127 is CLOSED.
Evaluators Cue:     Control Room Supervisor acknowledges.
Performanc e Step: 9 Verify CLOS ED EG-HV-59, CCW from RCS Out e r CTMT ISO.
Terminating Cue:       When all CIS-B valves are closed, the JPM is complete STOP TIME:
S t a n d a r d: Operator should verify position of E G-HV-59. N O T E: Pen 7 5    S t a n d a r d: Valves in Steps 9 throug h 11 can be operated in any order.
2005 NRC JPM P2                                               NUREG 1021, Revision 9
C o m m e n t:  Evaluator's Cue:
 
EG-HV-59 is OPEN.
Appendix C                             Page 8 of 9               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM P2 Examinees Name:
Performanc e Step: 10 CLOSE EG-HV-59, CCW from Out e r CTMT ISO.
S t a n d a r d: Operator should CLOSE EG-HV-59.
N O T E: Pen 7 5    S t a n d a r d: Valves in Steps 9 throug h 11 can be operated in any order.
C o m m e n t:  Evaluator's Cue:
EG-HV-59 is no w CLOSED. 2005 NRC J P M P2  NUREG 102 1, Revision 9 Appendix C Page 6 of 9 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 11 Verify CLOSED EG-HV-131, CCW from RCS CT MT Bypass.
S t a n d a r d: Operator should verify CLOSED EG-HV-131.
N O T E: Pen 7 5    S t a n d a r d: Valves in Steps 9 throug h 11 can be operated in any order.
C o m m e n t:   Evaluator's Cue:
EG-HV-131 is CLOSED.
Performanc e Step: 12 Verify CLOS ED EG-HV-61, CCW from RCS Out e r CTMT ISO.
S t a n d a r d: Operator should verify position of E G-HV-61. N O T E: Pen 7 6    S t a n d a r d: Valves in Steps 12 throu gh 14 can b e operated in any order.
C o m m e n t:   Evaluator's Cue:
EG-HV-61 is OPEN.
Performanc e Step: 13 CLOSE EG-HV-61, CCW from RCS Outer CT MT ISO. S t a n d a r d: Operator should CLOSE EG-HV-61, CCW from RCS Outer CTMT ISO. N O T E: Pen 7 6    S t a n d a r d: Valves in Steps 12 throu gh 14 can b e operated in any order.
C o m m e n t:   Evaluator's Cue:
EG-HV-61 is no w CLOSED. 2005 NRC J P M P2 NUREG 102 1, Revision 9 Appendix C Page 7 of 9 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 14 Verify CLOSED EG-HV-133, CCW from RCS CT MT BYPASS.
S t a n d a r d: Operator should verify CLOSED EG-HV-133.
N O T E: Pen 7 6    S t a n d a r d: Valves in Steps 12 throu gh 14 can b e operated in any order.
C o m m e n t:   Evaluator's Cue:
EG-HV-133 is CLOSED.
Performanc e Step: 15 S t a n d a r d: Operator should inform Control Room Supervisor Local Operator Action is co mpleted to Isolated CIS-B Valves.
C o m m e n t:   Evaluator's Cue:
Control Ro om Supervisor acknowledges.
Terminating Cue:
When all CIS-B valves are closed, the JPM is complete   STOP TI ME:     2005 NRC J P M P2 NUREG 102 1, Revision 9 Appendix C Page 8 of 9 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC J P M P2   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,286: Line 2,270:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M P2 NUREG 102 1, Revision 9 Appendix C Page 9 of 9 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant was at 100% power when a Loss of All AC Power occurred. T he Control Room entered emergency procedure ECA-0.0, Lo ss of All AC Power. A containment spray signal has been received and required valve po sitions can n o t be performed from the Co ntrol Room.
2005 NRC JPM P2                                         NUREG 1021, Revision 9
INITIATING CUE: The Control Room supervi sor has dir e cted you to perform Local Operator Actions of Step 21B RNO (CISB Outer Containmen t Valves), of ECA-0.0. Reposition an y required valves and in form him when done.
 
2005 NRC J P M P2 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
Appendix C                         Page 9 of 9                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant was at 100% power when a Loss of All AC Power occurred. The Control Room entered emergency procedure ECA-0.0, Loss of All AC Power. A containment spray signal has been received and required valve positions can not be performed from the Control Room.
: Perform Fire Water System Makeup to CST JPM No.: 2005 NRC J P M P3     K/A Referen c e: 061 K4.01 3.9 / 4.2 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
INITIATING CUE:     The Control Room supervisor has directed you to perform Local Operator Actions of Step 21B RNO (CISB Outer Containment Valves), of ECA-0.0. Reposition any required valves and inform him when done.
Date: Method of testing:
2005 NRC JPM P2                                           NUREG 1021, Revision 9
Simulated Performance:
 
X Actual Performance:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
C l a s s r o o m  S i m u l a t o r  P l a n t X READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant has lost all AC power due to an earthquake.
Task
Plant operators ar e currently in emergency procedure ECA-0.0, Lo ss of All AC Power, stabilizing the pla n t. Task Stand ard: Upon completion of this JPM, the operator will h a ve comme n ced fill ing the CST from the Firewater System.
 
Required Materials:
==Title:==
Key #131, Locked Valve and Breaker Key General  
Perform Fire Water System Makeup       JPM No.:     2005 NRC JPM P3 to CST K/A  
 
==Reference:==
061 K4.01       3.9 / 4.2 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:           X                         Actual Performance:
Classroom                Simulator            Plant        X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant has lost all AC power due to an earthquake. Plant operators are currently in emergency procedure ECA-0.0, Loss of All AC Power, stabilizing the plant.
Task Standard:             Upon completion of this JPM, the operator will have commenced filling the CST from the Firewater System.
Required Materials:         Key #131, Locked Valve and Breaker Key General  


==References:==
==References:==
EOP Addendum 23, Local CST Emergency Fill Initiating Cue:            The Control Room Supervisor has directed you to fill the condensate storage tank using Addendum 23, Local CST Emergency Fill. Inform the Control Room Supervisor when you have started filling the CST.
Time Critical Task:        NO Validation Time:            10 minutes 2005 NRC JPM P3                                                            NUREG 1021, Revision 9
Appendix C                                  Page 2 of 6                          Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtain a copy of Addendum 23, Local CST Emergency Fill.
Standard:                Operator should obtain procedure copy.
Comment:
Performance Step: 2      Review Addendum.
Standard:                Operator may review Addendum.
Comment:
Step 1.0 Performance Step: 3      Obtain hydrant wrench, 1 50 ft. section of 2 1/2 fire hose, 1 spanner wrench, 1 fire water to CST emergency fill connector.
Standard:                Operator should Obtain hydrant wrench, 1 50 ft. section of 2 1/2 fire hose, 1 spanner wrench, 1 Fire Water to CST Emergency Fill Connector.
Comment:
Step 2.A Performance Step: 4      Connect the CST Emergency Fill Connector to the Ecolo Chem Connection on APV0043.
Standard:                Operator should hook up CST Emergency Fill Connector to the Ecolo Chem Connection on APV0043 located plant south side of CST.
Comment:
Evaluators Cue:          CST Emergency Fill Connector is hooked up to APV0043 2005 NRC JPM P3                                                    NUREG 1021, Revision 9
Appendix C                            Page 3 of 6                        Form ES-C-1 PERFORMANCE INFORMATION Step 2.B Performance Step: 5 Connect 2 1/2 fire hose to the CST Emergency Fill Connector at APV0043.
Standard:          Operator should connect the 2 1/2 fire hose to the CST Emergency Fill Connector.
Comment:
Evaluators Cue:    2 1/2 fire hose is hooked up to the CST Emergency Fill Connector.
Step 2.C Performance Step: 6 Hook up the 2 1/2 hose to the fire hydrant.
Standard:          Operator should hook up the 2 1/2 hose to the fire hydrant.
Comment:
Evaluators Cue:    2 1/2 hose is hooked up to the fire hydrant.
Step 3.B Performance Step: 7 Open APV0043, CST Deoxygenated Water Outlet Valve.
Standard:          Operator should break the lock (or unlock) and open APV0043, CST Deoxygenated Water Outlet Valve.
Comment:
Evaluators Cue:    APV0043 is OPEN.
Step 3.C Performance Step: 8 Open fire water hydrant using hydrant wrench.
Standard:          Operator should open fire water hydrant.
Comment:
Evaluators Cue:    Fire water hydrant is OPEN.
2005 NRC JPM P3                                              NUREG 1021, Revision 9


EOP Adden dum 23, Local CST Eme r gency Fill Initiating Cu e: The Control Room Supe rvisor has di rected you to fill the con densate storage tank using Adde ndum 23, Local CST Emergency Fill.
Appendix C                             Page 4 of 6                         Form ES-C-1 PERFORMANCE INFORMATION Step 4 Performance Step: 9  Ensure fire water is flowing to the CST.
Inform the Control Room Supervisor when you have started filling th e CST. Time Critical Task:
Standard:           Operator should verify the fire water is flowing.
NO  Validation Time:
Comment:
10 minutes 2005 NRC J P M P3  NUREG 102 1, Revision 9 Appendix C Page 2 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
Evaluators Cue:     2 1/2 fire hose fills and fire water starts to flow.
START TI ME:        Performanc e Step: 1 Obtain a copy of Addendum 23, Local CST Eme r gency Fill.
Step 5 Performance Step: 10 Notify SS/CRS of CST Emergency Fill status.
S t a n d a r d: Operator should obtain procedure copy.
Standard:           Operator should notify SS/OS of CST Fill from fire water.
C o m m e n t:        Performanc e Step: 2 Review Add endum. S t a n d a r d: Operator may review Addendum.
Comment:
C o m m e n t:      Step 1.0  Performanc e Step: 3 Obtain hydrant wrench, 1 50 ft. sect ion of 2 1/2" fire hose, 1 spanner wrench, 1 fire w a ter to CST emergency fill conne ctor. S t a n d a r d: Operator should Obtain hydrant wre n ch, 1 50 ft.
Evaluators Cue:     SS/CRS acknowledges.
section of 2 1/2" fire hose, 1 spanner wrench, 1 Fire Water to CST Emergency Fill Connector.
Terminating Cue:       When the control room has been informed, this JPM is complete.
C o m m e n t:      Step 2.A  Performanc e Step: 4 Connect the CST Emergency Fill Connector to th e Ecolo Chem Connection on APV004 3. S t a n d a r d: Operator should hook u p CST Emergency Fill Connector to t he Ecolo Chem Connection on APV0043 located plant south side of CST. C o m m e n t:  Evaluator's Cue:
STOP TIME:
CST Emerg enc y Fill Connector is hooked up to APV004 3  2005 NRC J P M P3  NUREG 102 1, Revision 9 Appendix C Page 3 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 2.B  Performanc e Step: 5 Connect 2 1/2" fire hose to the CST Emergency Fill Connect o r at APV0043. S t a n d a r d: Operator should connect the 2 1/2" fir e hose to th e CST Emergency Fill Connect o r. C o m m e n t:  Evaluator's Cue:
2005 NRC JPM P3                                                 NUREG 1021, Revision 9
2 1/2" fire hose is hooked up to the CST Emerg enc y Fill Connector.
 
Step 2.C  Performanc e Step: 6 Hook up the 2 1/2" hose t o the fire hydrant.
Appendix C                             Page 5 of 6               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM P3 Examinees Name:
S t a n d a r d: Operator should hook u p the 2 1/2" h o se to the fir e hydrant.
C o m m e n t:  Evaluator's Cue:
2 1/2" hose i s hooked up to the fire h y drant. Step 3.B  Performanc e Step: 7 Open APV0 043, CST Deoxygenate d Water Outlet Valve.
S t a n d a r d: Operator should break t he lock (or unlock) and open APV00 43, CST Deo x ygenated Water Outlet Valve.
C o m m e n t:  Evaluator's Cue:
APV0043 is OPEN. Step 3.C  Performanc e Step: 8 Open fire water hydrant using hydrant wrench.
S t a n d a r d: Operator should open fir e water hydrant.
C o m m e n t:  Evaluator's Cue:
Fire w a ter h y drant is OPEN. 2005 NRC J P M P3  NUREG 102 1, Revision 9 Appendix C Page 4 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4 Performanc e Step: 9 Ensure fire water is flowing to the CST.
S t a n d a r d: Operator should verify the fire water is flowing.
C o m m e n t:   Evaluator's Cue:
2 1/2" fire hose fills and fire w a ter s t arts to flow. Step 5 Performanc e Step: 10 Notify SS/CRS of CST Emergency Fill statu
: s. S t a n d a r d: Operator should notify SS/OS of CST Fill from fir e water. C o m m e n t:   Evaluator's Cue:
SS/CRS acknowledge
: s.      Terminating Cue:
When the control roo m has been informed, this JPM is complete.
STOP TI ME:     2005 NRC J P M P3 NUREG 102 1, Revision 9 Appendix C Page 5 of 6 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC J P M P3   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,340: Line 2,352:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M P3 NUREG 102 1, Revision 9 Appendix C Page 6 of 6 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant has lost all AC power due to an earthquake.
2005 NRC JPM P3                                         NUREG 1021, Revision 9
Plant operators ar e currently in emergency procedure ECA-0.0, Lo ss of All AC Powe r, stabilizing the plant.
 
INITIATING CUE: The Control Room Supe rvisor has di rected you to fill the condensate storage tank using Adde ndum 23, Local CST Emergency Fill. Inform t he Cont rol Room Supe rvisor when you have started filling th e CST. 2005 NRC J P M P3 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Appendix C                           Page 6 of 6                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant has lost all AC power due to an earthquake. Plant operators are currently in emergency procedure ECA-0.0, Loss of All AC Power, stabilizing the plant.
Callaw a y Pl ant Task No.:
INITIATING CUE:     The Control Room Supervisor has directed you to fill the condensate storage tank using Addendum 23, Local CST Emergency Fill. Inform the Control Room Supervisor when you have started filling the CST.
Task Title
2005 NRC JPM P3                                           NUREG 1021, Revision 9
: Raise Reactor Power To 10
 
-8 Amps JPM No.: 2005 NRC J P M S1     K/A Referen c e: 001 A2.11 (4.4/4.7) 001 AA1.05 (4.3/4.2)
Appendix C                                     Job Performance Measure                         Form ES-C-1 Worksheet Facility:                 Callaway Plant                              Task No.:
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
Task
Date: Method of testing:
 
Simulated Performance:
==Title:==
Actual Performance:
Raise Reactor Power To 10-8 Amps             JPM No.:     2005 NRC JPM S1 K/A  
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ TO THE EXAMINEE I will explain the initial co nd itions, whi c h step s to simu l a te or discu s s, and p r ovid e initiating cu es. Whe n you compl e te the task successf ully, t he objective for this Job Perfor mance Measure will be satisfi ed. Initial Condit i ons: A reactor st artup is in pr ogress in a c cordance with OTG-ZZ-00002, Reactor Startup The following co nditions exist: All shutdow n bank rods are fully withdrawn. Control Bank "D" is at 9 2 steps. The estimated critica l p o sition is 10 1 steps on Control Bank "D". Most recent ICRR predicts 100 steps on Control Bank D Task Stand ard: The reactor is tripped in response to inappropriat e continuou s control rod motion. Required Materials:
 
None   General  
==Reference:==
001 A2.11       (4.4/4.7)                   001 AA1.05     (4.3/4.2)
Examinee:                                                         NRC Examiner:
Facility Evaluator:                                               Date:
Method of testing:
Simulated Performance:                                             Actual Performance:           X Classroom                  Simulator        X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:           A reactor startup is in progress in accordance with OTG-ZZ-00002, Reactor Startup The following conditions exist:
All shutdown bank rods are fully withdrawn.
Control Bank D is at 92 steps.
The estimated critical position is 101 steps on Control Bank D.
Most recent ICRR predicts 100 steps on Control Bank D Task Standard:               The reactor is tripped in response to inappropriate continuous control rod motion.
Required Materials:           None General  


==References:==
==References:==
OTG-ZZ-00002, Reactor Startup Handouts:                    OTG-ZZ-00002, Reactor Startup marked up through step 4.1.17 Initiating Cue:              The Control Room Supervisor directs you to continue with the reactor startup and withdraw control rods to criticality in accordance with OTG-ZZ-00002, Reactor Startup, beginning at Step 4.1.18.
Time Critical Task:          NO Validation Time:              12 minutes Callaway NRC JPM S1                                                              NUREG 1021, Revision 9
Appendix C                          Job Performance Measure          Form ES-C-1 Worksheet Simulator Setup:      reset to IC-187 Password = startup Run Batch File startup.txt Callaway NRC JPM S1                                        NUREG 1021, Revision 9
Appendix C                                    Page 3 of 8                        Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Evaluator Cue:
Inform the candidate that all precautions and limitations are satisfied Performance Step: 1        Candidate initiates control bank withdrawal, monitoring Source Range counts, Intermediate Range Amps, and P-6 bistables.
Standard:                  Candidate determines that P-6 is energized and refers to Attachment 3 Comment:
Performance Step: 2        Verify one decade of overlap between the source and intermediate range level instruments.
Standard:                  Observes Source Range and Intermediate Range instruments and determines that sufficient overlap exists Comment:
Callaway NRC JPM S1                                                    NUREG 1021, Revision 9
Appendix C                              Page 4 of 8                        Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Verify indication on both the source and intermediate startup rate instruments.
Standard:          Candidate determines that SR and IR startup rate indication exists Comment:
Performance Step: 4 Transfer the SE NR-45 recorder to the intermediate ranges.
Standard:          Transfers NR-45 trend to IR channels Comment:
Performance Step: 5 Prior to exceeding 5E4 CPS on SR instruments, BLOCK the Source Range High Flux Trips Standard:          Block A Train by depressing the BLOCK pushbutton on SE HS-5.
Standard:          Verify SR TRIP A BLOC illuminates on SB069.
Standard:          Block B Train by depressing the BLOCK pushbutton on SE HS-10.
Callaway NRC JPM S1                                            NUREG 1021, Revision 9
Appendix C                                Page 5 of 8                          Form ES-C-1 PERFORMANCE INFORMATION Standard:            Verify SR TRIP B BLOCK illuminates on SB069.
Standard:            Verify that the high voltage has been removed from the source range detectors.
Comment:
Evaluator Cue:        If the candidate reports that Source Range High Flux Trips have been blocked, acknowledge and provide direction to continue the control rod withdrawal Performance Step: 6  Continue incremental rod withdrawal until the reactor is critical, as indicated by a stable positive startup rate with no rod motion, on the intermediate range instrumentation once the prompt jump has receded.
Standard:            Candidate initiates control rod withdrawal in small increments Comment:
Note: The following steps represent the alternate path of this JPM Performance Step: 7  Determine that rods are withdrawing with NO demand signal.
Standard:            Candidate determines from CONTROL BANK D GROUP 1 and GROUP 2 ROD POSITION indication that rods are withdrawing with NO demand signal.
Comment:
Callaway NRC JPM S1                                                NUREG 1021, Revision 9


OTG-ZZ-00 002, Reactor Startup Han dout s: OTG-ZZ-00 002, Reactor Startup ma rked up thro ugh step 4.1
Appendix C                                 Page 6 of 8                         Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8  Trip the reactor in response to inappropriate continuous rod motion.
.17    Initiating Cu e: The Control Room Supe rvisor direct s you to continue with th e reactor sta r tup and withdraw control rods to crit icality in accord ance with OTG-ZZ-00002, Reactor Startup, beginning at Step 4.1.18.
Candidate trips the reactor in response to inappropriate continuous rod motion.
Time Critical Task:
NO  Validation Time:
12 minutes Callaway N RC JPM S1  NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup:
reset to IC-187 Password = startup Run Batch File startup.tx t            Callaway N RC JPM S1  NURE G 102 1, Revision 9 Appendix C Page 3 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Critical Steps with a check mark)  START TI ME:       Evaluator Cue:
Inform the candidate that all precautions and limitations are satisfied Performanc e Step: 1 Candidate initiates cont rol bank wit hdrawal, mo nitoring Sou r ce Range counts, Intermediate Range Amps, and P-6 bistable
: s. S t a n d a r d: Candidate determines that P-6 is en ergized and refers to C o m m e n t:      Performanc e Step: 2 Verify one decade of overlap between the source and intermediate range level instruments.
S t a n d a r d: Observes Source Range and Intermediate Range instruments and determines that suff icient overla p exists    C o m m e n t:      Callaway N RC JPM S1  NURE G 102 1, Revision 9 Appendix C Page 4 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Performanc e Step: 3 Verify indication on both the source a nd intermediate startup r a te instrum ents. S t a n d a r d: Candidate determines that SR and IR startup rate indicatio n exists    C o m m e n t:      Performanc e Step: 4 Transfer the SE NR-45 recorder to t he intermediate ranges.
S t a n d a r d: Transfers NR-45 trend to IR channels C o m m e n t:      Performanc e Step: 5 Prior to exceeding 5E4 CPS on SR instruments, BLOCK the Source Range High Flu x Trips    Standard:
Block "A" Train by depressing the BL OCK pushb utton on SE HS-5. S t a n d a r d: Verify SR T R IP A BL OC illuminates on SB069.
Standard:
Standard:
Block "B" Train by depressing the BL OCK pushb utton on SE HS-10.
NOTE: Candidate may refer to OTO-SF-00001 and determine that a reactor trip is required based on Step 6 RNO.
Callaway N RC JPM S1  NURE G 102 1, Revision 9 Appendix C Page 5 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      S t a n d a r d: Verify SR T R IP B BL OCK illuminates on SB069.
Comment:
S t a n d a r d: Verify that the high voltage has bee n removed f r om the source range detect o rs. C o m m e n t:      Evaluator Cue:
Terminating Cue:   When the Candidate trips the reactor, the evaluation for this JPM is complete.
If the candidate reports that Source Range High Flux Trips have been blocked, acknowledge and provide direction to continue the control rod withdra w al    Performanc e Step: 6 Continue incremental rod withdrawal until the rea c tor is cr itica l , as indicated by a stable po sitive startu p rate with no rod motion, on the intermediate range in strumentation once the p r ompt jump has receded. S t a n d a r d: Candidate initiates cont rol rod withdrawal in small incremen ts    C o m m e n t:  Note: The follow i ng steps represent th e alternate path of this JPM Performanc e Step: 7 Determine t hat rods are withdrawing with NO de mand signal.
STOP TIME:
S t a n d a r d: Candidate determines from CONTROL BANK D GROUP 1 and GROUP 2 ROD POSITI ON indication that rods a r e withdrawing with NO de mand signal.
Callaway NRC JPM S1                                               NUREG 1021, Revision 9
C o m m e n t:  Callaway N RC JPM S1  NURE G 102 1, Revision 9 Appendix C Page 6 of 8 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Performanc e Step: 8 Trip the rea c tor in respo n se to inapp ropriate cont inuous rod motion. Candidate trips the react o r in respon se to inappr opriate continuous r od motion.
 
S t a n d a r d:    NOTE: Candidate ma y refe r to OTO-SF-0 0001 and determine that a reactor trip is re quired based on Step 6 RNO.
Appendix C                                 Page 7 of 8               Form ES-C-1 VERIFICATION OF COMPLETION JPM No.:                     2005 JPM S1 Examinees Name:
C o m m e n t:   Terminating Cue:
Examiners Name:
When the Candidate trip s the reactor
, the evaluation for this JPM is complete.
STOP TI ME:     Callaway N RC JPM S1 NURE G 102 1, Revision 9 Appendix C Page 7 of 8 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  JPM No.: 2005 JPM S1 Exa m inee's Name:
Exa m iner's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,388: Line 2,430:
Time to Complete:
Time to Complete:
Question Documentation:
Question Documentation:
Q u e s t i o n:          
Question:


Response:          
===Response===
Result: Satisfactory/Unsatisfactory Examiners Signature:                                            Date:
Callaway NRC JPM S1                                          NUREG 1021, Revision 9


Result: Satisfactory/Unsatisfactory Exa m iner's Signature:
Appendix C                           Page 8 of 8                           Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A reactor startup is in progress in accordance with OTG-ZZ-00002, Reactor Startup. The following conditions exist:
Date:    Callaway N RC JPM S1  NURE G 102 1, Revision 9 Appendix C Page 8 of 8 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
All shutdown bank rods are fully withdrawn.
A reactor st artup is in pr ogress in a c cordance with OTG-ZZ-00002, Reactor Startup. The fo llowing cond itions exist: All shutdow n bank rods are fully withdrawn. Control Bank "D" is at 9 2 steps. The estimated critica l p o sition is 10 1 steps on Control Bank "D". Most recent ICRR predicts 100 steps on Control Bank D INITIATING CUE:
Control Bank D is at 92 steps.
The Control Room Supe rvisor direct s you to continue with th e reactor start up and withdraw control rods to crit icality in accordance with OTG-Z Z-00002, Reactor Startup, beginning at Step 4.1.18.
The estimated critical position is 101 steps on Control Bank D.
Callaway N RC JPM S1 NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Most recent ICRR predicts 100 steps on Control Bank D INITIATING CUE:     The Control Room Supervisor directs you to continue with the reactor startup and withdraw control rods to criticality in accordance with OTG-ZZ-00002, Reactor Startup, beginning at Step 4.1.18.
Callaw a y Task No.:
Callaway NRC JPM S1                                           NUREG 1021, Revision 9
0111-011-01-013 Task Title
 
: Isolate SI A ccumulators During a LOCA JPM No.: 2005 NRC J P M S2     K/A Referen c e: 009 EA1.13 (4.4/4.4)
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                    Task No.:   0111-011-01-013 Task
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
 
Date: Method of testing:
==Title:==
Simulated Performance:
Isolate SI Accumulators During a LOCA       JPM No.:   2005 NRC JPM S2 K/A  
Actual Performance:
 
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: A LOCA has occurred.
==Reference:==
The crew is performing ES-1.2, Post LOCA Cooldown and Depressurization.
009 EA1.13     (4.4/4.4)
Task Stand ard: SI Accumulators A, B, and C are iso l ated. SI Accumulator D is vented.
Examinee:                                                   NRC Examiner:
Required Materials:
Facility Evaluator:                                         Date:
None General  
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator      X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         A LOCA has occurred. The crew is performing ES-1.2, Post LOCA Cooldown and Depressurization.
Task Standard:             SI Accumulators A, B, and C are isolated. SI Accumulator D is vented.
Required Materials:         None General  


==References:==
==References:==
ES-1.2, Post LOCA Cooldown and Depressurization Handouts:                  ES-1.2, Post LOCA Cooldown and Depressurization Initiating Cue:            The Control Room Supervisor directs you to isolate the SI accumulators in accordance with ES-1.2, Post LOCA Cooldown and Depressurization, Step 23.
Time Critical Task:        NO Validation Time:            7 Minutes Callaway JPM S2                                                            NUREG 1021, Revision 9
Appendix C                        Job Performance Measure          Form ES-C-1 Worksheet Simulator Setup:  Initialize IC-184 Password spa321 Run bat.siacc.txt Callaway JPM S2                                          NUREG 1021, Revision 9
Appendix C                                    Page 3 of 6                        Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1        RCS subcooling based on core exit TCs - GREATER THAN 30°F (Step 23.a)
Standard:                  Candidate verifies RCS subcooling based on core exit TCs is greater than 30°F Comment:
Performance Step: 2        PRZR level - GREATER THAN 9% [29% ADVERSE CNMT]
(Step 23.b)
Standard:                  Candidate locates and verifies PRZR level indication is greater than 9%.
Comment:
Performance Step: 3        Restore power to EP-HV-8808A, B, C, D (Step 23.c)
Standard:                  Candidate directs Local Operator to restore power to EP-HV-8808A - D Standard:                  Candidate contacts Local Operator to restore power Comment:                  Booth Instructor: Inform candidate that power is restored to all 4 accumulator outlet valves Callaway JPM S2                                                      NUREG 1021, Revision 9
Appendix C                                  Page 4 of 6                        Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4      Close EP-HIS-8808A, B, C, D (Step 23.d)
Standard:                Candidate locates EP-HV-8808A, B, C and D control switches and places in CLOSE.
Standard:                Candidate verifies green close light on and red open light off for each valve.
Comment:                EP HV-8808C does not close using the handswitch on the MCB.
NOTE:    The following step represents the alternate path portion of the JPM.
Performance Step: 5      If any accumulator cannot be isolated, then open associated accumulator vent valve (Step 23.d RNO)
Standard:                Locates control switch for EITHER EP HIS-8950D OR EP HIS-8950E, and places switch in OPEN OR places BOTH switches in OPEN.
Standard:                Observes Green Light OFF, Red Light ON, and accumulator C pressure lowering.
Comment:
Terminating Cue:    When the Candidate verifies that accumulator C pressure is lowering, the evaluation for this JPM is complete.
STOP TIME:
Callaway JPM S2                                                      NUREG 1021, Revision 9


ES-1.2, Post LOCA Coo l down and Depressurizat i on  Handouts:
Appendix C                                 Page 5 of 6               Form ES-C-1 VERIFICATION OF COMPLETION JPM No.:                   2005 JPM S2 Examinees Name:
ES-1.2, Post LOCA Coo l down and Depressurizat i on  Initiating Cu e: The Control Room Supe rvisor di rect s you to isolate the SI accumulators in accordan ce with ES-1.2, Post LOCA Cooldown and Depressurizat i on, Step 23. Time Critical Task:
Examiners Name:
NO Validation Time:
7 Minutes Callaway JP M S2  NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup:
Initialize IC-184  Password spa321 Run bat.siacc.txt Callaway JP M S2  NURE G 102 1, Revision 9 Appendix C Page 3 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Critical Steps with a check mark)  START TI ME:        Performanc e Step: 1 (Step 23.a)
RCS subcooling based on core exit TCs - GREATER THAN 30°F S t a n d a r d: Candidate verifies RCS subcooling based on co re exit TCs is greater than 30°F C o m m e n t:      Performanc e Step: 2 (Step 23.b)
PRZR level - GREATER THAN 9% [
29% ADVERSE CNMT]
S t a n d a r d: Candidate locates and verifies PRZR level indication is grea ter than 9%. C o m m e n t:      Performanc e Step: 3 (Step 23.c)
Restore power to EP-HV-8808A, B, C, D  S t a n d a r d: Candidate directs Local Operator to restore power to EP-HV-8808A - D S t a n d a r d: Candidate contacts Local Operator to restore po wer    Comment: Booth Instructor:  Inform candidate that po wer is restored to all 4 accumulator outlet valves Callaway JP M S2  NURE G 102 1, Revision 9 Appendix C Page 4 of 6 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Performanc e Step: 4 (Step 23.d)
Close EP-HI S-8808A, B, C, D  S t a n d a r d: Candidate locates EP-HV-8808A, B, C and D control switches and places in CLOSE.
S t a n d a r d: Candidate verifies green close light o n and red open light off for each valve.
Comment: EP HV-8808 C does not close using the handsw itch on th e MCB. NOTE: The follo w i ng step represents the alternate path portion of the JPM.
Performanc e Step: 5 (Step 23.d RNO)
If any accumulator cannot be isolat ed, then ope n associate d accumulator vent valve S t a n d a r d: Locates con t rol switch fo r EITHER EP HIS-8950 D OR  EP HIS-895 0E, and places switch in OPEN OR p l aces BOTH switches in OPEN. S t a n d a r d: Observes Green Light OFF, Red Light ON, and accumulator C pressure lo wering. C o m m e n t:    Terminating Cue:
When the Candidate verifies that a c cumulator C pressure is lowering, the evaluation for this JPM is complete.
STOP TI ME:    Callaway JP M S2  NURE G 102 1, Revision 9 Appendix C Page 5 of 6 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  JPM No.: 2005 JPM S2 Exa m inee's Name:
Exa m iner's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,435: Line 2,495:
Time to Complete:
Time to Complete:
Question Documentation:
Question Documentation:
Q u e s t i o n:          
Question:


Response:          
===Response===
Result: Satisfactory/Unsatisfactory Examiners Signature:                                            Date:
Callaway JPM S2                                              NUREG 1021, Revision 9


Result: Satisfactory/Unsatisfactory Exa m iner's Signature:
Appendix C                         Page 6 of 6                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A LOCA has occurred. The crew is performing ES-1.2, Post LOCA Cooldown and Depressurization.
Date:  Callaway JP M S2  NURE G 102 1, Revision 9 Appendix C Page 6 of 6 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
INITIATING CUE:     The Control Room Supervisor directs you to isolate the SI accumulators in accordance with ES-1.2, Post LOCA Cooldown and Depressurization, Step 23.
A LOCA has occurred.
Callaway JPM S2                                           NUREG 1021, Revision 9
The crew is performing ES-1.2, Post LOCA Cooldown and Depressurizat i on. INITIATING CUE:
 
The Control Room Supe rvisor di rect s you to isolate the SI accumulators in accorda n ce with ES-1.2, Post L O CA Cooldown and Depressurization, Step 23.
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway Plant                          Task No.:
Callaway JP M S2 NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Task
Callaway Pl ant Task No.:
 
Task Title
==Title:==
: Respond to a Stuck Open Pressurizer Spray Valve JPM No.: 2005 NRC J P M S3     K/A Referen c e: 010 A2.02 (3.9/3.9)
Respond to a Stuck Open                 JPM No.:     2005 NRC JPM S3 Pressurizer Spray Valve K/A  
Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
 
Date: Method of testing:
==Reference:==
Simulated Performance:
010 A2.02 (3.9/3.9)
Actual Performance:
Examinee:                                                   NRC Examiner:
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: A Reactor Trip has occu rred. The cr ew has transitioned to E S-0.1, Reactor Trip Response Task Stand ard: RCPs A and D are tripped Required Materials:
Facility Evaluator:                                         Date:
ES-0.1   General  
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator      X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         A Reactor Trip has occurred. The crew has transitioned to ES-0.1, Reactor Trip Response Task Standard:             RCPs A and D are tripped Required Materials:         ES-0.1 General  


==References:==
==References:==
ES-0.1 Handouts:                  None Initiating Cue:            The Control Room Supervisor directs you to perform actions to stabilize the plant in accordance with ES-0.1 Time Critical Task:        NO Validation Time:            8 minutes Callaway NRC JPM S3                                                        NUREG 1021, Revision 9
Appendix C          Job Performance Measure          Form ES-C-1 Worksheet SIMULATOR SETUP Reset to IC-188 Password = spray Callaway NRC JPM S3                          NUREG 1021, Revision 9
Appendix C                                    Page 3 of 7                      Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
START TIME:
Performance Step: 1        Check RCS temperature - ANY RCP Running - Tave stable at or trending to 557°F.
Standard:                  Candidate verifies RCPs are running and Tave is at approximately 557°F.
Comment:
Performance Step: 2        Check Generator Output Breakers open.
Standard:                  Candidate verifies ML ZA-3A (V55) and ML ZA-4A (V53) indicate OPEN.
Comment:
Performance Step: 3        Check all AC busses energized by Off-Site power Standard:                  Determines that PA01 and PA02, NB01 and NB02 are energized by off-site power Comment:
Performance Step: 4        Check Pressurizer Pressure Control - Pressure greater than 1849 psig Standard:                  Candidate evaluates pressurizer pressure and determines it is greater than 1849 psig.
Comment:
Callaway NRC JPM S3                                                NUREG 1021, Revision 9


ES-0.1  H a n d o u t s: N o n e  Initiating Cu e: The Control Room Supe rvisor di rect s you to perform actions to stabilize the plant in accordance with ES-0.1 Time Critical Task:
Appendix C                             Page 4 of 7                         Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Check Pressurizer Pressure stable at or trending to 2235 psig.
NO  Validation Time:
Standard:           Candidate determines that Pressurizer Pressure is below 2235 psig and lowering.
8 minutes Callaway N RC JPM S3  NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP    Reset to IC-188 Password = spray Callaway N RC JPM S3  NURE G 102 1, Revision 9 Appendix C Page 3 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Critical Steps with an asterisk)
Comment:
START TI ME:        Performanc e Step: 1 Check RCS temperature - ANY RCP Running - Tave stable at or trending t o 557°F. S t a n d a r d: Candidate verifies RCPs are running and Tave is at approximate l y 557°F. C o m m e n t:        Performanc e Step: 2 Check Generator Output Breakers o pen. S t a n d a r d: Candidate verifies ML ZA-3A (V55) and ML ZA-4A (V53) indicate OPE N. C o m m e n t:      Performanc e Step: 3 Check all A C busses en ergized by Off-Site power S t a n d a r d: Determines that PA01 and PA02, NB01 and NB02 are energized by off-site power C o m m e n t:        Performanc e Step: 4 Check Pressurizer Pressure Control - Pressure greater than 1849 psig S t a n d a r d: Candidate evaluates pressurizer pre ssure and d e termines it is greater than 1849 psig.
Note: The following steps represent the alternate path of this JPM Performance Step: 6 Check PORVs closed Standard:           Candidate verifies BB-HIS-455A and 456A indicate CLOSED.
C o m m e n t:    Callaway N RC JPM S3  NURE G 102 1, Revision 9 Appendix C Page 4 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 5 Check Pressurizer Pressure stable at or trendin g to 2235 psig.
Comment:
S t a n d a r d: Candidate determines that Pressurizer Pressure is below 223 5 psig and low e ring. C o m m e n t:   Note: The follow ing steps represent the alternate path of this JPM Performanc e Step: 6 Check PORVs closed S t a n d a r d: Candidate verifies BB-HIS-455A and 456A indica te CLOSED.
Performance Step: 7 Check Spray Valves closed Standard:           Candidate determines that Spray Valve BB-PCV-455B is OPEN Comment:
C o m m e n t:       Performanc e Step: 7 Check Spray Valves closed S t a n d a r d: Candidate determines that Spray Val v e BB-PCV-455B is OPEN C o m m e n t:       Performanc e Step: 8 Close Spray Valve S t a n d a r d: Candidate places BB-PCV-455B controller in MANUAL and attempts to reduce outpu t to ZERO.
Performance Step: 8 Close Spray Valve Standard:           Candidate places BB-PCV-455B controller in MANUAL and attempts to reduce output to ZERO. Determines valve remains OPEN Comment:
Determines valve re mains OPE N    C o m m e n t:       Performanc e Step: 9 Stop RCPs A and D S t a n d a r d: Candidate places RCP A and D control switches in STOP C o m m e n t:   Callaway N RC JPM S3 NURE G 102 1, Revision 9 Appendix C Page 5 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Performanc e Step: 10 Verify PRZ R Heaters - ON S t a n d a r d: Candidate verifies PRZR Heaters - ON.
Performance Step: 9 Stop RCPs A and D Standard:           Candidate places RCP A and D control switches in STOP Comment:
C o m m e n t:         Terminating Cue:
Callaway NRC JPM S3                                           NUREG 1021, Revision 9
When A and D RCPs a r e tripped or upon completion of ES-0.1 Step 3, this JPM is complete.
 
STOP TI ME:     Callaway N RC JPM S3 NURE G 102 1, Revision 9 Appendix C Page 6 of 7 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Appendix C                               Page 5 of 7                 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 10 Verify PRZR Heaters - ON Standard:           Candidate verifies PRZR Heaters - ON.
Callaway NRC JPM S3   Exa m inee's Name:
Comment:
Terminating Cue:         When A and D RCPs are tripped or upon completion of ES-0.1 Step 3, this JPM is complete.
STOP TIME:
Callaway NRC JPM S3                                         NUREG 1021, Revision 9
 
Appendix C                             Page 6 of 7               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: Callaway NRC JPM S3 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,475: Line 2,560:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   Callaway N RC JPM S3 NURE G 102 1, Revision 9 Appendix C Page 7 of 7 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
A reactor Trip has occurr ed. The cre w has transitioned to ES-0.1, Reactor Trip Response INITIATING CUE:
Callaway NRC JPM S3                                     NUREG 1021, Revision 9
The Control Room Supe rvisor dire ct s you to perform actions to stabilize the plant in accordance wit h ES-0.1 Callaway N RC JPM S3 NURE G 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
 
: Start "A" Re actor Coola n t Pump JPM No.: 2005 NRC J P M S4     K/A Referen c e: 002 K6.02 3.6 / 3.8 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
Appendix C                           Page 7 of 7                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A reactor Trip has occurred. The crew has transitioned to ES-0.1, Reactor Trip Response INITIATING CUE:     The Control Room Supervisor directs you to perform actions to stabilize the plant in accordance with ES-0.1 Callaway NRC JPM S3                                         NUREG 1021, Revision 9
Date: Method of testing:
 
Simulated Performance:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
Actual Performance:
Task
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant is in mo de 3 at 557°F and 2235 psig. "A" Reactor Coolant Pump had been secured fo r breaker work on PA0107. CCW is in operation and is supp lying cooling water to the Thermal Barrier Cooling coils per OTN-EG-00001.
 
