ML100710757: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 08/24/2009
| issue date = 08/24/2009
| title = 2009 Clinton Power Station Initial License Examination Administered Scenarios
| title = 2009 Clinton Power Station Initial License Examination Administered Scenarios
| author name = Valos N A
| author name = Valos N
| author affiliation = NRC/RGN-III/DRS/OB
| author affiliation = NRC/RGN-III/DRS/OB
| addressee name =  
| addressee name =  
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-01 Exam Scenario 1 REVISION 00  
{{#Wiki_filter:Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-01 Exam Scenario 1 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                          /
Operations                      Date


DEVELOPER:
Overview Makeup/Reject:             All CPs except H and J are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                      RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                      N/A Electrical:                6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Tom Pickley 
Radwaste:                  1WF Evap is in operating. A and B RT F/D are in service.
Plant Status On Line Risk Green Reactor Operational Condition:          Mode 1 Total Core Flow:                __70.7___ mlb/hr FCV Position:                  A: __52.8_____%        B: __53.1____%
Reactor Power                  __65__% (<=100%) _2282__ MWt (<=3473)                  _737__ Mwe Xenon:                          Stable RPV Level                      _33_ in Narrow Range RPV Pressure                    _963__ psi (< 1045)
In service SDC loop            None MODE 1 Containment Suppression Pool Temperature:            _75.5_ F                        (<=93.1 F)
Suppression Pool Level                  _19.2_ ft                      (19 ft 0 to 19 ft 5 in)
Drywell Pressure                        _0.8 _ psi                      (0 to 1 psig)
Drywell to Containment dp:              _0.8 _ psi                      >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:            _104_ F                        (<=146.53 F)
Secondary Containment:                  _0.74_ in WG                    (>= 0.25 in WG vacuum)
BOP                                                            Plant Chemistry Condenser Vacuum:                        _28_ in Hg            CPI (goal < 1.1):                1.00 Off - Gas Flow:                          _38.5_scfm            Reactor Sulfates (goal < 2)      1.31 ppb Condensate Temperature:                  _94_ F                Reactor Chlorides:                0.51 ppb Generator Reactive Load:                _228_MVARS            FW Iron (goal < 2.1)              0.85 ppb Protected Equip: None Comments:      See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety


REVIEWED BY:
OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station: Clinton         Valid Date(s): xx/xx/xxxx               Reactivity Maneuver Plan #: C11-Simu.1 Multiple Activations Allowed?           No             (If yes, CRS may make additional copies)
Simulator Instructor
Prepared by:       Joe Top               / xx/xx/xx           Reviewed by:                 Roger Bottom /xx/xx/xx Reactor Engineer     /      Date                           Qualified Nuclear Engineer /     Date Approved by:         Michelle Strange / xx/xx/xx               Authorized by:                               / xx/xx/xx RE Manager           /    Date                             Senior Reactor Operator /     Date NF Review by         Michael Charm               / xx/xx/xx NF Reciewer               /     Date ReMA Activated:                                 / xx/xx/xx     ReMA Terminated:                               / xx/xx/xx Unit Supervisor       /   Date                                   Unit Supervisor     /   Date Title of Evolution: Power Reduction to Removal of A TDRFP Purpose/Overview of Evolution:
 
APPROVED BY:
 
/  Operations Date Overview Makeup/Reject:
All CP's except H and J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste: 1WF Evap is in operating. A and B RT F/D are in service.
Plant Status On Line Risk Green  Reactor  Operational Condition: Mode 1 Total Core Flow: __70.7___ mlb/hr FCV Position: A:  __52.8_____%      B:  __53.1____%
Reactor Power __65__%  (<=100%)    _2282__ MWt  (<=3473)      _737__ Mwe Xenon: Stable RPV Level _33_ in Narrow Range RPV Pressure _963__ psi  (< 1045) In service SDC loop None    MODE 1 Containment Suppression Pool Temperature: _75.5_ F
(<=93.1 F) Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.8 _ psi (0 to 1 psig) Drywell to Containment dp: _0.8 _ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _104_ F
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
BOP  Plant Chemistry Condenser Vacuum: _28_ in Hg CPI (goal < 1.1):
1.00 Off - Gas Flow: _38.5_scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
_94_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load: _228_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
:  None  Comments: See Turnover Sheet
 
From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
 
OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station:
Clinton Valid Date(s):   xx/xx/xxxx     Reactivity Maneuver Plan #: C11-Simu.1
 
Multiple Activations Allowed?     No   (If yes, CRS may make additional copies) Prepared by:
Joe Top                   / xx/xx/xx   Reviewed by:                   Roger Bottom /xx/xx/xx Reactor Engineer       /      Date     Qualified Nuclear Engineer /       Date Approved by:     Michelle Strange / xx/xx/xx Authorized by:   / xx/xx/xx RE Manager           /    Date Senior Reactor Operator /       Date NF Review by     Michael Charm         / xx/xx/xx NF Reciewer               /         Date ReMA Activated:
/ xx/xx/xx ReMA Terminated:
/ xx/xx/xx     Unit Supervisor       /     Date   Unit Supervisor     /       Date Title of Evolution: Power Reduction to Removal of A TDRFP Purpose/Overview of Evolution:
This ReMA is provided for a non emergent load reduction to support removal of the A TDRFP.
This ReMA is provided for a non emergent load reduction to support removal of the A TDRFP.
This ReMA is NOT intended to take the place of emergency load reductions per the guidance of CPS 3005.01, Unit Power Changes. Emergency load reductions shall be implemented per the guidance of CPS 3005.01, Unit Power Changes. Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction 1. Reduce reactor power to 60% with flow 2. Maintain reactor power using rods and flow
This ReMA is NOT intended to take the place of emergency load reductions per the guidance of CPS 3005.01, Unit Power Changes. Emergency load reductions shall be implemented per the guidance of CPS 3005.01, Unit Power Changes.
: 3. 4. General Issues: The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003. Main Steam Line Radiation Monitors may initially show elevated response from crud burst in core (due to rod movements) and from "hydrogen pockets" being swept into the core (due to flow perturbations in the condensate / feedwater piping). Response should diminish as the feedwater system comes to equilibrium.
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction
 
: 1. Reduce reactor power to 60% with flow
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1  of    2                                                    Reactivity Maneuver Plan # C11-Simu.1 Description of Step :
: 2. Maintain reactor power using rods and flow 3.
 
4.
Reduce reactor power to
General Issues:
~ 60% with flow.
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
 
Main Steam Line Radiation Monitors may initially show elevated response from crud burst in core (due to rod movements) and from hydrogen pockets being swept into the core (due to flow perturbations in the condensate /
Rod notching may also be used if necessary to control FCL. The Reactor Engineer will provide
feedwater piping). Response should diminish as the feedwater system comes to equilibrium.
 
guidance on the control rods to be moved to achieve the FCL necessa ry to support operating at 60%.  


OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP      1    of    2                                          Reactivity Maneuver Plan # C11-Simu.1 Description of Step :
Reduce reactor power to ~ 60% with flow.
Rod notching may also be used if necessary to control FCL. The Reactor Engineer will provide guidance on the control rods to be moved to achieve the FCL necessary to support operating at 60%.
It is acceptable to stop at intermediate power levels as necessary to support plant conditions.
It is acceptable to stop at intermediate power levels as necessary to support plant conditions.
_________________________________________________________________________________ Note: Additional monitoring is required per C PS 3005.01, in addition to what is specified below. QNE presence required in the Control Room? Yes No   X* *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
Note: Additional monitoring is required per CPS 3005.01, in addition to what is specified below.
N/A N/A MFLCPR < 0.900 Core Flow (Mlb/hr or %)
QNE presence required in the Control Room? Yes                   No X*
N/A N/AMFLPD < 0.900 FCL (%) < 90.0 % MAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
High Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after completion of power reduction. Contingency: Insert control rods in reverse order sequence to reduce FCL.
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter               Value or Range Init.                 Parameter           Value or Range Init.
90.0 % N/A    Step Complete: ___________________
Core Power (MWth or %)                   N/A             N/A MFLCPR                             < 0.900 Core Flow (Mlb/hr or %)                 N/A             N/A MFLPD                              < 0.900 FCL (%)                               < 90.0 %                   MAPRAT                           N/A         N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                         High             Low FCL                                                                                   90.0 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after completion of power reduction.
/_______         Verified by: _________________
Contingency: Insert control rods in reverse order sequence to reduce FCL.
/_______                                         Reactor Operator       /     Date                                             Unit Supervisor           /     Date    
Step Complete: ___________________/_______                       Verified by: _________________/_______
Reactor Operator       /   Date                         Unit Supervisor     / Date


OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    2 of    2                                                   Reactivity Maneuver Plan # C11-Simu.1 Description of Step :
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    2     of    2                                       Reactivity Maneuver Plan # C11-Simu.1 Description of Step :
Maintain target power level using available flow. Rod notching ma y also be used, as needed, to maintain power level. The Reactor Engineer will provide guidance on when to notch control rods.
Maintain target power level using available flow. Rod notching may also be used, as needed, to maintain power level. The Reactor Engineer will provide guidance on when to notch control rods.
QNE presence required in the Control Room? Yes _
QNE presence required in the Control Room? Yes _ _ No X*
_ No X*
* RE Coverage will be provided consistent with OP-AB-300-1003 and NF-AB-701.
* RE Coverage will be provided consistent with OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %) ~60%  (~2084 MWt)
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter               Value or Range Init.               Parameter             Value or Range   Init.
MFLCPR N/A N/ACore Flow (Mlb/hr or %)
                                      ~60%                                                    N/A        N/A Core Power (MWth or %)                                     MFLCPR
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/A     Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
(~2084 MWt)
High Low           Step Complete: ___________________
Core Flow (Mlb/hr or %)               N/A           N/A MFLPD                              N/A         N/A FCL (%)                               N/A           N/A MAPRAT                              N/A         N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                     High             Low Step Complete: ___________________/_______                   Verified by: _________________/_______
/_______         Verified by: _________________
Reactor Operator     / Date                       Unit Supervisor   / Date
/_______                                         Reactor Operator       /     Date                                             Unit Supervisor           /     Date    


FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP 03476951042138917372084 2431 2778312634730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)
FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0         10         20       30         40         50       60         70           80       90           100              110 3473                                                                                                                                      100 MELLLA Limit [100.7% FCL]
THERMAL POWER -  MWTh 0
3126                                                                                                                                      90 Restricted                                                                                    90% FCL (Typ.)
10 20 30 40 50 60 70 80 901000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWE RRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE  60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND    < 60% FLOW]90% FCL (Typ.) 80%25868MELLLA Limit  [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]
2778              Zone                                                                                        80%
 
80 THERMAL POWER - MWTh 2431                                                                                                                                      70 PERCENT THERMAL POWER 2084                                                                                                                                      60 60%
Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
CON T R OLLE D 1737                                                                                                                                      50 E N T R Y R E GION 50%
One                    Operating Test No.:
1389                                                                                                                                      40 40%
08-01  Examiners: ____________________________  Operators: ____________________          ____________________________           
1042                                                                                                                                      30 868                                                                                                                                      25 695                                                                                                                                      20 OPRM ENABLED          CAVITATION 347                                                                              REGION          PROTECTION LINES                      10 OPRM OPERABLE
 
[21.6 % CTP, 750 MWth]                       SINGLE LOOP        [> 25% CTP AND        (HIGH SPEED, 2 PUMP ENVELOPE            < 60% FLOW]        OPERATION) 0                                                                                                                                        0 0.0        8.5        16.9    25.4      33.8      42.3      50.7      59.2      67.6        76.1         84.5              93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)
____________________
____________________________                    ____________________
 
Initial Conditions: 


Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station            Scenario No.: One              Operating Test No.: 08-01 Examiners: ____________________________                            Operators: ____________________
Initial Conditions:
65% power, Drywell pressure is high.
65% power, Drywell pressure is high.
Thunderstorm storms are expected in the area within the next hour.  
Thunderstorm storms are expected in the area within the next hour.
 
Turnover:
Turnover:
: 1. Run 'B' mixer to reduce DW pressure - First Priority
: 1. Run B mixer to reduce DW pressure - First Priority
: 2. Power needs lowered to 60% power to remove the 'A' RFPT from service for a scheduled outage due to problems.
: 2. Power needs lowered to 60% power to remove the A RFPT from service for a scheduled outage due to problems.
Event No. Malf. No.
Event       Malf. No. Event                                       Event No.                    Type*                                     Description 1       HVAC_SP       N-BOP       Reduce DW pressure, B mixer trips, entry into ITS.
Event Type* Event Description 1 HVAC_SP ARE_L3 1 N-BOP TS-CRS Reduce DW pressure, 'B' mixer trips, entry into ITS.
ARE_L3 1 TS-CRS 2       NA             R-ATC       Power reduction to support removal of A TDRFP 3       Override       C-ATC       A TDRFP trouble alarm 4       Override       C-ATC       B RWCU pump seal plate temperature high 5       YP_XMFT        TS-CRS       A APRM fails downscale.
2 NA R-ATC Power reduction to support removal of 'A' TDRFP 3 Override       C-ATC 'A' TDRFP trouble alarm 4 Override C-ATC 'B' RWCU pump seal plate temperature high 5 YP_XMFTB_4912 1 TS-CRS 'A' APRM fails downscale.
B_4912 1 6       YFFWPPS       C-BOP       B MC pump coupling fails S_13 1 7       YPXMALS       C-BOP       Fuel failure E_1 8       YP_XMFT        M-ALL       Debris in the Condenser causes all CD pumps to trip B_4068, 69, 70, 71 9       RR03           M-ALL       A small RR leak occurs in the Drywell 10       YFRIPPSS       M-ALL       The RCIC shaft breaks 11       YP_XMFT        M-ALL       HPCS Injects and then trips B_4103
6 YFFWPPS S_13 1 C-BOP 'B' MC pump coupling fails 7 YPXMALS E_1 C-BOP Fuel failure 8 YP_XMFTB_4068, 69, 70, 71 M-ALL Debris in the Condenser causes all CD pumps to trip 9 RR03 M-ALL A small RR leak occurs in the Drywell 10 YFRIPPSS M-ALL The RCIC shaft breaks 11 YP_XMFTB_4103 M-ALL HPCS Injects and then trips *(N)ormal,   (R)eactivity,   (I)nstrument,   (C)omponent,   (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Page 2 of 2 Scenario No.:
*(N)ormal,     (R)eactivity,   (I)nstrument,   (C)omponent,     (M)ajor Page 1 of 2
One                          Operating Test No.:
08-01  Narrative Summary
 
Event # Description
: 1. Drywell pressure is high requiring the BOP to run 'B' mixing compressor to reduce Drywell pressure. Operational Requirement Manual action 3.5.2 for the test Prep switch entered. The mixing compressor trips and the CRS enters ITS
 
3.6.3.3. 2. Power is reduced with recirculation flow to allow removal of the RFPT.
: 3. 'A' TDRFP experiences a trouble alarm on a thrust bearing wear condition requiring tripping of the 'A' TDRFP. This will require verification that the running 'B' TDRFP is adequately maintaining level. A RR FCV runback will require entry to CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core


Stability Control to verify no core instabilities along with entry into CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power
Appendix D                                Scenario Outline                              Form ES-D-1 Scenario No.: One                                                Operating Test No.: 08-01 Narrative Summary Event #                                      Description
: 1. Drywell pressure is high requiring the BOP to run B mixing compressor to reduce Drywell pressure. Operational Requirement Manual action 3.5.2 for the test Prep switch entered. The mixing compressor trips and the CRS enters ITS 3.6.3.3.
: 2. Power is reduced with recirculation flow to allow removal of the RFPT.
: 3. A TDRFP experiences a trouble alarm on a thrust bearing wear condition requiring tripping of the A TDRFP. This will require verification that the running B TDRFP is adequately maintaining level. A RR FCV runback will require entry to CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control to verify no core instabilities along with entry into CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power
: 4. RWCU pump B develops a seal leak requiring its removal from service.
: 4. RWCU pump B develops a seal leak requiring its removal from service.
: 5. 'A' APRM fails down scale entry into ITS 3.3.1.1 and OPRM ITS 3.3.1.3.
: 5. A APRM fails down scale entry into ITS 3.3.1.1 and OPRM ITS 3.3.1.3.
: 6. 'B' MC pump coupling fails results in the loss of makeup condensate. This requires the startup of the standby pump.
: 6. B MC pump coupling fails results in the loss of makeup condensate. This requires the startup of the standby pump.
: 7. Fuel clad failure will require entry to the CPS 4010.01. Subsequent activities will  
: 7. Fuel clad failure will require entry to the CPS 4010.01. Subsequent activities will require the BOP to shut valves RE021&22, RF021&22, along with other activities.
8, 9, 10 & 11. Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps. A small RR loop leak occurs and the RCIC shaft breaks and HPCS injects and then trips. A Blowdown is performed at TAF and level is recovered with Low Pressure ECCS.
EOPS 1,3,6 Critical tasks:
* Emergency Depressurize when less than TAF.
* Recover level to above TAF.
Page 2 of 2


require the BOP to shut valves RE021&22, RF021&22, along with other
D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                      08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
(Plant power level) 65% Power/70% FCL                                      CPS 3005.01 thru step 8.2.9 2312 MWt                                              A-2, step 36 is complete 747 MWe 70.7 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Reactor Power has been reduced to 65% and is scheduled to continue to 60% with RR FCVs to allow for RFPT 1A removal from service for maintenance to work on some problems.
Existing LCOs, date of next surveillance None Surviellances or major maintenance CPS 9014.01 RPC Sys W/D Limitation Test was completed SAT last month.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.
Online Safety is Green                                Containment pressure is 0.3 psig First Priority - Run B mixer to reduce DW            Lower power to 60% with flow within pressure (lowest run time).                            the next hour to support removal of A Per Cumulative Date 9094.01D001for this                TDRFP.
month: A Mixer run time is 4 hrs 52 minutes B Mixer run time is 5 minutes Cumulative data will be taken care of by the WCS 1


activities.
D-2, Dynamic Simulator Scenario 1             EXAM DATE: 08-24-09                         08-01 Operator Actions Event No.(s):         1                                                                   Page   1 of 1
8, 9, 10 & 11. Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps. A small RR loop leak occurs and the RCIC shaft breaks and HPCS injects and then trips. A Blowdown is performed at TAF and level is
 
recovered with Low Pressure ECCS.
EOPS 1,3,6 Critical tasks:  Emergency Depressurize when less than TAF. Recover level to above TAF.
 
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 1  Shift Turnover Information  Day of week and shift  Today Day Shift  Weather conditions Thunderstorms are expected in the area within the next hour.  (Plant power level)  65% Power/70% FCL  CPS 3005.01 thru step 8.2.9  2312 MWt  A-2, step 36 is complete  747 MWe    70.7 Mlbm/hr CORE FLOW    Thermal Limit Problems/Power Evolutions Reactor Power has been reduced to 65% and is scheduled to continue to 60%  with RR FCVs to allow for RFPT 1A removal from service for maintenance to work on some problems.            Existing LCOs, date of next surveillance  None        Surviellances or major maintenance  CPS 9014.01 RPC Sys W/D Limitation Test was completed SAT last month.            Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment          Comments, evolutions, problems, etc.
Online Safety is Green  First Priority  - Run 'B' mixer to reduce DW pressure (lowest run time).
Per Cumulative Date 9094.01D001for this month: 'A' Mixer run time is 4 hrs 52 minutes
                      'B' Mixer run time is 5 minutes  Cumulative data will be taken care of by the WCS  Containment pressure is 0.3 psig  Lower power to 60% with flow within the next hour to support removal of A TDRFP.
D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                    08-01 2  Operator Actions Event No.(s):
1 Page 1 of 1
 
== Description:==
 
Reduce Drywell pressure Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP Per CPS 3316.01, Containment Combustible Gas Control, step 8.3: Places MOV Test Prep Switch for CGCS Div 2 to Test and notes time.
: 1.        Start CGCS Hydrogen Cmpr 1B, 1HG02CB. Record start time IAW CPS 9094.01D001 2. Verify 1HG009B, CGCS Cmpr 1B Suct Vlv opens.
 
At DW pressure of .6 psig the B Mixer will trip off.


==
Description:==
Reduce Drywell pressure Initiation: Following shift turnover Cues: Directed by SRO Time      Position                              Applicants Actions or Behavior BOP      Per CPS 3316.01, Containment Combustible Gas Control, step 8.3:
Places MOV Test Prep Switch for CGCS Div 2 to Test and notes time.
: 1.      Start CGCS Hydrogen Cmpr 1B, 1HG02CB.
* Record start time IAW CPS 9094.01D001
: 2.      Verify 1HG009B, CGCS Cmpr 1B Suct Vlv opens.
At DW pressure of .6 psig the B Mixer will trip off.
SECURING DRYWELL VENTING
SECURING DRYWELL VENTING
: 1. Stop CGCS Hydrogen Cmpr 1B, 1HG02CB. Record stop time IAW CPS 9094.01D001 2. Verify 1HG009A(B), CGCS Cmpr1B Suct Vlv shuts. (If the control switch is not taken to stop the suction valve will remain open)  
: 1.       Stop CGCS Hydrogen Cmpr 1B, 1HG02CB.
* Record stop time IAW CPS 9094.01D001
: 2.       Verify 1HG009A(B), CGCS Cmpr1B Suct Vlv shuts. (If the control switch is not taken to stop the suction valve will remain open)
* Places MOV Test Prep Switch for CGCS Div 2 into NORMAL and notes time.
RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Applies ORM ACTION 3.5.2 for MOV Test Prep Switch for CGCS Div 2
* Enters ITS 3.6.3.3 A.1 for B Mixer.
Terminus: D/W Venting is completed and ITS call completed NOTES:
2


Places MOV Test Prep Switch for CGCS Div 2 into NORMAL and notes time.
D-2, Dynamic Simulator Scenario 1             EXAM DATE: 08-24-09                         08-01 Operator Actions Event No.(s):               2                                                             Page   1 of 1
RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Applies ORM ACTION 3.5.2 for MOV Test Prep Switch for CGCS Div 2  Enters ITS 3.6.3.3 A.1 for B Mixer.
Terminus:  D/W Venting is completed and ITS call completed NOTES:
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 3  Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
==
Description:==
Power reduction to support removal of the A RFPT turbine Initiation: Following D/W Venting and ITS call.
Power reduction to support removal of the A RFPT turbine Initiation: Following D/W Venting and ITS call.
Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per CPS 3005.01, Unit Power Changes, step 8.2.8.
Cues: Directed by SRO Time     Position                                 Applicants Actions or Behavior Per CPS 3005.01, Unit Power Changes, step 8.2.8.
Reduce power with Flow to ~60%.
RO
BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Reduce power with Flow to ~60%.
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
BOP
Terminus: Clearly observable plant response from change in power level.  
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
Terminus: Clearly observable plant response from change in power level.
NOTES:
3


NOTES:
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                         08-01 Operator Actions Event No.(s):           3                                                                 Page   1 of 1
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 4  Operator Actions Event No.(s):
3 Page 1 of 1


== Description:==
==
'A' TDRFP trouble alarm Initiation: Following the power reduction, on the signal of lead examiner Cues: Annunciator 5002-1B alarms , report from field operator Time Position Applicant's Actions or Behavior RO Per CPS 5002-1B, RFP 1A trouble: Trips the  
Description:==
'A' TDRFP due to high thrust bearing wear Observes Low Level Alarm and RR FCV runback Per CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, monitor for: Entry to the restricted zone Core Instabilities power operating Map CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power As necessary, Start/stop Condensate, Condensate Booster or Reactor Feedwater pumps in support of level control.
A TDRFP trouble alarm Initiation: Following the power reduction, on the signal of lead examiner Cues: Annunciator 5002-1B alarms , report from field operator Time     Position                                   Applicants Actions or Behavior RO       Per CPS 5002-1B, RFP 1A trouble:
Maintain adequate NPSH to the Feed Pumps (> 320 psig)
* Trips the A TDRFP due to high thrust bearing wear
BOP Dispatches a field operator   Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Observes Low Level Alarm and RR FCV runback Per CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, monitor for:
SRO Enters CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, Directs actions listed above. Enters CPS 4002.01, Abnormal RPV Level/Lo ss of Feedwater At Power, Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
* Entry to the restricted zone
* Core Instabilities power operating Map CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power
* As necessary, Start/stop Condensate, Condensate Booster or Reactor Feedwater pumps in support of level control.
* Maintain adequate NPSH to the Feed Pumps (> 320 psig)
BOP
* Dispatches a field operator
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, Directs actions listed above.
* Enters CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power, Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
o Contacts Shift Manager and recommends notifications.
o Contacts Shift Manager and recommends notifications.
Terminus: 'A' TDRFP tripped and RPV level stabilized NOTES: TO EVALUATORS: If computer points FW-BC902 and or FW-BC903 are called up on DCS, inform the operators they both indicate High. (This is a limitation of the simulator.)  
Terminus: A TDRFP tripped and RPV level stabilized NOTES:
TO EVALUATORS: If computer points FW-BC902 and or FW-BC903 are called up on DCS, inform the operators they both indicate High. (This is a limitation of the simulator.)
4


D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 5  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 1             EXAM DATE: 08-24-09                         08-01 Operator Actions Event No.(s):       4                                                                   Page   1 of 1
4 Page 1 of 1


== Description:==
==
RWCU Pump seal plate temperature high Initiation: Upon resolution of the FW transient on the signal of the lead evaluator Cues: Annunciator CPS 5000-2E alarms Time Position Applicant's Actions or Behavior RO Per CPS 3303.01, RWCU step 8.1.4 and 8.1.3: Direct field Operator to remove all Filter demins from service Open the F/D bypass valve Shutdown RWCU pump 'B'  Place one F/D in service BOP Dispatches a field operator to support RWCU operation Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Description:==
SRO Enters CPS 3303.01 Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
RWCU Pump seal plate temperature high Initiation: Upon resolution of the FW transient on the signal of the lead evaluator Cues: Annunciator CPS 5000-2E alarms Time     Position                                 Applicants Actions or Behavior RO     Per CPS 3303.01, RWCU step 8.1.4 and 8.1.3:
* Direct field Operator to remove all Filter demins from service
* Open the F/D bypass valve
* Shutdown RWCU pump B
* Place one F/D in service BOP
* Dispatches a field operator to support RWCU operation
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 3303.01 Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
o Contacts Shift Manager and recommends notifications.
o Contacts Shift Manager and recommends notifications.
Terminus: RWCU pump has been shutdown IAW CPS 3303.01 NOTES:
Terminus: RWCU pump has been shutdown IAW CPS 3303.01 NOTES:
D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                    08-01 6  Operator Actions Event No.(s):
5
5 Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 1              EXAM DATE: 08-24-09                          08-01 Operator Actions Event No.(s):        5                                                                    Page    1  of 1
Failure of 'A 'APRM Initiation: RWCU pump has been shutdown IAW CPS 3303.01, on the signal of lead examiner Cues: Annunciator 5060-8E Time Position Applicant's Actions or Behavior BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
 
RO Acknowledges and announces 'A' AP RM annunciator and reading Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any additional unusual or unexpected conditions.
==
SRO Directs actions listed above. Declares 'A' APRM Inop per ITS 3.3.1.1 A.1 and 'A' OPRM Inop per ITS 3.3.1.3.A.1 or A.2 or A.3.
Description:==
Complies with action statement(s) for T.S. Section o May direct going to Sensor Bypass for Div 1. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Failure of A APRM Initiation: RWCU pump has been shutdown IAW CPS 3303.01, on the signal of lead examiner Cues: Annunciator 5060-8E Time     Position                                 Applicants Actions or Behavior BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
RO
* Acknowledges and announces A APRM annunciator and reading
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any additional unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Declares A APRM Inop per ITS 3.3.1.1 A.1 and A OPRM Inop per ITS 3.3.1.3.A.1 or A.2 or A.3.
* Complies with action statement(s) for T.S. Section o May direct going to Sensor Bypass for Div 1.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
o Contacts Shift Manager and recommends notifications.
o Contacts Shift Manager and recommends notifications.
Terminus: SRO has addressed ITS requirements.
Terminus: SRO has addressed ITS requirements.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                    08-01 7  Operator Actions Event No.(s):
6
6 Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 1            EXAM DATE: 08-24-09                        08-01 Operator Actions Event No.(s):        6                                                                Page    1    of    1
MC pump "B" coupling fails Initiation: SRO has addressed I.T.S. requirements, on the signal of lead examiner Cues: Annunciator CPS 5014-2C alarming Time Position Applicant's Actions or Behavior BOP Per CPS 3208.01 MC/CY, STEP 8.1.1.1 (or 8.2.2): Direct shutting the discharge valve and reopen upon pump start (if section 8.1.1.1 is used). Start up the standby pump Shutdown the failed pump RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
 
SRO Directs actions listed above. Enforces OPS expectations and standards.
==
Description:==
MC pump B coupling fails Initiation: SRO has addressed I.T.S. requirements, on the signal of lead examiner Cues: Annunciator CPS 5014-2C alarming Time     Position                               Applicants Actions or Behavior BOP     Per CPS 3208.01 MC/CY, STEP 8.1.1.1 (or 8.2.2):
* Direct shutting the discharge valve and reopen upon pump start (if section 8.1.1.1 is used).
* Start up the standby pump
* Shutdown the failed pump RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Enforces OPS expectations and standards.
o Contacts Shift Manager.
o Contacts Shift Manager.
Terminus: Standby Pump started and shutdown of the failed pump  
Terminus: Standby Pump started and shutdown of the failed pump NOTES:
7


NOTES:
D-2, Dynamic Simulator Scenario 1             EXAM DATE: 08-24-09                         08-01 Operator Actions Event No.(s):         7                                                                   Page     1   of   1
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 8  Operator Actions Event No.(s):
7 Page 1 of 1


== Description:==
==
 
Description:==
Fuel failure Initiation: After crew has started an other MC pump, on the signal of lead examiner Cues: OG pretreat alarming, MSL rad monitors trending up Time Position Applicant's Actions or Behavior BOP Per CPS 4010.01, Reactor Coolant Hi Activity, Sub. Action: Sound the CNMT evacuation alarm. Shut: 1RE021, EQ Drain Sump Disch CNMT Inbd Vlv. 1RE022, EQ Drain Sump Disch CNMT Outbd Vlv. 1RF021, Flr Drain Sump Disch CNMT Inbd Vlv. 1RF022, Flr Drain Sump Disch CNMT Outbd Vlv.
Fuel failure Initiation: After crew has started an other MC pump, on the signal of lead examiner Cues: OG pretreat alarming, MSL rad monitors trending up Time     Position                                 Applicants Actions or Behavior BOP       Per CPS 4010.01, Reactor Coolant Hi Activity, Sub. Action:
* Sound the CNMT evacuation alarm.
* Shut:
* 1RE021, EQ Drain Sump Disch CNMT Inbd Vlv.
* 1RE022, EQ Drain Sump Disch CNMT Outbd Vlv.
* 1RF021, Flr Drain Sump Disch CNMT Inbd Vlv.
* 1RF022, Flr Drain Sump Disch CNMT Outbd Vlv.
CPS 3408.01 VR/VQ, Step 8.1.1.2:
CPS 3408.01 VR/VQ, Step 8.1.1.2:
o Shift CNMT Building HVAC System to Continuous CNMT Purge Filtered mode RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
o Shift CNMT Building HVAC System to Continuous CNMT Purge Filtered mode RO
SRO Enters CPS 4010.01, Reactor Coolant Hi Activity, and directs actions listed above. Directs Chemistry to sample the Reactor Coolant Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 4010.01, Reactor Coolant Hi Activity, and directs actions listed above.
* Directs Chemistry to sample the Reactor Coolant
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
o Contacts Shift Manager and recommends notifications.
o Contacts Shift Manager and recommends notifications.
Terminus: Valves shut, SRO has entered CPS 4010.01 and directed actions accordingly.
Terminus: Valves shut, SRO has entered CPS 4010.01 and directed actions accordingly.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 Operator Actions Event No.(s): 8, 9,10,11 Page 1 of 2
8
 
D-2, Dynamic Simulator Scenario 1             EXAM DATE: 08-24-09                               08-01 Operator Actions Event No.(s):           8, 9,10,11                                                           Page   1   of   2


== Description:==
== Description:==
Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps and small RR leak. Initiation:
Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps and small RR leak.
After Fuel Failure has been addressed, on the signal of lead examiner Cues: All Condensate and Feedwater pumps trip Time Position Applicant's Actions or Behavior RO Inserts a manual scram CPS 4100.01, Reactor Scram: Place mode switch in Shutdown Check and report power 1% and trending down Check rods, reports shutdown criteria is met Report level and pressure are following expected trends Verify turbine and generator are tripped Stabilize pressure <1065 psig Performs EOP/ON actions as directed by SRO Coordinates with BOP operator to monitor and control RPV press BOP Makes plant announcement for reactor scram and evacuate the containment Coordinates with RO to monitor and control RPV press Evacuate the Containment Performs EOP/ON actions as directed by SRO Reports HPCS Injection and trip Reports RCIC will not inject Maximize CRD   Inject with SLC Initiates ADS verifies 7 ADS valves are open Maximizes injection and restores level above TAF Critical Task NOTES:       Critical Task 9
Initiation: After Fuel Failure has been addressed, on the signal of lead examiner Cues: All Condensate and Feedwater pumps trip Time     Position                               Applicants Actions or Behavior RO     Inserts a manual scram CPS 4100.01, Reactor Scram:
D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                    08-01 Event No.(s): 8, 9,10 Unisolable main steam line Page 2 of 2 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-1, EOP-6 for high drywell pressure a nd  EOP-3 (Blowdown) actions as entry conditions are met. Directs Stabilize pressure below 1065 psig  Hold level above TAF  Maximize CRD  Inject with SLC When RPV water level is less than TAF, directs entry into EOP-3 and EOP actions:  Initiation of ADS  verify 7 ADS valves are open Terminus:
Critical Task
Reactor scrammed  ADS has been initiated  Level restored above TAF  Upon approval of lead examiner Critical Task NOTES:          10 D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                    08-01 11  Simulator Operator Instructions
* Place mode switch in Shutdown
* Check and report power 1% and trending down
* Check rods, reports shutdown criteria is met
* Report level and pressure are following expected trends
* Verify turbine and generator are tripped
* Stabilize pressure <1065 psig Performs EOP/ON actions as directed by SRO
* Coordinates with BOP operator to monitor and control RPV press BOP
* Makes plant announcement for reactor scram and evacuate the containment
* Coordinates with RO to monitor and control RPV press
* Evacuate the Containment Performs EOP/ON actions as directed by SRO
* Reports HPCS Injection and trip
* Reports RCIC will not inject
* Maximize CRD
* Inject with SLC Critical Task
* Initiates ADS
* verifies 7 ADS valves are open
* Maximizes injection and restores level above TAF NOTES:
9


Initial Setup
D-2, Dynamic Simulator Scenario 1          EXAM DATE: 08-24-09                        08-01 Event No.(s):          8, 9,10                  Unisolable main steam line          Page    2  of 2 Time    Position                                Applicants Actions or Behavior SRO    Directs entry into EOP-1, EOP-6 for high drywell pressure and EOP-3 (Blowdown) actions as entry conditions are met.
* Directs Stabilize pressure below 1065 psig
* Hold level above TAF
* Maximize CRD
* Inject with SLC Critical Task      When RPV water level is less than TAF, directs entry into EOP-3 and EOP actions:
* Initiation of ADS
* verify 7 ADS valves are open Terminus:
* Reactor scrammed
* ADS has been initiated
* Level restored above TAF
* Upon approval of lead examiner NOTES:
10
 
D-2, Dynamic Simulator Scenario 1                EXAM DATE: 08-24-09                            08-01 Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to IC-41 (Verify/Adjust Power to 65% with rods and/or flow to match turnover). Make sure DW pressure is up to ~1.0 psig built into the initial conditions or the Lesson plan Ensure B MC pump is running B RT pump is running. A TDRFP is running.
: 2. Reset to IC-41 (Verify/Adjust Power to 65% with rods and/or flow to match turnover).
* Make sure DW pressure is up to ~1.0 psig built into the initial conditions or the Lesson plan
* Ensure B MC pump is running
* B RT pump is running.
* A TDRFP is running.
: 3. Load the lesson plan for this scenario.
: 3. Load the lesson plan for this scenario.
: 4. Place simulator in RUN
: 4. Place simulator in RUN
Line 231: Line 316:
: 8. Identify T/S issues associated with OOS and turnover
: 8. Identify T/S issues associated with OOS and turnover
: 9. Ensure PR001 is on service and PR002 is in Standby. (Main Stack monitors).
: 9. Ensure PR001 is on service and PR002 is in Standby. (Main Stack monitors).
1 0. Ensure PR012 is operating / in-service. (If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. This is a limitation discovered during ITR/Validation of scenario, PR012 won't auto start and can't be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)
: 10. Ensure PR012 is operating / in-service. (If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. This is a limitation discovered during ITR/Validation of scenario, PR012 wont auto start and cant be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)
1 1. Verify simulator conditions match the turnover 1 2. Provide a copy of CPS 3005.01, signing for step 8.2.9.
: 11. Verify simulator conditions match the turnover
1 3. Fill out plant status and have Turnover Sheet ready for the crew.
: 12. Provide a copy of CPS 3005.01, signing for step 8.2.9.
1 4. Provide pull sheets, REMA, Re instructions and Cram Instructions.
: 13. Fill out plant status and have Turnover Sheet ready for the crew.
D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 12  Event Triggers and Role Play If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. (This is a limitation discovered during ITR/Validation of scenario, PR012 won't auto start and can't be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)
: 14. Provide pull sheets, REMA, Re instructions and Cram Instructions.
Event # 1. Lower DW pressure.
11
 
D-2, Dynamic Simulator Scenario 1                 EXAM DATE: 08-24-09                               08-01 Event Triggers and Role Play If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. (This is a limitation discovered during ITR/Validation of scenario, PR012 wont auto start and cant be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)
Event #
: 1. Lower DW pressure.
: a. No trigger. Activates when D/W pressure is less than .6 psig.
: a. No trigger. Activates when D/W pressure is less than .6 psig.
: b. Role play - To support this evolution. If sent to B Mixer it appears fine. If sent to B Mixer breaker it is tripped and has a bad smell. NO FIRE.
: b. Role play - To support this evolution. If sent to B Mixer it appears fine. If sent to B Mixer breaker it is tripped and has a bad smell. NO FIRE.
Line 242: Line 331:
: 2. Power reduction to support removal of a RFPT turbine
: 2. Power reduction to support removal of a RFPT turbine
: a. No triggers
: a. No triggers
: 3. 'A' TDRFP trouble alarm
: 3. A TDRFP trouble alarm
: a. Remote trigger 1
: a. Remote trigger 1
: b. Role Play- field Operator that 43 psig on Thrust Bearing Wear Pressure at 1PL76JA and starting to hear unusual sounds from 'A' TDRFP.
: b. Role Play- field Operator that 43 psig on Thrust Bearing Wear Pressure at 1PL76JA and starting to hear unusual sounds from A TDRFP.
: c. TO EVALUATORS / Booth Operators: If computer points FW-BC902 and or FW-BC903 are called up on PPC, inform the operators they both indicate High. (This is a limitation of the simulator.)
: c. TO EVALUATORS / Booth Operators: If computer points FW-BC902 and or FW-BC903 are called up on PPC, inform the operators they both indicate High. (This is a limitation of the simulator.)
: d. Role Play for Chemistry, RP and RE.
: d. Role Play for Chemistry, RP and RE.
: 4. 'B' RT pump seal plate temperature high
: 4. B RT pump seal plate temperature high
: a. Remote trigger 2 on request from lead evaluator
: a. Remote trigger 2 on request from lead evaluator
: b. Role play field operator that 'B' RT pump seal temperature is 285 degrees and rising slowly. The CCW is lined up to this pump and the other 'A' RT pump is at 175 degrees and stable. No steam in the room.
: b. Role play field operator that B RT pump seal temperature is 285 degrees and rising slowly. The CCW is lined up to this pump and the other A RT pump is at 175 degrees and stable. No steam in the room.
: c. Remote trigger 7 to remove RT F/D 'A', Remote trigger 8 to remove RT F/D 'B'.
: c. Remote trigger 7 to remove RT F/D A, Remote trigger 8 to remove RT F/D B.
: d. Remote trigger 9 to place on service RT F/D 'A', Remote trigger 10 to place on service RT F/D 'B'
: d. Remote trigger 9 to place on service RT F/D A, Remote trigger 10 to place on service RT F/D B
: 5. 'A' APRM fails down scale
: 5. A APRM fails down scale
: a. Remote trigger 3 on request from lead evaluator
: a. Remote trigger 3 on request from lead evaluator
: b. Role play as C/I if requested, investigating. Will come up with troubleshooting plan.
: b. Role play as C/I if requested, investigating. Will come up with troubleshooting plan.
: 6. 'B' MC pump coupling fails. a. Remote trigger 4 on request from lead evaluator
: 6. B MC pump coupling fails.
: b. Role Play - 'B' MC coupling is failed and support the startup of the 'A' MC pump.
: a. Remote trigger 4 on request from lead evaluator
: b. Role Play - B MC coupling is failed and support the startup of the A MC pump.
: 7. Fuel failure
: 7. Fuel failure
: a. Remote trigger 5 on request from lead evaluator
: a. Remote trigger 5 on request from lead evaluator
: b. Role Play - 'If requested Primary to secondary Ctnt d/p is .0125 psid.
: b. Role Play - If requested Primary to secondary Ctnt d/p is .0125 psid.
: c. Role Play - As Chemistry and RP is called.
: c. Role Play - As Chemistry and RP is called.
: d. If back panels are checked, inform operators all MSL Rads are tracking together.
: d. If back panels are checked, inform operators all MSL Rads are tracking together.
12


D-2, Dynamic Simulator Scenario 1               EXAM DATE: 08-24-09                   08-01 13  8. Loss of all Condensate Pumps
D-2, Dynamic Simulator Scenario 1         EXAM DATE: 08-24-09   08-01
: 8. Loss of all Condensate Pumps
: a. Remote trigger 6 on request from lead evaluator.
: a. Remote trigger 6 on request from lead evaluator.
: b. After 2 minutes from scram announcement go to MCR as IMD.  
: b. After 2 minutes from scram announcement go to MCR as IMD.
13


Procedures Used During Simulator Scenario # 1 (List of Annunciators on back of page)
Procedures Used During Simulator Scenario # 1 (List of Annunciators on back of page)
: 1. EOP-1 2. EOP-3 3. EOP-9 4. 3316.01 CCGS
: 1. EOP-1
: 2. EOP-3
: 3. EOP-9
: 4. 3316.01 CCGS
: 5. ITS/ORM/ODCM
: 5. ITS/ORM/ODCM
: 6. 3005.01 Unit Power Changes
: 6. 3005.01 Unit Power Changes
: 7. 4008.01 O/N
: 7. 4008.01 O/N
: 8. 4100.02 O/N
: 8. 4100.02 O/N
: 9. 4002.01 O/N
: 9. 4002.01 O/N
: 10. 3303.01 RT
: 10. 3303.01 RT
: 11. 3208.01 MC/CY
: 11. 3208.01 MC/CY
: 12. 4010.01 O/N
: 12. 4010.01 O/N
: 13. 3408.01 VR/VQ
: 13. 3408.01 VR/VQ
: 14. 4100.01 O/N
: 14. 4100.01 O/N
: 15. 4001.02 O/N
: 15. 4001.02 O/N
: 16. 4979.01 O/N
: 16. 4979.01 O/N
: 17. 4411.03 18. 4411.09
: 17. 4411.03
: 18. 4411.09
: 19. Annuciators:
: 19. Annuciators:
5002-1B, 1C, 2Q, 4G 5000-2E, 2C 5060-8E 5014-2C 5041-7H,1C 5041-1c, 7H 5031-1G 5003-1D/E 5006-3D 5015-1A-M, 4C-M 5016-1G 5000-2C/E/F 5043-2A, 1G 5042-5H 5043-1G 5067-3E/F, 2L 5013-3A, 4E 5064-3C/D, 4C/D 5130-1G, 2G 5004-1L 5006-3D, 2H 5062-8E All alarms after the Scram
* 5002-1B, 1C, 2Q, 4G
* 5000-2E, 2C
* 5060-8E
* 5014-2C
* 5041-7H,1C
* 5041-1c, 7H
* 5031-1G
* 5003-1D/E
* 5006-3D
* 5015-1A-M, 4C-M
* 5016-1G
* 5000-2C/E/F
* 5043-2A, 1G
* 5042-5H
* 5043-1G
* 5067-3E/F, 2L
* 5013-3A, 4E
* 5064-3C/D, 4C/D
* 5130-1G, 2G
* 5004-1L
* 5006-3D, 2H
* 5062-8E
* All alarms after the Scram


Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00  
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                          /
Operations                      Date


DEVELOPER:
Overview Makeup/Reject:             CPs B,C,D,E and F are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                      RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                      N/A Electrical:                6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Tom Pickley   
Radwaste:                  1WF Evap is in Hot Standby. A and B RT F/D are in service.
Plant Status On Line Risk Green Reactor Operational Condition:          Mode 1 Total Core Flow:                _32.4_ mlb/hr FCV Position:                  A: __90___%        B: __90__%
Reactor Power                  _27_% (<=100%) _919_ MWt (<=3473)                _244_ Mwe Xenon:                          Stable RPV Level                      _29_ in Narrow Range RPV Pressure                    _929_ psi (< 1045)
In service SDC loop            None MODE 1 Containment Suppression Pool Temperature:            _75.5_ F                        (<=93.1 F)
Suppression Pool Level                  _19.2_ ft                      (19 ft 0 to 19 ft 5 in)
Drywell Pressure                        _0.5_ psi                      (0 to 1 psig)
Drywell to Containment dp:              _0.5_ psi                      >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:            _103_ F                        (<=146.53 F)
Secondary Containment:                  _0.74_ in WG                    (>= 0.25 in WG vacuum)
BOP                                                            Plant Chemistry Condenser Vacuum:                        _28.7_ in Hg          CPI (goal < 1.1):                1.00 Off - Gas Flow:                          _34.4_ scfm          Reactor Sulfates (goal < 2)      1.31 ppb Condensate Temperature:                  _84_ F                Reactor Chlorides:                0.51 ppb Generator Reactive Load:                _85.4_MVARS          FW Iron (goal < 2.1)              0.85 ppb Protected Equip: None Comments:      See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety


REVIEWED BY:
OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station: Clinton          Valid Date(s): xx/xx/xxxx                  Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed?            No                (If yes, CRS may make additional copies)
Simulator Instructor
Prepared by:        Roger Bottom            / xx/xx/xx          Reviewed by:        Joe QNE                / xx/xx/xx Reactor Engineer        /    Date                            Qualified Nuclear Engineer /    Date Approved by:        Michelle QNE Boss/ xx/xx/xx                    Authorized by:                              / xx/xx/xx RE Manager            /    Date                              Senior Reactor Operator /    Date NF Review        Carlos Quark                        / xx/xx/xx NF Reviewer                /      Date ReMA Activated:                                  / xx/xx/xx      ReMA Terminated:                              / xx/xx/xx Unit Supervisor        /    Date                                  Unit Supervisor    /    Date Title of Evolution: RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for raising reactor power to support upshift of the RR Pumps.
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power increase
: 1. Withdraw control rods to achieve conditions to support RR Upshift
: 2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr) 3.
4.
General Issues:
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.


APPROVED BY:  
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP      1    of    2                                          Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed.
Perform control rod pulls in accordance with approved sequence.
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.
QNE presence required in the Control Room? Yes X No *
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                  Parameter            Value or Range  Init.
Core Power (MWth or %)                  N/A            N/A MFLCPR                              N/A        N/A Core Flow (Mlb/hr or %)                  N/A            N/A MFLPD                                N/A        N/A FCL (%)                                  N/A            N/A MAPRAT                              N/A        N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                        High            Low FCL                                                                                    57.3 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.
Contingency: Insert control rods in reverse order sequence to reduce FCL.
Step Complete: ___________________/_______                        Verified by: _________________/_______
Reactor Operator      /  Date                        Unit Supervisor    /  Date


/  Operations Date Overview Makeup/Reject:
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    2    of    2                                            Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
CP's B,C,D,E and F are in service. RO tr ain #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.
Radwaste: 1WF Evap is in Hot Standby. A and B RT F/D are in service.
Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.
Plant Status On Line Risk Green  Reactor Operational Condition: Mode 1 Total Core Flow: _32.4_ mlb/hr FCV Position: A:  __90___%      B:  __90__%
Note: It is possible that performing a pump upshift will cause the plant to enter into the CONTROLLED ENTRY REGION of the power / flow operating map. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable.
Reactor Power _27_% (<=100%)    _919_ MWt (<=3473)     _244_ Mwe Xenon: Stable RPV Level _29_ in Narrow Range RPV Pressure _929_ psi  (< 1045) In service SDC loop None    MODE 1 Containment Suppression Pool Temperature: _75.5_ F
QNE presence required in the Control Room? Yes X* No *
(<=93.1 F) Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.5_ psi (0 to 1 psig) Drywell to Containment dp: _0.5_ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _103_ F
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                 Parameter            Value or Range    Init.
BOP  Plant Chemistry Condenser Vacuum: _28.7_ in Hg CPI (goal < 1.1):
Core Power (MWth or %)                N/A            N/A MFLCPR                              < 0.900 Core Flow (Mlb/hr or %)               N/A            N/A MFLPD                                < 0.900 FCL (%)                             < 57.3%                    MAPRAT                            N/A          N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                       High              Low Step Complete: ___________________/_______                      Verified by: _________________/_______
1.00 Off - Gas Flow: _34.4_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
Reactor Operator      /  Date                          Unit Supervisor    / Date
_84_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load: _85.4_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
: None  Comments: See Turnover Sheet


From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0          10        20       30         40        50       60         70          80       90          100              110 3473                                                                                                                                      100 MELLLA Limit [100.7% FCL]
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
3126                                                                                                                                      90 Restricted                                                                                    90% FCL (Typ.)
 
2778              Zone                                                                                        80%
OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station:
80 THERMAL POWER - MWTh 2431                                                                                                                                      70 PERCENT THERMAL POWER 2084                                                                                                                                      60 60%
Clinton  Valid Date(s):
CON T R OLLE D 1737                                                                                                                                      50 E N T R Y R E GION 50%
xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed?    No    (If yes, CRS may make additional copies) Prepared by:       Roger Bottom         / xx/xx/xx Reviewed by:      Joe QNE / xx/xx/xx Reactor Engineer       /      Date      Qualified Nuclear Engineer /        Date Approved by:    Michelle QNE Boss/ xx/xx/xx Authorized by:    / xx/xx/xx RE Manager            /    Date  Senior Reactor Operator  /      Date NF Review      Carlos Quark / xx/xx/xx NF Reviewer                /         Date ReMA Activated: 
1389                                                                                                                                      40 40%
/ xx/xx/xx ReMA Terminated: 
1042                                                                                                                                      30 868                                                                                                                                      25 695                                                                                                                                      20 OPRM ENABLED          CAVITATION 347                                                                              REGION          PROTECTION LINES                      10 OPRM OPERABLE
/ xx/xx/xx      Unit Supervisor       /    Date  Unit Supervisor      /      Date Title of Evolution:  RR Pump Upshift Purpose/Overview of Evolution:
[21.6 % CTP, 750 MWth]                      SINGLE LOOP        [> 25% CTP AND       (HIGH SPEED, 2 PUMP ENVELOPE            < 60% FLOW]        OPERATION) 0                                                                                                                                        0 0.0       8.5        16.9     25.4     33.8      42.3      50.7      59.2      67.6        76.1        84.5              93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)
This ReMA provides the steps for raising reac tor power to support upshift of the RR Pumps. Reactivity Maneuver Steps Extended General Issues:  Select desired amount of power increase 1. Withdraw control rods to achieve conditions to support RR Upshift 2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr)
: 3. 4. General Issues:  The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003. The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.
 
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1  of    2                                                    Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed. Perform control rod pulls in accordance with approved sequence.
 
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes X  No  *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
High  Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.
57.3 % N/A    Step Complete: ___________________
/_______          Verified by: _________________
/_______                                        Reactor Operator       /    Date                                              Unit Supervisor          /    Date     
 
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    2  of    2                                                    Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.
 
Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.
 
Note:  It is possible that performing a pump upshift will cause the plan t to enter into the CONTROLLED ENTRY REGION of the power / flow operating ma
: p. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable. QNE presence required in the Control Room? Yes X*  No  *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
N/A N/A MFLCPR < 0.900  Core Flow (Mlb/hr or %)
N/A N/AMFLPD < 0.900  FCL (%) < 57.3%  MAPRAT N/A N/A      Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
High  Low          Step Complete: ___________________
/_______          Verified by: _________________
/_______                                        Reactor Operator        /     Date                                              Unit Supervisor          /    Date      
 
FIGURE 1:  CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP 03476951042138917372084 2431 2778312634730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)
THERMAL POWER -  MWTh 0
10 20 30 40 50 60 70 80 901000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWE RRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE  60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND    < 60% FLOW]90% FCL (Typ.)  80%25868MELLLA Limit  [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]
 
Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
Two                    Operating Test No.:
08-01  Examiners: ____________________________  Operators: ____________________          ____________________________           
 
____________________
____________________________                    ____________________
 
Initial Conditions: 
 
27% power RR Pumps on LFMG,  Pulling rods to 30% power for Recirculation pump upshift.
Thunderstorms are expected in the area within the next hour.


Appendix D                                      Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station          Scenario No.: Two                Operating Test No.: 08-01 Examiners: ____________________________                              Operators: ____________________
Initial Conditions:
27% power RR Pumps on LFMG, Pulling rods to 30% power for Recirculation pump upshift.
Thunderstorms are expected in the area within the next hour.
Turnover:
Turnover:
: 1. Shift Main EHC pump to support maintenance - First Priority.
: 1. Shift Main EHC pump to support maintenance - First Priority.
: 2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.
: 2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.
Malf. No.
Malf. No. Event                                          Event Type*                                       Description 1       NA           N-BOP         Main EHC pump swap.
Event Type* Event Description 1 NA N-BOP Main EHC pump swap.
2       NA           R-ATC         Pull rods to raise power.
2 NA R-ATC Pull rods to raise power.
3       4025I_Acti   C-ATC         Rod drifts outward.
3 4025I_Acti on3ROD16 49I_ACTIO N3 1 C-ATC TS-CRS Rod drifts outward.
on3ROD16 49I_ACTIO    TS-CRS N3 1 4       HP01HP_1    C-BOP         HPCS WLP Shaft shears.
4 HP01HP_1E22C003_
E22C003_
MTFSHEA R 1 C-BOP TS-CRS HPCS WLP Shaft shears.
MTFSHEA      TS-CRS R1 5       YAFWPPL      C-ATC         A CB pump clogged oil filter/bearing oil deficiency.
5 YAFWPPLB_5 30.000 C-ATC "A" CB pump clogged oil filter/bearing oil deficiency.
B_5 30.000 6       YP_XMFT     C-BOP         Trip of B CCW pump.
6 YP_XMFT B_3918 1 C-BOP Trip of 'B' CCW pump.
B_3918 1 7       YAMSAVF     I-BOP         SSE level control failure.
7 YAMSAVF P_15 0.0 I-BOP SSE level control failure.
P_15 0.0 8       YP_XMFT     M-ALL         RPV Instrument line failure in the secondary containment.
8 YP_XMFT B_5082 1 M-ALL RPV Instrument line failure in the secondary containment.
B_5082 1 9       YP_XMFT     M-ALL         Auto and Manual scram failure.
9 YP_XMFT B_4963 1 M-ALL Auto and Manual scram failure.
B_4963 1 10       YP_XMFT     M-ALL         One SLC Pump fails to start B_5107 _1
10 YP_XMFT B_5107 _1 M-ALL One SLC Pump fails to start *(N)ormal,   (R)eactivity,   (I)nstrument,   (C)omponent,   (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
*(N)ormal,     (R)eactivity,   (I)nstrument,   (C)omponent,       (M)ajor Page 1 of 2
Two                                Operating Test No.:
08-01 Narrative Summary


Event # Description
Appendix D                                Scenario Outline                          Form ES-D-1 Scenario No.: Two                                                Operating Test No.: 08-01 Narrative Summary Event #                                     Description
: 1. Swap the running Main EHC pumps, the 'A' Main EHC pump will be started and the 'B' Main EHC pump shutdown.
: 1. Swap the running Main EHC pumps, the A Main EHC pump will be started and the B Main EHC pump shutdown.
: 2. Allow rod withdrawal to raise power.
: 2. Allow rod withdrawal to raise power.
: 3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the  
: 3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.
 
: 4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1 and B.2.
rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.
: 5. A CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the A pump.
: 4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1  
: 6. Trip of B CCW pump. Start up A CCW pump.
 
: 7. SSE level control fails causing level to go low requiring the manual level control to restore level on the SSE.
and B.2. 5. "A" CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the "A" pump.
: 6. Trip of 'B' CCW pump. Start up 'A' CCW pump.
: 7. SSE level control fails causing level to go low requiring the manual level control to  
 
restore level on the SSE.
: 8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.
: 8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.
: 9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to  
: 9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to shutdown the reactor.
 
: 10. When SLC is started the B SLC pump fails to start.
shutdown the reactor.
EOPS 8,1A,3 Critical tasks:
: 10. When SLC is started the B SLC pump fails to start.  
* Insert control rods and/or start SLC to shutdown the reactor
* Terminate and Prevent Injection prior to emergency depressurization
* Initiate emergency depressurization once two Max Safe temperatures are exceeded.
* Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.
Page 2 of 2


EOPS 8,1A,3 Critical tasks:  Insert control rods and/or start SLC to shutdown the reactor  Terminate and Prevent Injection prior to emergency depressurization  Initiate emergency depressurization once two Max Safe temperatures are exceeded. Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.
D-2, Dynamic Simulator Scenario 2             EXAM DATE: 08-24-09                       08-01I Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
Page    of 2 2
(Plant power level) 27% Power                                             A-2, step 27 is complete, 16-33 at 26 944 MWt 252 MWe 32.4 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed.
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  1  Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) 27% Power A-2, step 27 is complete, 16-33 at 26 944 MWt   252 MWe   32.4 Mlbm/hr CORE FLOW   Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed. RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized       Existing LCOs, date of next surveillance         Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift.   .        Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment         Comments, evolutions, problems, etc. Online Safety is Green   Shift Main EHC pump to support maintenance - First Priority. In 3004.01 complete thru step 8.3.10 Carrying electrical load in accordance with the Power Team.  
RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized Existing LCOs, date of next surveillance Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.
Online Safety is Green                                 In 3004.01 complete thru step 8.3.10 Shift Main EHC pump to support                        Carrying electrical load in accordance maintenance - First Priority.                          with the Power Team.
1


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  2  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):         1                                                                   Page     1   of 1
1 Page 1 of 1


== Description:==
==
Description:==
Main EHC running pump swap.
Main EHC running pump swap.
Initiation: Following turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP Per CPS 3105.02, EHC, STEP 8.1.2.1: Startup the standby pump (A) Wait for at least thirty seconds Shutdown the running pump (B) 5017-3A may or may not alarm. Test the standby pump (B)
Initiation: Following turnover Cues: Directed by SRO Time     Position                                 Applicants Actions or Behavior BOP     Per CPS 3105.02, EHC, STEP 8.1.2.1:
The standby pump is started by a local operation and then stopped in the control room. RO   Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Startup the standby pump (A)
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Wait for at least thirty seconds
Terminus: Main EHC pumps shifted  
* Shutdown the running pump (B) 5017-3A may or may not alarm.
* Test the standby pump (B)
The standby pump is started by a local operation and then stopped in the control room.
RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: Main EHC pumps shifted NOTES:
2


NOTES:
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):               2                                                             Page   1 of 1
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  3  Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
==
Description:==
Pull rods to raise power Initiation: Following Main EHC pump shift.
Pull rods to raise power Initiation: Following Main EHC pump shift.
Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-CL-721 series: Withdraw rods to raise power to 30% Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.  
Cues: Directed by SRO Time     Position                                 Applicants Actions or Behavior Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-RO      CL-721 series:
* Withdraw rods to raise power to 30%
Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Clearly observable plant response from change in power level.
NOTES:
3


BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
D-2, Dynamic Simulator Scenario 2                EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):            3                                                              Page    1 of 1
Terminus:  Clearly observable plant response from change in power level.


==
Description:==
Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time      Position                                  Applicants Actions or Behavior RO      Per Inadvertent Rod Movement, CPS 4007.02:
Immediate actions
* Select and fully insert the moving rod with the In Timer Skip button Subsequent actions;
* Once fully inserted release the In Timer Skip button
* Observe rod withdrawal
* Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled:
Monitor for core instabilities BOP
* Dispatch a field operator to the HCU for the rod
* Directs field operator to Individually scram rod
* Evaluates thermal limits
* Evaluate MSL rad monitor values
* Evaluates OG Rad levels SRO
* Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02
* Control Rod Operability, Tech. Spec. LCO 3.1.3 action C.1&2
* Contacts Shift Manager and recommends notifications.
Terminus: Once rod is fully inserted, individually scrammed and Tech Specs referenced.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  4 Operator Actions Event No.(s):
4
3  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 2                EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):         4                                                                    Page    1 of 1
Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time Position Applicant's Actions or Behavior RO  Per  Inadvertent Rod Movement, CPS 4007.02: Immediate actions Select and fully insert the moving rod with the In Timer Skip button Subsequent actions; Once fully inserted release the In Timer Skip button  Observe rod withdrawal Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled:  Monitor for core instabilities BOP  Dispatch a field operator to the HCU for the rod  Directs field operator to Individually scram rod  Evaluates thermal limits  Evaluate MSL rad monitor values  Evaluates OG Rad levels SRO  Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02  Control Rod Operability, Tech. Spec. LCO 3.1.3 action C.1&2 Contacts Shift Manager and recommends notifications.
Terminus:  Once rod is fully inserted, individually scrammed and Tech Specs referenced.


==
Description:==
HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time      Position                                  Applicants Actions or Behavior BOP      Per ARP Procedure CPS 5062-7D:
* Dispatches NLO to investigate.
o If ATM is checked for pressure it reads 0 psig When directed:
* Shutdown the HPCS WLP Pump.
Per HPCS CPS 3309.01 precaution 4.3:
* Dispatches NLO to remove HPCS control power fuses.
5062-7B will alarm.
RO
* Monitors reactor to ensure operations remain within established bands.
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Contacts Shift Manager and recommends notifications.
Terminus: HPCS control power fuses removed and Technical Specifications evaluated.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  5  Operator Actions Event No.(s):
If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.
4  Page 1 of 1
5


== Description:==
D-2, Dynamic Simulator Scenario 2              EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):         5                                                                  Page    1 of  1
HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time Position Applicant's Actions or Behavior BOP Per ARP Procedure CPS 5062-7D:
Dispatches NLO to investigate.
o If ATM is checked for pressure it reads 0 psig When directed:  Shutdown the HPCS WLP Pump. Per HPCS CPS 3309.01 precaution 4.3:
Dispatches NLO to remove HPCS control power fuses. 5062-7B will alarm.
RO  Monitors reactor to ensure operati ons remain within established bands. Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Directs actions listed above. Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Contacts Shift Manager and recommends notifications.
Terminus:  HPCS control power fuses removed and Technical Specifications evaluated.


NOTES: If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.  
==
Description:==
CB pump A clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.
Cues: Annunciator CPS 5001-1H alarming, Time      Position                                Applicants Actions or Behavior RO      CPS 5001-1H, Clogged Oil Filter CB 1A:
Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2:
* Startup standby CB pump
* Shutdown A CB pump BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Standby CB pump started and shutdown the A CB pump.
NOTES:
6


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  6  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):         6                                                                    Page   1 of 1
5  Page 1 of 1


== Description:==
==
CB pump "A" clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.
Description:==
Cues: Annunciator CPS 5001-1H alarming, Time Position Applicant's Actions or Behavior RO CPS 5001-1H, Clogged Oil Filter CB 1A:  Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2:  Startup standby CB pump Shutdown 'A' CB pump BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Trip of B CCW pump Initiation: After shifting of CB pumps, on the signal of lead examiner Cues: Annunciator CPS 5040-1B alarming, Time     Position                                   Applicants Actions or Behavior RO
SRO Directs actions listed above. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Monitors reactor to ensure operations remain within established bands
Terminus: Standby CB pump started and shutdown the 'A' CB pump.
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Responds to annunciator 5003-3D and 3E, RR Low Cooling Water Flow.
BOP
* Respond to annunciator 5040-1B,Informs CRS B CCW pump tripped.
* Starts standby pump per ARP (O/A 2.a).
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Directs starting of A CCW pump.
* Directs RO to monitor RR and RT Temps.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Standby CCW pump started.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  7 Operator Actions Event No.(s):
7
6  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):         7                                                                   Page   1 of 1
Trip of 'B' CCW pump Initiation:
After shifting of CB pumps, on the signal of lead examiner Cues:  Annunciator CPS 5040-1B alarming,  Time Position Applicant's Actions or Behavior RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions. Responds to annunciator 5003-3D and 3E, RR Low Cooling Water Flow.
BOP  Respond to annunciator 5040-1B,Informs CRS B CCW pump tripped. Starts standby pump per ARP (O/A 2.a). Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above. Directs starting of  'A' CCW pump. Directs RO to monitor RR and RT Temps. Enforces OPS expectations and standards  Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus:  Standby CCW pump started.
NOTES:
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  8  Operator Actions Event No.(s):
7 Page 1 of 1


== Description:==
==
SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2: Determines level to be low. Direct field operator to investigate. Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2. Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.
Description:==
RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time     Position                                 Applicants Actions or Behavior BOP     Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2:
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Determines level to be low.
Terminus: SSE level restored and alarm clear NOTES: May take up to (2) minutes for alarm to come in. (This is normal.)  
* Direct field operator to investigate.
* Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2.
Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.
RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: SSE level restored and alarm clear NOTES:
May take up to (2) minutes for alarm to come in. (This is normal.)
8


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  9  Operator Actions Event No.(s): 8,9,10 Page 1 of 5
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):             8,9,10                                                         Page     1   of 5


== Description:==
== Description:==
RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown Check and report power unchanged Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is not met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to monitor and control RPV level and press BOP Reports secondary containment high temperature and rad alarms to SRO   Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF, Fuel Bldg Vent. Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports a secondary containment Max Sa fe temperature being approached to SRO Reports two secondary containment Max Safe temperatures are being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task
RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time       Position                               Applicants Actions or Behavior RO     Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO
* Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram:
* Place mode switch in Shutdown
* Check and report power unchanged
* Operate FW to control level 3 to 8
* Check rods, reports shutdown criteria is not met
* Report level and pressure are following expected trends
* Stabilize pressure <1065 psig
* Coordinates with BOP operator to monitor and control RPV level and press BOP
* Reports secondary containment high temperature and rad alarms to SRO
* Makes plant announcement for reactor scram
* Should make plant announcement to evacuate Fuel/Aux buildings.
Performs EOP actions as directed by SRO
* Verifies operation of area coolers
* Verifies operation of VF, Fuel Bldg Vent.
* Evacuates affected areas of Secondary Containment
* Monitors area temperatures, levels and radiation levels Critical Task
* Reports a secondary containment Max Safe temperature being approached to SRO
* Reports two secondary containment Max Safe temperatures are being exceeded to SRO
* Coordinates with RO to monitor and control RPV level and press NOTES:
9


NOTES:
D-2, Dynamic Simulator Scenario 2             EXAM DATE: 08-24-09                       08-01I Event No.(s):         8,9,10                                                           Page     2 of 5 Time     Position                                 Applicants Actions or Behavior SRO     Directs entry into EOP-8 and EOP actions as entry conditions are met:
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  10  Event No.(s): 8,9,10 Page 2 of 5 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:
: 1. Operate VF
: 1. Operate VF
: 2. Operate area coolers
: 2. Operate area coolers
: 3. Hold floor drain sump levels below max. normal
: 3. Hold floor drain sump levels below max. normal
: 4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting
: 4. Isolate all discharges into the affected area except systems needed for:
: 5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage: Directs BOP to isolate the source of leakage 6. Direct a scram prior to exceeding Maximum safe temperature 7. Enters EOP-1 Directs additional actions:
* EOP Actions
* Fire Fighting
: 5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage:
* Directs BOP to isolate the source of leakage
: 6. Direct a scram prior to exceeding Maximum safe temperature
: 7. Enters EOP-1 Directs additional actions:
: 1. Notification of Radiation Protection (RP) Department
: 1. Notification of Radiation Protection (RP) Department
: 2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:
: 2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:
: 1. Mode Switch to SHUTDOWN Per EOP-1 enters EOP-1A Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas Critical Task NOTES:
: 1. Mode Switch to SHUTDOWN
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  11  Event No.(s): 8,9,10 Page 3 of 5 Time Position Applicant's Actions or Behavior RO Performs EOP actions as directed by SRO:
* Per EOP-1 enters EOP-1A Critical Task      Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas NOTES:
Arms and depresses MANUAL SCRAM push-buttons.
10
Initiates ARI.
CPS No. 4411.08, Alternate Control Rod Insertion  Inserts control rods until RPC lockup  Directs defeating RPC for further rod insertion  Verifies RR downshifts at Level 3, and trips at Level 2.
Terminates and prevents injection CB/FW systems CPS 4411.02


When RPV level reaches -60", control RPV water level between TAF and -60" using only the listed Preferred ATWS Systems BOP Performs EOP-1A actions as directed by SRO: I nhibits ADS. Verifies needed auto actions. I solations  D G Start   Dispatches area operator to monitor DGs Starts and verifies injection of SLC trains 'A' and 'B'. Reports SLC B failure to start.  
D-2, Dynamic Simulator Scenario 2              EXAM DATE: 08-24-09                      08-01I Event No.(s):          8,9,10                                                        Page    3 of 5 Time      Position                                Applicants Actions or Behavior RO    Performs EOP actions as directed by SRO:
* Arms and depresses MANUAL SCRAM push-buttons.
* Initiates ARI.
* CPS No. 4411.08, Alternate Control Rod Insertion
* Inserts control rods until RPC lockup
* Directs defeating RPC for further rod insertion
* Verifies RR downshifts at Level 3, and trips at Level 2.
Critical Task
* Terminates and prevents injection CB/FW systems CPS 4411.02 Critical Task
* When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems BOP     Performs EOP-1A actions as directed by SRO:
* Inhibits ADS.
* Verifies needed auto actions.
* Isolations
* DG Start
* Dispatches area operator to monitor DGs Critical Task
* Starts and verifies injection of SLC trains 'A' and 'B'.
* Reports SLC B failure to start.
* Terminates and prevents injection systems CPS 4411.02 Critical Task              1. HPCS
: 2. RCIC
: 3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. B RO may have to give LPCS-5 valve a close signal to complete the T/P.
: 4. LPCI Stabilizes RPV pressure below 1065 psig NOTES:
11


Terminates and prevents injection systems CPS 4411.02
D-2, Dynamic Simulator Scenario 2             EXAM DATE: 08-24-09                       08-01I Event No.(s):           8,9,10                                                         Page     4   of 5 Time     Position                               Applicants Actions or Behavior SRO     Directs entry into EOP-1A and EOP actions as entry conditions are met:
: 1. HPCS 2. RCIC 3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. 'B' RO may have to give LPCS-5 valve a close signal to complete the T/P.
: 1. Inhibit ADS
: 4. LPCI  Stabilizes RPV pressure below 1065 psig Critical Task Critical Task Critical Task Critical Task NOTES:
: 2. Arm and depress MANUAL SCRAM push-buttons
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  12  Event No.(s): 8,9,10 Page 4 of 5 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-1A and EOP actions as entry conditions are met: 1. Inhibit ADS 2. Arm and depress MANUAL SCRAM push-buttons
: 3. Initiate ARI Critical Task      5. Determines Power to be greater than 5% and Directs injection of SLC
: 3. Initiate ARI
: 6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion
: 5. Determines Power to be greater than 5% and Directs injection of SLC 6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion 7. Verifies needed auto actions. Isolations DG Start 8. Terminate and prevent injection of Detail F1 CPS 4411.02
: 7. Verifies needed auto actions.
: 9. When RPV level reaches -60", control RPV water level between TAF and -60" using only the listed Preferred ATWS Systems 10. Enters EOP-6 for High Drywell Temperature 11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identif ied parameters below (within) specified values. On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Isolations
Critical Task NOTES:       Critical Task Critical Task D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  13  Event No.(s): 8,9,10 Page 5 of 5 Time Position Applicant's Actions or Behavior RO Performs EOP-3 actions as directed by SRO Termination and prevention of injection of all F1 systems
* DG Start Critical Task
: 8. Terminate and prevent injection of Detail F1 CPS 4411.02 Critical Task      9. When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems
: 10. Enters EOP-6 for High Drywell Temperature
: 11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identified parameters below (within) specified values.
* On transient, positions himself as command authority on the unit.
* Acknowledges immediate operator actions and directs subsequent actions.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
NOTES:
12
 
D-2, Dynamic Simulator Scenario 2           EXAM DATE: 08-24-09                     08-01I Event No.(s):           8,9,10                                                     Page   5 of   5 Time   Position                             Applicants Actions or Behavior RO   Performs EOP-3 actions as directed by SRO Critical Task
* Termination and prevention of injection of all F1 systems
: 1. CB/FW At less then 138 psig:
: 1. CB/FW At less then 138 psig:
Re-feed to level band OF -60 to TAF BOP Performs EOP-3 actions as directed by SRO termination and prevention of injection of all F1 systems
Critical Task
: 1. LPCS 2. LPCI initiation of ADS and verify 7 ADS valves open SRO Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas Directs termination and prevention of injection of all F1 systems Directs initiation of ADS and verify 7 ADS valves open Directs Re-feed at 138 psig Directs level band at -60 to -TAF Terminus:   E OP-8 actions initiated S LC started Rod Insert commenced R PV level lowered ADS initiated Level restored and stabilized Upon approval of lead examiner Critical Task Critical Task Critical Task Critical Task 4 Critical Tasks NOTES:
* Re-feed to level band OF -60 to TAF BOP   Performs EOP-3 actions as directed by SRO Critical Task
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                    08-01 I  14  Simulator Operator Instructions Initial Setup
* termination and prevention of injection of all F1 systems
: 1. LPCS
: 2. LPCI Critical Task
* initiation of ADS and verify 7 ADS valves open SRO   Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas 4 Critical Tasks
* Directs termination and prevention of injection of all F1 systems
* Directs initiation of ADS and verify 7 ADS valves open
* Directs Re-feed at 138 psig
* Directs level band at -60 to -TAF Terminus:
* EOP-8 actions initiated
* SLC started
* Rod Insert commenced
* RPV level lowered
* ADS initiated
* Level restored and stabilized
* Upon approval of lead examiner NOTES:
13
 
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                    08-01I Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).
: 2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).
Line 516: Line 771:
: 8. Verify the AR/PR server is running and stabilize AR/PR.
: 8. Verify the AR/PR server is running and stabilize AR/PR.
: 9. Verify Rod Drive pressure at 250#.
: 9. Verify Rod Drive pressure at 250#.
1 0. Identify T/S issues associated with OOS and turnover.
: 10. Identify T/S issues associated with OOS and turnover.
1 1. Verify simulator conditions match the turnover.
: 11. Verify simulator conditions match the turnover.
1 2. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26 1 3. Provide marked up CPS 3004.01 complete to step 8.3.10.
: 12. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26
1 4. Fill out plant status sheet and have Turnover sheet ready for crew.
: 13. Provide marked up CPS 3004.01 complete to step 8.3.10.
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  15 Event Triggers and Role Play Event # 1. Main EHC pump swap
: 14. Fill out plant status sheet and have Turnover sheet ready for crew.
: a. No trigger - to start b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal
14
: c. Remote trigger 10  
 
- When requested to test auto start feature
D-2, Dynamic Simulator Scenario 2                   EXAM DATE: 08-24-09                     08-01I Event Triggers and Role Play Event #
: 1. Main EHC pump swap
: a. No trigger - to start
: b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal
: c. Remote trigger 10 - When requested to test auto start feature
: d. The Pump will shutoff when stopped with the control room switch.
: d. The Pump will shutoff when stopped with the control room switch.
: 2. Pull rods to raise power
: 2. Pull rods to raise power
Line 532: Line 791:
: b. No problem lights at the RGDC or RACCs
: b. No problem lights at the RGDC or RACCs
: c. Role Play - Field operator reports no indications of problem at the HCU.
: c. Role Play - Field operator reports no indications of problem at the HCU.
: d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.
: d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.
: e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed
: e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed
: 4. HPCS WLP shaft shears
: 4. HPCS WLP shaft shears
Line 538: Line 797:
: b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.
: b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.
: c. If ATM is checked it is reading 0 psig.
: c. If ATM is checked it is reading 0 psig.
: d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.
: d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.
: e. If called - Respond as maintenance to investigate.
: e. If called - Respond as maintenance to investigate.
: f. If requested by CRS, RCIC is operable by administrative means.
: f. If requested by CRS, RCIC is operable by administrative means.
NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.
NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.
: 5. CB pump "A" clogged oil filter/bearing oil deficiency
: 5. CB pump A clogged oil filter/bearing oil deficiency
: a. Remote trigger 3 - on request from lead evaluator
: a. Remote trigger 3 - on request from lead evaluator
: b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75 F) More Event Triggers and Role Play on the next page
: b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75&deg;F)
More Event Triggers and Role Play on the next page 15


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  16 6. 'B' CCW pump Trip
D-2, Dynamic Simulator Scenario 2                   EXAM DATE: 08-24-09                         08-01I
: 6. B CCW pump Trip
: a. Remote trigger 4 on request from lead evaluator
: a. Remote trigger 4 on request from lead evaluator
: b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.
: b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.
: c. Role play as maintenance personnel in the field if requested.
: c. Role play as maintenance personnel in the field if requested.
: 7. SSE level control failure
: 7. SSE level control failure
: a. Remote trigger 5 - on request from lead evaluator
: a. Remote trigger 5 - on request from lead evaluator
: b. Role play as field operator no indications locally that would explain failure.
: b. Role play as field operator no indications locally that would explain failure.
: c. Controller is set at 0 inches, but level control valve is shut.
: c. Controller is set at 0 inches, but level control valve is shut.
Line 558: Line 819:
: a. Remote trigger 6 on request from lead evaluator
: a. Remote trigger 6 on request from lead evaluator
: b. When the XL3 printout is requested provide attachment 1
: b. When the XL3 printout is requested provide attachment 1
: c. Role play as personnel in the field  
: c. Role play as personnel in the field (1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.
 
(1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.
: 9. Auto and Manual scram failure
: 9. Auto and Manual scram failure
: a. Triggers - already active
: a. Triggers - already active
: b. Perform Pending actions when requested
: b. Perform Pending actions when requested
: c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)
: c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)
: 10. RT-1 and RT-4 fail to shut on SLC initiation
: 10. RT-1 and RT-4 fail to shut on SLC initiation
: a. Triggers - already active D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  17  TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1
: a. Triggers - already active 16
=========================
====================
=====================
61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM


61-19 AB-781 East Col 121-124 AC ALARM  
D-2, Dynamic Simulator Scenario 2      EXAM DATE: 08-24-09        08-01I TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1
 
==================================================================
61-20 AB-781 East Col 121-124 AC ALARM  
61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM 61-19 AB-781 East Col 121-124 AC ALARM 61-20 AB-781 East Col 121-124 AC ALARM 17


Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)
Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)
: 1. EOP-1 2. EOP-1A 3. EOP-8 4. EOP-3 5. EOP-6 6. 3105.02 EHC
: 1. EOP-1
: 2. EOP-1A
: 3. EOP-8
: 4. EOP-3
: 5. EOP-6
: 6. 3105.02 EHC
: 7. ITS/ORM/ODCM
: 7. ITS/ORM/ODCM
: 8. 3004.01 TG S/U and Sync
: 8. 3004.01 TG S/U and Sync
: 9. 4007.02 O/N
: 9. 4007.02 O/N
: 10. 3309.01 HPCS
: 10. 3309.01 HPCS
: 11. 3104.01 CD/CB
: 11. 3104.01 CD/CB
: 12. 4100.01 O/N
: 12. 4100.01 O/N
: 13. 4001.01 O/N
: 13. 4001.01 O/N
: 14. 4411.08 ARI
: 14. 4411.08 ARI
: 15. 4411.02 T/P
: 15. 4411.02 T/P
: 16. SLC hard card
: 16. SLC hard card
: 17. T/P hard card (2)
: 17. T/P hard card (2)
: 18. 3203.01 CCW
: 18. 3203.01 CCW
: 19. 3107.01 GS
: 19. 3107.01 GS
: 20. 3304.02 RCIS
: 20. 3304.02 RCIS
: 21. 4411.104410.00 C012
: 21. 4411.104410.00 C012
: 22. 4411.09 23. 4410.00 C003
: 22. 4411.09
: 23. 4410.00 C003
: 24. 4410.00 C004
: 24. 4410.00 C004
: 25. 4411.03 26. 4411.04 27. 4411.11 28. 4411.02 29. 3101.01 30. HU-AA-1211
: 25. 4411.03
: 26. 4411.04
: 27. 4411.11
: 28. 4411.02
: 29. 3101.01
: 30. HU-AA-1211
: 31. OP-AB-300-1001
: 31. OP-AB-300-1001
: 32. Annuciators:
: 32. Annuciators:
5006-4G, 5D, 3H, 1H, 3D 5062-7D, 8E, 7B 5019-3A 5001-1H 5040-1B, 8D 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H 5017-3A 5130-1G ,2G 5003-3D, 3K 5002-2P, 1Q 5004-3A, 3F 5009-5B 5063-7H 5065-6F 5140 AR/PR All alarms after the Scram  
* 5006-4G, 5D, 3H, 1H, 3D
* 5062-7D, 8E, 7B
* 5019-3A
* 5001-1H
* 5040-1B, 8D
* 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H
* 5017-3A
* 5130-1G ,2G
* 5003-3D, 3K
* 5002-2P, 1Q
* 5004-3A, 3F
* 5009-5B
* 5063-7H
* 5065-6F
* 5140 AR/PR
* All alarms after the Scram


Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00  
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                          /
Operations                      Date


DEVELOPER:
Overview Makeup/Reject:             CPs B,C,D,E and F are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                      RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                      N/A Electrical:                6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Tom Pickley   
Radwaste:                  1WF Evap is in Hot Standby. A and B RT F/D are in service.
Plant Status On Line Risk Green Reactor Operational Condition:          Mode 1 Total Core Flow:                _32.4_ mlb/hr FCV Position:                  A: __90___%        B: __90__%
Reactor Power                  _27_% (<=100%) _919_ MWt (<=3473)                _244_ Mwe Xenon:                          Stable RPV Level                      _29_ in Narrow Range RPV Pressure                    _929_ psi (< 1045)
In service SDC loop            None MODE 1 Containment Suppression Pool Temperature:            _75.5_ F                        (<=93.1 F)
Suppression Pool Level                  _19.2_ ft                      (19 ft 0 to 19 ft 5 in)
Drywell Pressure                        _0.5_ psi                      (0 to 1 psig)
Drywell to Containment dp:              _0.5_ psi                      >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:            _103_ F                        (<=146.53 F)
Secondary Containment:                  _0.74_ in WG                    (>= 0.25 in WG vacuum)
BOP                                                            Plant Chemistry Condenser Vacuum:                        _28.7_ in Hg          CPI (goal < 1.1):                1.00 Off - Gas Flow:                          _34.4_ scfm          Reactor Sulfates (goal < 2)      1.31 ppb Condensate Temperature:                  _84_ F                Reactor Chlorides:                0.51 ppb Generator Reactive Load:                _85.4_MVARS          FW Iron (goal < 2.1)              0.85 ppb Protected Equip: None Comments:      See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety


REVIEWED BY:
OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station: Clinton          Valid Date(s): xx/xx/xxxx                  Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed?            No                (If yes, CRS may make additional copies)
Simulator Instructor
Prepared by:        Roger Bottom            / xx/xx/xx          Reviewed by:        Joe QNE                / xx/xx/xx Reactor Engineer        /    Date                            Qualified Nuclear Engineer /    Date Approved by:        Michelle QNE Boss/ xx/xx/xx                    Authorized by:                              / xx/xx/xx RE Manager            /    Date                              Senior Reactor Operator /    Date NF Review        Carlos Quark                        / xx/xx/xx NF Reviewer                /      Date ReMA Activated:                                  / xx/xx/xx      ReMA Terminated:                              / xx/xx/xx Unit Supervisor        /    Date                                  Unit Supervisor    /    Date Title of Evolution: RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for raising reactor power to support upshift of the RR Pumps.
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power increase
: 1. Withdraw control rods to achieve conditions to support RR Upshift
: 2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr) 3.
4.
General Issues:
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.


APPROVED BY:  
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP      1    of    2                                          Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed.
Perform control rod pulls in accordance with approved sequence.
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.
QNE presence required in the Control Room? Yes X No *
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                  Parameter            Value or Range  Init.
Core Power (MWth or %)                  N/A            N/A MFLCPR                              N/A        N/A Core Flow (Mlb/hr or %)                  N/A            N/A MFLPD                                N/A        N/A FCL (%)                                  N/A            N/A MAPRAT                              N/A        N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                        High            Low FCL                                                                                    57.3 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.
Contingency: Insert control rods in reverse order sequence to reduce FCL.
Step Complete: ___________________/_______                        Verified by: _________________/_______
Reactor Operator      /  Date                        Unit Supervisor    /  Date


/  Operations Date Overview Makeup/Reject:
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    2    of    2                                            Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
CP's B,C,D,E and F are in service. RO tr ain #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.
Radwaste: 1WF Evap is in Hot Standby. A and B RT F/D are in service.
Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.
Plant Status On Line Risk Green  Reactor Operational Condition: Mode 1 Total Core Flow: _32.4_ mlb/hr FCV Position: A:  __90___%      B:  __90__%
Note: It is possible that performing a pump upshift will cause the plant to enter into the CONTROLLED ENTRY REGION of the power / flow operating map. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable.
Reactor Power _27_% (<=100%)    _919_ MWt (<=3473)     _244_ Mwe Xenon: Stable RPV Level _29_ in Narrow Range RPV Pressure _929_ psi  (< 1045) In service SDC loop None    MODE 1 Containment Suppression Pool Temperature: _75.5_ F
QNE presence required in the Control Room? Yes X* No *
(<=93.1 F) Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.5_ psi (0 to 1 psig) Drywell to Containment dp: _0.5_ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _103_ F
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                 Parameter            Value or Range    Init.
BOP  Plant Chemistry Condenser Vacuum: _28.7_ in Hg CPI (goal < 1.1):
Core Power (MWth or %)                N/A            N/A MFLCPR                              < 0.900 Core Flow (Mlb/hr or %)               N/A            N/A MFLPD                                < 0.900 FCL (%)                             < 57.3%                    MAPRAT                            N/A          N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                       High              Low Step Complete: ___________________/_______                      Verified by: _________________/_______
1.00 Off - Gas Flow: _34.4_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
Reactor Operator      /  Date                          Unit Supervisor    / Date
_84_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load: _85.4_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
: None  Comments: See Turnover Sheet


From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0          10        20       30         40        50       60         70          80       90          100              110 3473                                                                                                                                      100 MELLLA Limit [100.7% FCL]
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
3126                                                                                                                                      90 Restricted                                                                                    90% FCL (Typ.)
 
2778              Zone                                                                                        80%
OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station:
80 THERMAL POWER - MWTh 2431                                                                                                                                      70 PERCENT THERMAL POWER 2084                                                                                                                                      60 60%
Clinton  Valid Date(s):
CON T R OLLE D 1737                                                                                                                                      50 E N T R Y R E GION 50%
xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed?    No    (If yes, CRS may make additional copies) Prepared by:       Roger Bottom         / xx/xx/xx Reviewed by:      Joe QNE / xx/xx/xx Reactor Engineer       /      Date      Qualified Nuclear Engineer /        Date Approved by:    Michelle QNE Boss/ xx/xx/xx Authorized by:    / xx/xx/xx RE Manager            /    Date  Senior Reactor Operator  /      Date NF Review      Carlos Quark / xx/xx/xx NF Reviewer                /         Date ReMA Activated: 
1389                                                                                                                                      40 40%
/ xx/xx/xx ReMA Terminated: 
1042                                                                                                                                      30 868                                                                                                                                      25 695                                                                                                                                      20 OPRM ENABLED          CAVITATION 347                                                                              REGION          PROTECTION LINES                      10 OPRM OPERABLE
/ xx/xx/xx      Unit Supervisor       /    Date  Unit Supervisor      /      Date Title of Evolution:  RR Pump Upshift Purpose/Overview of Evolution:
[21.6 % CTP, 750 MWth]                      SINGLE LOOP        [> 25% CTP AND       (HIGH SPEED, 2 PUMP ENVELOPE            < 60% FLOW]        OPERATION) 0                                                                                                                                        0 0.0       8.5        16.9     25.4     33.8      42.3      50.7      59.2      67.6        76.1        84.5              93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)
This ReMA provides the steps for raising reac tor power to support upshift of the RR Pumps. Reactivity Maneuver Steps Extended General Issues:  Select desired amount of power increase 1. Withdraw control rods to achieve conditions to support RR Upshift 2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr)
: 3. 4. General Issues:  The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003. The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.
 
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1  of    2                                                    Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed. Perform control rod pulls in accordance with approved sequence.
 
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes X  No  *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
High  Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.
57.3 % N/A    Step Complete: ___________________
/_______          Verified by: _________________
/_______                                        Reactor Operator       /    Date                                              Unit Supervisor          /    Date     
 
OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    2  of    2                                                    Reactivity Maneuver Plan # C11-Simu.3 Description of Step :
Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.
 
Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.
 
Note:  It is possible that performing a pump upshift will cause the plan t to enter into the CONTROLLED ENTRY REGION of the power / flow operating ma
: p. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable. QNE presence required in the Control Room? Yes X*  No  *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
N/A N/A MFLCPR < 0.900  Core Flow (Mlb/hr or %)
N/A N/AMFLPD < 0.900  FCL (%) < 57.3%  MAPRAT N/A N/A      Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
High  Low          Step Complete: ___________________
/_______          Verified by: _________________
/_______                                        Reactor Operator        /     Date                                              Unit Supervisor          /    Date      
 
FIGURE 1:  CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP 03476951042138917372084 2431 2778312634730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)
THERMAL POWER -  MWTh 0
10 20 30 40 50 60 70 80 901000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWE RRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE  60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND    < 60% FLOW]90% FCL (Typ.)  80%25868MELLLA Limit  [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]
 
Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
Two                    Operating Test No.:
08-01  Examiners: ____________________________  Operators: ____________________          ____________________________           
 
____________________
____________________________                    ____________________
 
Initial Conditions: 
 
27% power RR Pumps on LFMG,  Pulling rods to 30% power for Recirculation pump upshift.
Thunderstorms are expected in the area within the next hour.


Appendix D                                      Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station          Scenario No.: Two                Operating Test No.: 08-01 Examiners: ____________________________                              Operators: ____________________
Initial Conditions:
27% power RR Pumps on LFMG, Pulling rods to 30% power for Recirculation pump upshift.
Thunderstorms are expected in the area within the next hour.
Turnover:
Turnover:
: 1. Shift Main EHC pump to support maintenance - First Priority.
: 1. Shift Main EHC pump to support maintenance - First Priority.
: 2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.
: 2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.
Malf. No.
Malf. No. Event                                          Event Type*                                       Description 1       NA           N-BOP         Main EHC pump swap.
Event Type* Event Description 1 NA N-BOP Main EHC pump swap.
2       NA           R-ATC         Pull rods to raise power.
2 NA R-ATC Pull rods to raise power.
3       4025I_Acti   C-ATC         Rod drifts outward.
3 4025I_Acti on3ROD16 49I_ACTIO N3 1 C-ATC TS-CRS Rod drifts outward.
on3ROD16 49I_ACTIO    TS-CRS N3 1 4       HP01HP_1    C-BOP         HPCS WLP Shaft shears.
4 HP01HP_1E22C003_
E22C003_
MTFSHEA R 1 C-BOP TS-CRS HPCS WLP Shaft shears.
MTFSHEA      TS-CRS R1 5       YAFWPPL      C-ATC         A CB pump clogged oil filter/bearing oil deficiency.
5 YAFWPPLB_5 30.000 C-ATC "A" CB pump clogged oil filter/bearing oil deficiency.
B_5 30.000 6       YP_XMFT     C-BOP         Trip of B CCW pump. delete B_3918 1 7       YAMSAVF     I-BOP         SSE level control failure.
6 YP_XMFT B_3918 1 C-BOP Trip of 'B' CCW pump. delete 7 YAMSAVF P_15 0.0 I-BOP SSE level control failure.
P_15 0.0 8       YP_XMFT     M-ALL         RPV Instrument line failure in the secondary containment.
8 YP_XMFT B_5082 1 M-ALL RPV Instrument line failure in the secondary containment.
B_5082 1 9       YP_XMFT     M-ALL         Auto and Manual scram failure.
9 YP_XMFT B_4963 1 M-ALL Auto and Manual scram failure.
B_4963 1 10       YP_XMFT     M-ALL         One SLC Pump fails to start B_5107 _1
10 YP_XMFT B_5107 _1 M-ALL One SLC Pump fails to start *(N)ormal,   (R)eactivity,   (I)nstrument,   (C)omponent,   (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
*(N)ormal,     (R)eactivity,   (I)nstrument,   (C)omponent,       (M)ajor Page 1 of 2
Two                                Operating Test No.:
08-01 Narrative Summary


Event # Description
Appendix D                                Scenario Outline                          Form ES-D-1 Scenario No.: Two                                                Operating Test No.: 08-01 Narrative Summary Event #                                     Description
: 1. Swap the running Main EHC pumps, the 'A' Main EHC pump will be started and the 'B' Main EHC pump shutdown.
: 1. Swap the running Main EHC pumps, the A Main EHC pump will be started and the B Main EHC pump shutdown.
: 2. Allow rod withdrawal to raise power.
: 2. Allow rod withdrawal to raise power.
: 3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the  
: 3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.
 
: 4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1 and B.2.
rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.
: 5. A CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the A pump.
: 4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1  
: 6. Trip of B CCW pump. Start up A CCW pump.
 