There are no personnel in CTMT at this time.
==Title:==
Task Stand ard: Upon completion of this JPM, the operator will h a ve tripped "A" RCP due to high seal leakoff flow.
Start A Reactor Coolant Pump           JPM No.:     2005 NRC JPM S4 K/A  
Required Materials:
 
None   General  
==Reference:==
002 K6.02       3.6 / 3.8 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator        X   Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant is in mode 3 at 557°F and 2235 psig. A Reactor Coolant Pump had been secured for breaker work on PA0107. CCW is in operation and is supplying cooling water to the Thermal Barrier Cooling coils per OTN-EG-00001. There are no personnel in CTMT at this time.
Task Standard:             Upon completion of this JPM, the operator will have tripped A RCP due to high seal leakoff flow.
Required Materials:         None General  


==References:==
==References:==
OTN-BB-00003, Reactor Coolant Pumps, Revision 15 Initiating Cue:            Tags have been cleared on PA0107 and signed off. The Control Room Supervisor has directed you to start A RCP per OTN-BB-00003, Section 4.1. WPA was restored to the OTN-BB-00003 required positions. Inform the Control Room Supervisor when the A Reactor Coolant Pump has been started and the lift oil pump is secured.
Time Critical Task:        NO Validation Time:            16 minutes 2005 NRC JPM S4                                                            NUREG 1021, Revision 9
Appendix C                    Job Performance Measure                    Form ES-C-1 Worksheet SIMULATOR SETUP NOTES:          Use IC-7. Secure A RCP, close A seal inj and leakoff with BB HIS-8351A and BB HIS-8141A.
Close A PZR Spray Valve and place in MANUAL Set Event 1 x21i115r.eq.true 1 is cv06a severity 8, 12 second ramp, 10 second delay 2005 NRC JPM S4                                              NUREG 1021, Revision 9
Appendix C                                  Page 3 of 11                        Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtain a verified working copy of OTN-BB-00003, Reactor Coolant Pumps.
Standard:                Operator should obtain procedure copy.
Comment:
Section 2 Performance Step: 2      Review the Precautions and Limitations of OTN-BB-00003.
Standard:                Operator should review the Precautions and Limitations.
Comment:
Evaluators Cue:          All Precautions and Limitations are satisfied.
Section 3 Performance Step: 3      Review the Initial Conditions of OTN-BB-00003.
Standard:                Operator should read the Initial Conditions.
Comment:
Evaluators Cue:          All Initial Conditions are satisfied.
NOTE Prior To Step 4.1.1 Performance Step: 4      If the position of the CCW Outlet Throttle Valves are known to have changed, perform Section 5.2.
Standard:                Operator may ask if the WPA altered CCW Outlet Throttle Valve Positions.
Comment:
Evaluators Cue:          The CCW Outlet Throttle Valves position did not change.
2005 NRC JPM S4                                                      NUREG 1021, Revision 9
Appendix C                            Page 4 of 11                          Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.1.1 Performance Step: 5 Initiate Seal Water Injection Flow to A RCP. OPEN the RCP Seal Injection Isolation Valve BB HV-8351A with BB-HIS-8351A.
Standard:          Operator should initiate seal water injection flow with BB HIS-8351A, RCP A Seal WTR INJ VLV, OPEN on RL021.
Comment:
Evaluators Cue:    BB HIS-8351A RED light goes ON and GREEN light goes OFF.
Step 4.1.1.2 Performance Step: 6 OPEN A RCP #1 Seal Leakoff Isolation Valve with Handswitch BB HIS-8141A.
Standard:          Operator should OPEN, RCP A Seal WTR Return VLV with BB HIS-8141A, on RL001.
Comment:
Evaluators Cue:    BB HIS-8141A RED light goes ON and GREEN light goes OFF.
Step 4.1.3 Performance Step: 7 Verify current OSP-BG-00005 or adjust the Seal Water Injection Throttle Valve (BG-V-198) to establish 8 GPM flow to all RCPs.
Standard:          Operator should determine seal flow on BB FR-157, RCP A Seal Leakoff and Injection Flow, on RL021 or verify OSP-BG-00005 is current.
Comment:
Evaluators Cue:    OSP-BG-00005 is current all RCPs show a flow of 8 gpm on the Blue Pen for BG FR-157, 156, 155, and 154.
2005 NRC JPM S4                                                NUREG 1021, Revision 9
Appendix C                            Page 5 of 11                          Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.3.1 Performance Step: 8  Verify A RCP Seal Differential Pressure is > 200 psid.
Standard:            Operator should read BB PI-153A, RCP A Seal DP, on RL021.
Comment:
Evaluators Cue:    A RCP DP indicates > 400 psid.
Step 4.1.3.2 Performance Step: 9  Annunciator 73A RCP #2 Seal Flow HI Alarm is CLEARED.
Standard:            Operator should determine status of annunciator 73A, RCP #2 Seal Flow HI Alarm is CLEARED.
Comment:
Evaluators Cue:    Annunciator 73A is NOT on.
Step 4.1.3.3 Performance Step: 10 Verify Annunciator 42C VCT pressure HI/LO is CLEARED.
Standard:            Operator should determine status of Annunciator 42C, VCT Press HI/LO, on RL018 is CLEARED.
Comment:
Evaluators Cue:    Annunciator 42C is NOT on.
Step 4.1.3.4 Performance Step: 11 Verify Annunciator 74D RCP Oil RSVR LEV HI/LO CLEARED.
Standard:            Operator should determine status of Annunciator 74D, RCP Oil RSVR LEV HI/LO, on RL022 is CLEARED.
Comment:
Evaluators Cue:    Annunciator 74D is NOT on.
2005 NRC JPM S4                                                NUREG 1021, Revision 9
Appendix C                            Page 6 of 11                      Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.3.5 Performance Step: 12 Verify Annunciator 71A, RCP #1 Seal dP LO CLEARED.
Standard:            Operator should determine status of Annunciator 71A, RCP #1 Seal DP LO, on RL022 is cleared.
Comment:
Evaluators Cue:    Annunciator 71A RCP #1 seal dP LO is NOT on.
Step 4.1.3.6 Performance Step: 13 Verify Annunciators 70 - 73E RCP A - D Standpipe LEV LO CLEARED.
Standard:            Operator should determine status of Annunciator 70E, RCP A Standpipe, LEV LO, on RL022 is CLEARED.
Comment:
Evaluators Cue:    Annunciator 70E is NOT on.
Step 4.1.3.7 Performance Step: 14 Verify Annunciators 70 - 73C RCP A - D THERM BAR CCW Flow CLEARED.
Standard:            Operator should determine status of Annunciator 70C, RCP A THERM BAR CCW Flow, on Rl022 is CLEARED.
Comment:
Evaluators Cue:    Annunciator 70C is NOT on.
Step 4.1.3.8 Performance Step: 15 Verify #1 Seal Backpressure  15 psig. (VCT pressure).
Standard:            Operator should obtain VCT pressure from BG PI-115 on RL002.
Comment:
Evaluators Cue:    VCT pressure indicates 32 psig on BG PI-115.
2005 NRC JPM S4                                              NUREG 1021, Revision 9
Appendix C                            Page 7 of 11                          Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.3.9 Performance Step: 16 Verify A RCP Seal Leakoff is within the NORMAL operating range of Figure 1 on Page 4 of Attachment 1.
Standard:            Operator should verify A RCP Seal Leakoff Flow is within the NORMAL operating range of Figure 1 on page 4 of Attachment 1.
Comment:
Evaluators Cue:    A RCP Seal Leakoff Return is within the NORMAL operating range.
Step 4.1.3.9 Performance Step: 17 Obtain A RCP Seal Leakoff Indication from BG FR-157.
Standard:            Operator should obtain A RCP Seal Leakoff Indication from BG FR-157.
Comment:
Evaluators Cue:    BG FR-157 indicates Seal Leakoff is at 3 gpm on the Green Pen, the Red Pen is FULL SCALE.
Step 4.1.4.1 Performance Step: 18 Dispatch someone to inspect A RCP and warn personnel in the vicinity.
Standard:            Operator not required to call due to no personnel in CTMT.
Comment:
Step 4.1.4.2 Performance Step: 19 Start A RCPs Oil Lift Pump with switch BB HIS-41.
Standard:            Operator should select RUN ON BB HIS-41, RCP A Lift Pump.
Comment:
Evaluators Cue:    BB HIS-41 RED light is ON, after 20 seconds, the WHITE light on A Oil Lift Pump goes ON.
2005 NRC JPM S4                                                NUREG 1021, Revision 9
Appendix C                            Page 8 of 11                        Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.4.3 Performance Step: 20 Allow the Oil Lift Pump to RUN for at least 2 minutes.
Standard:            Operator should wait two (2) minutes from start time before performing next step.
Comment:
Evaluators Cue:    Two (2) minutes has elapsed.
Step 4.1.4.6 Performance Step: 21 Make plant announcement: ATTENTION IN THE PLANT STARTING THE A RCP. STAND CLEAR OF THE PUMP AND PA01 SWITCHGEAR.
Standard:            Operator should make plant announcement about starting A RCP.
Should wait 10 - 15 seconds between announcement and starting pump.
Comment:
Step 4.1.4.7 Performance Step: 22 Start A RCP by using Switch BB HIS-37.
Standard:            Operator should select RUN on BB HIS-37, RCP A.
Comment:
Evaluators Cue:    A RCP BB HS-37 RED light is ON and GREEN light is OFF.
Step 4.1.4.5.1 Performance Step: 23 Monitor RCP starting current and running current.
Standard:            Operator should monitor BB-II-1, RCP A Amps, and observe starting current decay away on RL021 to less than 351 amps.
Comment:
2005 NRC JPM S4                                                NUREG 1021, Revision 9


OTN-BB-00 003, Reactor Coolant Pumps, Revision 15 Initiating Cu e: Tags have been cleared on PA0107 and signed off. The Control Room Supervisor has directed you to start "A" RCP per OTN-BB-00003, Section 4.1.
Appendix C                               Page 9 of 11                       Form ES-C-1 PERFORMANCE INFORMATION The following steps represent the alternate path of this JPM Performance Step: 24     Acknowledge annunciators.
WPA was restored to th e OTN-BB-00003 requir ed positions. I n form the Control Room Supervisor when the "A" Reactor Coolant Pump has been started an d the lift oil pump is secured.
Standard:               Operator should determine that control room annunciators 70B and 72A are received. 72A, RCP #1 SEAL FLO HI, is an unexpected alarm.
Time Critical Task:
Comment:
NO  Validation Time:
Evaluators Cue:
16 minutes 2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP    NOTE S: Use IC-7. Secure "A" RCP, close "A" seal inj a n d leakoff wit h BB HIS-8351A and BB HIS-814 1A. Close "A" PZR Spray Valve and place in MANUAL Set Event 1
Performance Step: 25     Determine RCP A #1 seal flow Standard:               Operator should observe recorder BG FR-157 and verify seal flow is > 5 GPM Comment:
'x21i115r.eq.true' 1 is cv06a severity 8, 12 second ramp, 10 secon d delay 2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 3 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
Evaluators Note:       Candidate MAY refer to the OTAs or OTO-BB-00002 to determine action required on high seal flow.
START TI ME:        Performanc e Step: 1 Obtain a verified working copy of OT N-BB-00003 , Reactor Coolant Pumps.
Performance Step: 26     Trip A RCP Standard:               Places RCP A control switch in STOP Comment:
S t a n d a r d: Operator should obtain procedure copy.
Terminating Cue:           When RCP A is stopped, this JPM is complete.
C o m m e n t:      Section 2 Performanc e Step: 2 Review the Precautions and Limitations of OTN-BB-00003.
STOP TIME:
S t a n d a r d: Operator should review the Precautions and Limitations.
2005 NRC JPM S4                                                   NUREG 1021, Revision 9
C o m m e n t:  Evaluator's Cue:
 
All Precauti ons and Limitations are satisfied.
Appendix C                           Page 10 of 11               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S4 Examinees Name:
Section 3 Performanc e Step: 3 Review the I n itial Conditions of OTN-BB-00003.
S t a n d a r d: Operator should read th e Initial Con d itions. C o m m e n t:  Evaluator's Cue:
All Initial Conditions are satisfied.
NOTE Prior To Step 4.1.1 Performanc e Step: 4 If the positio n of the CCW Outlet Throttle Valves are known to have changed, perform Section 5.2.
S t a n d a r d: Operator may ask if the WPA altered CCW Outl et Throttle Valve Positions.
C o m m e n t:  Evaluator's Cue:
The CCW Outlet Throttle Valves position did not change.
2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 4 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.1.1 Performanc e Step: 5 Initiate Seal Water Injection Flow to "A" RCP.
OPEN the RCP Seal Injectio n Isolation V a lve BB HV-8351A with BB-HIS-835 1A. S t a n d a r d: Operator should initiat e seal water injection f l ow with BB HIS-835 1A, RCP "A" Seal WTR INJ VLV, OPEN on RL02
: 1. C o m m e n t:  Evaluator's Cue:
BB HIS-835 1A RED lig ht goes ON and GREEN light goes OFF. Step 4.1.1.2 Performanc e Step: 6 OPEN "A" RCP #1 Seal Leakoff Isolation Valve with Handswitch BB HIS-814 1A. S t a n d a r d: Operator should OPEN, RCP "A" Se al WTR Return VLV with BB HIS-814 1A, on RL001.
C o m m e n t:  Evaluator's Cue:
BB HIS-814 1A RED lig ht goes ON and GREEN light goes OFF. Step 4.1.3 Performanc e Step: 7 Verify current OSP-BG-00005 or adj ust the Seal Water Injection Throttle Valve (BG-V-19
: 8) to establish 8 GPM fl ow to all RCP's.
S t a n d a r d: Operator should determine seal flow on BB FR-1 57, RCP "A" Seal Leakoff and Injectio n Flow, on RL021 or ve rify OSP-BG-00 005 is curre nt. C o m m e n t:  Evaluator's Cue:
OSP-BG-00 005 is current all RCP's sho w a flo w of 8 gpm on the Blue Pen for BG F R-157, 156, 155, and 154.
2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 5 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.3.1 Performanc e Step: 8 Verify "A" RCP Seal Differential Pre ssure is > 2 00 psid. S t a n d a r d: Operator should read BB PI-153A, RCP "A" Se al DP, on RL021.
C o m m e n t:  Evaluator's Cue:
"A" RCP DP indicates > 400 psid.
Step 4.1.3.2 Performanc e Step: 9 Annunciator 73A RCP #
2 Seal Flow HI Alarm is CLEARED.
S t a n d a r d: Operator should determine status of annunciator 73A, RCP #
2 Seal Flow HI Alarm is CLEARED.
C o m m e n t:  Evaluator's Cue:
Annunciator 73A is NOT on.
Step 4.1.3.3 Performanc e Step: 10 Verify Annu nciator 42C VCT pressure HI/LO is CLEARED.
S t a n d a r d: Operator should determine status of Annunciator 42C, VCT Press HI/LO, on RL018 is CLEARED.
C o m m e n t:  Evaluator's Cue:
Annunciator 42C is NOT on.
Step 4.1.3.4 Performanc e Step: 11 Verify Annu nciator 74D RCP Oil RS VR LEV HI/
L O CLEA R E D. S t a n d a r d: Operator should determine status of Annunciator 74D, RCP Oil RSVR L EV HI/LO, on RL022 is CLEARED.
C o m m e n t:  Evaluator's Cue:
Annunciator 74D is NOT on.
2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 6 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.3.5 Performanc e Step: 12 Verify Annu nciator 71A, RCP #1 Se al dP LO CL EARED. S t a n d a r d: Operator should determine status of Annunciator 71A, RCP #
1 Seal DP LO, on RL022 is cleared.
C o m m e n t:  Evaluator's Cue:
Annunciator 71A RCP
#1 seal dP LO is NOT on. Step 4.1.3.6 Performanc e Step: 13 Verify Annu nciators 70
- 73E RCP A - D Stand pipe LEV LO CLEARED. S t a n d a r d: Operator should determine status of Annunciator 70E, RCP "A" Standpipe, LEV LO, on RL022 is CLEARED.
C o m m e n t:  Evaluator's Cue:
Annunciator 70E is NOT on.
Step 4.1.3.7 Performanc e Step: 14 Verify Annu nciators 70
- 73C RCP A - D THERM BAR CCW Flow CLEA RED. S t a n d a r d: Operator should determine status of Annunciator 70C, RCP "A" THERM BAR CCW Flo w , on Rl022 is CLEARED.
C o m m e n t:  Evaluator's Cue:
Annunciator 70C is NOT on.
Step 4.1.3.8 Performanc e Step: 15 Verify #1 Se al Backpressure  15 psig.  (VCT pressure).
S t a n d a r d: Operator should obtain VCT pressure from BG PI-115 on RL002.
C o m m e n t:  Evaluator's Cue:
VCT pressu re indicates 32 psig on BG PI-115.
2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 7 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.3.9 Performanc e Step: 16 Verify "A" RCP Seal Leakoff is with in the NORMAL operating range of Fig u re 1 on Page 4 of Attachment 1.
S t a n d a r d: Operator should verify "A" RCP Seal Leakoff Flo w is within t he NORMAL o perating ran ge of Figure 1 on page 4 of Attachment 1.
C o m m e n t:  Evaluator's Cue:
"A" RCP Seal Leakoff Return is within the NORMAL operating range.
Step 4.1.3.9 Performanc e Step: 17 Obtain "A" RCP Seal Leakoff Indicat i on from BG FR-157.
S t a n d a r d: Operator should obtain "
A" RCP Seal Leakoff Ind i cation from BG FR-157.
C o m m e n t:  Evaluator's Cue:
BG FR-157 indicates Seal Leakoff is at 3 gpm on the Gree n Pen, the Red Pen is FULL SCALE.
Step 4.1.4.1 Performanc e Step: 18 Dispatch so meone to inspect "A" RCP and warn personnel in the vicinity.
S t a n d a r d: Operator not required to call due to no personne l in CTMT.
C o m m e n t:      Step 4.1.4.2  Performanc e Step: 19 Start "A" RCP's Oil Lift P u mp with switch BB HIS-41.
S t a n d a r d: Operator should select RUN ON BB HIS-41, RCP "A" Lift Pump.
C o m m e n t:  Evaluator's Cue:
BB HIS-41 RED light i s ON, after 20 seconds, the WHITE light on "A" Oil Lift Pump goes ON.
2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 8 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.1.4.3 Performanc e Step: 20 Allow the Oil Lift Pump to RUN for at least 2 minutes.
S t a n d a r d: Operator should wait two (2) minutes from start time before performing next step.
C o m m e n t:  Evaluator's Cue:
Tw o (2) min u tes has elapsed.
Step 4.1.4.6 Performanc e Step: 21 Make plant announcement:  ATTENTION IN THE PLANT STARTING THE "A" RCP. STAND CLEAR OF THE PUMP AND PA01 SWIT CHGEAR. S t a n d a r d: Operator should make plant announ cement about starting "
A" RCP. Should wait 10 - 15 seconds between announcement and starting pump.
C o m m e n t:      Step 4.1.4.7  Performanc e Step: 22 Start "A" RCP by using Switch BB HIS-37.
S t a n d a r d: Operator should select RUN on BB HIS-37, RCP "A".
C o m m e n t:  Evaluator's Cue:
"A" RCP BB HS-37 RE D light is ON and GREEN light is OFF.
Step 4.1.4.5.1 Performanc e Step: 23 Monitor RCP starting cu rrent and running curren
: t. S t a n d a r d: Operator should monitor BB-II-1, RCP "A" Amps, and observe starting curr ent decay away on RL0 21 to less th an 351 amps.
C o m m e n t:        2005 NRC J P M S4  NUREG 102 1, Revision 9 Appendix C Page 9 of 11 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  The follo w i ng steps represent the alternate path of this JPM Performanc e Step: 24 Acknowledge annunciat o rs. S t a n d a r d: Operator should determine that contr o l room annunciators 70 B and 72A are received. 72A, RCP #1 SEAL FLO HI, is an unexpected alarm.
C o m m e n t:   E v a l u a t o r's C u e:       Performanc e Step: 25 Determine RCP "A" #1 seal flow S t a n d a r d: Operator should observe recorder BG FR-157 a nd verify seal flow is > 5 GPM C o m m e n t:   Evaluator's Note:
Candidate MAY refer to the OTAs or OTO-BB-00002 to determine action required on high seal flo
: w.      Performanc e Step: 26 Trip "A" RCP S t a n d a r d: Places RCP "A" control switch in ST OP    C o m m e n t:     Terminating Cue:
When RCP "A" is stop ped, this JPM is comp l ete. STOP TI ME:     2005 NRC J P M S4 NUREG 102 1, Revision 9 Appendix C Page 10 of 11 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC J P M S4   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,592: Line 2,710:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S4 NUREG 102 1, Revision 9 Appendix C Page 11 of 11 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant is in mo de 3 at 557°F and 2235 psig. "A" Reactor Coolant Pump had been secured fo r breaker work on PA0107.
2005 NRC JPM S4                                         NUREG 1021, Revision 9
CCW is in operation and is supplying cooling wat e r to the Th ermal Barrier Cooling coils per OTN-EG-00 001. There are no personnel in CTMT at this time.
 
INITIATING CUE: Tags have been cleared on PA0107 and signed off. The Control Room Supe rvisor has directed you to start "A" RCP per OTN-BB-00 003, Section 4.1. WPA was restored to the OTN-BB-00 003 require d position
Appendix C                           Page 11 of 11                     Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant is in mode 3 at 557°F and 2235 psig. A Reactor Coolant Pump had been secured for breaker work on PA0107.
: s. Inform the Control Room Supervisor when the "A" Reactor Coolant Pump has been started and the lift o il pump is se cured. 2005 NRC J P M S4 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
CCW is in operation and is supplying cooling water to the Thermal Barrier Cooling coils per OTN-EG-00001. There are no personnel in CTMT at this time.
: Place Steam Du mps in Steam Pressure Mode JPM No.: 2005 NRC J P M S5     K/A Referen c e: 041 A4.08 3.0 / 3.1 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
INITIATING CUE:     Tags have been cleared on PA0107 and signed off. The Control Room Supervisor has directed you to start A RCP per OTN-BB-00003, Section 4.1. WPA was restored to the OTN-BB-00003 required positions. Inform the Control Room Supervisor when the A Reactor Coolant Pump has been started and the lift oil pump is secured.
Date: Method of testing:
2005 NRC JPM S4                                           NUREG 1021, Revision 9
Simulated Performance:
 
Actual Performance:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant is shutt i ng down for a fall outage. Reactor power is approximate l y 17.5%. The crew is p e rforming OTG-ZZ-00005.
Task
Task Stand ard: Upon completion of this JPM, the operator has placed the ste a m dumps in the steam pressure mode and the n closed the failed stea m dumps prior to causing the stea m dumps to close due to Permissive P-12 (LO LO TAVE - 550°F)
 
Required Materials:
==Title:==
None   General  
Place Steam Dumps in Steam             JPM No.:     2005 NRC JPM S5 Pressure Mode K/A  
 
==Reference:==
041 A4.08       3.0 / 3.1 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator      X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant is shutting down for a fall outage. Reactor power is approximately 17.5%. The crew is performing OTG-ZZ-00005.
Task Standard:             Upon completion of this JPM, the operator has placed the steam dumps in the steam pressure mode and then closed the failed steam dumps prior to causing the steam dumps to close due to Permissive P-12 (LO LO TAVE - 550°F)
Required Materials:         None General  


==References:==
==References:==
OTN-AB-00001, Main Steam System, Revision 13 Initiating Cue:            The Control Room Supervisor has directed you to verify the Steam Dump Controller, AB PK-507, is set for 1092 PSIG, then transfer the Steam Dump Selector switch to the Steam Pressure Mode per OTN-AB-00001, Main Steam System, Section 4.5 and inform the CRS when done.
Time Critical Task:        NO Validation Time:            9 minutes 2005 NRC JPM S5                                                            NUREG 1021, Revision 9


OTN-AB-00 001, Main Steam Syste m , Re vision 13 Initiating Cu e: The Control Room Supe rvisor has directed you to verify the Steam Dump Controller, AB PK-507, is set f o r 1092 PSIG, then transfer the Steam Du mp Selector switch to the Steam Pres sure Mode per OTN-AB-00001, Main Steam System, Section 4.5 and infor m the CRS when done. Time Critical Task:
Appendix C                     Job Performance Measure               Form ES-C-1 Worksheet SIMULATOR SETUP Use IC- 68 password redsox Use event trigger mode and set X05I162S.EQ.TRUE.SET Malfunction MSS13b to AB PT-507 reading 1500 psig, 90 second ramp, 0 second time delay, set to event trigger.
NO  Validation Time:
9 minutes 2005 NRC J P M S5  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP     Use IC- 68 password redsox Use event trigger mode and set X 05I162S.EQ.T RUE.SET Malfunction MSS13b to AB PT-507 reading 1500 psig, 90 se cond ramp, 0 second time delay, set to event trigger.
Ensure AB PK-0507 is set at something other than 7.28.
Ensure AB PK-0507 is set at something other than 7.28.
2005 NRC J P M S5 NUREG 102 1, Revision 9 Appendix C Page 3 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
2005 NRC JPM S5                                           NUREG 1021, Revision 9
START TI ME:       Performanc e Step: 1 Obtain a verified working copy of OT N-AB-00001 , Main Steam System. S t a n d a r d: Operator should obtain a procedure copy. C o m m e n t:     Section 2.0 Performanc e Step: 2 Review the Precautions and Limitations of OTN-AB-00001.
 
S t a n d a r d: Operator should read th e Precautio ns and Limit a tions. C o m m e n t:   Evaluator's Cue:
Appendix C                                   Page 3 of 7                       Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
All Precauti ons and Limitations are satisfied.
START TIME:
Section 3.0 Performanc e Step: 3 Review the I n itial Conditions of OTN-AB-00001.
Performance Step: 1       Obtain a verified working copy of OTN-AB-00001, Main Steam System.
S t a n d a r d: Operator should read th e Initial Con d itions. C o m m e n t:   Evaluator's Cue:
Standard:                 Operator should obtain a procedure copy.
All Initial Conditions are satisfied.
Comment:
Ask if the operator understands the Initial con ditions and Initiating Cues.
Section 2.0 Performance Step: 2       Review the Precautions and Limitations of OTN-AB-00001.
Performanc e Step: 4 The operator may verify AB PK-0507 is set for 10 92 psig. S t a n d a r d: OOA-RL-00 004 states t hat 1092 psig = 7.28.
Standard:                 Operator should read the Precautions and Limitations.
C o m m e n t:   2005 NRC J P M S5 NUREG 102 1, Revision 9 Appendix C Page 4 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    NOTE: CAUTION prior to Step 4.5.1 Performanc e Step: 5 Ensure Steam Header Pressure Controller AB PK-507 matches steam dump demand AB UI-500.
Comment:
S t a n d a r d: Operator should ensure AB PK-507 Steam Head er Pressure Controller matches AB UI-500.
Evaluators Cue:         All Precautions and Limitations are satisfied.
C o m m e n t:     Step 4.5.1 Performanc e Step: 6 Place the Steam Du mp Selector Switch AB US-0 500Z to Reset.
Section 3.0 Performance Step: 3       Review the Initial Conditions of OTN-AB-00001.
S t a n d a r d: Operator should place S t eam Du mp Selector Switch AB US-0500 Z to Reset.
Standard:                 Operator should read the Initial Conditions.
C o m m e n t:     Step 4.5.1 Performanc e Step: 7 Place the Steam Du mp Selector Switch AB US-0 500Z to the Steam Pres sure Mode.
Comment:
S t a n d a r d: Operator should place t he Steam Dump Selector Switch AB US-0500 Z to the Steam Pressure Mode.
Evaluators Cue:         All Initial Conditions are satisfied.
NOTE: When operator notices the steam dump failure, he ma y then omit Steps 8 and 9 and continue with Step 10.
Ask if the operator understands the Initial conditions and Initiating Cues.
C o m m e n t:       Step 4.5.1.1 Performanc e Step: 8 Verify C-7, L o ss of Load Interlock L i g h t is OFF.
Performance Step: 4       The operator may verify AB PK-0507 is set for 1092 psig.
S t a n d a r d: Operator should verify C-7, Loss of L oad Interlock Light is OFF on SC066W Panel.
Standard:                 OOA-RL-00004 states that 1092 psig = 7.28.
C o m m e n t:   2005 NRC J P M S5 NUREG 102 1, Revision 9 Appendix C Page 5 of 7 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.5.2 Performanc e Step: 9 Operator may inquire if cooldown is required.
Comment:
S t a n d a r d: Operator may ask if a plant cooldow n is required
2005 NRC JPM S5                                                     NUREG 1021, Revision 9
. C o m m e n t:   Evaluator's Cue:
 
Respond by informing the operator that a cooldo w n is n o t required at this time.
Appendix C                           Page 4 of 7                         Form ES-C-1 PERFORMANCE INFORMATION NOTE: CAUTION prior to Step 4.5.1 Performance Step: 5 Ensure Steam Header Pressure Controller AB PK-507 matches steam dump demand AB UI-500.
Note: The follo w i ng st eps represent the alternate path of this JPM Performanc e Step: 10 Place Steam Du mp Interlock Select Switches AB HS-63, 64 in the OFF/RESET positio
Standard:           Operator should ensure AB PK-507 Steam Header Pressure Controller matches AB UI-500.
: n. S t a n d a r d: Operator should place b o th Steam Dump Selector Switches AB HAS-63, 64 in the OFF position.
Comment:
Operator should CLOSE Steam Du mps by any means prior to Steam Du mps automatically closing at 550°F due to P-12, LO LO Ta ve. (May also go back to T a ve Mode)     C o m m e n t:       Terminating Cue:
Step 4.5.1 Performance Step: 6 Place the Steam Dump Selector Switch AB US-0500Z to Reset.
When Steam Dumps are closed, this JPM is complete.
Standard:           Operator should place Steam Dump Selector Switch AB US-0500Z to Reset.
STOP TI ME:     2005 NRC J P M S5 NUREG 102 1, Revision 9 Appendix C Page 6 of 7 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Comment:
2005 NRC J P M S5   Exa m inee's Name:
Step 4.5.1 Performance Step: 7 Place the Steam Dump Selector Switch AB US-0500Z to the Steam Pressure Mode.
Standard:           Operator should place the Steam Dump Selector Switch AB US-0500Z to the Steam Pressure Mode.
NOTE:               When operator notices the steam dump failure, he may then omit Steps 8 and 9 and continue with Step 10.
Comment:
Step 4.5.1.1 Performance Step: 8 Verify C-7, Loss of Load Interlock Light is OFF.
Standard:           Operator should verify C-7, Loss of Load Interlock Light is OFF on SC066W Panel.
Comment:
2005 NRC JPM S5                                               NUREG 1021, Revision 9
 
Appendix C                                 Page 5 of 7                       Form ES-C-1 PERFORMANCE INFORMATION Step 4.5.2 Performance Step: 9     Operator may inquire if cooldown is required.
Standard:               Operator may ask if a plant cooldown is required.
Comment:
Evaluators Cue:         Respond by informing the operator that a cooldown is not required at this time.
Note: The following steps represent the alternate path of this JPM Performance Step: 10     Place Steam Dump Interlock Select Switches AB HS-63, 64 in the OFF/RESET position.
Standard:               Operator should place both Steam Dump Selector Switches AB HAS-63, 64 in the OFF position.
Operator should CLOSE Steam Dumps by any means prior to Steam Dumps automatically closing at 550°F due to P-12, LO LO Tave. (May also go back to Tave Mode)
Comment:
Terminating Cue:           When Steam Dumps are closed, this JPM is complete.
STOP TIME:
2005 NRC JPM S5                                                   NUREG 1021, Revision 9
 
Appendix C                             Page 6 of 7               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S5 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,648: Line 2,796:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S5 NUREG 102 1, Revision 9 Appendix C Page 7 of 7 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant is shutt i ng down for a fall outage. Reactor power is approximately 17.5%. The crew is performing OTG-ZZ-00 005. INITIATING CUE: The Control Room Supe rv isor has directed you to verify the Steam Du mp Controller, AB PK-507, is set for 10 92 PSIG, th en transfer the Steam Du mp Selector switch to the Steam Pres sure Mode per OTN-AB-0000 1, Main Steam System, Section 4.5 and inform the CRS when do ne. 2005 NRC J P M S5 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
2005 NRC JPM S5                                         NUREG 1021, Revision 9
: Placing Containment H2 Analyzer In Service JPM No.: 2005 NRC J P M S6     K/A Referen c e: 028 A4.03 3.1 / 3.3 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
 
Date: Method of testing:
Appendix C                           Page 7 of 7                         Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant is shutting down for a fall outage. Reactor power is approximately 17.5%. The crew is performing OTG-ZZ-00005.
Simulated Performance:
INITIATING CUE:     The Control Room Supervisor has directed you to verify the Steam Dump Controller, AB PK-507, is set for 1092 PSIG, then transfer the Steam Dump Selector switch to the Steam Pressure Mode per OTN-AB-00001, Main Steam System, Section 4.5 and inform the CRS when done.
Actual Performance:
2005 NRC JPM S5                                             NUREG 1021, Revision 9
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant has experienced a L a rge Loss of Coolant Accident. A Safety Injection has occurred.
 
Task Stand ard: Upon completion of this JPM, the operator will h a ve placed "A" hydrogen analyzer in-service.
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
Required Materials:
Task
None   General  
 
==Title:==
Placing Containment H2 Analyzer In     JPM No.:     2005 NRC JPM S6 Service K/A  
 
==Reference:==
028 A4.03       3.1 / 3.3 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator      X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.
Task Standard:             Upon completion of this JPM, the operator will have placed A hydrogen analyzer in-service.
Required Materials:         None General  


==References:==
==References:==
OTN-GS-00001, Containment Hydrogen Control System, Revision 10 Initiating Cue:            The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.
Time Critical Task:        NO Validation Time:            10 minutes 2005 NRC JPM S6                                                            NUREG 1021, Revision 9
Appendix C                    Job Performance Measure          Form ES-C-1 Worksheet Simulator Setup Reset to IC-184 CTMT H2 Indication Set Malf Meter
* GSAI19
* Ramp Start=0
* Ramp Time=60 Sec
* Delay Time=15 Sec
* Value=1.5
* Event Trigger=1
* Set Event Trigger 1
* 1=X20I36A 2005 NRC JPM S6                                        NUREG 1021, Revision 9
Appendix C                                  Page 3 of 10                      Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtain a verified working copy of OTN-GS-0001.
Standard:                Operator should obtain procedure copy.
Comment:
Section 2 Performance Step: 2      Review Precautions and Limitations.
Standard:                Operator should review Precautions and Limitations.
Comment:
Evaluators Cue:          All Precautions and Limitations are satisfied.
Step 4.2.1 Performance Step: 3      Ensure Section 4.1, Pre-service Startup and Standby Alignment of hydrogen analyzers is complete.
Standard:                Operator may verify Section 4.1 has been completed.
NOTE:                    Given in Initial Conditions.
Comment:
Evaluators Cue:          Section 4.1 has been completed.
2005 NRC JPM S6                                                      NUREG 1021, Revision 9
Appendix C                            Page 4 of 10                      Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.2 Performance Step: 4 Ensure the H2 mixing fans and CTMT coolers re in service.
Standard:          Operator should verify H2 mixing fans and CTMT coolers are in service.
Comment:
Evaluators Cue:    All H2 mixing fans and CTMT coolers are in service.
Step 4.2.3 Performance Step: 5 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves place GS HIS-40 in Non-Iso.
Standard:          Operator should place GS HIS-40, Hydrogen Analyzer A CTMT ISO Valve, in Non-Iso located on RL011.
NOTE:              Steps 5 and 6 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-40 is in the Non-Iso position.
Step 4.2.3 Performance Step: 6 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves, place GS HIS-42 in the Non-Iso position.
Standard:          Operator should place GS HIS-42, Hydrogen Analyzer A CTMT ISO Valve in Non-Iso.
NOTE:              Steps 5 and 6 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-42 is in the Non-Iso position.
2005 NRC JPM S6                                              NUREG 1021, Revision 9
Appendix C                          Page 5 of 10                    Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 7 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-13 with pushbutton GS HIS-13.
Standard:          Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS-HV-13 with pushbutton GS HIS-13.
NOTE:              Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-13 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.4 Performance Step: 8 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.
Standard:          Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.
NOTE:              Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-14 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.4 Performance Step: 9 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.
Standard:          Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.
NOTE:              Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-12 shows RED light goes ON and GREEN light goes OFF.
2005 NRC JPM S6                                          NUREG 1021, Revision 9
Appendix C                            Page 6 of 10                      Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 10 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.
Standard:            Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.
NOTE:                Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-17 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.4 Performance Step: 11 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.
Standard:            Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.
NOTE:                Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-18 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.6 Performance Step: 12 Place Hydrogen Analyzer A in the ANLYZ position by taking switch GS HIS-16A for SGS02A to ANLYZ.
Standard:            Operator should take switch GS HIS-16A to ANLYZ on RL020 Comment:
2005 NRC JPM S6                                              NUREG 1021, Revision 9
Appendix C                            Page 7 of 10                        Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.6.1 Performance Step: 13 Monitor GS AI-19 for hydrogen concentration.
Standard:            Operator should monitor GS AI-19 for hydrogen concentration.
Comment:            Meter will begin to deflect 15 seconds after placing GS HIS-16 in ANALYZ Evaluators Cue:    Hydrogen concentration indicates approximately 0% on GS AI-19.
Step 4.2.6.1 Note b Performance Step: 14 Verify Hydrogen Analyzer SGS02A was in the Standby Lineup.
Standard:            Operator may verify A Hydrogen Analyzer was in the Standby Lineup.
Comment:
Evaluators Cue:    Note A Hydrogen analyzer was in the Standby Position.
Step 4.2.6.1 Note b Performance Step: 15 Wait for a 15 minute warmup period prior to taking data.
Standard:            Operator should wait a minimum of 15 minutes for A hydrogen analyzer use.
Comment:            Ensure meter has risen to 1 - 1.5% before continuing Evaluators Cue:    Over 15 minutes has gone by.
Step 4.2.6.1 Performance Step: 16 Monitor containment hydrogen concentration on GS AI-19.
Standard:            Operator should monitor GS AI-19 for hydrogen concentration.
Comment:
Evaluators Cue:    GS AI-19 shows hydrogen concentration to be at 1.5%.
2005 NRC JPM S6                                              NUREG 1021, Revision 9
Appendix C                      Page 8 of 10                  Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: When the candidate has determined that H2 concentration is 1.5, this JPM is complete.
STOP TIME:
2005 NRC JPM S6                                  NUREG 1021, Revision 9


OTN-GS-00 001, Contai nment Hydrogen Control System, Revision 10 Initiating Cu e: The Control Room Supe rvisor has directed you to place the "
Appendix C                             Page 9 of 10               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S6 Examinees Name:
A" Containmen t Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alig nment of hydrogen analyzers has already been completed, (Section 4.
1). Inform the Control room Supervisor when SGS02A is in service.
Time Critical Task:
NO  Validation Time:
10 minutes 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup Reset to IC-184 CTMT H2 In dication  Set Malf Me ter  GSAI19  Ramp Start=0  Ramp Time=60 Sec  Delay Time
=15 Sec  Value=1.5 Event Trigger=1 Set Event Trigger 1 1=X 20I36A 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 3 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
START TI ME:        Performanc e Step: 1 Obtain a verified working copy of OT N-GS-0001.
S t a n d a r d: Operator should obtain procedure copy.
C o m m e n t:      Section 2 Performanc e Step: 2 Review Pre c autions an d Limitation
: s. S t a n d a r d: Operator should review Precautions and Limitations.
C o m m e n t:  E v a l u a t o r's C u e: All Precautions and Limitations are satisfied. Step 4.2.1 Performanc e Step: 3 Ensure Section 4.1, Pre-service Startup and Standby Alignme n t of hydrogen analyzers is complete.
S t a n d a r d: Operator may verif y Se ction 4.1 ha s been completed.
NOTE: Given in Initial Conditions.
C o m m e n t:  Evaluator's Cue:
Section 4.1 has been completed.
2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 4 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.2 Performanc e Step: 4 Ensure the H2 mixing fa ns and CTMT coolers re in service.
S t a n d a r d: Operator should verify H2 mixing fans and CTMT coolers are in serv ice. C o m m e n t:  Evaluator's Cue:
All H2 mixing fans and CTMT co olers are in service.
Step 4.2.3 Performanc e Step: 5 Restore ele c trical powe r to Hydroge n Analyzer "A" CTMT ISO Valves place GS HIS-4 0 in Non-Iso
. S t a n d a r d: Operator should place GS HIS-40, Hydrogen Analyzer "A" CTMT ISO Valve, i n Non-Iso lo cated on RL011.
NOTE: Steps 5 and 6 ma y be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-40 i s in the Non-Iso position.
Step 4.2.3 Performanc e Step: 6 Restore ele c trical powe r to Hydroge n Analyzer "A" CTMT ISO Valves, place GS HIS-4 2 in the Non-Iso position
. S t a n d a r d: Operator should place GS HIS-42, Hydrogen Analyzer "A" CTMT ISO Valve in Non-Iso.
NOTE: Steps 5 and 6 ma y be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-42 i s in the Non-Iso position.
2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 5 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.4  Performanc e Step: 7 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 3 with pushbu tton GS HIS-13.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS-HV-13 with pushbutton GS HIS-13.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-13 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.4  Performanc e Step: 8 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 4 with pushbu tton GS HIS-14.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-14 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.4  Performanc e Step: 9 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 2 with pushbu tton GS HIS-12.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-12 shows RED light goes ON and GREEN light g oes OFF. 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 6 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.4  Performanc e Step: 10 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 7 with pushbu tton GS HIS-17.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-17 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.4  Performanc e Step: 11 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 8 with pushbu tton GS HIS-18.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-18 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.6  Performanc e Step: 12 Place Hydro gen Analyzer "A" in the ANLYZ position by takin g switch GS HIS-16A for SGS02A to "ANLYZ".
S t a n d a r d: Operator should take sw itch GS HIS-16A to "ANL YZ" on RL020 C o m m e n t:    2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 7 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.6.1 Performanc e Step: 13 Monitor GS AI-19 for hydrogen concentration.
S t a n d a r d: Operator should monitor GS AI-19 fo r hydrogen concentration. Comment: Meter w ill b egin to deflect 15 seconds after placing GS HIS-16 in ANAL YZ  Evaluator's Cue:
Hy d r ogen concentration indicates approximatel y 0% on GS AI-19. Step 4.2.6.1 Note b Performanc e Step: 14 Verify Hydro gen Analyzer SGS02A was in the Sta ndby Lineup.
S t a n d a r d: Operator may verif y "A" Hydrogen Analyzer was in the Stand by Lineup. C o m m e n t:  Evaluator's Cue:
Note "A" Hy drogen an al y z er w as i n the Standb y Position. Step 4.2.6.1 Note b Performanc e Step: 15 Wait for a 1 5 minute warmup period prior to taking data.
S t a n d a r d: Operator should wait a minimu m of 15 minutes for "A" hydro gen analyzer use.
Comment: Ensure meter has risen to 1 - 1.5%
b e fore c ontinuing Evaluator's Cue:
Over 15 mi nutes has gone b
: y. Step 4.2.6.1 Performanc e Step: 16 Monitor containment hyd r ogen conce n tration on GS AI-19.
S t a n d a r d: Operator should monitor GS AI-19 fo r hydrogen concentration. C o m m e n t:  Evaluator's Cue:
GS AI-19 s how s hy d r ogen concentration to be at 1.5
%. 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 8 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  Terminating Cue:
When the candidate has determined that H2 concentration is 1.5, this JPM is complete.
STOP TI ME:    2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 9 of 10 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC J P M S6   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,728: Line 2,924:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S6 NUREG 102 1, Revision 9 Appendix C Page 10 of 10 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant has experienced a L a rge Loss of Coolant Accident. A Safety Injection has occurred.
2005 NRC JPM S6                                         NUREG 1021, Revision 9
INITIATING CUE: The Control Room Supe rvis or has directed you to place the "
 
A" Containmen t Hydrogen Analyzer, SGS02A, in service per OTN-GS-00 001, Section 4.2. The pr e-service st artup and standby alig nment of hydr ogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS0 2A is in serv ice. 2005 NRC J P M S6 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
Appendix C                         Page 10 of 10                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.
: Placing Containment H2 Analyzer In Service JPM No.: 2005 NRC J P M S6     K/A Referen c e: 028 A4.03 3.1 / 3.3 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
INITIATING CUE:     The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.
Date: Method of testing:
2005 NRC JPM S6                                           NUREG 1021, Revision 9
Simulated Performance:
 
Actual Performance:
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant has experienced a L a rge Loss of Coolant Accident. A Safety Injection has occurred.
Task
Task Stand ard: Upon completion of this JPM, the operator will h a ve placed "A" hydrogen analyzer in-service.
 