: 7. SSE level control fails causing level to go low requiring the manual level control to restore level on the SSE.
and B.2. 5. "A" CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the "A" pump.
: 6. Trip of 'B' CCW pump. Start up 'A' CCW pump.
: 7. SSE level control fails causing level to go low requiring the manual level control to  
 
restore level on the SSE.
: 8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.
: 8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.
: 9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to  
: 9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to shutdown the reactor.
: 10. When SLC is started the B SLC pump fails to start.
EOPS 8,1A,3 Critical tasks:
* Insert control rods and/or start SLC to shutdown the reactor
* Terminate and Prevent Injection prior to emergency depressurization
* Initiate emergency depressurization once two Max Safe temperatures are exceeded.
* Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.
Page 2 of 2


shutdown the reactor.
D-2, Dynamic Simulator Scenario 2              EXAM DATE: 08-24-09                        08-01I Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
: 10. When SLC is started the B SLC pump fails to start.  
(Plant power level) 27% Power                                              A-2, step 27 is complete, 16-33 at 26 944 MWt 252 MWe 32.4 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed.
RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized Existing LCOs, date of next surveillance Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.
Online Safety is Green                                In 3004.01 complete thru step 8.3.10 Shift Main EHC pump to support                        Carrying electrical load in accordance maintenance - First Priority.                           with the Power Team.
1


EOPS 8,1A,3 Critical tasks:  Insert control rods and/or start SLC to shutdown the reactor  Terminate and Prevent Injection prior to emergency depressurization  Initiate emergency depressurization once two Max Safe temperatures are exceeded. Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):        1                                                                  Page    1   of 1
Page    of 2 2
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  1  Shift Turnover Information  Day of week and shift  Today Day Shift  Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) 27% Power  A-2, step 27 is complete, 16-33 at 26  944 MWt   252 MWe    32.4 Mlbm/hr CORE FLOW    Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed. RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized        Existing LCOs, date of next surveillance          Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift.    .        Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment          Comments, evolutions, problems, etc. Online Safety is Green  Shift Main EHC pump to support maintenance - First Priority. In 3004.01 complete thru step 8.3.10  Carrying electrical load in accordance with the Power Team.


D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  2  Operator Actions Event No.(s):
==
1  Page 1 of 1
Description:==
 
== Description:==
Main EHC running pump swap.
Main EHC running pump swap.
Initiation: Following turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP Per CPS 3105.02, EHC, STEP 8.1.2.1: Startup the standby pump (A) Wait for at least thirty seconds Shutdown the running pump (B) 5017-3A may or may not alarm. Test the standby pump (B)
Initiation: Following turnover Cues: Directed by SRO Time     Position                                 Applicants Actions or Behavior BOP     Per CPS 3105.02, EHC, STEP 8.1.2.1:
The standby pump is started by a local operation and then stopped in the control room. RO   Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Startup the standby pump (A)
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Wait for at least thirty seconds
Terminus: Main EHC pumps shifted  
* Shutdown the running pump (B) 5017-3A may or may not alarm.
* Test the standby pump (B)
The standby pump is started by a local operation and then stopped in the control room.
RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: Main EHC pumps shifted NOTES:
2


NOTES:
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):               2                                                             Page   1 of 1
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  3  Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
==
Description:==
Pull rods to raise power Initiation: Following Main EHC pump shift.
Pull rods to raise power Initiation: Following Main EHC pump shift.
Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-CL-721 series: Withdraw rods to raise power to 30% Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.  
Cues: Directed by SRO Time     Position                                 Applicants Actions or Behavior Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-RO      CL-721 series:
* Withdraw rods to raise power to 30%
Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Clearly observable plant response from change in power level.
NOTES:
3


BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
D-2, Dynamic Simulator Scenario 2                EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):            3                                                              Page    1 of 1
Terminus:  Clearly observable plant response from change in power level.


==
Description:==
Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time      Position                                  Applicants Actions or Behavior RO      Per Inadvertent Rod Movement, CPS 4007.02:
Immediate actions
* Select and fully insert the moving rod with the In Timer Skip button Subsequent actions;
* Once fully inserted release the In Timer Skip button
* Observe rod withdrawal
* Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled:
Monitor for core instabilities BOP
* Dispatch a field operator to the HCU for the rod
* Directs field operator to Individually scram rod
* Evaluates thermal limits
* Evaluate MSL rad monitor values
* Evaluates OG Rad levels SRO
* Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02
* Control Rod Operability, Tech. Spec. LCO 3.1.3 action C.1&2
* Contacts Shift Manager and recommends notifications.
Terminus: Once rod is fully inserted, individually scrammed and Tech Specs referenced.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  4 Operator Actions Event No.(s):
4
3  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 2                EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):         4                                                                    Page    1 of 1
Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time Position Applicant's Actions or Behavior RO  Per  Inadvertent Rod Movement, CPS 4007.02: Immediate actions Select and fully insert the moving rod with the In Timer Skip button Subsequent actions; Once fully inserted release the In Timer Skip button  Observe rod withdrawal Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled:  Monitor for core instabilities BOP  Dispatch a field operator to the HCU for the rod  Directs field operator to Individually scram rod  Evaluates thermal limits  Evaluate MSL rad monitor values  Evaluates OG Rad levels SRO  Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02  Control Rod Operability, Tech. Spec. LCO 3.1.3 action C.1&2 Contacts Shift Manager and recommends notifications.
Terminus:  Once rod is fully inserted, individually scrammed and Tech Specs referenced.


==
Description:==
HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time      Position                                  Applicants Actions or Behavior BOP      Per ARP Procedure CPS 5062-7D:
* Dispatches NLO to investigate.
o If ATM is checked for pressure it reads 0 psig When directed:
* Shutdown the HPCS WLP Pump.
Per HPCS CPS 3309.01 precaution 4.3:
* Dispatches NLO to remove HPCS control power fuses.
5062-7B will alarm.
RO
* Monitors reactor to ensure operations remain within established bands.
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Contacts Shift Manager and recommends notifications.
Terminus: HPCS control power fuses removed and Technical Specifications evaluated.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  5  Operator Actions Event No.(s):
If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.
4  Page 1 of 1
5


== Description:==
D-2, Dynamic Simulator Scenario 2              EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):         5                                                                  Page    1 of  1
HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time Position Applicant's Actions or Behavior BOP Per ARP Procedure CPS 5062-7D:
Dispatches NLO to investigate.
o If ATM is checked for pressure it reads 0 psig When directed:  Shutdown the HPCS WLP Pump. Per HPCS CPS 3309.01 precaution 4.3:
Dispatches NLO to remove HPCS control power fuses. 5062-7B will alarm.
RO  Monitors reactor to ensure operati ons remain within established bands. Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Directs actions listed above. Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Contacts Shift Manager and recommends notifications.
Terminus:  HPCS control power fuses removed and Technical Specifications evaluated.


NOTES: If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.  
==
Description:==
CB pump A clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.
Cues: Annunciator CPS 5001-1H alarming, Time      Position                                Applicants Actions or Behavior RO      CPS 5001-1H, Clogged Oil Filter CB 1A:
Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2:
* Startup standby CB pump
* Shutdown A CB pump BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Standby CB pump started and shutdown the A CB pump.
NOTES:
6


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  6  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):         6                                                                    Pa g e    1   of 1
5  Page 1 of 1


== Description:==
==
CB pump "A" clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.
Description:==
Cues: Annunciator CPS 5001-1H alarming, Time Position Applicant's Actions or Behavior RO CPS 5001-1H, Clogged Oil Filter CB 1A:  Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2:  Startup standby CB pump Shutdown 'A' CB pump BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Trip of B CCW pump Initiation: After shifting of CB pumps, on the signal of lead examiner Cues: Annunciator CPS 5040-1B alarming, Time     Position                                   Applicants Actions or Behavior RO
SRO Directs actions listed above. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Monitors reactor to ensure operations remain within established bands
Terminus: Standby CB pump started and shutdown the 'A' CB pump.
* Monitors control room panels and notifies notifies the SRO of any unusual or unexpected conditions.
* Responds to annunciator 5003-5003-3D and 3E, RR Low Cooling Water Flow.
BOP
* Respond to annunciator 5040-5040-1B,Informs CRS B CCW pump tripped.
* Starts standby pump per ARP (O/A 2.a).
* Monitors control room panels panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Directs starting of A CCW pump.
* Directs RO to monitor RR and RT Temps.
* Enforces OPS expectations and standards
* Ensures operations are conducted within within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Standby CCW pump started.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  7 Operator Actions E E v v e e n n t t  N N o o..((s s))::  6 6    P P a a g g e e  1 1  o o f f  1 1  D D e e s s c c r r i i p p t t i i o o n n::  T T r r i i p p  o o f f  ''B B''  C C C C W W  p p u u m m p p  I I n n i i t t i i a a t t i i o o n n::    A A f f t t e e r r  s s h h i i f f t t i i n n g g  o o f f  C C B B  p p u u m m p p s s , ,  o o n n  t t h h e e  s s i i g g n n a a l l  o o f f  l l e e a a d d  e e x x a a m m i i n n e e r r  C C u u e e s s::    A A n n n n u u n n c c i i a a t t o o r r  C C P P S S  5 5 0 0 4 4 0 0--1 1 B B  a a l l a a r r m m i i n n g g , ,    T T i i m m e e  P P o o s s i i t t i i o o n n  A A p p p p l l i i c c a a n n t t''s s  A A c c t t i i o o n n s s  o o r r  B B e e h h a a v v i i o o r r    R R O O      Monitors  reactor  to  ensure  operations remain  within  established bands M o n i t o r s r e a c t o r t o e n s u r e o p e r a t i o n s r e m a i n w i t h i n e s t a b l i s h e d b a n d s    Monitors  control  room  panels  and  n M o n i t o r s c o n t r o l r o o m p a n e l s a n d notifies  the  SRO  of  any  unusual  or  unexpected o t i f i e s t h e S R O o f a n y u n u s u a l o r u n e x p e c t e dconditions.
7
c o n d i t i o n s. Responds  to  R e s p o n d s t oannunciator 5003 a n n u n c i a t o r 5 0 0 3--3D  and  3E,  RR  Low  Cooling  Water  Flow.3 D a n d 3 E , R R L o w C o o l i n g W a t e r F l o w.      B B O O P P    Respond  to  annunciator R e s p o n d t o a n n u n c i a t o r5040 5 0 4 0--1B,Informs CRS  B  CCW  pump  tripped.1 B , I n f o r m s C R S B C C W p u m p t r i p p e d. Starts  standby  pump  per  ARP  (O/A  2.a).S t a r t s s t a n d b y p u m p p e r A R P (O/A 2.a). Monitors  control  room  p M o n i t o r s c o n t r o l r o o m panels  and  notifies  the  SRO  of  any  unusual  or  unexpected a n e l s a n d n o t i f i e s t h e S R O o f a n y u n u s u a l o r u n e x p e c t e dconditions.
c o n d i t i o n s.      S S R R O O    Directs  actions  listed  above.D i r e c t s a c t i o n s l i s t e d a b o v e. Directs  starting  of    'A'  CCW  pump.D i r e c t s s t a r t i n g o f'A'C C W p u m p. Directs  RO  to  monitor  RR  and  RT  Temps.D i r e c t s R O t o m o n i t o r R R a n d R T T e m p s. Enforces  OPS  expectations and  standards E n f o r c e s O P S e x p e c t a t i o n s a n d s t a n d a r d s    Ensures  operations are  conducted with E n s u r e s o p e r a t i o n s a r e c o n d u c t e d w i t hin  the  bounds  of  Tech  Specs  and  IAW  i n t h e b o u n d s o f T e c h S p e c s a n d I A WOperations standards and  approved  procedures.
O p e r a t i o n s s t a n d a r d s a n d a p p r o v e d p r o c e d u r e s. T T e e r r m m i i n n u u s s::    S S t t a a n n d d b b y y  C C C C W W  p p u u m m p p  s s t t a a r r t t e e d d.. N N O O T T E E S S::
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  8  Operator Actions Event No.(s):
7  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 2                EXAM DATE: 08-24-09                      08-01I Operator Actions Event No.(s):        7                                                                    Page    1  of  1
SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2: Determines level to be low. Direct field operator to investigate. Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2. Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.
 
RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
==
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Description:==
Terminus: SSE level restored and alarm clear NOTES: May take up to (2) minutes for alarm to come in. (This is normal.)  
SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time     Position                                 Applicants Actions or Behavior BOP     Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2:
* Determines level to be low.
* Direct field operator to investigate.
* Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2.
Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.
RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: SSE level restored and alarm clear NOTES:
May take up to (2) minutes for alarm to come in. (This is normal.)
8


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  9  Operator Actions Event No.(s): 8,9,10 Page 1 of 5
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                       08-01I Operator Actions Event No.(s):             8,9,10                                                         Page     1   of 5


== Description:==
== Description:==
RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown Check and report power unchanged Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is not met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to monitor and control RPV level and press BOP Reports secondary containment high temperature and rad alarms to SRO   Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF, Fuel Bldg Vent. Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports a secondary containment Max Sa fe temperature being approached to SRO Reports two secondary containment Max Safe temperatures are being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task
RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time       Position                               Applicants Actions or Behavior RO     Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO
* Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram:
* Place mode switch in Shutdown
* Check and report power unchanged
* Operate FW to control level 3 to 8
* Check rods, reports shutdown criteria is not met
* Report level and pressure are following expected trends
* Stabilize pressure <1065 psig
* Coordinates with BOP operator to monitor and control RPV level and press BOP
* Reports secondary containment high temperature and rad alarms to SRO
* Makes plant announcement for reactor scram
* Should make plant announcement to evacuate Fuel/Aux buildings.
Performs EOP actions as directed by SRO
* Verifies operation of area coolers
* Verifies operation of VF, Fuel Bldg Vent.
* Evacuates affected areas of Secondary Containment
* Monitors area temperatures, levels and radiation levels Critical Task
* Reports a secondary containment Max Safe temperature being approached to SRO
* Reports two secondary containment Max Safe temperatures are being exceeded to SRO
* Coordinates with RO to monitor and control RPV level and press NOTES:
9


NOTES:
D-2, Dynamic Simulator Scenario 2             EXAM DATE: 08-24-09                       08-01I Event No.(s):         8,9,10                                                           Page     2 of 5 Time     Position                                 Applicants Actions or Behavior SRO     Directs entry into EOP-8 and EOP actions as entry conditions are met:
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  10  Event No.(s): 8,9,10 Page 2 of 5 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:
: 1. Operate VF
: 1. Operate VF
: 2. Operate area coolers
: 2. Operate area coolers
: 3. Hold floor drain sump levels below max. normal
: 3. Hold floor drain sump levels below max. normal
: 4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting
: 4. Isolate all discharges into the affected area except systems needed for:
: 5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage: Directs BOP to isolate the source of leakage 6. Direct a scram prior to exceeding Maximum safe temperature 7. Enters EOP-1 Directs additional actions:
* EOP Actions
* Fire Fighting
: 5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage:
* Directs BOP to isolate the source of leakage
: 6. Direct a scram prior to exceeding Maximum safe temperature
: 7. Enters EOP-1 Directs additional actions:
: 1. Notification of Radiation Protection (RP) Department
: 1. Notification of Radiation Protection (RP) Department
: 2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:
: 2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:
: 1. Mode Switch to SHUTDOWN Per EOP-1 enters EOP-1A Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas Critical Task NOTES:
: 1. Mode Switch to SHUTDOWN
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  11  Event No.(s): 8,9,10 Page 3 of 5 Time Position Applicant's Actions or Behavior RO Performs EOP actions as directed by SRO:
* Per EOP-1 enters EOP-1A Critical Task      Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas NOTES:
Arms and depresses MANUAL SCRAM push-buttons.
10
Initiates ARI.
 
CPS No. 4411.08, Alternate Control Rod Insertion   Inserts control rods until RPC lockup Directs defeating RPC for further rod insertion Verifies RR downshifts at Level 3, and trips at Level 2.
D-2, Dynamic Simulator Scenario 2             EXAM DATE: 08-24-09                       08-01I Event No.(s):           8,9,10                                                         Page     3 of 5 Time     Position                                 Applicants Actions or Behavior RO     Performs EOP actions as directed by SRO:
Terminates and prevents injection CB/FW systems CPS 4411.02  
* Arms and depresses MANUAL SCRAM push-buttons.
* Initiates ARI.
* CPS No. 4411.08, Alternate Control Rod Insertion
* Inserts control rods until RPC lockup
* Directs defeating RPC for further rod insertion
* Verifies RR downshifts at Level 3, and trips at Level 2.
Critical Task
* Terminates and prevents injection CB/FW systems CPS 4411.02 Critical Task
* When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems BOP    Performs EOP-1A actions as directed by SRO:
* Inhibits ADS.
* Verifies needed auto actions.
* Isolations
* DG Start
* Dispatches area operator to monitor DGs Critical Task
* Starts and verifies injection of SLC trains 'A' and 'B'.
* Reports SLC B failure to start.
* Terminates and prevents injection systems CPS 4411.02 Critical Task              1. HPCS
: 2. RCIC
: 3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. B RO may have to give LPCS-5 valve a close signal to complete the T/P.
: 4. LPCI Stabilizes RPV pressure below 1065 psig NOTES:
11


When RPV level reaches -60", control RPV water level between TAF and -60" using only the listed Preferred ATWS Systems BOP Performs EOP-1A actions as directed by SRO: I nhibits ADS. Verifies needed auto actions. I solations  D G Start  Dispatches area operator to monitor DGs Starts and verifies injection of SLC trains 'A' and 'B'. Reports SLC B failure to start.  
D-2, Dynamic Simulator Scenario 2              EXAM DATE: 08-24-09                      08-01I Event No.(s):          8,9,10                                                        Page      4    of 5 Time      Position                                Applicants Actions or Behavior SRO    Directs entry into EOP-1A and EOP actions as entry conditions are met:
: 1. Inhibit ADS
: 2. Arm and depress MANUAL SCRAM push-buttons
: 3. Initiate ARI Critical Task      5. Determines Power to be greater than 5% and Directs injection of SLC
: 6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion
: 7. Verifies needed auto actions.
* Isolations
* DG Start Critical Task
: 8. Terminate and prevent injection of Detail F1 CPS 4411.02 Critical Task      9. When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems
: 10. Enters EOP-6 for High Drywell Temperature
: 11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identified parameters below (within) specified values.
* On transient, positions himself as command authority on the unit.
* Acknowledges immediate operator actions and directs subsequent actions.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
NOTES:
12


Terminates and prevents injection systems CPS 4411.02
D-2, Dynamic Simulator Scenario 2           EXAM DATE: 08-24-09                     08-01I Event No.(s):           8,9,10                                                     Page   5 of   5 Time   Position                             Applicants Actions or Behavior RO   Performs EOP-3 actions as directed by SRO Critical Task
: 1. HPCS 2. RCIC 3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. 'B' RO may have to give LPCS-5 valve a close signal to complete the T/P.
* Termination and prevention of injection of all F1 systems
: 4. LPCI  Stabilizes RPV pressure below 1065 psig Critical Task Critical Task Critical Task Critical Task NOTES:
D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  12  Event No.(s): 8,9,10  Page 4 of 5 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-1A and EOP actions as entry conditions are met: 1. Inhibit ADS 2. Arm and depress MANUAL SCRAM push-buttons
: 3. Initiate ARI
: 5. Determines Power to be greater than 5% and Directs injection of SLC 6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion 7. Verifies needed auto actions. Isolations  DG Start 8. Terminate and prevent injection of  Detail F1 CPS 4411.02
: 9. When RPV level reaches -60", control RPV water level between TAF and -60" using only the listed Preferred ATWS Systems 10. Enters EOP-6 for High Drywell Temperature 11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identif ied parameters below (within) specified values. On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Critical Task NOTES:        Critical Task Critical Task D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  13  Event No.(s): 8,9,10 Page 5 of 5 Time Position Applicant's Actions or Behavior RO Performs EOP-3 actions as directed by SRO Termination and prevention of injection of all F1 systems
: 1. CB/FW At less then 138 psig:
: 1. CB/FW At less then 138 psig:
Re-feed to level band OF -60 to TAF BOP Performs EOP-3 actions as directed by SRO termination and prevention of injection of all F1 systems
Critical Task
: 1. LPCS 2. LPCI initiation of ADS and verify 7 ADS valves open SRO Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas Directs termination and prevention of injection of all F1 systems Directs initiation of ADS and verify 7 ADS valves open Directs Re-feed at 138 psig Directs level band at -60 to -TAF Terminus:   E OP-8 actions initiated S LC started Rod Insert commenced R PV level lowered ADS initiated Level restored and stabilized Upon approval of lead examiner Critical Task Critical Task Critical Task Critical Task 4 Critical Tasks NOTES:
* Re-feed to level band OF -60 to TAF BOP   Performs EOP-3 actions as directed by SRO Critical Task
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                    08-01 I  14  Simulator Operator Instructions Initial Setup
* termination and prevention of injection of all F1 systems
: 1. LPCS
: 2. LPCI Critical Task
* initiation of ADS and verify 7 ADS valves open SRO   Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas 4 Critical Tasks
* Directs termination and prevention of injection of all F1 systems
* Directs initiation of ADS and verify 7 ADS valves open
* Directs Re-feed at 138 psig
* Directs level band at -60 to -TAF Terminus:
* EOP-8 actions initiated
* SLC started
* Rod Insert commenced
* RPV level lowered
* ADS initiated
* Level restored and stabilized
* Upon approval of lead examiner NOTES:
13
 
D-2, Dynamic Simulator Scenario 2               EXAM DATE: 08-24-09                    08-01I Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).
: 2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).
Line 824: Line 1,247:
: 8. Verify the AR/PR server is running and stabilize AR/PR.
: 8. Verify the AR/PR server is running and stabilize AR/PR.
: 9. Verify Rod Drive pressure at 250#.
: 9. Verify Rod Drive pressure at 250#.
1 0. Identify T/S issues associated with OOS and turnover.
: 10. Identify T/S issues associated with OOS and turnover.
1 1. Verify simulator conditions match the turnover.
: 11. Verify simulator conditions match the turnover.
1 2. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26 1 3. Provide marked up CPS 3004.01 complete to step 8.3.10.
: 12. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26
1 4. Fill out plant status sheet and have Turnover sheet ready for crew.
: 13. Provide marked up CPS 3004.01 complete to step 8.3.10.
D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  15 Event Triggers and Role Play Event # 1. Main EHC pump swap
: 14. Fill out plant status sheet and have Turnover sheet ready for crew.
: a. No trigger - to start b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal
14
: c. Remote trigger 10  
 
- When requested to test auto start feature
D-2, Dynamic Simulator Scenario 2                   EXAM DATE: 08-24-09                     08-01I Event Triggers and Role Play Event #
: 1. Main EHC pump swap
: a. No trigger - to start
: b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal
: c. Remote trigger 10 - When requested to test auto start feature
: d. The Pump will shutoff when stopped with the control room switch.
: d. The Pump will shutoff when stopped with the control room switch.
: 2. Pull rods to raise power
: 2. Pull rods to raise power
Line 840: Line 1,267:
: b. No problem lights at the RGDC or RACCs
: b. No problem lights at the RGDC or RACCs
: c. Role Play - Field operator reports no indications of problem at the HCU.
: c. Role Play - Field operator reports no indications of problem at the HCU.
: d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.
: d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.
: e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed
: e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed
: 4. HPCS WLP shaft shears
: 4. HPCS WLP shaft shears
Line 846: Line 1,273:
: b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.
: b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.
: c. If ATM is checked it is reading 0 psig.
: c. If ATM is checked it is reading 0 psig.
: d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.
: d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.
: e. If called - Respond as maintenance to investigate.
: e. If called - Respond as maintenance to investigate.
: f. If requested by CRS, RCIC is operable by administrative means.
: f. If requested by CRS, RCIC is operable by administrative means.
NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.
NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.
: 5. CB pump "A" clogged oil filter/bearing oil deficiency
: 5. CB pump A clogged oil filter/bearing oil deficiency
: a. Remote trigger 3 - on request from lead evaluator
: a. Remote trigger 3 - on request from lead evaluator
: b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75 F) More Event Triggers and Role Play on the next page
: b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75&deg;F)
More Event Triggers and Role Play on the next page 15


D-2, Dynamic Simulator Scenario 2                 EXAM DATE: 08-24-09                   08-01 I  16 6. 'B' CCW pump Trip
D-2, Dynamic Simulator Scenario 2                   EXAM DATE: 08-24-09                         08-01I
: 6. B CCW pump Trip
: a. Remote trigger 4 on request from lead evaluator
: a. Remote trigger 4 on request from lead evaluator
: b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.
: b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.
: c. Role play as maintenance personnel in the field if requested.
: c. Role play as maintenance personnel in the field if requested.
: 7. SSE level control failure
: 7. SSE level control failure
: a. Remote trigger 5 - on request from lead evaluator
: a. Remote trigger 5 - on request from lead evaluator
: b. Role play as field operator no indications locally that would explain failure.
: b. Role play as field operator no indications locally that would explain failure.
: c. Controller is set at 0 inches, but level control valve is shut.
: c. Controller is set at 0 inches, but level control valve is shut.
Line 866: Line 1,295:
: a. Remote trigger 6 on request from lead evaluator
: a. Remote trigger 6 on request from lead evaluator
: b. When the XL3 printout is requested provide attachment 1
: b. When the XL3 printout is requested provide attachment 1
: c. Role play as personnel in the field  
: c. Role play as personnel in the field (1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.
 
(1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.
: 9. Auto and Manual scram failure
: 9. Auto and Manual scram failure
: a. Triggers - already active
: a. Triggers - already active
: b. Perform Pending actions when requested
: b. Perform Pending actions when requested
: c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)
: c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)
: 10. RT-1 and RT-4 fail to shut on SLC initiation
: 10. RT-1 and RT-4 fail to shut on SLC initiation
: a. Triggers - already active D-2, Dynamic Simulator Scenario 2                  EXAM DATE: 08-24-09                    08-01 I  17  TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1
: a. Triggers - already active 16
=========================
====================
=====================
61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM


61-19 AB-781 East Col 121-124 AC ALARM  
D-2, Dynamic Simulator Scenario 2      EXAM DATE: 08-24-09        08-01I TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1
 
==================================================================
61-20 AB-781 East Col 121-124 AC ALARM  
61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM 61-19 AB-781 East Col 121-124 AC ALARM 61-20 AB-781 East Col 121-124 AC ALARM 17


Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)
Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)
: 1. EOP-1 2. EOP-1A 3. EOP-8 4. EOP-3 5. EOP-6 6. 3105.02 EHC
: 1. EOP-1
: 2. EOP-1A
: 3. EOP-8
: 4. EOP-3
: 5. EOP-6
: 6. 3105.02 EHC
: 7. ITS/ORM/ODCM
: 7. ITS/ORM/ODCM
: 8. 3004.01 TG S/U and Sync
: 8. 3004.01 TG S/U and Sync
: 9. 4007.02 O/N
: 9. 4007.02 O/N
: 10. 3309.01 HPCS
: 10. 3309.01 HPCS
: 11. 3104.01 CD/CB
: 11. 3104.01 CD/CB
: 12. 4100.01 O/N
: 12. 4100.01 O/N
: 13. 4001.01 O/N
: 13. 4001.01 O/N
: 14. 4411.08 ARI
: 14. 4411.08 ARI
: 15. 4411.02 T/P
: 15. 4411.02 T/P
: 16. SLC hard card
: 16. SLC hard card
: 17. T/P hard card (2)
: 17. T/P hard card (2)
: 18. 3203.01 CCW
: 18. 3203.01 CCW
: 19. 3107.01 GS
: 19. 3107.01 GS
: 20. 3304.02 RCIS
: 20. 3304.02 RCIS
: 21. 4411.104410.00 C012
: 21. 4411.104410.00 C012
: 22. 4411.09 23. 4410.00 C003
: 22. 4411.09
: 23. 4410.00 C003
: 24. 4410.00 C004
: 24. 4410.00 C004
: 25. 4411.03 26. 4411.04 27. 4411.11 28. 4411.02 29. 3101.01 30. HU-AA-1211
: 25. 4411.03
: 26. 4411.04
: 27. 4411.11
: 28. 4411.02
: 29. 3101.01
: 30. HU-AA-1211
: 31. OP-AB-300-1001
: 31. OP-AB-300-1001
: 32. Annuciators:
: 32. Annuciators:
5006-4G, 5D, 3H, 1H, 3D 5062-7D, 8E, 7B 5019-3A 5001-1H 5040-1B, 8D 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H 5017-3A 5130-1G ,2G 5003-3D, 3K 5002-2P, 1Q 5004-3A, 3F 5009-5B 5063-7H 5065-6F 5140 AR/PR All alarms after the Scram  
* 5006-4G, 5D, 3H, 1H, 3D
* 5062-7D, 8E, 7B
* 5019-3A
* 5001-1H
* 5040-1B, 8D
* 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H
* 5017-3A
* 5130-1G ,2G
* 5003-3D, 3K
* 5002-2P, 1Q
* 5004-3A, 3F
* 5009-5B
* 5063-7H
* 5065-6F
* 5140 AR/PR
* All alarms after the Scram


Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00  
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                          /
Operations                      Date


DEVELOPER:
Overview Makeup/Reject:             A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                     RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                       N/A Electrical:               6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Tom Pickley 
Radwaste:                 FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
 
Plant Status On Line Risk Green Reactor Operational Condition:         Mode 2 Total Core Flow:               __26.9___ mlb/hr FCV Position:                   A: ___90____%       B: _ _90____%
REVIEWED BY:
Reactor Power                   __0__% (<=100%) _0__ MWt (<=3473)               _0__ Mwe Xenon:                         Stable RPV Level                       _26.7_ in Narrow Range RPV Pressure                   _600__ psi (< 1045)
Simulator Instructor
In service SDC loop             None MODE 2 Containment Suppression Pool Temperature:           _75.5_ F                       (<=93.1 F)
 
Suppression Pool Level                   _19.1_ ft                       (19 ft 0 to 19 ft 5 in)
APPROVED BY:
Drywell Pressure                         _0.4__ psi                     (0 to 1 psig)
 
Drywell to Containment dp:               _0.4__ psi                     >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:             _100__ F                       (<=146.53 F)
/  Operations Date Overview Makeup/Reject:
Secondary Containment:                   _0.74_ in WG                   (>= 0.25 in WG vacuum)
A,B,C CP's are in service. RO trai n #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
BOP                                                           Plant Chemistry Condenser Vacuum:                       _27_ in Hg           CPI (goal < 1.1):                 1.00 Off - Gas Flow:                         _12.8_ scfm           Reactor Sulfates (goal < 2)       1.31 ppb Condensate Temperature:                 _78_ F               Reactor Chlorides:               0.51 ppb Generator Reactive Load:                 _0_MVARS             FW Iron (goal < 2.1)             0.85 ppb Protected Equip: None Comments:       See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Participate in training program activities.
Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: __26.9___ mlb/hr FCV Position: A: ___90____%     B: _
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
_90____% Reactor Power __0__% (<=100%)   _0__ MWt (<=3473)     _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi (< 1045) In service SDC loop None   MODE 2 Containment Suppression Pool Temperature: _75.5_ F
(<=93.1 F) Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.4__ psi (0 to 1 psig) Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
BOP Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1):
1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
_78_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
: None Comments: See Turnover Sheet  
 
From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety  
 
OP-AB-300-1003Revision 3 Page 26 of 39 Attachment 1 Reactivity Maneuver Approval Cover Page Station:  Clinton  Valid Date(s):
2/2-2/15/08 Reactivity Maneuver Plan #:  C12-0001 Are Multiple Activations Allowed:
No  (If yes, US may make additional copies) Prepared by: ______________/______  Reviewed by:  ________________/_______
Reactor Engineer / Date    Qualified Nuclear Engineer / Date Approved by: _____________/_______  Au thorized by: ____
_______________/______                                RE Manager    / Date Senior Reactor Operator  / Date NF Review (circle one) yes/declined    by ________________/______


OP-AB-300-1003 Revision 3 Page 26 of 39 Attachment 1 Reactivity Maneuver Approval Cover Page Station: Clinton              Valid Date(s): 2/2-2/15/08 Reactivity Maneuver Plan #:                            C12-0001 Are Multiple Activations Allowed: No                          (If yes, US may make additional copies)
Prepared by: ______________/______                                Reviewed by: ________________/_______
Reactor Engineer / Date                                      Qualified Nuclear Engineer / Date Approved by: _____________/_______                                Authorized by: ___________________/______
RE Manager        / Date                                        Senior Reactor Operator / Date NF Review (circle one) yes/declined                  by ________________/______
NF Individual Contacted/Date ReMA Activated: ______________/_______ ReMA Terminated: ______________/______
NF Individual Contacted/Date ReMA Activated: ______________/_______ ReMA Terminated: ______________/______
Unit Supervisor     / Date     Unit Supervisor   /   Date Title of Evolution: BOC 12 Plant Startup Purpose/Overview of Evolution:
Unit Supervisor     / Date                                       Unit Supervisor     / Date Title of Evolution: BOC 12 Plant Startup Purpose/Overview of Evolution:
This ReMA provides the steps for starting up t he reactor from C1R11 refueling outage. The ReMA covers power ascension from All Rods In (ARI) to ~96.
This ReMA provides the steps for starting up the reactor from C1R11 refueling outage. The ReMA covers power ascension from All Rods In (ARI) to ~96.9% CTP (~3365 MWth).
9% CTP (~3365 MWth).
Maneuver Steps
Maneuver Steps
: 1. Withdraw rods from ARI to ~29% CTP.
: 1. Withdraw rods from ARI to ~29% CTP.
: 2. Shift RR pumps to fast speed & increase core flow to ~65% (~54.9 Mlbm/hr)
: 2. Shift RR pumps to fast speed & increase core flow to ~65% (~54.9 Mlbm/hr)
: 3. Increase reactor power to ~96.9% CTP (~3365 MWth).
: 3. Increase reactor power to ~96.9% CTP (~3365 MWth).
: 4. Maintain power at ~96.9% CTP (~3365 MWth) with rods & flow General Issues: The plan is to pull control rods until the target rod pattern is achieved. However, since this will be a xenon free startup, all rods cannot be fully withdrawn to their target positions during the power ascension. Also fuel conditioning limits will require a slow flow ramp (0.35 kw/ft/hr; ~30 MWe/hr) to reach rated power. A second downpower will be required (separate ReMA) to achieve the target rod pattern. The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA procedure OP-AB-300-1003. Main Steam Line Radiation Monitors may initially show elevated response from crud burst in the core (due to rod movements) and from "hydrogen pockets" being swept into the core (due to flow perturbations in the condensate/
: 4. Maintain power at ~96.9% CTP (~3365 MWth) with rods & flow General Issues:
feedwater piping). Response should diminish as the feedwater system comes to equilibrium. Turbine Control Valve (TCV) oscillations have been experienced at ~87% (~3021 MWth). It may be necessary to flow quickly through this region to avoid excessive valve oscillations.
The plan is to pull control rods until the target rod pattern is achieved. However, since this will be a xenon free startup, all rods cannot be fully withdrawn to their target positions during the power ascension. Also fuel conditioning limits will require a slow flow ramp (0.35 kw/ft/hr; ~30 MWe/hr) to reach rated power. A second downpower will be required (separate ReMA) to achieve the target rod pattern.
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA procedure OP-AB-300-1003.
Main Steam Line Radiation Monitors may initially show elevated response from crud burst in the core (due to rod movements) and from hydrogen pockets being swept into the core (due to flow perturbations in the condensate/
feedwater piping). Response should diminish as the feedwater system comes to equilibrium.
Turbine Control Valve (TCV) oscillations have been experienced at ~87% (~3021 MWth). It may be necessary to flow quickly through this region to avoid excessive valve oscillations.


OP-AB-300-1003Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step   1     of   4                  
OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 1         of 4                                     Reactivity Maneuver Plan # C12-0001 Description of Step:
 
Reactivity Maneuver Plan #
C12-0001 Description of Step:
Withdraw rods from ARI to ~29% CTP.
Withdraw rods from ARI to ~29% CTP.
Initial Complete a) Withdraw control rods in accordance with Startup Sequence A2-01 to ~29%(~1007 MWth) to support RR pump shift to fast speed.
Initial Complete a) Withdraw control rods in accordance with Startup Sequence A2-01 to ~29%(~1007 MWth) to support RR pump shift to fast speed.
b) Verify scram time testing is complete before shifting RR pumps to fast speed. A separate control rod sequence package will be provided for this testing.
b) Verify scram time testing is complete before shifting RR pumps to fast speed. A separate control rod sequence package will be provided for this testing.
Note: Prior to exceeding 21.6% power verify feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWth). Reference App. A of CPS 3102.01. The Reactor Engineer will provide guidance on adjustments to the rod pattern or flow to accommodate predictor uncertainties or schedule changes.
Note: Prior to exceeding 21.6% power verify feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWth). Reference App. A of CPS 3102.01.
QNE presence required in the Control Room? Yes X No           Onsite Only? Yes No       Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init.Parameter Value or Range Init.Generator Output N/A N/A MFLCPR N/A N/A Core Power (MWt or %)
The Reactor Engineer will provide guidance on adjustments to the rod pattern or flow to accommodate predictor uncertainties or schedule changes.
N/A N/A MFLPD N/A N/A Core Flow (Mlb/hr or %)
QNE presence required in the Control Room? Yes X No                           Onsite Only? Yes         No Initial Conditions (may be ranges) to be verified at the START of the Step Parameter             Value or Range Init.               Parameter           Value or Range Init.
N/A N/A MAPRAT N/A N/A FCL (%) N/A N/A         Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and contingency actions (if needed)
Generator Output                       N/A         N/A   MFLCPR                               N/A           N/A Core Power (MWt or %)                 N/A         N/A   MFLPD                               N/A           N/A Core Flow (Mlb/hr or %)               N/A         N/A   MAPRAT                               N/A           N/A FCL (%)                               N/A         N/A Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High              Low contingency actions (if needed)
High Low FCL Monitor frequency : Demand 3D case after crossing 21.6% (750 MWth) & just prior to RR pump shift to fast speed. Power and flow indications on the P680 displays may also be used. (Contingency: Insert control rods to reduce FCL.) 57.3% N/A     
FCL Monitor frequency : Demand 3D case after crossing 21.6% (750 MWth) &
 
just prior to RR pump shift to fast speed. Power and flow indications on the       57.3%                N/A P680 displays may also be used.
ReMA Step Complete:
(Contingency: Insert control rods to reduce FCL.)
_________________/______ Verified by
ReMA Step Complete: _________________/______ Verified by: _______________/_______
: _______________/_______                                                         Reactor Operator/Date                                             Unit Supervisor/Date
Reactor Operator/Date                             Unit Supervisor/Date
 
OP-AB-300-1003Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step  2    of  4                 


Reactivity Maneuver Plan #
OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 2      of 4                                    Reactivity Maneuver Plan # C12-0001 Description of Step:
C12-0001 Description of Step:
Shift RR pumps to fast speed & increase core flow to ~65% (~54.9 Mlbm/hr)
Shift RR pumps to fast speed & increase core flow to ~65% (~54.9 Mlbm/hr)
Initial Complete a) Shift RR pumps to fast speed. During upshifts of RR pumps there is a potential for entry in to the Controlled Entry Re gion. This has been evaluated and is acceptable.
Initial Complete a) Shift RR pumps to fast speed. During upshifts of RR pumps there is a potential for entry in to the Controlled Entry Region. This has been evaluated and is acceptable.
b) Increase core flow to ~65% (~54.9 Mlbm/h r). Increasing flow may be performed in increments to support minimizing throttling of FCVs and as necessary to support plant systems. At the completion of this step reactor power will be ~40-45% (~1389-1563 MWth).
b) Increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support minimizing throttling of FCVs and as necessary to support plant systems. At the completion of this step reactor power will be ~40-45% (~1389-1563 MWth).
Reactor Engineer to provide guidance on adjustments to rod pattern or flow to accommodate predictor uncertainties and schedule changes.
Reactor Engineer to provide guidance on adjustments to rod pattern or flow to accommodate predictor uncertainties and schedule changes.
QNE presence required in the Control Room? Yes X   No           Onsite Only? Yes No       Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init.Parameter Value or Range Init.Generator Output N/A N/A MFLCPR < 0.900 Core Power (MWt or %)
QNE presence required in the Control Room? Yes X No                           Onsite Only? Yes         No Initial Conditions (may be ranges) to be verified at the START of the Step Parameter             Value or Range Init.               Parameter             Value or Range         Init.
N/A N/A MFLPD < 0.750 Core Flow (Mlb/hr or %)
Generator Output                   N/A         N/A     MFLCPR                             < 0.900 Core Power (MWt or %)               N/A         N/A     MFLPD                             < 0.750 Core Flow (Mlb/hr or %)             N/A         N/A     MAPRAT                               N/A             N/A FCL (%)                           < 57.3%
N/A N/A MAPRAT N/A N/A FCL (%) < 57.3%           Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and contingency actions (if needed)
Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High                Low contingency actions (if needed)
High Low NONE  
NONE ReMA Step Complete: _________________/______ Verified by: _______________/_______
Reactor Operator/Date                            Unit Supervisor/Date


ReMA Step Complete: _________________/______  Verified by:  _______________/_______                                                          Reactor Operator/Date                                            Unit Supervisor/Date
OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 3       of 4                                           Reactivity Maneuver Plan # C12-0001 Description of Step:
 
OP-AB-300-1003Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step   3   of   4      
 
Reactivity Maneuver Plan #
C12-0001 Description of Step:
Increase power to ~96.9% CTP (~3365 MWth) with flow and rods. Power may be increased in increments as necessary to support plant evolutions. Flow adjustments may be used to maintain power approximately constant for any hold points.
Increase power to ~96.9% CTP (~3365 MWth) with flow and rods. Power may be increased in increments as necessary to support plant evolutions. Flow adjustments may be used to maintain power approximately constant for any hold points.
Note: At ~80% power, bundle nodal powers of exposed fuel are expected to reach the threshold of ~8.5kw/ft. In accordance with NF-AB-440, a fuel conditional ramp rate of 0.35kw/ft/hr will be required. RE will provide guidance on fuel conditioning ramp. The intent is to withdraw as many rods as possible. However, xenon conditions and fuel conditioning requirements will not permit withdrawal of the control rods to desire d target positions. Reactor Engi neer will provide guidance on control rod movements and flow increases.
Note:
 
At ~80% power, bundle nodal powers of exposed fuel are expected to reach the threshold of ~8.5kw/ft. In accordance with NF-AB-440, a fuel conditional ramp rate of 0.35kw/ft/hr will be required. RE will provide guidance on fuel conditioning ramp.
The intent is to withdraw as many rods as possible. However, xenon conditions and fuel conditioning requirements will not permit withdrawal of the control rods to desired target positions. Reactor Engineer will provide guidance on control rod movements and flow increases.
Reactor Engineer to provide guidance on adjustments to rod pattern or flow to accommodate predictor uncertainties and schedule changes.
Reactor Engineer to provide guidance on adjustments to rod pattern or flow to accommodate predictor uncertainties and schedule changes.
QNE presence required in the Control Room? Yes X*   No           Onsite Only? Yes No     *RE coverage will be provided consistent with OP-AB-300-1003 & NF-AB-701.
QNE presence required in the Control Room? Yes X* No                             Onsite Only? Yes           No
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init.P arameter Value or Range Init. Generator Output N/A N/A MFLCPR < 0.900 Core Power (MWt or %)
*RE coverage will be provided consistent with OP-AB-300-1003 & NF-AB-701.
N/A N/A MFLPD < 0.900 Core Flow (Mlb/hr or %)  
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter             Value or Range Init.                 Parameter            Value or Range Init.
~65% (~54.9 Mlbm/hr)
Generator Output                     N/A           N/A MFLCPR                               < 0.900 Core Power (MWt or %)                 N/A           N/A MFLPD                               < 0.900
MAPRAT N/A N/A FCL (%) N/A N/A         Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and contingency actions (if needed)
                                    ~65%                                                        N/A            N/A Core Flow (Mlb/hr or %)                                     MAPRAT
High Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after each 50 MWe increase in electrical output. Contingency: Insert control rods as recommended by the Reactor Engineer.
(~54.9 Mlbm/hr)
98.7% N/A MFLCPR   Monitor Frequency: 3D case at each 50 MWe increase in electrical output when MFLCPR > 0.900.
FCL (%)                               N/A           N/A Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High              Low contingency actions (if needed)
Contingency:  Refer to CPS 2202.03 for correction of power distribution problems.
FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after each 50 MWe increase in electrical output.
0.980 N/A OP-AB-300-1003Revision 3 Page 27 of 39 MFLPD  Monitor Frequency: 3D case at each 50 MWe reduction in electrical output when MFLPD > 0.900. Contingency: Refer to CPS 2202.03 for correction of power distribution problems. 0.980 N/A Fuel Conditioning Limits Monitor Frequency:
98.7%              N/A Contingency: Insert control rods as recommended by the Reactor Engineer.
: 1. Approach to threshold (when PCRAT > 0.900) - use 3D cases (PCIOMR edits) at ~5% increase in power;
MFLCPR Monitor Frequency: 3D case at each 50 MWe increase in electrical output when MFLCPR > 0.900.                                                                             0.980             N/A Contingency: Refer to CPS 2202.03 for correction of power distribution problems.
: 2. Fuel conditioning ramp rate (when P-Max (PC,KWTH) > 0.0) - Use 3D cases (PCIOMR edits) at ~30 minute intervals.
 
(Contingency:  Refer to NF-AB-440 for actions to take if fuel conditioning limits are exceeded.)
Approach to threshold:
P-Max (PC,KWTH)
= 0.45  Fuel Conditioning Ramp Rate:
0.45 kw/ft/hr (nominal ramp rate is 0.35 kw/ft/hr)
 
ReMA Step Complete: _________________/______  Verified by:  _______________/_______                                                          Reactor Operator/Date                                            Unit Supervisor/Date
 
OP-AB-300-1003Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step  4    of  4                   


Reactivity Maneuver Plan #
OP-AB-300-1003 Revision 3 Page 27 of 39 MFLPD Monitor Frequency: 3D case at each 50 MWe reduction in electrical output when MFLPD > 0.900.                                                                          0.980          N/A Contingency: Refer to CPS 2202.03 for correction of power distribution problems.
C12-0001  Description of Step:    
Fuel Conditioning Limits                                                            Approach to Monitor Frequency:                                                                    threshold:
: 1. Approach to threshold (when PCRAT > 0.900) - use 3D cases (PCIOMR            P-Max (PC,KWTH) edits) at ~5% increase in power;                                                    = 0.45
: 2. Fuel conditioning ramp rate (when P-Max (PC,KWTH) > 0.0) - Use 3D cases (PCIOMR edits) at ~30 minute intervals.                                      Fuel Conditioning Ramp Rate:
0.45 kw/ft/hr (Contingency: Refer to NF-AB-440 for actions to take if fuel conditioning limits (nominal ramp rate are exceeded.)                                                                    is 0.35 kw/ft/hr)
ReMA Step Complete: _________________/______ Verified by: _______________/_______
Reactor Operator/Date                            Unit Supervisor/Date


OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 4      of 4                                        Reactivity Maneuver Plan # C12-0001 Description of Step:
Maintain power with flow adjustments and control rod notching. Xenon will be building in Reactor Engineer will provide guidance to ensure margins are maintained. This will continue until the next down power to achieve target rod pattern (~24 hours later). A separate ReMA will be provided for this downpower.
Maintain power with flow adjustments and control rod notching. Xenon will be building in Reactor Engineer will provide guidance to ensure margins are maintained. This will continue until the next down power to achieve target rod pattern (~24 hours later). A separate ReMA will be provided for this downpower.
Note: The FCL critical parameter has been specified at 99.7%, which is within 1.0% of the 100.7% limit. The reduced margin is being specified to accommodate the xenon transient.
Note: The FCL critical parameter has been specified at 99.7%, which is within 1.0% of the 100.7% limit. The reduced margin is being specified to accommodate the xenon transient.
QNE presence required in the Control Room? Yes X*   No           Onsite Only? Yes No     *RE coverage will be provided consistent with OP-AB-300-1003 & NF-AB-701.
QNE presence required in the Control Room? Yes X* No                           Onsite Only? Yes         No
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init.P arameter Value or Range Init. Generator Output N/A N/A MFLCPR < 0.980 Core Power (MWt or %)  
*RE coverage will be provided consistent with OP-AB-300-1003 & NF-AB-701.
~ 96.9% (~3365 MWth)
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter               Value or Range Init.               Parameter            Value or Range Init.
MFLPD < 0.980  Core Flow (Mlb/hr or %)
Generator Output                     N/A           N/A   MFLCPR                           < 0.980
N/A N/A MAPRAT N/A N/A FCL (%) < 98.7%           Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and contingency actions (if needed)
                                  ~ 96.9%
High Low FCL Monitor Frequency: Normal monitoring Contingency: Insert control rods in reverse order of sequence as determined by Reactor Engineer. 99.7%  MFLCPR Monitor Frequency: Normal monitoring Contingency: Refer to CPS 2202.03 for correction of power distribution problems. 0.980  MFLPD Monitor Frequency: Normal monitoring Contingency: Refer to CPS 2202.03 for correction of power distribution problems. 0.980 ReMA Step Complete: _________________/______ Verified by: _______________/_______                                                         Reactor Operator/Date                                             Unit Supervisor/Date
Core Power (MWt or %)                                     MFLPD                            < 0.980
 
(~3365 MWth)
FIGURE 1:  CPS STABILITY CONTROL & POWER/FLOW OPERATING MAPFIGURE 1:  CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP 0 347 695 1042 1389 1737 2084 2431 2778 3126 34730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)
Core Flow (Mlb/hr or %)               N/A           N/A   MAPRAT                             N/A           N/A FCL (%)                           < 98.7%
THERMAL POWER -  MWTh 0 10 20 30 40 50 60 70 80 90 1000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWERRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE  60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND  < 60% FLOW]90% FCL (Typ.)  80%25 868 MELLLA Limit  [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]
Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High            Low contingency actions (if needed)
0 347 695 1042 1389 1737 2084 2431 2778 3126 34730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)
FCL Monitor Frequency: Normal monitoring 99.7%
THERMAL POWER -  MWTh 0 10 20 30 40 50 60 70 80 90 1000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWERRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE  60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND  < 60% FLOW]90% FCL (Typ.)  80%25 868 MELLLA Limit  [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]
Contingency: Insert control rods in reverse order of sequence as determined by Reactor Engineer.
MFLCPR Monitor Frequency: Normal monitoring 0.980 Contingency: Refer to CPS 2202.03 for correction of power distribution problems.
MFLPD Monitor Frequency: Normal monitoring 0.980 Contingency: Refer to CPS 2202.03 for correction of power distribution problems.
ReMA Step Complete: _________________/______ Verified by: _______________/_______
Reactor Operator/Date                             Unit Supervisor/Date


ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station:
FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0          10        20      30        40        50        60        70        80          90            100              110 3473                                                                                                                                      100 MELLLA Limit [100.7% FCL]
Clinton  Valid Date(s):    XX/XX/XXXX      Reactivity Maneuver Plan #:
3126                                                                                                                                      90 Restricted                                                                                    90% FCL (Typ.)
C11-Simu.4 Multiple Activations Allowed?
2778              Zone                                                                                          80%
No    (If yes, CRS may make additional copies) Prepared by:  Roger QNE /
80 THERMAL POWER - MWTh 2431                                                                                                                                      70 PERCENT THERMAL POWER 2084                                                                                                                                      60 60%
XX/XX/XX Reviewed by:
CONTROLLED 1737                                                                                                                                      50 ENTRY REGION 50%
Joe QNE                    /
1389                                                                                                                                      40 40%
XX/XX/XX        Reactor Engineer       /      Date      Qualified Nuclear Engineer /       Date Approved by:    Michelle QNE Boss/
1042                                                                                                                                      30 868                                                                                                                                      25 695                                                                                                                                      20 OPRM ENABLED        CAVITATION 347            OPRM OPERABLE                                                    REGION          PROTECTION LINES                        10
XX/XX/XX Authorized by:    / XX/XX/XX                                      RE Manager            /    Date    Senior Reactor Operator  /      Date NF Review Carlos Quark          /
[21.6 % CTP, 750 MWth]                      SINGLE LOOP       [> 25% CTP AND      (HIGH SPEED, 2 PUMP ENVELOPE            < 60% FLOW]       OPERATION) 0                                                                                                                                        0 0.0         8.5      16.9     25.4     33.8       42.3      50.7      59.2      67.6        76.1         84.5            93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)
XX/XX/XX  NF Reviewer /         Date ReMA Activated: 
/ XX/XX/XX ReMA Terminated: 
/ XX/XX/XX     Unit Supervisor        /    Date  Unit Supervisor     /       Date Title of Evolution:  Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift. Reactivity Maneuver Steps Extended General Issues:  Select desired amount of power reduction 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:  The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1 of    1                                                    Reactivity Maneuver Plan # C11-Simu.4 Description of Step : From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.


Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes
ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton          Valid Date(s): XX/XX/XXXX                  Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed?           No             (If yes, CRS may make additional copies)
* No   *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
Prepared by: Roger QNE                        / XX/XX/XX        Reviewed by:        Joe QNE                  / XX/XX/XX Reactor Engineer      /      Date                          Qualified Nuclear Engineer /    Date Approved by:        Michelle QNE Boss/ XX/XX/XX                Authorized by:                                / XX/XX/XX RE Manager          /    Date                                Senior Reactor Operator /     Date NF Review Carlos Quark                / XX/XX/XX NF Reviewer /         Date ReMA Activated:                                  / XX/XX/XX    ReMA Terminated:                              / XX/XX/XX Unit Supervisor        /   Date                                  Unit Supervisor    /   Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction
High  Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.
: 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:
57.3 % N/A    Step Complete: ___________________
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
/_______          Verified by: _________________
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet
/_______                                        Reactor Operator        /    Date                                              Unit Supervisor          /    Date     


CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
STEP      1    of    1                                          Reactivity Maneuver Plan # C11-Simu.4 Description of Step :
This form was updated as a result of the procedure revision.
From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.
ROUTINE USE ORIGINATOR:
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.
Christian Small CLASS CODE:
QNE presence required in the Control Room? Yes
SNNN1    SQR: Mark Vandermyde APPROVAL DATE:
* No *
04/25/05  CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages                                  Rev. 4  Page  1 of 2
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                  Parameter            Value or Range  Init.
Core Power (MWth or %)                  N/A            N/A MFLCPR                              N/A        N/A Core Flow (Mlb/hr or %)                  N/A            N/A MFLPD                                N/A        N/A FCL (%)                                  N/A            N/A MAPRAT                              N/A        N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                        High            Low FCL                                                                                    57.3 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.
Contingency: Insert control rods in reverse order sequence to reduce FCL.
Step Complete: ___________________/_______                        Verified by: _________________/_______
Reactor Operator      /   Date                        Unit Supervisor    /  Date


CPS 2202.04F001 Rev. 4  Page  2 of 2 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4
CPS   2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
 
* This form was updated as a result of the procedure revision.
Core Conditions Expected
ROUTINE USE ORIGINATOR: Christian Small                        CLASS CODE: SNNN1 SQR: Mark Vandermyde                APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change #      Date     List of Affected Pages n
:
o p
Estimated Date/Time of criticality 
q r
        /
Rev. 4                                                    Page   1 of 2
Xenon    Increasing          Decreasing None  Moderator Temperature:
468   
&deg;F  Cycle Exposure:
9000 MWD/T  Sequence:
A2 - Simulator Comments:
Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup
__________________________________________
 
Estimated Critical Position
 
Criticality is estimated to occur between steps 17 and     35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse
 
order up to and including step _______ and investigate with the Reactor Engineer
 
and Nuclear Fuels.
 
For BOC, if criticality is not reached at the completion of step ________, insert
 
rods in reverse order, up to and including step ________ and investigate with the
 
Reactor Engineer and Nuclear Fuels.  
 
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17    or after step 35   , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality. 


CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:
Estimated Date/Time of criticality            /
Xenon                Increasing Decreasing
:      None Moderator Temperature:  468    &deg;F Cycle Exposure:            9000    MWD/T Sequence:                A2 - Simulator Comments:            Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps      17    and      35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.
For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step      17    or after step 35  , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.
Instructions
Instructions
* Expect the reactor to become critical at any time.
* Expect the reactor to become critical at any time.
* Move control rods with careful attention.
* Move control rods with careful attention.
* Monitor nuclear instruments during and following rod movements.
* Monitor nuclear instruments during and following rod movements.
* If a nontransient period of less than 30 sec occurs, insert rods and
* If a nontransient period of less than 30 sec occurs, insert rods and investigate.
 
* Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____
investigate.
___25____ ___26____ ___27____ ___28____
* Perform 1/M plots at steps ___
___29____ ___31____ ___33____ ___35____
17____  ___19____ ___22____ ___23____   ___25____ ___26____ ___27____ ___28____   ___29____ ___31____ ___33____ ___35____ ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.  
ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.
 
Michelle QNE Boss                               /
Michelle QNE Boss        
Reactor Engineer                     Date       Time Rev. 4                                                    Page   2 of 2
                    /
Reactor Engineer                   Date       Time Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
Three                    Operating Test No.:
08-01  Examiners: ____________________________   Operators: ____________________          ____________________________           
 
____________________
____________________________                    ____________________


Appendix D                                      Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station              Scenario No.: Three                Operating Test No.: 08-01 Examiners: ____________________________                                  Operators: ____________________
Initial Conditions:
Initial Conditions:
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by th e electrode boiler, hot restart. Thunderstorm storms are expected in the area within the next hour.  
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.
 
Thunderstorm storms are expected in the area within the next hour.
Turnover:
Turnover:
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 2. Pull Rods to criticality.
: 2. Pull Rods to criticality.
Event No. Malf. No.
Event           Malf. No.       Event                                          Event No.                            Type*                                       Description 1       NA                   N-BOP       Test the Generator Emergency Seal Oil Pump 2       Rod                   C-ATC       Continue with startup, discovers Uncoupled rod 0825I_ACTIONA
Event Type* Event Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump 2 Rod 0825I_ACTIONA-Rod uncoupled C-ATC TS-CRS  Continue with startup, discovers Uncoupled rod 3 NA R-ATC Pull rods for criticality 4 SRM_BI_ACTIO N2 and 1 I-ATC B SRM fails 5 CDSR_VAC_P MP_A I-BOP Vacuum Pump Trip 6 SRM_CI_ACTIO N2 and 1 TS-CRS A SRM fails   7 Override C-BOP RCIC drain trap level high 8 YARITPLA_1 Override M-ALL RCIC unisolable steam leak 9 YP_XMFTB_500 2 M-ALL Reactor scrams on initiation of RPT/ARI 10 CAM1PR006AT V_VALUE1 CAM1PR006CT
            -Rod uncoupled        TS-CRS 3       NA                   R-ATC       Pull rods for criticality 4       SRM_BI_ACTIO         I-ATC       B SRM fails N2 and 1 5       CDSR_VAC_P           I-BOP       Vacuum Pump Trip MP_A 6       SRM_CI_ACTIO         TS-CRS     A SRM fails N2 and 1 7       Override             C-BOP       RCIC drain trap level high 8       YARITPLA_1           M-ALL       RCIC unisolable steam leak Override 9       YP_XMFTB_500         M-ALL       Reactor scrams on initiation of RPT/ARI 2
 
10       CAM1PR006AT           M-ALL      Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC
V_VALUE1 CAM1PR006DT
        *(N)ormal,  (R)eactivity,    (I)nstrument,    (C)omponent,        (M)ajor Page 1 of 2


V_VALUE1 CAM1PR006BT
Appendix D                               Scenario Outline                               Form ES-D-1 Scenario No.: Three                                         Operating Test No.: 08-01 Narrative Summary Event #                                   Description
 
V_VALUE1 VGCEFUSE_V
 
677503CC VGBZFUSE_V 421691CC M-ALL Radiation monitor fails to initiate an isolation *(N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
Three                     Operating Test No.:
08-01 Narrative Summary  
 
Event # Description
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 3. Withdrawal rods for criticality.
: 3. Withdrawal rods for criticality.
: 4. 'B' SRM fails causing a rod block requiring bypassing to proceed with startup.
: 4. B SRM fails causing a rod block requiring bypassing to proceed with startup.
 
Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
Requiring a review of Technical Sp ecification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 6. 'A' SRM fails causing a rod block and requiring entry into Technical Specification  
: 6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
 
3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.
EOP 8,1A,1 Critical tasks:
* Manual insertion of ARI prior to exceeding Maximum safe temperature
* Manually shutdown and isolate VF and startup VG Page 2 of 2


1A will be exited and EOP-1 will be entered.
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                        08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.  
(Plant power level)
Subcritical, with equilibrium Xenon, 3 days            CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt                                                CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.
Comments, evolutions, problems, etc.
Online Safety is Green                                Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by
                                                                - First Priority.
the electrode boiler Continue with Reactor startup.
1


EOP 8,1A,1  Critical tasks:  Manual insertion of ARI prior to exceeding Maximum safe temperature  Manually shutdown and isolate VF and startup VG Page    of 2 2
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):        1                                                                    Page   1 of  1
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 1  Shift Turnover Information  Day of week and shift  Today Day Shift  Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) Subcritical, with equilibrium Xenon, 3 days after shutdown  CPS 3001.01 complete to step 8.2.5  na- MWt  CPS 3002.01 at step 8.5.2  na- MWe   27.0 Mlbm/hr CORE FLOW    Thermal Limit Problems/Power Evolutions  Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12            Existing LCOs, date of next surveillance None        Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT.
Comments, evolutions, problems, etc. Online Safety is Green  Steam seals and Auxiliary Steam is provided by the electrode boiler Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT
-  First Priority.
Continue with Reactor startup.


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                    08-01  2  Operator Actions Event No.(s):
==
1  Page 1 of 1
Description:==
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior BOP      Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:
* Depress Gen H2 Emerg Seal Oil Pump Test push-button
* Verify Gen H2 Emergency Seal Oil Pump starts
* Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
* Stop the Gen H2 Emergency Seal Oil Pump
* Verify annunciators and computer point off RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Emergency Seal Oil Pump test complete NOTES:
2


== Description:==
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                           08-01 Operator Actions Event No.(s):           2                                                                   Page   1 of 1
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP  Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:  Depress Gen H2 Emerg Seal Oil Pump Test push-button  Verify Gen H2 Emergency Seal Oil Pump starts  Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK  Stop the Gen H2 Emergency Seal Oil Pump  Verify annunciators and computer point off RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus:  Emergency Seal Oil Pump test complete NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 3 Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
== Description:==
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicant's Actions or Behavior RO CPS 5006-5G, Rod Overtravel: Determine the rod that alarmed 08-25. Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time     Position                               Applicants Actions or Behavior RO     CPS 5006-5G, Rod Overtravel:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button. 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod. 3) Determine if the rod has recoupled by performing a coupling check 4) If the rod has recoupled, return to normal operation.  
* Determine the rod that alarmed 08-25.
* Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
: 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
: 3) Determine if the rod has recoupled by performing a coupling check
: 4) If the rod has recoupled, return to normal operation.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2
* When the rod is recoupled declare the rod Operable and exit the LCOs
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:
3


BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                          08-01 Event No.(s):                3                                                                Page    1 of 1
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2  When the rod is recoupled declare the rod Operable and exit the LCOs  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  Rod has been recoupled and SRO applied LCO actions 


NOTES:          
==
Description:==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO      Sequence:
* Withdraw rods for criticality
* Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
* Depress the POWER ON button
* Select the SRMs
* Depress the drive out button until withdrawn
* Depress the drive out button
* Announce reactor is critical BOP
* Announce reactor criticality
* Log in the date/time criticality was achieved, and criticality data:
* Rod Sequence
* Group/Array
* Rod
* Rod Position
* SRM reading and Period
* RR loop temperature
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above
* Stays in a position of oversite
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
NOTES:
4


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 4 Event No.(s):
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         4                                                                    Page   1 of 1
3  Page 1 of 1


== Description:==
==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod Sequence: Withdraw rods for criticality  Prior to exceeding 1 x 10 6 cps, withdraw SRM's Per CPS 3306.01, SRM/IRM step 8.1.2:
Description:==
Depress the POWER ON button  Select the SRMs  Depress the drive out button until withdrawn  Depress the drive out button  Announce reactor is critical BOP Announce reactor criticality  Log in the date/time criticality was achieved, and criticality data:  Rod Sequence  Group/Array  Rod  Rod Position  SRM reading and Period  RR loop temperature  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                                 Applicants Actions or Behavior RO       Per CPS 5006-2H, SRM Inop:
SRO Directs actions listed above Stays in a position of oversite  Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
* Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
* Place the SRM Bypass joy stick to B SRM
* Observe the rod block clears BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Directs Bypassing SRM B and continue with the startup
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B SRM has been bypassed IAW CPS 3306.01.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  5  Operator Actions Event No.(s):
If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.
4  Page 1 of 1
5


== Description:==
D-2, Dynamic Simulator Scenario 3              EXAM DATE: 08/24/09                        08-01 Operator Actions Event No.(s):         5                                                                  Page    1 of  1
'B' SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues:  Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop:  Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:  Place the SRM Bypass joy stick to B SRM  Observe the rod block clears BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews  TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Directs Bypassing SRM B and continue with the startup  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  B SRM has been bypassed IAW CPS 3306.01.
NOTES: If the B RO appears about to perform the operation to bypass the 'B' SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  6  Operator Actions Event No.(s):
==
5 Page 1 of 1
Description:==
Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time      Position                                Applicants Actions or Behavior BOP      Per CPS 3112.01, Condenser Vacuum
* Dispatches field operator to perform local actions to start B Vacuum Pump
* After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 4004.02 Loss of Vacuum
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B Vacuum Pump is in operation NOTES:
6


== Description:==
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         6                                                                 Page   1 of 1
Vacuum Pump trips Initiation:  After crew has addressed SRM problem, on the signal of lead examiner Cues:  Annunciator CPS 5019-1A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum  Dispatches field operator to perform local actions to start B Vacuum Pump  After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Enters CPS 4004.02 Loss of Vacuum  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  B Vacuum Pump is in operation NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 7  Operator Actions Event No.(s):
6 Page 1 of 1


== Description:==
==
'A' SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop: Reports annunciator to CRS Monitors reactor to ensure operati ons remain within established bands BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Description:==
SRO Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                             Applicants Actions or Behavior RO     Per CPS 5006-2H, SRM Inop:
Terminus: ITS actions reviewed and entered NOTES: TO LEAD EVALUATOR: Ensure this event is started before IRM's are on Range 2 to ensure a Tech Spec call can be made.  
* Reports annunciator to CRS
* Monitors reactor to ensure operations remain within established bands BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: ITS actions reviewed and entered NOTES:
TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.
7


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 8  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         7                                                                   Page   1 of 1
7 Page 1 of 1


== Description:==
==
RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicant's Actions or Behavior BOP Per CPS 5063-2C, RCIC Steam Drain Trap Level High
Description:==
:  Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually. Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open Reports failure RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time     Position                                 Applicants Actions or Behavior BOP       Per CPS 5063-2C, RCIC Steam Drain Trap Level High:
SRO Directs actions listed above. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.  
* Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
* Reports failure RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.
NOTES:
8


NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                             08-01 Operator Actions Event No.(s):               8,9                                                                   Page   1 of 2
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 9  Operator Actions Event No.(s):
8,9 Page 1 of 2


== Description:==
==
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown, check and report power unchanged Arms and depresses MANUAL SCRAM push-buttons Initiates ARI Reports control rods inserted, shutdown criteria met Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to mon itor and control RPV level and press.
Description:==
BOP Reports secondary containment high temperature and rad alarms to SRO   Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports secondary containment Max Safe temperature being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time     Position                                   Applicants Actions or Behavior RO     Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO
* Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram:
* Place mode switch in Shutdown, check and report power unchanged
* Arms and depresses MANUAL SCRAM push-buttons Critical Task
* Initiates ARI
* Reports control rods inserted, shutdown criteria met
* Operate FW to control level 3 to 8
* Check rods, reports shutdown criteria is met
* Report level and pressure are following expected trends
* Stabilize pressure <1065 psig
* Coordinates with BOP operator to monitor and control RPV level and press.
BOP
* Reports secondary containment high temperature and rad alarms to SRO
* Makes plant announcement for reactor scram
* Should make plant announcement to evacuate Fuel/Aux buildings.
* Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
* Verifies operation of area coolers
* Verifies operation of VF
* Evacuates affected areas of Secondary Containment
* Monitors area temperatures, levels and radiation levels
* Reports secondary containment Max Safe temperature being exceeded to SRO
* Coordinates with RO to monitor and control RPV level and press NOTES:
9


NOTES:
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                         08-01 Event No.(s):             8,9                                                           Page     2 of 2 Time     Position                                 Applicants Actions or Behavior SRO     Directs entry into EOP-8 and EOP actions as entry conditions are met:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 10 Event No.(s):
: 1. Operate VF
8,9 Page 2 of 2 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met: 1. Operate VF 2. Operate area coolers
: 2. Operate area coolers
: 3. Hold floor drain sump levels below max. normal
: 3. Hold floor drain sump levels below max. normal
: 4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting 5. Per EOP-8/CPS 4001.02: Directs BOP to isolate RCIC steam lines
: 4. Isolate all discharges into the affected area except systems needed for:
: 6. Direct a scram prior to exceeding Maximum safe temperature
* EOP Actions
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.: Inhibit ADS Arm and Depress MANUAL SCRAM pushbuttons Initiate ARI
* Fire Fighting
: 8. Directs additional actions: Notification of Radiation Protection (RP) Department Evacuate affected areas of Secondary Containment
: 5. Per EOP-8/CPS 4001.02:
* Directs BOP to isolate RCIC steam lines Critical Task      6. Direct a scram prior to exceeding Maximum safe temperature
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
* Inhibit ADS
* Arm and Depress MANUAL SCRAM pushbuttons
* Initiate ARI
: 8. Directs additional actions:
* Notification of Radiation Protection (RP) Department
* Evacuate affected areas of Secondary Containment
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: a. Mode Switch to SHUTDOWN
: a. Mode Switch to SHUTDOWN
Line 1,236: Line 1,750:
: c. Control RPV Water Level between Level 3 and Level 8
: c. Control RPV Water Level between Level 3 and Level 8
: d. Stabilize RPV pressure below 1065 psig
: d. Stabilize RPV pressure below 1065 psig
: e. Verify needed automatic actions: Isolations   ECCS Start DG Start         Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:   Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 11  Operator Actions Event No.(s):
: e. Verify needed automatic actions:
10 Page 1 of 1
* Isolations
* ECCS Start
* DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:
10
 
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         10                                                                 Page   1 of 1


== Description:==
== Description:==
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicant's Actions or Behavior BOP   Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG: Verify alarming condition of 1RIX-PR006A-D Report EOP-8 entry condition Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time     Position                                   Applicants Actions or Behavior BOP     Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:
SRO Directs entry into EOP-8 and EOP actions as entry conditions are met. When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Startup VG CPS 3319.01, Standby Gas General:
* Verify alarming condition of 1RIX-PR006A-D
On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Report EOP-8 entry condition Critical Task
Terminus:   RPV level stable and under control in required band Reactor is Scrammed Effort has been made to isolate RCIC steam lines Failed automatic isolation and actuation (VF/VG) manually performed Upon approval of lead examiner NOTES:       Critical Task Critical Task Critical Task Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 12  Simulator Operator Instructions Initial Setup
* Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
* Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs entry into EOP-8 and EOP actions as entry conditions are met.
Critical Task
* When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
* Startup VG CPS 3319.01, Standby Gas General:
* On transient, positions himself as command authority on the unit.
* Acknowledges immediate operator actions and directs subsequent actions.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus:
* RPV level stable and under control in required band
* Reactor is Scrammed
* Effort has been made to isolate RCIC steam lines
* Failed automatic isolation and actuation (VF/VG) manually performed
* Upon approval of lead examiner NOTES:
11
 
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                 08-01 Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
Line 1,251: Line 1,791:
: 6. Turn on and advance recorders
: 6. Turn on and advance recorders
: 7. Reset SRM A drawer
: 7. Reset SRM A drawer
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 9. Provide and ECP and RE instructions 1 0. Verify the AR/PR server is running and stabilize AR/PR 1 1. Verify TT alarm is reset 1 2. Verify Rod Drive pressure at 250#
: 9. Provide and ECP and RE instructions
1 3. Hang OOS tags per turnover on #2 SAC 1 4. Identify T/S issues associated with OOS and turnover 1 5. Verify simulator conditions match the turnover 1 6. Provide marked up CPS 3001.01 complete to step 8.2.5 1 7. Provide a marked up CPS 3002.01 complete to step 8.6
: 10. Verify the AR/PR server is running and stabilize AR/PR
: 11. Verify TT alarm is reset
: 12. Verify Rod Drive pressure at 250#
: 13. Hang OOS tags per turnover on #2 SAC
: 14. Identify T/S issues associated with OOS and turnover
: 15. Verify simulator conditions match the turnover
: 16. Provide marked up CPS 3001.01 complete to step 8.2.5
: 17. Provide a marked up CPS 3002.01 complete to step 8.6
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions  
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 13 Event Triggers and Role Play Event # 1. Test the Generator Emergency Seal Oil Pump
D-2, Dynamic Simulator Scenario 3                     EXAM DATE: 08/24/09                           08-01 Event Triggers and Role Play Event #
: 1. Test the Generator Emergency Seal Oil Pump
: a. No trigger.
: a. No trigger.
: 2. Uncoupled rod
: 2. Uncoupled rod
Line 1,265: Line 1,813:
: 3. Withdraw Rods To criticality
: 3. Withdraw Rods To criticality
: a. No triggers
: a. No triggers
: 4. 'B' SRM fails
: 4. B SRM fails
: a. Remote trigger 2 on request from lead evaluator
: a. Remote trigger 2 on request from lead evaluator
: b. If SRM 'B' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 5. Vacuum Pump trip
: 5. Vacuum Pump trip
: a. Remote trigger 3 on request from lead evaluator
: a. Remote trigger 3 on request from lead evaluator
: b. Role Play- Field operator
: b. Role Play- Field operator
: 6. 'A' SRM fails
: 6. A SRM fails
: a. Remote trigger 4 on request from lead evaluator
: a. Remote trigger 4 on request from lead evaluator
: b. If SRM 'A' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 7. RCIC drain trap level high
: 7. RCIC drain trap level high
Line 1,281: Line 1,829:
: 8. RCIC unisolable steam leak
: 8. RCIC unisolable steam leak
: a. Remote trigger 6 on request from lead evaluator
: a. Remote trigger 6 on request from lead evaluator
: b. If RCIC ATM's are checked they read 10 times higher than on the last 9000.01 reading.
: b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: d. If valve breakers are checked, no problems are found.
: d. If valve breakers are checked, no problems are found.
Line 1,289: Line 1,837:
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: a. No triggers
: a. No triggers
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
 
13
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM  ILT 08-1 Exam Scenario 3 REVISION 00
 
DEVELOPER:
Tom Pickley 
 
REVIEWED BY:
Simulator Instructor
 
APPROVED BY:
 
/  Operations Date Overview Makeup/Reject:
A,B,C CP's are in service. RO trai n #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Plant Status On Line Risk Green  Reactor  Operational Condition: Mode  2 Total Core Flow: __26.9___ mlb/hr FCV Position: A:  ___90____%      B:  _
_90____% Reactor Power __0__%  (<=100%)    _0__ MWt  (<=3473)      _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi  (< 1045) In service SDC loop None    MODE 2 Containment Suppression Pool Temperature: _75.5_ F
(<=93.1 F) Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.4__ psi (0 to 1 psig) Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
BOP  Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1):
1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
_78_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
:  None  Comments: See Turnover Sheet
 
From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
 
ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station:
Clinton  Valid Date(s):    XX/XX/XXXX      Reactivity Maneuver Plan #:
C11-Simu.4 Multiple Activations Allowed?
No    (If yes, CRS may make additional copies) Prepared by:  Roger QNE /
XX/XX/XX Reviewed by:
Joe QNE                    /
XX/XX/XX        Reactor Engineer        /      Date      Qualified Nuclear Engineer /        Date Approved by:    Michelle QNE Boss/
XX/XX/XX Authorized by:    / XX/XX/XX                                      RE Manager            /    Date    Senior Reactor Operator  /      Date NF Review Carlos Quark          /
XX/XX/XX  NF Reviewer /        Date ReMA Activated: 
/ XX/XX/XX ReMA Terminated: 
/ XX/XX/XX      Unit Supervisor        /    Date  Unit Supervisor      /      Date Title of Evolution:  Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift. Reactivity Maneuver Steps Extended General Issues:  Select desired amount of power reduction 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:  The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1  of    1                                                    Reactivity Maneuver Plan # C11-Simu.4 Description of Step : From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.
 
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes
* No  *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
High  Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.
57.3 % N/A    Step Complete: ___________________
/_______          Verified by: _________________
/_______                                        Reactor Operator        /    Date                                              Unit Supervisor          /    Date     
 
CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
This form was updated as a result of the procedure revision.
ROUTINE USE ORIGINATOR:
Christian Small CLASS CODE:
SNNN1    SQR: Mark Vandermyde APPROVAL DATE:
04/25/05  CURRENT CHANGES TO GENERAL REVISION Change #  Date  List of Affected Pages                                  Rev. 4  Page  1 of 2
 
CPS  2202.04F001 Rev. 4  Page  2 of 2 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4


Core Conditions Expected
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER:                     Tom Pickley REVIEWED BY:
:
Simulator Instructor APPROVED BY:                         /
Estimated Date/Time of criticality 
Operations                      Date
        /
Xenon    Increasing          Decreasing None  Moderator Temperature:
468   
&deg;F  Cycle Exposure:
9000 MWD/T  Sequence:
A2 - Simulator Comments:
Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup
__________________________________________


Estimated Critical Position
Overview Makeup/Reject:            A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                      RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                      N/A Electrical:                6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste:                  FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Plant Status On Line Risk Green Reactor Operational Condition:          Mode 2 Total Core Flow:                __26.9___ mlb/hr FCV Position:                  A: ___90____%        B: _ _90____%
Reactor Power                  __0__% (<=100%) _0__ MWt (<=3473)                _0__ Mwe Xenon:                          Stable RPV Level                      _26.7_ in Narrow Range RPV Pressure                    _600__ psi (< 1045)
In service SDC loop            None MODE 2 Containment Suppression Pool Temperature:            _75.5_ F                        (<=93.1 F)
Suppression Pool Level                  _19.1_ ft                      (19 ft 0 to 19 ft 5 in)
Drywell Pressure                        _0.4__ psi                      (0 to 1 psig)
Drywell to Containment dp:              _0.4__ psi                      >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:            _100__ F                        (<=146.53 F)
Secondary Containment:                  _0.74_ in WG                    (>= 0.25 in WG vacuum)
BOP                                                            Plant Chemistry Condenser Vacuum:                        _27_ in Hg            CPI (goal < 1.1):                1.00 Off - Gas Flow:                          _12.8_ scfm          Reactor Sulfates (goal < 2)      1.31 ppb Condensate Temperature:                  _78_ F                Reactor Chlorides:                0.51 ppb Generator Reactive Load:                _0_MVARS              FW Iron (goal < 2.1)              0.85 ppb Protected Equip: None Comments:      See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety


Criticality is estimated to occur between steps 17 and     35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse
ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton          Valid Date(s): XX/XX/XXXX                  Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed?            No              (If yes, CRS may make additional copies)
Prepared by: Roger QNE                        / XX/XX/XX        Reviewed by:        Joe QNE                  / XX/XX/XX Reactor Engineer      /      Date                          Qualified Nuclear Engineer /    Date Approved by:        Michelle QNE Boss/ XX/XX/XX                Authorized by:                                / XX/XX/XX RE Manager          /    Date                                Senior Reactor Operator /      Date NF Review Carlos Quark                / XX/XX/XX NF Reviewer /        Date ReMA Activated:                                  / XX/XX/XX    ReMA Terminated:                              / XX/XX/XX Unit Supervisor        /  Date                                  Unit Supervisor    /  Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction
: 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet


order up to and including step _______ and investigate with the Reactor Engineer
STEP      1    of    1                                          Reactivity Maneuver Plan # C11-Simu.4 Description of Step :
From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.
QNE presence required in the Control Room? Yes
* No *
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                  Parameter            Value or Range  Init.
Core Power (MWth or %)                  N/A            N/A MFLCPR                              N/A        N/A Core Flow (Mlb/hr or %)                  N/A            N/A MFLPD                                N/A        N/A FCL (%)                                  N/A            N/A MAPRAT                              N/A        N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                        High            Low FCL                                                                                    57.3 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.
Contingency: Insert control rods in reverse order sequence to reduce FCL.
Step Complete: ___________________/_______                        Verified by: _________________/_______
Reactor Operator      /  Date                        Unit Supervisor    /  Date


and Nuclear Fuels.  
CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
 
* This form was updated as a result of the procedure revision.
For BOC, if criticality is not reached at the completion of step ________, insert
ROUTINE USE ORIGINATOR: Christian Small                        CLASS CODE: SNNN1 SQR: Mark Vandermyde                APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change #      Date      List of Affected Pages n
 
o p
rods in reverse order, up to and including step ________ and investigate with the
q r
 
Rev. 4                                                    Page   1 of 2
Reactor Engineer and Nuclear Fuels.  
 
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17    or after step 35   , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality. 


CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:
Estimated Date/Time of criticality            /
Xenon                Increasing Decreasing
:      None Moderator Temperature:  468    &deg;F Cycle Exposure:            9000    MWD/T Sequence:                A2 - Simulator Comments:            Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps      17    and      35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.
For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step      17    or after step 35  , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.
Instructions
Instructions
* Expect the reactor to become critical at any time.
* Expect the reactor to become critical at any time.
* Move control rods with careful attention.
* Move control rods with careful attention.
* Monitor nuclear instruments during and following rod movements.
* Monitor nuclear instruments during and following rod movements.
* If a nontransient period of less than 30 sec occurs, insert rods and
* If a nontransient period of less than 30 sec occurs, insert rods and investigate.
 
* Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____
investigate.
___25____ ___26____ ___27____ ___28____
* Perform 1/M plots at steps ___
___29____ ___31____ ___33____ ___35____
17____  ___19____ ___22____ ___23____   ___25____ ___26____ ___27____ ___28____   ___29____ ___31____ ___33____ ___35____ ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.  
ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.
 
Michelle QNE Boss                               /
Michelle QNE Boss        
Reactor Engineer                     Date       Time Rev. 4                                                    Page   2 of 2
                    /
Reactor Engineer                   Date       Time Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
Three                    Operating Test No.:
08-01  Examiners: ____________________________   Operators: ____________________          ____________________________           
 
____________________
____________________________                    ____________________


Appendix D                                      Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station              Scenario No.: Three                Operating Test No.: 08-01 Examiners: ____________________________                                  Operators: ____________________
Initial Conditions:
Initial Conditions:
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by th e electrode boiler, hot restart. Thunderstorm storms are expected in the area within the next hour.  
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.
 
Thunderstorm storms are expected in the area within the next hour.
Turnover:
Turnover:
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 2. Pull Rods to criticality.
: 2. Pull Rods to criticality.
Event No. Malf. No.
Event           Malf. No.       Event                                          Event No.                            Type*                                       Description 1       NA                   N-BOP       Test the Generator Emergency Seal Oil Pump 2       Rod                   C-ATC       Continue with startup, discovers Uncoupled rod 0825I_ACTIONA
Event Type* Event Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump 2 Rod 0825I_ACTIONA-Rod uncoupled C-ATC TS-CRS  Continue with startup, discovers Uncoupled rod 3 NA R-ATC Pull rods for criticality 4 SRM_BI_ACTIO N2 and 1 I-ATC B SRM fails 5 CDSR_VAC_P MP_A I-BOP Vacuum Pump Trip 6 SRM_CI_ACTIO N2 and 1 TS-CRS A SRM fails delete   7 Override C-BOP RCIC drain trap level high 8 YARITPLA_1 Override M-ALL RCIC unisolable steam leak 9 YP_XMFTB_500 2 M-ALL Reactor scrams on initiation of RPT/ARI 10 CAM1PR006AT V_VALUE1 CAM1PR006CT
            -Rod uncoupled        TS-CRS 3       NA                   R-ATC       Pull rods for criticality 4       SRM_BI_ACTIO         I-ATC       B SRM fails N2 and 1 5       CDSR_VAC_P           I-BOP       Vacuum Pump Trip MP_A 6       SRM_CI_ACTIO         TS-CRS     A SRM fails delete N2 and 1 7       Override             C-BOP       RCIC drain trap level high 8       YARITPLA_1           M-ALL       RCIC unisolable steam leak Override 9       YP_XMFTB_500         M-ALL       Reactor scrams on initiation of RPT/ARI 2
 
10       CAM1PR006AT           M-ALL      Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC
V_VALUE1 CAM1PR006DT
        *(N)ormal,  (R)eactivity,    (I)nstrument,    (C)omponent,        (M)ajor Page 1 of 2
 
V_VALUE1 CAM1PR006BT


V_VALUE1 VGCEFUSE_V
Appendix D                               Scenario Outline                               Form ES-D-1 Scenario No.: Three                                         Operating Test No.: 08-01 Narrative Summary Event #                                   Description
 
677503CC VGBZFUSE_V 421691CC M-ALL Radiation monitor fails to initiate an isolation *(N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
Three                     Operating Test No.:
08-01 Narrative Summary  
 
Event # Description
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 3. Withdrawal rods for criticality.
: 3. Withdrawal rods for criticality.
: 4. 'B' SRM fails causing a rod block requiring bypassing to proceed with startup.
: 4. B SRM fails causing a rod block requiring bypassing to proceed with startup.
 
Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
Requiring a review of Technical Sp ecification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 6. 'A' SRM fails causing a rod block and requiring entry into Technical Specification  
: 6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
 
3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.
EOP 8,1A,1 Critical tasks:
* Manual insertion of ARI prior to exceeding Maximum safe temperature
* Manually shutdown and isolate VF and startup VG Page 2 of 2


1A will be exited and EOP-1 will be entered.
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                        08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.  
(Plant power level)
Subcritical, with equilibrium Xenon, 3 days            CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt                                                CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.
Comments, evolutions, problems, etc.
Online Safety is Green                                Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by
                                                                - First Priority.
the electrode boiler Continue with Reactor startup.
1


EOP 8,1A,1  Critical tasks:  Manual insertion of ARI prior to exceeding Maximum safe temperature  Manually shutdown and isolate VF and startup VG Page    of 2 2
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):        1                                                                    Page   1 of  1
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 1  Shift Turnover Information  Day of week and shift  Today Day Shift  Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) Subcritical, with equilibrium Xenon, 3 days after shutdown  CPS 3001.01 complete to step 8.2.5  na- MWt  CPS 3002.01 at step 8.5.2  na- MWe   27.0 Mlbm/hr CORE FLOW    Thermal Limit Problems/Power Evolutions  Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12            Existing LCOs, date of next surveillance None        Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT.
Comments, evolutions, problems, etc. Online Safety is Green  Steam seals and Auxiliary Steam is provided by the electrode boiler Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT
-  First Priority.
Continue with Reactor startup.


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                    08-01  2  Operator Actions Event No.(s):
==
1  Page 1 of 1
Description:==
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior BOP      Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:
* Depress Gen H2 Emerg Seal Oil Pump Test push-button
* Verify Gen H2 Emergency Seal Oil Pump starts
* Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
* Stop the Gen H2 Emergency Seal Oil Pump
* Verify annunciators and computer point off RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Emergency Seal Oil Pump test complete NOTES:
2


== Description:==
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                           08-01 Operator Actions Event No.(s):           2                                                                   Page   1 of 1
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP  Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:  Depress Gen H2 Emerg Seal Oil Pump Test push-button  Verify Gen H2 Emergency Seal Oil Pump starts  Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK  Stop the Gen H2 Emergency Seal Oil Pump  Verify annunciators and computer point off RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus:  Emergency Seal Oil Pump test complete NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 3 Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
== Description:==
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicant's Actions or Behavior RO CPS 5006-5G, Rod Overtravel: Determine the rod that alarmed 08-25. Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time     Position                               Applicants Actions or Behavior RO     CPS 5006-5G, Rod Overtravel:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button. 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod. 3) Determine if the rod has recoupled by performing a coupling check 4) If the rod has recoupled, return to normal operation.  
* Determine the rod that alarmed 08-25.
* Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
: 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
: 3) Determine if the rod has recoupled by performing a coupling check
: 4) If the rod has recoupled, return to normal operation.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2
* When the rod is recoupled declare the rod Operable and exit the LCOs
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:
3


BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                          08-01 Event No.(s):                3                                                                Page    1 of 1
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2  When the rod is recoupled declare the rod Operable and exit the LCOs  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  Rod has been recoupled and SRO applied LCO actions 


NOTES:          
==
Description:==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO      Sequence:
* Withdraw rods for criticality
* Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
* Depress the POWER ON button
* Select the SRMs
* Depress the drive out button until withdrawn
* Depress the drive out button
* Announce reactor is critical BOP
* Announce reactor criticality
* Log in the date/time criticality was achieved, and criticality data:
* Rod Sequence
* Group/Array
* Rod
* Rod Position
* SRM reading and Period
* RR loop temperature
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above
* Stays in a position of oversite
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
NOTES:
4


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 4 Event No.(s):
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         4                                                                    Page   1 of 1
3  Page 1 of 1


== Description:==
==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod Sequence: Withdraw rods for criticality  Prior to exceeding 1 x 10 6 cps, withdraw SRM's Per CPS 3306.01, SRM/IRM step 8.1.2:
Description:==
Depress the POWER ON button  Select the SRMs  Depress the drive out button until withdrawn  Depress the drive out button  Announce reactor is critical BOP Announce reactor criticality  Log in the date/time criticality was achieved, and criticality data:  Rod Sequence  Group/Array  Rod  Rod Position  SRM reading and Period  RR loop temperature  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                                 Applicants Actions or Behavior RO       Per CPS 5006-2H, SRM Inop:
SRO Directs actions listed above Stays in a position of oversite  Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
* Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
* Place the SRM Bypass joy stick to B SRM
* Observe the rod block clears BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Directs Bypassing SRM B and continue with the startup
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B SRM has been bypassed IAW CPS 3306.01.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  5  Operator Actions Event No.(s):
If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.
4  Page 1 of 1
5


== Description:==
D-2, Dynamic Simulator Scenario 3              EXAM DATE: 08/24/09                        08-01 Operator Actions Event No.(s):         5                                                                  Page    1 of  1
'B' SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues:  Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop:  Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:  Place the SRM Bypass joy stick to B SRM  Observe the rod block clears BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews  TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Directs Bypassing SRM B and continue with the startup  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  B SRM has been bypassed IAW CPS 3306.01.
NOTES: If the B RO appears about to perform the operation to bypass the 'B' SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  6  Operator Actions Event No.(s):
==
5 Page 1 of 1
Description:==
Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time      Position                                Applicants Actions or Behavior BOP      Per CPS 3112.01, Condenser Vacuum
* Dispatches field operator to perform local actions to start B Vacuum Pump
* After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 4004.02 Loss of Vacuum
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B Vacuum Pump is in operation NOTES:
6


== Description:==
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         6                                                                 Page   1 of 1
Vacuum Pump trips Initiation:  After crew has addressed SRM problem, on the signal of lead examiner Cues:  Annunciator CPS 5019-1A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum  Dispatches field operator to perform local actions to start B Vacuum Pump  After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Enters CPS 4004.02 Loss of Vacuum  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  B Vacuum Pump is in operation NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 7  Operator Actions Event No.(s):
6 Page 1 of 1


== Description:==
==
'A' SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annuncia tors CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop: Reports annunciator to CRS Monitors reactor to ensure operati ons remain within established bands BOP Monitors reactor to ensure oper ations remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Description:==
SRO Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                             Applicants Actions or Behavior RO     Per CPS 5006-2H, SRM Inop:
Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Reports annunciator to CRS
Enforces OPS expectations and standards.
* Monitors reactor to ensure operations remain within established bands BOP
Contacts Shift Manager and recommends notifications.
* Monitors reactor to ensure operations remain within established bands
Terminus: ITS actions reviewed and entered NOTES: TO LEAD EVALUATOR: Ensure this event is started before IRM's are on Range 2 to ensure a Tech Spec call can be made.
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: ITS actions reviewed and entered NOTES:
TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.
7


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 8  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         7                                                                   Page   1 of 1
7 Page 1 of 1


== Description:==
==
RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicant's Actions or Behavior BOP Per CPS 5063-2C, RCIC Steam Drain Trap Level High
Description:==
:  Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually. Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open Reports failure RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time     Position                                 Applicants Actions or Behavior BOP       Per CPS 5063-2C, RCIC Steam Drain Trap Level High:
SRO Directs actions listed above. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.  
* Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
* Reports failure RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.
NOTES:
8


NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                             08-01 Operator Actions Event No.(s):               8,9                                                                   Page   1 of 2
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 9  Operator Actions Event No.(s):
8,9 Page 1 of 2


== Description:==
==
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown, check and report power unchanged Arms and depresses MANUAL SCRAM push-buttons Initiates ARI Reports control rods inserted, shutdown criteria met Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to mon itor and control RPV level and press.
Description:==
BOP Reports secondary containment high temperature and rad alarms to SRO   Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports secondary containment Max Safe temperature being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time     Position                                   Applicants Actions or Behavior RO     Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO
* Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram:
* Place mode switch in Shutdown, check and report power unchanged
* Arms and depresses MANUAL SCRAM push-buttons Critical Task
* Initiates ARI
* Reports control rods inserted, shutdown criteria met
* Operate FW to control level 3 to 8
* Check rods, reports shutdown criteria is met
* Report level and pressure are following expected trends
* Stabilize pressure <1065 psig
* Coordinates with BOP operator to monitor and control RPV level and press.
BOP
* Reports secondary containment high temperature and rad alarms to SRO
* Makes plant announcement for reactor scram
* Should make plant announcement to evacuate Fuel/Aux buildings.
* Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
* Verifies operation of area coolers
* Verifies operation of VF
* Evacuates affected areas of Secondary Containment
* Monitors area temperatures, levels and radiation levels
* Reports secondary containment Max Safe temperature being exceeded to SRO
* Coordinates with RO to monitor and control RPV level and press NOTES:
9