Required Materials:
==Title:==
None   General  
Placing Containment H2 Analyzer In     JPM No.:     2005 NRC JPM S6 Service K/A  
 
==Reference:==
028 A4.03       3.1 / 3.3 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator      X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.
Task Standard:             Upon completion of this JPM, the operator will have placed A hydrogen analyzer in-service.
Required Materials:         None General  


==References:==
==References:==
OTN-GS-00001, Containment Hydrogen Control System, Revision 10 Initiating Cue:            The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.
Time Critical Task:        NO Validation Time:            10 minutes 2005 NRC JPM S6                                                            NUREG 1021, Revision 9
Appendix C                    Job Performance Measure          Form ES-C-1 Worksheet Simulator Setup Reset to IC-184 CTMT H2 Indication Set Malf Meter
* GSAI19
* Ramp Start=0
* Ramp Time=60 Sec
* Delay Time=15 Sec
* Value=1.5
* Event Trigger=1
* Set Event Trigger 1
* 1=X20I36A 2005 NRC JPM S6                                        NUREG 1021, Revision 9
Appendix C                                  Page 3 of 10                      Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtain a verified working copy of OTN-GS-0001.
Standard:                Operator should obtain procedure copy.
Comment:
Section 2 Performance Step: 2      Review Precautions and Limitations.
Standard:                Operator should review Precautions and Limitations.
Comment:
Evaluators Cue:          All Precautions and Limitations are satisfied.
Step 4.2.1 Performance Step: 3      Ensure Section 4.1, Pre-service Startup and Standby Alignment of hydrogen analyzers is complete.
Standard:                Operator may verify Section 4.1 has been completed.
NOTE:                    Given in Initial Conditions.
Comment:
Evaluators Cue:          Section 4.1 has been completed.
2005 NRC JPM S6                                                      NUREG 1021, Revision 9
Appendix C                            Page 4 of 10                      Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.2 Performance Step: 4 Ensure the H2 mixing fans and CTMT coolers re in service.
Standard:          Operator should verify H2 mixing fans and CTMT coolers are in service.
Comment:
Evaluators Cue:    All H2 mixing fans and CTMT coolers are in service.
Step 4.2.3 Performance Step: 5 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves place GS HIS-40 in Non-Iso.
Standard:          Operator should place GS HIS-40, Hydrogen Analyzer A CTMT ISO Valve, in Non-Iso located on RL011.
NOTE:              Steps 5 and 6 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-40 is in the Non-Iso position.
Step 4.2.3 Performance Step: 6 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves, place GS HIS-42 in the Non-Iso position.
Standard:          Operator should place GS HIS-42, Hydrogen Analyzer A CTMT ISO Valve in Non-Iso.
NOTE:              Steps 5 and 6 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-42 is in the Non-Iso position.
2005 NRC JPM S6                                              NUREG 1021, Revision 9
Appendix C                          Page 5 of 10                    Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 7 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-13 with pushbutton GS HIS-13.
Standard:          Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS-HV-13 with pushbutton GS HIS-13.
NOTE:              Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-13 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.4 Performance Step: 8 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.
Standard:          Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.
NOTE:              Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-14 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.4 Performance Step: 9 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.
Standard:          Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.
NOTE:              Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-12 shows RED light goes ON and GREEN light goes OFF.
2005 NRC JPM S6                                          NUREG 1021, Revision 9
Appendix C                            Page 6 of 10                      Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 10 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.
Standard:            Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.
NOTE:                Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-17 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.4 Performance Step: 11 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.
Standard:            Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.
NOTE:                Steps 7 through 11 may be performed in any order.
Comment:
Evaluators Cue:    GS HIS-18 shows RED light goes ON and GREEN light goes OFF.
Step 4.2.6 Performance Step: 12 Place Hydrogen Analyzer A in the ANLYZ position by taking switch GS HIS-16A for SGS02A to ANLYZ.
Standard:            Operator should take switch GS HIS-16A to ANLYZ on RL020 Comment:
2005 NRC JPM S6                                              NUREG 1021, Revision 9


OTN-GS-00 001, Contai nment Hydrogen Control System, Revision 10 Initiating Cu e: The Control Room Supe rvisor has directed you to place the "
Appendix C                             Page 7 of 10                       Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.6.1 Performance Step: 13 Monitor GS AI-19 for hydrogen concentration.
A" Containmen t Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alig nment of hydrogen analyzers has already been completed, (Section 4.
Standard:           Operator should monitor GS AI-19 for hydrogen concentration.
1). Inform the Control room Supervisor when SGS02A is in service.
Comment:             Meter will begin to deflect 15 seconds after placing GS HIS-16 in ANALYZ Evaluators Cue:     Hydrogen concentration indicates approximately 0% on GS AI-19.
Time Critical Task:
Step 4.2.6.1 Note b Performance Step: 14 Verify Hydrogen Analyzer SGS02A was in the Standby Lineup.
NO  Validation Time:
Standard:           Operator may verify A Hydrogen Analyzer was in the Standby Lineup.
10 minutes 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup Reset to IC-184 CTMT H2 In dication  Set Malf Me ter  GSAI19  Ramp Start=0  Ramp Time=60 Sec  Delay Time
Comment:
=15 Sec  Value=1.5 Event Trigger=1 Set Event Trigger 1 1=X 20I36A 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 3 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
Evaluators Cue:     Note A Hydrogen analyzer was in the Standby Position.
START TI ME:        Performanc e Step: 1 Obtain a verified working copy of OT N-GS-0001.
Step 4.2.6.1 Note b Performance Step: 15 Wait for a 15 minute warmup period prior to taking data.
S t a n d a r d: Operator should obtain procedure copy.
Standard:           Operator should wait a minimum of 15 minutes for A hydrogen analyzer use.
C o m m e n t:      Section 2 Performanc e Step: 2 Review Pre c autions an d Limitation
Comment:             Ensure meter has risen to 1 - 1.5% before continuing Evaluators Cue:     Over 15 minutes has gone by.
: s. S t a n d a r d: Operator should review Precautions and Limitations.
Step 4.2.6.1 Performance Step: 16 Monitor containment hydrogen concentration on GS AI-19.
C o m m e n t:  E v a l u a t o r's C u e: All Precautions and Limitations are satisfied. Step 4.2.1 Performanc e Step: 3 Ensure Section 4.1, Pre-service Startup and Standby Alignme n t of hydrogen analyzers is complete.
Standard:           Operator should monitor GS AI-19 for hydrogen concentration.
S t a n d a r d: Operator may verif y Se ction 4.1 ha s been completed.
Comment:
NOTE: Given in Initial Conditions.
Evaluators Cue:     GS AI-19 shows hydrogen concentration to be at 1.5%.
C o m m e n t:  Evaluator's Cue:
2005 NRC JPM S6                                               NUREG 1021, Revision 9
Section 4.1 has been completed.
 
2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 4 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.2 Performanc e Step: 4 Ensure the H2 mixing fa ns and CTMT coolers re in service.
Appendix C                     Page 8 of 10                 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: When the candidate has determined that H2 concentration is 1.5, this JPM is complete.
S t a n d a r d: Operator should verify H2 mixing fans and CTMT coolers are in serv ice. C o m m e n t:  Evaluator's Cue:
STOP TIME:
All H2 mixing fans and CTMT co olers are in service.
2005 NRC JPM S6                                   NUREG 1021, Revision 9
Step 4.2.3 Performanc e Step: 5 Restore ele c trical powe r to Hydroge n Analyzer "A" CTMT ISO Valves place GS HIS-4 0 in Non-Iso
 
. S t a n d a r d: Operator should place GS HIS-40, Hydrogen Analyzer "A" CTMT ISO Valve, i n Non-Iso lo cated on RL011.
Appendix C                             Page 9 of 10               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S6 Examinees Name:
NOTE: Steps 5 and 6 ma y be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-40 i s in the Non-Iso position.
Step 4.2.3 Performanc e Step: 6 Restore ele c trical powe r to Hydroge n Analyzer "A" CTMT ISO Valves, place GS HIS-4 2 in the Non-Iso position
. S t a n d a r d: Operator should place GS HIS-42, Hydrogen Analyzer "A" CTMT ISO Valve in Non-Iso.
NOTE: Steps 5 and 6 ma y be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-42 i s in the Non-Iso position.
2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 5 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.4  Performanc e Step: 7 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 3 with pushbu tton GS HIS-13.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS-HV-13 with pushbutton GS HIS-13.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-13 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.4  Performanc e Step: 8 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 4 with pushbu tton GS HIS-14.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-14 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.4  Performanc e Step: 9 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 2 with pushbu tton GS HIS-12.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-12 shows RED light goes ON and GREEN light g oes OFF. 2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 6 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.4  Performanc e Step: 10 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 7 with pushbu tton GS HIS-17.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-17 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.4  Performanc e Step: 11 Open "A" Hydrogen Analyzer CTMT I s olation Valve GS HV-1 8 with pushbu tton GS HIS-18.
S t a n d a r d: Operator should OPEN "A" Hydroge n Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.
NOTE: Steps 7 through 11 may be performed in an y order. C o m m e n t:  Evaluator's Cue:
GS HIS-18 shows RED light goes ON and GREEN light g oes OFF. Step 4.2.6  Performanc e Step: 12 Place Hydro gen Analyzer "A" in the ANLYZ position by takin g switch GS HIS-16A for SGS02A to "ANLYZ".
S t a n d a r d: Operator should take sw itch GS HIS-16A to "ANL YZ" on RL020 C o m m e n t:    2005 NRC J P M S6  NUREG 102 1, Revision 9 Appendix C Page 7 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 4.2.6.1 Performanc e Step: 13 Monitor GS AI-19 for hydrogen concentration.
S t a n d a r d: Operator should monitor GS AI-19 fo r hydrogen concentration. Comment: Meter w ill b egin to deflect 15 seconds after placing GS HIS-16 in ANAL YZ  Evaluator's Cue:
Hy d r ogen concentration indicates approximatel y 0% on GS AI-19. Step 4.2.6.1 Note b Performanc e Step: 14 Verify Hydro gen Analyzer SGS02A was in the Sta ndby Lineup.
S t a n d a r d: Operator may verif y "A" Hydrogen Analyzer was in the Stand by Lineup. C o m m e n t:   Evaluator's Cue:
Note "A" Hy drogen an al y z er w as i n the Standb y Position. Step 4.2.6.1 Note b Performanc e Step: 15 Wait for a 1 5 minute warmup period prior to taking data.
S t a n d a r d: Operator should wait a minimu m of 15 minutes for "A" hydro gen analyzer use.
Comment: Ensure meter has risen to 1 - 1.5%
b e fore c ontinuing Evaluator's Cue:
Over 15 mi nutes has gone b
: y. Step 4.2.6.1 Performanc e Step: 16 Monitor containment hyd r ogen conce n tration on GS AI-19.
S t a n d a r d: Operator should monitor GS AI-19 fo r hydrogen concentration. C o m m e n t:   Evaluator's Cue:
GS AI-19 s how s hy d r ogen concentration to be at 1.5
%. 2005 NRC J P M S6 NUREG 102 1, Revision 9 Appendix C Page 8 of 10 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  Terminating Cue:
When the candidate has determined that H2 concentration is 1.5, this JPM is complete.
STOP TI ME:     2005 NRC J P M S6 NUREG 102 1, Revision 9 Appendix C Page 9 of 10 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
2005 NRC J P M S6   Exa m inee's Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,810: Line 3,052:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S6 NUREG 102 1, Revision 9 Appendix C Page 10 of 10 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant has experienced a L a rge Loss of Coolant Accident. A Safety Injection has occurred.
2005 NRC JPM S6                                         NUREG 1021, Revision 9
INITIATING CUE: The Control Room Supe rvis or has directed you to place the "
 
A" Containmen t Hydrogen Analyzer, SGS02A, in service per OTN-GS-00 001, Section 4.2. The pr e-service st artup and standby alig nment of hydr ogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS0 2A is in serv ice. 2005 NRC J P M S6 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
Appendix C                         Page 10 of 10                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.
: Paralleling Diesel Generator "A" To XNB01 JPM No.: 2005 NRC J P M S7     K/A Referen c e: 064 A4.01 4.0 / 4.3 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
INITIATING CUE:     The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.
Date: Method of testing:
2005 NRC JPM S6                                           NUREG 1021, Revision 9
Simulated Performance:
 
Actual Performance:
Appendix C                                   Job Performance Measure                   Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: The plant is operating in Mode 3. The "A" Emerg ency Diesel Generator has been st arted per OTN-NE-000 1A, Section 5.3. NB01 is energized from its normal off-site power source. X N B01 L T C is in manual and Ta p 13 is set for modes 1 through 4.
Task
Task Stand ard: NE01 is con nected to NB01 and is carrying at least 2 Mwe load.
 
Required Materials:
==Title:==
None   General  
Paralleling Diesel Generator A To     JPM No.:     2005 NRC JPM S7 XNB01 K/A  
 
==Reference:==
064 A4.01         4.0 / 4.3 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                  Simulator      X   Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3. NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.
Task Standard:             NE01 is connected to NB01 and is carrying at least 2 Mwe load.
Required Materials:         None General  


==References:==
==References:==
OTN-NE-0001A, Standby Diesel Generation System Train A, Rev. 14 Initiating Cue:            You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4. Inform the Control Room Supervisor when NE01 is running loaded > 2 Mwe.
Time Critical Task:        NO Validation Time:            15 minutes 2005 NRC JPM S7                                                            NUREG 1021, Revision 9


OTN-NE-00 01A, Standby Diesel Ge neration System Train "A", Rev. 14 Initiating Cu e: You have b een directed to parallel t he "A" Diesel Generator to NB01 and load to at le ast 2 MW per OTN-NE-0001A, Section 5.4. Info rm the Control Room Supervisor when NE0 1 is running loaded > 2 Mwe. Time Critical Task:
Appendix C                     Job Performance Measure                 Form ES-C-1 Worksheet SIMULATOR SETUP NOTES:         May be run with JPM S4 Ensure A Emergency Diesel Generator is running unloaded if performing on the simulator. Use remote NBHS0037 place in manual.
NO  Validation Time:
15 minutes 2005 NRC J P M S7  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP   NOTE S: May be run with JPM S4 Ensure "A" Emergency Diesel Generator is running unloaded if performing on the simulator. Use remote NBHS0037 place in manual.
Monitor NEPSLTC (1).
Monitor NEPSLTC (1).
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 3 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
2005 NRC JPM S7                                             NUREG 1021, Revision 9
START TI ME:       Performanc e Step: 1 Obtain a verified working copy of OT N-NE-0001 A, Standby Diesel Generation System Train "A".
 
S t a n d a r d: Operator should obtain procedure copy.
Appendix C                                   Page 3 of 14                     Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
C o m m e n t:     Section 3 Performanc e Step: 2 Review the Precautions and Limitations of OTN-NE-0001A.
START TIME:
S t a n d a r d: Operator should read th e Precautio ns and Limit a tions. C o m m e n t:   Evaluator's Cue:
Performance Step: 1       Obtain a verified working copy of OTN-NE-0001A, Standby Diesel Generation System Train A.
All Precauti ons and Limitations are satisfied.
Standard:                 Operator should obtain procedure copy.
Section 4 Performanc e Step: 3 Review the Prerequisite s of OTN-NE-0001A.
Comment:
S t a n d a r d: Operator should read th e Initial Con d itions. C o m m e n t:   Evaluator's Cue:
Section 3 Performance Step: 2       Review the Precautions and Limitations of OTN-NE-0001A.
All prerequi sites are satisfied.
Standard:                 Operator should read the Precautions and Limitations.
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 4 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.1 Performanc e Step: 4 Ensure that the Local Master Transf e r Switch KJHS0009 is in the AUTO position.
Comment:
S t a n d a r d: Operator should verify absence of MCB ANN 20 E and/or request Local Obser v ation of Ma ster Transfe r Switch.
Evaluators Cue:         All Precautions and Limitations are satisfied.
C o m m e n t:   Evaluator's Cue:
Section 4 Performance Step: 3       Review the Prerequisites of OTN-NE-0001A.
The Local Master Tra nsfer Sw itc h KJHS000 9 is in the AUTO position.
Standard:                Operator should read the Initial Conditions.
Step 5.4.2 Performanc e Step: 5 At RL015, Check NE-HIS-25, NB01 EMERG SUPPLY BREAKER NB0111, is OPEN.
Comment:
S t a n d a r d: Green light for NE-HIS-2 5 is ON       C o m m e n t:     Step 5.4.3 Performanc e Step: 6 Check NB-HIS-2, NB01 NORM SUPPLY BK R NB0112, is CLOS ED  S t a n d a r d: Red light for NB-HIS-2 is ON       C o m m e n t:   2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 5 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.4 Performanc e Step: 7 Check diese l generator voltage and fr equency are stable in th e following ra nges: 3740 to 432 0 VAC indicated by NE EI-1, DG VOLTS 58.8 to 61.2 HZ indicate d by NE ST-1, DG FREQ/SPD S t a n d a r d: Determines that voltage is stable at approximate l y 4100 - 4200 VAC and fre quency is st able at 60 HZ C o m m e n t:     Step 5.4.5 Performanc e Step: 8 Ensure operating parameters are being monitored and recor ded per Attachment 1 S t a n d a r d: Refer to Attachment 1 C o m m e n t:   Evaluator's Cue:
Evaluators Cue:         All prerequisites are satisfied.
Parameters are being monitored b y another operator     Step 5.4.6 Performanc e Step: 9 If the White Parallel Operation Light is not lit, mo mentarily place NE HS-5, NE01 Unit Parallel SW to the parallel position.
2005 NRC JPM S7                                                     NUREG 1021, Revision 9
S t a n d a r d: Operator should determine WHITE parallel light is NOT lit by calling the EO at NE107.
 
After determining white light not lit, places NE HS-5 to PARALLEL.
Appendix C                             Page 4 of 14                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.1 Performance Step: 4 Ensure that the Local Master Transfer Switch KJHS0009 is in the AUTO position.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator should verify absence of MCB ANN 20E and/or request Local Observation of Master Transfer Switch.
When asked if WHITE Parallel Op eration Light is lit on NE107, rep o rt that it is NOT lit.
Comment:
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 6 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.7 Performanc e Step: 10 Check the White Parallel Operation Light is lit o n NE107. S t a n d a r d: Operator should contact EO to verif y the White Parallel Light is lit on NE107.
Evaluators Cue:   The Local Master Transfer Switch KJHS0009 is in the AUTO position.
C o m m e n t:   Evaluator's Cue:
Step 5.4.2 Performance Step: 5 At RL015, Check NE-HIS-25, NB01 EMERG SUPPLY BREAKER NB0111, is OPEN.
The White Parallel Light is lit on NE107.
Standard:          Green light for NE-HIS-25 is ON Comment:
Step 5.4.8 Performanc e Step: 11 Verify Main Control board Annunciat o r 22B, Voltage Control Freeze is lit.
Step 5.4.3 Performance Step: 6 Check NB-HIS-2, NB01 NORM SUPPLY BK R NB0112, is CLOSED Standard:           Red light for NB-HIS-2 is ON Comment:
S t a n d a r d: Operator should verify Annunciator 2 2 B, Voltage Control Freeze is lit.       C o m m e n t:   Evaluator's Cue:
2005 NRC JPM S7                                             NUREG 1021, Revision 9
Annunciator 22B, Volta ge Control Freeze is lit.
 
Step 5.4.9 Performanc e Step: 12 Verify EITHER Co mput er Point NBQ0003 indicates Capacit or Bank NB03 is in FREEZE OR Disconnect NB0301 is OPEN.
Appendix C                             Page 5 of 14                         Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.4 Performance Step: 7 Check diesel generator voltage and frequency are stable in the following ranges:
S t a n d a r d: Operator should verify NBQ0003 is in FREEZE or DISC ONN E CTED.       C o m m e n t:   Evaluator's Cue:
* 3740 to 4320 VAC indicated by NE EI-1, DG VOLTS
Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE mode. 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 7 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.10 Performanc e Step: 13 Verify EITHER Co mput er Point NBX 0001 indicates FREEZE or transformer XNB01 LTC is in MANUAL and set at the appropriate Tap Changer setting.
* 58.8 to 61.2 HZ indicated by NE ST-1, DG FREQ/SPD Standard:           Determines that voltage is stable at approximately 4100 - 4200 VAC and frequency is stable at 60 HZ Comment:
S t a n d a r d: Operator should verify XNB01 LTC i s in MANUAL and Tap Setting 13 is selected O R Computer Point NBX 0 001 indicate s FREEZE     NOTE: Given in Initial Conditions C o m m e n t:   Evaluator's Cue:
Step 5.4.5 Performance Step: 8 Ensure operating parameters are being monitored and recorded per Attachment 1 Standard:           Refer to Attachment 1 Comment:
Annunciator 19D, XNB01 XFMR/VOLT CTRL TRBL is LIT A N D  Computer Point NBX0 001 indicates FREEZE.
Evaluators Cue:   Parameters are being monitored by another operator Step 5.4.6 Performance Step: 9 If the White Parallel Operation Light is not lit, momentarily place NE HS-5, NE01 Unit Parallel SW to the parallel position.
Step 5.4.11 Performanc e Step: 14 Periodically monitor and adjust volta ge and frequency to maintain 4160 VAC and 60 HZ (nominal).
Standard:           Operator should determine WHITE parallel light is NOT lit by calling the EO at NE107. After determining white light not lit, places NE HS-5 to PARALLEL.
S t a n d a r d: Operator will adjust para m eters as necessary C o m m e n t:     Step 5.4.12 Performanc e Step: 15 Place the Sync Transfer Switch NE HS-27 in the ON position.
Comment:
S t a n d a r d: Operator selects ON with Sync Transfer Switch NE HS-27.
Evaluators Cue:   When asked if WHITE Parallel Operation Light is lit on NE107, report that it is NOT lit.
C o m m e n t:   Evaluator's Cue:
2005 NRC JPM S7                                                 NUREG 1021, Revision 9
NE HS-27 i s in the ON position.
 
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 8 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.13 Performanc e Step: 16 Place the Synchroscop e Selector Switch NB HS-10 in the D/G Feeder Breaker Position.
Appendix C                             Page 6 of 14                         Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.7 Performance Step: 10 Check the White Parallel Operation Light is lit on NE107.
S t a n d a r d: Operator should place t he Synchroscope Select or Switch NB HS-10 in the D/G Feeder Breaker Position.
Standard:           Operator should contact EO to verify the White Parallel Light is lit on NE107.
C o m m e n t:   Evaluator's Cue:
Comment:
NB HS-10 i s selected to DG Feede r BKR Posit i on. The Sy nc Scope is rotating in fast direction; Sy nc Lights NB ZL-9 are flashing.
Evaluators Cue:     The White Parallel Light is lit on NE107.
Step 5.4.14 Performanc e Step: 17 Adjust the diesel generat or speed using Governor Control, KJ HS-7A until the Synchroscope NB EI-3 is rotating slowly in the fact direct io n. S t a n d a r d: Operator turns KJ HS-7A, DG NE01 GOV, to RAISE if speed is SLOW and t o LOWER if speed FAST as indicate d by 4.16 KV Bus NB01 Sync Scope, NB EI-13 on RL015 to satisfy Synch check Relay
Step 5.4.8 Performance Step: 11 Verify Main Control board Annunciator 22B, Voltage Control Freeze is lit.
. C o m m e n t:   Evaluator's Cue:
Standard:           Operator should verify Annunciator 22B, Voltage Control Freeze is lit.
Sy nch roscope NB EI-3 is rotating slo w ly in the FAST direction.
Comment:
Step 5.4.15 Performanc e Step: 18 Adjust NE01 voltage to be within +50
Evaluators Cue:     Annunciator 22B, Voltage Control Freeze is lit.
, -0 volts of t he NB01 Bu s Voltage usin g the Auto Voltage Regulator NE HS-13A.
Step 5.4.9 Performance Step: 12 Verify EITHER Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE OR Disconnect NB0301 is OPEN.
S t a n d a r d: Operator should adjust NE01 voltag e to be within +50, -0 volts of the NB01 Bus Voltage u s ing the Aut o Voltage Regulator NE HS-13 A. C o m m e n t:   2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 9 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.15 Performanc e Step: 19 Determine NE01 voltag e by placing the Synchroscope Sele ctor Switch NB HS-10 in the D/G Feeder Breaker position and reading NB EI-28.
Standard:           Operator should verify NBQ0003 is in FREEZE or DISCONNECTED.
S t a n d a r d: Operator should place N B HS-10 in the D/G Fee der Breaker Position and read NB EI-28 to determine NE01 voltage. C o m m e n t:   Evaluator's Cue:
Comment:
NE EI-28 vo ltage is 4190 volts w h e n NB HS-10 is in the D/G Feeder Bre aker Position.
Evaluators Cue:     Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE mode.
Step 5.4.15 Performanc e Step: 20 Determine NB01 voltag e by placing the Synchroscope Sele ctor Switch NB HS-10 in the Main FDR BKR Position and readin g the voltage from NB EI-28.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
S t a n d a r d: Operator should determine NB01 vol t age by placing NB HS-1 0 in the Main FDR BKR Posit i on and read ing voltage from NB EI-28. C o m m e n t:   Evaluator's Cue:
 
NB EI-28 vo ltage is 4160 w hen NB HS-10 is in the Main FDR BKR Positi on. Step 5.4.16 Performanc e Step: 21 When NE01 voltage has been verified to be within +50, -0 volts of NB01 volt age, ensure the Synchroscope Selector Switch NB HS-10 is placed in th e D/G Feed er Breaker Position.
Appendix C                             Page 7 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.10 Performance Step: 13 Verify EITHER Computer Point NBX0001 indicates FREEZE or transformer XNB01 LTC is in MANUAL and set at the appropriate Tap Changer setting.
S t a n d a r d: Operator should place N B HS-10 in the D/G Fee der Breaker Position.
Standard:           Operator should verify XNB01 LTC is in MANUAL and Tap Setting 13 is selected OR Computer Point NBX0001 indicates FREEZE NOTE:               Given in Initial Conditions Comment:
C o m m e n t:     Step 5.4.17 Performanc e Step: 22 Verify proper operation of Sync Light NB ZL-9.
Evaluators Cue:     Annunciator 19D, XNB01 XFMR/VOLT CTRL TRBL is LIT AND Computer Point NBX0001 indicates FREEZE.
S t a n d a r d: Operator should verify proper operation of NB ZL-9.
Step 5.4.11 Performance Step: 14 Periodically monitor and adjust voltage and frequency to maintain 4160 VAC and 60 HZ (nominal).
C o m m e n t:   Evaluator's Cue:
Standard:           Operator will adjust parameters as necessary Comment:
Dimmest at 12 o'clock and brightest at 6 o'clock on Sy nc h Scope NB EI-3 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 10 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Step 5.4.18 Performanc e Step: 23 Verify that the Diesel Generator to Bus Synchronizing Lig h t NE ZL-27A illu minates when the Synchroscope i s between the 11 o'clock and t he 12 o'clo c k positio n. S t a n d a r d: Operator should verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illu minates when the Synchroscope is betwe en the 11 o'clock an d th e 12 o'clo ck position.
Step 5.4.12 Performance Step: 15 Place the Sync Transfer Switch NE HS-27 in the ON position.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator selects ON with Sync Transfer Switch NE HS-27.
NE ZL-27A is coming on at five (5) degrees before the 12 o'clock position and off at five (5) degrees after 12 o'clock.
Comment:
Step 5.4.19 Performanc e Step: 24 Allow Synch r oscope NB EI-3 to complete one re volution to verify proper spee d for synchronization.
Evaluators Cue:     NE HS-27 is in the ON position.
S t a n d a r d: Operator should observe the Sync Scope for one complete revolutions and adjust t he speed as necessary.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
C o m m e n t:   Evaluator's Cue:
 
Sy nch roscope is rotating in the FAST directi on at about the speed of the second had of a clock.
Appendix C                             Page 8 of 14                         Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.13 Performance Step: 16 Place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.
Step 5.4.20 Performanc e Step: 25 When the Synchroscop e reaches th e 11 o'clo ck position turn NE HIS-25 t o CLOSE a nd hold until Breaker NB0111 indicat e s CLOSED, th en release t he control switch.
Standard:           Operator should place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.
S t a n d a r d: When Sync Scope reaches the 11 o'clock posit ion and Synch Check Permissive Light ON, CL OSE NB01 EMERG SPL Y BKR NB0111 with Switch NE HIS-25 and hold until th e RED light is ON and the GREEN light is OFF, the n the operat or should release the switch. C o m m e n t:   Evaluator's Cue:
Comment:
NE HIS-25 RED light i s ON and the GREEN l i ght is OFF.
Evaluators Cue:     NB HS-10 is selected to DG Feeder BKR Position.
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 11 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.21 Performanc e Step: 26 Immediately upon closur e of the D/G Breaker Pickup Load to at least 0.2 MW by operating the D/G Governor Control JK HS-7A in the RAISE direction if necessary.
The Sync Scope is rotating in fast direction; Sync Lights NB ZL-9 are flashing.
S t a n d a r d: Operator should RAISE DG Load to prevent NB0 111 Reverse Power Trip using KJ HS-7A.
Step 5.4.14 Performance Step: 17 Adjust the diesel generator speed using Governor Control, KJ HS-7A until the Synchroscope NB EI-3 is rotating slowly in the fact direction.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator turns KJ HS-7A, DG NE01 GOV, to RAISE if speed is SLOW and to LOWER if speed FAST as indicated by 4.16 KV Bus NB01 Sync Scope, NB EI-13 on RL015 to satisfy Synch check Relay.
D/G Load is greater than 0.2 MW.
Comment:
Step 5.4.22 Performanc e Step: 27 Adjust Diesel Generator Voltage with the Auto Voltage Regulator NE HS-13 A to maintain a power factor of 0.9 LAG.
Evaluators Cue:     Synchroscope NB EI-3 is rotating slowly in the FAST direction.
S t a n d a r d: Operator should adjust D/G VAR Lo ading using NE HS-13 A , Auto Voltage Regulator.
Step 5.4.15 Performance Step: 18 Adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator should adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.
Pow e r fact or is 0.9 LAG.
Comment:
Step 5.4.23 Performanc e Step: 28 Return the Synchroscope Selector Switch NB HS-10 to the "OFF" position.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
S t a n d a r d: Operator should return t he Synchroscope Select or Switch NB HS-10 to the "OFF" position.
 
C o m m e n t:   Evaluator's Cue:
Appendix C                             Page 9 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.15 Performance Step: 19 Determine NE01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker position and reading NB EI-28.
NB HS-10 i s in "OFF".
Standard:           Operator should place NB HS-10 in the D/G Feeder Breaker Position and read NB EI-28 to determine NE01 voltage.
Step 5.4.24 Performanc e Step: 29 Place Sync Transfer Switch NE HS-27 in the OFF position.
Comment:
S t a n d a r d: Operator should place S y nc Transfer Switch NE HS-27 in the OFF positio
Evaluators Cue:     NE EI-28 voltage is 4190 volts when NB HS-10 is in the D/G Feeder Breaker Position.
: n. C o m m e n t:  Evaluator's Cue:
Step 5.4.15 Performance Step: 20 Determine NB01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the Main FDR BKR Position and reading the voltage from NB EI-28.
NE HS-27 i s in OFF. 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 12 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.25 Performanc e Step: 30 Increase Diesel Generator Load as directed by the SS/OS.
Standard:            Operator should determine NB01 voltage by placing NB HS-10 in the Main FDR BKR Position and reading voltage from NB EI-28.
S t a n d a r d: The operator should in crease Diesel Generator Load as directed by the Control Room Su pervisor.
Comment:
NOTE: Initial Conditions directed NE01 BE Loaded to > 2MW.
Evaluators Cue:     NB EI-28 voltage is 4160 when NB HS-10 is in the Main FDR BKR Position.
C o m m e n t:   Evaluator's Cue:
Step 5.4.16 Performance Step: 21 When NE01 voltage has been verified to be within +50, -0 volts of NB01 voltage, ensure the Synchroscope Selector Switch NB HS-10 is placed in the D/G Feeder Breaker Position.
If asked, report that 'it has been 5 minutes at current increment' Evaluator's Cue:
Standard:           Operator should place NB HS-10 in the D/G Feeder Breaker Position.
The Contro l Room Supervisor dire cts y ou to i ncrease D/G Load to > tw o (2) MW. Step 5.4.25 Performanc e Step: 31 Increase Diesel Generator Load, by placing KJ HS-7A in the RAISE position, to > two (2) MW.
Comment:
S t a n d a r d: Operator should go to RAISE on KJ HS-7A on RL015 to RAISE D/G Load to
Step 5.4.17 Performance Step: 22 Verify proper operation of Sync Light NB ZL-9.
> two (2) MW.
Standard:           Operator should verify proper operation of NB ZL-9.
C o m m e n t:   Evaluator's Cue:
Comment:
D/G Load is
Evaluators Cue:     Dimmest at 12 oclock and brightest at 6 oclock on Synch Scope NB EI-3 2005 NRC JPM S7                                               NUREG 1021, Revision 9
> tw o (2) MW.       Performanc e Step: 32 Inform the Control Room Supervisor that NE01 is loaded >
 
2 MWe. S t a n d a r d: Operator should inform the Control Room Supe rvisor that NE01 is loaded >
Appendix C                             Page 10 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.18 Performance Step: 23 Verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.
2 Mwe. C o m m e n t:   Evaluator's Cue:
Standard:           Operator should verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.
The Contro l Room Supervisor acknowledges.
Comment:
Terminating Cue:
Evaluators Cue:     NE ZL-27A is coming on at five (5) degrees before the 12 oclock position and off at five (5) degrees after 12 oclock.
When DG l oad is >2 MW, this JPM is complete.
Step 5.4.19 Performance Step: 24 Allow Synchroscope NB EI-3 to complete one revolution to verify proper speed for synchronization.
STOP TI ME:     2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 13 of 14 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Standard:           Operator should observe the Sync Scope for one complete revolutions and adjust the speed as necessary.
2005 NRC J P M S7   Exa m inee's Name:
Comment:
Evaluators Cue:     Synchroscope is rotating in the FAST direction at about the speed of the second had of a clock.
Step 5.4.20 Performance Step: 25 When the Synchroscope reaches the 11 oclock position turn NE HIS-25 to CLOSE and hold until Breaker NB0111 indicates CLOSED, then release the control switch.
Standard:           When Sync Scope reaches the 11 oclock position and Synch Check Permissive Light ON, CLOSE NB01 EMERG SPLY BKR NB0111 with Switch NE HIS-25 and hold until the RED light is ON and the GREEN light is OFF, then the operator should release the switch.
Comment:
Evaluators Cue:     NE HIS-25 RED light is ON and the GREEN light is OFF.
2005 NRC JPM S7                                                 NUREG 1021, Revision 9
 
Appendix C                           Page 11 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.21 Performance Step: 26 Immediately upon closure of the D/G Breaker Pickup Load to at least 0.2 MW by operating the D/G Governor Control JK HS-7A in the RAISE direction if necessary.
Standard:           Operator should RAISE DG Load to prevent NB0111 Reverse Power Trip using KJ HS-7A.
Comment:
Evaluators Cue:     D/G Load is greater than 0.2 MW.
Step 5.4.22 Performance Step: 27 Adjust Diesel Generator Voltage with the Auto Voltage Regulator NE HS-13A to maintain a power factor of 0.9 LAG.
Standard:           Operator should adjust D/G VAR Loading using NE HS-13A, Auto Voltage Regulator.
Comment:
Evaluators Cue:     Power factor is 0.9 LAG.
Step 5.4.23 Performance Step: 28 Return the Synchroscope Selector Switch NB HS-10 to the OFF position.
Standard:           Operator should return the Synchroscope Selector Switch NB HS-10 to the OFF position.
Comment:
Evaluators Cue:     NB HS-10 is in OFF.
Step 5.4.24 Performance Step: 29 Place Sync Transfer Switch NE HS-27 in the OFF position.
Standard:           Operator should place Sync Transfer Switch NE HS-27 in the OFF position.
Comment:
Evaluators Cue:     NE HS-27 is in OFF.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
 
Appendix C                             Page 12 of 14                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.25 Performance Step: 30 Increase Diesel Generator Load as directed by the SS/OS.
Standard:           The operator should increase Diesel Generator Load as directed by the Control Room Supervisor.
NOTE:               Initial Conditions directed NE01 BE Loaded to > 2MW.
Comment:
Evaluators Cue:     If asked, report that it has been 5 minutes at current increment Evaluators Cue:     The Control Room Supervisor directs you to increase D/G Load to > two (2) MW.
Step 5.4.25 Performance Step: 31 Increase Diesel Generator Load, by placing KJ HS-7A in the RAISE position, to > two (2) MW.
Standard:           Operator should go to RAISE on KJ HS-7A on RL015 to RAISE D/G Load to > two (2) MW.
Comment:
Evaluators Cue:     D/G Load is > two (2) MW.
Performance Step: 32 Inform the Control Room Supervisor that NE01 is loaded >
2 MWe.
Standard:           Operator should inform the Control Room Supervisor that NE01 is loaded > 2 Mwe.
Comment:
Evaluators Cue:     The Control Room Supervisor acknowledges.
Terminating Cue:       When DG load is >2 MW, this JPM is complete.
STOP TIME:
2005 NRC JPM S7                                               NUREG 1021, Revision 9
 
Appendix C                           Page 13 of 14               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S7 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 1,935: Line 3,230:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 14 of 14 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
The plant is operating in Mode 3. The "A" Emerg ency Diesel Generator has been star ted per OTN-NE-0001A, Section 5.3.
2005 NRC JPM S7                                         NUREG 1021, Revision 9
NB01 is energized from its normal off-site power source. X N B01 LTC is in manual and T ap 13 is set for modes 1 through 4.
 
INITIATING CUE: You have b een directed to parallel t he "A" Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-00 01A, Section 5.4.
Appendix C                         Page 14 of 14                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3.
Inform the Control Room Supervisor when NE01 is running lo aded > 2 Mwe. 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.
: Paralleling Diesel Generator "A" To XNB01 JPM No.: 2005 NRC J P M S7     K/A Referen c e: 064 A4.01 4.0 / 4.3 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
INITIATING CUE:     You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4.
Date: Method of testing:
Inform the Control Room Supervisor when NE01 is running loaded
Simulated Performance:
                    > 2 Mwe.
Actual Performance:
2005 NRC JPM S7                                             NUREG 1021, Revision 9
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: The plant is operating in Mode 3. The "A" Emerg ency Diesel Generator has been st arted per OTN-NE-000 1A, Section 5.3. NB01 is energized from its normal off-site power source. X N B01 L T C is in manual and Ta p 13 is set for modes 1 through 4.
 
Task Stand ard: NE01 is con nected to NB01 and is carrying at least 2 Mwe load.
Appendix C                                   Job Performance Measure                   Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
Required Materials:
Task
None   General  
 
==Title:==
Paralleling Diesel Generator A To     JPM No.:     2005 NRC JPM S7 XNB01 K/A  
 
==Reference:==
064 A4.01         4.0 / 4.3 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                  Simulator      X   Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3. NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.
Task Standard:             NE01 is connected to NB01 and is carrying at least 2 Mwe load.
Required Materials:         None General  


==References:==
==References:==
OTN-NE-0001A, Standby Diesel Generation System Train A, Rev. 14 Initiating Cue:            You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4. Inform the Control Room Supervisor when NE01 is running loaded > 2 Mwe.
Time Critical Task:        NO Validation Time:            15 minutes 2005 NRC JPM S7                                                            NUREG 1021, Revision 9


OTN-NE-00 01A, Standby Diesel Ge neration System Train "A", Rev. 14 Initiating Cu e: You have b een directed to parallel t he "A" Diesel Generator to NB01 and load to at le ast 2 MW per OTN-NE-0001A, Section 5.4. Info rm the Control Room Supervisor when NE0 1 is running loaded > 2 Mwe. Time Critical Task:
Appendix C                     Job Performance Measure                 Form ES-C-1 Worksheet SIMULATOR SETUP NOTES:         May be run with JPM S4 Ensure A Emergency Diesel Generator is running unloaded if performing on the simulator. Use remote NBHS0037 place in manual.
NO  Validation Time:
15 minutes 2005 NRC J P M S7  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP   NOTE S: May be run with JPM S4 Ensure "A" Emergency Diesel Generator is running unloaded if performing on the simulator. Use remote NBHS0037 place in manual.
Monitor NEPSLTC (1).
Monitor NEPSLTC (1).
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 3 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
2005 NRC JPM S7                                             NUREG 1021, Revision 9
START TI ME:       Performanc e Step: 1 Obtain a verified working copy of OT N-NE-0001 A, Standby Diesel Generation System Train "A".
 
S t a n d a r d: Operator should obtain procedure copy.
Appendix C                                   Page 3 of 14                     Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
C o m m e n t:     Section 3 Performanc e Step: 2 Review the Precautions and Limitations of OTN-NE-0001A.
START TIME:
S t a n d a r d: Operator should read th e Precautio ns and Limit a tions. C o m m e n t:   Evaluator's Cue:
Performance Step: 1       Obtain a verified working copy of OTN-NE-0001A, Standby Diesel Generation System Train A.
All Precauti ons and Limitations are satisfied.
Standard:                 Operator should obtain procedure copy.
Section 4 Performanc e Step: 3 Review the Prerequisite s of OTN-NE-0001A.
Comment:
S t a n d a r d: Operator should read th e Initial Con d itions. C o m m e n t:   Evaluator's Cue:
Section 3 Performance Step: 2       Review the Precautions and Limitations of OTN-NE-0001A.
All prerequi sites are satisfied.
Standard:                 Operator should read the Precautions and Limitations.
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 4 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.1 Performanc e Step: 4 Ensure that the Local Master Transf e r Switch KJHS0009 is in the AUTO position.
Comment:
S t a n d a r d: Operator should verify absence of MCB ANN 20 E and/or request Local Obser v ation of Ma ster Transfe r Switch.
Evaluators Cue:         All Precautions and Limitations are satisfied.
C o m m e n t:   Evaluator's Cue:
Section 4 Performance Step: 3       Review the Prerequisites of OTN-NE-0001A.
The Local Master Tra nsfer Sw itc h KJHS000 9 is in the AUTO position.
Standard:                Operator should read the Initial Conditions.
Step 5.4.2 Performanc e Step: 5 At RL015, Check NE-HIS-25, NB01 EMERG SUPPLY BREAKER NB0111, is OPEN.
Comment:
S t a n d a r d: Green light for NE-HIS-2 5 is ON       C o m m e n t:     Step 5.4.3 Performanc e Step: 6 Check NB-HIS-2, NB01 NORM SUPPLY BK R NB0112, is CLOS ED  S t a n d a r d: Red light for NB-HIS-2 is ON       C o m m e n t:   2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 5 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.4 Performanc e Step: 7 Check diese l generator voltage and fr equency are stable in th e following ra nges: 3740 to 432 0 VAC indicated by NE EI-1, DG VOLTS 58.8 to 61.2 HZ indicate d by NE ST-1, DG FREQ/SPD S t a n d a r d: Determines that voltage is stable at approximate l y 4100 - 4200 VAC and fre quency is st able at 60 HZ C o m m e n t:     Step 5.4.5 Performanc e Step: 8 Ensure operating parameters are being monitored and recor ded per Attachment 1 S t a n d a r d: Refer to Attachment 1 C o m m e n t:   Evaluator's Cue:
Evaluators Cue:         All prerequisites are satisfied.
Parameters are being monitored b y another operator     Step 5.4.6 Performanc e Step: 9 If the White Parallel Operation Light is not lit, mo mentarily place NE HS-5, NE01 Unit Parallel SW to the parallel position.
2005 NRC JPM S7                                                     NUREG 1021, Revision 9
S t a n d a r d: Operator should determine WHITE parallel light is NOT lit by calling the EO at NE107.
 
After determining white light not lit, places NE HS-5 to PARALLEL.
Appendix C                             Page 4 of 14                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.1 Performance Step: 4 Ensure that the Local Master Transfer Switch KJHS0009 is in the AUTO position.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator should verify absence of MCB ANN 20E and/or request Local Observation of Master Transfer Switch.
When asked if WHITE Parallel Op eration Light is lit on NE107, rep o rt that it is NOT lit.
Comment:
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 6 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.7 Performanc e Step: 10 Check the White Parallel Operation Light is lit o n NE107. S t a n d a r d: Operator should contact EO to verif y the White Parallel Light is lit on NE107.
Evaluators Cue:   The Local Master Transfer Switch KJHS0009 is in the AUTO position.
C o m m e n t:   Evaluator's Cue:
Step 5.4.2 Performance Step: 5 At RL015, Check NE-HIS-25, NB01 EMERG SUPPLY BREAKER NB0111, is OPEN.
The White Parallel Light is lit on NE107.
Standard:          Green light for NE-HIS-25 is ON Comment:
Step 5.4.8 Performanc e Step: 11 Verify Main Control board Annunciat o r 22B, Voltage Control Freeze is lit.
Step 5.4.3 Performance Step: 6 Check NB-HIS-2, NB01 NORM SUPPLY BK R NB0112, is CLOSED Standard:           Red light for NB-HIS-2 is ON Comment:
S t a n d a r d: Operator should verify Annunciator 2 2 B, Voltage Control Freeze is lit.       C o m m e n t:   Evaluator's Cue:
2005 NRC JPM S7                                             NUREG 1021, Revision 9
Annunciator 22B, Volta ge Control Freeze is lit.
 
Step 5.4.9 Performanc e Step: 12 Verify EITHER Co mput er Point NBQ0003 indicates Capacit or Bank NB03 is in FREEZE OR Disconnect NB0301 is OPEN.
Appendix C                             Page 5 of 14                         Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.4 Performance Step: 7 Check diesel generator voltage and frequency are stable in the following ranges:
S t a n d a r d: Operator should verify NBQ0003 is in FREEZE or DISC ONN E CTED.       C o m m e n t:   Evaluator's Cue:
* 3740 to 4320 VAC indicated by NE EI-1, DG VOLTS
Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE mode. 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 7 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.10 Performanc e Step: 13 Verify EITHER Co mput er Point NBX 0001 indicates FREEZE or transformer XNB01 LTC is in MANUAL and set at the appropriate Tap Changer setting.
* 58.8 to 61.2 HZ indicated by NE ST-1, DG FREQ/SPD Standard:           Determines that voltage is stable at approximately 4100 - 4200 VAC and frequency is stable at 60 HZ Comment:
S t a n d a r d: Operator should verify XNB01 LTC i s in MANUAL and Tap Setting 13 is selected O R Computer Point NBX 0 001 indicate s FREEZE     NOTE: Given in Initial Conditions C o m m e n t:   Evaluator's Cue:
Step 5.4.5 Performance Step: 8 Ensure operating parameters are being monitored and recorded per Attachment 1 Standard:           Refer to Attachment 1 Comment:
Annunciator 19D, XNB01 XFMR/VOLT CTRL TRBL is LIT A N D  Computer Point NBX0 001 indicates FREEZE.
Evaluators Cue:   Parameters are being monitored by another operator Step 5.4.6 Performance Step: 9 If the White Parallel Operation Light is not lit, momentarily place NE HS-5, NE01 Unit Parallel SW to the parallel position.
Step 5.4.11 Performanc e Step: 14 Periodically monitor and adjust volta ge and frequency to maintain 4160 VAC and 60 HZ (nominal).
Standard:           Operator should determine WHITE parallel light is NOT lit by calling the EO at NE107. After determining white light not lit, places NE HS-5 to PARALLEL.
S t a n d a r d: Operator will adjust para m eters as necessary C o m m e n t:     Step 5.4.12 Performanc e Step: 15 Place the Sync Transfer Switch NE HS-27 in the ON position.
Comment:
S t a n d a r d: Operator selects ON with Sync Transfer Switch NE HS-27.
Evaluators Cue:   When asked if WHITE Parallel Operation Light is lit on NE107, report that it is NOT lit.
C o m m e n t:   Evaluator's Cue:
2005 NRC JPM S7                                                 NUREG 1021, Revision 9
NE HS-27 i s in the ON position.
 
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 8 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.13 Performanc e Step: 16 Place the Synchroscop e Selector Switch NB HS-10 in the D/G Feeder Breaker Position.
Appendix C                             Page 6 of 14                         Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.7 Performance Step: 10 Check the White Parallel Operation Light is lit on NE107.
S t a n d a r d: Operator should place t he Synchroscope Select or Switch NB HS-10 in the D/G Feeder Breaker Position.
Standard:           Operator should contact EO to verify the White Parallel Light is lit on NE107.
C o m m e n t:   Evaluator's Cue:
Comment:
NB HS-10 i s selected to DG Feede r BKR Posit i on. The Sy nc Scope is rotating in fast direction; Sy nc Lights NB ZL-9 are flashing.
Evaluators Cue:     The White Parallel Light is lit on NE107.
Step 5.4.14 Performanc e Step: 17 Adjust the diesel generat or speed using Governor Control, KJ HS-7A until the Synchroscope NB EI-3 is rotating slowly in the fact direct io n. S t a n d a r d: Operator turns KJ HS-7A, DG NE01 GOV, to RAISE if speed is SLOW and t o LOWER if speed FAST as indicate d by 4.16 KV Bus NB01 Sync Scope, NB EI-13 on RL015 to satisfy Synch check Relay
Step 5.4.8 Performance Step: 11 Verify Main Control board Annunciator 22B, Voltage Control Freeze is lit.
. C o m m e n t:   Evaluator's Cue:
Standard:           Operator should verify Annunciator 22B, Voltage Control Freeze is lit.
Sy nch roscope NB EI-3 is rotating slo w ly in the FAST direction.
Comment:
Step 5.4.15 Performanc e Step: 18 Adjust NE01 voltage to be within +50
Evaluators Cue:     Annunciator 22B, Voltage Control Freeze is lit.
, -0 volts of t he NB01 Bu s Voltage usin g the Auto Voltage Regulator NE HS-13A.
Step 5.4.9 Performance Step: 12 Verify EITHER Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE OR Disconnect NB0301 is OPEN.
S t a n d a r d: Operator should adjust NE01 voltag e to be within +50, -0 volts of the NB01 Bus Voltage u s ing the Aut o Voltage Regulator NE HS-13 A. C o m m e n t:   2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 9 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.15 Performanc e Step: 19 Determine NE01 voltag e by placing the Synchroscope Sele ctor Switch NB HS-10 in the D/G Feeder Breaker position and reading NB EI-28.
Standard:           Operator should verify NBQ0003 is in FREEZE or DISCONNECTED.
S t a n d a r d: Operator should place N B HS-10 in the D/G Fee der Breaker Position and read NB EI-28 to determine NE01 voltage. C o m m e n t:   Evaluator's Cue:
Comment:
NE EI-28 vo ltage is 4190 volts w h e n NB HS-10 is in the D/G Feeder Bre aker Position.
Evaluators Cue:     Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE mode.
Step 5.4.15 Performanc e Step: 20 Determine NB01 voltag e by placing the Synchroscope Sele ctor Switch NB HS-10 in the Main FDR BKR Position and readin g the voltage from NB EI-28.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
S t a n d a r d: Operator should determine NB01 vol t age by placing NB HS-1 0 in the Main FDR BKR Posit i on and read ing voltage from NB EI-28. C o m m e n t:   Evaluator's Cue:
 
NB EI-28 vo ltage is 4160 w hen NB HS-10 is in the Main FDR BKR Positi on. Step 5.4.16 Performanc e Step: 21 When NE01 voltage has been verified to be within +50, -0 volts of NB01 volt age, ensure the Synchroscope Selector Switch NB HS-10 is placed in th e D/G Feed er Breaker Position.
Appendix C                             Page 7 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.10 Performance Step: 13 Verify EITHER Computer Point NBX0001 indicates FREEZE or transformer XNB01 LTC is in MANUAL and set at the appropriate Tap Changer setting.
S t a n d a r d: Operator should place N B HS-10 in the D/G Fee der Breaker Position.
Standard:           Operator should verify XNB01 LTC is in MANUAL and Tap Setting 13 is selected OR Computer Point NBX0001 indicates FREEZE NOTE:               Given in Initial Conditions Comment:
C o m m e n t:     Step 5.4.17 Performanc e Step: 22 Verify proper operation of Sync Light NB ZL-9.
Evaluators Cue:     Annunciator 19D, XNB01 XFMR/VOLT CTRL TRBL is LIT AND Computer Point NBX0001 indicates FREEZE.
S t a n d a r d: Operator should verify proper operation of NB ZL-9.
Step 5.4.11 Performance Step: 14 Periodically monitor and adjust voltage and frequency to maintain 4160 VAC and 60 HZ (nominal).
C o m m e n t:   Evaluator's Cue:
Standard:           Operator will adjust parameters as necessary Comment:
Dimmest at 12 o'clock and brightest at 6 o'clock on Sy nc h Scope NB EI-3 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 10 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N      Step 5.4.18 Performanc e Step: 23 Verify that the Diesel Generator to Bus Synchronizing Lig h t NE ZL-27A illu minates when the Synchroscope i s between the 11 o'clock and t he 12 o'clo c k positio n. S t a n d a r d: Operator should verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illu minates when the Synchroscope is betwe en the 11 o'clock an d th e 12 o'clo ck position.
Step 5.4.12 Performance Step: 15 Place the Sync Transfer Switch NE HS-27 in the ON position.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator selects ON with Sync Transfer Switch NE HS-27.
NE ZL-27A is coming on at five (5) degrees before the 12 o'clock position and off at five (5) degrees after 12 o'clock.
Comment:
Step 5.4.19 Performanc e Step: 24 Allow Synch r oscope NB EI-3 to complete one re volution to verify proper spee d for synchronization.
Evaluators Cue:     NE HS-27 is in the ON position.
S t a n d a r d: Operator should observe the Sync Scope for one complete revolutions and adjust t he speed as necessary.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
C o m m e n t:   Evaluator's Cue:
 
Sy nch roscope is rotating in the FAST directi on at about the speed of the second had of a clock.
Appendix C                             Page 8 of 14                         Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.13 Performance Step: 16 Place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.
Step 5.4.20 Performanc e Step: 25 When the Synchroscop e reaches th e 11 o'clo ck position turn NE HIS-25 t o CLOSE a nd hold until Breaker NB0111 indicat e s CLOSED, th en release t he control switch.
Standard:           Operator should place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.
S t a n d a r d: When Sync Scope reaches the 11 o'clock posit ion and Synch Check Permissive Light ON, CL OSE NB01 EMERG SPL Y BKR NB0111 with Switch NE HIS-25 and hold until th e RED light is ON and the GREEN light is OFF, the n the operat or should release the switch. C o m m e n t:   Evaluator's Cue:
Comment:
NE HIS-25 RED light i s ON and the GREEN l i ght is OFF.
Evaluators Cue:     NB HS-10 is selected to DG Feeder BKR Position.
2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 11 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.21 Performanc e Step: 26 Immediately upon closur e of the D/G Breaker Pickup Load to at least 0.2 MW by operating the D/G Governor Control JK HS-7A in the RAISE direction if necessary.
The Sync Scope is rotating in fast direction; Sync Lights NB ZL-9 are flashing.
S t a n d a r d: Operator should RAISE DG Load to prevent NB0 111 Reverse Power Trip using KJ HS-7A.
Step 5.4.14 Performance Step: 17 Adjust the diesel generator speed using Governor Control, KJ HS-7A until the Synchroscope NB EI-3 is rotating slowly in the fact direction.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator turns KJ HS-7A, DG NE01 GOV, to RAISE if speed is SLOW and to LOWER if speed FAST as indicated by 4.16 KV Bus NB01 Sync Scope, NB EI-13 on RL015 to satisfy Synch check Relay.
D/G Load is greater than 0.2 MW.
Comment:
Step 5.4.22 Performanc e Step: 27 Adjust Diesel Generator Voltage with the Auto Voltage Regulator NE HS-13 A to maintain a power factor of 0.9 LAG.
Evaluators Cue:     Synchroscope NB EI-3 is rotating slowly in the FAST direction.
S t a n d a r d: Operator should adjust D/G VAR Lo ading using NE HS-13 A , Auto Voltage Regulator.
Step 5.4.15 Performance Step: 18 Adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator should adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.
Pow e r fact or is 0.9 LAG.
Comment:
Step 5.4.23 Performanc e Step: 28 Return the Synchroscope Selector Switch NB HS-10 to the "OFF" position.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
S t a n d a r d: Operator should return t he Synchroscope Select or Switch NB HS-10 to the "OFF" position.
 
C o m m e n t:   Evaluator's Cue:
Appendix C                             Page 9 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.15 Performance Step: 19 Determine NE01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker position and reading NB EI-28.
NB HS-10 i s in "OFF".
Standard:           Operator should place NB HS-10 in the D/G Feeder Breaker Position and read NB EI-28 to determine NE01 voltage.
Step 5.4.24 Performanc e Step: 29 Place Sync Transfer Switch NE HS-27 in the OFF position.
Comment:
S t a n d a r d: Operator should place S y nc Transfer Switch NE HS-27 in the OFF positio
Evaluators Cue:     NE EI-28 voltage is 4190 volts when NB HS-10 is in the D/G Feeder Breaker Position.
: n. C o m m e n t:  Evaluator's Cue:
Step 5.4.15 Performance Step: 20 Determine NB01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the Main FDR BKR Position and reading the voltage from NB EI-28.
NE HS-27 i s in OFF. 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 12 of 14 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.4.25 Performanc e Step: 30 Increase Diesel Generator Load as directed by the SS/OS.
Standard:            Operator should determine NB01 voltage by placing NB HS-10 in the Main FDR BKR Position and reading voltage from NB EI-28.
S t a n d a r d: The operator should in crease Diesel Generator Load as directed by the Control Room Su pervisor.
Comment:
NOTE: Initial Conditions directed NE01 BE Loaded to > 2MW.
Evaluators Cue:     NB EI-28 voltage is 4160 when NB HS-10 is in the Main FDR BKR Position.
C o m m e n t:   Evaluator's Cue:
Step 5.4.16 Performance Step: 21 When NE01 voltage has been verified to be within +50, -0 volts of NB01 voltage, ensure the Synchroscope Selector Switch NB HS-10 is placed in the D/G Feeder Breaker Position.
If asked, report that 'it has been 5 minutes at current increment' Evaluator's Cue:
Standard:           Operator should place NB HS-10 in the D/G Feeder Breaker Position.
The Contro l Room Supervisor dire cts y ou to i ncrease D/G Load to > tw o (2) MW. Step 5.4.25 Performanc e Step: 31 Increase Diesel Generator Load, by placing KJ HS-7A in the RAISE position, to > two (2) MW.
Comment:
S t a n d a r d: Operator should go to RAISE on KJ HS-7A on RL015 to RAISE D/G Load to
Step 5.4.17 Performance Step: 22 Verify proper operation of Sync Light NB ZL-9.
> two (2) MW.
Standard:           Operator should verify proper operation of NB ZL-9.
C o m m e n t:   Evaluator's Cue:
Comment:
D/G Load is
Evaluators Cue:     Dimmest at 12 oclock and brightest at 6 oclock on Synch Scope NB EI-3 2005 NRC JPM S7                                               NUREG 1021, Revision 9
> tw o (2) MW.       Performanc e Step: 32 Inform the Control Room Supervisor that NE01 is loaded >
 
2 MWe. S t a n d a r d: Operator should inform the Control Room Supe rvisor that NE01 is loaded >
Appendix C                             Page 10 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.18 Performance Step: 23 Verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.
2 Mwe. C o m m e n t:   Evaluator's Cue:
Standard:           Operator should verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.
The Contro l Room Supervisor acknowledges.
Comment:
Terminating Cue:
Evaluators Cue:     NE ZL-27A is coming on at five (5) degrees before the 12 oclock position and off at five (5) degrees after 12 oclock.
When DG l oad is >2 MW, this JPM is complete.
Step 5.4.19 Performance Step: 24 Allow Synchroscope NB EI-3 to complete one revolution to verify proper speed for synchronization.
STOP TI ME:     2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 13 of 14 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Standard:           Operator should observe the Sync Scope for one complete revolutions and adjust the speed as necessary.
2005 NRC J P M S7   Exa m inee's Name:
Comment:
Evaluators Cue:     Synchroscope is rotating in the FAST direction at about the speed of the second had of a clock.
Step 5.4.20 Performance Step: 25 When the Synchroscope reaches the 11 oclock position turn NE HIS-25 to CLOSE and hold until Breaker NB0111 indicates CLOSED, then release the control switch.
Standard:           When Sync Scope reaches the 11 oclock position and Synch Check Permissive Light ON, CLOSE NB01 EMERG SPLY BKR NB0111 with Switch NE HIS-25 and hold until the RED light is ON and the GREEN light is OFF, then the operator should release the switch.
Comment:
Evaluators Cue:     NE HIS-25 RED light is ON and the GREEN light is OFF.
2005 NRC JPM S7                                                 NUREG 1021, Revision 9
 
Appendix C                           Page 11 of 14                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.21 Performance Step: 26 Immediately upon closure of the D/G Breaker Pickup Load to at least 0.2 MW by operating the D/G Governor Control JK HS-7A in the RAISE direction if necessary.
Standard:           Operator should RAISE DG Load to prevent NB0111 Reverse Power Trip using KJ HS-7A.
Comment:
Evaluators Cue:     D/G Load is greater than 0.2 MW.
Step 5.4.22 Performance Step: 27 Adjust Diesel Generator Voltage with the Auto Voltage Regulator NE HS-13A to maintain a power factor of 0.9 LAG.
Standard:           Operator should adjust D/G VAR Loading using NE HS-13A, Auto Voltage Regulator.
Comment:
Evaluators Cue:     Power factor is 0.9 LAG.
Step 5.4.23 Performance Step: 28 Return the Synchroscope Selector Switch NB HS-10 to the OFF position.
Standard:           Operator should return the Synchroscope Selector Switch NB HS-10 to the OFF position.
Comment:
Evaluators Cue:     NB HS-10 is in OFF.
Step 5.4.24 Performance Step: 29 Place Sync Transfer Switch NE HS-27 in the OFF position.
Standard:           Operator should place Sync Transfer Switch NE HS-27 in the OFF position.
Comment:
Evaluators Cue:     NE HS-27 is in OFF.
2005 NRC JPM S7                                               NUREG 1021, Revision 9
 
Appendix C                             Page 12 of 14                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.25 Performance Step: 30 Increase Diesel Generator Load as directed by the SS/OS.
Standard:           The operator should increase Diesel Generator Load as directed by the Control Room Supervisor.
NOTE:               Initial Conditions directed NE01 BE Loaded to > 2MW.
Comment:
Evaluators Cue:     If asked, report that it has been 5 minutes at current increment Evaluators Cue:     The Control Room Supervisor directs you to increase D/G Load to > two (2) MW.
Step 5.4.25 Performance Step: 31 Increase Diesel Generator Load, by placing KJ HS-7A in the RAISE position, to > two (2) MW.
Standard:           Operator should go to RAISE on KJ HS-7A on RL015 to RAISE D/G Load to > two (2) MW.
Comment:
Evaluators Cue:     D/G Load is > two (2) MW.
Performance Step: 32 Inform the Control Room Supervisor that NE01 is loaded >
2 MWe.
Standard:           Operator should inform the Control Room Supervisor that NE01 is loaded > 2 Mwe.
Comment:
Evaluators Cue:     The Control Room Supervisor acknowledges.
Terminating Cue:       When DG load is >2 MW, this JPM is complete.
STOP TIME:
2005 NRC JPM S7                                               NUREG 1021, Revision 9
 
Appendix C                           Page 13 of 14               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S7 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 2,061: Line 3,411:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Page 14 of 14 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
The plant is operating in Mode 3. The "A" Emerg ency Diesel Generator has been star ted per OTN-NE-0001A, Section 5.3.
2005 NRC JPM S7                                         NUREG 1021, Revision 9
NB01 is energized from its normal off-site power source. X N B01 LTC is in manual and T ap 13 is set for modes 1 through 4.
 
INITIATING CUE: You have b een directed to parallel t he "A" Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-00 01A, Section 5.4.
Appendix C                         Page 14 of 14                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3.
Inform the Control Room Supervisor when NE01 is running lo aded > 2 Mwe. 2005 NRC J P M S7 NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet F a c i l i t y: C a l l a w a y T a s k N o.:     Task Title
NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.
: Reinitiate CTMT Purge Following CPIS JPM No.: 2005 NRC J P M S8     K/A Referen c e: 013 A2.06 3.7 / 4.0 Exa m i n e e: NRC Exa m i n e r: Facility Evaluator:
INITIATING CUE:     You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4.
Date: Method of testing:
Inform the Control Room Supervisor when NE01 is running loaded
Simulated Performance:
                    > 2 Mwe.
Actual Performance:
2005 NRC JPM S7                                             NUREG 1021, Revision 9
X C l a s s r o o m  S i m u l a t o r X P l a n t  READ T O T H E EX AMI N EE I will explain the initia l co nditions, whi c h steps to simulate or discuss, and provide initi a ting cues. When you complete the task successf ully, the objectiv e for this Jo b Performan c e Measure will be satisf ied. Initial Condit i ons: Callaway Pl ant is in Mo de 1. A con t ainment mi ni purge was in progress to prepare for a contain m ent entry.
 
One hour ago, a CPIS/CRVIS occurred du e to a spike on GTRE00 22. Repairs have been made to GTRE0022 and it is now operable.
Appendix C                                 Job Performance Measure                     Form ES-C-1 Worksheet Facility:               Callaway                                Task No.:
Outside air t e mperature is expected to remain > 50°F.
Task
Task Stand ard: Upon completion of this JPM, the operator will h a ve reset CPIS and re-establish ed containment mini purge.
 
Required Materials:
==Title:==
Copy of Gas eous Radwaste Release Permit Covers installed on the E S FAS Switc hes for GTRE0022 and GTRE0033 General  
Reinitiate CTMT Purge Following         JPM No.:     2005 NRC JPM S8 CPIS K/A  
 
==Reference:==
013 A2.06       3.7 / 4.0 Examinee:                                                   NRC Examiner:
Facility Evaluator:                                         Date:
Method of testing:
Simulated Performance:                                       Actual Performance:       X Classroom                Simulator      X     Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:         Callaway Plant is in Mode 1. A containment mini purge was in progress to prepare for a containment entry. One hour ago, a CPIS/CRVIS occurred due to a spike on GTRE0022. Repairs have been made to GTRE0022 and it is now operable. Outside air temperature is expected to remain > 50°F.
Task Standard:             Upon completion of this JPM, the operator will have reset CPIS and re-established containment mini purge.
Required Materials:         Copy of Gaseous Radwaste Release Permit Covers installed on the ESFAS Switches for GTRE0022 and GTRE0033 General  


==References:==
==References:==
OTN-GT-00001, Containment Purge System, Revision 20 CAR 199301739, 199400025, 199501723, 199700736 Initiating Cue:            The Control Room Supervisor has directed you to re-initiate the containment mini purge per OTN-GT-00001, Section 5.6. The Control Room Supervisor has decided to not realign the control building HVAC at this time. The SS has authorized reinitiating CTMT mini purge.
Inform the Control Room Supervisor when the mini purge has been re-initiated.
2005 NRC JPM S8                                                            NUREG 1021, Revision 9
Appendix C                    Job Performance Measure          Form ES-C-1 Worksheet Time Critical Task: NO Validation Time:    22 minutes 2005 NRC JPM S8                                        NUREG 1021, Revision 9
Appendix C                            Job Performance Measure                Form ES-C-1 Worksheet SIMULATOR SETUP Reset to IC - 68 (May be run with S5)
NOTES:                Manually initiate a CPIS and CRVIS (both trains).
2005 NRC JPM S8                                                      NUREG 1021, Revision 9
Appendix C                                  Page 4 of 17                      Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1      Obtain a verified working copy of OTN-GT-00001, Containment Purge System.
Standard:                Operator should obtain procedure copy.
Comment:
Section 3 Performance Step: 2      Review Precautions and Limitations of OTN-GT-00001.
Standard:                Operator should review Precautions and Limitations.
Comment:
Evaluators Cue:          All Precautions and Limitations are satisfied.
Section 4 Performance Step: 3      Review Prerequisites of OTN-GT-00001.
Standard:                Operator should review Prerequisites.
Comment:
Evaluators Cue:          All Prerequisites are satisfied.
Step 5.6.1 Performance Step: 4      The purge may be reinitiated w/out terminating the release permit provided the time between stopping and restarting the release does not exceed two hours.
Standard:                Operator should realize purge was only secured for one hour and SS has given permission to reinitiate purge.
Comment:
2005 NRC JPM S8                                                    NUREG 1021, Revision 9
Appendix C                            Page 5 of 17                          Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.2 Performance Step: 5 Have the Count Room Technician verify alarm/trip setpoints for GT-RE-21B, GT-RE-22, and GT-RE-33 are correct per the release permit.
Standard:          Operator should contact the Count Room Technician to verify setpoint for GT-RE-21, 22 and 33 are correct per the release permit.
Comment:
Evaluators Cue:    The Count Room Technician has verified setpoints correct per the release permit.
Step 5.6.3 Performance Step: 6 If monitor readings are  the hihi alarm setpoint, close the permit, resample, and generate a new permit.
Standard:          Operator should use the RM11 console to determine the color of channels 211, 212, 221, 222, 223, 331, 332, and 333 are NOT lit RED.
Comment:
Evaluators Cue:    RM 11 channels 211, 212, 221, 222, 2223, 331, 332, and 333 are lit GREEN.
Step 5.6.4 Performance Step: 7 Check SA036D and SA036E. If any bistable trip lights are lit, record on the URO Log and reset the bistable by depressing and then releasing the bistable trip light.
Standard:          Operator should go to the SA036D and SA036E panel in the back of the Control Room and verify NO bistable lights lit.
Comment:
Evaluators Cue:    NO bistable lights are lit on SA036D and SA036E.
2005 NRC JPM S8                                                NUREG 1021, Revision 9
Appendix C                              Page 6 of 17                        Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.5 Performance Step: 8  If required, with SS/CRS permission, reset the following:
Standard:
Comment:
Evaluators Note:    The SS has authorized resetting switches.
Step 5.6.6 Performance Step: 9  Reset CPIS by depressing SA HS-15, CTMT purge Train B ISO on RL018.
NOTE:                Steps 9 through 12 may be performed in any order.
Standard:            Operator should depress the reset button on SA HS-15, CTMT Purge Train B ISO on RL018.
Comment:
Evaluators Note:    The reset button on SA HS-15 has been depressed.
Step 5.6.6 Performance Step: 10 Reset CRVIS by depressing SA HS-13, Ctrl Bldg Vent Train B ISO.
NOTE:                Steps 9 through 12 may be performed in any order.
Standard:            Operator should depress the reset button on SA HS-13, Ctrl Bldg Vent Train B ISO on RL018.
Comment:
Evaluators Note:    The reset button on SA HS-13 has been depressed.
2005 NRC JPM S8                                                NUREG 1021, Revision 9
Appendix C                            Page 7 of 17                      Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.5 Performance Step: 11 Reset CPIS by depressing SA HS-11, CTMT Purge Train A ISO on RL018.
NOTE:                Steps 9 through 12 may be performed in any order.
Standard:            Operator should depress the reset button on SA HS-11, CTMT Purge Train A ISO on RL018.
Comment:
Evaluators Cue:    The reset button on SA HS-11 has been depressed.
Step 5.6.5 Performance Step: 12 Reset CRVIS by depressing SA HS-9, Ctrl Bldg Vent Train A ISO on RL018.
NOTE:                Steps 9 through 12 may be performed in any order.
Standard:            Operator should depress the reset button on SA HS-9, Ctrl Bldg Vent Train A ISO on RL018.
Comment:
Evaluators Cue:    The reset button on SA HS-9 has been depressed.
Step 5.6.7 Performance Step: 13 Ensure CPIS and CRVIS lights OUT on ESFAS status panels; if required use SA HS-24 and/or SA HS-23, ESF panel mode SEL switches, to reset.
Standard:            Operator should ensure CPIS and CRVIS lights OUT on ESFAS status panels.
Comment:
Evaluators Cue:    CPIS and CRVIS lights on ESFAS status panel are OUT.
2005 NRC JPM S8                                              NUREG 1021, Revision 9


OTN-GT-00 001, Containment Purg e System, Revision 20 CAR 19930 1739, 19940 0025, 19950 1723, 19970 0736  Initiating Cu e: The Control Room Supe rvisor has directed you to re-initiate t he containment mini purge per OTN-GT-00001, Section 5.6. Th e Control Room Supe rvisor has decided to no t realign the control build ing HVAC at this time.
Appendix C                             Page 8 of 17                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.8 Performance Step: 14 Ensure MCB annunciators 59D (CPIS) and 63A (CRVIS) are clear.
The SS has authorized r e initiating C T MT mini pu rge. Inform the Control Room Supervisor when the mini purge has been re-initiated.
Standard:           Operator should verify MCB annunciators 59D and 63A are clear.
2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task:
Comment:
NO  Validation Time:
Evaluators Cue:     MCB annunciators 59D and 63A are clear.
22 minutes 2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMUL A TOR SETUP  Reset to IC - 68 (May b e run with S5)
Step 5.6.9 Performance Step: 15 If required, realign the Control Building HVAC per OTN-GK-00001.
NOTE S: Manually initiate a CPIS and CRVIS (both trains)
Standard:           The operator should continue with Step 5.6.10 and not align Control Building HVAC at this time.
. 2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Page 4 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  (Denote Cri t ical Steps with a check mark)
START TI ME:        Performanc e Step: 1 Obtain a verified working copy of OT N-GT-00001 , Containment Purge Syste
: m. S t a n d a r d: Operator should obtain procedure copy.
C o m m e n t:      Section 3 Performanc e Step: 2 Review Pre c autions an d Limitation s of OTN-GT-00001.
S t a n d a r d: Operator should review Precautions and Limitations.
C o m m e n t:  Evaluator's Cue:
All Precauti ons and Limitations are satisfied.
Section 4 Performanc e Step: 3 Review Prerequisites of OTN-GT-00 001. S t a n d a r d: Operator should review Prerequisite
: s. C o m m e n t:  Evaluator's Cue:
All Prerequ isites are satisfied.
Step 5.6.1 Performanc e Step: 4 The purge may be reini t iated w/out terminating the release permit provi ded the time between stopping and r e starting the release doe s not exceed two hours.
S t a n d a r d: Operator should realize purge was only secured for one hour and SS has given permissio n to reinitiat e purge. C o m m e n t:    2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Page 5 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.6.2 Performanc e Step: 5 Have the Co unt Room T e chnician ve rify alarm/trip setpoints f o r GT-RE-21 B, GT-RE-22, and GT-RE-33 are corre ct per the release per mit. S t a n d a r d: Operator should contact the Count Room Tech n ician to ver i fy setpoint for GT-RE-21, 22 and 33 a r e correct p e r the release permit. C o m m e n t:  Evaluator's Cue:
The Count Room Technician has verified setpoints correct per the release permit.
Step 5.6.3 Performanc e Step: 6 If monitor readings are  the hihi alar m setpoint, close the pe rmit, resample, and generate a new permit.
S t a n d a r d: Operator should use the RM11 console to deter mine the color of channels 21 1, 212, 221, 222, 223, 33 1, 332, and 333 are NOT lit RED. C o m m e n t:  Evaluator's Cue:
RM 11 chan nels 211, 2 12, 221, 222 , 2223, 331, 332, and 333 are lit GREEN.
Step 5.6.4 Performanc e Step: 7 Check SA036D and SA0 36E. If any bistable trip lights are lit, record on th e URO Log and reset th e bistable b y depressin g and then releasing the bista b le trip ligh
: t. S t a n d a r d: Operator should go to th e SA036D a nd SA036E panel in the back of the Control Room and verify NO bistable lights lit.
C o m m e n t:  Evaluator's Cue:
NO bistable lights are lit on SA036D and SA03 6E. 2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Page 6 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.6.5 Performanc e Step: 8 If required, with SS/CRS permission, reset the f o llowing:  S t a n d a r d:      C o m m e n t:  Evaluator's Note:
The SS has authorized resetting switches.
Step 5.6.6  Performanc e Step: 9 Reset CPIS by depressing SA HS-1 5, CTMT pu rge Train B ISO on RL018.
NOTE: Steps 9 through 12 may be performed in an y order. S t a n d a r d: Operator should depress the reset b u tton on SA HS-15, CT MT Purge Train B ISO on RL018.
C o m m e n t:  Evaluator's Note:
The reset button on SA HS-15 ha s been depressed.
Step 5.6.6 Performanc e Step: 10 Reset CRVI S by depressing SA HS-13, Ctrl Bldg Vent Train B ISO. NOTE: Steps 9 through 12 may be performed in an y order. S t a n d a r d: Operator should depress the reset b u tton on SA HS-13, Ctrl Bldg Vent Train B ISO on RL0
: 18. C o m m e n t:  Evaluator's Note:
The reset button on SA HS-13 ha s been depressed.
2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Page 7 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.6.5  Performanc e Step: 11 Reset CPIS by depressing SA HS-1 1, CTMT Pu rge Train A ISO on RL018.
NOTE: Steps 9 through 12 may be performed in an y order. S t a n d a r d: Operator should depress the reset b u tton on SA HS-11, CT MT Purge Train A ISO on RL018.
C o m m e n t:  Evaluator's Cue:
The reset button on SA HS-11 ha s been depressed.
Step 5.6.5 Performanc e Step: 12 Reset CRVI S by depressing SA HS-9, Ctrl Bldg Vent Train A ISO on RL018.
NOTE: Steps 9 through 12 may be performed in an y order. S t a n d a r d: Operator should depress the reset b u tton on SA HS-9, Ctrl Bl dg Vent Train A ISO on RL0
: 18. C o m m e n t:  Evaluator's Cue:
The reset button on SA HS-9 has been depressed.
Step 5.6.7 Performanc e Step: 13 Ensure CPIS and CRVI S lights OUT on ESFAS status pane ls; if required use SA HS-24 a nd/or SA HS-23, ESF panel mode SEL switches, to reset. S t a n d a r d: Operator should ensure CPIS and CRVIS lights OUT on ESFAS status panels.
C o m m e n t:  Evaluator's Cue:
CPIS and CRVIS lights on ESFAS status panel are OUT.
2005 NRC J P M S8  NUREG 102 1, Revision 9 Appendix C Page 8 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.6.8 Performanc e Step: 14 Ensure MCB annunciat o rs 59D (CPIS) and 63A (CRVIS) are clear. S t a n d a r d: Operator should verify MCB annun ciators 59D and 63A are clear. C o m m e n t:   Evaluator's Cue:
MCB annun ciators 59D and 63A are clear.
Step 5.6.9 Performanc e Step: 15 If required, r ealign the C ontrol Building HVAC pe r OTN-GK-00 001. S t a n d a r d: The operator should con t inue with Step 5.6.10 an d not align Control Building HVAC at this time.
Given in Initial Conditions.
Given in Initial Conditions.
C o m m e n t:   Evaluator's Cue:
Comment:
The O.S. has determined to align mini-purge prior to realigning the Control Building HVAC.
Evaluators Cue:     The O.S. has determined to align mini-purge prior to realigning the Control Building HVAC.
Step 5.6.10 Performanc e Step: 16 Reinitiate Mini-Purge per Section 5.2 of this proce dure. S t a n d a r d: Operator should go to S e ction 5.2.
Step 5.6.10 Performance Step: 16 Reinitiate Mini-Purge per Section 5.2 of this procedure.
C o m m e n t:     Section 5.2.
Standard:           Operator should go to Section 5.2.
1 Performanc e Step: 17 Ensure Shutdown Purge is not in ser v ice. S t a n d a r d: Operator should verify Shutdown Purge is not in service. C o m m e n t:   Evaluator's Cue:
Comment:
Shutdow n Purge is not in service.
Section 5.2.1 Performance Step: 17 Ensure Shutdown Purge is not in service.
2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 9 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.2.2 Performanc e Step: 18 Monitor or trend SD-RE-41, SD-RE-42, and GT-PDI-040.
Standard:           Operator should verify Shutdown Purge is not in service.
S t a n d a r d: Operator monitor or tre nd SD-RE-4 1 , SD-RE-4 2 , and GT-PD-040.
Comment:
Operator may use time trend "minivent".
Evaluators Cue:     Shutdown Purge is not in service.
C o m m e n t:   E v a l u a t o r's C u e: SD-RE-41, SD-RE-42, and GT-PD-040 are all stable.
2005 NRC JPM S8                                                   NUREG 1021, Revision 9
Step 5.2.3 Performanc e Step: 19 Record cont ainment pressure, using GTPDI0040 or GTD004 0, on the Gaseous Radwaste Permit.
 
S t a n d a r d: Operator should record containment pressure GTPDI0040 or GTD0040, o n the Gaseous Radwaste Permit.
Appendix C                             Page 9 of 17                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.2 Performance Step: 18 Monitor or trend SD-RE-41, SD-RE-42, and GT-PDI-040.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator monitor or trend SD-RE-41, SD-RE-42, and GT-PD-040. Operator may use time trend minivent.
Containment pressure has been recorded.
Comment:
Step 5.2.4 Performanc e Step: 20 Ensure that GTRE0022 and GTRE0 033 are not in bypass, and ensure the "
Evaluators Cue:     SD-RE-41, SD-RE-42, and GT-PD-040 are all stable.
C TMT Purg e In Prog - Do Not Byp a ss" cover o v er the ESFAS switches for GTRE0022 and GTRE0 033. S t a n d a r d: Operator should verify GTRE0022 and GTRE0 033 are not in bypass and covers have been place d over GTRE0022 and GTRE0033 ESFAS Switches.
Step 5.2.3 Performance Step: 19 Record containment pressure, using GTPDI0040 or GTD0040, on the Gaseous Radwaste Permit.
C o m m e n t:   Evaluator's Cue:
Standard:           Operator should record containment pressure GTPDI0040 or GTD0040, on the Gaseous Radwaste Permit.
GTRE022 a nd GTRE00 33 are not in b y pass. Covers have been placed over GT RE0022 and GTRE003 3 ESFAS Sw itches.                     2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 10 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.2.6 Performanc e Step: 22 Start CGT0 2 Containment Mini Purge Exhaust Fan using GT HIS-20.
Comment:
S t a n d a r d: Operator should select RUN on GT HIS-20, CT MT Mini Pur ge Exh Fan. C o m m e n t:   Evaluator's Cue:
Evaluators Cue:     Containment pressure has been recorded.
GT HIS-20 RED lights illuminate and GREEN lights extinguish.
Step 5.2.4 Performance Step: 20 Ensure that GTRE0022 and GTRE0033 are not in bypass, and ensure the CTMT Purge In Prog - Do Not Bypass cover over the ESFAS switches for GTRE0022 and GTRE0033.
Step 5.2.7 Performanc e Step: 23 Open GTHZ 0011 using GT HIS-11.
Standard:           Operator should verify GTRE0022 and GTRE0033 are not in bypass and covers have been placed over GTRE0022 and GTRE0033 ESFAS Switches.
NOTE: Steps 23 - 26 ma y be accomplished in an y o r der. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-11.
Comment:
C o m m e n t:   Evaluator's Cue:
Evaluators Cue:     GTRE022 and GTRE0033 are not in bypass.
GT HIS-11 RED light il luminates and three (3) seconds later, the GREEN light extinguishes.
Covers have been placed over GTRE0022 and GTRE0033 ESFAS Switches.
Step 5.2.8 Performanc e Step: 24 Open GTHZ 0012 using GT HIS-12.
2005 NRC JPM S8                                             NUREG 1021, Revision 9
NOTE: Steps 23 - 26 ma y be accomplished in an y o r der. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-12.
 
C o m m e n t:   Evaluator's Cue:
Appendix C                           Page 10 of 17                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.6 Performance Step: 22 Start CGT02 Containment Mini Purge Exhaust Fan using GT HIS-20.
GT HIS-12 RED light il luminates and three (3) seconds later, the GREEN light extinguishes.
Standard:           Operator should select RUN on GT HIS-20, CTMT Mini Purge Exh Fan.
2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 11 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.2.9 Performanc e Step: 25 Open GTHZ 0028 using GT HIS-28.
Comment:
NOTE: Steps 23 - 26 ma y be accomplished in an y o r der. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-28.
Evaluators Cue:     GT HIS-20 RED lights illuminate and GREEN lights extinguish.
C o m m e n t:   Evaluator's Cue:
Step 5.2.7 Performance Step: 23 Open GTHZ0011 using GT HIS-11.
GT HIS-28 RED light il luminates and three (3) seconds later, the GREEN light extinguishes.
NOTE:               Steps 23 - 26 may be accomplished in any order.
Step 5.2.10 Performanc e Step: 26 Open GTHZ 0029 using GT HIS-29.
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-11.
NOTE: Steps 23 - 26 ma y be accomplished in an y o r der. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-29.
Comment:
C o m m e n t:   Evaluator's Cue:
Evaluators Cue:     GT HIS-11 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.
GT HIS-29 RED light il luminates and three (3) seconds later, the GREEN light extinguishes.
Step 5.2.8 Performance Step: 24 Open GTHZ0012 using GT HIS-12.
Step 5.2.11 Performanc e Step: 27 Record the date and time the CTMT Purge Exha ust and Mini Purge Exha ust Dampers are opene d on the Gaseous Radwaste Release Permit.
NOTE:               Steps 23 - 26 may be accomplished in any order.
S t a n d a r d: Operator should record t he date and time the CTMT Purge Exhaust and Mini Purge Exhaust Da mpers are opened on th e Gaseous Radwaste Release Permit.
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-12.
C o m m e n t:   Evaluator's Cue:
Comment:
The Gaseous Radw ast e Release Permit has been updated.
Evaluators Cue:     GT HIS-12 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.
2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 12 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.2.12 Performanc e Step: 28 Inform Coun t Room Technician whe n purge initiated.
2005 NRC JPM S8                                             NUREG 1021, Revision 9
S t a n d a r d: Operator should notify the Count Room Technician of the time the purge was initiat ed. C o m m e n t:   Evaluator's Cue:
 
Count Roo m Technician ackno w l edges. Step 5.2.13 Performanc e Step: 29 When CTMT pressure is less than 10" WG, OPEN GT HZ0041 and GTHZ0 042 using GT HIS-41.
Appendix C                           Page 11 of 17                     Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.9 Performance Step: 25 Open GTHZ0028 using GT HIS-28.
S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton o n GT HIS-41 when CTMT pressure is less than 10
NOTE:               Steps 23 - 26 may be accomplished in any order.
" WG. C o m m e n t:   Evaluator's Cue:
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-28.
CTMT pres sure is less than 10" W G. GT HIS-41 RED light il luminates and five (5) seconds later, the GREEN light extinguishes.
Comment:
2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 13 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.2.14 Performanc e Step: 31 When CTMT pressure is less than 4.25" WG, OPEN GTHZ0026 using GT HIS-26.
Evaluators Cue:     GT HIS-28 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.
NOTE: Steps 31 and 32 ma y b e performe d in an y order. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-26 when CTMT pressure is less than 4.
Step 5.2.10 Performance Step: 26 Open GTHZ0029 using GT HIS-29.
25" WG. C o m m e n t:   Evaluator's Cue:
NOTE:               Steps 23 - 26 may be accomplished in any order.
CTMT pres sure is now 2.5" WG.
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-29.
GT HIS-26 RED light il luminates and three (3) seconds later, the GREEN light extinguishes.
Comment:
Step 5.2.14 Performanc e Step: 32 When CTMT pressure is less than 4.25" WG, OPEN GTHZ0027 using GT HIS-27.
Evaluators Cue:     GT HIS-29 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.
NOTE: Steps 31 and 32 ma y b e performe d in an y order. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-27 when CTMT pressure is less than 4.
Step 5.2.11 Performance Step: 27 Record the date and time the CTMT Purge Exhaust and Mini Purge Exhaust Dampers are opened on the Gaseous Radwaste Release Permit.
25" WG. C o m m e n t:   Evaluator's Cue:
Standard:           Operator should record the date and time the CTMT Purge Exhaust and Mini Purge Exhaust Dampers are opened on the Gaseous Radwaste Release Permit.
CTMT pres sure is now 2.5" WG.
Comment:
GT HIS-27 RED light il luminates and three (3) seconds later, the GREEN light extinguishes.
Evaluators Cue:     The Gaseous Radwaste Release Permit has been updated.
Step 5.2.15 Performanc e Step: 33 Start SGT02 , CTMT Mini Purge Air Supply Unit with GT HIS-2
2005 NRC JPM S8                                               NUREG 1021, Revision 9
: 3. S t a n d a r d: Operator should select RUN on GT HIS-23.
 
C o m m e n t:   Evaluator's Cue:
Appendix C                           Page 12 of 17                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.12 Performance Step: 28 Inform Count Room Technician when purge initiated.
GT HIS-23 RED light il luminates and the GREEN light extinguishes.
Standard:           Operator should notify the Count Room Technician of the time the purge was initiated.
2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 14 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N    Step 5.2.16 Performanc e Step: 34 OPEN GTHZ0005 using GT HIS-5.
Comment:
NOTE: Steps 34 and 35 ma y b e performe d in an y order. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-5.
Evaluators Cue:     Count Room Technician acknowledges.
C o m m e n t:   Evaluator's Cue:
Step 5.2.13 Performance Step: 29 When CTMT pressure is less than 10 WG, OPEN GTHZ0041 and GTHZ0042 using GT HIS-41.
GT HIS-5 RED light illuminates and tw o (2) se conds later, the GREEN lig ht extinguishes.
Standard:           Operator should depress and hold the OPEN pushbutton on GT HIS-41 when CTMT pressure is less than 10 WG.
5.2.17 Performanc e Step: 35 OPEN GTHZ0004 using GT HIS-4.
Comment:
NOTE: Steps 34 and 35 ma y b e performe d in an y order. S t a n d a r d: Operator should depress and hold t he OPEN p u shbutton fo r GT HIS-4.
Evaluators Cue:     CTMT pressure is less than 10 WG.
C o m m e n t:   Evaluator's Cue:
GT HIS-41 RED light illuminates and five (5) seconds later, the GREEN light extinguishes.
GT HIS-4 RED light illuminates and tw o (2) se conds later, the GREEN lig ht extinguishes.
2005 NRC JPM S8                                             NUREG 1021, Revision 9
Performanc e Step: 36 Inform the Control Room Supervisor that CTMT Mini Purge has been reinitia ted. S t a n d a r d: Operator should inform the Control Room Supe rvisor that Mini Purge has been reinitiat ed. C o m m e n t:   Evaluator's Cue:
 
Control Ro om Supervisor acknowledges.
Appendix C                           Page 13 of 17                       Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.14 Performance Step: 31 When CTMT pressure is less than 4.25 WG, OPEN GTHZ0026 using GT HIS-26.
Terminating Cue:
NOTE:               Steps 31 and 32 may be performed in any order.
When Mini-Purge is rei n itiated, this JPM is co mplete. 2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 15 of 17 Form ES-C-1 PERF O R M ANCE I N FORMATI O N  STOP TI ME:     2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 16 of 17 Form ES-C-1 VERIFICATI O N OF COMPLETI ON  Job Performance Measure No.:
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-26 when CTMT pressure is less than 4.25 WG.
2005 NRC J P M S8   Exa m inee's Name:
Comment:
Evaluators Cue:     CTMT pressure is now 2.5 WG.
GT HIS-26 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.
Step 5.2.14 Performance Step: 32 When CTMT pressure is less than 4.25 WG, OPEN GTHZ0027 using GT HIS-27.
NOTE:               Steps 31 and 32 may be performed in any order.
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-27 when CTMT pressure is less than 4.25 WG.
Comment:
Evaluators Cue:     CTMT pressure is now 2.5 WG.
GT HIS-27 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.
Step 5.2.15 Performance Step: 33 Start SGT02, CTMT Mini Purge Air Supply Unit with GT HIS-23.
Standard:           Operator should select RUN on GT HIS-23.
Comment:
Evaluators Cue:     GT HIS-23 RED light illuminates and the GREEN light extinguishes.
2005 NRC JPM S8                                             NUREG 1021, Revision 9
 
Appendix C                             Page 14 of 17                   Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.16 Performance Step: 34 OPEN GTHZ0005 using GT HIS-5.
NOTE:               Steps 34 and 35 may be performed in any order.
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-5.
Comment:
Evaluators Cue:     GT HIS-5 RED light illuminates and two (2) seconds later, the GREEN light extinguishes.
5.2.17 Performance Step: 35 OPEN GTHZ0004 using GT HIS-4.
NOTE:               Steps 34 and 35 may be performed in any order.
Standard:           Operator should depress and hold the OPEN pushbutton for GT HIS-4.
Comment:
Evaluators Cue:     GT HIS-4 RED light illuminates and two (2) seconds later, the GREEN light extinguishes.
Performance Step: 36 Inform the Control Room Supervisor that CTMT Mini Purge has been reinitiated.
Standard:           Operator should inform the Control Room Supervisor that Mini Purge has been reinitiated.
Comment:
Evaluators Cue:     Control Room Supervisor acknowledges.
Terminating Cue:       When Mini-Purge is reinitiated, this JPM is complete.
2005 NRC JPM S8                                             NUREG 1021, Revision 9
 
Appendix C           Page 15 of 17             Form ES-C-1 PERFORMANCE INFORMATION STOP TIME:
2005 NRC JPM S8                         NUREG 1021, Revision 9
 
Appendix C                           Page 16 of 17               Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S8 Examinees Name:
Date Performed:
Date Performed:
Facility Evaluator:
Facility Evaluator:
Line 2,209: Line 3,634:
Question Documentation:
Question Documentation:
Question:
Question:
Response:
 
R e s u l t: S A T  U N S A T    Exa m iner's Signature:
===Response===
Date:   2005 NRC J P M S8 NUREG 102 1, Revision 9 Appendix C Page 17 of 17 Form ES-C-1 JPM CUE S H EET  INITIAL CONDITIONS:
Result:                     SAT            UNSAT Examiners Signature:                               Date:
Callaway Pl ant is in Mo de 1. A con t ainment mi ni purge was in progress to prepare for a containment entry. On e hour ago, a CPIS/CRVI S occurred due to a spike on GTRE0022. Repairs have been made to GT RE0022 and it is now op erable. Outside air temperature is expected to remain > 50°F.
2005 NRC JPM S8                                         NUREG 1021, Revision 9
INITIATING CUE: The Control Room Supe rvis or has directed you to re-initiate t he containment mini purge per OTN-GT-00001, Section 4.7. Th e Control Room Supervisor has decide d to not realign the contr o l building HVAC at this time. The SS has authorized reinitia ting CTMT mini purge. Inform the Control Room Su pervisor when the mini purge has been re-initiated.
 