NOTES:
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                         08-01 Event No.(s):             8,9                                                           Page     2 of 2 Time     Position                                 Applicants Actions or Behavior SRO     Directs entry into EOP-8 and EOP actions as entry conditions are met:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 10 Event No.(s):
: 1. Operate VF
8,9 Page 2 of 2 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met: 1. Operate VF 2. Operate area coolers
: 2. Operate area coolers
: 3. Hold floor drain sump levels below max. normal
: 3. Hold floor drain sump levels below max. normal
: 4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting 5. Per EOP-8/CPS 4001.02: Directs BOP to isolate RCIC steam lines
: 4. Isolate all discharges into the affected area except systems needed for:
: 6. Direct a scram prior to exceeding Maximum safe temperature
* EOP Actions
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.: Inhibit ADS Arm and Depress MANUAL SCRAM pushbuttons Initiate ARI
* Fire Fighting
: 8. Directs additional actions: Notification of Radiation Protection (RP) Department Evacuate affected areas of Secondary Containment
: 5. Per EOP-8/CPS 4001.02:
* Directs BOP to isolate RCIC steam lines Critical Task      6. Direct a scram prior to exceeding Maximum safe temperature
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
* Inhibit ADS
* Arm and Depress MANUAL SCRAM pushbuttons
* Initiate ARI
: 8. Directs additional actions:
* Notification of Radiation Protection (RP) Department
* Evacuate affected areas of Secondary Containment
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: a. Mode Switch to SHUTDOWN
: a. Mode Switch to SHUTDOWN
Line 1,526: Line 2,137:
: c. Control RPV Water Level between Level 3 and Level 8
: c. Control RPV Water Level between Level 3 and Level 8
: d. Stabilize RPV pressure below 1065 psig
: d. Stabilize RPV pressure below 1065 psig
: e. Verify needed automatic actions: Isolations   ECCS Start DG Start         Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:   Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 11  Operator Actions Event No.(s):
: e. Verify needed automatic actions:
10 Page 1 of 1
* Isolations
* ECCS Start
* DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:
10
 
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         10                                                                 Page   1 of 1


== Description:==
== Description:==
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicant's Actions or Behavior BOP   Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG: Verify alarming condition of 1RIX-PR006A-D Report EOP-8 entry condition Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time     Position                                   Applicants Actions or Behavior BOP     Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:
SRO Directs entry into EOP-8 and EOP actions as entry conditions are met. When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Startup VG CPS 3319.01, Standby Gas General:
* Verify alarming condition of 1RIX-PR006A-D
On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Report EOP-8 entry condition Critical Task
Terminus:   RPV level stable and under control in required band Reactor is Scrammed Effort has been made to isolate RCIC steam lines Failed automatic isolation and actuation (VF/VG) manually performed Upon approval of lead examiner NOTES:       Critical Task Critical Task Critical Task Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 12  Simulator Operator Instructions Initial Setup
* Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
* Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs entry into EOP-8 and EOP actions as entry conditions are met.
Critical Task
* When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
* Startup VG CPS 3319.01, Standby Gas General:
* On transient, positions himself as command authority on the unit.
* Acknowledges immediate operator actions and directs subsequent actions.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus:
* RPV level stable and under control in required band
* Reactor is Scrammed
* Effort has been made to isolate RCIC steam lines
* Failed automatic isolation and actuation (VF/VG) manually performed
* Upon approval of lead examiner NOTES:
11
 
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                 08-01 Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
Line 1,541: Line 2,178:
: 6. Turn on and advance recorders
: 6. Turn on and advance recorders
: 7. Reset SRM A drawer
: 7. Reset SRM A drawer
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 9. Provide and ECP and RE instructions 1 0. Verify the AR/PR server is running and stabilize AR/PR 1 1. Verify TT alarm is reset 1 2. Verify Rod Drive pressure at 250#
: 9. Provide and ECP and RE instructions
1 3. Hang OOS tags per turnover on #2 SAC 1 4. Identify T/S issues associated with OOS and turnover 1 5. Verify simulator conditions match the turnover 1 6. Provide marked up CPS 3001.01 complete to step 8.2.5 1 7. Provide a marked up CPS 3002.01 complete to step 8.6
: 10. Verify the AR/PR server is running and stabilize AR/PR
: 11. Verify TT alarm is reset
: 12. Verify Rod Drive pressure at 250#
: 13. Hang OOS tags per turnover on #2 SAC
: 14. Identify T/S issues associated with OOS and turnover
: 15. Verify simulator conditions match the turnover
: 16. Provide marked up CPS 3001.01 complete to step 8.2.5
: 17. Provide a marked up CPS 3002.01 complete to step 8.6
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions  
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 13 Event Triggers and Role Play Event # 1. Test the Generator Emergency Seal Oil Pump
D-2, Dynamic Simulator Scenario 3                     EXAM DATE: 08/24/09                           08-01 Event Triggers and Role Play Event #
: 1. Test the Generator Emergency Seal Oil Pump
: a. No trigger.
: a. No trigger.
: 2. Uncoupled rod
: 2. Uncoupled rod
Line 1,555: Line 2,200:
: 3. Withdraw Rods To criticality
: 3. Withdraw Rods To criticality
: a. No triggers
: a. No triggers
: 4. 'B' SRM fails
: 4. B SRM fails
: a. Remote trigger 2 on request from lead evaluator
: a. Remote trigger 2 on request from lead evaluator
: b. If SRM 'B' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 5. Vacuum Pump trip
: 5. Vacuum Pump trip
: a. Remote trigger 3 on request from lead evaluator
: a. Remote trigger 3 on request from lead evaluator
: b. Role Play- Field operator
: b. Role Play- Field operator
: 6. 'A' SRM fails
: 6. A SRM fails
: a. Remote trigger 4 on request from lead evaluator
: a. Remote trigger 4 on request from lead evaluator
: b. If SRM 'A' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 7. RCIC drain trap level high
: 7. RCIC drain trap level high
Line 1,571: Line 2,216:
: 8. RCIC unisolable steam leak
: 8. RCIC unisolable steam leak
: a. Remote trigger 6 on request from lead evaluator
: a. Remote trigger 6 on request from lead evaluator
: b. If RCIC ATM's are checked they read 10 times higher than on the last 9000.01 reading.
: b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: d. If valve breakers are checked, no problems are found.
: d. If valve breakers are checked, no problems are found.
Line 1,579: Line 2,224:
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: a. No triggers
: a. No triggers
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
 
13
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM  ILT 08-1 Exam Scenario 3 REVISION 00
 
DEVELOPER:
Tom Pickley 
 
REVIEWED BY:
Simulator Instructor
 
APPROVED BY:
 
/  Operations Date Overview Makeup/Reject:
A,B,C CP's are in service. RO trai n #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Plant Status On Line Risk Green  Reactor  Operational Condition: Mode  2 Total Core Flow: __26.9___ mlb/hr FCV Position: A:  ___90____%      B:  _
_90____% Reactor Power __0__%  (<=100%)    _0__ MWt  (<=3473)      _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi  (< 1045) In service SDC loop None    MODE 2 Containment Suppression Pool Temperature: _75.5_ F
(<=93.1 F) Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.4__ psi (0 to 1 psig) Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
BOP  Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1):
1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
_78_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
:  None  Comments: See Turnover Sheet
 
From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
 
ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station:
Clinton  Valid Date(s):    XX/XX/XXXX      Reactivity Maneuver Plan #:
C11-Simu.4 Multiple Activations Allowed?
No    (If yes, CRS may make additional copies) Prepared by:  Roger QNE /
XX/XX/XX Reviewed by:
Joe QNE                    /
XX/XX/XX        Reactor Engineer        /      Date      Qualified Nuclear Engineer /        Date Approved by:    Michelle QNE Boss/
XX/XX/XX Authorized by:    / XX/XX/XX                                      RE Manager            /    Date    Senior Reactor Operator  /      Date NF Review Carlos Quark          /
XX/XX/XX  NF Reviewer /        Date ReMA Activated: 
/ XX/XX/XX ReMA Terminated: 
/ XX/XX/XX      Unit Supervisor        /    Date  Unit Supervisor      /      Date Title of Evolution:  Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift. Reactivity Maneuver Steps Extended General Issues:  Select desired amount of power reduction 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:  The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1  of    1                                                    Reactivity Maneuver Plan # C11-Simu.4 Description of Step : From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.
 
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes
* No  *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
High  Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.
57.3 % N/A    Step Complete: ___________________
/_______          Verified by: _________________
/_______                                        Reactor Operator        /    Date                                              Unit Supervisor          /    Date     
 
CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
This form was updated as a result of the procedure revision.
ROUTINE USE ORIGINATOR:
Christian Small CLASS CODE:
SNNN1    SQR: Mark Vandermyde APPROVAL DATE:
04/25/05  CURRENT CHANGES TO GENERAL REVISION Change #  Date  List of Affected Pages                                  Rev. 4  Page  1 of 2
 
CPS  2202.04F001 Rev. 4  Page  2 of 2 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4
 
Core Conditions Expected
:
Estimated Date/Time of criticality 
        /
Xenon    Increasing          Decreasing None  Moderator Temperature:
468   
&deg;F  Cycle Exposure:
9000 MWD/T  Sequence:
A2 - Simulator Comments:
Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup
__________________________________________
 
Estimated Critical Position
 
Criticality is estimated to occur between steps 17 and      35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse
 
order up to and including step _______ and investigate with the Reactor Engineer


and Nuclear Fuels.
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                          /
Operations                      Date


For BOC, if criticality is not reached at the completion of step ________, insert
Overview Makeup/Reject:            A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                      RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                      N/A Electrical:                6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste:                  FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Plant Status On Line Risk Green Reactor Operational Condition:          Mode 2 Total Core Flow:                __26.9___ mlb/hr FCV Position:                  A: ___90____%        B: _ _90____%
Reactor Power                  __0__% (<=100%) _0__ MWt (<=3473)                _0__ Mwe Xenon:                          Stable RPV Level                      _26.7_ in Narrow Range RPV Pressure                    _600__ psi (< 1045)
In service SDC loop            None MODE 2 Containment Suppression Pool Temperature:            _75.5_ F                        (<=93.1 F)
Suppression Pool Level                  _19.1_ ft                      (19 ft 0 to 19 ft 5 in)
Drywell Pressure                        _0.4__ psi                      (0 to 1 psig)
Drywell to Containment dp:              _0.4__ psi                      >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:            _100__ F                        (<=146.53 F)
Secondary Containment:                  _0.74_ in WG                    (>= 0.25 in WG vacuum)
BOP                                                            Plant Chemistry Condenser Vacuum:                        _27_ in Hg            CPI (goal < 1.1):                1.00 Off - Gas Flow:                          _12.8_ scfm          Reactor Sulfates (goal < 2)      1.31 ppb Condensate Temperature:                  _78_ F                Reactor Chlorides:                0.51 ppb Generator Reactive Load:                _0_MVARS              FW Iron (goal < 2.1)              0.85 ppb Protected Equip: None Comments:      See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
Participate in training program activities.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety


rods in reverse order, up to and including step ________ and investigate with the  
ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton          Valid Date(s): XX/XX/XXXX                  Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed?            No              (If yes, CRS may make additional copies)
Prepared by: Roger QNE                        / XX/XX/XX        Reviewed by:        Joe QNE                  / XX/XX/XX Reactor Engineer      /      Date                          Qualified Nuclear Engineer /    Date Approved by:        Michelle QNE Boss/ XX/XX/XX                Authorized by:                                / XX/XX/XX RE Manager          /    Date                                Senior Reactor Operator /      Date NF Review Carlos Quark                / XX/XX/XX NF Reviewer /        Date ReMA Activated:                                  / XX/XX/XX    ReMA Terminated:                              / XX/XX/XX Unit Supervisor        /  Date                                  Unit Supervisor    /  Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction
: 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet


Reactor Engineer and Nuclear Fuels.  
STEP      1    of    1                                          Reactivity Maneuver Plan # C11-Simu.4 Description of Step :
From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.
QNE presence required in the Control Room? Yes
* No *
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                  Parameter            Value or Range  Init.
Core Power (MWth or %)                  N/A            N/A MFLCPR                              N/A        N/A Core Flow (Mlb/hr or %)                  N/A            N/A MFLPD                                N/A        N/A FCL (%)                                  N/A            N/A MAPRAT                              N/A        N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                        High            Low FCL                                                                                    57.3 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.
Contingency: Insert control rods in reverse order sequence to reduce FCL.
Step Complete: ___________________/_______                        Verified by: _________________/_______
Reactor Operator      /  Date                        Unit Supervisor    /  Date


Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17    or after step 35   , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.
CPS   2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
* This form was updated as a result of the procedure revision.
ROUTINE USE ORIGINATOR: Christian Small                        CLASS CODE: SNNN1 SQR: Mark Vandermyde                APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change #      Date      List of Affected Pages n
o p
q r
Rev. 4                                                    Page  1 of 2


CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:
Estimated Date/Time of criticality            /
Xenon                Increasing Decreasing
:      None Moderator Temperature:  468    &deg;F Cycle Exposure:            9000    MWD/T Sequence:                A2 - Simulator Comments:            Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps      17    and      35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.
For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step      17    or after step 35  , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.
Instructions
Instructions
* Expect the reactor to become critical at any time.
* Expect the reactor to become critical at any time.
* Move control rods with careful attention.
* Move control rods with careful attention.
* Monitor nuclear instruments during and following rod movements.
* Monitor nuclear instruments during and following rod movements.
* If a nontransient period of less than 30 sec occurs, insert rods and
* If a nontransient period of less than 30 sec occurs, insert rods and investigate.
 
* Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____
investigate.
___25____ ___26____ ___27____ ___28____
* Perform 1/M plots at steps ___
___29____ ___31____ ___33____ ___35____
17____  ___19____ ___22____ ___23____   ___25____ ___26____ ___27____ ___28____   ___29____ ___31____ ___33____ ___35____ ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.  
ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.
 
Michelle QNE Boss                               /
Michelle QNE Boss        
Reactor Engineer                     Date       Time Rev. 4                                                    Page   2 of 2
                    /
Reactor Engineer                   Date       Time Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
Three                    Operating Test No.:
08-01  Examiners: ____________________________   Operators: ____________________          ____________________________           
 
____________________
____________________________                    ____________________


Appendix D                                      Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station              Scenario No.: Three                Operating Test No.: 08-01 Examiners: ____________________________                                  Operators: ____________________
Initial Conditions:
Initial Conditions:
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by th e electrode boiler, hot restart. Thunderstorm storms are expected in the area within the next hour.  
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.
 
Thunderstorm storms are expected in the area within the next hour.
Turnover:
Turnover:
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 2. Pull Rods to criticality.
: 2. Pull Rods to criticality.
Event No. Malf. No.
Event           Malf. No.       Event                                            Event No.                            Type*                                       Description 1       NA                   N-BOP       Test the Generator Emergency Seal Oil Pump delete 2       Rod                   C-ATC       Continue with startup, discovers Uncoupled rod 0825I_ACTIONA
Event Type* Event Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump delete 2 Rod 0825I_ACTIONA-Rod uncoupled C-ATC TS-CRS  Continue with startup, discovers Uncoupled rod 3 4 NA R-ATC Pull rods for criticality 4 3 SRM_BI_ACTIO N2 and 1 I-ATC B SRM fails 5 CDSR_VAC_P MP_A I-BOP Vacuum Pump Trip delete 6 SRM_CI_ACTIO N2 and 1 TS-CRS A SRM fails 7 Override C-BOP RCIC drain trap level high delete 8 YARITPLA_1 Override M-ALL RCIC unisolable steam leak 9 YP_XMFTB_500 2 M-ALL Reactor scrams on initiation of RPT/ARI 10 CAM1PR006AT V_VALUE1 CAM1PR006CT
            -Rod uncoupled        TS-CRS 3 4     NA                   R-ATC       Pull rods for criticality 4 3     SRM_BI_ACTIO         I-ATC       B SRM fails N2 and 1 5       CDSR_VAC_P           I-BOP       Vacuum Pump Trip         delete MP_A 6       SRM_CI_ACTIO         TS-CRS     A SRM fails N2 and 1 7       Override             C-BOP       RCIC drain trap level high     delete 8       YARITPLA_1           M-ALL       RCIC unisolable steam leak Override 9       YP_XMFTB_500         M-ALL       Reactor scrams on initiation of RPT/ARI 2
10     CAM1PR006AT           M-ALL      Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC
        *(N)ormal,  (R)eactivity,    (I)nstrument,    (C)omponent,        (M)ajor Page 1 of 2


V_VALUE1 CAM1PR006DT
Appendix D                               Scenario Outline                               Form ES-D-1 Scenario No.: Three                                         Operating Test No.: 08-01 Narrative Summary Event #                                   Description
 
V_VALUE1 CAM1PR006BT
 
V_VALUE1 VGCEFUSE_V
 
677503CC VGBZFUSE_V 421691CC M-ALL Radiation monitor fails to initiate an isolation *(N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
Three                     Operating Test No.:
08-01 Narrative Summary  
 
Event # Description
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 3. Withdrawal rods for criticality.
: 3. Withdrawal rods for criticality.
: 4. 'B' SRM fails causing a rod block requiring bypassing to proceed with startup.
: 4. B SRM fails causing a rod block requiring bypassing to proceed with startup.
 
Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
Requiring a review of Technical Sp ecification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 6. 'A' SRM fails causing a rod block and requiring entry into Technical Specification  
: 6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
 
3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.
EOP 8,1A,1 Critical tasks:
* Manual insertion of ARI prior to exceeding Maximum safe temperature
* Manually shutdown and isolate VF and startup VG Page 2 of 2


1A will be exited and EOP-1 will be entered.
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                        08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.  
(Plant power level)
Subcritical, with equilibrium Xenon, 3 days            CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt                                                CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.
Comments, evolutions, problems, etc.
Online Safety is Green                                Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by
                                                                - First Priority.
the electrode boiler Continue with Reactor startup.
1


EOP 8,1A,1  Critical tasks:  Manual insertion of ARI prior to exceeding Maximum safe temperature  Manually shutdown and isolate VF and startup VG Page    of 2 2
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):        1                                                                    Page   1 of  1
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 1  Shift Turnover Information  Day of week and shift  Today Day Shift  Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) Subcritical, with equilibrium Xenon, 3 days after shutdown  CPS 3001.01 complete to step 8.2.5  na- MWt  CPS 3002.01 at step 8.5.2  na- MWe   27.0 Mlbm/hr CORE FLOW    Thermal Limit Problems/Power Evolutions  Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12            Existing LCOs, date of next surveillance None        Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT.
Comments, evolutions, problems, etc. Online Safety is Green  Steam seals and Auxiliary Steam is provided by the electrode boiler Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT
-  First Priority.
Continue with Reactor startup.


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                    08-01  2  Operator Actions Event No.(s):
==
1  Page 1 of 1
Description:==
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior BOP      Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:
* Depress Gen H2 Emerg Seal Oil Pump Test push-button
* Verify Gen H2 Emergency Seal Oil Pump starts
* Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
* Stop the Gen H2 Emergency Seal Oil Pump
* Verify annunciators and computer point off RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Emergency Seal Oil Pump test complete NOTES:
2


== Description:==
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                           08-01 Operator Actions Event No.(s):           2                                                                   Page   1 of 1
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP  Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3
:  Depress Gen H2 Emerg Seal Oil Pump Test push
-button  Verify Gen H2 Emergency Seal Oil Pump starts Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK Stop the Gen H2 Emergency Seal Oil Pump Verify annunciators and computer point off  RO  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above.
Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus:  Emergency Seal Oil Pump test complete NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 3 Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
== Description:==
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicant's Actions or Behavior RO CPS 5006-5G, Rod Overtravel: Determine the rod that alarmed 08-25. Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time     Position                               Applicants Actions or Behavior RO     CPS 5006-5G, Rod Overtravel:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button. 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod. 3) Determine if the rod has recoupled by performing a coupling check 4) If the rod has recoupled, return to normal operation.  
* Determine the rod that alarmed 08-25.
* Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
: 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
: 3) Determine if the rod has recoupled by performing a coupling check
: 4) If the rod has recoupled, return to normal operation.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2
* When the rod is recoupled declare the rod Operable and exit the LCOs
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:
3


BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                          08-01 Event No.(s):              3 4                                                              Page    1 of 1
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2  When the rod is recoupled declare the rod Operable and exit the LCOs  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  Rod has been recoupled and SRO applied LCO actions 


NOTES:          
==
Description:==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO      Sequence:
* Withdraw rods for criticality
* Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
* Depress the POWER ON button
* Select the SRMs
* Depress the drive out button until withdrawn
* Depress the drive out button
* Announce reactor is critical BOP
* Announce reactor criticality
* Log in the date/time criticality was achieved, and criticality data:
* Rod Sequence
* Group/Array
* Rod
* Rod Position
* SRM reading and Period
* RR loop temperature
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above
* Stays in a position of oversite
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
NOTES:
4


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 4 Event No.(s):
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         4 3                                                                   Page   1 of 1
3 4  Page 1 of 1


== Description:==
==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod Sequence: Withdraw rods for criticality  Prior to exceeding 1 x 10 6 cps, withdraw SRM's Per CPS 3306.01, SRM/IRM step 8.1.2:
Description:==
Depress the POWER ON button  Select the SRMs  Depress the drive out button until withdrawn  Depress the drive out button  Announce reactor is critical BOP Announce reactor criticality  Log in the date/time criticality was achieved, and criticality data:  Rod Sequence  Group/Array  Rod  Rod Position  SRM reading and Period  RR loop temperature  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                                 Applicants Actions or Behavior RO       Per CPS 5006-2H, SRM Inop:
SRO Directs actions listed above Stays in a position of oversite  Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
* Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
* Place the SRM Bypass joy stick to B SRM
* Observe the rod block clears BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Directs Bypassing SRM B and continue with the startup
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B SRM has been bypassed IAW CPS 3306.01.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  5  Operator Actions Event No.(s):
If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.
4  3  Page 1 of 1
5


== Description:==
D-2, Dynamic Simulator Scenario 3              EXAM DATE: 08/24/09                        08-01 Operator Actions Event No.(s):         5                                                                  Page    1 of  1
'B' SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues:  Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop:  Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:  Place the SRM Bypass joy stick to B SRM  Observe the rod block clears BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews  TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Directs Bypassing SRM B and continue with the startup  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  B SRM has been bypassed IAW CPS 3306.01.
NOTES: If the B RO appears about to perform the operation to bypass the 'B' SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  6  Operator Actions Event No.(s):
==
5 Page 1 of 1
Description:==
Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time      Position                                Applicants Actions or Behavior BOP      Per CPS 3112.01, Condenser Vacuum
* Dispatches field operator to perform local actions to start B Vacuum Pump
* After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 4004.02 Loss of Vacuum
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B Vacuum Pump is in operation NOTES:
6


== Description:==
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         6                                                                 Page   1 of 1
Vacuum Pump trips Initiation:
After crew has addressed SRM problem, on the signal of lead examiner Cues:  Annunciator CPS 5019
-1A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum Dispatches field operator to perform local actions to start B Vacuum Pump After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Enters CPS 4004.02 Loss of Vacuum Directs actions listed above.
Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Enforces OPS expectations and standards.
Contacts Shift Manager and recommends notifications.
Terminus:  B Vacuum Pump is in operation NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 7  Operator Actions Event No.(s):
6 Page 1 of 1


== Description:==
==
'A' SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop: Reports annunciator to CRS Monitors reactor to ensure operati ons remain within established bands BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Description:==
SRO Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                             Applicants Actions or Behavior RO     Per CPS 5006-2H, SRM Inop:
Terminus: ITS actions reviewed and entered NOTES: TO LEAD EVALUATOR: Ensure this event is started before IRM's are on Range 2 to ensure a Tech Spec call can be made.  
* Reports annunciator to CRS
* Monitors reactor to ensure operations remain within established bands BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: ITS actions reviewed and entered NOTES:
TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.
7


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 8  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         7                                                                   Page   1 of 1
7 Page 1 of 1


== Description:==
==
RCIC drain trap level high Initiation: After ITS actions reviewed and entered
Description:==
, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicant's Actions or Behavior BOP Per CPS 5063
RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time     Position                                 Applicants Actions or Behavior BOP       Per CPS 5063-2C, RCIC Steam Drain Trap Level High:
-2C, RCIC Steam Drain Trap Level High
* Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
:  Recognizes failure of 1E51
* Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
* Reports failure RO
Verifies 1E51
* Monitors reactor to ensure operations remain within established bands
-F025 and 1E51
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open Reports failure RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
SRO Directs actions listed above.
* Directs actions listed above.
Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 9  Operator Actions Event No.(s):
8
8,9 Page 1 of 2
 
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                             08-01 Operator Actions Event No.(s):               8,9                                                                   Page   1 of 2


== Description:==
==
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown, check and report power unchanged Arms and depresses MANUAL SCRAM push-buttons Initiates ARI Reports control rods inserted, shutdown criteria met Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to mon itor and control RPV level and press.
Description:==
BOP Reports secondary containment high temperature and rad alarms to SRO   Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports secondary containment Max Safe temperature being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time     Position                                   Applicants Actions or Behavior RO     Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO
* Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram:
* Place mode switch in Shutdown, check and report power unchanged
* Arms and depresses MANUAL SCRAM push-buttons Critical Task
* Initiates ARI
* Reports control rods inserted, shutdown criteria met
* Operate FW to control level 3 to 8
* Check rods, reports shutdown criteria is met
* Report level and pressure are following expected trends
* Stabilize pressure <1065 psig
* Coordinates with BOP operator to monitor and control RPV level and press.
BOP
* Reports secondary containment high temperature and rad alarms to SRO
* Makes plant announcement for reactor scram
* Should make plant announcement to evacuate Fuel/Aux buildings.
* Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
* Verifies operation of area coolers
* Verifies operation of VF
* Evacuates affected areas of Secondary Containment
* Monitors area temperatures, levels and radiation levels
* Reports secondary containment Max Safe temperature being exceeded to SRO
* Coordinates with RO to monitor and control RPV level and press NOTES:
9


NOTES:
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                         08-01 Event No.(s):             8,9                                                           Page     2 of 2 Time     Position                                 Applicants Actions or Behavior SRO     Directs entry into EOP-8 and EOP actions as entry conditions are met:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 10 Event No.(s):
: 1. Operate VF
8,9 Page 2 of 2 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met: 1. Operate VF 2. Operate area coolers
: 2. Operate area coolers
: 3. Hold floor drain sump levels below max. normal
: 3. Hold floor drain sump levels below max. normal
: 4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting 5. Per EOP-8/CPS 4001.02: Directs BOP to isolate RCIC steam lines
: 4. Isolate all discharges into the affected area except systems needed for:
: 6. Direct a scram prior to exceeding Maximum safe temperature
* EOP Actions
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.: Inhibit ADS Arm and Depress MANUAL SCRAM pushbuttons Initiate ARI
* Fire Fighting
: 8. Directs additional actions: Notification of Radiation Protection (RP) Department Evacuate affected areas of Secondary Containment
: 5. Per EOP-8/CPS 4001.02:
* Directs BOP to isolate RCIC steam lines Critical Task      6. Direct a scram prior to exceeding Maximum safe temperature
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
* Inhibit ADS
* Arm and Depress MANUAL SCRAM pushbuttons
* Initiate ARI
: 8. Directs additional actions:
* Notification of Radiation Protection (RP) Department
* Evacuate affected areas of Secondary Containment
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: a. Mode Switch to SHUTDOWN
: a. Mode Switch to SHUTDOWN
Line 1,827: Line 2,524:
: c. Control RPV Water Level between Level 3 and Level 8
: c. Control RPV Water Level between Level 3 and Level 8
: d. Stabilize RPV pressure below 1065 psig
: d. Stabilize RPV pressure below 1065 psig
: e. Verify needed automatic actions: Isolations   ECCS Start DG Start         Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:   Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 11  Operator Actions Event No.(s):
: e. Verify needed automatic actions:
10 Page 1 of 1
* Isolations
* ECCS Start
* DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:
10
 
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         10                                                                 Page   1 of 1


== Description:==
== Description:==
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicant's Actions or Behavior BOP   Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG: Verify alarming condition of 1RIX-PR006A-D Report EOP-8 entry condition Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time     Position                                   Applicants Actions or Behavior BOP     Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:
SRO Directs entry into EOP-8 and EOP actions as entry conditions are met. When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Startup VG CPS 3319.01, Standby Gas General:
* Verify alarming condition of 1RIX-PR006A-D
On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Report EOP-8 entry condition Critical Task
Terminus:   RPV level stable and under control in required band Reactor is Scrammed Effort has been made to isolate RCIC steam lines Failed automatic isolation and actuation (VF/VG) manually performed Upon approval of lead examiner NOTES:       Critical Task Critical Task Critical Task Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 12  Simulator Operator Instructions Initial Setup
* Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
* Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs entry into EOP-8 and EOP actions as entry conditions are met.
Critical Task
* When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
* Startup VG CPS 3319.01, Standby Gas General:
* On transient, positions himself as command authority on the unit.
* Acknowledges immediate operator actions and directs subsequent actions.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus:
* RPV level stable and under control in required band
* Reactor is Scrammed
* Effort has been made to isolate RCIC steam lines
* Failed automatic isolation and actuation (VF/VG) manually performed
* Upon approval of lead examiner NOTES:
11
 
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                 08-01 Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
Line 1,842: Line 2,565:
: 6. Turn on and advance recorders
: 6. Turn on and advance recorders
: 7. Reset SRM A drawer
: 7. Reset SRM A drawer
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 9. Provide and ECP and RE instructions 1 0. Verify the AR/PR server is running and stabilize AR/PR 1 1. Verify TT alarm is reset 1 2. Verify Rod Drive pressure at 250#
: 9. Provide and ECP and RE instructions
1 3. Hang OOS tags per turnover on #2 SAC 1 4. Identify T/S issues associated with OOS and turnover 1 5. Verify simulator conditions match the turnover 1 6. Provide marked up CPS 3001.01 complete to step 8.2.5 1 7. Provide a marked up CPS 3002.01 complete to step 8.6
: 10. Verify the AR/PR server is running and stabilize AR/PR
: 11. Verify TT alarm is reset
: 12. Verify Rod Drive pressure at 250#
: 13. Hang OOS tags per turnover on #2 SAC
: 14. Identify T/S issues associated with OOS and turnover
: 15. Verify simulator conditions match the turnover
: 16. Provide marked up CPS 3001.01 complete to step 8.2.5
: 17. Provide a marked up CPS 3002.01 complete to step 8.6
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions  
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 13 Event Triggers and Role Play Event # 1. Test the Generator Emergency Seal Oil Pump
D-2, Dynamic Simulator Scenario 3                     EXAM DATE: 08/24/09                           08-01 Event Triggers and Role Play Event #
: 1. Test the Generator Emergency Seal Oil Pump
: a. No trigger.
: a. No trigger.
: 2. Uncoupled rod
: 2. Uncoupled rod
Line 1,856: Line 2,587:
: 3. Withdraw Rods To criticality
: 3. Withdraw Rods To criticality
: a. No triggers
: a. No triggers
: 4. 'B' SRM fails
: 4. B SRM fails
: a. Remote trigger 2 on request from lead evaluator
: a. Remote trigger 2 on request from lead evaluator
: b. If SRM 'B' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 5. Vacuum Pump trip
: 5. Vacuum Pump trip
: a. Remote trigger 3 on request from lead evaluator
: a. Remote trigger 3 on request from lead evaluator
: b. Role Play- Field operator
: b. Role Play- Field operator
: 6. 'A' SRM fails
: 6. A SRM fails
: a. Remote trigger 4 on request from lead evaluator
: a. Remote trigger 4 on request from lead evaluator
: b. If SRM 'A' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 7. RCIC drain trap level high
: 7. RCIC drain trap level high
Line 1,872: Line 2,603:
: 8. RCIC unisolable steam leak
: 8. RCIC unisolable steam leak
: a. Remote trigger 6 on request from lead evaluator
: a. Remote trigger 6 on request from lead evaluator
: b. If RCIC ATM's are checked they read 10 times higher than on the last 9000.01 reading.
: b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: d. If valve breakers are checked, no problems are found.
: d. If valve breakers are checked, no problems are found.
Line 1,880: Line 2,611:
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: a. No triggers
: a. No triggers
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
 
13
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM  ILT 08-1 Exam Scenario 3 REVISION 00
 
DEVELOPER:
Tom Pickley 
 
REVIEWED BY:
Simulator Instructor


APPROVED BY:  
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                         /
Operations                      Date


/  Operations Date Overview Makeup/Reject:
Overview Makeup/Reject:             A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                     RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                       N/A Electrical:               6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
A,B,C CP's are in service. RO trai n #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste:                 FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.
Plant Status On Line Risk Green Reactor Operational Condition:         Mode 2 Total Core Flow:               __26.9___ mlb/hr FCV Position:                   A: ___90____%       B: _ _90____%
Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: __26.9___ mlb/hr FCV Position: A: ___90____%     B: _
Reactor Power                   __0__% (<=100%) _0__ MWt (<=3473)               _0__ Mwe Xenon:                         Stable RPV Level                       _26.7_ in Narrow Range RPV Pressure                   _600__ psi (< 1045)
_90____% Reactor Power __0__% (<=100%)   _0__ MWt (<=3473)     _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi (< 1045) In service SDC loop None   MODE 2 Containment Suppression Pool Temperature: _75.5_ F
In service SDC loop             None MODE 2 Containment Suppression Pool Temperature:           _75.5_ F                       (<=93.1 F)
(<=93.1 F) Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.4__ psi (0 to 1 psig) Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F
Suppression Pool Level                   _19.1_ ft                       (19 ft 0 to 19 ft 5 in)
(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)
Drywell Pressure                         _0.4__ psi                     (0 to 1 psig)
BOP Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1):
Drywell to Containment dp:               _0.4__ psi                     >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:             _100__ F                       (<=146.53 F)
1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
Secondary Containment:                   _0.74_ in WG                   (>= 0.25 in WG vacuum)
_78_ F Reactor Chlorides:
BOP                                                           Plant Chemistry Condenser Vacuum:                       _27_ in Hg           CPI (goal < 1.1):                 1.00 Off - Gas Flow:                         _12.8_ scfm           Reactor Sulfates (goal < 2)       1.31 ppb Condensate Temperature:                 _78_ F               Reactor Chlorides:               0.51 ppb Generator Reactive Load:                 _0_MVARS             FW Iron (goal < 2.1)             0.85 ppb Protected Equip: None Comments:       See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip
Participate in training program activities.
: None Comments: See Turnover Sheet  
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety


From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton          Valid Date(s): XX/XX/XXXX                  Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed?            No              (If yes, CRS may make additional copies)
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
Prepared by: Roger QNE                        / XX/XX/XX        Reviewed by:        Joe QNE                  / XX/XX/XX Reactor Engineer      /      Date                          Qualified Nuclear Engineer /    Date Approved by:        Michelle QNE Boss/ XX/XX/XX                Authorized by:                                / XX/XX/XX RE Manager          /    Date                                Senior Reactor Operator /      Date NF Review Carlos Quark                / XX/XX/XX NF Reviewer /        Date ReMA Activated:                                  / XX/XX/XX    ReMA Terminated:                              / XX/XX/XX Unit Supervisor        /  Date                                  Unit Supervisor    /  Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.
Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction
: 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:
The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet


ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station:
STEP      1   of    1                                           Reactivity Maneuver Plan # C11-Simu.4 Description of Step :
Clinton  Valid Date(s):    XX/XX/XXXX      Reactivity Maneuver Plan #:
From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.
C11-Simu.4 Multiple Activations Allowed?
Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.
No    (If yes, CRS may make additional copies) Prepared by:  Roger QNE /
QNE presence required in the Control Room? Yes
XX/XX/XX Reviewed by:
* No *
Joe QNE                    /
*RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701.
XX/XX/XX        Reactor Engineer        /      Date      Qualified Nuclear Engineer /        Date Approved by:    Michelle QNE Boss/
Initial Conditions (may be ranges) to be verified at the START of the Step Parameter              Value or Range Init.                  Parameter            Value or Range Init.
XX/XX/XX Authorized by:    / XX/XX/XX                                      RE Manager            /    Date    Senior Reactor Operator  /      Date NF Review Carlos Quark          /
Core Power (MWth or %)                  N/A            N/A MFLCPR                              N/A        N/A Core Flow (Mlb/hr or %)                  N/A            N/A MFLPD                                N/A        N/A FCL (%)                                  N/A            N/A MAPRAT                              N/A        N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)                                                        High            Low FCL                                                                                    57.3 %            N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.
XX/XX/XX  NF Reviewer /        Date ReMA Activated: 
Contingency: Insert control rods in reverse order sequence to reduce FCL.
/ XX/XX/XX ReMA Terminated: 
Step Complete: ___________________/_______                        Verified by: _________________/_______
/ XX/XX/XX      Unit Supervisor        /    Date  Unit Supervisor      /      Date Title of Evolution:  Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:
Reactor Operator      /  Date                        Unit Supervisor    /  Date
This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift. Reactivity Maneuver Steps Extended General Issues:  Select desired amount of power reduction 1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:  The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.
ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP    1 of    1                                                    Reactivity Maneuver Plan # C11-Simu.4 Description of Step : From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.  


Ensure Feedwater heating is in service and that feedwater temperature is within 50&deg;F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes
CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
* No   *  *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)
* This form was updated as a result of the procedure revision.
N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)
ROUTINE USE ORIGINATOR: Christian Small                         CLASS CODE: SNNN1 SQR: Mark Vandermyde                 APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change #       Date     List of Affected Pages n
N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)
o p
High  Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.
q r
57.3 % N/A    Step Complete: ___________________
Rev. 4                                                   Page   1 of 2
/_______          Verified by: _________________
/_______                                        Reactor Operator        /    Date                                              Unit Supervisor          /    Date     
 
CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:
This form was updated as a result of the procedure revision.
ROUTINE USE ORIGINATOR:
Christian Small CLASS CODE:
SNNN1     SQR: Mark Vandermyde APPROVAL DATE:
04/25/05   CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages                                 Rev. 4  Page  1 of 2
 
CPS  2202.04F001 Rev. 4  Page  2 of 2 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4
 
Core Conditions Expected
:
Estimated Date/Time of criticality 
        /
Xenon    Increasing          Decreasing None  Moderator Temperature:
468   
&deg;F  Cycle Exposure:
9000 MWD/T  Sequence:
A2 - Simulator Comments:
Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup
__________________________________________
 
Estimated Critical Position
 
Criticality is estimated to occur between steps 17 and      35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse
 
order up to and including step _______ and investigate with the Reactor Engineer
 
and Nuclear Fuels.
 
For BOC, if criticality is not reached at the completion of step ________, insert
 
rods in reverse order, up to and including step ________ and investigate with the
 
Reactor Engineer and Nuclear Fuels.
 
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17    or after step 35  , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality. 


CPS  2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:
Estimated Date/Time of criticality            /
Xenon                Increasing Decreasing
:      None Moderator Temperature:  468    &deg;F Cycle Exposure:            9000    MWD/T Sequence:                A2 - Simulator Comments:            Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps      17    and      35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.
For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.
Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step      17    or after step 35  , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.
Instructions
Instructions
* Expect the reactor to become critical at any time.
* Expect the reactor to become critical at any time.
* Move control rods with careful attention.
* Move control rods with careful attention.
* Monitor nuclear instruments during and following rod movements.
* Monitor nuclear instruments during and following rod movements.
* If a nontransient period of less than 30 sec occurs, insert rods and
* If a nontransient period of less than 30 sec occurs, insert rods and investigate.
 
* Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____
investigate.
___25____ ___26____ ___27____ ___28____
* Perform 1/M plots at steps ___
___29____ ___31____ ___33____ ___35____
17____  ___19____ ___22____ ___23____   ___25____ ___26____ ___27____ ___28____   ___29____ ___31____ ___33____ ___35____ ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.  
ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.
 
Michelle QNE Boss                               /
Michelle QNE Boss        
Reactor Engineer                     Date       Time Rev. 4                                                    Page   2 of 2
                    /
Reactor Engineer                   Date       Time Appendix D Scenario Outline Form ES-D-1 Facility:  Clinton Power Station Scenario No.:
Three                    Operating Test No.:
08-01  Examiners: ____________________________   Operators: ____________________          ____________________________           
 
____________________
____________________________                    ____________________


Appendix D                                      Scenario Outline                                  Form ES-D-1 Facility: Clinton Power Station              Scenario No.: Three                Operating Test No.: 08-01 Examiners: ____________________________                                  Operators: ____________________
Initial Conditions:
Initial Conditions:
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by th e electrode boiler, hot restart. Thunderstorm storms are expected in the area within the next hour.  
Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.
 
Thunderstorm storms are expected in the area within the next hour.
Turnover:
Turnover:
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
: 2. Pull Rods to criticality.
: 2. Pull Rods to criticality.
Event No. Malf. No.
Event           Malf. No.       Event                                          Event No.                            Type*                                       Description 1       NA                   N-BOP       Test the Generator Emergency Seal Oil Pump delete 2       Rod                   C-ATC       Continue with startup, discovers Uncoupled rod 0825I_ACTIONA
Event Type* Event Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump delete 2 Rod 0825I_ACTIONA-Rod uncoupled C-ATC TS-CRS  Continue with startup, discovers Uncoupled rod 3   4 NA R-ATC Pull rods for criticality 4   3 SRM_BI_ACTIO N2 and 1 I-ATC B SRM fails 5 CDSR_VAC_P MP_A I-BOP Vacuum Pump Trip 6 SRM_CI_ACTIO N2 and 1 TS-CRS A SRM fails   7 Override C-BOP RCIC drain trap level high 8 YARITPLA_1 Override M-ALL RCIC unisolable steam leak 9 YP_XMFTB_500 2 M-ALL Reactor scrams on initiation of RPT/ARI 10 CAM1PR006AT V_VALUE1 CAM1PR006CT
            -Rod uncoupled        TS-CRS 3 4       NA                   R-ATC       Pull rods for criticality 4 3       SRM_BI_ACTIO         I-ATC       B SRM fails N2 and 1 5       CDSR_VAC_P           I-BOP       Vacuum Pump Trip MP_A 6       SRM_CI_ACTIO         TS-CRS     A SRM fails N2 and 1 7       Override             C-BOP       RCIC drain trap level high 8       YARITPLA_1           M-ALL       RCIC unisolable steam leak Override 9       YP_XMFTB_500         M-ALL       Reactor scrams on initiation of RPT/ARI 2
10       CAM1PR006AT           M-ALL      Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC
        *(N)ormal,  (R)eactivity,    (I)nstrument,    (C)omponent,        (M)ajor Page 1 of 2


V_VALUE1 CAM1PR006DT
Appendix D                               Scenario Outline                               Form ES-D-1 Scenario No.: Three                                         Operating Test No.: 08-01 Narrative Summary Event #                                   Description
 
V_VALUE1 CAM1PR006BT
 
V_VALUE1 VGCEFUSE_V
 
677503CC VGBZFUSE_V 421691CC M-ALL Radiation monitor fails to initiate an isolation *(N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
Three                     Operating Test No.:
08-01 Narrative Summary  
 
Event # Description
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
: 3. Withdrawal rods for criticality.
: 3. Withdrawal rods for criticality.
: 4. 'B' SRM fails causing a rod block requiring bypassing to proceed with startup.
: 4. B SRM fails causing a rod block requiring bypassing to proceed with startup.
 
Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
Requiring a review of Technical Sp ecification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
: 6. 'A' SRM fails causing a rod block and requiring entry into Technical Specification  
: 6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
 
3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-
: 9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.
EOP 8,1A,1 Critical tasks:
* Manual insertion of ARI prior to exceeding Maximum safe temperature
* Manually shutdown and isolate VF and startup VG Page 2 of 2


1A will be exited and EOP-1 will be entered.
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                        08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
: 10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.  
(Plant power level)
Subcritical, with equilibrium Xenon, 3 days            CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt                                                CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.
Comments, evolutions, problems, etc.
Online Safety is Green                                Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by
                                                                - First Priority.
the electrode boiler Continue with Reactor startup.
1


EOP 8,1A,1  Critical tasks:  Manual insertion of ARI prior to exceeding Maximum safe temperature  Manually shutdown and isolate VF and startup VG Page    of 2 2
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):        1                                                                    Page   1 of  1
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 1  Shift Turnover Information  Day of week and shift  Today Day Shift  Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) Subcritical, with equilibrium Xenon, 3 days after shutdown  CPS 3001.01 complete to step 8.2.5  na- MWt  CPS 3002.01 at step 8.5.2  na- MWe   27.0 Mlbm/hr CORE FLOW    Thermal Limit Problems/Power Evolutions  Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12            Existing LCOs, date of next surveillance None        Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT.
Comments, evolutions, problems, etc. Online Safety is Green  Steam seals and Auxiliary Steam is provided by the electrode boiler Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3  for PMT
-  First Priority.
Continue with Reactor startup.


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                    08-01  2  Operator Actions Event No.(s):
==
1  Page 1 of 1
Description:==
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior BOP      Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:
* Depress Gen H2 Emerg Seal Oil Pump Test push-button
* Verify Gen H2 Emergency Seal Oil Pump starts
* Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
* Stop the Gen H2 Emergency Seal Oil Pump
* Verify annunciators and computer point off RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Emergency Seal Oil Pump test complete NOTES:
2


== Description:==
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                           08-01 Operator Actions Event No.(s):           2                                                                   Page   1 of 1
Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.
Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP  Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3
:  Depress Gen H2 Emerg Seal Oil Pump Test push
-button  Verify Gen H2 Emergency Seal Oil Pump starts Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK Stop the Gen H2 Emergency Seal Oil Pump Verify annunciators and computer point off  RO  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above.
Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus:  Emergency Seal Oil Pump test complete NOTES:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 3 Operator Actions Event No.(s):
2 Page 1 of 1


== Description:==
== Description:==
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicant's Actions or Behavior RO CPS 5006-5G, Rod Overtravel: Determine the rod that alarmed 08-25. Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time     Position                               Applicants Actions or Behavior RO     CPS 5006-5G, Rod Overtravel:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button. 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod. 3) Determine if the rod has recoupled by performing a coupling check 4) If the rod has recoupled, return to normal operation.  
* Determine the rod that alarmed 08-25.
* Tell SRO to review TS LCO 3.1.3 As directed by SRO Per CPS 3304.02, RCIS step 8.2.6:
: 1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
: 2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
: 3) Determine if the rod has recoupled by performing a coupling check
: 4) If the rod has recoupled, return to normal operation.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2
* When the rod is recoupled declare the rod Operable and exit the LCOs
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:
3


BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                          08-01 Event No.(s):              3 4                                                              Page    1 of 1
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Declares the rod inoperable, enters LCO 3.1.3 Action C.1 and C.2  When the rod is recoupled declare the rod Operable and exit the LCOs  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  Rod has been recoupled and SRO applied LCO actions 


NOTES:          
==
Description:==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time      Position                                  Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO      Sequence:
* Withdraw rods for criticality
* Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
* Depress the POWER ON button
* Select the SRMs
* Depress the drive out button until withdrawn
* Depress the drive out button
* Announce reactor is critical BOP
* Announce reactor criticality
* Log in the date/time criticality was achieved, and criticality data:
* Rod Sequence
* Group/Array
* Rod
* Rod Position
* SRM reading and Period
* RR loop temperature
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above
* Stays in a position of oversite
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
NOTES:
4


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                   08-01 4 Event No.(s):
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         4 3                                                                   Page   1 of 1
3 4  Page 1 of 1


== Description:==
==
Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod Sequence: Withdraw rods for criticality  Prior to exceeding 1 x 10 6 cps, withdraw SRM's Per CPS 3306.01, SRM/IRM step 8.1.2:
Description:==
Depress the POWER ON button  Select the SRMs  Depress the drive out button until withdrawn  Depress the drive out button  Announce reactor is critical BOP Announce reactor criticality  Log in the date/time criticality was achieved, and criticality data:  Rod Sequence  Group/Array  Rod  Rod Position  SRM reading and Period  RR loop temperature  Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time     Position                                 Applicants Actions or Behavior RO       Per CPS 5006-2H, SRM Inop:
SRO Directs actions listed above Stays in a position of oversite  Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
* Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
Terminus: Clearly observable plant response from change in power level or Reactor is critical.
* Place the SRM Bypass joy stick to B SRM
* Observe the rod block clears BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Directs Bypassing SRM B and continue with the startup
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B SRM has been bypassed IAW CPS 3306.01.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  5  Operator Actions Event No.(s):
If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.
4  3  Page 1 of 1
5
 
== Description:==
'B' SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues:  Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop:  Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:  Place the SRM Bypass joy stick to B SRM  Observe the rod block clears BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO  Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews  TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Directs Bypassing SRM B and continue with the startup  Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  B SRM has been bypassed IAW CPS 3306.01.
NOTES: If the B RO appears about to perform the operation to bypass the 'B' SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 6  Operator Actions Event No.(s):
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         5                                                                   Page   1 of 1
5 Page 1 of 1


== Description:==
==
Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum Dispatches field operator to perform local actions to start B Vacuum Pump After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Description:==
SRO Enters CPS 4004.02 Loss of Vacuum Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time     Position                                 Applicants Actions or Behavior BOP     Per CPS 3112.01, Condenser Vacuum
Terminus: B Vacuum Pump is in operation NOTES:
* Dispatches field operator to perform local actions to start B Vacuum Pump
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  7  Operator Actions Event No.(s):
* After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
6 Page 1 of 1
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Enters CPS 4004.02 Loss of Vacuum
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: B Vacuum Pump is in operation NOTES:
6


== Description:==
D-2, Dynamic Simulator Scenario 3            EXAM DATE: 08/24/09                        08-01 Operator Actions Event No.(s):         6                                                                Page    1 of  1
'A' SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicant's Actions or Behavior RO Per CPS 5006-2H, SRM Inop:  Reports annunciator to CRS  Monitors reactor to ensure operati ons remain within established bands BOP  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
Terminus:  ITS actions reviewed and entered NOTES: TO LEAD EVALUATOR: Ensure this event is started before IRM's are on Range 2 to ensure a Tech Spec call can be made.