2005 NRC J P M S8 NUREG 102 1, Revision 9}}
Appendix C                         Page 17 of 17                       Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant is in Mode 1. A containment mini purge was in progress to prepare for a containment entry. One hour ago, a CPIS/CRVIS occurred due to a spike on GTRE0022. Repairs have been made to GTRE0022 and it is now operable. Outside air temperature is expected to remain > 50°F.
INITIATING CUE:     The Control Room Supervisor has directed you to re-initiate the containment mini purge per OTN-GT-00001, Section 4.7. The Control Room Supervisor has decided to not realign the control building HVAC at this time. The SS has authorized reinitiating CTMT mini purge. Inform the Control Room Supervisor when the mini purge has been re-initiated.
2005 NRC JPM S8                                             NUREG 1021, Revision 9}}

Latest revision as of 04:09, 14 March 2020

CW-08-2005-Final Operating Examination
ML061560189
Person / Time
Site: Callaway Ameren icon.png
Issue date: 03/10/2005
From:
NRC Region 4
To:
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Download: ML061560189 (258)
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Text

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 1 Op Test No.: NRC Examiners: Operators:

Initial Conditions: 100% power, BOL.

RE-52, Blowdown Discharge Pumps Discharge Monitor, is OOS.

BB-PCV-455A PORV Leakage - Block Valve Closed.

Motor Driven AFW Pump A OOS.

Turnover: Reduce power to less than 90% at 1% per minute to remove Condensate Pump A from service due to a seal leak Critical Task: Start EDG A to energize Emergency Bus prior to initiation of ECA 0.0 coping steps.

Manually Start A HHSI pump prior to exit from EOP Attachment 1.

Event No. Malf. No. Event Type* Event Description 1 R - RO Reduce power N - BOP, SRO 2 I - BOP, SG level transmitter failure.

FWM02A SRO TS - SRO 3 C - ALL 4KV Bus NB02 Normal Feeder Breaker trip.

EPS05B TS - SRO 4 PRS02A I - RO, SRO Pressurizer Level Transmitter fails low TS - SRO 5 C - RO, RCS Leak requiring reactor trip.

RCS06C SRO 6 M - ALL Loss of off-site power, SBLOCA.

BAT 7 EPS06B C - BOP B DG Trips - A DG fails to AUTO Start. MANUAL Start required.

KJS012 8 C - RO A HHSI pump fails to AUTO Start - MANUAL Start required.

SBI008C

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 The crew will assume the shift at 100% power with instructions to reduce power due to a Condensate Pump seal leak.

At approximately 95% power, a Steam Generator Level transmitter will drift low, requiring the crew to take manual control of the feedwater regulating valve for the affected steam generator in accordance with OTO-AE-2. The SRO will also refer to Technical Specifications for the appropriate action requirements.

When technical specifications have been addressed, 4KV Vital Bus NB02 normal feeder breaker will trip. B EDG will automatically start and energize bus NB02. The crew will respond in accordance with alarm response procedures, OTO-NB-00002 and OTO-SA-1 to stop AFW flow and secure unnecessary equipment started by the Shutdown Sequencer. The SRO will refer to technical specifications.

When the plant is stable, a Pressurizer Level Transmitter will fail low, causing Letdown isolation.

The crew will restore letdown in accordance with OTO-BG-1. The SRO will address Technical Specifications.

An RCS leak will develop when Letdown is placed in service, requiring the crew to determine that the reactor must be tripped.

When the reactor is tripped, a loss of off-site power will occur. The RCS leak will progress to a SBLOCA.

Diesel Generator B trips and cannot be started. Diesel Generator A fails to automatically start, and must be manually started and aligned in accordance with E-0 or ECA-0.0. HHSI pump A fails to automatically start, and must be manually started.

The scenario may be terminated upon entry to ES-1.2, Post LOCA Cooldown and Depressurization.

EOP flow path: E-0, ECA-0.0, E-0, E-1, ES-1.2 Scenario 1 Scenario Malfunction List

1) Initialize at IC-20.
2) Run Batch File "iltone.txt", and verify the actions on the following page are loaded correctly.
3) Ensure Immediate Boration Timer is reset.
4) Check RX trip switch has a RED flag.
5) Ensure NIS indicates 100%
6) Ensure step counters for Control Bank D are set at 215 steps and all other step counters are set for 228.
7) Ensure the digital display is selected to REP0480A and RET0499A.
8) Ensure AE-LT-519 is selected
9) Ensure BB-LT-459 is selected
10) Hang hold off tags on the "A" MDAFP.
11) Ensure Decrease Loading Rate Button is ON.
12) Update status board for B Protected Train week. Record "A" MDAFP, LCO 3.7.5, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
13) Place Letdown orifi A and B in service with a caution tag on C
14) White board has the following boron concentrations:
  • "A" MDAFP T/S 3.7.5, Action C.1. 72 Hours. OOS @ 0500 Today
  • 'A' CCP "5 days ago" 1107 ppm
  • 'B' CCP "two weeks ago" 1135 ppm
15) Supply turnover and log sheets and OTG-ZZ-00004.
16) Ensure the RM-11 is on the training system.
17) Microphones available for each person being evaluated and a video tape is in the VCR.
18) Ensure chart recorders are "rolled forward".
19) Ensure copies of the following procedures are in the file drawers:
  • OTO-AE-00002 OTG-ZZ-00004
  • OTO-NB-00002 OTN-AD-00001
  • OTO-SA-00001 OTN-BG-00001, Addendum 4
  • OTO-BG-00001 OTN-EC-00001
  • ECA-0.0
  • E-0
  • E-1 E-2 Scenario 1 Scenario Malfunction List File: iltone.TXT

>Author: S. P. Aufdemberge

>Date: 20050504

>=============SCENARIO SETUP ITEMS===========================================

>TAGOUT "A" MDAFW PUMP

> FILE: AL01A.TXT

> Red lights stay on the ESFAS Panel bat al01a.txt

>Simulates de-energization of "A" PORV Block valve due to PORV Leakage ior bbhis8000a_ic (-1 0) 0 irf bbs014 (-1 0) 0

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT A

>'A' S/G lev xmttr fails to 0 psig over 60 sec from trigger #1 (MANUAL) imf fwm02a (1) 0 60

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT B

>Loss of NB02 normal feeder breaker, from trigger #2 (MANUAL) imf eps05b (2)

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT C

>Pressurizer Level Transmitter Fails Low, from trigger #3 (MANUAL) imf prs02a (3) 0 60

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT D

>RCS leak requiring Reactor trip,Grows to 600gpm over 10 minutes from Manual Trigger #5 imf rcs06c (5) 600 600

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT E

>Loss of Off-Site Power, from Manual trigger #6

> Incoming Lines imf eps03a (6 0) imf eps03b (6 3) imf eps03c (6 20) imf eps03g (6 5)

>Incoming Line lights irf msb006 (6 0) 0 irf msb007 (6 5) 0 irf msb008 (6 3) 0

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT F

>"B" EDG trips and "A" EDG will fail to automatically start. "B" EDG fails on the loss of off-site power imf eps06b (7)

>Loss of off-site power "sensed" by green light on RCP control switch trgset 7 "x21o115g.eq.0"

>Disable Automatic start of "A" EDG irf kjs012 (-1 0) 1

>============================================================================

>=======================EVENT PRELOAD========================================

>EVENT G

> "A" CCP fails to auto start, manual will be successful irf sbi008c (-1 0) 1

>end of file Scenario 1 Crew Turnover Separate Turnover sheets provided Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 6 of 36 Event

Description:

Reduce Power Time Position Applicants Actions or Behavior SRO Refer to OTO-MA-00008, Rapid Load Reduction CREW Determine amount of boric acid to reduce reactor power to 90%

CREW Record rate of turbine load change Discuss amount and rate of turbine load change and boric acid SRO addition with crew SRO Notify Load Dispatcher SRO Notify Chemistry, Health Physics, and Radwaste Initiate boron equalization

  • Energize at least 1 group of backup heaters RO
  • Place the PZR Master Controller in MAN
  • Lower PZR Master Controller output to 38% to 42%
  • Place the PZR Master Controller in AUTO 6

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 7 of 36 Event

Description:

Reduce Power Time Position Applicants Actions or Behavior Borate from the BAST using any of the following:

  • Emergency Boration o Start at least 1 Boric Acid Transfer Pump o Open Emergency Boration to Charging Pump suction BG HIS-8104 o Check Emergency Borate flow is greater than 30 GPM on BG FI-183A
  • Borate to the VCT RO o Place RCS Makeup Control to STOP (BG HS-26) o Place RCS Makeup Control Selector to BORATE (BG HS-25) o Reset Boric Acid counter to 000 (BG FY-110B) o Set BG FY-110B for the desired galloons of boric acid to be added o Place BG HS-26 in RUN RO Place Rod Control in AUTO Reduce turbine load at less than or equal to 5% per minute using any of the following:

o Reduce turbine load using the Load Limit potentiometer o Reduce turbine load using the %/min loading rate o Rotate Load Limit Set potentiometer clockwise until both of the following are met:

BOP Load Limit light extinguished At Set Load - LIT o Set Loading Rate Limit %/min to desired value o Select Decrease Loading Rate - ON o Lower load set MW toward desired load using DECREASE LOAD pushbutton 7

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 8 of 36 Event

Description:

Reduce Power Time Position Applicants Actions or Behavior BOP Check MFP Turbine Speed control in AUTO When power has been reduced approximately 5%, or at Lead Evaluators discretion, proceed to Event 2 8

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 2 Page 9 of 36 Event

Description:

SG Level Transmitter Failure Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for SG Level Transmitter failure Indications available:

REACTOR PARTIAL TRIP, annunciator 83C SG A LEV DEV, annunciator 108C SG A LEV LO, Annunciator 108B SRO Refer to OTO-AE-00002 for level malfunction IDENTIFY failed channel (LT-519) by comparing steam BOP generator level indicators.

BOP SELECT alternate level channel LT-551.

STABILIZE steam generator level at its programmed level (45-BOP 55%).

WHEN steam generator level is returned to programmed level BOP and IF placed in MANUAL during the transient, PLACE feedwater regulating valve to automatic control.

Refer to T/S LCO 3.3.1 TAB 3.3.1-1 Item 14 and T/S LCO 3.3.2 TAB 3.3.2-1 Item 5 and 6 and ENSURE compliance with SRO requirement for minimum operable channels and action statements.

o TS 3.3.1 and 3.3.2 apply (72 Hour Action)

Refer to T/S LCO 3.3.4 and T/S LCO 3.3.3 and ENSURE SRO compliance.

When Tech Specs have been identified, proceed to Event 3.

9

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 10 of 36 Event

Description:

4KV Bus NB02 Normal Feeder Breaker Trip Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for Bus NB02 breaker trip Indications available:

DG B starts and supplies NB02 SHUTDOWN SEQUENCER ACTUATED TRAIN B Annunciator 21C DIESEL GENERATOR NE02 TROUBLE Annunciator 23D NB01 BREAKER NOT OPERABLE Annunciator 18F SRO Refer to OTO-NB-00002, Loss of Power to NB02 RO Check 4160 VAC Bus NB02 ENERGIZED RO Check EDG B-Running BOP Check ESW Flow Aligned to EDG B BOP Check ESW Train A Properly Aligned RO Check Reactor Power less than 100%

BOP Check SG NR Level trending to or within 45 -55%

Check TDAFP Secured BOP o Throttle CLOSE TDAFP discharge FCVs Check MDAFP Secured BOP Throttle Closed MDAFP B Discharge FCVs RO Check Pressurizer Level at or trending to program level 10

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 11 of 36 Event

Description:

4KV Bus NB02 Normal Feeder Breaker Trip Time Position Applicants Actions or Behavior RO Check Pressurizer Pressure at or trending to 2220 - 2250 psig BOP Check CCW Pump B or D running Check only one charging pump running.

RO

  • Stop one charging pump RO Check RCP Seal Injection Flow between 8 -13 gpm/pump Crew Check any Service Air Compressors running BOP Check Panel PN08 Transferred to normal source RO/BOP Check SFP Cooling in service BOP Check CR (A or B) and Class IE (A and B) AC units running BOP Check busses PK02 and PK04 Go to OTA-RL-RK021, Attachment C, and verify automatic RO LSELS actuations o Ensure equipment is in normal alignment Refer to Attachment G for guidance concerning possible Tech SRO Spec action statements o TS 3.8.1 applies If desired, cross-tie PK02 and PK04 to functional battery SRO chargers in accordance with OTN-PK-00001 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 12 of 36 Event

Description:

4KV Bus NB02 Normal Feeder Breaker Trip Time Position Applicants Actions or Behavior If Swing Charger (NK26) is available, refer to OTN-NK-00001 SRO and, as required, charge batteries NK12 and NK14 RO/BOP Ensure A Control Room Air Conditioner is running Ensure A Class 1E Air Conditioner is running and take action SRO in accordance with FSAR 16.7.13.1 for the inoperable B Class 1E Air Conditioner When TDAFP and MDAFP flow is throttled, plant is stable, and Tech Specs have been addressed, or at Lead Examiners discretion, proceed to Event 4 12

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 13 of 36 Event

Description:

PZR Level Transmitter fails low. PZR LCV fails closed Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for Pressurizer Level transmitter failure Indications available:

PRESSURIZER LOW LEVEL DEVIATION Annunciator 32C LETDOWN HEAT EXCHANGER DISCHARGE FLOW HIGH LOW Annunciator 39E Letdown isolates CREW Identify the cause of the loss of letdown.

CREW Determine that PZR LVL INST FAILURE occurred. (LT-459)

RO Select alternate Pressurizer Level Control Channel (LT-461)

Isolate letdown by closing all orifice isolation valves. (Already RO closed)

Reduce charging flow to minimum required for RCP seal RO injection as follows:

If the CCP is in service, SLOWLY CLOSE BH HC-182 while RO reducing charging flow using BG FK-121. Maintain approximately 8 GPM to each RCP seal.

RO ENSURE BG-HC-182 is FULL CLOSED.

Verify Reactor Makeup Control System set in automatic for the RO correct boron concentrations and is maintaining VCT level.

RO STABILIZE pressurizer level as follows:

13

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 14 of 36 Event

Description:

PZR Level Transmitter fails low. PZR LCV fails closed Time Position Applicants Actions or Behavior Restore normal letdown per OTO-BG-00001, Pressurizer Level CREW Control Malfunctions.

Ensure Letdown system containment isolation valves are open RO

  • BG HIS-8152
  • BG HIS-8160 Ensure RCS Letdown to Regenerative Heat Exchanger Valves are open RO
  • BG HIS-459
  • BG HIS-460 Throttle Charging Header back Pressure Control Valve to RO establish 85-90 GPM
  • BG HIS-182 Place Letdown HX Outlet Pressure Controller in Manual and RO RAISE setpoint to greater than 75% open
  • BG PK-131 Open Orifice Isolation Valve(s) to establish desired letdown flow RO
  • BG HIS-8149AA
  • BG HIS-8149BA
  • BG HIS-8149CA Adjust Letdown HX Outlet Pressure Controller to maintain RO between 300 psig and 350 psig and place in Automatic
  • BG PK-131 Adjust Charging flow as necessary to maintain Pressurizer RO level 14

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 15 of 36 Event

Description:

PZR Level Transmitter fails low. PZR LCV fails closed Time Position Applicants Actions or Behavior When Letdown is restored, proceed to Event 5 15

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 16 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert commands for remaining events as sequenced Indications available:

PROCESS RADIATION HIGH Annunciator 61B Rising trend on Iodine and Particulate Channels 31, 32 If RMS has not been reset from previous failure, the following alarms will also indicate an RCS leak:

PRESSURIZER LOW LEVEL DEVIATION, 32C PRESSURIZER PRESSURE LOW HEATERS ON, 33C DETERMINE the approximate size of the leak. Should CREW determine greater than 50 GPM leak NOTE: The plant computer group tabular time trend GT-SG17 can be used to approximate the leak size.

USE trends of VCT level (20 GAL/%) and/or PZR level RO (60 GAL/%).

NOTE: Only one charging pump should be in operation until PZR level is increased for the plant cooldown.

COMPARE Charging and Letdown flow rates. Crew should RO determine that PZR level CANNOT be maintained.

SRO Direct Reactor Trip RO CHECK Reactor Trip:

  • Rod Bottom Lights - ALL LIT
  • Neutron Flux - LOWERING 16

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 17 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior BOP CHECK Turbine Trip:

All turbine Stop valves - CLOSED.

CREW CHECK Power to AC Emergency Buses:

AC emergency buses - AT LEAST ONE ENERGIZED

  • NB01(NO)

OR

  • NB02(NO)

SRO DIRECTS Go to ECA-0.0, Loss of All AC Power, Step 1.

RO CHECK Reactor Trip:

  • Neutron Flux - LOWERING BOP CHECK Turbine Trip:

All Turbine Stop valves - CLOSED.

RO CHECK if RCS is Isolated:

a. PZR PORVs - CLOSED
  • BB HIS-455A
  • BB HIS-456A
b. Letdown Isolation Valves - CLOSED 17

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 18 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

1. Letdown Orifice Isolation valves:
  • BG HIS-8149AA
  • BG HIS8149BA
  • BG HIS-8149CA
2. RCS Letdown to Regen HX valves:
  • BG HIS-459
  • BG HIS-460
c. RCS to Excess Letdown HX valves - CLOSED
  • BG HIS-8153A
  • BG HIS-8154A
  • BG HIS-8153B
  • BG HIS-8154B RO CLOSE valve(s) as necessary.
d. Reactor Head Vent Valves - CLOSED
  • BB HIS-8001A
  • BB HIS-8002A
  • BB HIS-8001B
  • BB HIS-8002B BOP CHECK AFW Flow - GREATER THAN 300,000 LBM/HR CREW TRY to Restore Power to Any AC Emergency Bus:
a. ENERGIZE AC emergency bus with diesel generator:

18

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 19 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior CRITICAL TASK 1. START DG(s):

  • KJ HS-8A - DG - A
2. CHECK AC emergency buses - AT LEAST ONE ENERGIZED
  • NB01 - ENERGIZED OR
  • NB02 - NOT ENERGIZED
b. CHECK AC emergency buses - AT LEAST ONE CREW ENERGIZED
  • NB01 - YES
c. CHECK ESW Pump associated with energized AC BOP emergency bus(es) - RUNNING
  • EF HIS-55A (NB01) - YES
d. Return to procedure and step in effect and IMPLEMENT Functional Restoration Procedures as necessary.
  • Crew will review CSF Status Trees. None currently required for implementation SRO DIRECTS return to E-0.

RO CHECK SI Status:

a. CHECK is SI is actuated:
  • SB069 SI Actuate RED light - LIT OR 19

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 20 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

b. CHECK both Trains of SI - ACTUATED
  • SB069 SI Actuate RED light - LIT SOLID (NOT blinking)

Note: PERFORM Attachment A, Automatic Action Verification, while Attachment BOP continuing with this procedure.

A contains a Critical Task (Actions for Attachment A begin on page 32 of this guide)

RO CHECK Generator Output Breakers - OPEN

  • MA ZL-3A (V55)
  • MA ZL-4A (V53)

RO CHECK Feedwater Isolation:

a. Main Feedwater Pumps - TRIPPED
b. Main Feedwater Reg Valves - CLOSED
  • AE ZL-510 (SG A)
  • AE ZL-520 (SG B)
  • AE ZL-530 (SG C)
  • AE ZL-540 (SG D)
c. Main Feedwater Reg Bypass Valves - CLOSED
  • AE ZL-550 (SG A) 20

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 21 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

  • AE ZL-560 (SG B)
  • AE ZL-570 (SG C)
  • AE ZL-580 (SG D)
d. Feedwater Isolation Valves - CLOSED
  • AE HIS-39 (SG A)
  • AE HIS-40 (SG B)
  • AE HIS-41 (SG C)
  • AE HIS-42 (SG D)

RO CHECK AFW Pumps:

a. MD AFW Pumps - BOTH RUNNING
  • AL HIS-23A
  • AL HIS-22A
b. TD AFW Pump - RUNNING IF NECESSARY RO CHECK AFW Valves - PROPER EMERGENCY ALIGNMENT
  • MD AFP Flow Control Valves - THROTTLED
  • AL-HK-5A
  • TD AFP Flow Control Valves - FULL OPEN
  • AL HK-6A 21

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 22 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior RO CHECK Total AFW Flow - GREATER THAN 300,000 LBM/HR RO CHECK PZR PORVs and Spray Valves:

a. PZR PORVs - CLOSED
  • BB HIS-455A
  • BB HIS-456A
b. PZR PORVs - BOTH IN AUTO
  • BB HIS-455A
  • BB HIS-456A
c. PORV Block Valves - BOTH OPEN
  • BB HIS-8000A
  • BB HIS-8000B
d. Normal PZR Spray Valves - CLOSED
  • BB ZL-455B
  • BB ZL-455C RO CHECK If RCPs Should Be Stopped:
a. RCPs - ANY RUNNING (NO)

SRO Go to Step 13.

RO CHECK RCS Temperatures:

  • NO RCPs running - RCS COLD LEG TEMPERATURES STABLE AT 557°F OR TRENDING TO 557°F 22

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 23 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior CREW CHECK If any SG Is Faulted:

a. CHECK pressures in all SGs:
  • ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR
  • ANY SG COMPLETELY DEPRESSURIZED SRO Go to Step 15.

CREW CHECK If SG Tubes Are Intact:

  • Levels in all SGs:
  • NO SG NARROW RANGE LEVEL RISING IN AN UNCONTROLLED MANNER
  • SG Steamline N16 radiation - NORMAL
  • N16 161 (SG A)
  • N16 162 (SG B)
  • N16 163 (SG C)
  • N16 164 (SG D)
  • Condenser Air Removal radiation - NORMAL BEFORE ISOLATION
  • GEG 925
  • SG Blowdown and Sample radiation - NORMAL BEFORE ISOLATION
  • BML 256
  • SJL 026 23

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 24 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

  • SG ASD radiation - NORMAL
  • Containment Pressure - NORMAL (NO)
  • GN PI-934
  • GN PI-935
  • GN PI-936
  • GN PI-937
  • GN PR-934
  • Containment Normal Sump Level - NORMAL
  • EJ LI-8
  • EJ LI-7
  • EJ LR-6
  • Containment Normal sump Level - NORMAL
  • LF LI-9
  • LF LI-10 24

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 25 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

  • Containment Radiation - NORMAL BEFORE ISOLATION
  • GTG 313
  • GTG 323
  • GTA 591
  • GTA 601 SRO Go To E-1, Loss of Reactor or Secondary Coolant, Step 1.

NOTE: Seal injection flow should be maintained to all RCPs.

CHECK If RCPs Should Be Stopped:

Loss of Power, already - TRIPPED BOP CHECK If Any SG Is Faulted:

CHECK pressures in all SGs:

  • ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR
  • ANY SG COMPLETELY DEPRESSURIZED (NO)

Go to Step 3.

BOP CHECK Intact SG Levels:

a. Narrow range levels - GREATER THAN 7% [25%]
b. CONTROL feed flow to maintain narrow range levels between 7% [25%] and 50%

25

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 26 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior BOP CHECK Secondary Radiation - NORMAL

a. PERFORM the following:
  • PERFORM EOP Addendum 11, Restoring SG Sampling After SI Actuation
  • DIRECT Chemistry to periodically sample all SGs for activity.
  • DIRECT Health Physics to survey steamlines in Auxiliary Building Area 5 as necessary
b. CHECK unisolated secondary radiation monitors:
  • SG Sample radiation:
  • SJL 026
c. Secondary radiation - NORMAL RO CHECK PZR PORVs and Block Valves:
a. Power to Block Valves - AVAILABLE
  • BB HIS-8000A (NO)
  • BB HIS-8000B 26

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 27 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

b. PZR PORVs - CLOSED
  • BB HIS-455A
  • BB HIS-456A
c. Block Valves - BOTH OPEN
  • BB HIS-8000A (NO)
  • BB HIS-8000B Crew CHECK If ECCS Flow Should Be Reduced:
a. RCS subcooling - GREATER THAN 30°F
b. Secondary heat sink:
  • Narrow range level in at least one intact SG -

GREATER THAN 7% [25%]

OR

  • Total feed flow to intact SGs - GREATER THAN 300,00 LBM/HR
c. RCS pressure - STABLE OR RISING
d. PZR level - GREATER THAN 9% [29%] (NO)

RO CHECK If Containment Spray should Be Stopped:

a. Spray Pumps - ANY RUNNING SRO Go to Step 8. OBSERVE CAUTIONS prior to Step 8.

27

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 28 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior CAUTION: If RCS pressure lowers in an uncontrolled manner to less than 325 PSIG, the RHR pumps must be manually restarted to supply water to the RCS.

RO CHECK If RHR Pumps Should Be Stopped:

a. CHECK RCS pressure:
1. Pressure - GREATER THAN 325 PSIG
2. Pressure - STABLE OR RISING
b. RHR Pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST
c. RESET SI if necessary:
d. STOP RHR Pumps and PLACE in standby:
  • EJ HIS-1
  • EJ HIS-2
e. MONITOR RCS pressure CREW CHECK SG and RCS Pressures:
  • CHECK pressure in all SGs - STABLE OR RISING
  • CHECK RCS pressure - STABLE OR LOWERING CREW CHECK If Diesel Generators Should Be Stopped:

28

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 29 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

a. AC emergency buses - ENERGIZED BY OFFSITE POWER
  • NB01 (NO)
  • NB02 (NO)

TRY to restore offsite power to AC emergency buses using EOP Addendum 7, Restoring Offsite Power.

b. RESET SI if necessary:
c. LOAD equipment on AC emergency bus(es) as necessary using EOP Addendum 8, Loading Equipment on AC emergency Buses.

CREW INITIATE Evaluation of Plant Status:

a. CHECK cold leg recirculation capability:
  • Train A - AVAILABLE
  • RHR Pump A (EJ HIS-1)
  • CCW Pump A (EG HIS-21) or CCW Pump C (EG HIS-23)
  • RWST To RHR Pump A Suction (BN HIS-8812A)
  • Containment Recirc Sump to RHR Pump A Suction (EJ HIS-8811A)
  • Train B - AVAILABLE
  • RHR Pump B (EJ HIS-2)
  • CCW Pump B (EG HIS-22) or CCW Pump D (EG HIS-24)
  • RWST To RHR Pump B Suction (BN HIS-8812B) 29

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 30 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

b. CHECK Auxiliary Building radiation - NORMAL
  • Aux Building Process Radiation monitor:
  • GLP 604
  • Aux Building Area Radiation monitors TRY to identify and isolate leakage:
  • DIRECT Health Physics and Chemistry to assist in the evaluation as necessary.

IF the cause is a loss of RCS inventory outside containment, THEN Go To ECA-1.2, LOCA Outside Containment, Step 1.

c. OBTAIN samples:
1. DIRECT Chemistry to initiate post accident sampling:
  • Containment atmosphere
2. PLACE Hydrogen Analyzers in Service using EOP Addendum 16, Placing Hydrogen Analyzers In Service.
3. CONSULT Plant Engineering Staff for assessing additional sampling requirements for fuel damage.
d. EVALUATE plant equipment for long term recovery as necessary:
  • Radwaste systems
  • Radiation monitoring
  • Operating safeguards equipment:

30

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5, 6, 7, & 8 Page 31 of 36 Event

Description:

RCS Leak - Loss of Off-Site Power - SBLOCA - DG Trip - HHSI Pump Failure Time Position Applicants Actions or Behavior

  • Containment Cooler Fans
  • Control Room ventilation
  • Auxiliary Building ventilation
  • Fuel Building ventilation
e. START additional plant equipment to assist in recovery as directed by SS/CRS CREW CHECK If RCS Cooldown And Depressurization Is Required
a. RCS pressure - GREATER THAN 325 PSIG
b. Go to ES-1.2, Post LOCA Cooldown And Depressurization, Step 1 Scenario may be terminated on transition to ES-1.2, or when all critical tasks are complete and at Lead Examiner discretion 31

ATTACHMENT A Automatic Action Verification BOP CHECK Charging Pumps:

CRITICAL TASK BOP a. CCPs - BOTH RUNNING

  • BG HIS-1A (Must manually start HHSI Pump A)
  • BG HIS-2A BOP b. STOP NCP:
  • SI Pumps - BOTH RUNNING (NO)
  • RHR Pumps - BOTH RUNNING
  • EJ HIS-1

BOP a. CCPs to Boron Inj Header - FLOW INDICATED

  • EM FI-917A
  • EM FI-917B BOP b. RCS pressure - LESS THAN 1700 PSIG BOP c. SI Pump Discharge - FLOW INDICATED

ATTACHMENT A Automatic Action Verification BOP e. RHR To Accumulator Injection Loop - FLOW INDICATED

  • EJ FI-618
  • EJ FI-619 CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

BOP CHECK ESW Pumps - BOTH RUNNING

  • EF HIS-55A
  • EF HIS-56A BOP CHECK CCW Alignment:

BOP a. CCW Pumps - ONE RUNNING IN EACH TRAIN

  • Red Train:
  • EG HIS-21 or EG HIS-23
  • Yellow Train
  • EG HIS-22 or EG HIS-24
b. CCW Service Loop Supply and Return valves for one BOP operating CCW pump - OPEN
  • EG ZL-15 AND EG ZL-53 OR
  • EG ZL-16 AND EG ZL-54 CHECK Containment Cooler Fans - RUNNING IN SLOW BOP SPEED
  • GN HIS-9
  • GN HIS-17
  • GN HIS-5
  • GN HIS-13 CHECK Containment Hydrogen Mixing Fans - RUNNING IN BOP SLOW SPEED 33

ATTACHMENT A Automatic Action Verification

  • GN HIS-2
  • GN HIS-4
  • GN HIS-1

BOP a. CHECK the following:

  • Containment pressure - GREATER THAN 27 PSIG OR
  • GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR
  • EN HIS-3
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP d. ESFAS status panels CISB sections:
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:

BOP a. CHECK for any of the following:

  • Containment pressure - GREATER THAN 17 PSIG 34

ATTACHMENT A Automatic Action Verification OR

  • GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 17 PSIG OR
  • Steamline pressure - LESS THAN 615 PSIG OR
  • AB PR-514 or PR-535 indicates steamline pressure -

HAS BEEN LESS THAN 615 PSIG BOP b. CHECK MSIVs and Bypass valves - CLOSED BOP CHECK ECCS Valves - PROPER EMERGENCY ALIGNMENT BOP a. ESFAS status panels SIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK Containment Isolation Phase A:

BOP a. ESFAS status panels CISA sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK SG Blowdown Isolation:

BOP ESFAS status panels SGBSIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

BOP CHECK Both Trains of control Room Ventilation Isolation:

35

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 2 Op Test No.: NRC Examiners: Operators:

Initial Conditions: 50% power, BOL.

RE-52, Blowdown Discharge Pumps Discharge Monitor, is OOS.

BB-PCV-455A PORV Leakage - Block Valve Closed.

Motor Driven AFW Pump A OOS.

Turnover: Maintain stable plant conditions Critical Task: Insert negative reactivity by inserting control rods or initiating emergency boration prior to the end of step 4 of FR-S.1.

Isolate AFW to faulted SG prior to occurrence of an ORANGE condition on the Integrity CSF Status Tree.

Event Malf. Event Event No. No. Type* Description 1 I - RO, Pressurizer pressure instrument fails high T+10 PRS01A SRO TS - SRO 2 C - BOP, B Feedwater Control Valve fails closed in automatic T+25 FWM03B SRO 3 I - ALL Turbine First Stage Pressure Transmitter fails low T+35 PCS02B TS - SRO 4 CRF04_52 M - ALL Multiple Dropped Rods - requires reactor trip T+50 CRF04_53 5 C - ALL ATWS CRF13 6 C - BOP Stuck open safety valve.

MSS14A

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 The crew will assume the shift with instructions to maintain present plant conditions The controlling pressurizer pressure transmitter will fail high, requiring the crew to select an alternate pressure channel to control heaters and spray in accordance with OTO-BB-6. The SRO will also determine the appropriate technical specification action requirements.

When the plant is stable, a Feedwater Control Valve will fail closed in automatic, requiring manual operation to restore SG level.

When SG level is restored, PT-506 will fail low, requiring the RO to place Rod Control in manual to stop rod motion, the BOP to select PT-505 for control, reset C-7, and place steam dumps in the Steam Pressure mode in accordance with OTO-AC-3. The SRO will also address Technical Specifications.

Multiple control rods will drop. A reactor trip is required but an ATWS occurs. The crew must take action to initiate RCS emergency boration and de-energize rod drive MG sets. A SG safety valve will stick open, requiring the crew to isolate AFW flow to the SG and attempt isolation.

The scenario may be terminated when the crew transitions to ES-1.1, SI Termination.

EOP Flow Path: E-0, FR-S.1, E-0, E-2, ES-1.1 Scenario 2 Scenario Malfunction List

1) Initialize at IC-17, 50%.
2) Run Batch File ilttwo.txt and verify the actions on the following page are loaded correctly.
3) Ensure immediate boration timer is reset.
4) Ensure BB PT-455 is selected as the controlling pressure channel.
5) Ensure First Stage Pressure Transmitter PT-506 is selected for control
6) Ensure NIS indicates 50% power.
7) Check Rx Trip switch has a red flag.
8) Ensure step counters for Control Bank "D" are set at 150 steps and all other step counters are set at 228 steps.
9) Ensure the digital display is selected to REP0480A and RET0499A.
10) Place 'A' MDAFP in PTL and hand a Hold Off tag on handswitch ALHIS23A.
11) Ensure Decrease Loading Rate Button is "ON".
12) Update the status board for "B" train week.
13) Update Status Board - 'A' MDAFP, TS 3.7.5, Condition C, 72 hrs. Current outage time is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
14) Ensure Letdown orifi A and B are in service, and a caution tag placed on C
15) Ensure AEHV38 is appropriately throttled
16) White board has the following boron concentrations:
  • "A" CCP 5 days ago 1105 ppm
  • "B" CCP 15 days ago 1132 ppm
17) Ensure chart recorders are "rolled forward".
18) Microphones are available for each person being evaluated and a videotape is in the VCR.
19) Ensure the RM-11 is on the training system.
20) Ensure turnover sheets and log sheets are on the desks.
21) Ensure copies of the following procedures are in the file drawers:
  • OTO-BB-00006
  • OTO-AE-00001
  • OTO-AC-00003
  • E-0
  • FR-S.1
  • E-2
  • ES-1.1 Scenario 2 Scenario Malfunction List File: ilttwo.TXT

>Author: S. P. Aufdemberge

>Date: 20050504

>=============SCENARIO SETUP ITEMS===========================================

>Remove 'A' MDAFP from service

>FILE AL01A.TXT

>Simulates tag out of the MD AFP A in the Pull-to-lock position bat al01a.txt

>Simulates de-energization of "A" PORV Block valve due to PORV Leakage ior bbhis8000a_ic (-1 0) 0 irf bbs014 (-1 0) 0

>===========================================================================

>=============EVENT PRELOAD=================================================

>EVENT 1

>Pressurizer Pressure Channel BBPT0455 fails to 2500 over 60 seconds

>Manually Input Event 1 imf prs01a (1 0) 2500 60

>===========================================================================

>=============EVENT PRELOAD=================================================

>EVENT 2

>"B" Feed Reg Valve fails closed in Automatic over 90 seconds

>Manually Input Event 2 imf fwm03b (2 0) 0 90

>===========================================================================

>=============EVENT PRELOAD=================================================

>EVENT 3

>ACPT0506 fails low over 60 second ramp

>Manually Input Event 3 imf pcs02b (3 0) 0 60

>===========================================================================

>=============EVENT PRELOAD=================================================

> EVENT 4

>Multiple Dropped Rods

>Manually Input Event 4 imf crf04_52 (4) imf crf04_53 (4)

>===========================================================================

>=============EVENT PRELOAD=================================================

>EVENT 5

>PROTECTIVE SYSTEM FAILURE (ATWS) Preloaded into scenario. No Manual Input >required imf crf13 (-1 0) both

>===========================================================================

>=============EVENT PRELOAD=================================================

>EVENT 6

>Main Steam Safety Valve Fails 100% Open, with a 10 sec delay, and a 1 sec >ramp from trigger #6 (CONDITIONAL) trgset 6 "sac.le.10" imf mss14a (6 10) 100 1

>===========================================================================

>end of file Scenario 2 Crew Turnover Separate Turnover Sheets provided Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 1 Page 6 of 28 Event

Description:

Pressurizer Pressure Instrument Failure Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for PT-455 failure HIGH Indications Available:

PRESSURIZER HIGH PRESSURE DEVIATION Annunciator 33B PRESSURIZER PRESSURE LOW HEATERS ON Annunciator 33C REACTOR PARTIAL TRIP Annunciator 83C PT-455 indicates high Refer to OTO-BB-0006, Pressurizer Pressure Control System SRO Instrument Failures RO Select an alternate channel (457/456)

RO Check PZR pressure 2200 - 2250 psig RO Check P-11 correct state (Not Lit)

BOP Select recorder to valid channel SRO Direct I&C to trip the affected bistables SRO Refer to Tech Specs

  • 3.3.1, Condition E, M
  • 3.3.2 Condition D, L
  • 3.3.4 Item 3

After Technical Specifications have been addressed, proceed to Event 2

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 7 of 28 Event

Description:

B Feedwater Control Valve fails closed in automatic Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for Feedwater Control Valve failure Indications Available:

B FRV failing closed Feedwater flow to B SG Lowering STEAM GENERATOR B FLOW MISMATCH Annunciator 109D BOP Determines SG B level is lowering.

Place AE-FK-520, SG B MFW Reg Valve Control, in BOP MANUAL, and restore SG level.

SRO Refer to OTO-AE-0001, Feedwater System Malfunctions.

RO Place Rod Control in AUTO BOP Check Main Feed Pump tripped (NO)

BOP Check Main Feed Pump Speed controlling in auto and stable Check Main Feed Reg Valves controlling in Auto (NO)

BOP

  • Ensure Manual control
  • Check Main Feed Reg Bypass Valves in service (NO)

BOP

  • Check Condensate Pump operation
  • Check Heater Drain Pump operation BOP Verify SG NR level trend 45 - 55% and maintain RO Monitor or operate rod control to maintain Tave/Tref +/- 5 °F

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 8 of 28 Event

Description:

B Feedwater Control Valve fails closed in automatic Time Position Applicants Actions or Behavior BOP Check MFP Oil Pressure normal SRO Perform communications per Ops Communications-01 SRO Verify Power change less than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> When the plant is stable, proceed to Event 3

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 9 of 28 Event

Description:

Turbine First Stage Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for First Stage Pressure Channel PT-506 failing low Indications Available:

PT-506 indication failing low Control Rods stepping in if in auto Rx Deviation alarm Refer to OTO-AC-00003, Turbine Impulse Pressure Channel SRO Failure RO Place Rod Control in MANUAL Identify the failed channel by comparing meter indications and BOP identifying alarmed annunciators. (PT-506)

Select the alternate impulse pressure channel by utilizing the BOP Impulse Pressure selector switch AC PS-505Z.

RO Check Tave within 1.5°F of Tref (When restored, then maintain)

Check Rod Control in AUTO RO

  • Will place in AUTO if directed by SRO and Tave and Tref are matched Maintain Tavg at the corresponding Tref value for existing plant RO power. Ensure RX power is less than 3565 MWth.

Place the Steam Dump Interlock Selector switches (AB-HS-64 BOP and AB-HS-63) to the OFF/RESET position.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 10 of 28 Event

Description:

Turbine First Stage Pressure Transmitter Fails Low Time Position Applicants Actions or Behavior BOP Check C-7, Load Loss Stm Dump Armed - Extinguished Transfer Steam Dumps to the Steam Pressure Mode:

  • Set the AB PK-507, Steam Header Pressure controller BOP for 7.28 turns (1092 psig)
  • Place the Steam Dump Select to STEAM PRESS BOP Place the Steam Dump Bypass Interlock switches to ON Check the following permissives are in their correct state within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the channel failure per Attachment B, permissives:

CREW

  • P-7 (LIT)
  • P-13 (LIT)

Direct an RO to Place SW12 for PT-506 at AMSAC SRO Test/Bypass Panel and place SW11, Bypass toggle switch, to the right hand position Refer to T/S LCO 3.3.1 (Improved T/S LCO 3.3.1) to ensure SRO compliance with the requirements for minimum channels.

  • Condition T RO Restore Rod Control to Manual if directed Note:

10 minutes after the failure, ATWS System Trouble Alarm, 83F, will annunciate.

(No consequence)

When Tech Specs have been addressed, proceed to Event 4

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 11 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior Booth Instructor Instructions:

When directed, insert commands to initiate remainder of events as sequenced Indications Available:

Two dropped control rods Rod Bottom lights Multiple annunciators CREW Recognizes more than one control rod dropped.

SRO Directs reactor trip.

RO Attempts to trip reactor. Reactor will not trip.

SRO Directs entry to FR-S.1 RO CHECK Reactor Trip:

  • Rod Bottom Lights - ALL LIT (NO)
  • Neutron Flux - LOWERING (Possible, if Control Rod insertion is in progress))

Manually TRIP Reactor:

IF reactor will NOT trip, THEN PERFORM the following:

CRITICAL a. Manually INSERT control rods when AUTO slows TASK RO below 48 SPM, or insert manually continuously.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 12 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior BOP b. OPEN supply breakers to PG19 and PG20:

  • PG HIS-16
  • PG HIS-18 WHEN reactor is tripped, THEN CLOSE supply breakers to PG19 and PG20.

BOP CHECK Turbine trip:

All Turbine Stop valves - CLOSED BOP CHECK AFW Pumps Running:

a. MD AFW Pumps - BOTH RUNNING (Must start B MDAFW Pump)
  • AL HIS-23A
  • AL HIS-22A
b. TD AFW Pump - RUNNING IF NECESSARY (May need to start)

CRITICAL TASK RO INITIATE Emergency Boration of RCS:

Note:

If SI is actuated, HHSI will be providing boration flow via the RWST

a. CHECK charging pumps - AT LEAST ONE RUNNING
  • BG HIS-1A
  • BG HIS-2A OR

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 13 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

  • NCP:
  • BG HIS-3 RO b. ALIGN emergency boration flow path:
1. START Boric Acid Transfer Pumps:
  • BG HIS-5A
  • BG HIS-6A
2. OPEN Emergency Borate to Charging Pump Suction valve:
  • BG HIS-8104
3. CHECK Emergency Boration Flow - GREATER THAN 30 GPM
  • BG FI-183A
4. MAINTAIN charging flow - GREATER THAN EMERGENCY BORATION FLOW
c. CHECK PZR Pressure - LESS THAN 2335 PSIG CREW CHECK Containment Purge Isolation:
a. ESFAS status panels CPIS sections:
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT RO CHECK If the Following Trips Have Occurred:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 14 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

a. Reactor trip:
  • Rod Bottom Lights - ALL LIT (YES)
  • Neutron Flux - LOWERING (YES)

BOP b. Turbine trip:

  • All Turbine Stop Valves - CLOSED RO CHECK If Reactor Is Subcritical:
a. Power Range channels - LESS THAN 5% (POST ACCIDENT PR - LESS THAN 5%)
b. Intermediate Range channels - NEGATIVE STARTUP RATE (POST ACCIDENT PR - STABLE OR LOWERING)

Go to Step 16. OBSERVE CAUTION prior to Step 16.

SRO Directs entry to E-0.

RO CHECK Reactor Trip:

  • Rod Bottom Lights - ALL LIT (YES)
  • Reactor Trip and Bypass Breakers - OPEN (NO) o Dispatch AO to Open RTBs
  • Neutron Flux - LOWERING (YES)

BOP CHECK Turbine Trip:

a. All turbine Stop Valves - CLOSED BOP CHECK Power to AC Emergency Buses:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 15 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

a. AC emergency buses - AT LEAST ONE ENERGIZED
  • NB02
b. AC emergency buses - BOTH ENERGIZED CREW CHECK SI Status:
a. CHECK if SI is actuated:
  • SB069 SI Actuate RED light - LIT OR
b. CHECK both Trains of SI - ACTUATED
  • SB069 SI Actuate RED light - LIT SOLID (NOT blinking)

PERFORM Attachment A, Automatic Action Verification, while BOP continuing with this procedure.

BOP CHECK Generator Output Breakers - OPEN

  • MA ZL-3A (V55)
  • MA ZL-4A (V53)

BOP CHECK Feedwater Isolation:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 16 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior BOP a. Main Feedwater Pumps - TRIPPED

  • AE ZL-510 (SG A)
  • AE ZL-520 (SG B)
  • AE ZL-530 (SG C)
  • AE ZL-540 (SG D)

BOP c. Main Feedwater Reg Bypass Valves - CLOSED

  • AE ZL-550 (SG A)
  • AE ZL-560 (SG B)
  • AE ZL-570 (SG C)
  • AE ZL-580 (SG D)

BOP d. Feedwater Isolation Valves - CLOSED

  • AE HIS-39 (SG A)
  • AE HIS-40 (SG B)
  • AE HIS-41 (SG C)
  • AE HIS-42 (SG D)

BOP CHECK AFW Pumps:

a. MD AFW Pumps - BOTH RUNNING (B MDAFW Pump is running. A MDAFW Pump is OFF)
  • AL HIS-23A
  • AL HIS-22A

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 17 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

b. TD AFW Pump - RUNNING IF NECESSARY BOP CHECK AFW Valves - PROPER EMERGENCY ALIGNMENT
  • MD AFP Flow Control Valves - THROTTLED
  • TD AFP Flow Control Valves - FULL OPEN (May isolate to BOP faulted SG)
  • AL HK-6A BOP CHECK total AFW Flow - GREATER THAN 300,000 LBM/HR RO CHECK PZR PORVs and Spray Valves:

RO a. PZR PORVs - CLOSED

  • BB HIS-455A
  • BB HIS-456A RO b. PZR PORVs - BOTH IN AUTO
  • BB HIS-455A
  • BB HIS-456A RO c. PORV Block Valves - BOTH OPEN (NO)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 18 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

  • BB HIS-8000A (CLOSED)
  • BB HIS-8000B RO d. Normal PZR Spray Valves - CLOSED
  • BB ZL-455B
  • BB ZL-455C NOTE: Seal injection flow should be maintained to all RCPs.

RO CHECK If RCPs Should Be Stopped:

RO a. RCPs - ANY RUNNING RO b. ECCS Pumps - AT LEAST ONE RUNNING

CREW CHECK RCS Temperatures:

  • Any RCP running - RCS TAVG STABLE AT 557°F OR TRENDING TO 557°F (NO)

If TEMPERATURE IS LESS THAN 557°F and LOWERING, then perform THE FOLLOWING:

BOP a. STOP dumping steam.

b. IF cooldown continues, THEN CONTROL total feed flow:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 19 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

  • MAINTAIN total feed flow greater than 300,000 LBM/HR until narrow range level is greater than 7%

[25%] in at least one SG.

c. IF cooldown continues, THEN FAST CLOSE all MSIVs and BOP Bypass valves: (May have been performed)
  • AB HS-80 BOP CHECK If Any SG Is Faulted:
a. CHECK pressures in all SGs:
  • ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER (A SG)

OR

CAUTIONS: At least one SG must be maintained available for RCS cooldown.

Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

BOP CHECK MSIVs and Bypass Valves - CLOSED BOP CHECK If Any SG Secondary Pressure Boundary Is Intact:

a. CHECK pressures in all SGs - ANY STABLE OR RISING BOP IDENTIFY Faulted SG(s):

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 20 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior BOP a. CHECK pressures in all SGs:

  • ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER (A)

OR

  • ANY SG COMPLETELY DEPRESSURIZED BOP ISOLATE Faulted SG(s):

CRITICAL TASK BOP a. ISOLATE AFW flow to faulted SG(s):

  • CLOSE associated MD AFP Flow Control Valve(s):
  • CLOSE associated TD AFP Flow Control Valve(s):

BOP b. CHECK ASD from faulted SG(s) - CLOSED

c. Locally CLOSE TDAFP Steam Supply From Main steam Loop Manual Isolation valve from faulted SG(s):
  • ABV0085 (SG B)
  • ABV0087 (SB C)
d. CHECK Main Feedwater valves to faulted SG(s) -

BOP CLOSED

  • AE ZL-510 (SG A)
  • AE ZL-550 (SG A)
  • AE HIS-39 (SG A)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 21 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior

e. CHECK SG Blowdown containment Isolation Valve from BOP faulted SG(s) - CLOSED
  • BM HIS-1A (SG A)
f. CLOSE Steamline Low Point Drain valve from faulted BOP SG(s):

CHECK CST To AFP Suction Header Pressure - GREATER BOP THAN 2.7 PSIG CREW CHECK Secondary Radiation:

a. PERFORM EOP Addendum 11, Restoring SG Sampling BOP/SRO After SI Actuation
  • PERFORM EOP Addendum 11, Restoring SG Sampling After SI Actuation
  • DIRECT Chemistry to periodically sample all SGs for activity
  • DIRECT Health Physics to survey steamlines in Auxiliary Building Area 5 as necessary CREW b. CHECK unisolated secondary radiation monitors:
  • SG Sample radiation:
  • SJL 026

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 22 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior radiation:

c. Secondary radiation - NORMAL CREW CHECK If ECCS Flow Should Be Reduced:
a. RCS subcooling - GREATER THAN 30°F
b. Secondary heat sink:
  • Narrow range level in at least one intact SG -

GREATER THAN 7% [25%]

OR

  • Total feed flow to intact SGs - GREATER THAN 300,000 LBM/HR
c. RCS pressure - STABLE OR RISING
d. PZR level - GREATER THAN 9% [29%]

RO RESET SI:

  • SB HS-43A RO STOP All But One CCP:
  • BG HIS-1A OR

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4,5,6 Page 23 of 28 Event

Description:

Multiple dropped rods, ATWS, Stuck Open Main Steam Safety Valve Time Position Applicants Actions or Behavior Scenario may be terminated upon transition to ES-1.1, or at Lead Examiners discretion after all critical tasks are complete

ATTACHMENT A Automatic Action Verification BOP CHECK Charging Pumps:

BOP a. CCPs - BOTH RUNNING

  • BG HIS-1A
  • BG HIS-2A BOP b. STOP NCP:
  • SI Pumps - BOTH RUNNING
  • RHR Pumps - BOTH RUNNING
  • EJ HIS-1

BOP a. CCPs to Boron Inj Header - FLOW INDICATED

  • EM FI-917A
  • EM FI-917B BOP b. RCS pressure - LESS THAN 1700 PSIG BOP c. SI Pump Discharge - FLOW INDICATED
  • EJ FI-618

ATTACHMENT A Automatic Action Verification

  • EJ FI-619 CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

BOP CHECK ESW Pumps - BOTH RUNNING

  • EF HIS-55A
  • EF HIS-56A BOP CHECK CCW Alignment:

BOP a. CCW Pumps - ONE RUNNING IN EACH TRAIN

  • Red Train:
  • EG HIS-21 or EG HIS-23
  • Yellow Train
  • EG HIS-22 or EG HIS-24
b. CCW Service Loop Supply and Return valves for one BOP operating CCW pump - OPEN
  • EG ZL-15 AND EG ZL-53 OR
  • EG ZL-16 AND EG ZL-54 CHECK Containment Cooler Fans - RUNNING IN SLOW BOP SPEED
  • GN HIS-9
  • GN HIS-17
  • GN HIS-5
  • GN HIS-13 CHECK Containment Hydrogen Mixing Fans - RUNNING IN BOP SLOW SPEED
  • GN HIS-2
  • GN HIS-4

ATTACHMENT A Automatic Action Verification

  • GN HIS-1

BOP a. CHECK the following:

  • Containment pressure - GREATER THAN 27 PSIG OR
  • GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR
  • EN HIS-3
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP d. ESFAS status panels CISB sections:
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:

BOP a. CHECK for any of the following:

  • Containment pressure - GREATER THAN 17 PSIG OR
  • GN PR-934 indicates containment pressure - HAS

ATTACHMENT A Automatic Action Verification BEEN GREATER THAN 17 PSIG OR

  • Steamline pressure - LESS THAN 615 PSIG OR
  • AB PR-514 or PR-535 indicates steamline pressure -

HAS BEEN LESS THAN 615 PSIG BOP b. CHECK MSIVs and Bypass valves - CLOSED BOP CHECK ECCS Valves - PROPER EMERGENCY ALIGNMENT BOP a. ESFAS status panels SIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK Containment Isolation Phase A:

BOP a. ESFAS status panels CISA sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK SG Blowdown Isolation:

BOP ESFAS status panels SGBSIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

BOP CHECK Both Trains of control Room Ventilation Isolation:

BOP a. ESFAS status panels CRVIS sections:

  • SA066X WHITE lights - ALL LIT

ATTACHMENT A Automatic Action Verification

  • SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:

BOP a. ESFAS status panels CPIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
  • Manual actions taken
  • Failed Equipment
  • Attachment A, Automatic Action Verification, completed

ATTACHMENT A Automatic Action Verification BOP a. ESFAS status panels CRVIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:

BOP a. ESFAS status panels CPIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
  • Manual actions taken
  • Failed Equipment
  • Attachment A, Automatic Action Verification, completed 36

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 3 Op Test No.: NRC Examiners: Operators:

Initial Conditions: 5 - 10% power, BOL.

RE-52, Blowdown Discharge Pumps Discharge Monitor, is OOS.

BB-PCV-455A PORV Leakage - Block Valve Closed.

Turnover: Increase power to 100% at 3% per hour Critical Task: Isolate ruptured SG in step 3 of E-3.

Establish and Maintain RCS temperature below that required for depressurization of the ruptured SG.

Event Malf. Event Event No. No. Type* Description 1 R - RO Raise power.

T+0 N - BOP, SRO 2 I - ALL Power Range NI failure.

NIS03D T+10 TS - SRO 3 I - BOP, Steam Dump pressure setpoint failure.

MSS13B T+30 SRO 4 C - RO, RCP high vibration.

T+40 BBV001 SRO TS - SRO 5 M - ALL SGTR. Reactor trip required.

RCS02A T+60 6 C - BOP Atmospheric dump valve fails open, requiring manual isolation.

MSS07A 7 Component C - RO Instrument air to containment fails closed, requiring alternate RCS Override depressurization.

KAHIS29

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 The crew will assume the shift with instructions to raise reactor power in preparation for returning the unit to full power.

When the power ascension is in progress, a power range instrument will fail high, requiring the crew to respond in accordance with OTO-SE-1. The crew will manually control feedwater bypass flow and remove the failed channel from service. The SRO will also determine the appropriate technical specification action requirements.

When the plant is stable and technical specifications have been addressed, a steam dump pressure setpoint failure will require the crew to place steam dumps in off/reset and control reactor power and Tave manually in accordance with OTO-AB-1 and OTO-AB-4.

When the plant is stable, increasing RCP vibration will require the crew to enter OTO-BB-2 to determine that the RCP must be stopped in accordance with OTN-BB-3. The crew will stop the affected RCP after determining reactor power is below P-8. Actions of OTO-BB-4 will also be performed to defeat Loop Delta T and Tave inputs. The SRO will also determine the appropriate technical specification action requirements.

When the plant is stable, a SGTR develops, requiring the crew to trip the reactor and initiate Safety Injection. An atmospheric dump valve will fail open in automatic and require manual closure. Instrument Air to containment will fail closed, requiring alternate RCS depressurization.

The scenario may be terminated when ECCS pumps are stopped in E-3, Steam Generator Tube Rupture.

EOP Flow Path: E-0, E-3 SCENARIO SETUP GUIDE EXAM #: ILT-1 Scenario Malfunction List

1) Initialize at IC-67. password = redsox, MONITOR CAF20(4) equal 1.0
2) Run Batch File "iltthree.txt", and verify the actions on the following page are loaded correctly.
3) Ensure Immediate Boration Timer is reset.
4) Check RX trip switch has a RED flag.
5) Ensure NIS indicates 10%
6) Ensure step counters for Control Bank D are set at 114 steps and all other step counters are set for 228.
7) Ensure the digital display is selected to REP0480A and RET0499A.
8) Ensure Decrease Loading Rate Button is ON.
9) Update status board for B Protected Train week.
10) Place Letdown orifi A and B in service with a caution tag on C
11) White board has the following boron concentrations:
  • 'A' CCP "5 days ago" 1107 ppm
  • 'B' CCP "two weeks ago" 1135 ppm
12) Supply turnover and log sheets, Xe Predict, Dilution/Boration calculation and OTG-ZZ-00003.
13) Ensure the RM-11 is on the training system.
14) Microphones available for each person being evaluated and a video tape is in the VCR.
15) Ensure chart recorders are "rolled forward".
16) Ensure copies of the following procedures are in the file drawers:
  • OTO-SE-00001
  • OTO-AB-00004
  • OTO-AB-00001
  • OTO-BB-00002
  • OTN-BB-00003
  • E-0
  • E-3 Scenario 3

>File: iltthree.txt

>Author: S. P. Aufdemberge

>Date: 20050517

>=============SCENARIO SETUP ITEMS===========================================

>Simulates de-energization of "A" PORV Block valve due to PORV Leakage irf bbs014 (-1 0) 0

>BMRE52 OOS Pre-Setup imf rms6_08 (-1 0)

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT A

>Fail N44 to full scale high imf nis03d (1 0) 200 10

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT B

>Steam Dump Pressure Setpoint Failure imf mss13b (2 0) 1500 100

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT C

>RCP Hi Vibration irf bbv001 (3 0) 6.1 30

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT D

>SGTR A Leak grows from 0 to 300 over 100 seconds AUTOMATICALLY inserted when >BBHIS37 taken to stop or PTL.

trgset 4 x21i115s imf rcs02a (4 120) 300 100

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT E

> A ASD fails open requiring manual isolation trgset 5 x04o9o imf mss07a (5 0)

>============================================================================

>========================EVENT PRELOAD=======================================

>EVENT F

>Instrument Air Fails closed requiring Alternate RCS Depressurization trgset 6 jstsisa.eq.1 ior kahis29_ic (6) on ior kahis29_io (6) off ior kahis29_og (6) on ior kahis29_or (6) off

>================================================================================

==================================================================

To FAST CLOSE A MSIV ONLY:

SAS013A set to OFF SAS013B set to OFF SAS013C set to OFF SAS017 set to ENABLE SAS018A set to FC

>end of file Scenario 3 Crew Turnover Separate Turnover sheets provided Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 1 Page 6 of 31 Event

Description:

Raise Power Time Position Applicants Actions or Behavior Refer to OTG-ZZ-0003, Plant Startup Hot Zero Power to 30%

SRO Power, section 6.3 Perform a Pre-Job Brief of power ascension:

  • General strategy for proceeding to 30% Power.
  • Any items not completed as expected to this point.
  • Applicable Precautions and Limitations
  • Activities that can be performed at any time during the next CREW sections(s) of this procedure such as Stroking MFRV's and Placing Reboiler in service.
  • Steam Dump strategy Discuss the use of Optional Parameter Alarms as an aid to avoid undesired challenges to legal or system requirements BOP Initiate a 3% per hour loading rate RO Commence raising reactor power When power is >10%, verify P-7 and P-10 permissives are RO illuminated When control of the plant is demonstrated during startup, proceed to the next event

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 7 of 31 Event

Description:

Power Range NI Failure Time Position Applicants Actions or Behavior Booth Instructor Instructions:

When directed, insert command for Power Range NI failure Indications Available:

PRNI N-44 failing HIGH Annunciators 78A, 78E, 82A for Power Range Channel deviation REACTOR PARTIAL TRIP Annunciator 83C BOP Refer to Annunciator Response procedures SRO Refer to OTO-SE-00001, Nuclear Instrument Malfunction Check Power Range Instruments normal.

RO

  • N-44 is failing high RO Ensure Rod Control is in MANUAL BOP Place SG Main Feed Reg Bypass valves in MANUAL BOP Control SG levels from 45 - 55%

BOP Stop any Main Turbine load changes (None in progress)

RO Maintain Tave/Tref within 1.5°F using manual rod control Check the following permissives are in their required state

  • P-7 CREW
  • P-8
  • P-9
  • P-10 CREW Select an operable channel on the NI Recorder

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 8 of 31 Event

Description:

Power Range NI Failure Time Position Applicants Actions or Behavior Bypass the malfunctioning channel at the Detector Current Comparator Drawer

  • Place UPPER SECTION switch to N-44 CREW
  • Place LOWER SECTION switch to N-44
  • Place ROD STOP BYPASS switch to N-44
  • Place POWER MISMATCH BYPASS switch to N-44 At the Comparator and Rate drawer, place Comparator CREW Channel Defeat switch to N-44 Ensure the following annunciator windows are extinguished:
  • 78A, PR CHANNEL DEV CREW
  • 78B, PR UPPER DETECTOR FLUX DEV
  • 78C, PR LOWER DETECTOR FLUX DEV
  • 82A, PR OVER PWR ROD STOP Check Rod Control in AUTO RO
  • Rod Control is in MANUAL Return Feed Reg Bypass valves to automatic operation as BOP required by the SRO BOP Control SG levels at 45 - 55%

Check Reactor Power >10% (NO)

CREW

  • Perform Attachment B, Low Power Trips Enabled, within the time limit specified in TS Refer to applicable Tech Specs SRO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 9 of 31 Event

Description:

Power Range NI Failure Time Position Applicants Actions or Behavior When Tech Specs have been identified, proceed to Event 3

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 3 Page 10 of 31 Event

Description:

Steam Dump Pressure Setpoint Failure Time Position Applicants Actions or Behavior Booth Instructor Instructions:

When directed, insert command for the Steam Dump pressure transmitter failure Indications Available:

Steam Dumps start to open Refers to OTO-AB-00004, Steam Header Pressure Channel SRO Failure Check Steam header pressure indicator AB PI-507 indicating BOP significantly different than SG pressure indicators Check Feed Pump Speed Changing due to failed channel

  • Must control feed pump speed using GE potentiometers BOP with speed controller in manual, due to PT-507 failure
  • Restore programmed DP BOP Check Steam Dump Control in Pressure Mode BOP Place Steam Header Pressure Controller in MANUAL BOP Check steam dumps responding in MANUAL BOP Manually control SG pressure to the desired value SRO Initiate actions to repair failed transmitter SRO Perform notifications per OPS-Communications-01 When steam pressure is under manual control, proceed to the next event

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 4 Page 11 of 31 Event

Description:

RCP High Vibration Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command to initiate RCP high vibration Indications Available:

RCP VIB DANGER Annunciator 70A RCP VIB/SYS ALERT Annunciator 70B NOTE:

In Modes 1 & 2 when a RCP is stopped, the idle loop RTD channel is INOPERABLE and the actions of OTO-BB-00004, RTD Channel Failures, should be performed.

SRO Refer to OTO-BB-00002, Reactor Coolant Pump Off-Normal RO Check RCP Vibrations

a. RCP Vibration level;
  • ALL RCPs Less than 5 MILS on the frame AND
  • ALL RCPs Less than 20 MILS on the shaft (at RP312, B YI-471) (See cue sheet posted behind back boards)

IF Reactor power LESS THAN 48%

(P-8 extinguished on SB069)

SECURE the affected RCP IAW OTN-BB-00003. (Will stop RO pump in a subsequent step)

RO Continue to MONITOR RCP parameters for all RCPs.

REFER to OTG-ZZ-00004, Power Operations, to shutdown the SRO plant.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 4 Page 12 of 31 Event

Description:

RCP High Vibration Time Position Applicants Actions or Behavior SRO Refer to T/S LCO 3.3.1, T/S LCO 3.3.2, and T/S LCO 3.4.4.

CREW Verify that permissive P8 is extinguished.

CAUTION: Consider the effects of securing the RCP WILL have on S/G level and Pzr Pressure control. The FRV in Auto should handle the transient but will later need to be closed and the FRV Bypass placed in service to prevent a high level Turbine Trip. If the D RCP is secured, Pzr Press control is accomplished by cycling heaters.

RO STOP the Reactor Coolant Pump.

In Modes 1, and 2, when a RCP is stopped, the idle loop RTD channel is INOPERABLE. PERFORM actions of OTO-BB-CREW 00004, RTD CHANNEL FAILURES, for the INOPERABLE RTD channel and refer to T/S LCO 3.3.1, T/S LCO 3.3.2, T/S LCO 3.4.4 and CARS 199601236.

GO TO OTG-ZZ-00005, Plant Shutdown 20% Power to Hot CREW Standby.

The next event is initiated on a trigger from RCP trip

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 13 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior Indications Available:

PRESSURIZER LOW LEVEL DEVIATION Annunciator 32C PRESSURIZER PRESSURE LOW HEATERS ON Annunciator 33C RO Determines PZR level dropping rapidly.

SRO Directs Reactor Trip and Safety Injection actuation.

RO CHECK Reactor Trip:

  • Rod Bottom Lights - ALL LIT
  • Neutron Flux - LOWERING BOP CHECK Turbine Trip:
a. All Turbine Stop valves - CLOSED CREW CHECK Power To AC Emergency Buses:

RO/BOP a. AC emergency buses - AT LEAST ONE ENERGIZED

  • NB02
b. AC emergency buses - BOTH ENERGIZED CHECK SI Status:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 14 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior RO a. CHECK if SI is actuated:

  • SB069 SI Actuate RED light - LIT OR
  • SB069 SI Actuate RED light - LIT SOLID (NOT blinking)

PERFORM Attachment A, Automatic Action Verification, while BOP continuing with this procedure.

BOP CHECK Generator Output Breakers - OPEN

  • MA ZL-3A (V55)
  • MA ZL-4A (V53)

BOP CHECK Feedwater Isolation:

BOP a. Main Feedwater Pumps - TRIPPED

  • AE ZL-510 (SG A)
  • AE ZL 520 (SG B)
  • AE ZL 530 (SG C)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 15 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior

  • AE ZL 540 (SG D)

BOP c. Main Feedwater Reg Bypass Valves - CLOSED

  • AE ZL-550 (SG A)
  • AE ZL 560 (SG B)
  • AE ZL 570 (SG C)
  • AE ZL 580 (SG D)

BOP d. Feedwater Isolation valves - CLOSED

  • AE HIS-39 (SG A)
  • AE HIS-40 (SG B)
  • AE HIS-41 (SG C)
  • AE HIS-42 (SG D)

BOP CHECK AFW Pumps:

a. MD AFW Pumps - BOTH RUNNING
  • AL HIS-23A
  • AL-HIS-22A
b. TD AFW Pumps - RUNNING IF NECESSARY BOP CHECK AFW Valves - PROPER EMERGENCY ALIGNMENT
  • MD AFP Flow Control Valves - THROTTLED
  • TD AFP Flow Control Valves - FULL OPEN

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 16 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior

  • AL HK-6A BOP CHECK Total AFW Flow - GREATER THAN 300,00 LBM/HR RO CHECK PZR PORVs and Spray Valves:
a. PZR PORVs - CLOSED
  • BB HIS-455A
  • BB-HIS-456A
b. PZR PORVs - BOTH IN AUTO
  • BB HIS-455A
  • BB-HIS-456A
c. PORV Block Valves - BOTH OPEN (NO)
  • BB HIS-8000A (Closed)
  • BB-HIS-8000A
d. Normal PZR Spray Valves - CLOSED
  • BB ZL-455A
  • BB-ZL-456A RO CHECK If RCPs Should Be Stopped:
a. RCPs - ANY RUNNING

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 17 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior

b. ECCS Pumps - AT LEAST ONE RUNNING
c. RCS pressure - LESS THAN 1425 PSIG RO CHECK RCS Temperatures:
  • Any RCP running - RCS TAVG STABLE AT 557°F OR TRENDING TO 557°F RO CHECK If Any SG Is Faulted:
a. CHECK pressures in all SGs:
  • ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER (NO)

OR

  • ANY SG COMPLETELY DEPRESSURIZED RO CHECK If SG Tubes Are Intact:
  • Levels in all SGs:
  • NO SG NARROW RANGE LEVEL RISING IN AN UNCONTROLLED MANNER
  • SG Steamline N16 radiation - NORMAL
  • N16 161 (SGA)
  • N16 162 (SGB)
  • N16 163 (SGC)
  • N16 164 (SGD)
  • Condenser Air Removal radiation - NORMAL BEFORE ISOLATION
  • GEG 925

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 18 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior

  • SG Blowdown and Sample radiation - NORMAL BEFORE ISOLATION
  • BML 256
  • SJL 026
  • SG ASD radiation - NORMAL
a. RCPs - ANY RUNNING
b. ECCS pumps - AT LEAST ONE RUNNING
c. RCS pressure - LESS THAN 1425 PSIG CREW IDENTIFY Ruptured SG(s):
  • Unexpected rise in any SG narrow range level (A SG)

OR

  • High radiation from any SG sample

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 19 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior OR

  • High radiation from any SG steamline OR
  • High radiation from any SG Blowdown line sample CRITICAL TASK BOP ISOLATE Flow From Ruptured SG(s):
a. ADJUST ruptured SG(s) ASD controller setpoint to 1160 PSIG:
b. CHECK ruptured SG(s) ADS - CLOSED

IF SG ASD is NOT closed, THEN PLACE SG ASD controller BOP in MANUAL and CLOSE SGT ASD.

c. Locally CLOSE TDAFP Steam Supply From Main Steam Loop Manual Isolation valve from ruptured SG(s):
  • ABV0085 (SG B)
  • ABV0087 (SG C)
d. CHECK SG Blowdown and Sample Isolation valves from ruptured SG(s) - CLOSED
  • Blowdown Containment Isolation Valve:
  • BM HIS-1A (SG A)
  • Upper Sample Inner Containment Isolation valve:
  • BM HIS-19 (SG A)
e. CLOSE Steamline Low Point Drain valve from ruptured

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 20 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior SG(s):

f. CHECK if C-9 interlocks - LIT Cue:

When Logic Channel Toggle Switches are placed in OFF during the next step, the associated FAIL light comes ON (Back Board Mockup)

g. CLOSE MSIV and MSIV Bypass valve from ruptured SG(s):
  • CLOSE ruptured SG(s) MSIV (preferred order):
  • FAST CLOSE using EOP Addendum 35, MSIV Fast Closure, at MSFIS cabinets SA075A and SA075B OR
  • CLOSE all MSIV Bypass valves (preferred order):
  • USE Main Steamline Isolation Bypass Valves Controller AB HIK-15 OR
  • Locally ISOLATE MSIV Bypass valve(s) as necessary CREW CHECK Ruptured SG(s) Level:
a. Narrow range level - GREATER THAN 7% [25%]

Stop Feed flow to the ruptured SG

  • Close MDAFP flow control valve AL-HK-7A
  • Close TDAFP flow control valve AL-HK-8A

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 21 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior CHECK Ruptured SG(s) Pressure - GREATER THAN 340 BOP PSIG BOP INITIATE RCS Cooldown:

a. CHECK RCS pressure - LESS THAN 1970 PSIG
  • P-11 light - LIT
b. BLOCK Steamline Pressure SI:
  • SB-HS-10 CRITICAL TASK CREW c. DETERMINE required core exit temperature: (variable)
d. DUMP steam to condenser from intact SG(s) at maximum BOP rate:
1. CHECK condenser - AVAILABLE
  • C-9 interlocks - LIT
2. PLACE Steam Header Pressure Controller in MANUAL and ZERO OUTPUT:
3. PLACE Steam Dump Select switch in STM PRESS position:
  • AB US-500Z
4. ADJUST Steam Header Pressure Controller in STM PRESS mode to achieve maximum cooldown rate:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 22 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior

e. Core exit TCs - LESS THAN REQUIRED RO TEMPERATURE BOP f. STOP RCS cooldown
g. MAINTAIN core exit TCs - LESS THAN REQUIRED BOP TEMPERATURE BOP CHECK Intact SG Levels:
a. Narrow range levels - GREATER THAN 7% [25%]
b. CONTROL feed flow to maintain narrow range levels between 27% and 50%

RO CHECK PZR PORVs And Block Valves:

a. Power to Block Valves - AVAILABLE
  • BB HIS 8000A
  • BB HIS 8000B
b. PZR PORVs - CLOSED
  • BB HIS 455A
  • BB HIS 456B
c. Block Valves - AT LEAST ONE OPEN
  • BB HIS 8000A
  • BB HIS 8000B

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 23 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior RO RESET SI:

  • SB HS-43A RO RESET Containment Isolation Phase A and Phase B
  • Phase A (CISA):
  • Phase B (CISB):
  • SB HS-55 RO ESTABLISH Instrument Air To Containment:
a. CHECK if ESW To Air Compressor valves - OPEN
  • EF HIS-43
  • EF HIS-44
b. START Air Compressor(s):
c. OPEN Instrument Air Supply Containment Isolation valve:
  • KA HIS-29 (will not open)

PERFORM the following:

IF valve CANNOT be opened, THEN locally OPEN valve.

(2000 Aux South piping pen room, P-30) (Will NOT open)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 24 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior RO CHECK If RHR Pumps Should Be Stopped:

a. RHR Pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST
b. RCS pressure - GREATER THAN 325 PSIG
c. STOP RHR Pumps and PLACE in standby:
  • EJ HIS-1
  • EJ HIS-2
d. MONITOR RCS pressure BOP CHECK If RCS Cooldown Should Be Stopped:
a. Core exit TCs - LESS THAN REQUIRED TEMPERATURE
b. STOP RCS cooldown
c. MAINTAIN core exit TCs - LESS THAN REQUIRED CREW TEMPERATURE BOP CHECK Ruptured SG(s) Pressure - STABLE OR RISING RO CHECK RCS Subcooling - GREATER THAN 50°F DEPRESSURIZE RCS To minimize Break Flow And Refill PZR:
a. Normal PZR spray - AVAILABLE (NO)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 25 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior DEPRESSURIZE RCS Using PZR PORV To Minimize Break RO Flow And Refill PZR:

a. PZR PORV - AT LEAST ONE AVAILABLE
  • BB HIS-455A OR
  • BB HIS-456A
b. OPEN one PZR PORV until any of the following conditions satisfied:
  • Both of the following:
1. RCS pressure - LESS THAN RUPTURED SG(s)

PRESSURE

2. PZR level - GREATER THAN 9% [29%]

OR

  • PZR level - GREATER THAN 74% [64%]

OR

  • RCS subcooling LESS THAN 30°F
c. CLOSE PZR PORV:
  • BB HIS-455A
  • BB HIS-456A RO CHECK RCS Pressure - RISING CREW CHECK If ECCS Flow Should Be Terminated:
a. RCS subcooling - GREATER THAN 30°f
b. Secondary heat sink:

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6, 7 Page 26 of 31 Event

Description:

SGTR; Reactor Trip Required, ADV Fails Open, IA to CTMT Fails Closed Time Position Applicants Actions or Behavior

  • Narrow range level in at least one intact SG -

GREATER THAN 7% [25%]

OR

  • Total feed flow to SG(s) - GREATER THAN 300,000 LBM/HR
c. RCS pressure - STABLE OR RISING
d. PZR level - GREATER THAN 9% [29%]

RO STOP ECCS Pumps And Place In Standby:

a. Both SI Pumps:
b. All but one CCP:
  • BG HIS-1A OR
  • BG HIS-2A Scenario may be terminated when ECCS pumps are stopped, or at Lead Examiners discretion when all critical tasks have been met.

ATTACHMENT A Automatic Action Verification BOP CHECK Charging Pumps:

BOP a. CCPs - BOTH RUNNING

  • BG HIS-1A
  • BG HIS-2A BOP b. STOP NCP:
  • SI Pumps - BOTH RUNNING
  • RHR Pumps - BOTH RUNNING
  • EJ HIS-1

BOP a. CCPs to Boron Inj Header - FLOW INDICATED

  • EM FI-917A
  • EM FI-917B BOP b. RCS pressure - LESS THAN 1700 PSIG BOP c. SI Pump Discharge - FLOW INDICATED

ATTACHMENT A Automatic Action Verification

  • EJ FI-618
  • EJ FI-619 CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

BOP CHECK ESW Pumps - BOTH RUNNING

  • EF HIS-55A
  • EF HIS-56A BOP CHECK CCW Alignment:

BOP a. CCW Pumps - ONE RUNNING IN EACH TRAIN

  • Red Train:
  • EG HIS-21 or EG HIS-23
  • Yellow Train
  • EG HIS-22 or EG HIS-24
b. CCW Service Loop Supply and Return valves for one BOP operating CCW pump - OPEN
  • EG ZL-15 AND EG ZL-53 OR
  • EG ZL-16 AND EG ZL-54 CHECK Containment Cooler Fans - RUNNING IN SLOW BOP SPEED
  • GN HIS-9
  • GN HIS-17
  • GN HIS-5
  • GN HIS-13 CHECK Containment Hydrogen Mixing Fans - RUNNING IN BOP SLOW SPEED
  • GN HIS-2

ATTACHMENT A Automatic Action Verification

  • GN HIS-4
  • GN HIS-1

BOP a. CHECK the following:

  • Containment pressure - GREATER THAN 27 PSIG OR
  • GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR
  • EN HIS-3
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP d. ESFAS status panels CISB sections:
  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK If Main Steamlines Should Be Isolated:

BOP a. CHECK for any of the following:

  • Containment pressure - GREATER THAN 17 PSIG OR

ATTACHMENT A Automatic Action Verification

  • GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 17 PSIG OR
  • Steamline pressure - LESS THAN 615 PSIG OR
  • AB PR-514 or PR-535 indicates steamline pressure -

HAS BEEN LESS THAN 615 PSIG BOP b. CHECK MSIVs and Bypass valves - CLOSED BOP CHECK ECCS Valves - PROPER EMERGENCY ALIGNMENT BOP a. ESFAS status panels SIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK Containment Isolation Phase A:

BOP a. ESFAS status panels CISA sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK SG Blowdown Isolation:

BOP ESFAS status panels SGBSIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

BOP CHECK Both Trains of control Room Ventilation Isolation:

BOP a. ESFAS status panels CRVIS sections:

ATTACHMENT A Automatic Action Verification

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP CHECK Containment Purge Isolation:

BOP a. ESFAS status panels CPIS sections:

  • SA066X WHITE lights - ALL LIT
  • SA066Y WHITE lights - ALL LIT BOP Notify CRS of the following:
  • Manual actions taken
  • Failed Equipment
  • Attachment A, Automatic Action Verification, completed

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Determine the volume and RMCS JPM No.: 2005 NRC RO/SRO controls settings for raising RWST A1-2 level.

K/A

Reference:

2.1.25 (2.8)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: This JPM can be performed in any setting with the required references available.

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

  • The unit is coming out of a refueling outage.
  • A significant leak occurred during the refuel pool draindown process.
  • BAST concentration is 7000 ppm Task Standard: Volume addition and controls settings within the specified range.

Required Materials:

  • Straight Edge
  • Calculator General

References:

OTN-BG-00002, REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM, Rev. 020 Handouts:

  • OTN-BG-0002
  • RWST Level/Volume Curve Initiating Cue: You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM Time Critical Task: No Validation Time: 10 Minutes NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a )

Evaluator Note: There is no required sequence of steps. The candidate may first refer to OTN-BG-00002.

Performance Step: 1 Determine the volume to be added.

Standard: Refers to RWST Level/Volume Curve and determines 23,500 gallons but 25,500 must be added.

Comment:

Evaluator Cue: Provide a copy of the RWST Level/Volume Curve if the book is not available where the JPM is performed or the existing document cannot be marked.

Performance Step: 2 Locate/review the applicable procedure.

Standard: Locates OTN-BG-00002 and determines that Section 5.5 -

MANUAL MODE OF RMCS OPERATION applies.

Comment:

Evaluator Cue: Provide OTN-BG-00002, Section 5.5.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Procedure NOTES

  • If the makeup water is to be blended for use somewhere preceding the step: other than the Chemical and Volume Control System, ensure that the VCT level is sufficient for expected plant operating conditions.
  • If makeup is required to the Spent Fuel Pool refer to OTN-EC-00001 Performance Step: 3 Determine the desired boric acid and makeup water flow rates, for blended flow using Figure 7-2.

Standard: Refers to Figure 7-2 and determines by interpolation:

  • Makeup Water flow = 59.46 GPM Evaluator Cue: Assume that adequate supply capacity is available to perform the evolution.

Performance Step: 4 Determines RMCS settings based upon required blended flow rates Standard: Refers to Figure 7-2 and determines:

Evaluator Cue: Assume that adequate supply capacity is available to perform the evolution.

Terminating Cue: After the controls settings are determined, this JPM is complete.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO/SRO A1-2 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

  • The unit is coming out of a refueling outage.
  • A significant leak occurred during the refuel pool draindown process.
  • BAST concentration is 7000 ppm INITIATING CUE: You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM.

NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Determine the volume and RMCS JPM No.: 2005 NRC RO/SRO controls settings for raising RWST A1-2 level.

K/A

Reference:

2.1.25 (2.8)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: This JPM can be performed in any setting with the required references available.

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

  • The unit is coming out of a refueling outage.
  • A significant leak occurred during the refuel pool draindown process.
  • BAST concentration is 7000 ppm Task Standard: Volume addition and controls settings within the specified range.

Required Materials:

  • Straight Edge
  • Calculator General

References:

OTN-BG-00002, REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM, Rev. 020 Handouts:

  • OTN-BG-0002
  • RWST Level/Volume Curve Initiating Cue: You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM Time Critical Task: No Validation Time: 10 Minutes NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a )

Evaluator Note: There is no required sequence of steps. The candidate may first refer to OTN-BG-00002.

Performance Step: 1 Determine the volume to be added.

Standard: Refers to RWST Level/Volume Curve and determines 23,500 gallons but 25,500 must be added.

Comment:

Evaluator Cue: Provide a copy of the RWST Level/Volume Curve if the book is not available where the JPM is performed or the existing document cannot be marked.

Performance Step: 2 Locate/review the applicable procedure.

Standard: Locates OTN-BG-00002 and determines that Section 5.5 -

MANUAL MODE OF RMCS OPERATION applies.

Comment:

Evaluator Cue: Provide OTN-BG-00002, Section 5.5.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Procedure NOTES

  • If the makeup water is to be blended for use somewhere preceding the step: other than the Chemical and Volume Control System, ensure that the VCT level is sufficient for expected plant operating conditions.
  • If makeup is required to the Spent Fuel Pool refer to OTN-EC-00001 Performance Step: 3 Determine the desired boric acid and makeup water flow rates, for blended flow using Figure 7-2.

Standard: Refers to Figure 7-2 and determines by interpolation:

  • Makeup Water flow = 59.46 GPM Evaluator Cue: Assume that adequate supply capacity is available to perform the evolution.

Performance Step: 4 Determines RMCS settings based upon required blended flow rates Standard: Refers to Figure 7-2 and determines:

Evaluator Cue: Assume that adequate supply capacity is available to perform the evolution.

Terminating Cue: After the controls settings are determined, this JPM is complete.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO/SRO A1-2 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

  • The unit is coming out of a refueling outage.
  • A significant leak occurred during the refuel pool draindown process.
  • BAST concentration is 7000 ppm INITIATING CUE: You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at its current value with a makeup flow rate of 90 GPM.

NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Plant Task No.:

Task

Title:

Determine isolation points for a JPM No.: 2005 NRC RO A2 tagging request K/A

Reference:

2.2.13 (3.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.

A job has been initiated to drain the associated piping and repair the flow element Task Standard: Tagging boundaries are identified to provide minimum isolation of EN FE-5 Required Materials: ODP-ZZ-00310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 General

References:

ODP-ZZ-0310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 Initiating Cue: You have been directed to identify the tagging boundaries to allow work to be performed on flow element EN FE-5.

Time Critical Task: NO Validation Time: 15 Minutes Callaway 2005 NRC RO A2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP None Required Callaway 2005 NRC RO A2 NUREG 1021, Revision 9

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtains required drawings Standard: Locates print rack and identifies required drawings Evaluator Note: Isolation points may be identified in any order Comment:

Performance Step: 2 EN HV-1, Containment Recirc Sump Supply valve will be closed Standard: Locates and marks EN HV-1 closed Comment:

Performance Step: 3 EN HV-6, Containment Spray A discharge to Containment will be closed Standard: Locates and marks EN HV-6 closed Comment:

Performance Step: 4 EN V-24, Recirculation valve to RWST, will be closed Standard: Locates and marks EN V-24 closed Comment:

Callaway 2005 NRC RO A2 NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 BN HV-4, RWST suction supply to Containment Spray Pump A, will be closed Standard: Locates and marks BN HV-4 closed Comment:

Performance Step: 6 EITHER ONE of EN V-90, EN V-92 or EN V-67, Containment Spray line drain or vent valves, will be open Standard: Locates and marks any of EN V-90, EN V-92, or EN V-67 open Comment: More than 1 valve is acceptable Performance Step: 7 Pump breaker may be opened and electrically isolated Standard: Identifies isolation of Containment Spray Pump A electrical circuit breaker Comment: May also tag breakers for MOVs, but not required Terminating Cue: When the applicant has determined the isolation boundaries for the work to be performed.

STOP TIME:

Callaway 2005 NRC RO A2 NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO A2 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Callaway 2005 NRC RO A2 NUREG 1021, Revision 9

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.

A job has been initiated to drain the associated piping and repair the flow element INITIATING CUE: You have been directed to identify the tagging boundaries to allow work to be performed.

Callaway 2005 NRC RO A2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Plant Task No.:

Task

Title:

Review a tagging request for JPM No.: 2005 NRC SRO A2 approval K/A

Reference:

2.2.13 (3.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.