D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  8  Operator Actions Event No.(s):
==
7 Page 1 of 1
Description:==
A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time      Position                            Applicants Actions or Behavior RO      Per CPS 5006-2H, SRM Inop:
* Reports annunciator to CRS
* Monitors reactor to ensure operations remain within established bands BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus: ITS actions reviewed and entered NOTES:
TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.
7


== Description:==
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                        08-01 Operator Actions Event No.(s):         7                                                                    Page    1 of  1
RCIC drain trap level high Initiation:  After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicant's Actions or Behavior BOP Per CPS  5063-2C, RCIC Steam Drain Trap Level High
:  Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually. Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open  Reports failure RO  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO Directs actions listed above. Enforces OPS expectations and standards  Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.


==
Description:==
RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time      Position                                  Applicants Actions or Behavior BOP      Per CPS 5063-2C, RCIC Steam Drain Trap Level High:
* Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
* Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
* Reports failure RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.
NOTES:
NOTES:
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                    08-01  9  Operator Actions Event No.(s):
8
8,9  Page 1 of 2


== Description:==
D-2, Dynamic Simulator Scenario 3                EXAM DATE: 08/24/09                              08-01 Operator Actions Event No.(s):              8,9                                                                  Page    1 of 2
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown, check and report power unchanged Arms and depresses MANUAL SCRAM push-buttons Initiates ARI Reports control rods inserted, shutdown criteria met Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to mon itor and control RPV level and press.
 
BOP Reports secondary containment high temperature and rad alarms to SRO   Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports secondary containment Max Safe temperature being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task
==
Description:==
RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time     Position                                   Applicants Actions or Behavior RO     Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO
* Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram:
* Place mode switch in Shutdown, check and report power unchanged
* Arms and depresses MANUAL SCRAM push-buttons Critical Task
* Initiates ARI
* Reports control rods inserted, shutdown criteria met
* Operate FW to control level 3 to 8
* Check rods, reports shutdown criteria is met
* Report level and pressure are following expected trends
* Stabilize pressure <1065 psig
* Coordinates with BOP operator to monitor and control RPV level and press.
BOP
* Reports secondary containment high temperature and rad alarms to SRO
* Makes plant announcement for reactor scram
* Should make plant announcement to evacuate Fuel/Aux buildings.
* Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
* Verifies operation of area coolers
* Verifies operation of VF
* Evacuates affected areas of Secondary Containment
* Monitors area temperatures, levels and radiation levels
* Reports secondary containment Max Safe temperature being exceeded to SRO
* Coordinates with RO to monitor and control RPV level and press NOTES:
9


NOTES:
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                         08-01 Event No.(s):             8,9                                                           Page     2 of 2 Time     Position                                 Applicants Actions or Behavior SRO     Directs entry into EOP-8 and EOP actions as entry conditions are met:
D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 10 Event No.(s):
: 1. Operate VF
8,9 Page 2 of 2 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met: 1. Operate VF 2. Operate area coolers
: 2. Operate area coolers
: 3. Hold floor drain sump levels below max. normal
: 3. Hold floor drain sump levels below max. normal
: 4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting 5. Per EOP-8/CPS 4001.02: Directs BOP to isolate RCIC steam lines
: 4. Isolate all discharges into the affected area except systems needed for:
: 6. Direct a scram prior to exceeding Maximum safe temperature
* EOP Actions
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.: Inhibit ADS Arm and Depress MANUAL SCRAM pushbuttons Initiate ARI
* Fire Fighting
: 8. Directs additional actions: Notification of Radiation Protection (RP) Department Evacuate affected areas of Secondary Containment
: 5. Per EOP-8/CPS 4001.02:
* Directs BOP to isolate RCIC steam lines Critical Task      6. Direct a scram prior to exceeding Maximum safe temperature
: 7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
* Inhibit ADS
* Arm and Depress MANUAL SCRAM pushbuttons
* Initiate ARI
: 8. Directs additional actions:
* Notification of Radiation Protection (RP) Department
* Evacuate affected areas of Secondary Containment
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: 9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
: a. Mode Switch to SHUTDOWN
: a. Mode Switch to SHUTDOWN
Line 2,117: Line 2,911:
: c. Control RPV Water Level between Level 3 and Level 8
: c. Control RPV Water Level between Level 3 and Level 8
: d. Stabilize RPV pressure below 1065 psig
: d. Stabilize RPV pressure below 1065 psig
: e. Verify needed automatic actions: Isolations   ECCS Start DG Start         Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:   Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 11  Operator Actions Event No.(s):
: e. Verify needed automatic actions:
10 Page 1 of 1
* Isolations
* ECCS Start
* DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:
10
 
D-2, Dynamic Simulator Scenario 3               EXAM DATE: 08/24/09                       08-01 Operator Actions Event No.(s):         10                                                                 Page   1 of 1


== Description:==
== Description:==
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicant's Actions or Behavior BOP   Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG: Verify alarming condition of 1RIX-PR006A-D Report EOP-8 entry condition Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time     Position                                   Applicants Actions or Behavior BOP     Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:
SRO Directs entry into EOP-8 and EOP actions as entry conditions are met. When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Startup VG CPS 3319.01, Standby Gas General:
* Verify alarming condition of 1RIX-PR006A-D
On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.
* Report EOP-8 entry condition Critical Task
Terminus:   RPV level stable and under control in required band Reactor is Scrammed Effort has been made to isolate RCIC steam lines Failed automatic isolation and actuation (VF/VG) manually performed Upon approval of lead examiner NOTES:       Critical Task Critical Task Critical Task Critical Task D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 12  Simulator Operator Instructions Initial Setup
* Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
* Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs entry into EOP-8 and EOP actions as entry conditions are met.
Critical Task
* When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
* Startup VG CPS 3319.01, Standby Gas General:
* On transient, positions himself as command authority on the unit.
* Acknowledges immediate operator actions and directs subsequent actions.
* Enforces OPS expectations and standards.
* Contacts Shift Manager and recommends notifications.
Terminus:
* RPV level stable and under control in required band
* Reactor is Scrammed
* Effort has been made to isolate RCIC steam lines
* Failed automatic isolation and actuation (VF/VG) manually performed
* Upon approval of lead examiner NOTES:
11
 
D-2, Dynamic Simulator Scenario 3             EXAM DATE: 08/24/09                 08-01 Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
: 2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
Line 2,132: Line 2,952:
: 6. Turn on and advance recorders
: 6. Turn on and advance recorders
: 7. Reset SRM A drawer
: 7. Reset SRM A drawer
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 8. Provide pull sheets: on step 25 rod 08-25 is at 12
: 9. Provide and ECP and RE instructions 1 0. Verify the AR/PR server is running and stabilize AR/PR 1 1. Verify TT alarm is reset 1 2. Verify Rod Drive pressure at 250#
: 9. Provide and ECP and RE instructions
1 3. Hang OOS tags per turnover on #2 SAC 1 4. Identify T/S issues associated with OOS and turnover 1 5. Verify simulator conditions match the turnover 1 6. Provide marked up CPS 3001.01 complete to step 8.2.5 1 7. Provide a marked up CPS 3002.01 complete to step 8.6
: 10. Verify the AR/PR server is running and stabilize AR/PR
: 11. Verify TT alarm is reset
: 12. Verify Rod Drive pressure at 250#
: 13. Hang OOS tags per turnover on #2 SAC
: 14. Identify T/S issues associated with OOS and turnover
: 15. Verify simulator conditions match the turnover
: 16. Provide marked up CPS 3001.01 complete to step 8.2.5
: 17. Provide a marked up CPS 3002.01 complete to step 8.6
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 18. Provide a marked up CPS 9000.06D001 with stable heatup values
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 19. Fill out plant status and have Turnover Sheet ready for the crew
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions  
: 20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12


D-2, Dynamic Simulator Scenario 3                 EXAM DATE: 08/24/09                   08-01 13 Event Triggers and Role Play Event # 1. Test the Generator Emergency Seal Oil Pump
D-2, Dynamic Simulator Scenario 3                     EXAM DATE: 08/24/09                           08-01 Event Triggers and Role Play Event #
: 1. Test the Generator Emergency Seal Oil Pump
: a. No trigger.
: a. No trigger.
: 2. Uncoupled rod
: 2. Uncoupled rod
Line 2,146: Line 2,974:
: 3. Withdraw Rods To criticality
: 3. Withdraw Rods To criticality
: a. No triggers
: a. No triggers
: 4. 'B' SRM fails
: 4. B SRM fails
: a. Remote trigger 2 on request from lead evaluator
: a. Remote trigger 2 on request from lead evaluator
: b. If SRM 'B' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 5. Vacuum Pump trip
: 5. Vacuum Pump trip
: a. Remote trigger 3 on request from lead evaluator
: a. Remote trigger 3 on request from lead evaluator
: b. Role Play- Field operator
: b. Role Play- Field operator
: 6. 'A' SRM fails
: 6. A SRM fails
: a. Remote trigger 4 on request from lead evaluator
: a. Remote trigger 4 on request from lead evaluator
: b. If SRM 'A' drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: c. Maintenance will need a work package to determine the extent of the problem with the SRM.
: 7. RCIC drain trap level high
: 7. RCIC drain trap level high
Line 2,162: Line 2,990:
: 8. RCIC unisolable steam leak
: 8. RCIC unisolable steam leak
: a. Remote trigger 6 on request from lead evaluator
: a. Remote trigger 6 on request from lead evaluator
: b. If RCIC ATM's are checked they read 10 times higher than on the last 9000.01 reading.
: b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: c. Role play as personnel in the field (1) Heavy steam in RCIC room
: d. If valve breakers are checked, no problems are found.
: d. If valve breakers are checked, no problems are found.
Line 2,170: Line 2,998:
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: 10. Radiation monitor fails to initiate an isolation and start up VG.
: a. No triggers
: a. No triggers
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
: b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.
 
13
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM  ILT 08-1 Exam Scenario 4 REVISION 00
 
DEVELOPER:
Tom Pickley 
 
REVIEWED BY:
Simulator Instructor


APPROVED BY:  
Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 4 REVISION 00 DEVELOPER:                    Tom Pickley REVIEWED BY:
Simulator Instructor APPROVED BY:                         /
Operations                      Date


/  Operations Date Overview Makeup/Reject:
Overview Makeup/Reject:             All CPs except J are in service. RO train #1 & 2 are in-service in auto to WD ECCS:                     RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC:                       N/A Electrical:               6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
All CP's except J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:
Radwaste:                 FP/FP 1B in service. 1WF Evap is in Hot Standby. A and B RT F/D are in service.
Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A and B RT F/D are in service.
Plant Status On Line Risk Yellow Reactor Operational Condition:         Mode 1 Total Core Flow:               _84.2 mlb/hr FCV Position:                   A: __86.6__%       B: __87.3 _%
Plant Status Protected Equip
Reactor Power                   _95.8_% (<=100%) _3321_ MWt (<=3473)                 _1089_ Mwe Xenon:                         Stable RPV Level                       _35__ in Narrow Range RPV Pressure                   _1020_ psi (< 1045)
: HPCS and Div 1 & 2 Backup ADS Air Supply On Line Risk Yellow Reactor Operational Condition: Mode 1 Total Core Flow: _84.2   mlb/hr FCV Position: A: __86.6__%     B: __87.3
In service SDC loop             None MODE 1 Containment Suppression Pool Temperature:           _75.5_ F                       (<=93.1 F)
_% Reactor Power _95.8_% (<=100%)   _3321_ MWt (<=3473)     _1089_ Mwe Xenon: Stable RPV Level _35__ in Narrow Range RPV Pressure _1020_ psi (< 1045) In service SDC loop None   MODE 1 Containment Suppression Pool Temperature: _75.5_ F
Suppression Pool Level                   _ 19.2 ft                       (19 ft 0 to 19 ft 5 in)
(<=93.1 F) Suppression Pool Level
Drywell Pressure                         _ 0.6 _ psi                     (0 to 1 psig)
_ 19.2 ft (19 ft 0 to 19 ft 5 in) Drywell Pressure
Drywell to Containment dp:               _ 0.6 _ psi                     >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature:             _ 104_ F                       (<=146.53 F)
_ 0.6 _ psi (0 to 1 psig) Drywell to Containment dp: _
Secondary Containment:                   _ 0.74 in WG                   (>= 0.25 in WG vacuum)
0.6 _ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _
BOP                                                           Plant Chemistry Condenser Vacuum:                       _26.4_ in Hg         CPI (goal < 1.1):                 1.00 Off - Gas Flow:                         _66.6_ scfm           Reactor Sulfates (goal < 2)       1.31 ppb Condensate Temperature:                 _ 109_ F             Reactor Chlorides:               0.51 ppb Generator Reactive Load:                 _ 256 _MVARS         FW Iron (goal < 2.1)             0.85 ppb Protected Equip: HPCS and Div 1 & 2 Backup ADS Air Supply Comments: MDRFP is CO From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)
104_ F (<=146.53 F) Secondary Containment:
Participate in training program activities.
_ 0.74 in WG (>= 0.25 in WG vacuum)
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety
BOP Plant Chemistry Condenser Vacuum: _26.4_ in Hg CPI (goal < 1.1):
1.00 Off - Gas Flow: _66.6_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:
_ 109_ F Reactor Chlorides:
0.51 ppb Generator Reactive Load:
_ 256 _MVARS FW Iron (goal < 2.1) 0.85 ppb Comments: MDRFP is CO  


From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.
Turnover This page contains the Turnover information not found in the Overview page.
Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety Turnover This page contains the Turnover inform ation not found in the Overview page.
: 1. Power, xenon and time in life Power was reduced to 80% for surveillance testing.
: 1. Power, xenon and time in life  
 
Power was reduced to 80% for surveillance testing.
: 2. Status of Tagged Out Equipment MDRFP is OOS for coupling replacement
: 2. Status of Tagged Out Equipment MDRFP is OOS for coupling replacement
: 3. Shift conditions Day Shift Today
: 3. Shift conditions Day Shift Today
: 4. Weather Conditions   Sunny and clear. 5. Thermal Limit Problems or concerns
: 4. Weather Conditions Sunny and clear.
: 6. LCO's in effect
: 5. Thermal Limit Problems or concerns
: 7. Surveillances in progress   Perform 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test.
: 6. LCOs in effect
: 8. 9. Evolutions planned for the shift
: 7. Surveillances in progress Perform 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test.
: 10. Risk Levels Yellow 11. Other Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station   Scenario No.:
8.
Four                   Operating Test No.:
: 9. Evolutions planned for the shift
08-01   Examiners: ____________________________   Operators: ____________________         ____________________________                                                        ____________________                    ____________________________                    ____________________ Initial Conditions:
: 10. Risk Levels Yellow
: 11. Other
 
Appendix D                                   Scenario Outline                                   Form ES-D-1 Facility: Clinton Power Station           Scenario No.: Four             Operating Test No.: 08-01 Examiners: ____________________________                             Operators: ____________________
Initial Conditions:
96% power, steady state.
96% power, steady state.
MDRFP is CO for coupling replacement.
MDRFP is CO for coupling replacement.
Turnover:   VC running for 9070.01, Control Room Hvac Air Filter Package Operability Test Run. A Reduction in power will be requestred by dispatch. Perform 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Event No. Malf. No. Event Type* Event Description 1 IO C-ATC TS-CRS Perform SDV Vent and Drain Valve test one valve fails 2 None R-ATC Reduce power with flow 3 IO C-ATC A RR FCV Drifts shut 4 VC01VC_VC06YA_MTVFA ILSP C-BOP TS-CRS VC Makeup Train A Outlet DMPR fails shut during surveilance run. 5 None N-BOP Shift to the B VC train.
Turnover:
6 F041LTVFAI LSP C-BOP SRV 41L Fails open, closes on first attempt to close 7 YPXMALSE_527 M-ALL Small break LOCA requiring an Emergency Depressurization.
* VC running for 9070.01, Control Room Hvac Air Filter Package Operability Test Run.
8 YP_XMFTB_4106 M-ALL LPCS Pump fails to start on High Drywell Pressure  
* A Reduction in power will be requestred by dispatch.
    *(N)ormal,   (R)eactivity,    (I)nstrument,    (C)omponent,   (M)ajor Page 1 of 2 10/13/2009 Appendix D Scenario Outline Form ES-D-1 Scenario No.:
* Perform 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Event         Malf. No.     Event Type*                                   Event No.                                                                    Description 1               IO           C-ATC     Perform SDV Vent and Drain Valve test one valve fails TS-CRS 2             None           R-ATC     Reduce power with flow 3               IO           C-ATC     A RR FCV Drifts shut 4       VC01VC_VC0            C-BOP     VC Makeup Train A Outlet DMPR fails shut during surveilance run.
Four                        Operating Test No.:
6YA_MTVFA          TS-CRS ILSP 5             None           N-BOP     Shift to the B VC train.
08-01  Narrative Summary
6       F041LTVFAI           C-BOP     SRV 41L Fails open, closes on first attempt to close LSP 7       YPXMALSE_          M-ALL       Small break LOCA requiring an Emergency Depressurization.
527 8       YP_XMFTB_          M-ALL       LPCS Pump fails to start on High Drywell Pressure 4106
*(N)ormal,       (R)eactivity,    (I)nstrument,    (C)omponent,       (M)ajor Page 1 of 2                                     10/13/2009


Event # Description
Appendix D                                Scenario Outline                            Form ES-D-1 Scenario No.: Four                                    Operating Test No.: 08-01 Narrative Summary Event #                                     Description
: 1. The ATC will perform the SDV vent and dr ain valve test and one of the valves will indicate intermediate requiring TS entry
: 1. The ATC will perform the SDV vent and drain valve test and one of the valves will indicate intermediate requiring TS entry
: 2. After shift turnover the Control Room staff will receive a phone call to reduce power for grid stability concerns.
: 2. After shift turnover the Control Room staff will receive a phone call to reduce power for grid stability concerns.
: 3. The A Flow control valve will continue to drift shut slowly requiring the ATC to manually lock out the RR FCV. This may require the ATC to match flows after the transient. 4, 5. The ongoing VC train surveillance will have a damper failure causing TS entry and start of the opposite VC train
: 3. The A Flow control valve will continue to drift shut slowly requiring the ATC to manually lock out the RR FCV. This may require the ATC to match flows after the transient.
: 6. SRV 41L will inadvertantly open this valve is NON-ADS and NON-LLS requiring the BOP to take it to off and will not be available for the B/D. 7. Small break LOCA will get the crew into EOP-1 and EOP-6 the Reactor will require a blow down on Figure N PSP.
4, 5. The ongoing VC train surveillance will have a damper failure causing TS entry and start of the opposite VC train
: 8. Manually start LPCS
: 6. SRV 41L will inadvertantly open this valve is NON-ADS and NON-LLS requiring the BOP to take it to off and will not be available for the B/D.
: 7. Small break LOCA will get the crew into EOP-1 and EOP-6 the Reactor will require a blow down on Figure N PSP.
: 8. Manually start LPCS EOP 1,3,6 Critical tasks:
* Starting Containment Sprays
* Blow Down when Figure N is exceeded.
Page 2 of 2                              10/13/2009


EOP 1,3,6 Critical tasks:  Starting Containment Sprays  Blow Down when Figure N is exceeded. Page  2 of 2 10/13/2009 D-2, Dynamic Simulator Scenario   4     EXAM DATE: 8/24/09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) 96% Power/100% FCL CPS 3005.01 thru step 8.1.19 3328 MWt A-2, step 36 is complete 1092 MWe   84.5 Mlbm/hr CORE FLOW   Thermal Limit Problems/Power Evolutions             Existing LCOs, date of next surveillance None       Surviellances or major maintenance VC running for 9070.01, Control Room HVAC Air Filter Package Operability Test Run 4 hrs 27 min into the 10 hour run.
D-2, Dynamic Simulator Scenario 4             EXAM DATE: 8/24/09                         08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.
(Plant power level) 96% Power/100% FCL                                     CPS 3005.01 thru step 8.1.19 3328 MWt                                               A-2, step 36 is complete 1092 MWe 84.5 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Existing LCOs, date of next surveillance None Surviellances or major maintenance VC running for 9070.01, Control Room HVAC Air Filter Package Operability Test Run 4 hrs 27 min into the 10 hour run.
9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test for position indication only. Stroke times are not needed.
9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test for position indication only. Stroke times are not needed.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment MDRFP is CO for coupling replacement.       Comments, evolutions, problems, etc. Online Safety is Yellow 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test for position indication only. Stroke times are not needed.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment MDRFP is CO for coupling replacement.
Page 1 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
Comments, evolutions, problems, etc.
1  Page 1 of 1
Online Safety is Yellow 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test for position indication only. Stroke times are not needed.
Page 1 of 11


== Description:==
D-2, Dynamic Simulator Scenario 4          EXAM DATE: 8/24/09                              08-01 Operator Actions Event No.(s):        1                                                                    Page    1    of  1


Perform SDV Vent and Drain Valve test one valve fails Initiation: Following turnover Cues:   Shift Turnover Time Position Applicant's Actions or Behavior ATC Performs 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Simultaneously, depress and hold both: Scram Disch Vol Vent V, and Scram Disch Vol DR V Test SW push-buttons, When the valves indicate closed, Release the Scram Disch Vol Vent V and Scram Disch Vol DR V Test Sw push-buttons Report C11-F011 did not fully open BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions Directs the determination of C11-F011 position locally Reports C11-F011 is in an intermediate position SRO Directs the above actions Declares C11-F011 Inop Enters Tech Spec LCO 3.1.8 A.1 Isolate the Line in 7 days.
==
Description:==
Perform SDV Vent and Drain Valve test one valve fails Initiation: Following turnover Cues: Shift Turnover Time     Position                             Applicants Actions or Behavior ATC
* Performs 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test
* Simultaneously, depress and hold both:
Scram Disch Vol Vent V, and Scram Disch Vol DR V Test SW push-buttons, When the valves indicate closed, Release the Scram Disch Vol Vent V and Scram Disch Vol DR V Test Sw push-buttons
* Report C11-F011 did not fully open BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions
* Directs the determination of C11-F011 position locally
* Reports C11-F011 is in an intermediate position SRO
* Directs the above actions
* Declares C11-F011 Inop
* Enters Tech Spec LCO 3.1.8 A.1 Isolate the Line in 7 days.
Terminus: Tech Specs have been entered.
Terminus: Tech Specs have been entered.
Page 2 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
Page 2 of 11
2  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 4            EXAM DATE: 8/24/09                            08-01 Operator Actions Event No.(s):              2                                                            Page    1  of    1
 
==
Description:==
Reduce power with flow Initiation: MISO calls requesting a power reduction to 90% within 30 minutes for Grid Stability.
Reduce power with flow Initiation: MISO calls requesting a power reduction to 90% within 30 minutes for Grid Stability.
Cues: Directed by SRO General Note Time Position Applicant's Actions or Behavior ATC Per CPS 3005.01, Unit Power Changes, step 8.2.8.
Cues: Directed by SRO General Note Time     Position                                 Applicants Actions or Behavior Per CPS 3005.01, Unit Power Changes, step 8.2.8.
Reduce power with Flow to ~90%.
ATC
BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Reduce power with Flow to ~90%.
SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.
BOP
Terminus: Power change complete.
* Monitors reactor to ensure operations remain within established bands
Note: Denotes an action that should be performed.
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs actions listed above.
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Enforces OPS expectations and standards.
Terminus: Power change complete.
Note:
* Denotes an action that should be performed.
o Denotes an action that may be performed.
o Denotes an action that may be performed.
Page 3 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
Page 3 of 11
3  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 4            EXAM DATE: 8/24/09                            08-01 Operator Actions Event No.(s):        3                                                                    Page    1    of  1
 
==
Description:==
A RR FCV Drifts shut Initiation: Following the power change, and upon direction of Lead Examiner.
A RR FCV Drifts shut Initiation: Following the power change, and upon direction of Lead Examiner.
Cues:   Time Position Applicant's Actions or Behavior ATC   Communicates that the A RR FCV is closing. Locksout the A RR FCV by shutting down the HPU o Verifies the FCV motion stops.
Cues:
o ATC may need to match recirc loop flows depending on the time the RRFCV gets locked out.
Time       Position                               Applicants Actions or Behavior ATC
BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO Directs actions listed above. Verifies that the RR loop flows are within Tech Spec limits:  
* Communicates that the A RR FCV is closing.
-if less than 70% rated core flow then loop mismatch is limited to 10% of rated core flow (8.45mlbm/hr)  
* Locksout the A RR FCV by shutting down the HPU o   Verifies the FCV motion stops.
- if greater than or equal to 70% rated core flow then loop mismatch is limited to 5% of rated core flow (4.225 mlbm/hr)
o   ATC may need to match recirc loop flows depending on the time the RRFCV gets locked out.
BOP
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO
* Directs actions listed above.
* Verifies that the RR loop flows are within Tech Spec limits:
                          -if less than 70% rated core flow then loop mismatch is limited to 10% of rated core flow (8.45mlbm/hr)
                          - if greater than or equal to 70% rated core flow then loop mismatch is limited to 5%
of rated core flow (4.225 mlbm/hr)
Terminus: The A RR FCV is locked out.
Terminus: The A RR FCV is locked out.
Page 4 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
Page 4 of 11
4  Page 1 of 1


== Description:==
D-2, Dynamic Simulator Scenario 4          EXAM DATE: 8/24/09                              08-01 Operator Actions Event No.(s):        4                                                                  Page    1  of    1
 
==
Description:==
VC Makeup Train A Outlet DMPR fails shut during surveilance run.
VC Makeup Train A Outlet DMPR fails shut during surveilance run.
Initiation: Following the Tech Spec call and upon direction from the Lead Examiner.
Initiation: Following the Tech Spec call and upon direction from the Lead Examiner.
Cues: Annunciator 5050-5D, Low Flow Downstream 0VC09SA Time Position Applicant's Actions or Behavior BOP Communicates Annunciator 5050-5D References ARP Per CPS 5050-5D Low Flow Downstream 0VC09SA. Stop 0VC05CA CONT RM HVAC MU Air Fan ATC Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Cues: Annunciator 5050-5D, Low Flow Downstream 0VC09SA Time       Position                             Applicants Actions or Behavior BOP
SRO Directs the above actions Enforces OPS expectations and standards Enters Tech Spec LCO 3.7.3 A.1 Restore VC subsystem in 7 days.
* Communicates Annunciator 5050-5D
Terminus: 0VC05CA is off Page 5 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
* References ARP Per CPS 5050-5D Low Flow Downstream 0VC09SA.
5  Page 1 of 1
* Stop 0VC05CA CONT RM HVAC MU Air Fan ATC
* Monitors reactor to ensure operations remain within established bands
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
SRO
* Directs the above actions
* Enforces OPS expectations and standards
* Enters Tech Spec LCO 3.7.3 A.1 Restore VC subsystem in 7 days.
Terminus: 0VC05CA is off Page 5 of 11


== Description:==
D-2, Dynamic Simulator Scenario 4          EXAM DATE: 8/24/09                              08-01 Operator Actions Event No.(s):            5                                                                Page    1  of    1
 
==
Description:==
Shift to the B VC train.
Shift to the B VC train.
Initiation:
Initiation: N/A Cues: Annunciator 5050-5D, Low Flow Downstream 0VC09SA Time     Position                               Applicants Actions or Behavior ATC
N/A Cues: Annunciator 5050-5D, Low Flow Downstream 0VC09SA Time Position Applicant's Actions or Behavior ATC Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Monitors reactor to ensure operations remain within established bands
BOP Per 3402.01P001, CV Train Shifting Direct Equipment Operator to perform local operations Shut Locker Room EXH Fan ISOL DMPR 0VC69Y Shut Locker Room EXH Fan ISOL DMPR 0VC70Y Stop Cont Rm Trn A Supply Fan 0VC03CA Verify Dampers reposition Start Cont Rm Trn B Supply Fan 0VC03CB Verify Dampers reposition Open Locker Room EXH Fan ISOL DMPR 0VC69Y Open Locker Room EXH Fan ISOL DMPR 0VC70Y Direct Chiller Startup SRO Directs the above actions Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
Terminus: VC Train B is running Page 6 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
Per 3402.01P001, CV Train Shifting BOP
6  Page 1 of 1 Description SRV 41L Fails open, closes on first attempt to close Initiation: After VC train B is running and upon direction from the Lead Examiner.
* Direct Equipment Operator to perform local operations
Cues:  Annunciator 5067-8L, SRV Monitoring System Trouble Time Position Applicant's Actions or Behavior ATC  Assists in determination of which SRV is open  Monitors reactor to ensure operati ons remain within established bands  Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
* Shut Locker Room EXH Fan ISOL DMPR 0VC69Y
BOP  Sounds the Containment Evacuation alarm  Place the switch for SRV 41L to OPEN and then back to OFF  Determine the SRV 41L is shut SRO  Enters 4009.01, Inadvertant Opening SRV  Directs the above actions  Enforces OPS expectations and standards  Determines SRV 41L is not required by Tech Specs.
* Shut Locker Room EXH Fan ISOL DMPR 0VC70Y
Terminus:  SRO has determined SRV 41L is not required by Tech Specs
* Stop Cont Rm Trn A Supply Fan 0VC03CA
. Page 7 of 11 D-2, Dynamic Simulator Scenario  4    EXAM DATE: 8/24/09 08-01  Operator Actions Event No.(s):
* Verify Dampers reposition
7 & 8  Page 1 of 2
* Start Cont Rm Trn B Supply Fan 0VC03CB
* Verify Dampers reposition
* Open Locker Room EXH Fan ISOL DMPR 0VC69Y
* Open Locker Room EXH Fan ISOL DMPR 0VC70Y
* Direct Chiller Startup SRO
* Directs the above actions
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: VC Train B is running Page 6 of 11


== Description:==
D-2, Dynamic Simulator Scenario 4          EXAM DATE: 8/24/09                              08-01 Operator Actions Event No.(s):        6                                                                    Page    1  of    1 Description      SRV 41L Fails open, closes on first attempt to close Initiation: After VC train B is running and upon direction from the Lead Examiner.
Small break LOCA requiring an Emergency Depressurization and LPCS Pump fails to start on High Drywell Pressure Initiation: After SRV 41L is shut and upon direction of Lead Examiner Cues:   Rising Drywell Pressure Time Position Applicant's Actions or Behavior ATC Places the Mode Switch in S/D Carries out Scram Choreography by reporting Mode Switch in Shutdown, Power is-  Rod status is-  Reactor Power is- and trend Reactor pressure is- and trend Reactor level is- and trend Any EOPs with entry conditions (EOP-1, 6) Per CPS 4100.01, Reactor Scram Turn Mode Switch to SHUTDOWN Verify reactor power is lowering Verify SHUTDOWN CRITERIA met IF RPV level is rising with 2 feed pumps operating THEN Secure 1 Feed Pump and control RPV water level Level 3 to Level 8. Verify Turbine and Generator trip when required Performs EOP actions as directed by SRO.
Cues: Annunciator 5067-8L, SRV Monitoring System Trouble Time      Position                              Applicants Actions or Behavior ATC
BOP Carries out Scram Choreography by:
* Assists in determination of which SRV is open
Making an Announcement Reactor Scram MDRFP may start Evacuate the RCIC room Evacuate the Containment Determine Rod status and report to CRS Per EOP-6 Primary Containment Control Starts Drywell Mixers, as directed. Starts Containment Spray, as directed.
* Monitors reactor to ensure operations remain within established bands
o Monitors the start of the ECCS Systems on High Drywell Pressure. Determines LPCS did not start and manually starts LPCS Operates ECCS Systems as needed, to control RPV Water Level, Level 3 to Level 8 Initiates ADS Critical Task Critical Task
* Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
BOP
* Sounds the Containment Evacuation alarm
* Place the switch for SRV 41L to OPEN and then back to OFF
* Determine the SRV 41L is shut SRO
* Enters 4009.01, Inadvertant Opening SRV
* Directs the above actions
* Enforces OPS expectations and standards
* Determines SRV 41L is not required by Tech Specs.
Terminus: SRO has determined SRV 41L is not required by Tech Specs.
Page 7 of 11
 
D-2, Dynamic Simulator Scenario 4          EXAM DATE: 8/24/09                          08-01 Operator Actions Event No.(s):      7&8                                                                Page      1  of  2
 
==
Description:==
Small break LOCA requiring an Emergency Depressurization and LPCS Pump fails to start on High Drywell Pressure Initiation: After SRV 41L is shut and upon direction of Lead Examiner Cues: Rising Drywell Pressure Time     Position                             Applicants Actions or Behavior ATC
* Places the Mode Switch in S/D
* Carries out Scram Choreography by reporting Mode Switch in Shutdown, Power is Rod status is Reactor Power is and trend Reactor pressure is and trend Reactor level is and trend Any EOPs with entry conditions (EOP-1, 6)
Per CPS 4100.01, Reactor Scram
* Turn Mode Switch to SHUTDOWN Verify reactor power is lowering Verify SHUTDOWN CRITERIA met
* IF RPV level is rising with 2 feed pumps operating
* THEN         Secure 1 Feed Pump and control RPV water level Level 3 to Level 8.
* Verify Turbine and Generator trip when required
* Performs EOP actions as directed by SRO.
Carries out Scram Choreography by:
BOP
* Making an Announcement Reactor Scram MDRFP may start Evacuate the RCIC room Evacuate the Containment
* Determine Rod status and report to CRS Per EOP-6 Primary Containment Control
* Starts Drywell Mixers, as directed.
Critical Task
* Starts Containment Spray, as directed.
o Monitors the start of the ECCS Systems on High Drywell Pressure.
* Determines LPCS did not start and manually starts LPCS Critical Task
* Operates ECCS Systems as needed, to control RPV Water Level, Level 3 to Level 8
* Initiates ADS Page 8 of 11


Page 8 of 11 D-2, Dynamic Simulator Scenario   4     EXAM DATE: 8/24/09 08-01 Event No.(s):
D-2, Dynamic Simulator Scenario 4         EXAM DATE: 8/24/09                             08-01 Event No.(s):       8&9                                                                 Page   2 of   2 Time     Position                             Applicants Actions or Behavior SRO
8 & 9 Page 2 of 2 Time Position Applicant's Actions or Behavior SRO     Carries out Scram Choreography by performing an Update: Entering EOP-1 and 6 Entering Scram Off-Normal Transient Annunciator Response is authorized Enters EOP-1, RPV Control, and directs the following:
* Carries out Scram Choreography by performing an Update:
Determines Mode Switch is in SHUTDOWN. Determines Shutdown Criteria is met. Directs control of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs. Directs maintaining RPV Level, Level 3 to Level 8 by using Preferred Injection Systems. Enters EOP-6, Primary Containment Control, and directs the following:
Entering EOP-1 and 6 Entering Scram Off-Normal Transient Annunciator Response is authorized Enters EOP-1, RPV Control, and directs the following:
Starting Mixers IAW Fig. O, directs the start of Containment Sprays.
* Determines Mode Switch is in SHUTDOWN.
Enters EOP-3, Emergency RPV Depressurization, when Figure N is exceeded. Directs initiation of ADS Directs opening other SRVs until 7 are open May direct the isolation of RT and/or RR. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
* Determines Shutdown Criteria is met.
* Directs control of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs.
* Directs maintaining RPV Level, Level 3 to Level 8 by using Preferred Injection Systems.
Enters EOP-6, Primary Containment Control, and directs the following:
* Starting Mixers Critical Task
* IAW Fig. O, directs the start of Containment Sprays.
Enters EOP-3, Emergency RPV Depressurization, when Figure N is exceeded.
Critical Task
* Directs initiation of ADS
* Directs opening other SRVs until 7 are open May direct the isolation of RT and/or RR.
* Enforces OPS expectations and standards
* Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
Terminus: 7 SRVs are open, level band of 3 to 8 is established and upon direction of Lead Examiner.
Terminus: 7 SRVs are open, level band of 3 to 8 is established and upon direction of Lead Examiner.
Critical Tasks Initiate Containment Sprays. Initiate ADS.
Critical Tasks
Critical Task Critical Task Page 9 of 11 D-2, Dynamic Simulator Scenario   4     EXAM DATE: 8/24/09 08-01 Simulator Operator Instructions Initial Setup
* Initiate Containment Sprays.
* Initiate ADS.
Page 9 of 11
 
D-2, Dynamic Simulator Scenario 4           EXAM DATE: 8/24/09                         08-01 Simulator Operator Instructions Initial Setup
: 1. Verify daily lamp test completed
: 1. Verify daily lamp test completed
: 2. Reset to IC for this scenario (Verify/Adjust Power to 96% with flow).
: 2. Reset to IC for this scenario (Verify/Adjust Power to 96% with flow).
Line 2,309: Line 3,239:
: 7. Verify RCIC Flow Controller is set at 620 psig.
: 7. Verify RCIC Flow Controller is set at 620 psig.
: 8. Ensure the correct number of CPs are in service.
: 8. Ensure the correct number of CPs are in service.
: 9. Make sure CRD drive water D/P is in the expected range 1 0. Verify correct Control Rod Move Sheets in P680 Book and the correct Cram array are used 1 1. Turn on and advance recorders 1 2. Hang OOS tags per turnover 1 3. Identify T/S issues associated with OOS and turnover 1 4. Verify simulator conditions match the turnover 1 5. Provide copies of the following: 9070.01, Control Room Hvac Air Filter Package Operability Test Run. 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Page 10 of 11 D-2, Dynamic Simulator Scenario   4     EXAM DATE: 8/24/09 08-01 Page 11 of 11    Event Triggers and Role Play Event #   1. Perform SDV Vent and Drain Valve test one valve fails
: 9. Make sure CRD drive water D/P is in the expected range
: 10. Verify correct Control Rod Move Sheets in P680 Book and the correct Cram array are used
: 11. Turn on and advance recorders
: 12. Hang OOS tags per turnover
: 13. Identify T/S issues associated with OOS and turnover
: 14. Verify simulator conditions match the turnover
: 15. Provide copies of the following:
9070.01, Control Room Hvac Air Filter Package Operability Test Run.
9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Page 10 of 11
 
D-2, Dynamic Simulator Scenario 4         EXAM DATE: 8/24/09                       08-01 Event Triggers and Role Play Event #
: 1. Perform SDV Vent and Drain Valve test one valve fails
: a. On a Trigger
: a. On a Trigger
: b. Roll play:
: b. Roll play:
Line 2,318: Line 3,259:
: b. Role play: As the MISO call requesting a power reduction to 90% within 30 minutes for Grid Stability.
: b. Role play: As the MISO call requesting a power reduction to 90% within 30 minutes for Grid Stability.
: 3. RR FCV Fails shut
: 3. RR FCV Fails shut
: a. Remote 1 b. Role play: None
: a. Remote 1
: b. Role play: None
: 4. VC Makeup Train A Outlet DMPR fails shut during surveilance run
: 4. VC Makeup Train A Outlet DMPR fails shut during surveilance run
: a. Remote 2 b. Role play: The 'A' 0VC05CA Fan is making noise and vibrating.
: a. Remote 2
: b. Role play: The A 0VC05CA Fan is making noise and vibrating.
: 5. Shift to the B VC train
: 5. Shift to the B VC train
: a. P ending Page
: a. Pending Page
: b. Role play:
: b. Role play: Equipment Operator Perform Local operations Report the backdraft dampers are shut when asked by the CR.
Equipment Operator Perform Local operations Report the backdraft dampers are shut when asked by the CR.
Start VC Chiller
Start VC Chiller
: 6. SRV 41L Fails open, closes on first attempt to close intermittent.
: 6. SRV 41L Fails open, closes on first attempt to close intermittent.
: a. Remote 3 b. Role Play: None
: a. Remote 3
: b. Role Play: None
: 7. Small break LOCA requiring an Emergency Depressurization.
: 7. Small break LOCA requiring an Emergency Depressurization.
: a. Remote 4 b. Role play: None.
: a. Remote 4
: b. Role play: None.
: 8. LPCS Pump fails to start on High Drywell Pressure
: 8. LPCS Pump fails to start on High Drywell Pressure
: a. N one b. Role play: None}}
: a. None
: b. Role play: None Page 11 of 11}}

Latest revision as of 02:23, 12 March 2020

2009 Clinton Power Station Initial License Examination Administered Scenarios
ML100710757
Person / Time
Site: Clinton Constellation icon.png
Issue date: 08/24/2009
From: Valos N
Operations Branch III
To:
References
Download: ML100710757 (184)
v • d • e


Text

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-01 Exam Scenario 1 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: All CPs except H and J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: 1WF Evap is in operating. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: __70.7___ mlb/hr FCV Position: A: __52.8_____% B: __53.1____%

Reactor Power __65__% (<=100%) _2282__ MWt (<=3473) _737__ Mwe Xenon: Stable RPV Level _33_ in Narrow Range RPV Pressure _963__ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.8 _ psi (0 to 1 psig)

Drywell to Containment dp: _0.8 _ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _104_ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _28_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _38.5_scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _94_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _228_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station: Clinton Valid Date(s): xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.1 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Joe Top / xx/xx/xx Reviewed by: Roger Bottom /xx/xx/xx Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle Strange / xx/xx/xx Authorized by: / xx/xx/xx RE Manager / Date Senior Reactor Operator / Date NF Review by Michael Charm / xx/xx/xx NF Reciewer / Date ReMA Activated: / xx/xx/xx ReMA Terminated: / xx/xx/xx Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: Power Reduction to Removal of A TDRFP Purpose/Overview of Evolution:

This ReMA is provided for a non emergent load reduction to support removal of the A TDRFP.

This ReMA is NOT intended to take the place of emergency load reductions per the guidance of CPS 3005.01, Unit Power Changes. Emergency load reductions shall be implemented per the guidance of CPS 3005.01, Unit Power Changes.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction

1. Reduce reactor power to 60% with flow
2. Maintain reactor power using rods and flow 3.

4.

General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

Main Steam Line Radiation Monitors may initially show elevated response from crud burst in core (due to rod movements) and from hydrogen pockets being swept into the core (due to flow perturbations in the condensate /

feedwater piping). Response should diminish as the feedwater system comes to equilibrium.

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 1 of 2 Reactivity Maneuver Plan # C11-Simu.1 Description of Step :

Reduce reactor power to ~ 60% with flow.

Rod notching may also be used if necessary to control FCL. The Reactor Engineer will provide guidance on the control rods to be moved to achieve the FCL necessary to support operating at 60%.

It is acceptable to stop at intermediate power levels as necessary to support plant conditions.

Note: Additional monitoring is required per CPS 3005.01, in addition to what is specified below.

QNE presence required in the Control Room? Yes No X*

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR < 0.900 Core Flow (Mlb/hr or %) N/A N/A MFLPD < 0.900 FCL (%) < 90.0 % MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 90.0 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after completion of power reduction.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 2 of 2 Reactivity Maneuver Plan # C11-Simu.1 Description of Step :

Maintain target power level using available flow. Rod notching may also be used, as needed, to maintain power level. The Reactor Engineer will provide guidance on when to notch control rods.

QNE presence required in the Control Room? Yes _ _ No X*

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

~60% N/A N/A Core Power (MWth or %) MFLCPR

(~2084 MWt)

Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0 10 20 30 40 50 60 70 80 90 100 110 3473 100 MELLLA Limit [100.7% FCL]

3126 90 Restricted 90% FCL (Typ.)

2778 Zone 80%

80 THERMAL POWER - MWTh 2431 70 PERCENT THERMAL POWER 2084 60 60%

CON T R OLLE D 1737 50 E N T R Y R E GION 50%

1389 40 40%

1042 30 868 25 695 20 OPRM ENABLED CAVITATION 347 REGION PROTECTION LINES 10 OPRM OPERABLE

[21.6 % CTP, 750 MWth] SINGLE LOOP [> 25% CTP AND (HIGH SPEED, 2 PUMP ENVELOPE < 60% FLOW] OPERATION) 0 0 0.0 8.5 16.9 25.4 33.8 42.3 50.7 59.2 67.6 76.1 84.5 93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: One Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

65% power, Drywell pressure is high.

Thunderstorm storms are expected in the area within the next hour.

Turnover:

1. Run B mixer to reduce DW pressure - First Priority
2. Power needs lowered to 60% power to remove the A RFPT from service for a scheduled outage due to problems.

Event Malf. No. Event Event No. Type* Description 1 HVAC_SP N-BOP Reduce DW pressure, B mixer trips, entry into ITS.

ARE_L3 1 TS-CRS 2 NA R-ATC Power reduction to support removal of A TDRFP 3 Override C-ATC A TDRFP trouble alarm 4 Override C-ATC B RWCU pump seal plate temperature high 5 YP_XMFT TS-CRS A APRM fails downscale.