A job has been initiated to drain the associated piping and repair the flow element Task Standard: Tagging boundaries are identified to provide minimum isolation of EN FE-5. WPA not approved due to 2 deficiencies Required Materials: ODP-ZZ-00310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 General

References:

ODP-ZZ-0310, Workmens Protection Assurance M-22BN01, M-22EN01, E-23EN01 Initiating Cue: You have been directed to review the WPA for approval to allow work to be performed on flow element EN FE-5.

Time Critical Task: NO Validation Time: 15 minutes Callaway 2005 NRC SRO A2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP None Required Callaway 2005 NRC SRO A2 NUREG 1021, Revision 9

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtains required drawings Standard: Locates print rack and identifies required drawings Evaluator Note: Isolation points may be identified in any order Comment:

Performance Step: 2 Reviews WPA to determine appropriate isolation points for Containment Spray Pump A flow element FE-5 Standard: Reviews tag listing Comment:

Performance Step: 3 Determines that BN HV-4, RWST suction supply to Containment Spray Pump A must be closed and tagged Standard: Identifies deficiency on tagging request. Local handwheel must be tagged as part of valve isolation Comment:

Performance Step: 4 Determines that Containment Spray Pump A breaker must be tagged Standard: Identifies that the Containment Spray Pump A breaker is not tagged and requires tagging Comment:

Callaway 2005 NRC SRO A2 NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Return the WPA without approval Standard: Determines that WPA cannot be approved Comment:

Terminating Cue: When the applicant has provided disposition of the WPA, this JPM is complete STOP TIME:

Callaway 2005 NRC SRO A2 NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO A2 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Callaway 2005 NRC SRO A2 NUREG 1021, Revision 9

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Containment Spray Pump A flow element EN FE-5 is leaking on the high side tap.

A job has been initiated to drain the associated piping and repair the flow element INITIATING CUE: You have been directed to review the WPA for approval to allow work to be performed on flow element EN FE-5.

Callaway 2005 NRC SRO A2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Plant Task No.: N/A Task

Title:

Determine Maximum Allowable Stay JPM No.: 2005 NRC RO A3 Time K/A

Reference:

2.3.2 (2.5)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A job is being performed on RHR Pump A that requires isolating and draining system piping.

You have been directed to open RHR Pump A drain valve EJ V-148 and route a hose to the local floor drain Task Standard: Correct RWP is selected and stay time identified as 30 minutes based upon exceeding maximum dose Required Materials: RWPs, Survey Maps General

References:

RWPs, Survey Maps Initiating Cue: Identify the appropriate RWP for entry and determine maximum allowable stay time before a dosimeter limit is exceeded.

Time Critical Task: NO Validation Time: 8 Minutes Callaway 2005 NRC RO/SRO A3 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP None Required Callaway 2005 NRC RO/SRO A3 NUREG 1021, Revision 9

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Determine RWP required for task performed Standard: Selects RWP 500501WPA Comment:

Performance Step: 2 Determines stay time based upon dosimeter setting Standard: Determines dosimeter setting is 10 mr total dose and 100 mr/hr dose rate.

Standard: Selects survey map #1111, RHR Pump A room Standard: Determines dose rate in the area of the work is 20 mr/hr Standard: Determines maximum stay time at 20 mr/hr is 30 minutes to avoid exceeding 10 mr total dose.

Comment:

Terminating Cue: When the candidate indicates stay time for the work performed, this JPM is complete STOP TIME:

Callaway 2005 NRC RO/SRO A3 NUREG 1021, Revision 9

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC RO A3 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Callaway 2005 NRC RO/SRO A3 NUREG 1021, Revision 9

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A job is being performed on RHR Pump A that requires isolating and draining system piping.

You have been directed to open RHR Pump A drain valve EJ V-148 and route a hose to the local floor drain INITIATING CUE: Identify the appropriate RWP for entry and determine maximum allowable stay time before a dosimeter limit is exceeded.

Callaway 2005 NRC RO/SRO A3 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Evaluate plant conditions, upgrade JPM No.: 2005 NRC SRO A4 the emergency classification and make a PAR.

K/A

Reference:

2.4.44 (4.0)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

  • A large break LOCA is in progress.
  • A Site Emergency was declared 20 minutes ago based on loss of the RCS subcooling and radiation monitor GT-RE-59 reading 3.1E+3 R/hr.
  • One minute ago containment pressure lowered rapidly and now continues to lower at a slower rate.
  • Wind speed is 5 Miles/Hr.
  • Wind direction is from 218°
  • The outside temperature is 88 F.

Task Standard: Upgrades classification and makes a PAR.

Required Materials: SENTRY Computer General

References:

  • EIP-ZZ-00101, CLASSIFICATION OF EMERGENCIES, Rev.

032

  • EIP-ZZ-00102, EMERGENCY IMPLEMENTING ACTIONS, Rev.

034

  • EIP-ZZ-00212, PROTECTIVE ACTION RECOMMENDATIONS, Rev. 021 Handouts: EIP-ZZ-00101, EIP-ZZ-00102, EIP-ZZ-00212 Initiating Cue: Reevaluate the Emergency Classification and perform required follow up actions required of the Emergency Coordinator.

Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: Yes Validation Time: 24 Minutes Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A JPM Setup:

Ensure SENTRY Screen is called up on computer with plant WIND SECTOR data deleted, then minimize screen prior to JPM performance Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a )

Performance Step: 1 Review changing conditions.

Standard:

  • Enters EIP-ZZ-00101
  • Reviews Group 2 (Fission Product Barrier) EALs
  • Declares General Emergency based on uncontrolled depressurization of containment.

Comment:

Performance Step: 2 Enters EIP-ZZ-00102 Standard: Announces GE and reason to control room personnel.

Comment: The candidate may work through the next several steps using EIP-ZZ-00102, ATTACHMENT 5 (flowcharted procedure steps).

Mark the time of the GE announcement: __________.

ATTACHMENT 4, OFF SITE NOTIFICATION FORM, must be provided to the communicator within 15 minutes from this time.

Performance Step: 3 Manually initiate ERFIS.

Standard: Locates ERFIS button.

Comment:

Evaluator Cue: ERFIS was actuated when the Site Emergency was declared.

Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Notify On-site personnel Standard:

  • Completes ATTACHMENT 1
  • Sounds plant emergency alarm.
  • Makes the scripted announcement and repeats.

Comment:

Evaluator Cue: For the purpose of examination security, direct the candidate to simulate the alarm actuation and announcement.

Performance Step: 5 Have SAS activate the callout.

Standard: Acknowledges cue.

Comment:

Evaluator Cue: SAS was activated when the Site Emergency was declared.

Performance Step: 6 Complete the SENTRY screen or fill out ATTACHMENT 4.

Standard: Completes the SENTRY screen. Critical task data:

  • Release in progress
  • Wind speed and direction
  • PAR - Evacuate 2 miles all around and 5 miles in downwind sectors B, C, and D Comment:

Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Provide ATTACHMENT 4 to the communicator.

Standard: Provides ATTACHMENT 4 to the communicator within 15 minutes after the GE declaration.

Comment: Mark the time that ATTACHMENT 4 is provided to the communicator: __________.

Terminating Cue: After ATTACHMENT 4 is provided to the communicator, this JPM is complete.

Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC SRO A4 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

  • A large break LOCA is in progress.
  • A Site Emergency was declared 20 minutes ago based on loss of the RCS subcooling and radiation monitor GT-RE-59 reading 3.1E+3 R/hr.
  • One minute ago containment pressure lowered rapidly and now continues to lower at a slower rate.
  • Wind speed is 5 Miles/Hr
  • Wind direction is from 218°
  • The outside temperature is 88 F.

INITIATING CUE: Reevaluate the Emergency Classification and perform required follow up actions required of the Emergency Coordinator.

Callaway SRO NRC JPM A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Borate RCS During Cooldown JPM No.: 2005 NRC JPM P1 Outside the Control Room K/A

Reference:

068 EA 1.11 3.9 / 4.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The control room is damaged beyond use and systems are aligned as per OTO-ZZ-00001, Control Room Inaccessibility. The plant is shutdown with control from the Aux S/D Panel due to a fire. The plant is in Mode 3 at normal operating temperature and pressure. Pressurizer level is 25%, RCS boron concentration is 1000 ppm, and all shutdown and control rods are fully inserted. Core burnup is 295 EFPD. The B CCP is in service.

Task Standard: RCS boration from outside the control room has been completed Required Materials: OTS-ZZ-00001, Cooldown From Outside the Control Room, Revision 13 Curve Book Table 1-8 Figure 7-3 General

References:

OTS-ZZ-00001, Cooldown From Outside the Control Room, Revision 13 Initiating Cue: You have been directed by the Shift Supervisor to perform Section 4.1 of OTS-ZZ-00001 to borate the RCS from the Boric Acid Tanks.

Time Critical Task: NO Validation Time: 39 minutes 2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a controlled copy of OTS-ZZ-00001, Cooldown From Outside the Control Room.

Standard: Operator should obtain procedure copy.

Comment:

Step 2.0 Performance Step: 2 Review the Precautions and Limitations of OTS-ZZ-00001.

Standard: Operator should review all precautions and limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Performance Step: 3 Review the Initial Conditions of OTS-ZZ-00001.

Standard: Operator should review all Initial Conditions.

Comment:

Evaluators Cue: All Initial Conditions are satisfied.

Ask if the Operator understands the Initial Conditions and Initiating Cues.

Step 4.1 Performance Step: 4 Borate the RCS to Xenon-Free Cold Shutdown as follows.

Standard: Operator should determine to borate the RCS to Cold Xenon-Free Shutdown.

Comment:

2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.1 Performance Step: 5 Determine the required boron concentration for cold shutdown using Curve Book Table 1-8.

Standard: Operator should determine required boron concentration is approximately 1100 - 1200 ppm.

Comment:

Step 4.1.1.1 Performance Step: 6 Determine the number of gallons of 4 WT % boric acid from the BAT required to achieve the boron concentration in Step 4.1.1 using Figure 7-3 of the Curve Book.

Standard: Operator should calculate 1567 +/- 200 GAL.

If nomograph is used, then 1350 - 1400 gallons will be the volume indicated 515676 7000-1000 VB In ( )

8.33 7000-1150 Comment: Nomograph indicates approximately 1350 -1400 gallons Cue: If requested, Boric Acid Tank concentration is 7000 ppm Step 4.1.2.1 Performance Step: 7 Start a Boric Acid Transfer Pump A or B with local control switch or with the pushbutton on the associated breaker pump A(B) NG01AHF4 (NG02AAF4).

Standard: Operator should start A or B Boric Acid Pump.

Evaluators Cue: Direct the candidate to use the local HIS for the Boric Acid Pump Comment:

Evaluators Cue: The Boric Acid Transfer Pump is running.

2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.2.2 Performance Step: 8 Open the Immediate Boration valve BGHV8104.

Standard: Operator goes to A SI Pump Room and manually OPENS BG-HV-8104.

Comment:

Evaluators Cue: BGHV8104 is OPEN.

Step 4.1.2.3 Performance Step: 9 Monitor boric acid flow on Local Indicator BGFI183B.

Standard: Operator should monitor boric acid flow on BGFI183B.

Comment: BGFI183B is outside the room Evaluators Cue: Local Indicator shows 100 GPM.

Step 4.1.4 Performance Step: 10 Determine the boration time required by dividing the gallons of acid by the flow rate indicated.

Standard: 1567 GAL

= 16 MIN (+/- 3 MIN) 100 GPM Comment:

Evaluators Cue: The required time has elapsed.

Step 4.1.5.1 Performance Step: 11 When the required time has elapsed, stop the Boric Acid Transfer Pump.

Standard: Operator should secure A or B Boric Acid Pump with the local control switch or the pushbutton on the breaker A - NG01AHF4 B - NG02AAF4 Comment:

Evaluators Cue: The Boric Acid Transfer Pump is STOPPED.

2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.5.2 Performance Step: 12 CLOSE BGHV8104.

Standard: Operator should CLOSE BGHV8104.

Comment:

Evaluators Cue: BGHV8104 is CLOSED.

Step 4.1.7 Performance Step: 13 Have the RCS sampled to ensure the required SDM has been obtained.

Standard: Operator should call for Chemistry to sample RCS for boron.

Comment:

Evaluators Cue: When called, Hot Lab Chem Tech will sample RCS for boron.

Terminating Cue: When boration of the RCS has been performed, this JPM is complete.

STOP TIME:

2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM P1 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The control room is damaged beyond use and systems are aligned as per OTO-ZZ-00001, Control Room Inaccessibility. The plant is shutdown with control from the Aux S/D Panel due to a fire. The plant is in Mode 3 at normal operating temperature and pressure. Pressurizer level is 25%, RCS boron concentration is 1000 ppm, and all shutdown and control rods are fully inserted.

Core burnup is 295 EFPD. The B CCP is in service.

INITIATING CUE: You have been directed by the Shift Supervisor to perform Section 4.1 of OTS-ZZ-00001 to borate the RCS from the Boric Acid Tanks.

2005 NRC JPM P1 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Locally Close Valves for CIS-B JPM No.: 2005 NRC JPM P2 K/A

Reference:

103 A2.03 3.5 / 3.8 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant was at 100% power when a Loss of All AC Power occurred. The Control Room entered emergency procedure ECA-0.0, Loss of All AC Power. A containment spray signal has been received and required valve positions can not be performed from the Control Room.

Task Standard: Upon completion of this JPM, valves associated with Penetrations 74, 75, and 76 will be closed or verified closed.

Required Materials: None General

References:

ECA-0.0, Loss of All AC Power, Revision 5 Initiating Cue: The Control Room supervisor has directed you to perform Local Operator Actions of Step 21B RNO (CISB Outer Containment Valves),

of ECA-0.0. Reposition any required valves and inform him when done.

Time Critical Task: NO Validation Time: 10 minutes 2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 2 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator Note: All valves will be in the normal positions as stated in the JPM Performance Step: 1 Obtain a verified working copy of ECA-0.0, Loss of All AC Power.

Standard: Operator should obtain ECA-0.0 copy.

Comment:

Evaluators Cue: Provide operator with copy of ECA-0.0.

Performance Step: 2 Go to the Aux Building North Piping Penetration Room #1323.

Standard: Operator should go to the North Piping Penetration Room #1323.

NOTE: Operator should go thru HP Access.

Comment:

Performance Step: 3 Verify CLOSED EG-HV-58, CCW to RCS outer CTMT ISO.

Standard: Operator should demonstrate knowledge of how to verify a motor-operated valve OPEN/CLOSED.

NOTE: Pen 74, valves in Steps 3 through 8 can be operated in any order.

Comment:

Evaluator Cue: EG-HV-58 is open 2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 CLOSE EG-HV-58, CCW to RCS Outer CTMT ISO.

Standard: Operator should CLOSE EG-HV-58.

NOTE: Operator should be able to describe how to CLOSE a limitorque valve.

Standard: Valves in Steps 3 through 8 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-58 is now CLOSED.

Performance Step: 5 Verify CLOSED EG-HV-71, CCW to RCS Outer CTMT ISO.

Standard: Operator should verify position of EG-HV-71.

NOTE: Pen 74 Standard: Valves in Steps 3 through 8 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-71 is OPEN.

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Operator should CLOSE EG-HV-71, CCW to RCS Outer CTMT ISO.

Standard: Operator should CLOSE EG-HV-71.

NOTE: Pen 74 Standard: Valves in Steps 3 through 8 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-71 is now CLOSED.

Performance Step: 7 Verify CLOSED EG-HV-126, CCW to RCS CTMT Bypass.

Standard: Operator should verify CLOSED EG-HV-126, CCW to RCS CTMT Bypass.

NOTE: Pen 74 Standard: Valves in Steps 3 through 8 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-126 is CLOSED.

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8 Verify CLOSED EG-HV-127, CCW to RCS CTMT Bypass.

Standard: Operator should verify CLOSED EG-HV-127, CCW to RCS CTMT Bypass.

NOTE: Pen 74 Standard: Valves in Steps 3 through 8 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-127 is CLOSED.

Performance Step: 9 Verify CLOSED EG-HV-59, CCW from RCS Outer CTMT ISO.

Standard: Operator should verify position of EG-HV-59.

NOTE: Pen 75 Standard: Valves in Steps 9 through 11 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-59 is OPEN.

Performance Step: 10 CLOSE EG-HV-59, CCW from Outer CTMT ISO.

Standard: Operator should CLOSE EG-HV-59.

NOTE: Pen 75 Standard: Valves in Steps 9 through 11 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-59 is now CLOSED.

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 11 Verify CLOSED EG-HV-131, CCW from RCS CTMT Bypass.

Standard: Operator should verify CLOSED EG-HV-131.

NOTE: Pen 75 Standard: Valves in Steps 9 through 11 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-131 is CLOSED.

Performance Step: 12 Verify CLOSED EG-HV-61, CCW from RCS Outer CTMT ISO.

Standard: Operator should verify position of EG-HV-61.

NOTE: Pen 76 Standard: Valves in Steps 12 through 14 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-61 is OPEN.

Performance Step: 13 CLOSE EG-HV-61, CCW from RCS Outer CTMT ISO.

Standard: Operator should CLOSE EG-HV-61, CCW from RCS Outer CTMT ISO.

NOTE: Pen 76 Standard: Valves in Steps 12 through 14 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-61 is now CLOSED.

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 14 Verify CLOSED EG-HV-133, CCW from RCS CTMT BYPASS.

Standard: Operator should verify CLOSED EG-HV-133.

NOTE: Pen 76 Standard: Valves in Steps 12 through 14 can be operated in any order.

Comment:

Evaluators Cue: EG-HV-133 is CLOSED.

Performance Step: 15 Standard: Operator should inform Control Room Supervisor Local Operator Action is completed to Isolated CIS-B Valves.

Comment:

Evaluators Cue: Control Room Supervisor acknowledges.

Terminating Cue: When all CIS-B valves are closed, the JPM is complete STOP TIME:

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM P2 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant was at 100% power when a Loss of All AC Power occurred. The Control Room entered emergency procedure ECA-0.0, Loss of All AC Power. A containment spray signal has been received and required valve positions can not be performed from the Control Room.

INITIATING CUE: The Control Room supervisor has directed you to perform Local Operator Actions of Step 21B RNO (CISB Outer Containment Valves), of ECA-0.0. Reposition any required valves and inform him when done.

2005 NRC JPM P2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Perform Fire Water System Makeup JPM No.: 2005 NRC JPM P3 to CST K/A

Reference:

061 K4.01 3.9 / 4.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant has lost all AC power due to an earthquake. Plant operators are currently in emergency procedure ECA-0.0, Loss of All AC Power, stabilizing the plant.

Task Standard: Upon completion of this JPM, the operator will have commenced filling the CST from the Firewater System.

Required Materials: Key #131, Locked Valve and Breaker Key General

References:

EOP Addendum 23, Local CST Emergency Fill Initiating Cue: The Control Room Supervisor has directed you to fill the condensate storage tank using Addendum 23, Local CST Emergency Fill. Inform the Control Room Supervisor when you have started filling the CST.

Time Critical Task: NO Validation Time: 10 minutes 2005 NRC JPM P3 NUREG 1021, Revision 9

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a copy of Addendum 23, Local CST Emergency Fill.

Standard: Operator should obtain procedure copy.

Comment:

Performance Step: 2 Review Addendum.

Standard: Operator may review Addendum.

Comment:

Step 1.0 Performance Step: 3 Obtain hydrant wrench, 1 50 ft. section of 2 1/2 fire hose, 1 spanner wrench, 1 fire water to CST emergency fill connector.

Standard: Operator should Obtain hydrant wrench, 1 50 ft. section of 2 1/2 fire hose, 1 spanner wrench, 1 Fire Water to CST Emergency Fill Connector.

Comment:

Step 2.A Performance Step: 4 Connect the CST Emergency Fill Connector to the Ecolo Chem Connection on APV0043.

Standard: Operator should hook up CST Emergency Fill Connector to the Ecolo Chem Connection on APV0043 located plant south side of CST.

Comment:

Evaluators Cue: CST Emergency Fill Connector is hooked up to APV0043 2005 NRC JPM P3 NUREG 1021, Revision 9

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION Step 2.B Performance Step: 5 Connect 2 1/2 fire hose to the CST Emergency Fill Connector at APV0043.

Standard: Operator should connect the 2 1/2 fire hose to the CST Emergency Fill Connector.

Comment:

Evaluators Cue: 2 1/2 fire hose is hooked up to the CST Emergency Fill Connector.

Step 2.C Performance Step: 6 Hook up the 2 1/2 hose to the fire hydrant.

Standard: Operator should hook up the 2 1/2 hose to the fire hydrant.

Comment:

Evaluators Cue: 2 1/2 hose is hooked up to the fire hydrant.

Step 3.B Performance Step: 7 Open APV0043, CST Deoxygenated Water Outlet Valve.

Standard: Operator should break the lock (or unlock) and open APV0043, CST Deoxygenated Water Outlet Valve.

Comment:

Evaluators Cue: APV0043 is OPEN.

Step 3.C Performance Step: 8 Open fire water hydrant using hydrant wrench.

Standard: Operator should open fire water hydrant.

Comment:

Evaluators Cue: Fire water hydrant is OPEN.

2005 NRC JPM P3 NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Step 4 Performance Step: 9 Ensure fire water is flowing to the CST.

Standard: Operator should verify the fire water is flowing.

Comment:

Evaluators Cue: 2 1/2 fire hose fills and fire water starts to flow.

Step 5 Performance Step: 10 Notify SS/CRS of CST Emergency Fill status.

Standard: Operator should notify SS/OS of CST Fill from fire water.

Comment:

Evaluators Cue: SS/CRS acknowledges.

Terminating Cue: When the control room has been informed, this JPM is complete.

STOP TIME:

2005 NRC JPM P3 NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM P3 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM P3 NUREG 1021, Revision 9

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant has lost all AC power due to an earthquake. Plant operators are currently in emergency procedure ECA-0.0, Loss of All AC Power, stabilizing the plant.

INITIATING CUE: The Control Room Supervisor has directed you to fill the condensate storage tank using Addendum 23, Local CST Emergency Fill. Inform the Control Room Supervisor when you have started filling the CST.

2005 NRC JPM P3 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Plant Task No.:

Task

Title:

Raise Reactor Power To 10-8 Amps JPM No.: 2005 NRC JPM S1 K/A

Reference:

001 A2.11 (4.4/4.7) 001 AA1.05 (4.3/4.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A reactor startup is in progress in accordance with OTG-ZZ-00002, Reactor Startup The following conditions exist:

All shutdown bank rods are fully withdrawn.

Control Bank D is at 92 steps.

The estimated critical position is 101 steps on Control Bank D.

Most recent ICRR predicts 100 steps on Control Bank D Task Standard: The reactor is tripped in response to inappropriate continuous control rod motion.

Required Materials: None General

References:

OTG-ZZ-00002, Reactor Startup Handouts: OTG-ZZ-00002, Reactor Startup marked up through step 4.1.17 Initiating Cue: The Control Room Supervisor directs you to continue with the reactor startup and withdraw control rods to criticality in accordance with OTG-ZZ-00002, Reactor Startup, beginning at Step 4.1.18.

Time Critical Task: NO Validation Time: 12 minutes Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup: reset to IC-187 Password = startup Run Batch File startup.txt Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator Cue:

Inform the candidate that all precautions and limitations are satisfied Performance Step: 1 Candidate initiates control bank withdrawal, monitoring Source Range counts, Intermediate Range Amps, and P-6 bistables.

Standard: Candidate determines that P-6 is energized and refers to Attachment 3 Comment:

Performance Step: 2 Verify one decade of overlap between the source and intermediate range level instruments.

Standard: Observes Source Range and Intermediate Range instruments and determines that sufficient overlap exists Comment:

Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Verify indication on both the source and intermediate startup rate instruments.

Standard: Candidate determines that SR and IR startup rate indication exists Comment:

Performance Step: 4 Transfer the SE NR-45 recorder to the intermediate ranges.

Standard: Transfers NR-45 trend to IR channels Comment:

Performance Step: 5 Prior to exceeding 5E4 CPS on SR instruments, BLOCK the Source Range High Flux Trips Standard: Block A Train by depressing the BLOCK pushbutton on SE HS-5.

Standard: Verify SR TRIP A BLOC illuminates on SB069.

Standard: Block B Train by depressing the BLOCK pushbutton on SE HS-10.

Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION Standard: Verify SR TRIP B BLOCK illuminates on SB069.

Standard: Verify that the high voltage has been removed from the source range detectors.

Comment:

Evaluator Cue: If the candidate reports that Source Range High Flux Trips have been blocked, acknowledge and provide direction to continue the control rod withdrawal Performance Step: 6 Continue incremental rod withdrawal until the reactor is critical, as indicated by a stable positive startup rate with no rod motion, on the intermediate range instrumentation once the prompt jump has receded.

Standard: Candidate initiates control rod withdrawal in small increments Comment:

Note: The following steps represent the alternate path of this JPM Performance Step: 7 Determine that rods are withdrawing with NO demand signal.

Standard: Candidate determines from CONTROL BANK D GROUP 1 and GROUP 2 ROD POSITION indication that rods are withdrawing with NO demand signal.

Comment:

Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8 Trip the reactor in response to inappropriate continuous rod motion.

Candidate trips the reactor in response to inappropriate continuous rod motion.

Standard:

NOTE: Candidate may refer to OTO-SF-00001 and determine that a reactor trip is required based on Step 6 RNO.

Comment:

Terminating Cue: When the Candidate trips the reactor, the evaluation for this JPM is complete.

STOP TIME:

Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION JPM No.: 2005 JPM S1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature: Date:

Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A reactor startup is in progress in accordance with OTG-ZZ-00002, Reactor Startup. The following conditions exist:

All shutdown bank rods are fully withdrawn.

Control Bank D is at 92 steps.

The estimated critical position is 101 steps on Control Bank D.

Most recent ICRR predicts 100 steps on Control Bank D INITIATING CUE: The Control Room Supervisor directs you to continue with the reactor startup and withdraw control rods to criticality in accordance with OTG-ZZ-00002, Reactor Startup, beginning at Step 4.1.18.

Callaway NRC JPM S1 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.: 0111-011-01-013 Task

Title:

Isolate SI Accumulators During a LOCA JPM No.: 2005 NRC JPM S2 K/A

Reference:

009 EA1.13 (4.4/4.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A LOCA has occurred. The crew is performing ES-1.2, Post LOCA Cooldown and Depressurization.

Task Standard: SI Accumulators A, B, and C are isolated. SI Accumulator D is vented.

Required Materials: None General

References:

ES-1.2, Post LOCA Cooldown and Depressurization Handouts: ES-1.2, Post LOCA Cooldown and Depressurization Initiating Cue: The Control Room Supervisor directs you to isolate the SI accumulators in accordance with ES-1.2, Post LOCA Cooldown and Depressurization, Step 23.

Time Critical Task: NO Validation Time: 7 Minutes Callaway JPM S2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup: Initialize IC-184 Password spa321 Run bat.siacc.txt Callaway JPM S2 NUREG 1021, Revision 9

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 RCS subcooling based on core exit TCs - GREATER THAN 30°F (Step 23.a)

Standard: Candidate verifies RCS subcooling based on core exit TCs is greater than 30°F Comment:

Performance Step: 2 PRZR level - GREATER THAN 9% [29% ADVERSE CNMT]

(Step 23.b)

Standard: Candidate locates and verifies PRZR level indication is greater than 9%.

Comment:

Performance Step: 3 Restore power to EP-HV-8808A, B, C, D (Step 23.c)

Standard: Candidate directs Local Operator to restore power to EP-HV-8808A - D Standard: Candidate contacts Local Operator to restore power Comment: Booth Instructor: Inform candidate that power is restored to all 4 accumulator outlet valves Callaway JPM S2 NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Close EP-HIS-8808A, B, C, D (Step 23.d)

Standard: Candidate locates EP-HV-8808A, B, C and D control switches and places in CLOSE.

Standard: Candidate verifies green close light on and red open light off for each valve.

Comment: EP HV-8808C does not close using the handswitch on the MCB.

NOTE: The following step represents the alternate path portion of the JPM.

Performance Step: 5 If any accumulator cannot be isolated, then open associated accumulator vent valve (Step 23.d RNO)

Standard: Locates control switch for EITHER EP HIS-8950D OR EP HIS-8950E, and places switch in OPEN OR places BOTH switches in OPEN.

Standard: Observes Green Light OFF, Red Light ON, and accumulator C pressure lowering.

Comment:

Terminating Cue: When the Candidate verifies that accumulator C pressure is lowering, the evaluation for this JPM is complete.

STOP TIME:

Callaway JPM S2 NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION JPM No.: 2005 JPM S2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature: Date:

Callaway JPM S2 NUREG 1021, Revision 9

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A LOCA has occurred. The crew is performing ES-1.2, Post LOCA Cooldown and Depressurization.

INITIATING CUE: The Control Room Supervisor directs you to isolate the SI accumulators in accordance with ES-1.2, Post LOCA Cooldown and Depressurization, Step 23.

Callaway JPM S2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Plant Task No.:

Task

Title:

Respond to a Stuck Open JPM No.: 2005 NRC JPM S3 Pressurizer Spray Valve K/A

Reference:

010 A2.02 (3.9/3.9)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A Reactor Trip has occurred. The crew has transitioned to ES-0.1, Reactor Trip Response Task Standard: RCPs A and D are tripped Required Materials: ES-0.1 General

References:

ES-0.1 Handouts: None Initiating Cue: The Control Room Supervisor directs you to perform actions to stabilize the plant in accordance with ES-0.1 Time Critical Task: NO Validation Time: 8 minutes Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Reset to IC-188 Password = spray Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

START TIME:

Performance Step: 1 Check RCS temperature - ANY RCP Running - Tave stable at or trending to 557°F.

Standard: Candidate verifies RCPs are running and Tave is at approximately 557°F.

Comment:

Performance Step: 2 Check Generator Output Breakers open.

Standard: Candidate verifies ML ZA-3A (V55) and ML ZA-4A (V53) indicate OPEN.

Comment:

Performance Step: 3 Check all AC busses energized by Off-Site power Standard: Determines that PA01 and PA02, NB01 and NB02 are energized by off-site power Comment:

Performance Step: 4 Check Pressurizer Pressure Control - Pressure greater than 1849 psig Standard: Candidate evaluates pressurizer pressure and determines it is greater than 1849 psig.

Comment:

Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Check Pressurizer Pressure stable at or trending to 2235 psig.

Standard: Candidate determines that Pressurizer Pressure is below 2235 psig and lowering.

Comment:

Note: The following steps represent the alternate path of this JPM Performance Step: 6 Check PORVs closed Standard: Candidate verifies BB-HIS-455A and 456A indicate CLOSED.

Comment:

Performance Step: 7 Check Spray Valves closed Standard: Candidate determines that Spray Valve BB-PCV-455B is OPEN Comment:

Performance Step: 8 Close Spray Valve Standard: Candidate places BB-PCV-455B controller in MANUAL and attempts to reduce output to ZERO. Determines valve remains OPEN Comment:

Performance Step: 9 Stop RCPs A and D Standard: Candidate places RCP A and D control switches in STOP Comment:

Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 10 Verify PRZR Heaters - ON Standard: Candidate verifies PRZR Heaters - ON.

Comment:

Terminating Cue: When A and D RCPs are tripped or upon completion of ES-0.1 Step 3, this JPM is complete.

STOP TIME:

Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: Callaway NRC JPM S3 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: A reactor Trip has occurred. The crew has transitioned to ES-0.1, Reactor Trip Response INITIATING CUE: The Control Room Supervisor directs you to perform actions to stabilize the plant in accordance with ES-0.1 Callaway NRC JPM S3 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Start A Reactor Coolant Pump JPM No.: 2005 NRC JPM S4 K/A

Reference:

002 K6.02 3.6 / 3.8 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in mode 3 at 557°F and 2235 psig. A Reactor Coolant Pump had been secured for breaker work on PA0107. CCW is in operation and is supplying cooling water to the Thermal Barrier Cooling coils per OTN-EG-00001. There are no personnel in CTMT at this time.

Task Standard: Upon completion of this JPM, the operator will have tripped A RCP due to high seal leakoff flow.

Required Materials: None General

References:

OTN-BB-00003, Reactor Coolant Pumps, Revision 15 Initiating Cue: Tags have been cleared on PA0107 and signed off. The Control Room Supervisor has directed you to start A RCP per OTN-BB-00003, Section 4.1. WPA was restored to the OTN-BB-00003 required positions. Inform the Control Room Supervisor when the A Reactor Coolant Pump has been started and the lift oil pump is secured.

Time Critical Task: NO Validation Time: 16 minutes 2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NOTES: Use IC-7. Secure A RCP, close A seal inj and leakoff with BB HIS-8351A and BB HIS-8141A.

Close A PZR Spray Valve and place in MANUAL Set Event 1 x21i115r.eq.true 1 is cv06a severity 8, 12 second ramp, 10 second delay 2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 3 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-BB-00003, Reactor Coolant Pumps.

Standard: Operator should obtain procedure copy.

Comment:

Section 2 Performance Step: 2 Review the Precautions and Limitations of OTN-BB-00003.

Standard: Operator should review the Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Section 3 Performance Step: 3 Review the Initial Conditions of OTN-BB-00003.

Standard: Operator should read the Initial Conditions.

Comment:

Evaluators Cue: All Initial Conditions are satisfied.

NOTE Prior To Step 4.1.1 Performance Step: 4 If the position of the CCW Outlet Throttle Valves are known to have changed, perform Section 5.2.

Standard: Operator may ask if the WPA altered CCW Outlet Throttle Valve Positions.

Comment:

Evaluators Cue: The CCW Outlet Throttle Valves position did not change.

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.1.1 Performance Step: 5 Initiate Seal Water Injection Flow to A RCP. OPEN the RCP Seal Injection Isolation Valve BB HV-8351A with BB-HIS-8351A.

Standard: Operator should initiate seal water injection flow with BB HIS-8351A, RCP A Seal WTR INJ VLV, OPEN on RL021.

Comment:

Evaluators Cue: BB HIS-8351A RED light goes ON and GREEN light goes OFF.

Step 4.1.1.2 Performance Step: 6 OPEN A RCP #1 Seal Leakoff Isolation Valve with Handswitch BB HIS-8141A.

Standard: Operator should OPEN, RCP A Seal WTR Return VLV with BB HIS-8141A, on RL001.

Comment:

Evaluators Cue: BB HIS-8141A RED light goes ON and GREEN light goes OFF.

Step 4.1.3 Performance Step: 7 Verify current OSP-BG-00005 or adjust the Seal Water Injection Throttle Valve (BG-V-198) to establish 8 GPM flow to all RCPs.

Standard: Operator should determine seal flow on BB FR-157, RCP A Seal Leakoff and Injection Flow, on RL021 or verify OSP-BG-00005 is current.

Comment:

Evaluators Cue: OSP-BG-00005 is current all RCPs show a flow of 8 gpm on the Blue Pen for BG FR-157, 156, 155, and 154.

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.3.1 Performance Step: 8 Verify A RCP Seal Differential Pressure is > 200 psid.

Standard: Operator should read BB PI-153A, RCP A Seal DP, on RL021.

Comment:

Evaluators Cue: A RCP DP indicates > 400 psid.

Step 4.1.3.2 Performance Step: 9 Annunciator 73A RCP #2 Seal Flow HI Alarm is CLEARED.

Standard: Operator should determine status of annunciator 73A, RCP #2 Seal Flow HI Alarm is CLEARED.

Comment:

Evaluators Cue: Annunciator 73A is NOT on.

Step 4.1.3.3 Performance Step: 10 Verify Annunciator 42C VCT pressure HI/LO is CLEARED.

Standard: Operator should determine status of Annunciator 42C, VCT Press HI/LO, on RL018 is CLEARED.

Comment:

Evaluators Cue: Annunciator 42C is NOT on.

Step 4.1.3.4 Performance Step: 11 Verify Annunciator 74D RCP Oil RSVR LEV HI/LO CLEARED.

Standard: Operator should determine status of Annunciator 74D, RCP Oil RSVR LEV HI/LO, on RL022 is CLEARED.

Comment:

Evaluators Cue: Annunciator 74D is NOT on.

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.3.5 Performance Step: 12 Verify Annunciator 71A, RCP #1 Seal dP LO CLEARED.

Standard: Operator should determine status of Annunciator 71A, RCP #1 Seal DP LO, on RL022 is cleared.

Comment:

Evaluators Cue: Annunciator 71A RCP #1 seal dP LO is NOT on.

Step 4.1.3.6 Performance Step: 13 Verify Annunciators 70 - 73E RCP A - D Standpipe LEV LO CLEARED.

Standard: Operator should determine status of Annunciator 70E, RCP A Standpipe, LEV LO, on RL022 is CLEARED.

Comment:

Evaluators Cue: Annunciator 70E is NOT on.

Step 4.1.3.7 Performance Step: 14 Verify Annunciators 70 - 73C RCP A - D THERM BAR CCW Flow CLEARED.

Standard: Operator should determine status of Annunciator 70C, RCP A THERM BAR CCW Flow, on Rl022 is CLEARED.

Comment:

Evaluators Cue: Annunciator 70C is NOT on.

Step 4.1.3.8 Performance Step: 15 Verify #1 Seal Backpressure 15 psig. (VCT pressure).

Standard: Operator should obtain VCT pressure from BG PI-115 on RL002.

Comment:

Evaluators Cue: VCT pressure indicates 32 psig on BG PI-115.

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.3.9 Performance Step: 16 Verify A RCP Seal Leakoff is within the NORMAL operating range of Figure 1 on Page 4 of Attachment 1.

Standard: Operator should verify A RCP Seal Leakoff Flow is within the NORMAL operating range of Figure 1 on page 4 of Attachment 1.

Comment:

Evaluators Cue: A RCP Seal Leakoff Return is within the NORMAL operating range.

Step 4.1.3.9 Performance Step: 17 Obtain A RCP Seal Leakoff Indication from BG FR-157.

Standard: Operator should obtain A RCP Seal Leakoff Indication from BG FR-157.

Comment:

Evaluators Cue: BG FR-157 indicates Seal Leakoff is at 3 gpm on the Green Pen, the Red Pen is FULL SCALE.

Step 4.1.4.1 Performance Step: 18 Dispatch someone to inspect A RCP and warn personnel in the vicinity.

Standard: Operator not required to call due to no personnel in CTMT.

Comment:

Step 4.1.4.2 Performance Step: 19 Start A RCPs Oil Lift Pump with switch BB HIS-41.

Standard: Operator should select RUN ON BB HIS-41, RCP A Lift Pump.

Comment:

Evaluators Cue: BB HIS-41 RED light is ON, after 20 seconds, the WHITE light on A Oil Lift Pump goes ON.

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION Step 4.1.4.3 Performance Step: 20 Allow the Oil Lift Pump to RUN for at least 2 minutes.

Standard: Operator should wait two (2) minutes from start time before performing next step.

Comment:

Evaluators Cue: Two (2) minutes has elapsed.

Step 4.1.4.6 Performance Step: 21 Make plant announcement: ATTENTION IN THE PLANT STARTING THE A RCP. STAND CLEAR OF THE PUMP AND PA01 SWITCHGEAR.

Standard: Operator should make plant announcement about starting A RCP.

Should wait 10 - 15 seconds between announcement and starting pump.

Comment:

Step 4.1.4.7 Performance Step: 22 Start A RCP by using Switch BB HIS-37.

Standard: Operator should select RUN on BB HIS-37, RCP A.

Comment:

Evaluators Cue: A RCP BB HS-37 RED light is ON and GREEN light is OFF.

Step 4.1.4.5.1 Performance Step: 23 Monitor RCP starting current and running current.

Standard: Operator should monitor BB-II-1, RCP A Amps, and observe starting current decay away on RL021 to less than 351 amps.

Comment:

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION The following steps represent the alternate path of this JPM Performance Step: 24 Acknowledge annunciators.

Standard: Operator should determine that control room annunciators 70B and 72A are received. 72A, RCP #1 SEAL FLO HI, is an unexpected alarm.

Comment:

Evaluators Cue:

Performance Step: 25 Determine RCP A #1 seal flow Standard: Operator should observe recorder BG FR-157 and verify seal flow is > 5 GPM Comment:

Evaluators Note: Candidate MAY refer to the OTAs or OTO-BB-00002 to determine action required on high seal flow.

Performance Step: 26 Trip A RCP Standard: Places RCP A control switch in STOP Comment:

Terminating Cue: When RCP A is stopped, this JPM is complete.

STOP TIME:

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S4 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant is in mode 3 at 557°F and 2235 psig. A Reactor Coolant Pump had been secured for breaker work on PA0107.

CCW is in operation and is supplying cooling water to the Thermal Barrier Cooling coils per OTN-EG-00001. There are no personnel in CTMT at this time.

INITIATING CUE: Tags have been cleared on PA0107 and signed off. The Control Room Supervisor has directed you to start A RCP per OTN-BB-00003, Section 4.1. WPA was restored to the OTN-BB-00003 required positions. Inform the Control Room Supervisor when the A Reactor Coolant Pump has been started and the lift oil pump is secured.

2005 NRC JPM S4 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Place Steam Dumps in Steam JPM No.: 2005 NRC JPM S5 Pressure Mode K/A

Reference:

041 A4.08 3.0 / 3.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is shutting down for a fall outage. Reactor power is approximately 17.5%. The crew is performing OTG-ZZ-00005.

Task Standard: Upon completion of this JPM, the operator has placed the steam dumps in the steam pressure mode and then closed the failed steam dumps prior to causing the steam dumps to close due to Permissive P-12 (LO LO TAVE - 550°F)

Required Materials: None General

References:

OTN-AB-00001, Main Steam System, Revision 13 Initiating Cue: The Control Room Supervisor has directed you to verify the Steam Dump Controller, AB PK-507, is set for 1092 PSIG, then transfer the Steam Dump Selector switch to the Steam Pressure Mode per OTN-AB-00001, Main Steam System, Section 4.5 and inform the CRS when done.

Time Critical Task: NO Validation Time: 9 minutes 2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Use IC- 68 password redsox Use event trigger mode and set X05I162S.EQ.TRUE.SET Malfunction MSS13b to AB PT-507 reading 1500 psig, 90 second ramp, 0 second time delay, set to event trigger.

Ensure AB PK-0507 is set at something other than 7.28.

2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-AB-00001, Main Steam System.

Standard: Operator should obtain a procedure copy.

Comment:

Section 2.0 Performance Step: 2 Review the Precautions and Limitations of OTN-AB-00001.

Standard: Operator should read the Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Section 3.0 Performance Step: 3 Review the Initial Conditions of OTN-AB-00001.

Standard: Operator should read the Initial Conditions.

Comment:

Evaluators Cue: All Initial Conditions are satisfied.

Ask if the operator understands the Initial conditions and Initiating Cues.

Performance Step: 4 The operator may verify AB PK-0507 is set for 1092 psig.

Standard: OOA-RL-00004 states that 1092 psig = 7.28.

Comment:

2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION NOTE: CAUTION prior to Step 4.5.1 Performance Step: 5 Ensure Steam Header Pressure Controller AB PK-507 matches steam dump demand AB UI-500.

Standard: Operator should ensure AB PK-507 Steam Header Pressure Controller matches AB UI-500.

Comment:

Step 4.5.1 Performance Step: 6 Place the Steam Dump Selector Switch AB US-0500Z to Reset.

Standard: Operator should place Steam Dump Selector Switch AB US-0500Z to Reset.

Comment:

Step 4.5.1 Performance Step: 7 Place the Steam Dump Selector Switch AB US-0500Z to the Steam Pressure Mode.

Standard: Operator should place the Steam Dump Selector Switch AB US-0500Z to the Steam Pressure Mode.

NOTE: When operator notices the steam dump failure, he may then omit Steps 8 and 9 and continue with Step 10.

Comment:

Step 4.5.1.1 Performance Step: 8 Verify C-7, Loss of Load Interlock Light is OFF.

Standard: Operator should verify C-7, Loss of Load Interlock Light is OFF on SC066W Panel.

Comment:

2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Step 4.5.2 Performance Step: 9 Operator may inquire if cooldown is required.

Standard: Operator may ask if a plant cooldown is required.

Comment:

Evaluators Cue: Respond by informing the operator that a cooldown is not required at this time.

Note: The following steps represent the alternate path of this JPM Performance Step: 10 Place Steam Dump Interlock Select Switches AB HS-63, 64 in the OFF/RESET position.

Standard: Operator should place both Steam Dump Selector Switches AB HAS-63, 64 in the OFF position.

Operator should CLOSE Steam Dumps by any means prior to Steam Dumps automatically closing at 550°F due to P-12, LO LO Tave. (May also go back to Tave Mode)

Comment:

Terminating Cue: When Steam Dumps are closed, this JPM is complete.

STOP TIME:

2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S5 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant is shutting down for a fall outage. Reactor power is approximately 17.5%. The crew is performing OTG-ZZ-00005.

INITIATING CUE: The Control Room Supervisor has directed you to verify the Steam Dump Controller, AB PK-507, is set for 1092 PSIG, then transfer the Steam Dump Selector switch to the Steam Pressure Mode per OTN-AB-00001, Main Steam System, Section 4.5 and inform the CRS when done.

2005 NRC JPM S5 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Placing Containment H2 Analyzer In JPM No.: 2005 NRC JPM S6 Service K/A

Reference:

028 A4.03 3.1 / 3.3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.

Task Standard: Upon completion of this JPM, the operator will have placed A hydrogen analyzer in-service.

Required Materials: None General

References:

OTN-GS-00001, Containment Hydrogen Control System, Revision 10 Initiating Cue: The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.

Time Critical Task: NO Validation Time: 10 minutes 2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup Reset to IC-184 CTMT H2 Indication Set Malf Meter

  • GSAI19
  • Ramp Start=0
  • Ramp Time=60 Sec
  • Delay Time=15 Sec
  • Value=1.5
  • Event Trigger=1
  • Set Event Trigger 1

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-GS-0001.

Standard: Operator should obtain procedure copy.

Comment:

Section 2 Performance Step: 2 Review Precautions and Limitations.

Standard: Operator should review Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Step 4.2.1 Performance Step: 3 Ensure Section 4.1, Pre-service Startup and Standby Alignment of hydrogen analyzers is complete.

Standard: Operator may verify Section 4.1 has been completed.

NOTE: Given in Initial Conditions.

Comment:

Evaluators Cue: Section 4.1 has been completed.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.2 Performance Step: 4 Ensure the H2 mixing fans and CTMT coolers re in service.

Standard: Operator should verify H2 mixing fans and CTMT coolers are in service.

Comment:

Evaluators Cue: All H2 mixing fans and CTMT coolers are in service.

Step 4.2.3 Performance Step: 5 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves place GS HIS-40 in Non-Iso.

Standard: Operator should place GS HIS-40, Hydrogen Analyzer A CTMT ISO Valve, in Non-Iso located on RL011.

NOTE: Steps 5 and 6 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-40 is in the Non-Iso position.

Step 4.2.3 Performance Step: 6 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves, place GS HIS-42 in the Non-Iso position.

Standard: Operator should place GS HIS-42, Hydrogen Analyzer A CTMT ISO Valve in Non-Iso.

NOTE: Steps 5 and 6 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-42 is in the Non-Iso position.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 7 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-13 with pushbutton GS HIS-13.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS-HV-13 with pushbutton GS HIS-13.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-13 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.4 Performance Step: 8 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-14 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.4 Performance Step: 9 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-12 shows RED light goes ON and GREEN light goes OFF.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 10 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-17 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.4 Performance Step: 11 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-18 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.6 Performance Step: 12 Place Hydrogen Analyzer A in the ANLYZ position by taking switch GS HIS-16A for SGS02A to ANLYZ.

Standard: Operator should take switch GS HIS-16A to ANLYZ on RL020 Comment:

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.6.1 Performance Step: 13 Monitor GS AI-19 for hydrogen concentration.

Standard: Operator should monitor GS AI-19 for hydrogen concentration.

Comment: Meter will begin to deflect 15 seconds after placing GS HIS-16 in ANALYZ Evaluators Cue: Hydrogen concentration indicates approximately 0% on GS AI-19.

Step 4.2.6.1 Note b Performance Step: 14 Verify Hydrogen Analyzer SGS02A was in the Standby Lineup.

Standard: Operator may verify A Hydrogen Analyzer was in the Standby Lineup.

Comment:

Evaluators Cue: Note A Hydrogen analyzer was in the Standby Position.

Step 4.2.6.1 Note b Performance Step: 15 Wait for a 15 minute warmup period prior to taking data.

Standard: Operator should wait a minimum of 15 minutes for A hydrogen analyzer use.

Comment: Ensure meter has risen to 1 - 1.5% before continuing Evaluators Cue: Over 15 minutes has gone by.

Step 4.2.6.1 Performance Step: 16 Monitor containment hydrogen concentration on GS AI-19.

Standard: Operator should monitor GS AI-19 for hydrogen concentration.

Comment:

Evaluators Cue: GS AI-19 shows hydrogen concentration to be at 1.5%.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: When the candidate has determined that H2 concentration is 1.5, this JPM is complete.

STOP TIME:

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S6 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.

INITIATING CUE: The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Placing Containment H2 Analyzer In JPM No.: 2005 NRC JPM S6 Service K/A

Reference:

028 A4.03 3.1 / 3.3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.

Task Standard: Upon completion of this JPM, the operator will have placed A hydrogen analyzer in-service.

Required Materials: None General

References:

OTN-GS-00001, Containment Hydrogen Control System, Revision 10 Initiating Cue: The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.

Time Critical Task: NO Validation Time: 10 minutes 2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Simulator Setup Reset to IC-184 CTMT H2 Indication Set Malf Meter

  • GSAI19
  • Ramp Start=0
  • Ramp Time=60 Sec
  • Delay Time=15 Sec
  • Value=1.5
  • Event Trigger=1
  • Set Event Trigger 1

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-GS-0001.

Standard: Operator should obtain procedure copy.

Comment:

Section 2 Performance Step: 2 Review Precautions and Limitations.

Standard: Operator should review Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Step 4.2.1 Performance Step: 3 Ensure Section 4.1, Pre-service Startup and Standby Alignment of hydrogen analyzers is complete.

Standard: Operator may verify Section 4.1 has been completed.

NOTE: Given in Initial Conditions.

Comment:

Evaluators Cue: Section 4.1 has been completed.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.2 Performance Step: 4 Ensure the H2 mixing fans and CTMT coolers re in service.

Standard: Operator should verify H2 mixing fans and CTMT coolers are in service.

Comment:

Evaluators Cue: All H2 mixing fans and CTMT coolers are in service.

Step 4.2.3 Performance Step: 5 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves place GS HIS-40 in Non-Iso.

Standard: Operator should place GS HIS-40, Hydrogen Analyzer A CTMT ISO Valve, in Non-Iso located on RL011.

NOTE: Steps 5 and 6 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-40 is in the Non-Iso position.

Step 4.2.3 Performance Step: 6 Restore electrical power to Hydrogen Analyzer A CTMT ISO Valves, place GS HIS-42 in the Non-Iso position.

Standard: Operator should place GS HIS-42, Hydrogen Analyzer A CTMT ISO Valve in Non-Iso.

NOTE: Steps 5 and 6 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-42 is in the Non-Iso position.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 7 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-13 with pushbutton GS HIS-13.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS-HV-13 with pushbutton GS HIS-13.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-13 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.4 Performance Step: 8 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-14 with pushbutton GS HIS-14.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-14 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.4 Performance Step: 9 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-12 with pushbutton GS HIS-12.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-12 shows RED light goes ON and GREEN light goes OFF.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.4 Performance Step: 10 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-17 with pushbutton GS HIS-17.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-17 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.4 Performance Step: 11 Open A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.

Standard: Operator should OPEN A Hydrogen Analyzer CTMT Isolation Valve GS HV-18 with pushbutton GS HIS-18.

NOTE: Steps 7 through 11 may be performed in any order.

Comment:

Evaluators Cue: GS HIS-18 shows RED light goes ON and GREEN light goes OFF.

Step 4.2.6 Performance Step: 12 Place Hydrogen Analyzer A in the ANLYZ position by taking switch GS HIS-16A for SGS02A to ANLYZ.

Standard: Operator should take switch GS HIS-16A to ANLYZ on RL020 Comment:

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION Step 4.2.6.1 Performance Step: 13 Monitor GS AI-19 for hydrogen concentration.

Standard: Operator should monitor GS AI-19 for hydrogen concentration.

Comment: Meter will begin to deflect 15 seconds after placing GS HIS-16 in ANALYZ Evaluators Cue: Hydrogen concentration indicates approximately 0% on GS AI-19.

Step 4.2.6.1 Note b Performance Step: 14 Verify Hydrogen Analyzer SGS02A was in the Standby Lineup.

Standard: Operator may verify A Hydrogen Analyzer was in the Standby Lineup.

Comment:

Evaluators Cue: Note A Hydrogen analyzer was in the Standby Position.

Step 4.2.6.1 Note b Performance Step: 15 Wait for a 15 minute warmup period prior to taking data.

Standard: Operator should wait a minimum of 15 minutes for A hydrogen analyzer use.

Comment: Ensure meter has risen to 1 - 1.5% before continuing Evaluators Cue: Over 15 minutes has gone by.

Step 4.2.6.1 Performance Step: 16 Monitor containment hydrogen concentration on GS AI-19.

Standard: Operator should monitor GS AI-19 for hydrogen concentration.

Comment:

Evaluators Cue: GS AI-19 shows hydrogen concentration to be at 1.5%.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: When the candidate has determined that H2 concentration is 1.5, this JPM is complete.

STOP TIME:

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S6 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant has experienced a Large Loss of Coolant Accident. A Safety Injection has occurred.

INITIATING CUE: The Control Room Supervisor has directed you to place the A Containment Hydrogen Analyzer, SGS02A, in service per OTN-GS-00001, Section 4.2. The pre-service startup and standby alignment of hydrogen analyzers has already been completed, (Section 4.1). Inform the Control room Supervisor when SGS02A is in service.

2005 NRC JPM S6 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Paralleling Diesel Generator A To JPM No.: 2005 NRC JPM S7 XNB01 K/A

Reference:

064 A4.01 4.0 / 4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3. NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.

Task Standard: NE01 is connected to NB01 and is carrying at least 2 Mwe load.

Required Materials: None General

References:

OTN-NE-0001A, Standby Diesel Generation System Train A, Rev. 14 Initiating Cue: You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4. Inform the Control Room Supervisor when NE01 is running loaded > 2 Mwe.

Time Critical Task: NO Validation Time: 15 minutes 2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NOTES: May be run with JPM S4 Ensure A Emergency Diesel Generator is running unloaded if performing on the simulator. Use remote NBHS0037 place in manual.

Monitor NEPSLTC (1).

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 3 of 14 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-NE-0001A, Standby Diesel Generation System Train A.

Standard: Operator should obtain procedure copy.

Comment:

Section 3 Performance Step: 2 Review the Precautions and Limitations of OTN-NE-0001A.

Standard: Operator should read the Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Section 4 Performance Step: 3 Review the Prerequisites of OTN-NE-0001A.

Standard: Operator should read the Initial Conditions.

Comment:

Evaluators Cue: All prerequisites are satisfied.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.1 Performance Step: 4 Ensure that the Local Master Transfer Switch KJHS0009 is in the AUTO position.

Standard: Operator should verify absence of MCB ANN 20E and/or request Local Observation of Master Transfer Switch.

Comment:

Evaluators Cue: The Local Master Transfer Switch KJHS0009 is in the AUTO position.

Step 5.4.2 Performance Step: 5 At RL015, Check NE-HIS-25, NB01 EMERG SUPPLY BREAKER NB0111, is OPEN.

Standard: Green light for NE-HIS-25 is ON Comment:

Step 5.4.3 Performance Step: 6 Check NB-HIS-2, NB01 NORM SUPPLY BK R NB0112, is CLOSED Standard: Red light for NB-HIS-2 is ON Comment:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.4 Performance Step: 7 Check diesel generator voltage and frequency are stable in the following ranges:

  • 3740 to 4320 VAC indicated by NE EI-1, DG VOLTS
  • 58.8 to 61.2 HZ indicated by NE ST-1, DG FREQ/SPD Standard: Determines that voltage is stable at approximately 4100 - 4200 VAC and frequency is stable at 60 HZ Comment:

Step 5.4.5 Performance Step: 8 Ensure operating parameters are being monitored and recorded per Attachment 1 Standard: Refer to Attachment 1 Comment:

Evaluators Cue: Parameters are being monitored by another operator Step 5.4.6 Performance Step: 9 If the White Parallel Operation Light is not lit, momentarily place NE HS-5, NE01 Unit Parallel SW to the parallel position.

Standard: Operator should determine WHITE parallel light is NOT lit by calling the EO at NE107. After determining white light not lit, places NE HS-5 to PARALLEL.

Comment:

Evaluators Cue: When asked if WHITE Parallel Operation Light is lit on NE107, report that it is NOT lit.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.7 Performance Step: 10 Check the White Parallel Operation Light is lit on NE107.

Standard: Operator should contact EO to verify the White Parallel Light is lit on NE107.

Comment:

Evaluators Cue: The White Parallel Light is lit on NE107.

Step 5.4.8 Performance Step: 11 Verify Main Control board Annunciator 22B, Voltage Control Freeze is lit.

Standard: Operator should verify Annunciator 22B, Voltage Control Freeze is lit.

Comment:

Evaluators Cue: Annunciator 22B, Voltage Control Freeze is lit.

Step 5.4.9 Performance Step: 12 Verify EITHER Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE OR Disconnect NB0301 is OPEN.

Standard: Operator should verify NBQ0003 is in FREEZE or DISCONNECTED.

Comment:

Evaluators Cue: Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE mode.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.10 Performance Step: 13 Verify EITHER Computer Point NBX0001 indicates FREEZE or transformer XNB01 LTC is in MANUAL and set at the appropriate Tap Changer setting.

Standard: Operator should verify XNB01 LTC is in MANUAL and Tap Setting 13 is selected OR Computer Point NBX0001 indicates FREEZE NOTE: Given in Initial Conditions Comment:

Evaluators Cue: Annunciator 19D, XNB01 XFMR/VOLT CTRL TRBL is LIT AND Computer Point NBX0001 indicates FREEZE.

Step 5.4.11 Performance Step: 14 Periodically monitor and adjust voltage and frequency to maintain 4160 VAC and 60 HZ (nominal).

Standard: Operator will adjust parameters as necessary Comment:

Step 5.4.12 Performance Step: 15 Place the Sync Transfer Switch NE HS-27 in the ON position.

Standard: Operator selects ON with Sync Transfer Switch NE HS-27.

Comment:

Evaluators Cue: NE HS-27 is in the ON position.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.13 Performance Step: 16 Place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.

Standard: Operator should place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.

Comment:

Evaluators Cue: NB HS-10 is selected to DG Feeder BKR Position.

The Sync Scope is rotating in fast direction; Sync Lights NB ZL-9 are flashing.

Step 5.4.14 Performance Step: 17 Adjust the diesel generator speed using Governor Control, KJ HS-7A until the Synchroscope NB EI-3 is rotating slowly in the fact direction.

Standard: Operator turns KJ HS-7A, DG NE01 GOV, to RAISE if speed is SLOW and to LOWER if speed FAST as indicated by 4.16 KV Bus NB01 Sync Scope, NB EI-13 on RL015 to satisfy Synch check Relay.

Comment:

Evaluators Cue: Synchroscope NB EI-3 is rotating slowly in the FAST direction.

Step 5.4.15 Performance Step: 18 Adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.

Standard: Operator should adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.

Comment:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.15 Performance Step: 19 Determine NE01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker position and reading NB EI-28.

Standard: Operator should place NB HS-10 in the D/G Feeder Breaker Position and read NB EI-28 to determine NE01 voltage.

Comment:

Evaluators Cue: NE EI-28 voltage is 4190 volts when NB HS-10 is in the D/G Feeder Breaker Position.

Step 5.4.15 Performance Step: 20 Determine NB01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the Main FDR BKR Position and reading the voltage from NB EI-28.

Standard: Operator should determine NB01 voltage by placing NB HS-10 in the Main FDR BKR Position and reading voltage from NB EI-28.

Comment:

Evaluators Cue: NB EI-28 voltage is 4160 when NB HS-10 is in the Main FDR BKR Position.

Step 5.4.16 Performance Step: 21 When NE01 voltage has been verified to be within +50, -0 volts of NB01 voltage, ensure the Synchroscope Selector Switch NB HS-10 is placed in the D/G Feeder Breaker Position.

Standard: Operator should place NB HS-10 in the D/G Feeder Breaker Position.

Comment:

Step 5.4.17 Performance Step: 22 Verify proper operation of Sync Light NB ZL-9.

Standard: Operator should verify proper operation of NB ZL-9.

Comment:

Evaluators Cue: Dimmest at 12 oclock and brightest at 6 oclock on Synch Scope NB EI-3 2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.18 Performance Step: 23 Verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.

Standard: Operator should verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.

Comment:

Evaluators Cue: NE ZL-27A is coming on at five (5) degrees before the 12 oclock position and off at five (5) degrees after 12 oclock.

Step 5.4.19 Performance Step: 24 Allow Synchroscope NB EI-3 to complete one revolution to verify proper speed for synchronization.

Standard: Operator should observe the Sync Scope for one complete revolutions and adjust the speed as necessary.

Comment:

Evaluators Cue: Synchroscope is rotating in the FAST direction at about the speed of the second had of a clock.

Step 5.4.20 Performance Step: 25 When the Synchroscope reaches the 11 oclock position turn NE HIS-25 to CLOSE and hold until Breaker NB0111 indicates CLOSED, then release the control switch.

Standard: When Sync Scope reaches the 11 oclock position and Synch Check Permissive Light ON, CLOSE NB01 EMERG SPLY BKR NB0111 with Switch NE HIS-25 and hold until the RED light is ON and the GREEN light is OFF, then the operator should release the switch.

Comment:

Evaluators Cue: NE HIS-25 RED light is ON and the GREEN light is OFF.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.21 Performance Step: 26 Immediately upon closure of the D/G Breaker Pickup Load to at least 0.2 MW by operating the D/G Governor Control JK HS-7A in the RAISE direction if necessary.

Standard: Operator should RAISE DG Load to prevent NB0111 Reverse Power Trip using KJ HS-7A.

Comment:

Evaluators Cue: D/G Load is greater than 0.2 MW.

Step 5.4.22 Performance Step: 27 Adjust Diesel Generator Voltage with the Auto Voltage Regulator NE HS-13A to maintain a power factor of 0.9 LAG.

Standard: Operator should adjust D/G VAR Loading using NE HS-13A, Auto Voltage Regulator.

Comment:

Evaluators Cue: Power factor is 0.9 LAG.

Step 5.4.23 Performance Step: 28 Return the Synchroscope Selector Switch NB HS-10 to the OFF position.

Standard: Operator should return the Synchroscope Selector Switch NB HS-10 to the OFF position.

Comment:

Evaluators Cue: NB HS-10 is in OFF.

Step 5.4.24 Performance Step: 29 Place Sync Transfer Switch NE HS-27 in the OFF position.

Standard: Operator should place Sync Transfer Switch NE HS-27 in the OFF position.

Comment:

Evaluators Cue: NE HS-27 is in OFF.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.25 Performance Step: 30 Increase Diesel Generator Load as directed by the SS/OS.

Standard: The operator should increase Diesel Generator Load as directed by the Control Room Supervisor.

NOTE: Initial Conditions directed NE01 BE Loaded to > 2MW.

Comment:

Evaluators Cue: If asked, report that it has been 5 minutes at current increment Evaluators Cue: The Control Room Supervisor directs you to increase D/G Load to > two (2) MW.

Step 5.4.25 Performance Step: 31 Increase Diesel Generator Load, by placing KJ HS-7A in the RAISE position, to > two (2) MW.

Standard: Operator should go to RAISE on KJ HS-7A on RL015 to RAISE D/G Load to > two (2) MW.

Comment:

Evaluators Cue: D/G Load is > two (2) MW.

Performance Step: 32 Inform the Control Room Supervisor that NE01 is loaded >

2 MWe.

Standard: Operator should inform the Control Room Supervisor that NE01 is loaded > 2 Mwe.

Comment:

Evaluators Cue: The Control Room Supervisor acknowledges.

Terminating Cue: When DG load is >2 MW, this JPM is complete.

STOP TIME:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S7 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 14 of 14 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3.

NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.

INITIATING CUE: You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4.

Inform the Control Room Supervisor when NE01 is running loaded

> 2 Mwe.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Paralleling Diesel Generator A To JPM No.: 2005 NRC JPM S7 XNB01 K/A

Reference:

064 A4.01 4.0 / 4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3. NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.

Task Standard: NE01 is connected to NB01 and is carrying at least 2 Mwe load.

Required Materials: None General

References:

OTN-NE-0001A, Standby Diesel Generation System Train A, Rev. 14 Initiating Cue: You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4. Inform the Control Room Supervisor when NE01 is running loaded > 2 Mwe.

Time Critical Task: NO Validation Time: 15 minutes 2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NOTES: May be run with JPM S4 Ensure A Emergency Diesel Generator is running unloaded if performing on the simulator. Use remote NBHS0037 place in manual.

Monitor NEPSLTC (1).

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 3 of 14 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-NE-0001A, Standby Diesel Generation System Train A.

Standard: Operator should obtain procedure copy.

Comment:

Section 3 Performance Step: 2 Review the Precautions and Limitations of OTN-NE-0001A.

Standard: Operator should read the Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Section 4 Performance Step: 3 Review the Prerequisites of OTN-NE-0001A.

Standard: Operator should read the Initial Conditions.

Comment:

Evaluators Cue: All prerequisites are satisfied.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.1 Performance Step: 4 Ensure that the Local Master Transfer Switch KJHS0009 is in the AUTO position.

Standard: Operator should verify absence of MCB ANN 20E and/or request Local Observation of Master Transfer Switch.

Comment:

Evaluators Cue: The Local Master Transfer Switch KJHS0009 is in the AUTO position.

Step 5.4.2 Performance Step: 5 At RL015, Check NE-HIS-25, NB01 EMERG SUPPLY BREAKER NB0111, is OPEN.

Standard: Green light for NE-HIS-25 is ON Comment:

Step 5.4.3 Performance Step: 6 Check NB-HIS-2, NB01 NORM SUPPLY BK R NB0112, is CLOSED Standard: Red light for NB-HIS-2 is ON Comment:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.4 Performance Step: 7 Check diesel generator voltage and frequency are stable in the following ranges:

  • 3740 to 4320 VAC indicated by NE EI-1, DG VOLTS
  • 58.8 to 61.2 HZ indicated by NE ST-1, DG FREQ/SPD Standard: Determines that voltage is stable at approximately 4100 - 4200 VAC and frequency is stable at 60 HZ Comment:

Step 5.4.5 Performance Step: 8 Ensure operating parameters are being monitored and recorded per Attachment 1 Standard: Refer to Attachment 1 Comment:

Evaluators Cue: Parameters are being monitored by another operator Step 5.4.6 Performance Step: 9 If the White Parallel Operation Light is not lit, momentarily place NE HS-5, NE01 Unit Parallel SW to the parallel position.

Standard: Operator should determine WHITE parallel light is NOT lit by calling the EO at NE107. After determining white light not lit, places NE HS-5 to PARALLEL.

Comment:

Evaluators Cue: When asked if WHITE Parallel Operation Light is lit on NE107, report that it is NOT lit.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.7 Performance Step: 10 Check the White Parallel Operation Light is lit on NE107.

Standard: Operator should contact EO to verify the White Parallel Light is lit on NE107.

Comment:

Evaluators Cue: The White Parallel Light is lit on NE107.

Step 5.4.8 Performance Step: 11 Verify Main Control board Annunciator 22B, Voltage Control Freeze is lit.

Standard: Operator should verify Annunciator 22B, Voltage Control Freeze is lit.

Comment:

Evaluators Cue: Annunciator 22B, Voltage Control Freeze is lit.

Step 5.4.9 Performance Step: 12 Verify EITHER Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE OR Disconnect NB0301 is OPEN.

Standard: Operator should verify NBQ0003 is in FREEZE or DISCONNECTED.

Comment:

Evaluators Cue: Computer Point NBQ0003 indicates Capacitor Bank NB03 is in FREEZE mode.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.10 Performance Step: 13 Verify EITHER Computer Point NBX0001 indicates FREEZE or transformer XNB01 LTC is in MANUAL and set at the appropriate Tap Changer setting.

Standard: Operator should verify XNB01 LTC is in MANUAL and Tap Setting 13 is selected OR Computer Point NBX0001 indicates FREEZE NOTE: Given in Initial Conditions Comment:

Evaluators Cue: Annunciator 19D, XNB01 XFMR/VOLT CTRL TRBL is LIT AND Computer Point NBX0001 indicates FREEZE.

Step 5.4.11 Performance Step: 14 Periodically monitor and adjust voltage and frequency to maintain 4160 VAC and 60 HZ (nominal).

Standard: Operator will adjust parameters as necessary Comment:

Step 5.4.12 Performance Step: 15 Place the Sync Transfer Switch NE HS-27 in the ON position.

Standard: Operator selects ON with Sync Transfer Switch NE HS-27.

Comment:

Evaluators Cue: NE HS-27 is in the ON position.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.13 Performance Step: 16 Place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.

Standard: Operator should place the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker Position.

Comment:

Evaluators Cue: NB HS-10 is selected to DG Feeder BKR Position.

The Sync Scope is rotating in fast direction; Sync Lights NB ZL-9 are flashing.

Step 5.4.14 Performance Step: 17 Adjust the diesel generator speed using Governor Control, KJ HS-7A until the Synchroscope NB EI-3 is rotating slowly in the fact direction.

Standard: Operator turns KJ HS-7A, DG NE01 GOV, to RAISE if speed is SLOW and to LOWER if speed FAST as indicated by 4.16 KV Bus NB01 Sync Scope, NB EI-13 on RL015 to satisfy Synch check Relay.

Comment:

Evaluators Cue: Synchroscope NB EI-3 is rotating slowly in the FAST direction.

Step 5.4.15 Performance Step: 18 Adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.

Standard: Operator should adjust NE01 voltage to be within +50, -0 volts of the NB01 Bus Voltage using the Auto Voltage Regulator NE HS-13A.

Comment:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.15 Performance Step: 19 Determine NE01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the D/G Feeder Breaker position and reading NB EI-28.

Standard: Operator should place NB HS-10 in the D/G Feeder Breaker Position and read NB EI-28 to determine NE01 voltage.

Comment:

Evaluators Cue: NE EI-28 voltage is 4190 volts when NB HS-10 is in the D/G Feeder Breaker Position.

Step 5.4.15 Performance Step: 20 Determine NB01 voltage by placing the Synchroscope Selector Switch NB HS-10 in the Main FDR BKR Position and reading the voltage from NB EI-28.

Standard: Operator should determine NB01 voltage by placing NB HS-10 in the Main FDR BKR Position and reading voltage from NB EI-28.

Comment:

Evaluators Cue: NB EI-28 voltage is 4160 when NB HS-10 is in the Main FDR BKR Position.

Step 5.4.16 Performance Step: 21 When NE01 voltage has been verified to be within +50, -0 volts of NB01 voltage, ensure the Synchroscope Selector Switch NB HS-10 is placed in the D/G Feeder Breaker Position.

Standard: Operator should place NB HS-10 in the D/G Feeder Breaker Position.

Comment:

Step 5.4.17 Performance Step: 22 Verify proper operation of Sync Light NB ZL-9.

Standard: Operator should verify proper operation of NB ZL-9.

Comment:

Evaluators Cue: Dimmest at 12 oclock and brightest at 6 oclock on Synch Scope NB EI-3 2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.18 Performance Step: 23 Verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.

Standard: Operator should verify that the Diesel Generator to Bus Synchronizing Light NE ZL-27A illuminates when the Synchroscope is between the 11 oclock and the 12 oclock position.

Comment:

Evaluators Cue: NE ZL-27A is coming on at five (5) degrees before the 12 oclock position and off at five (5) degrees after 12 oclock.

Step 5.4.19 Performance Step: 24 Allow Synchroscope NB EI-3 to complete one revolution to verify proper speed for synchronization.

Standard: Operator should observe the Sync Scope for one complete revolutions and adjust the speed as necessary.

Comment:

Evaluators Cue: Synchroscope is rotating in the FAST direction at about the speed of the second had of a clock.

Step 5.4.20 Performance Step: 25 When the Synchroscope reaches the 11 oclock position turn NE HIS-25 to CLOSE and hold until Breaker NB0111 indicates CLOSED, then release the control switch.

Standard: When Sync Scope reaches the 11 oclock position and Synch Check Permissive Light ON, CLOSE NB01 EMERG SPLY BKR NB0111 with Switch NE HIS-25 and hold until the RED light is ON and the GREEN light is OFF, then the operator should release the switch.

Comment:

Evaluators Cue: NE HIS-25 RED light is ON and the GREEN light is OFF.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.21 Performance Step: 26 Immediately upon closure of the D/G Breaker Pickup Load to at least 0.2 MW by operating the D/G Governor Control JK HS-7A in the RAISE direction if necessary.

Standard: Operator should RAISE DG Load to prevent NB0111 Reverse Power Trip using KJ HS-7A.

Comment:

Evaluators Cue: D/G Load is greater than 0.2 MW.

Step 5.4.22 Performance Step: 27 Adjust Diesel Generator Voltage with the Auto Voltage Regulator NE HS-13A to maintain a power factor of 0.9 LAG.

Standard: Operator should adjust D/G VAR Loading using NE HS-13A, Auto Voltage Regulator.

Comment:

Evaluators Cue: Power factor is 0.9 LAG.

Step 5.4.23 Performance Step: 28 Return the Synchroscope Selector Switch NB HS-10 to the OFF position.

Standard: Operator should return the Synchroscope Selector Switch NB HS-10 to the OFF position.

Comment:

Evaluators Cue: NB HS-10 is in OFF.

Step 5.4.24 Performance Step: 29 Place Sync Transfer Switch NE HS-27 in the OFF position.

Standard: Operator should place Sync Transfer Switch NE HS-27 in the OFF position.

Comment:

Evaluators Cue: NE HS-27 is in OFF.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION Step 5.4.25 Performance Step: 30 Increase Diesel Generator Load as directed by the SS/OS.

Standard: The operator should increase Diesel Generator Load as directed by the Control Room Supervisor.

NOTE: Initial Conditions directed NE01 BE Loaded to > 2MW.

Comment:

Evaluators Cue: If asked, report that it has been 5 minutes at current increment Evaluators Cue: The Control Room Supervisor directs you to increase D/G Load to > two (2) MW.

Step 5.4.25 Performance Step: 31 Increase Diesel Generator Load, by placing KJ HS-7A in the RAISE position, to > two (2) MW.

Standard: Operator should go to RAISE on KJ HS-7A on RL015 to RAISE D/G Load to > two (2) MW.

Comment:

Evaluators Cue: D/G Load is > two (2) MW.

Performance Step: 32 Inform the Control Room Supervisor that NE01 is loaded >

2 MWe.

Standard: Operator should inform the Control Room Supervisor that NE01 is loaded > 2 Mwe.

Comment:

Evaluators Cue: The Control Room Supervisor acknowledges.

Terminating Cue: When DG load is >2 MW, this JPM is complete.

STOP TIME:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S7 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Page 14 of 14 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The plant is operating in Mode 3. The A Emergency Diesel Generator has been started per OTN-NE-0001A, Section 5.3.

NB01 is energized from its normal off-site power source. XNB01 LTC is in manual and Tap 13 is set for modes 1 through 4.

INITIATING CUE: You have been directed to parallel the A Diesel Generator to NB01 and load to at least 2 MW per OTN-NE-0001A, Section 5.4.

Inform the Control Room Supervisor when NE01 is running loaded

> 2 Mwe.

2005 NRC JPM S7 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Callaway Task No.:

Task

Title:

Reinitiate CTMT Purge Following JPM No.: 2005 NRC JPM S8 CPIS K/A

Reference:

013 A2.06 3.7 / 4.0 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1. A containment mini purge was in progress to prepare for a containment entry. One hour ago, a CPIS/CRVIS occurred due to a spike on GTRE0022. Repairs have been made to GTRE0022 and it is now operable. Outside air temperature is expected to remain > 50°F.

Task Standard: Upon completion of this JPM, the operator will have reset CPIS and re-established containment mini purge.

Required Materials: Copy of Gaseous Radwaste Release Permit Covers installed on the ESFAS Switches for GTRE0022 and GTRE0033 General

References:

OTN-GT-00001, Containment Purge System, Revision 20 CAR 199301739, 199400025, 199501723, 199700736 Initiating Cue: The Control Room Supervisor has directed you to re-initiate the containment mini purge per OTN-GT-00001, Section 5.6. The Control Room Supervisor has decided to not realign the control building HVAC at this time. The SS has authorized reinitiating CTMT mini purge.

Inform the Control Room Supervisor when the mini purge has been re-initiated.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: NO Validation Time: 22 minutes 2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Reset to IC - 68 (May be run with S5)

NOTES: Manually initiate a CPIS and CRVIS (both trains).

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 4 of 17 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Obtain a verified working copy of OTN-GT-00001, Containment Purge System.

Standard: Operator should obtain procedure copy.

Comment:

Section 3 Performance Step: 2 Review Precautions and Limitations of OTN-GT-00001.

Standard: Operator should review Precautions and Limitations.

Comment:

Evaluators Cue: All Precautions and Limitations are satisfied.

Section 4 Performance Step: 3 Review Prerequisites of OTN-GT-00001.

Standard: Operator should review Prerequisites.

Comment:

Evaluators Cue: All Prerequisites are satisfied.

Step 5.6.1 Performance Step: 4 The purge may be reinitiated w/out terminating the release permit provided the time between stopping and restarting the release does not exceed two hours.

Standard: Operator should realize purge was only secured for one hour and SS has given permission to reinitiate purge.

Comment:

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 5 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.2 Performance Step: 5 Have the Count Room Technician verify alarm/trip setpoints for GT-RE-21B, GT-RE-22, and GT-RE-33 are correct per the release permit.

Standard: Operator should contact the Count Room Technician to verify setpoint for GT-RE-21, 22 and 33 are correct per the release permit.

Comment:

Evaluators Cue: The Count Room Technician has verified setpoints correct per the release permit.

Step 5.6.3 Performance Step: 6 If monitor readings are the hihi alarm setpoint, close the permit, resample, and generate a new permit.

Standard: Operator should use the RM11 console to determine the color of channels 211, 212, 221, 222, 223, 331, 332, and 333 are NOT lit RED.

Comment:

Evaluators Cue: RM 11 channels 211, 212, 221, 222, 2223, 331, 332, and 333 are lit GREEN.

Step 5.6.4 Performance Step: 7 Check SA036D and SA036E. If any bistable trip lights are lit, record on the URO Log and reset the bistable by depressing and then releasing the bistable trip light.

Standard: Operator should go to the SA036D and SA036E panel in the back of the Control Room and verify NO bistable lights lit.

Comment:

Evaluators Cue: NO bistable lights are lit on SA036D and SA036E.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 6 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.5 Performance Step: 8 If required, with SS/CRS permission, reset the following:

Standard:

Comment:

Evaluators Note: The SS has authorized resetting switches.

Step 5.6.6 Performance Step: 9 Reset CPIS by depressing SA HS-15, CTMT purge Train B ISO on RL018.

NOTE: Steps 9 through 12 may be performed in any order.

Standard: Operator should depress the reset button on SA HS-15, CTMT Purge Train B ISO on RL018.

Comment:

Evaluators Note: The reset button on SA HS-15 has been depressed.

Step 5.6.6 Performance Step: 10 Reset CRVIS by depressing SA HS-13, Ctrl Bldg Vent Train B ISO.

NOTE: Steps 9 through 12 may be performed in any order.

Standard: Operator should depress the reset button on SA HS-13, Ctrl Bldg Vent Train B ISO on RL018.

Comment:

Evaluators Note: The reset button on SA HS-13 has been depressed.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 7 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.5 Performance Step: 11 Reset CPIS by depressing SA HS-11, CTMT Purge Train A ISO on RL018.

NOTE: Steps 9 through 12 may be performed in any order.

Standard: Operator should depress the reset button on SA HS-11, CTMT Purge Train A ISO on RL018.

Comment:

Evaluators Cue: The reset button on SA HS-11 has been depressed.

Step 5.6.5 Performance Step: 12 Reset CRVIS by depressing SA HS-9, Ctrl Bldg Vent Train A ISO on RL018.

NOTE: Steps 9 through 12 may be performed in any order.

Standard: Operator should depress the reset button on SA HS-9, Ctrl Bldg Vent Train A ISO on RL018.

Comment:

Evaluators Cue: The reset button on SA HS-9 has been depressed.

Step 5.6.7 Performance Step: 13 Ensure CPIS and CRVIS lights OUT on ESFAS status panels; if required use SA HS-24 and/or SA HS-23, ESF panel mode SEL switches, to reset.

Standard: Operator should ensure CPIS and CRVIS lights OUT on ESFAS status panels.

Comment:

Evaluators Cue: CPIS and CRVIS lights on ESFAS status panel are OUT.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 8 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.6.8 Performance Step: 14 Ensure MCB annunciators 59D (CPIS) and 63A (CRVIS) are clear.

Standard: Operator should verify MCB annunciators 59D and 63A are clear.

Comment:

Evaluators Cue: MCB annunciators 59D and 63A are clear.

Step 5.6.9 Performance Step: 15 If required, realign the Control Building HVAC per OTN-GK-00001.

Standard: The operator should continue with Step 5.6.10 and not align Control Building HVAC at this time.

Given in Initial Conditions.

Comment:

Evaluators Cue: The O.S. has determined to align mini-purge prior to realigning the Control Building HVAC.

Step 5.6.10 Performance Step: 16 Reinitiate Mini-Purge per Section 5.2 of this procedure.

Standard: Operator should go to Section 5.2.

Comment:

Section 5.2.1 Performance Step: 17 Ensure Shutdown Purge is not in service.

Standard: Operator should verify Shutdown Purge is not in service.

Comment:

Evaluators Cue: Shutdown Purge is not in service.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 9 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.2 Performance Step: 18 Monitor or trend SD-RE-41, SD-RE-42, and GT-PDI-040.

Standard: Operator monitor or trend SD-RE-41, SD-RE-42, and GT-PD-040. Operator may use time trend minivent.

Comment:

Evaluators Cue: SD-RE-41, SD-RE-42, and GT-PD-040 are all stable.

Step 5.2.3 Performance Step: 19 Record containment pressure, using GTPDI0040 or GTD0040, on the Gaseous Radwaste Permit.

Standard: Operator should record containment pressure GTPDI0040 or GTD0040, on the Gaseous Radwaste Permit.

Comment:

Evaluators Cue: Containment pressure has been recorded.

Step 5.2.4 Performance Step: 20 Ensure that GTRE0022 and GTRE0033 are not in bypass, and ensure the CTMT Purge In Prog - Do Not Bypass cover over the ESFAS switches for GTRE0022 and GTRE0033.

Standard: Operator should verify GTRE0022 and GTRE0033 are not in bypass and covers have been placed over GTRE0022 and GTRE0033 ESFAS Switches.

Comment:

Evaluators Cue: GTRE022 and GTRE0033 are not in bypass.

Covers have been placed over GTRE0022 and GTRE0033 ESFAS Switches.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 10 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.6 Performance Step: 22 Start CGT02 Containment Mini Purge Exhaust Fan using GT HIS-20.

Standard: Operator should select RUN on GT HIS-20, CTMT Mini Purge Exh Fan.

Comment:

Evaluators Cue: GT HIS-20 RED lights illuminate and GREEN lights extinguish.

Step 5.2.7 Performance Step: 23 Open GTHZ0011 using GT HIS-11.

NOTE: Steps 23 - 26 may be accomplished in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-11.

Comment:

Evaluators Cue: GT HIS-11 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.

Step 5.2.8 Performance Step: 24 Open GTHZ0012 using GT HIS-12.

NOTE: Steps 23 - 26 may be accomplished in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-12.

Comment:

Evaluators Cue: GT HIS-12 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 11 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.9 Performance Step: 25 Open GTHZ0028 using GT HIS-28.

NOTE: Steps 23 - 26 may be accomplished in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-28.

Comment:

Evaluators Cue: GT HIS-28 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.

Step 5.2.10 Performance Step: 26 Open GTHZ0029 using GT HIS-29.

NOTE: Steps 23 - 26 may be accomplished in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-29.

Comment:

Evaluators Cue: GT HIS-29 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.

Step 5.2.11 Performance Step: 27 Record the date and time the CTMT Purge Exhaust and Mini Purge Exhaust Dampers are opened on the Gaseous Radwaste Release Permit.

Standard: Operator should record the date and time the CTMT Purge Exhaust and Mini Purge Exhaust Dampers are opened on the Gaseous Radwaste Release Permit.

Comment:

Evaluators Cue: The Gaseous Radwaste Release Permit has been updated.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 12 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.12 Performance Step: 28 Inform Count Room Technician when purge initiated.

Standard: Operator should notify the Count Room Technician of the time the purge was initiated.

Comment:

Evaluators Cue: Count Room Technician acknowledges.

Step 5.2.13 Performance Step: 29 When CTMT pressure is less than 10 WG, OPEN GTHZ0041 and GTHZ0042 using GT HIS-41.

Standard: Operator should depress and hold the OPEN pushbutton on GT HIS-41 when CTMT pressure is less than 10 WG.

Comment:

Evaluators Cue: CTMT pressure is less than 10 WG.

GT HIS-41 RED light illuminates and five (5) seconds later, the GREEN light extinguishes.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 13 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.14 Performance Step: 31 When CTMT pressure is less than 4.25 WG, OPEN GTHZ0026 using GT HIS-26.

NOTE: Steps 31 and 32 may be performed in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-26 when CTMT pressure is less than 4.25 WG.

Comment:

Evaluators Cue: CTMT pressure is now 2.5 WG.

GT HIS-26 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.

Step 5.2.14 Performance Step: 32 When CTMT pressure is less than 4.25 WG, OPEN GTHZ0027 using GT HIS-27.

NOTE: Steps 31 and 32 may be performed in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-27 when CTMT pressure is less than 4.25 WG.

Comment:

Evaluators Cue: CTMT pressure is now 2.5 WG.

GT HIS-27 RED light illuminates and three (3) seconds later, the GREEN light extinguishes.

Step 5.2.15 Performance Step: 33 Start SGT02, CTMT Mini Purge Air Supply Unit with GT HIS-23.

Standard: Operator should select RUN on GT HIS-23.

Comment:

Evaluators Cue: GT HIS-23 RED light illuminates and the GREEN light extinguishes.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 14 of 17 Form ES-C-1 PERFORMANCE INFORMATION Step 5.2.16 Performance Step: 34 OPEN GTHZ0005 using GT HIS-5.

NOTE: Steps 34 and 35 may be performed in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-5.

Comment:

Evaluators Cue: GT HIS-5 RED light illuminates and two (2) seconds later, the GREEN light extinguishes.

5.2.17 Performance Step: 35 OPEN GTHZ0004 using GT HIS-4.

NOTE: Steps 34 and 35 may be performed in any order.

Standard: Operator should depress and hold the OPEN pushbutton for GT HIS-4.

Comment:

Evaluators Cue: GT HIS-4 RED light illuminates and two (2) seconds later, the GREEN light extinguishes.

Performance Step: 36 Inform the Control Room Supervisor that CTMT Mini Purge has been reinitiated.

Standard: Operator should inform the Control Room Supervisor that Mini Purge has been reinitiated.

Comment:

Evaluators Cue: Control Room Supervisor acknowledges.

Terminating Cue: When Mini-Purge is reinitiated, this JPM is complete.

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 15 of 17 Form ES-C-1 PERFORMANCE INFORMATION STOP TIME:

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 16 of 17 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM S8 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM S8 NUREG 1021, Revision 9

Appendix C Page 17 of 17 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: Callaway Plant is in Mode 1. A containment mini purge was in progress to prepare for a containment entry. One hour ago, a CPIS/CRVIS occurred due to a spike on GTRE0022. Repairs have been made to GTRE0022 and it is now operable. Outside air temperature is expected to remain > 50°F.

INITIATING CUE: The Control Room Supervisor has directed you to re-initiate the containment mini purge per OTN-GT-00001, Section 4.7. The Control Room Supervisor has decided to not realign the control building HVAC at this time. The SS has authorized reinitiating CTMT mini purge. Inform the Control Room Supervisor when the mini purge has been re-initiated.

2005 NRC JPM S8 NUREG 1021, Revision 9

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