B_4912 1 6 YFFWPPS C-BOP B MC pump coupling fails S_13 1 7 YPXMALS C-BOP Fuel failure E_1 8 YP_XMFT M-ALL Debris in the Condenser causes all CD pumps to trip B_4068, 69, 70, 71 9 RR03 M-ALL A small RR leak occurs in the Drywell 10 YFRIPPSS M-ALL The RCIC shaft breaks 11 YP_XMFT M-ALL HPCS Injects and then trips B_4103

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: One Operating Test No.: 08-01 Narrative Summary Event # Description

1. Drywell pressure is high requiring the BOP to run B mixing compressor to reduce Drywell pressure. Operational Requirement Manual action 3.5.2 for the test Prep switch entered. The mixing compressor trips and the CRS enters ITS 3.6.3.3.
2. Power is reduced with recirculation flow to allow removal of the RFPT.
3. A TDRFP experiences a trouble alarm on a thrust bearing wear condition requiring tripping of the A TDRFP. This will require verification that the running B TDRFP is adequately maintaining level. A RR FCV runback will require entry to CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control to verify no core instabilities along with entry into CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power
4. RWCU pump B develops a seal leak requiring its removal from service.
5. A APRM fails down scale entry into ITS 3.3.1.1 and OPRM ITS 3.3.1.3.
6. B MC pump coupling fails results in the loss of makeup condensate. This requires the startup of the standby pump.
7. Fuel clad failure will require entry to the CPS 4010.01. Subsequent activities will require the BOP to shut valves RE021&22, RF021&22, along with other activities.

8, 9, 10 & 11. Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps. A small RR loop leak occurs and the RCIC shaft breaks and HPCS injects and then trips. A Blowdown is performed at TAF and level is recovered with Low Pressure ECCS.

EOPS 1,3,6 Critical tasks:

  • Emergency Depressurize when less than TAF.
  • Recover level to above TAF.

Page 2 of 2

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level) 65% Power/70% FCL CPS 3005.01 thru step 8.2.9 2312 MWt A-2, step 36 is complete 747 MWe 70.7 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Reactor Power has been reduced to 65% and is scheduled to continue to 60% with RR FCVs to allow for RFPT 1A removal from service for maintenance to work on some problems.

Existing LCOs, date of next surveillance None Surviellances or major maintenance CPS 9014.01 RPC Sys W/D Limitation Test was completed SAT last month.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.

Online Safety is Green Containment pressure is 0.3 psig First Priority - Run B mixer to reduce DW Lower power to 60% with flow within pressure (lowest run time). the next hour to support removal of A Per Cumulative Date 9094.01D001for this TDRFP.

month: A Mixer run time is 4 hrs 52 minutes B Mixer run time is 5 minutes Cumulative data will be taken care of by the WCS 1

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Reduce Drywell pressure Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3316.01, Containment Combustible Gas Control, step 8.3:

Places MOV Test Prep Switch for CGCS Div 2 to Test and notes time.

1. Start CGCS Hydrogen Cmpr 1B, 1HG02CB.
  • Record start time IAW CPS 9094.01D001
2. Verify 1HG009B, CGCS Cmpr 1B Suct Vlv opens.

At DW pressure of .6 psig the B Mixer will trip off.

SECURING DRYWELL VENTING

1. Stop CGCS Hydrogen Cmpr 1B, 1HG02CB.
  • Record stop time IAW CPS 9094.01D001
2. Verify 1HG009A(B), CGCS Cmpr1B Suct Vlv shuts. (If the control switch is not taken to stop the suction valve will remain open)
  • Places MOV Test Prep Switch for CGCS Div 2 into NORMAL and notes time.

RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Applies ORM ACTION 3.5.2 for MOV Test Prep Switch for CGCS Div 2
  • Enters ITS 3.6.3.3 A.1 for B Mixer.

Terminus: D/W Venting is completed and ITS call completed NOTES:

2

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Power reduction to support removal of the A RFPT turbine Initiation: Following D/W Venting and ITS call.

Cues: Directed by SRO Time Position Applicants Actions or Behavior Per CPS 3005.01, Unit Power Changes, step 8.2.8.

RO

  • Reduce power with Flow to ~60%.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

Terminus: Clearly observable plant response from change in power level.

NOTES:

3

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

A TDRFP trouble alarm Initiation: Following the power reduction, on the signal of lead examiner Cues: Annunciator 5002-1B alarms , report from field operator Time Position Applicants Actions or Behavior RO Per CPS 5002-1B, RFP 1A trouble:

  • Trips the A TDRFP due to high thrust bearing wear
  • Observes Low Level Alarm and RR FCV runback Per CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, monitor for:
  • Entry to the restricted zone
  • Core Instabilities power operating Map CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power
  • As necessary, Start/stop Condensate, Condensate Booster or Reactor Feedwater pumps in support of level control.
  • Maintain adequate NPSH to the Feed Pumps (> 320 psig)

BOP

  • Dispatches a field operator
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Enters CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, Directs actions listed above.
  • Enters CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power, Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

o Contacts Shift Manager and recommends notifications.

Terminus: A TDRFP tripped and RPV level stabilized NOTES:

TO EVALUATORS: If computer points FW-BC902 and or FW-BC903 are called up on DCS, inform the operators they both indicate High. (This is a limitation of the simulator.)

4

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

RWCU Pump seal plate temperature high Initiation: Upon resolution of the FW transient on the signal of the lead evaluator Cues: Annunciator CPS 5000-2E alarms Time Position Applicants Actions or Behavior RO Per CPS 3303.01, RWCU step 8.1.4 and 8.1.3:

  • Direct field Operator to remove all Filter demins from service
  • Open the F/D bypass valve
  • Shutdown RWCU pump B
  • Place one F/D in service BOP
  • Dispatches a field operator to support RWCU operation
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Enters CPS 3303.01 Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

o Contacts Shift Manager and recommends notifications.

Terminus: RWCU pump has been shutdown IAW CPS 3303.01 NOTES:

5

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Failure of A APRM Initiation: RWCU pump has been shutdown IAW CPS 3303.01, on the signal of lead examiner Cues: Annunciator 5060-8E Time Position Applicants Actions or Behavior BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any additional unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Declares A APRM Inop per ITS 3.3.1.1 A.1 and A OPRM Inop per ITS 3.3.1.3.A.1 or A.2 or A.3.
  • Complies with action statement(s) for T.S. Section o May direct going to Sensor Bypass for Div 1.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

o Contacts Shift Manager and recommends notifications.

Terminus: SRO has addressed ITS requirements.

NOTES:

6

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

MC pump B coupling fails Initiation: SRO has addressed I.T.S. requirements, on the signal of lead examiner Cues: Annunciator CPS 5014-2C alarming Time Position Applicants Actions or Behavior BOP Per CPS 3208.01 MC/CY, STEP 8.1.1.1 (or 8.2.2):

  • Direct shutting the discharge valve and reopen upon pump start (if section 8.1.1.1 is used).
  • Start up the standby pump
  • Shutdown the failed pump RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards.

o Contacts Shift Manager.

Terminus: Standby Pump started and shutdown of the failed pump NOTES:

7

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

Fuel failure Initiation: After crew has started an other MC pump, on the signal of lead examiner Cues: OG pretreat alarming, MSL rad monitors trending up Time Position Applicants Actions or Behavior BOP Per CPS 4010.01, Reactor Coolant Hi Activity, Sub. Action:

  • Sound the CNMT evacuation alarm.
  • Shut:
  • 1RF021, Flr Drain Sump Disch CNMT Inbd Vlv.
  • 1RF022, Flr Drain Sump Disch CNMT Outbd Vlv.

CPS 3408.01 VR/VQ, Step 8.1.1.2:

o Shift CNMT Building HVAC System to Continuous CNMT Purge Filtered mode RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

o Contacts Shift Manager and recommends notifications.

Terminus: Valves shut, SRO has entered CPS 4010.01 and directed actions accordingly.

NOTES:

8

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 8, 9,10,11 Page 1 of 2

Description:

Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps and small RR leak.

Initiation: After Fuel Failure has been addressed, on the signal of lead examiner Cues: All Condensate and Feedwater pumps trip Time Position Applicants Actions or Behavior RO Inserts a manual scram CPS 4100.01, Reactor Scram:

Critical Task

  • Place mode switch in Shutdown
  • Check and report power 1% and trending down
  • Check rods, reports shutdown criteria is met
  • Report level and pressure are following expected trends
  • Verify turbine and generator are tripped
  • Stabilize pressure <1065 psig Performs EOP/ON actions as directed by SRO
  • Coordinates with BOP operator to monitor and control RPV press BOP
  • Makes plant announcement for reactor scram and evacuate the containment
  • Coordinates with RO to monitor and control RPV press
  • Evacuate the Containment Performs EOP/ON actions as directed by SRO
  • Reports HPCS Injection and trip
  • Reports RCIC will not inject
  • Inject with SLC Critical Task
  • verifies 7 ADS valves are open
  • Maximizes injection and restores level above TAF NOTES:

9

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Event No.(s): 8, 9,10 Unisolable main steam line Page 2 of 2 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-1, EOP-6 for high drywell pressure and EOP-3 (Blowdown) actions as entry conditions are met.

  • Directs Stabilize pressure below 1065 psig
  • Hold level above TAF
  • Inject with SLC Critical Task When RPV water level is less than TAF, directs entry into EOP-3 and EOP actions:
  • Initiation of ADS
  • verify 7 ADS valves are open Terminus:
  • Reactor scrammed
  • ADS has been initiated
  • Level restored above TAF
  • Upon approval of lead examiner NOTES:

10

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to IC-41 (Verify/Adjust Power to 65% with rods and/or flow to match turnover).
  • Make sure DW pressure is up to ~1.0 psig built into the initial conditions or the Lesson plan
  • Ensure B MC pump is running
  • B RT pump is running.
  • A TDRFP is running.
3. Load the lesson plan for this scenario.
4. Place simulator in RUN
5. Verify Rod Drive pressure at 250 #.
6. Turn on and advance recorders
7. Verify the AR/PR server is running and stabilize AR/PR
8. Identify T/S issues associated with OOS and turnover
9. Ensure PR001 is on service and PR002 is in Standby. (Main Stack monitors).
10. Ensure PR012 is operating / in-service. (If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. This is a limitation discovered during ITR/Validation of scenario, PR012 wont auto start and cant be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)
11. Verify simulator conditions match the turnover
12. Provide a copy of CPS 3005.01, signing for step 8.2.9.
13. Fill out plant status and have Turnover Sheet ready for the crew.
14. Provide pull sheets, REMA, Re instructions and Cram Instructions.

11

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Event Triggers and Role Play If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. (This is a limitation discovered during ITR/Validation of scenario, PR012 wont auto start and cant be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)

Event #

1. Lower DW pressure.
a. No trigger. Activates when D/W pressure is less than .6 psig.
b. Role play - To support this evolution. If sent to B Mixer it appears fine. If sent to B Mixer breaker it is tripped and has a bad smell. NO FIRE.
c. Role play - If asked then Cumulative data will be taken care of by the WCS.
2. Power reduction to support removal of a RFPT turbine
a. No triggers
3. A TDRFP trouble alarm
a. Remote trigger 1
b. Role Play- field Operator that 43 psig on Thrust Bearing Wear Pressure at 1PL76JA and starting to hear unusual sounds from A TDRFP.
c. TO EVALUATORS / Booth Operators: If computer points FW-BC902 and or FW-BC903 are called up on PPC, inform the operators they both indicate High. (This is a limitation of the simulator.)
d. Role Play for Chemistry, RP and RE.
4. B RT pump seal plate temperature high
a. Remote trigger 2 on request from lead evaluator
b. Role play field operator that B RT pump seal temperature is 285 degrees and rising slowly. The CCW is lined up to this pump and the other A RT pump is at 175 degrees and stable. No steam in the room.
c. Remote trigger 7 to remove RT F/D A, Remote trigger 8 to remove RT F/D B.
d. Remote trigger 9 to place on service RT F/D A, Remote trigger 10 to place on service RT F/D B
5. A APRM fails down scale
a. Remote trigger 3 on request from lead evaluator
b. Role play as C/I if requested, investigating. Will come up with troubleshooting plan.
6. B MC pump coupling fails.
a. Remote trigger 4 on request from lead evaluator
b. Role Play - B MC coupling is failed and support the startup of the A MC pump.
7. Fuel failure
a. Remote trigger 5 on request from lead evaluator
b. Role Play - If requested Primary to secondary Ctnt d/p is .0125 psid.
c. Role Play - As Chemistry and RP is called.
d. If back panels are checked, inform operators all MSL Rads are tracking together.

12

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01

8. Loss of all Condensate Pumps
a. Remote trigger 6 on request from lead evaluator.
b. After 2 minutes from scram announcement go to MCR as IMD.

13

Procedures Used During Simulator Scenario # 1 (List of Annunciators on back of page)

1. EOP-1
2. EOP-3
3. EOP-9
4. 3316.01 CCGS
5. ITS/ORM/ODCM
6. 3005.01 Unit Power Changes
7. 4008.01 O/N
8. 4100.02 O/N
9. 4002.01 O/N
10. 3303.01 RT
11. 3208.01 MC/CY
12. 4010.01 O/N
13. 3408.01 VR/VQ
14. 4100.01 O/N
15. 4001.02 O/N
16. 4979.01 O/N
17. 4411.03
18. 4411.09
19. Annuciators:
  • 5002-1B, 1C, 2Q, 4G
  • 5000-2E, 2C
  • 5060-8E
  • 5014-2C
  • 5041-7H,1C
  • 5041-1c, 7H
  • 5031-1G
  • 5003-1D/E
  • 5006-3D
  • 5016-1G
  • 5000-2C/E/F
  • 5043-2A, 1G
  • 5042-5H
  • 5043-1G
  • 5067-3E/F, 2L
  • 5013-3A, 4E
  • 5064-3C/D, 4C/D
  • 5130-1G, 2G
  • 5004-1L
  • 5006-3D, 2H
  • 5062-8E
  • All alarms after the Scram

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: CPs B,C,D,E and F are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: _32.4_ mlb/hr FCV Position: A: __90___% B: __90__%

Reactor Power _27_% (<=100%) _919_ MWt (<=3473) _244_ Mwe Xenon: Stable RPV Level _29_ in Narrow Range RPV Pressure _929_ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.5_ psi (0 to 1 psig)

Drywell to Containment dp: _0.5_ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _103_ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _28.7_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _34.4_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _84_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _85.4_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station: Clinton Valid Date(s): xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Roger Bottom / xx/xx/xx Reviewed by: Joe QNE / xx/xx/xx Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ xx/xx/xx Authorized by: / xx/xx/xx RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / xx/xx/xx NF Reviewer / Date ReMA Activated: / xx/xx/xx ReMA Terminated: / xx/xx/xx Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for raising reactor power to support upshift of the RR Pumps.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power increase

1. Withdraw control rods to achieve conditions to support RR Upshift
2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr) 3.

4.

General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 1 of 2 Reactivity Maneuver Plan # C11-Simu.3 Description of Step :

Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed.

Perform control rod pulls in accordance with approved sequence.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.

QNE presence required in the Control Room? Yes X No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR N/A N/A Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 57.3 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 2 of 2 Reactivity Maneuver Plan # C11-Simu.3 Description of Step :

Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.

Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.

Note: It is possible that performing a pump upshift will cause the plant to enter into the CONTROLLED ENTRY REGION of the power / flow operating map. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable.

QNE presence required in the Control Room? Yes X* No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR < 0.900 Core Flow (Mlb/hr or %) N/A N/A MFLPD < 0.900 FCL (%) < 57.3% MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0 10 20 30 40 50 60 70 80 90 100 110 3473 100 MELLLA Limit [100.7% FCL]

3126 90 Restricted 90% FCL (Typ.)

2778 Zone 80%

80 THERMAL POWER - MWTh 2431 70 PERCENT THERMAL POWER 2084 60 60%

CON T R OLLE D 1737 50 E N T R Y R E GION 50%

1389 40 40%

1042 30 868 25 695 20 OPRM ENABLED CAVITATION 347 REGION PROTECTION LINES 10 OPRM OPERABLE

[21.6 % CTP, 750 MWth] SINGLE LOOP [> 25% CTP AND (HIGH SPEED, 2 PUMP ENVELOPE < 60% FLOW] OPERATION) 0 0 0.0 8.5 16.9 25.4 33.8 42.3 50.7 59.2 67.6 76.1 84.5 93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Two Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

27% power RR Pumps on LFMG, Pulling rods to 30% power for Recirculation pump upshift.

Thunderstorms are expected in the area within the next hour.

Turnover:

1. Shift Main EHC pump to support maintenance - First Priority.
2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.

Malf. No. Event Event Type* Description 1 NA N-BOP Main EHC pump swap.

2 NA R-ATC Pull rods to raise power.

3 4025I_Acti C-ATC Rod drifts outward.

on3ROD16 49I_ACTIO TS-CRS N3 1 4 HP01HP_1 C-BOP HPCS WLP Shaft shears.

E22C003_

MTFSHEA TS-CRS R1 5 YAFWPPL C-ATC A CB pump clogged oil filter/bearing oil deficiency.

B_5 30.000 6 YP_XMFT C-BOP Trip of B CCW pump.

B_3918 1 7 YAMSAVF I-BOP SSE level control failure.

P_15 0.0 8 YP_XMFT M-ALL RPV Instrument line failure in the secondary containment.

B_5082 1 9 YP_XMFT M-ALL Auto and Manual scram failure.

B_4963 1 10 YP_XMFT M-ALL One SLC Pump fails to start B_5107 _1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Two Operating Test No.: 08-01 Narrative Summary Event # Description

1. Swap the running Main EHC pumps, the A Main EHC pump will be started and the B Main EHC pump shutdown.
2. Allow rod withdrawal to raise power.
3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.
4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1 and B.2.
5. A CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the A pump.
6. Trip of B CCW pump. Start up A CCW pump.
7. SSE level control fails causing level to go low requiring the manual level control to restore level on the SSE.
8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.
9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to shutdown the reactor.
10. When SLC is started the B SLC pump fails to start.

EOPS 8,1A,3 Critical tasks:

  • Terminate and Prevent Injection prior to emergency depressurization
  • Initiate emergency depressurization once two Max Safe temperatures are exceeded.
  • Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.

Page 2 of 2

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level) 27% Power A-2, step 27 is complete, 16-33 at 26 944 MWt 252 MWe 32.4 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed.

RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized Existing LCOs, date of next surveillance Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.

Online Safety is Green In 3004.01 complete thru step 8.3.10 Shift Main EHC pump to support Carrying electrical load in accordance maintenance - First Priority. with the Power Team.

1

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Main EHC running pump swap.

Initiation: Following turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3105.02, EHC, STEP 8.1.2.1:

  • Startup the standby pump (A)
  • Wait for at least thirty seconds
  • Shutdown the running pump (B) 5017-3A may or may not alarm.
  • Test the standby pump (B)

The standby pump is started by a local operation and then stopped in the control room.

RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: Main EHC pumps shifted NOTES:

2

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Pull rods to raise power Initiation: Following Main EHC pump shift.

Cues: Directed by SRO Time Position Applicants Actions or Behavior Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-RO CL-721 series:

  • Withdraw rods to raise power to 30%

Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO
  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Clearly observable plant response from change in power level.

NOTES:

3

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time Position Applicants Actions or Behavior RO Per Inadvertent Rod Movement, CPS 4007.02:

Immediate actions

  • Select and fully insert the moving rod with the In Timer Skip button Subsequent actions;
  • Once fully inserted release the In Timer Skip button
  • Observe rod withdrawal
  • Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled:

Monitor for core instabilities BOP

  • Dispatch a field operator to the HCU for the rod
  • Directs field operator to Individually scram rod
  • Evaluates thermal limits
  • Evaluate MSL rad monitor values
  • Evaluates OG Rad levels SRO
  • Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02
  • Contacts Shift Manager and recommends notifications.

Terminus: Once rod is fully inserted, individually scrammed and Tech Specs referenced.

NOTES:

4

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time Position Applicants Actions or Behavior BOP Per ARP Procedure CPS 5062-7D:

  • Dispatches NLO to investigate.

o If ATM is checked for pressure it reads 0 psig When directed:

  • Shutdown the HPCS WLP Pump.

Per HPCS CPS 3309.01 precaution 4.3:

  • Dispatches NLO to remove HPCS control power fuses.

5062-7B will alarm.

RO

  • Monitors reactor to ensure operations remain within established bands.
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Contacts Shift Manager and recommends notifications.

Terminus: HPCS control power fuses removed and Technical Specifications evaluated.

NOTES:

If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.

5

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

CB pump A clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.

Cues: Annunciator CPS 5001-1H alarming, Time Position Applicants Actions or Behavior RO CPS 5001-1H, Clogged Oil Filter CB 1A:

Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2:

  • Startup standby CB pump
  • Shutdown A CB pump BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Standby CB pump started and shutdown the A CB pump.

NOTES:

6

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

Trip of B CCW pump Initiation: After shifting of CB pumps, on the signal of lead examiner Cues: Annunciator CPS 5040-1B alarming, Time Position Applicants Actions or Behavior RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.
  • Responds to annunciator 5003-3D and 3E, RR Low Cooling Water Flow.

BOP

  • Starts standby pump per ARP (O/A 2.a).
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Directs starting of A CCW pump.
  • Directs RO to monitor RR and RT Temps.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Standby CCW pump started.

NOTES:

7

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time Position Applicants Actions or Behavior BOP Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2:

  • Determines level to be low.
  • Direct field operator to investigate.
  • Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2.

Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.

RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: SSE level restored and alarm clear NOTES:

May take up to (2) minutes for alarm to come in. (This is normal.)

8

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 8,9,10 Page 1 of 5

Description:

RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time Position Applicants Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO

  • Place mode switch in Shutdown
  • Check and report power unchanged
  • Operate FW to control level 3 to 8
  • Check rods, reports shutdown criteria is not met
  • Report level and pressure are following expected trends
  • Stabilize pressure <1065 psig
  • Coordinates with BOP operator to monitor and control RPV level and press BOP
  • Makes plant announcement for reactor scram
  • Should make plant announcement to evacuate Fuel/Aux buildings.

Performs EOP actions as directed by SRO

  • Verifies operation of area coolers
  • Verifies operation of VF, Fuel Bldg Vent.
  • Monitors area temperatures, levels and radiation levels Critical Task
  • Coordinates with RO to monitor and control RPV level and press NOTES:

9

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 2 of 5 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF
2. Operate area coolers
3. Hold floor drain sump levels below max. normal
4. Isolate all discharges into the affected area except systems needed for:
  • Fire Fighting
5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage:
  • Directs BOP to isolate the source of leakage
6. Direct a scram prior to exceeding Maximum safe temperature
7. Enters EOP-1 Directs additional actions:
1. Notification of Radiation Protection (RP) Department
2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:
1. Mode Switch to SHUTDOWN
  • Per EOP-1 enters EOP-1A Critical Task Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas NOTES:

10

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 3 of 5 Time Position Applicants Actions or Behavior RO Performs EOP actions as directed by SRO:

  • Directs defeating RPC for further rod insertion
  • Verifies RR downshifts at Level 3, and trips at Level 2.

Critical Task

  • Terminates and prevents injection CB/FW systems CPS 4411.02 Critical Task
  • When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems BOP Performs EOP-1A actions as directed by SRO:
  • Verifies needed auto actions.
  • Isolations
  • Dispatches area operator to monitor DGs Critical Task
  • Starts and verifies injection of SLC trains 'A' and 'B'.
  • Reports SLC B failure to start.
  • Terminates and prevents injection systems CPS 4411.02 Critical Task 1. HPCS
2. RCIC
3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. B RO may have to give LPCS-5 valve a close signal to complete the T/P.
4. LPCI Stabilizes RPV pressure below 1065 psig NOTES:

11

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 4 of 5 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-1A and EOP actions as entry conditions are met:

1. Inhibit ADS
2. Arm and depress MANUAL SCRAM push-buttons
3. Initiate ARI Critical Task 5. Determines Power to be greater than 5% and Directs injection of SLC
6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion
7. Verifies needed auto actions.
  • Isolations
  • DG Start Critical Task
8. Terminate and prevent injection of Detail F1 CPS 4411.02 Critical Task 9. When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems
10. Enters EOP-6 for High Drywell Temperature
11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identified parameters below (within) specified values.
  • On transient, positions himself as command authority on the unit.
  • Acknowledges immediate operator actions and directs subsequent actions.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

NOTES:

12

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 5 of 5 Time Position Applicants Actions or Behavior RO Performs EOP-3 actions as directed by SRO Critical Task

  • Termination and prevention of injection of all F1 systems
1. CB/FW At less then 138 psig:

Critical Task

  • Re-feed to level band OF -60 to TAF BOP Performs EOP-3 actions as directed by SRO Critical Task
  • termination and prevention of injection of all F1 systems
1. LPCS
2. LPCI Critical Task
  • initiation of ADS and verify 7 ADS valves open SRO Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas 4 Critical Tasks
  • Directs termination and prevention of injection of all F1 systems
  • Directs initiation of ADS and verify 7 ADS valves open
  • Directs Re-feed at 138 psig
  • Directs level band at -60 to -TAF Terminus:
  • Rod Insert commenced
  • RPV level lowered
  • Level restored and stabilized
  • Upon approval of lead examiner NOTES:

13

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).
3. Load the lesson plan for this scenario.
4. Place simulator in RUN.
5. Select the FWLC level instrument B.
6. Turn on and advance recorders.
7. Verify Load set is at 600 MWe.
8. Verify the AR/PR server is running and stabilize AR/PR.
9. Verify Rod Drive pressure at 250#.
10. Identify T/S issues associated with OOS and turnover.
11. Verify simulator conditions match the turnover.
12. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26
13. Provide marked up CPS 3004.01 complete to step 8.3.10.
14. Fill out plant status sheet and have Turnover sheet ready for crew.

14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event Triggers and Role Play Event #

1. Main EHC pump swap
a. No trigger - to start
b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal
c. Remote trigger 10 - When requested to test auto start feature
d. The Pump will shutoff when stopped with the control room switch.
2. Pull rods to raise power
a. No triggers
b. RE -Xenon is at equilibrium. Gang is permissible, but continuos drive is NOT authorized
3. Rod drifts outward.
a. Remote trigger 1 - on request from lead evaluator.
b. No problem lights at the RGDC or RACCs
c. Role Play - Field operator reports no indications of problem at the HCU.
d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.
e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed
4. HPCS WLP shaft shears
a. Remote trigger 2 - on request from lead evaluator
b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.
c. If ATM is checked it is reading 0 psig.
d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.
e. If called - Respond as maintenance to investigate.
f. If requested by CRS, RCIC is operable by administrative means.

NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.

5. CB pump A clogged oil filter/bearing oil deficiency
a. Remote trigger 3 - on request from lead evaluator
b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75°F)

More Event Triggers and Role Play on the next page 15

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I

6. B CCW pump Trip
a. Remote trigger 4 on request from lead evaluator
b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.
c. Role play as maintenance personnel in the field if requested.
7. SSE level control failure
a. Remote trigger 5 - on request from lead evaluator
b. Role play as field operator no indications locally that would explain failure.
c. Controller is set at 0 inches, but level control valve is shut.
d. May take up to (2) minutes for alarm to come in. (This is normal.)
8. RPV Instrument line failure in the secondary containment
a. Remote trigger 6 on request from lead evaluator
b. When the XL3 printout is requested provide attachment 1
c. Role play as personnel in the field (1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.
9. Auto and Manual scram failure
a. Triggers - already active
b. Perform Pending actions when requested
c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)
10. RT-1 and RT-4 fail to shut on SLC initiation
a. Triggers - already active 16

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1

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

61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM 61-19 AB-781 East Col 121-124 AC ALARM 61-20 AB-781 East Col 121-124 AC ALARM 17

Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)

1. EOP-1
2. EOP-1A
3. EOP-8
4. EOP-3
5. EOP-6
6. 3105.02 EHC
7. ITS/ORM/ODCM
8. 3004.01 TG S/U and Sync
9. 4007.02 O/N
10. 3309.01 HPCS
11. 3104.01 CD/CB
12. 4100.01 O/N
13. 4001.01 O/N
14. 4411.08 ARI
15. 4411.02 T/P
16. SLC hard card
17. T/P hard card (2)
18. 3203.01 CCW
19. 3107.01 GS
20. 3304.02 RCIS
21. 4411.104410.00 C012
22. 4411.09
23. 4410.00 C003
24. 4410.00 C004
25. 4411.03
26. 4411.04
27. 4411.11
28. 4411.02
29. 3101.01
30. HU-AA-1211
31. OP-AB-300-1001
32. Annuciators:
  • 5006-4G, 5D, 3H, 1H, 3D
  • 5062-7D, 8E, 7B
  • 5019-3A
  • 5001-1H
  • 5040-1B, 8D
  • 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H
  • 5017-3A
  • 5130-1G ,2G
  • 5003-3D, 3K
  • 5002-2P, 1Q
  • 5004-3A, 3F
  • 5009-5B
  • 5063-7H
  • 5065-6F
  • 5140 AR/PR
  • All alarms after the Scram

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: CPs B,C,D,E and F are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: _32.4_ mlb/hr FCV Position: A: __90___% B: __90__%

Reactor Power _27_% (<=100%) _919_ MWt (<=3473) _244_ Mwe Xenon: Stable RPV Level _29_ in Narrow Range RPV Pressure _929_ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.5_ psi (0 to 1 psig)

Drywell to Containment dp: _0.5_ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _103_ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _28.7_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _34.4_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _84_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _85.4_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station: Clinton Valid Date(s): xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Roger Bottom / xx/xx/xx Reviewed by: Joe QNE / xx/xx/xx Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ xx/xx/xx Authorized by: / xx/xx/xx RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / xx/xx/xx NF Reviewer / Date ReMA Activated: / xx/xx/xx ReMA Terminated: / xx/xx/xx Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for raising reactor power to support upshift of the RR Pumps.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power increase

1. Withdraw control rods to achieve conditions to support RR Upshift
2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr) 3.

4.

General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 1 of 2 Reactivity Maneuver Plan # C11-Simu.3 Description of Step :

Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed.

Perform control rod pulls in accordance with approved sequence.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.

QNE presence required in the Control Room? Yes X No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR N/A N/A Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 57.3 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 2 of 2 Reactivity Maneuver Plan # C11-Simu.3 Description of Step :

Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.

Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.

Note: It is possible that performing a pump upshift will cause the plant to enter into the CONTROLLED ENTRY REGION of the power / flow operating map. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable.

QNE presence required in the Control Room? Yes X* No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR < 0.900 Core Flow (Mlb/hr or %) N/A N/A MFLPD < 0.900 FCL (%) < 57.3% MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0 10 20 30 40 50 60 70 80 90 100 110 3473 100 MELLLA Limit [100.7% FCL]

3126 90 Restricted 90% FCL (Typ.)

2778 Zone 80%

80 THERMAL POWER - MWTh 2431 70 PERCENT THERMAL POWER 2084 60 60%

CON T R OLLE D 1737 50 E N T R Y R E GION 50%

1389 40 40%

1042 30 868 25 695 20 OPRM ENABLED CAVITATION 347 REGION PROTECTION LINES 10 OPRM OPERABLE

[21.6 % CTP, 750 MWth] SINGLE LOOP [> 25% CTP AND (HIGH SPEED, 2 PUMP ENVELOPE < 60% FLOW] OPERATION) 0 0 0.0 8.5 16.9 25.4 33.8 42.3 50.7 59.2 67.6 76.1 84.5 93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Two Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

27% power RR Pumps on LFMG, Pulling rods to 30% power for Recirculation pump upshift.

Thunderstorms are expected in the area within the next hour.

Turnover:

1. Shift Main EHC pump to support maintenance - First Priority.
2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.

Malf. No. Event Event Type* Description 1 NA N-BOP Main EHC pump swap.

2 NA R-ATC Pull rods to raise power.

3 4025I_Acti C-ATC Rod drifts outward.

on3ROD16 49I_ACTIO TS-CRS N3 1 4 HP01HP_1 C-BOP HPCS WLP Shaft shears.

E22C003_

MTFSHEA TS-CRS R1 5 YAFWPPL C-ATC A CB pump clogged oil filter/bearing oil deficiency.

B_5 30.000 6 YP_XMFT C-BOP Trip of B CCW pump. delete B_3918 1 7 YAMSAVF I-BOP SSE level control failure.

P_15 0.0 8 YP_XMFT M-ALL RPV Instrument line failure in the secondary containment.

B_5082 1 9 YP_XMFT M-ALL Auto and Manual scram failure.

B_4963 1 10 YP_XMFT M-ALL One SLC Pump fails to start B_5107 _1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Two Operating Test No.: 08-01 Narrative Summary Event # Description

1. Swap the running Main EHC pumps, the A Main EHC pump will be started and the B Main EHC pump shutdown.
2. Allow rod withdrawal to raise power.
3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.
4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1 and B.2.
5. A CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the A pump.
6. Trip of B CCW pump. Start up A CCW pump.
7. SSE level control fails causing level to go low requiring the manual level control to restore level on the SSE.
8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.
9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to shutdown the reactor.
10. When SLC is started the B SLC pump fails to start.

EOPS 8,1A,3 Critical tasks:

  • Terminate and Prevent Injection prior to emergency depressurization
  • Initiate emergency depressurization once two Max Safe temperatures are exceeded.
  • Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.

Page 2 of 2

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level) 27% Power A-2, step 27 is complete, 16-33 at 26 944 MWt 252 MWe 32.4 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed.

RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized Existing LCOs, date of next surveillance Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.

Online Safety is Green In 3004.01 complete thru step 8.3.10 Shift Main EHC pump to support Carrying electrical load in accordance maintenance - First Priority. with the Power Team.

1

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Main EHC running pump swap.

Initiation: Following turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3105.02, EHC, STEP 8.1.2.1:

  • Startup the standby pump (A)
  • Wait for at least thirty seconds
  • Shutdown the running pump (B) 5017-3A may or may not alarm.
  • Test the standby pump (B)

The standby pump is started by a local operation and then stopped in the control room.

RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: Main EHC pumps shifted NOTES:

2

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Pull rods to raise power Initiation: Following Main EHC pump shift.

Cues: Directed by SRO Time Position Applicants Actions or Behavior Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-RO CL-721 series:

  • Withdraw rods to raise power to 30%

Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO
  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Clearly observable plant response from change in power level.

NOTES:

3

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time Position Applicants Actions or Behavior RO Per Inadvertent Rod Movement, CPS 4007.02:

Immediate actions

  • Select and fully insert the moving rod with the In Timer Skip button Subsequent actions;
  • Once fully inserted release the In Timer Skip button
  • Observe rod withdrawal
  • Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled:

Monitor for core instabilities BOP

  • Dispatch a field operator to the HCU for the rod
  • Directs field operator to Individually scram rod
  • Evaluates thermal limits
  • Evaluate MSL rad monitor values
  • Evaluates OG Rad levels SRO
  • Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02
  • Contacts Shift Manager and recommends notifications.

Terminus: Once rod is fully inserted, individually scrammed and Tech Specs referenced.

NOTES:

4

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time Position Applicants Actions or Behavior BOP Per ARP Procedure CPS 5062-7D:

  • Dispatches NLO to investigate.

o If ATM is checked for pressure it reads 0 psig When directed:

  • Shutdown the HPCS WLP Pump.

Per HPCS CPS 3309.01 precaution 4.3:

  • Dispatches NLO to remove HPCS control power fuses.

5062-7B will alarm.

RO

  • Monitors reactor to ensure operations remain within established bands.
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Contacts Shift Manager and recommends notifications.

Terminus: HPCS control power fuses removed and Technical Specifications evaluated.

NOTES:

If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.

5

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

CB pump A clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.

Cues: Annunciator CPS 5001-1H alarming, Time Position Applicants Actions or Behavior RO CPS 5001-1H, Clogged Oil Filter CB 1A:

Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2:

  • Startup standby CB pump
  • Shutdown A CB pump BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Standby CB pump started and shutdown the A CB pump.

NOTES:

6

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 6 Pa g e 1 of 1

==

Description:==

Trip of B CCW pump Initiation: After shifting of CB pumps, on the signal of lead examiner Cues: Annunciator CPS 5040-1B alarming, Time Position Applicants Actions or Behavior RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies notifies the SRO of any unusual or unexpected conditions.
  • Responds to annunciator 5003-5003-3D and 3E, RR Low Cooling Water Flow.

BOP

  • Starts standby pump per ARP (O/A 2.a).
  • Monitors control room panels panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Directs starting of A CCW pump.
  • Directs RO to monitor RR and RT Temps.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Standby CCW pump started.

NOTES:

7

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time Position Applicants Actions or Behavior BOP Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2:

  • Determines level to be low.
  • Direct field operator to investigate.
  • Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2.

Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.

RO

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: SSE level restored and alarm clear NOTES:

May take up to (2) minutes for alarm to come in. (This is normal.)

8

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Operator Actions Event No.(s): 8,9,10 Page 1 of 5

Description:

RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time Position Applicants Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO

  • Place mode switch in Shutdown
  • Check and report power unchanged
  • Operate FW to control level 3 to 8
  • Check rods, reports shutdown criteria is not met
  • Report level and pressure are following expected trends
  • Stabilize pressure <1065 psig
  • Coordinates with BOP operator to monitor and control RPV level and press BOP
  • Makes plant announcement for reactor scram
  • Should make plant announcement to evacuate Fuel/Aux buildings.

Performs EOP actions as directed by SRO

  • Verifies operation of area coolers
  • Verifies operation of VF, Fuel Bldg Vent.
  • Monitors area temperatures, levels and radiation levels Critical Task
  • Coordinates with RO to monitor and control RPV level and press NOTES:

9

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 2 of 5 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF
2. Operate area coolers
3. Hold floor drain sump levels below max. normal
4. Isolate all discharges into the affected area except systems needed for:
  • Fire Fighting
5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage:
  • Directs BOP to isolate the source of leakage
6. Direct a scram prior to exceeding Maximum safe temperature
7. Enters EOP-1 Directs additional actions:
1. Notification of Radiation Protection (RP) Department
2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:
1. Mode Switch to SHUTDOWN
  • Per EOP-1 enters EOP-1A Critical Task Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas NOTES:

10

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 3 of 5 Time Position Applicants Actions or Behavior RO Performs EOP actions as directed by SRO:

  • Directs defeating RPC for further rod insertion
  • Verifies RR downshifts at Level 3, and trips at Level 2.

Critical Task

  • Terminates and prevents injection CB/FW systems CPS 4411.02 Critical Task
  • When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems BOP Performs EOP-1A actions as directed by SRO:
  • Verifies needed auto actions.
  • Isolations
  • Dispatches area operator to monitor DGs Critical Task
  • Starts and verifies injection of SLC trains 'A' and 'B'.
  • Reports SLC B failure to start.
  • Terminates and prevents injection systems CPS 4411.02 Critical Task 1. HPCS
2. RCIC
3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. B RO may have to give LPCS-5 valve a close signal to complete the T/P.
4. LPCI Stabilizes RPV pressure below 1065 psig NOTES:

11

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 4 of 5 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-1A and EOP actions as entry conditions are met:

1. Inhibit ADS
2. Arm and depress MANUAL SCRAM push-buttons
3. Initiate ARI Critical Task 5. Determines Power to be greater than 5% and Directs injection of SLC
6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion
7. Verifies needed auto actions.
  • Isolations
  • DG Start Critical Task
8. Terminate and prevent injection of Detail F1 CPS 4411.02 Critical Task 9. When RPV level reaches -60, control RPV water level between TAF and -60 using only the listed Preferred ATWS Systems
10. Enters EOP-6 for High Drywell Temperature
11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identified parameters below (within) specified values.
  • On transient, positions himself as command authority on the unit.
  • Acknowledges immediate operator actions and directs subsequent actions.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

NOTES:

12

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event No.(s): 8,9,10 Page 5 of 5 Time Position Applicants Actions or Behavior RO Performs EOP-3 actions as directed by SRO Critical Task

  • Termination and prevention of injection of all F1 systems
1. CB/FW At less then 138 psig:

Critical Task

  • Re-feed to level band OF -60 to TAF BOP Performs EOP-3 actions as directed by SRO Critical Task
  • termination and prevention of injection of all F1 systems
1. LPCS
2. LPCI Critical Task
  • initiation of ADS and verify 7 ADS valves open SRO Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas 4 Critical Tasks
  • Directs termination and prevention of injection of all F1 systems
  • Directs initiation of ADS and verify 7 ADS valves open
  • Directs Re-feed at 138 psig
  • Directs level band at -60 to -TAF Terminus:
  • Rod Insert commenced
  • RPV level lowered
  • Level restored and stabilized
  • Upon approval of lead examiner NOTES:

13

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).
3. Load the lesson plan for this scenario.
4. Place simulator in RUN.
5. Select the FWLC level instrument B.
6. Turn on and advance recorders.
7. Verify Load set is at 600 MWe.
8. Verify the AR/PR server is running and stabilize AR/PR.
9. Verify Rod Drive pressure at 250#.
10. Identify T/S issues associated with OOS and turnover.
11. Verify simulator conditions match the turnover.
12. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26
13. Provide marked up CPS 3004.01 complete to step 8.3.10.
14. Fill out plant status sheet and have Turnover sheet ready for crew.

14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I Event Triggers and Role Play Event #

1. Main EHC pump swap
a. No trigger - to start
b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal
c. Remote trigger 10 - When requested to test auto start feature
d. The Pump will shutoff when stopped with the control room switch.
2. Pull rods to raise power
a. No triggers
b. RE -Xenon is at equilibrium. Gang is permissible, but continuos drive is NOT authorized
3. Rod drifts outward.
a. Remote trigger 1 - on request from lead evaluator.
b. No problem lights at the RGDC or RACCs
c. Role Play - Field operator reports no indications of problem at the HCU.
d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.
e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed
4. HPCS WLP shaft shears
a. Remote trigger 2 - on request from lead evaluator
b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.
c. If ATM is checked it is reading 0 psig.
d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.
e. If called - Respond as maintenance to investigate.
f. If requested by CRS, RCIC is operable by administrative means.

NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.

5. CB pump A clogged oil filter/bearing oil deficiency
a. Remote trigger 3 - on request from lead evaluator
b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75°F)

More Event Triggers and Role Play on the next page 15

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I

6. B CCW pump Trip
a. Remote trigger 4 on request from lead evaluator
b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.
c. Role play as maintenance personnel in the field if requested.
7. SSE level control failure
a. Remote trigger 5 - on request from lead evaluator
b. Role play as field operator no indications locally that would explain failure.
c. Controller is set at 0 inches, but level control valve is shut.
d. May take up to (2) minutes for alarm to come in. (This is normal.)
8. RPV Instrument line failure in the secondary containment
a. Remote trigger 6 on request from lead evaluator
b. When the XL3 printout is requested provide attachment 1
c. Role play as personnel in the field (1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.
9. Auto and Manual scram failure
a. Triggers - already active
b. Perform Pending actions when requested
c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)
10. RT-1 and RT-4 fail to shut on SLC initiation
a. Triggers - already active 16

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01I TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1

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

61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM 61-19 AB-781 East Col 121-124 AC ALARM 61-20 AB-781 East Col 121-124 AC ALARM 17

Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)

1. EOP-1
2. EOP-1A
3. EOP-8
4. EOP-3
5. EOP-6
6. 3105.02 EHC
7. ITS/ORM/ODCM
8. 3004.01 TG S/U and Sync
9. 4007.02 O/N
10. 3309.01 HPCS
11. 3104.01 CD/CB
12. 4100.01 O/N
13. 4001.01 O/N
14. 4411.08 ARI
15. 4411.02 T/P
16. SLC hard card
17. T/P hard card (2)
18. 3203.01 CCW
19. 3107.01 GS
20. 3304.02 RCIS
21. 4411.104410.00 C012
22. 4411.09
23. 4410.00 C003
24. 4410.00 C004
25. 4411.03
26. 4411.04
27. 4411.11
28. 4411.02
29. 3101.01
30. HU-AA-1211
31. OP-AB-300-1001
32. Annuciators:
  • 5006-4G, 5D, 3H, 1H, 3D
  • 5062-7D, 8E, 7B
  • 5019-3A
  • 5001-1H
  • 5040-1B, 8D
  • 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H
  • 5017-3A
  • 5130-1G ,2G
  • 5003-3D, 3K
  • 5002-2P, 1Q
  • 5004-3A, 3F
  • 5009-5B
  • 5063-7H
  • 5065-6F
  • 5140 AR/PR
  • All alarms after the Scram

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: __26.9___ mlb/hr FCV Position: A: ___90____% B: _ _90____%

Reactor Power __0__% (<=100%) _0__ MWt (<=3473) _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi (< 1045)

In service SDC loop None MODE 2 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.4__ psi (0 to 1 psig)

Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _78_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

OP-AB-300-1003 Revision 3 Page 26 of 39 Attachment 1 Reactivity Maneuver Approval Cover Page Station: Clinton Valid Date(s): 2/2-2/15/08 Reactivity Maneuver Plan #: C12-0001 Are Multiple Activations Allowed: No (If yes, US may make additional copies)

Prepared by: ______________/______ Reviewed by: ________________/_______

Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: _____________/_______ Authorized by: ___________________/______

RE Manager / Date Senior Reactor Operator / Date NF Review (circle one) yes/declined by ________________/______

NF Individual Contacted/Date ReMA Activated: ______________/_______ ReMA Terminated: ______________/______

Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: BOC 12 Plant Startup Purpose/Overview of Evolution:

This ReMA provides the steps for starting up the reactor from C1R11 refueling outage. The ReMA covers power ascension from All Rods In (ARI) to ~96.9% CTP (~3365 MWth).

Maneuver Steps

1. Withdraw rods from ARI to ~29% CTP.
2. Shift RR pumps to fast speed & increase core flow to ~65% (~54.9 Mlbm/hr)
3. Increase reactor power to ~96.9% CTP (~3365 MWth).
4. Maintain power at ~96.9% CTP (~3365 MWth) with rods & flow General Issues:

The plan is to pull control rods until the target rod pattern is achieved. However, since this will be a xenon free startup, all rods cannot be fully withdrawn to their target positions during the power ascension. Also fuel conditioning limits will require a slow flow ramp (0.35 kw/ft/hr; ~30 MWe/hr) to reach rated power. A second downpower will be required (separate ReMA) to achieve the target rod pattern.

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA procedure OP-AB-300-1003.

Main Steam Line Radiation Monitors may initially show elevated response from crud burst in the core (due to rod movements) and from hydrogen pockets being swept into the core (due to flow perturbations in the condensate/

feedwater piping). Response should diminish as the feedwater system comes to equilibrium.

Turbine Control Valve (TCV) oscillations have been experienced at ~87% (~3021 MWth). It may be necessary to flow quickly through this region to avoid excessive valve oscillations.

OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 1 of 4 Reactivity Maneuver Plan # C12-0001 Description of Step:

Withdraw rods from ARI to ~29% CTP.

Initial Complete a) Withdraw control rods in accordance with Startup Sequence A2-01 to ~29%(~1007 MWth) to support RR pump shift to fast speed.

b) Verify scram time testing is complete before shifting RR pumps to fast speed. A separate control rod sequence package will be provided for this testing.

Note: Prior to exceeding 21.6% power verify feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWth). Reference App. A of CPS 3102.01.

The Reactor Engineer will provide guidance on adjustments to the rod pattern or flow to accommodate predictor uncertainties or schedule changes.

QNE presence required in the Control Room? Yes X No Onsite Only? Yes No Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Generator Output N/A N/A MFLCPR N/A N/A Core Power (MWt or %) N/A N/A MFLPD N/A N/A Core Flow (Mlb/hr or %) N/A N/A MAPRAT N/A N/A FCL (%) N/A N/A Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High Low contingency actions (if needed)

FCL Monitor frequency : Demand 3D case after crossing 21.6% (750 MWth) &

just prior to RR pump shift to fast speed. Power and flow indications on the 57.3% N/A P680 displays may also be used.

(Contingency: Insert control rods to reduce FCL.)

ReMA Step Complete: _________________/______ Verified by: _______________/_______

Reactor Operator/Date Unit Supervisor/Date

OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 2 of 4 Reactivity Maneuver Plan # C12-0001 Description of Step:

Shift RR pumps to fast speed & increase core flow to ~65% (~54.9 Mlbm/hr)

Initial Complete a) Shift RR pumps to fast speed. During upshifts of RR pumps there is a potential for entry in to the Controlled Entry Region. This has been evaluated and is acceptable.

b) Increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support minimizing throttling of FCVs and as necessary to support plant systems. At the completion of this step reactor power will be ~40-45% (~1389-1563 MWth).

Reactor Engineer to provide guidance on adjustments to rod pattern or flow to accommodate predictor uncertainties and schedule changes.

QNE presence required in the Control Room? Yes X No Onsite Only? Yes No Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Generator Output N/A N/A MFLCPR < 0.900 Core Power (MWt or %) N/A N/A MFLPD < 0.750 Core Flow (Mlb/hr or %) N/A N/A MAPRAT N/A N/A FCL (%) < 57.3%

Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High Low contingency actions (if needed)

NONE ReMA Step Complete: _________________/______ Verified by: _______________/_______

Reactor Operator/Date Unit Supervisor/Date

OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 3 of 4 Reactivity Maneuver Plan # C12-0001 Description of Step:

Increase power to ~96.9% CTP (~3365 MWth) with flow and rods. Power may be increased in increments as necessary to support plant evolutions. Flow adjustments may be used to maintain power approximately constant for any hold points.

Note:

At ~80% power, bundle nodal powers of exposed fuel are expected to reach the threshold of ~8.5kw/ft. In accordance with NF-AB-440, a fuel conditional ramp rate of 0.35kw/ft/hr will be required. RE will provide guidance on fuel conditioning ramp.

The intent is to withdraw as many rods as possible. However, xenon conditions and fuel conditioning requirements will not permit withdrawal of the control rods to desired target positions. Reactor Engineer will provide guidance on control rod movements and flow increases.

Reactor Engineer to provide guidance on adjustments to rod pattern or flow to accommodate predictor uncertainties and schedule changes.

QNE presence required in the Control Room? Yes X* No Onsite Only? Yes No

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Generator Output N/A N/A MFLCPR < 0.900 Core Power (MWt or %) N/A N/A MFLPD < 0.900

~65% N/A N/A Core Flow (Mlb/hr or %) MAPRAT

(~54.9 Mlbm/hr)

FCL (%) N/A N/A Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High Low contingency actions (if needed)

FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after each 50 MWe increase in electrical output.

98.7% N/A Contingency: Insert control rods as recommended by the Reactor Engineer.

MFLCPR Monitor Frequency: 3D case at each 50 MWe increase in electrical output when MFLCPR > 0.900. 0.980 N/A Contingency: Refer to CPS 2202.03 for correction of power distribution problems.

OP-AB-300-1003 Revision 3 Page 27 of 39 MFLPD Monitor Frequency: 3D case at each 50 MWe reduction in electrical output when MFLPD > 0.900. 0.980 N/A Contingency: Refer to CPS 2202.03 for correction of power distribution problems.

Fuel Conditioning Limits Approach to Monitor Frequency: threshold:

1. Approach to threshold (when PCRAT > 0.900) - use 3D cases (PCIOMR P-Max (PC,KWTH) edits) at ~5% increase in power; = 0.45
2. Fuel conditioning ramp rate (when P-Max (PC,KWTH) > 0.0) - Use 3D cases (PCIOMR edits) at ~30 minute intervals. Fuel Conditioning Ramp Rate:

0.45 kw/ft/hr (Contingency: Refer to NF-AB-440 for actions to take if fuel conditioning limits (nominal ramp rate are exceeded.) is 0.35 kw/ft/hr)

ReMA Step Complete: _________________/______ Verified by: _______________/_______

Reactor Operator/Date Unit Supervisor/Date

OP-AB-300-1003 Revision 3 Page 27 of 39 Attachment 2 Reactivity Maneuver Guidance Sheet Step 4 of 4 Reactivity Maneuver Plan # C12-0001 Description of Step:

Maintain power with flow adjustments and control rod notching. Xenon will be building in Reactor Engineer will provide guidance to ensure margins are maintained. This will continue until the next down power to achieve target rod pattern (~24 hours later). A separate ReMA will be provided for this downpower.

Note: The FCL critical parameter has been specified at 99.7%, which is within 1.0% of the 100.7% limit. The reduced margin is being specified to accommodate the xenon transient.

QNE presence required in the Control Room? Yes X* No Onsite Only? Yes No

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Generator Output N/A N/A MFLCPR < 0.980

~ 96.9%

Core Power (MWt or %) MFLPD < 0.980

(~3365 MWth)

Core Flow (Mlb/hr or %) N/A N/A MAPRAT N/A N/A FCL (%) < 98.7%

Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High Low contingency actions (if needed)

FCL Monitor Frequency: Normal monitoring 99.7%

Contingency: Insert control rods in reverse order of sequence as determined by Reactor Engineer.

MFLCPR Monitor Frequency: Normal monitoring 0.980 Contingency: Refer to CPS 2202.03 for correction of power distribution problems.

MFLPD Monitor Frequency: Normal monitoring 0.980 Contingency: Refer to CPS 2202.03 for correction of power distribution problems.

ReMA Step Complete: _________________/______ Verified by: _______________/_______

Reactor Operator/Date Unit Supervisor/Date

FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP PERCENT CORE FLOW 0 10 20 30 40 50 60 70 80 90 100 110 3473 100 MELLLA Limit [100.7% FCL]

3126 90 Restricted 90% FCL (Typ.)

2778 Zone 80%

80 THERMAL POWER - MWTh 2431 70 PERCENT THERMAL POWER 2084 60 60%

CONTROLLED 1737 50 ENTRY REGION 50%

1389 40 40%

1042 30 868 25 695 20 OPRM ENABLED CAVITATION 347 OPRM OPERABLE REGION PROTECTION LINES 10

[21.6 % CTP, 750 MWth] SINGLE LOOP [> 25% CTP AND (HIGH SPEED, 2 PUMP ENVELOPE < 60% FLOW] OPERATION) 0 0 0.0 8.5 16.9 25.4 33.8 42.3 50.7 59.2 67.6 76.1 84.5 93.0 90.4 CORE FLOW - mlbm/hr (use core plate dP when Single Loop)

ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton Valid Date(s): XX/XX/XXXX Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Roger QNE / XX/XX/XX Reviewed by: Joe QNE / XX/XX/XX Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ XX/XX/XX Authorized by: / XX/XX/XX RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / XX/XX/XX NF Reviewer / Date ReMA Activated: / XX/XX/XX ReMA Terminated: / XX/XX/XX Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction

1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

ATTACHMENT 2 Reactivity Maneuver Guidance Sheet

STEP 1 of 1 Reactivity Maneuver Plan # C11-Simu.4 Description of Step :

From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.

QNE presence required in the Control Room? Yes

  • No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR N/A N/A Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 57.3 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:

  • This form was updated as a result of the procedure revision.

ROUTINE USE ORIGINATOR: Christian Small CLASS CODE: SNNN1 SQR: Mark Vandermyde APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages n

o p

q r

Rev. 4 Page 1 of 2

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:

Estimated Date/Time of criticality /

Xenon Increasing Decreasing

None Moderator Temperature: 468 °F Cycle Exposure: 9000 MWD/T Sequence: A2 - Simulator Comments: Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps 17 and 35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.

For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.

Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17 or after step 35 , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.

Instructions

  • Expect the reactor to become critical at any time.
  • Monitor nuclear instruments during and following rod movements.
  • If a nontransient period of less than 30 sec occurs, insert rods and investigate.
  • Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____

___25____ ___26____ ___27____ ___28____

___29____ ___31____ ___33____ ___35____

ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.

Michelle QNE Boss /

Reactor Engineer Date Time Rev. 4 Page 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Three Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.

Thunderstorm storms are expected in the area within the next hour.

Turnover:

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
2. Pull Rods to criticality.

Event Malf. No. Event Event No. Type* Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump 2 Rod C-ATC Continue with startup, discovers Uncoupled rod 0825I_ACTIONA

-Rod uncoupled TS-CRS 3 NA R-ATC Pull rods for criticality 4 SRM_BI_ACTIO I-ATC B SRM fails N2 and 1 5 CDSR_VAC_P I-BOP Vacuum Pump Trip MP_A 6 SRM_CI_ACTIO TS-CRS A SRM fails N2 and 1 7 Override C-BOP RCIC drain trap level high 8 YARITPLA_1 M-ALL RCIC unisolable steam leak Override 9 YP_XMFTB_500 M-ALL Reactor scrams on initiation of RPT/ARI 2

10 CAM1PR006AT M-ALL Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Three Operating Test No.: 08-01 Narrative Summary Event # Description

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
3. Withdrawal rods for criticality.
4. B SRM fails causing a rod block requiring bypassing to proceed with startup.

Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a

5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.

EOP 8,1A,1 Critical tasks:

  • Manual insertion of ARI prior to exceeding Maximum safe temperature
  • Manually shutdown and isolate VF and startup VG Page 2 of 2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level)

Subcritical, with equilibrium Xenon, 3 days CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.

Comments, evolutions, problems, etc.

Online Safety is Green Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by

- First Priority.

the electrode boiler Continue with Reactor startup.

1

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.

Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:

  • Depress Gen H2 Emerg Seal Oil Pump Test push-button
  • Verify Gen H2 Emergency Seal Oil Pump starts
  • Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
  • Stop the Gen H2 Emergency Seal Oil Pump
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Emergency Seal Oil Pump test complete NOTES:

2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 2 Page 1 of 1

Description:

Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicants Actions or Behavior RO CPS 5006-5G, Rod Overtravel:

  • Determine the rod that alarmed 08-25.
1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
3) Determine if the rod has recoupled by performing a coupling check
4) If the rod has recoupled, return to normal operation.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • When the rod is recoupled declare the rod Operable and exit the LCOs
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:

3

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 3 Page 1 of 1

==

Description:==

Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO Sequence:

  • Withdraw rods for criticality
  • Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
  • Depress the POWER ON button
  • Depress the drive out button until withdrawn
  • Depress the drive out button
  • Announce reactor is critical BOP
  • Announce reactor criticality
  • Log in the date/time criticality was achieved, and criticality data:
  • Rod Sequence
  • Group/Array
  • Rod
  • Rod Position
  • SRM reading and Period
  • RR loop temperature
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above
  • Stays in a position of oversite
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

Terminus: Clearly observable plant response from change in power level or Reactor is critical.

NOTES:

4

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
  • Place the SRM Bypass joy stick to B SRM
  • Observe the rod block clears BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Directs Bypassing SRM B and continue with the startup
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B SRM has been bypassed IAW CPS 3306.01.

NOTES:

If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.

5

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time Position Applicants Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum

  • Dispatches field operator to perform local actions to start B Vacuum Pump
  • After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Enters CPS 4004.02 Loss of Vacuum
  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B Vacuum Pump is in operation NOTES:

6

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Monitors reactor to ensure operations remain within established bands BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: ITS actions reviewed and entered NOTES:

TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.

7

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicants Actions or Behavior BOP Per CPS 5063-2C, RCIC Steam Drain Trap Level High:

  • Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
  • Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
  • Reports failure RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.

NOTES:

8

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 8,9 Page 1 of 2

==

Description:==

RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicants Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO

  • Place mode switch in Shutdown, check and report power unchanged
  • Operate FW to control level 3 to 8
  • Check rods, reports shutdown criteria is met
  • Report level and pressure are following expected trends
  • Stabilize pressure <1065 psig
  • Coordinates with BOP operator to monitor and control RPV level and press.

BOP

  • Makes plant announcement for reactor scram
  • Should make plant announcement to evacuate Fuel/Aux buildings.
  • Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
  • Verifies operation of area coolers
  • Verifies operation of VF
  • Monitors area temperatures, levels and radiation levels
  • Coordinates with RO to monitor and control RPV level and press NOTES:

9

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 8,9 Page 2 of 2 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF
2. Operate area coolers
3. Hold floor drain sump levels below max. normal
4. Isolate all discharges into the affected area except systems needed for:
  • Fire Fighting
5. Per EOP-8/CPS 4001.02:
  • Directs BOP to isolate RCIC steam lines Critical Task 6. Direct a scram prior to exceeding Maximum safe temperature
7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
8. Directs additional actions:
  • Notification of Radiation Protection (RP) Department
9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
a. Mode Switch to SHUTDOWN
b. Shutdown criteria verified
c. Control RPV Water Level between Level 3 and Level 8
d. Stabilize RPV pressure below 1065 psig
e. Verify needed automatic actions:
  • Isolations
  • DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:

10

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 10 Page 1 of 1

Description:

Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicants Actions or Behavior BOP Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:

  • Report EOP-8 entry condition Critical Task
  • Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
  • Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs entry into EOP-8 and EOP actions as entry conditions are met.

Critical Task

  • When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
  • Startup VG CPS 3319.01, Standby Gas General:
  • On transient, positions himself as command authority on the unit.
  • Acknowledges immediate operator actions and directs subsequent actions.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus:

  • RPV level stable and under control in required band
  • Reactor is Scrammed
  • Effort has been made to isolate RCIC steam lines
  • Failed automatic isolation and actuation (VF/VG) manually performed
  • Upon approval of lead examiner NOTES:

11

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
3. Load the lesson plan for this scenario
4. Place simulator in RUN
5. Select the B FWLC level instrument
6. Turn on and advance recorders
7. Reset SRM A drawer
8. Provide pull sheets: on step 25 rod 08-25 is at 12
9. Provide and ECP and RE instructions
10. Verify the AR/PR server is running and stabilize AR/PR
11. Verify TT alarm is reset
12. Verify Rod Drive pressure at 250#
13. Hang OOS tags per turnover on #2 SAC
14. Identify T/S issues associated with OOS and turnover
15. Verify simulator conditions match the turnover
16. Provide marked up CPS 3001.01 complete to step 8.2.5
17. Provide a marked up CPS 3002.01 complete to step 8.6
18. Provide a marked up CPS 9000.06D001 with stable heatup values
19. Fill out plant status and have Turnover Sheet ready for the crew
20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event Triggers and Role Play Event #

1. Test the Generator Emergency Seal Oil Pump
a. No trigger.
2. Uncoupled rod
a. Remote trigger 1 to remove the uncoupled malfunction once the rod is inserted to recouple
b. Role Play - Shift Manager - I will have WCS initiate AR/CR and take care of notifications. Proceed with pull to critical.
3. Withdraw Rods To criticality
a. No triggers
4. B SRM fails
a. Remote trigger 2 on request from lead evaluator
b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
5. Vacuum Pump trip
a. Remote trigger 3 on request from lead evaluator
b. Role Play- Field operator
6. A SRM fails
a. Remote trigger 4 on request from lead evaluator
b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
7. RCIC drain trap level high
a. Remote trigger 5 on request from lead evaluator
b. Role play - Field operator that the trap is lined up
8. RCIC unisolable steam leak
a. Remote trigger 6 on request from lead evaluator
b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
c. Role play as personnel in the field (1) Heavy steam in RCIC room
d. If valve breakers are checked, no problems are found.
9. Reactor scrams on initiation of RPT/ARI
a. No triggers
b. After 2 minutes from scram announcement go to MCR as IMD.
10. Radiation monitor fails to initiate an isolation and start up VG.
a. No triggers
b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.

13

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: __26.9___ mlb/hr FCV Position: A: ___90____% B: _ _90____%

Reactor Power __0__% (<=100%) _0__ MWt (<=3473) _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi (< 1045)

In service SDC loop None MODE 2 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.4__ psi (0 to 1 psig)

Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _78_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton Valid Date(s): XX/XX/XXXX Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Roger QNE / XX/XX/XX Reviewed by: Joe QNE / XX/XX/XX Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ XX/XX/XX Authorized by: / XX/XX/XX RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / XX/XX/XX NF Reviewer / Date ReMA Activated: / XX/XX/XX ReMA Terminated: / XX/XX/XX Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction

1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

ATTACHMENT 2 Reactivity Maneuver Guidance Sheet

STEP 1 of 1 Reactivity Maneuver Plan # C11-Simu.4 Description of Step :

From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.

QNE presence required in the Control Room? Yes

  • No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR N/A N/A Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 57.3 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:

  • This form was updated as a result of the procedure revision.

ROUTINE USE ORIGINATOR: Christian Small CLASS CODE: SNNN1 SQR: Mark Vandermyde APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages n

o p

q r

Rev. 4 Page 1 of 2

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:

Estimated Date/Time of criticality /

Xenon Increasing Decreasing

None Moderator Temperature: 468 °F Cycle Exposure: 9000 MWD/T Sequence: A2 - Simulator Comments: Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps 17 and 35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.

For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.

Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17 or after step 35 , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.

Instructions

  • Expect the reactor to become critical at any time.
  • Monitor nuclear instruments during and following rod movements.
  • If a nontransient period of less than 30 sec occurs, insert rods and investigate.
  • Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____

___25____ ___26____ ___27____ ___28____

___29____ ___31____ ___33____ ___35____

ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.

Michelle QNE Boss /

Reactor Engineer Date Time Rev. 4 Page 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Three Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.

Thunderstorm storms are expected in the area within the next hour.

Turnover:

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
2. Pull Rods to criticality.

Event Malf. No. Event Event No. Type* Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump 2 Rod C-ATC Continue with startup, discovers Uncoupled rod 0825I_ACTIONA

-Rod uncoupled TS-CRS 3 NA R-ATC Pull rods for criticality 4 SRM_BI_ACTIO I-ATC B SRM fails N2 and 1 5 CDSR_VAC_P I-BOP Vacuum Pump Trip MP_A 6 SRM_CI_ACTIO TS-CRS A SRM fails delete N2 and 1 7 Override C-BOP RCIC drain trap level high 8 YARITPLA_1 M-ALL RCIC unisolable steam leak Override 9 YP_XMFTB_500 M-ALL Reactor scrams on initiation of RPT/ARI 2

10 CAM1PR006AT M-ALL Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Three Operating Test No.: 08-01 Narrative Summary Event # Description

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
3. Withdrawal rods for criticality.
4. B SRM fails causing a rod block requiring bypassing to proceed with startup.

Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a

5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.

EOP 8,1A,1 Critical tasks:

  • Manual insertion of ARI prior to exceeding Maximum safe temperature
  • Manually shutdown and isolate VF and startup VG Page 2 of 2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level)

Subcritical, with equilibrium Xenon, 3 days CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.

Comments, evolutions, problems, etc.

Online Safety is Green Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by

- First Priority.

the electrode boiler Continue with Reactor startup.

1

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.

Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:

  • Depress Gen H2 Emerg Seal Oil Pump Test push-button
  • Verify Gen H2 Emergency Seal Oil Pump starts
  • Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
  • Stop the Gen H2 Emergency Seal Oil Pump
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Emergency Seal Oil Pump test complete NOTES:

2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 2 Page 1 of 1

Description:

Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicants Actions or Behavior RO CPS 5006-5G, Rod Overtravel:

  • Determine the rod that alarmed 08-25.
1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
3) Determine if the rod has recoupled by performing a coupling check
4) If the rod has recoupled, return to normal operation.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • When the rod is recoupled declare the rod Operable and exit the LCOs
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:

3

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 3 Page 1 of 1

==

Description:==

Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO Sequence:

  • Withdraw rods for criticality
  • Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
  • Depress the POWER ON button
  • Depress the drive out button until withdrawn
  • Depress the drive out button
  • Announce reactor is critical BOP
  • Announce reactor criticality
  • Log in the date/time criticality was achieved, and criticality data:
  • Rod Sequence
  • Group/Array
  • Rod
  • Rod Position
  • SRM reading and Period
  • RR loop temperature
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above
  • Stays in a position of oversite
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

Terminus: Clearly observable plant response from change in power level or Reactor is critical.

NOTES:

4

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
  • Place the SRM Bypass joy stick to B SRM
  • Observe the rod block clears BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Directs Bypassing SRM B and continue with the startup
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B SRM has been bypassed IAW CPS 3306.01.

NOTES:

If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.

5

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time Position Applicants Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum

  • Dispatches field operator to perform local actions to start B Vacuum Pump
  • After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Enters CPS 4004.02 Loss of Vacuum
  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B Vacuum Pump is in operation NOTES:

6

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Monitors reactor to ensure operations remain within established bands BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: ITS actions reviewed and entered NOTES:

TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.

7

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicants Actions or Behavior BOP Per CPS 5063-2C, RCIC Steam Drain Trap Level High:

  • Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
  • Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
  • Reports failure RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.

NOTES:

8

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 8,9 Page 1 of 2

==

Description:==

RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicants Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO

  • Place mode switch in Shutdown, check and report power unchanged
  • Operate FW to control level 3 to 8
  • Check rods, reports shutdown criteria is met
  • Report level and pressure are following expected trends
  • Stabilize pressure <1065 psig
  • Coordinates with BOP operator to monitor and control RPV level and press.

BOP

  • Makes plant announcement for reactor scram
  • Should make plant announcement to evacuate Fuel/Aux buildings.
  • Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
  • Verifies operation of area coolers
  • Verifies operation of VF
  • Monitors area temperatures, levels and radiation levels
  • Coordinates with RO to monitor and control RPV level and press NOTES:

9

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 8,9 Page 2 of 2 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF
2. Operate area coolers
3. Hold floor drain sump levels below max. normal
4. Isolate all discharges into the affected area except systems needed for:
  • Fire Fighting
5. Per EOP-8/CPS 4001.02:
  • Directs BOP to isolate RCIC steam lines Critical Task 6. Direct a scram prior to exceeding Maximum safe temperature
7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
8. Directs additional actions:
  • Notification of Radiation Protection (RP) Department
9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
a. Mode Switch to SHUTDOWN
b. Shutdown criteria verified
c. Control RPV Water Level between Level 3 and Level 8
d. Stabilize RPV pressure below 1065 psig
e. Verify needed automatic actions:
  • Isolations
  • DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:

10

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 10 Page 1 of 1

Description:

Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicants Actions or Behavior BOP Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:

  • Report EOP-8 entry condition Critical Task
  • Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
  • Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs entry into EOP-8 and EOP actions as entry conditions are met.

Critical Task

  • When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
  • Startup VG CPS 3319.01, Standby Gas General:
  • On transient, positions himself as command authority on the unit.
  • Acknowledges immediate operator actions and directs subsequent actions.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus:

  • RPV level stable and under control in required band
  • Reactor is Scrammed
  • Effort has been made to isolate RCIC steam lines
  • Failed automatic isolation and actuation (VF/VG) manually performed
  • Upon approval of lead examiner NOTES:

11

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
3. Load the lesson plan for this scenario
4. Place simulator in RUN
5. Select the B FWLC level instrument
6. Turn on and advance recorders
7. Reset SRM A drawer
8. Provide pull sheets: on step 25 rod 08-25 is at 12
9. Provide and ECP and RE instructions
10. Verify the AR/PR server is running and stabilize AR/PR
11. Verify TT alarm is reset
12. Verify Rod Drive pressure at 250#
13. Hang OOS tags per turnover on #2 SAC
14. Identify T/S issues associated with OOS and turnover
15. Verify simulator conditions match the turnover
16. Provide marked up CPS 3001.01 complete to step 8.2.5
17. Provide a marked up CPS 3002.01 complete to step 8.6
18. Provide a marked up CPS 9000.06D001 with stable heatup values
19. Fill out plant status and have Turnover Sheet ready for the crew
20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event Triggers and Role Play Event #

1. Test the Generator Emergency Seal Oil Pump
a. No trigger.
2. Uncoupled rod
a. Remote trigger 1 to remove the uncoupled malfunction once the rod is inserted to recouple
b. Role Play - Shift Manager - I will have WCS initiate AR/CR and take care of notifications. Proceed with pull to critical.
3. Withdraw Rods To criticality
a. No triggers
4. B SRM fails
a. Remote trigger 2 on request from lead evaluator
b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
5. Vacuum Pump trip
a. Remote trigger 3 on request from lead evaluator
b. Role Play- Field operator
6. A SRM fails
a. Remote trigger 4 on request from lead evaluator
b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
7. RCIC drain trap level high
a. Remote trigger 5 on request from lead evaluator
b. Role play - Field operator that the trap is lined up
8. RCIC unisolable steam leak
a. Remote trigger 6 on request from lead evaluator
b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
c. Role play as personnel in the field (1) Heavy steam in RCIC room
d. If valve breakers are checked, no problems are found.
9. Reactor scrams on initiation of RPT/ARI
a. No triggers
b. After 2 minutes from scram announcement go to MCR as IMD.
10. Radiation monitor fails to initiate an isolation and start up VG.
a. No triggers
b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.

13

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: __26.9___ mlb/hr FCV Position: A: ___90____% B: _ _90____%

Reactor Power __0__% (<=100%) _0__ MWt (<=3473) _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi (< 1045)

In service SDC loop None MODE 2 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.4__ psi (0 to 1 psig)

Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _78_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton Valid Date(s): XX/XX/XXXX Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Roger QNE / XX/XX/XX Reviewed by: Joe QNE / XX/XX/XX Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ XX/XX/XX Authorized by: / XX/XX/XX RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / XX/XX/XX NF Reviewer / Date ReMA Activated: / XX/XX/XX ReMA Terminated: / XX/XX/XX Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction

1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

ATTACHMENT 2 Reactivity Maneuver Guidance Sheet

STEP 1 of 1 Reactivity Maneuver Plan # C11-Simu.4 Description of Step :

From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.

QNE presence required in the Control Room? Yes

  • No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR N/A N/A Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 57.3 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:

  • This form was updated as a result of the procedure revision.

ROUTINE USE ORIGINATOR: Christian Small CLASS CODE: SNNN1 SQR: Mark Vandermyde APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages n

o p

q r

Rev. 4 Page 1 of 2

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:

Estimated Date/Time of criticality /

Xenon Increasing Decreasing

None Moderator Temperature: 468 °F Cycle Exposure: 9000 MWD/T Sequence: A2 - Simulator Comments: Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps 17 and 35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.

For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.

Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17 or after step 35 , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.

Instructions

  • Expect the reactor to become critical at any time.
  • Monitor nuclear instruments during and following rod movements.
  • If a nontransient period of less than 30 sec occurs, insert rods and investigate.
  • Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____

___25____ ___26____ ___27____ ___28____

___29____ ___31____ ___33____ ___35____

ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.

Michelle QNE Boss /

Reactor Engineer Date Time Rev. 4 Page 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Three Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.

Thunderstorm storms are expected in the area within the next hour.

Turnover:

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
2. Pull Rods to criticality.

Event Malf. No. Event Event No. Type* Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump delete 2 Rod C-ATC Continue with startup, discovers Uncoupled rod 0825I_ACTIONA

-Rod uncoupled TS-CRS 3 4 NA R-ATC Pull rods for criticality 4 3 SRM_BI_ACTIO I-ATC B SRM fails N2 and 1 5 CDSR_VAC_P I-BOP Vacuum Pump Trip delete MP_A 6 SRM_CI_ACTIO TS-CRS A SRM fails N2 and 1 7 Override C-BOP RCIC drain trap level high delete 8 YARITPLA_1 M-ALL RCIC unisolable steam leak Override 9 YP_XMFTB_500 M-ALL Reactor scrams on initiation of RPT/ARI 2

10 CAM1PR006AT M-ALL Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Three Operating Test No.: 08-01 Narrative Summary Event # Description

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
3. Withdrawal rods for criticality.
4. B SRM fails causing a rod block requiring bypassing to proceed with startup.

Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a

5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.

EOP 8,1A,1 Critical tasks:

  • Manual insertion of ARI prior to exceeding Maximum safe temperature
  • Manually shutdown and isolate VF and startup VG Page 2 of 2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level)

Subcritical, with equilibrium Xenon, 3 days CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.

Comments, evolutions, problems, etc.

Online Safety is Green Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by

- First Priority.

the electrode boiler Continue with Reactor startup.

1

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.

Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:

  • Depress Gen H2 Emerg Seal Oil Pump Test push-button
  • Verify Gen H2 Emergency Seal Oil Pump starts
  • Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
  • Stop the Gen H2 Emergency Seal Oil Pump
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Emergency Seal Oil Pump test complete NOTES:

2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 2 Page 1 of 1

Description:

Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicants Actions or Behavior RO CPS 5006-5G, Rod Overtravel:

  • Determine the rod that alarmed 08-25.
1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
3) Determine if the rod has recoupled by performing a coupling check
4) If the rod has recoupled, return to normal operation.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • When the rod is recoupled declare the rod Operable and exit the LCOs
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:

3

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 3 4 Page 1 of 1

==

Description:==

Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO Sequence:

  • Withdraw rods for criticality
  • Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
  • Depress the POWER ON button
  • Depress the drive out button until withdrawn
  • Depress the drive out button
  • Announce reactor is critical BOP
  • Announce reactor criticality
  • Log in the date/time criticality was achieved, and criticality data:
  • Rod Sequence
  • Group/Array
  • Rod
  • Rod Position
  • SRM reading and Period
  • RR loop temperature
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above
  • Stays in a position of oversite
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

Terminus: Clearly observable plant response from change in power level or Reactor is critical.

NOTES:

4

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 4 3 Page 1 of 1

==

Description:==

B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
  • Place the SRM Bypass joy stick to B SRM
  • Observe the rod block clears BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Directs Bypassing SRM B and continue with the startup
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B SRM has been bypassed IAW CPS 3306.01.

NOTES:

If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.

5

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time Position Applicants Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum

  • Dispatches field operator to perform local actions to start B Vacuum Pump
  • After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Enters CPS 4004.02 Loss of Vacuum
  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B Vacuum Pump is in operation NOTES:

6

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Monitors reactor to ensure operations remain within established bands BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: ITS actions reviewed and entered NOTES:

TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.

7

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicants Actions or Behavior BOP Per CPS 5063-2C, RCIC Steam Drain Trap Level High:

  • Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
  • Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
  • Reports failure RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.

NOTES:

8

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 8,9 Page 1 of 2

==

Description:==

RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicants Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO

  • Place mode switch in Shutdown, check and report power unchanged
  • Operate FW to control level 3 to 8
  • Check rods, reports shutdown criteria is met
  • Report level and pressure are following expected trends
  • Stabilize pressure <1065 psig
  • Coordinates with BOP operator to monitor and control RPV level and press.

BOP

  • Makes plant announcement for reactor scram
  • Should make plant announcement to evacuate Fuel/Aux buildings.
  • Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
  • Verifies operation of area coolers
  • Verifies operation of VF
  • Monitors area temperatures, levels and radiation levels
  • Coordinates with RO to monitor and control RPV level and press NOTES:

9

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 8,9 Page 2 of 2 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF
2. Operate area coolers
3. Hold floor drain sump levels below max. normal
4. Isolate all discharges into the affected area except systems needed for:
  • Fire Fighting
5. Per EOP-8/CPS 4001.02:
  • Directs BOP to isolate RCIC steam lines Critical Task 6. Direct a scram prior to exceeding Maximum safe temperature
7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
8. Directs additional actions:
  • Notification of Radiation Protection (RP) Department
9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
a. Mode Switch to SHUTDOWN
b. Shutdown criteria verified
c. Control RPV Water Level between Level 3 and Level 8
d. Stabilize RPV pressure below 1065 psig
e. Verify needed automatic actions:
  • Isolations
  • DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:

10

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 10 Page 1 of 1

Description:

Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicants Actions or Behavior BOP Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:

  • Report EOP-8 entry condition Critical Task
  • Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
  • Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs entry into EOP-8 and EOP actions as entry conditions are met.

Critical Task

  • When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
  • Startup VG CPS 3319.01, Standby Gas General:
  • On transient, positions himself as command authority on the unit.
  • Acknowledges immediate operator actions and directs subsequent actions.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus:

  • RPV level stable and under control in required band
  • Reactor is Scrammed
  • Effort has been made to isolate RCIC steam lines
  • Failed automatic isolation and actuation (VF/VG) manually performed
  • Upon approval of lead examiner NOTES:

11

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
3. Load the lesson plan for this scenario
4. Place simulator in RUN
5. Select the B FWLC level instrument
6. Turn on and advance recorders
7. Reset SRM A drawer
8. Provide pull sheets: on step 25 rod 08-25 is at 12
9. Provide and ECP and RE instructions
10. Verify the AR/PR server is running and stabilize AR/PR
11. Verify TT alarm is reset
12. Verify Rod Drive pressure at 250#
13. Hang OOS tags per turnover on #2 SAC
14. Identify T/S issues associated with OOS and turnover
15. Verify simulator conditions match the turnover
16. Provide marked up CPS 3001.01 complete to step 8.2.5
17. Provide a marked up CPS 3002.01 complete to step 8.6
18. Provide a marked up CPS 9000.06D001 with stable heatup values
19. Fill out plant status and have Turnover Sheet ready for the crew
20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event Triggers and Role Play Event #

1. Test the Generator Emergency Seal Oil Pump
a. No trigger.
2. Uncoupled rod
a. Remote trigger 1 to remove the uncoupled malfunction once the rod is inserted to recouple
b. Role Play - Shift Manager - I will have WCS initiate AR/CR and take care of notifications. Proceed with pull to critical.
3. Withdraw Rods To criticality
a. No triggers
4. B SRM fails
a. Remote trigger 2 on request from lead evaluator
b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
5. Vacuum Pump trip
a. Remote trigger 3 on request from lead evaluator
b. Role Play- Field operator
6. A SRM fails
a. Remote trigger 4 on request from lead evaluator
b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
7. RCIC drain trap level high
a. Remote trigger 5 on request from lead evaluator
b. Role play - Field operator that the trap is lined up
8. RCIC unisolable steam leak
a. Remote trigger 6 on request from lead evaluator
b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
c. Role play as personnel in the field (1) Heavy steam in RCIC room
d. If valve breakers are checked, no problems are found.
9. Reactor scrams on initiation of RPT/ARI
a. No triggers
b. After 2 minutes from scram announcement go to MCR as IMD.
10. Radiation monitor fails to initiate an isolation and start up VG.
a. No triggers
b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.

13

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 3 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: A,B,C CPs are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A RT F/D is in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: __26.9___ mlb/hr FCV Position: A: ___90____% B: _ _90____%

Reactor Power __0__% (<=100%) _0__ MWt (<=3473) _0__ Mwe Xenon: Stable RPV Level _26.7_ in Narrow Range RPV Pressure _600__ psi (< 1045)

In service SDC loop None MODE 2 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _19.1_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.4__ psi (0 to 1 psig)

Drywell to Containment dp: _0.4__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _100__ F (<=146.53 F)

Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _12.8_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _78_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _0_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: None Comments: See Turnover Sheet From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 2 Station: Clinton Valid Date(s): XX/XX/XXXX Reactivity Maneuver Plan #: C11-Simu.4 Multiple Activations Allowed? No (If yes, CRS may make additional copies)

Prepared by: Roger QNE / XX/XX/XX Reviewed by: Joe QNE / XX/XX/XX Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ XX/XX/XX Authorized by: / XX/XX/XX RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / XX/XX/XX NF Reviewer / Date ReMA Activated: / XX/XX/XX ReMA Terminated: / XX/XX/XX Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: Withdraw Rods from ARI to RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for starting up the plant from the ARI condition to the performance of RR pump upshift.

Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction

1. Withdraw control rods from ARI to RR pump shift to fast speed General Issues:

The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003.

ATTACHMENT 2 Reactivity Maneuver Guidance Sheet

STEP 1 of 1 Reactivity Maneuver Plan # C11-Simu.4 Description of Step :

From the ARI condition, increase power with control rods to ~29% (1007 MWt) to support RR pump shift to fast speed.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01.

QNE presence required in the Control Room? Yes

  • No *

Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.

Core Power (MWth or %) N/A N/A MFLCPR N/A N/A Core Flow (Mlb/hr or %) N/A N/A MFLPD N/A N/A FCL (%) N/A N/A MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed) High Low FCL 57.3 % N/A Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift.

Contingency: Insert control rods in reverse order sequence to reduce FCL.

Step Complete: ___________________/_______ Verified by: _________________/_______

Reactor Operator / Date Unit Supervisor / Date

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY SCOPE OF REVISION:

  • This form was updated as a result of the procedure revision.

ROUTINE USE ORIGINATOR: Christian Small CLASS CODE: SNNN1 SQR: Mark Vandermyde APPROVAL DATE: 04/25/05 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages n

o p

q r

Rev. 4 Page 1 of 2

CPS 2202.04F001 REACTOR OPERATOR INSTRUCTIONS FOR CRITICALITY Steps 8.3, 8.4, 8.7.4 Core Conditions Expected:

Estimated Date/Time of criticality /

Xenon Increasing Decreasing

None Moderator Temperature: 468 °F Cycle Exposure: 9000 MWD/T Sequence: A2 - Simulator Comments: Minimum Xenon conditions, High Moderator Temperature; Middle of Cycle Startup Estimated Critical Position Criticality is estimated to occur between steps 17 and 35 BOC Criticality Instructions For BOC, if criticality is reached prior to step ________, insert rods in reverse order up to and including step _______ and investigate with the Reactor Engineer and Nuclear Fuels.

For BOC, if criticality is not reached at the completion of step ________, insert rods in reverse order, up to and including step ________ and investigate with the Reactor Engineer and Nuclear Fuels.

Non-BOC Criticality Instructions For non-BOC, if criticality is reached either prior to step 17 or after step 35 , continue with the reactor startup and initiate a CR to document and trend the ECP being outside the expected range of criticality.

Instructions

  • Expect the reactor to become critical at any time.
  • Monitor nuclear instruments during and following rod movements.
  • If a nontransient period of less than 30 sec occurs, insert rods and investigate.
  • Perform 1/M plots at steps ___17____ ___19____ ___22____ ___23____

___25____ ___26____ ___27____ ___28____

___29____ ___31____ ___33____ ___35____

ADDITIONAL INSTRUCTIONS This is a middle of cycle, xenon-free startup at relatively high moderator temperature. Watch for potential high notch worths in interior regions of the core.

Michelle QNE Boss /

Reactor Engineer Date Time Rev. 4 Page 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Three Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Subcritical ~600 psig, Steam seals and Auxiliary Steam is provided by the electrode boiler, hot restart.

Thunderstorm storms are expected in the area within the next hour.

Turnover:

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 - First Priority.
2. Pull Rods to criticality.

Event Malf. No. Event Event No. Type* Description 1 NA N-BOP Test the Generator Emergency Seal Oil Pump delete 2 Rod C-ATC Continue with startup, discovers Uncoupled rod 0825I_ACTIONA

-Rod uncoupled TS-CRS 3 4 NA R-ATC Pull rods for criticality 4 3 SRM_BI_ACTIO I-ATC B SRM fails N2 and 1 5 CDSR_VAC_P I-BOP Vacuum Pump Trip MP_A 6 SRM_CI_ACTIO TS-CRS A SRM fails N2 and 1 7 Override C-BOP RCIC drain trap level high 8 YARITPLA_1 M-ALL RCIC unisolable steam leak Override 9 YP_XMFTB_500 M-ALL Reactor scrams on initiation of RPT/ARI 2

10 CAM1PR006AT M-ALL Radiation monitor fails to initiate an isolation V_VALUE1 CAM1PR006CT V_VALUE1 CAM1PR006DT V_VALUE1 CAM1PR006BT V_VALUE1 VGCEFUSE_V 677503CC VGBZFUSE_V 421691CC

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Three Operating Test No.: 08-01 Narrative Summary Event # Description

1. Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3.
2. Rod 08-25 is uncoupled and goes to overtravel. This will require action to recouple and entry into Technical Specification 3.1.3.
3. Withdrawal rods for criticality.
4. B SRM fails causing a rod block requiring bypassing to proceed with startup.

Requiring a review of Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a

5. The A Mechanical Vacuum Pump trips requiring starting the B Pump.
6. A SRM fails causing a rod block and requiring entry into Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a
7. The RCIC drain trap level high will require manually opening the drain trap bypass valve to drain the steam pot.
8. The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior exceeding the Maximum safe temperature.
9. The mode switch and manual scram pushbutton will not cause a scram requiring entry into EOP-1A. Manual initiation of ARI/RPT will insert the rods for a scram. EOP-1A will be exited and EOP-1 will be entered.
10. The VF exhaust radiation monitor trends up to the trip isolation but fails to actuate VF isolation and start of VG requiring BOP to manually perform.

EOP 8,1A,1 Critical tasks:

  • Manual insertion of ARI prior to exceeding Maximum safe temperature
  • Manually shutdown and isolate VF and startup VG Page 2 of 2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level)

Subcritical, with equilibrium Xenon, 3 days CPS 3001.01 complete to step 8.2.5 after shutdown na- MWt CPS 3002.01 at step 8.5.2 na- MWe 27.0 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Pull to critical, heatup and pressurization, step 25 on the pull sheet, 08-25 @ 12 Existing LCOs, date of next surveillance None Surveillances or major maintenance Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT.

Comments, evolutions, problems, etc.

Online Safety is Green Test the Generator Emergency Seal Oil Pump per 3109.01 section 8.1.2.3 for PMT Steam seals and Auxiliary Steam is provided by

- First Priority.

the electrode boiler Continue with Reactor startup.

1

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Test the Generator Emergency Seal Oil Pump per 3109.01 for PMT.

Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicants Actions or Behavior BOP Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3:

  • Depress Gen H2 Emerg Seal Oil Pump Test push-button
  • Verify Gen H2 Emergency Seal Oil Pump starts
  • Verify annunciators 5017 (6A6 and 5B5), computer point and local operation are OK
  • Stop the Gen H2 Emergency Seal Oil Pump
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Emergency Seal Oil Pump test complete NOTES:

2

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 2 Page 1 of 1

Description:

Uncoupled rod Initiation: Following Emergency Seal Oil Pump test Cues: Annunciator CPS 5006-5G alarms Time Position Applicants Actions or Behavior RO CPS 5006-5G, Rod Overtravel:

  • Determine the rod that alarmed 08-25.
1) Verify that the INDIVID DRIVE light is energized on the OCM. If not, select individual drive by depressing DRIVE MODE push-button.
2) Insert the drive 1 or 2 notches in an attempt to recouple the rod.
3) Determine if the rod has recoupled by performing a coupling check
4) If the rod has recoupled, return to normal operation.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • When the rod is recoupled declare the rod Operable and exit the LCOs
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: Rod has been recoupled and SRO applied LCO actions NOTES:

3

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 3 4 Page 1 of 1

==

Description:==

Pull rods for criticality Initiation: When directed by SRO after Rod has been recoupled Cues: Directed by SRO Time Position Applicants Actions or Behavior Per CPS 3001.01, Approach To Critical, Step 8.2.6 and CPS 2202.01F001, Control Rod RO Sequence:

  • Withdraw rods for criticality
  • Prior to exceeding 1 x 106 cps, withdraw SRMs Per CPS 3306.01, SRM/IRM step 8.1.2:
  • Depress the POWER ON button
  • Depress the drive out button until withdrawn
  • Depress the drive out button
  • Announce reactor is critical BOP
  • Announce reactor criticality
  • Log in the date/time criticality was achieved, and criticality data:
  • Rod Sequence
  • Group/Array
  • Rod
  • Rod Position
  • SRM reading and Period
  • RR loop temperature
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above
  • Stays in a position of oversite
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

Terminus: Clearly observable plant response from change in power level or Reactor is critical.

NOTES:

4

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 4 3 Page 1 of 1

==

Description:==

B SRM fails Initiation: After the rod is recoupled or on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Bypass the failed SRM Per CPS 3306.01, SRM/IRM step 8.2.2:
  • Place the SRM Bypass joy stick to B SRM
  • Observe the rod block clears BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Directs Bypassing SRM B and continue with the startup
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B SRM has been bypassed IAW CPS 3306.01.

NOTES:

If the B RO appears about to perform the operation to bypass the B SRM, the Lead Evaluator should signal for event # 5 to be started to draw the B RO away from P-680.

5

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Vacuum Pump trips Initiation: After crew has addressed SRM problem, on the signal of lead examiner Cues: Annunciator CPS 5019-1A alarming Time Position Applicants Actions or Behavior BOP Per CPS 3112.01, Condenser Vacuum

  • Dispatches field operator to perform local actions to start B Vacuum Pump
  • After at least 5 minutes of seal water pump operation, start the B Vacuum Pump RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Enters CPS 4004.02 Loss of Vacuum
  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: B Vacuum Pump is in operation NOTES:

6

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

A SRM fails Initiation: After B Vacuum Pump is running, on the signal of lead examiner Cues: Annunciators CPS 5006-2H & 5005-1K, 2K, & 3K alarm Time Position Applicants Actions or Behavior RO Per CPS 5006-2H, SRM Inop:

  • Monitors reactor to ensure operations remain within established bands BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Reviews and enters TS 3.3.1.2 Action A.1 and ORM 2.2.2 Action 3.2.2.a.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus: ITS actions reviewed and entered NOTES:

TO LEAD EVALUATOR: Ensure this event is started before IRMs are on Range 2 to ensure a Tech Spec call can be made.

7

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

RCIC drain trap level high Initiation: After ITS actions reviewed and entered, on the signal of lead examiner Cues: Annunciator 5063-2C alarming Time Position Applicants Actions or Behavior BOP Per CPS 5063-2C, RCIC Steam Drain Trap Level High:

  • Recognizes failure of 1E51-F054, RCIC Turbine Inlet Steam Line Water Drain Pot Trap Bypass to open and opens the valve manually.
  • Verifies 1E51-F025 and 1E51-F026, Upstream and Downstream RCIC Turbine Inlet Steam Line Water Drain Pot Normal Drains are open
  • Reports failure RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Drain Pot level alarm clear, SRO has directed actions accordingly.

NOTES:

8

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 8,9 Page 1 of 2

==

Description:==

RCIC unisolable steam leak, Reactor scrams on initiation of RPT/ARI Initiation: After RCIC drain trap level high problem has been addressed, on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, rods fail to insert upon manual/automatic SCRAM Time Position Applicants Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO

  • Place mode switch in Shutdown, check and report power unchanged
  • Operate FW to control level 3 to 8
  • Check rods, reports shutdown criteria is met
  • Report level and pressure are following expected trends
  • Stabilize pressure <1065 psig
  • Coordinates with BOP operator to monitor and control RPV level and press.

BOP

  • Makes plant announcement for reactor scram
  • Should make plant announcement to evacuate Fuel/Aux buildings.
  • Attempts to close RCIC steam isolation valves from the control room Performs EOP actions as directed by SRO
  • Verifies operation of area coolers
  • Verifies operation of VF
  • Monitors area temperatures, levels and radiation levels
  • Coordinates with RO to monitor and control RPV level and press NOTES:

9

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event No.(s): 8,9 Page 2 of 2 Time Position Applicants Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF
2. Operate area coolers
3. Hold floor drain sump levels below max. normal
4. Isolate all discharges into the affected area except systems needed for:
  • Fire Fighting
5. Per EOP-8/CPS 4001.02:
  • Directs BOP to isolate RCIC steam lines Critical Task 6. Direct a scram prior to exceeding Maximum safe temperature
7. Directs entry into EOP-1A and EOP actions as entry conditions are met.:
8. Directs additional actions:
  • Notification of Radiation Protection (RP) Department
9. Enters and Directs and verifies performance of appropriate actions per EOP-1:
a. Mode Switch to SHUTDOWN
b. Shutdown criteria verified
c. Control RPV Water Level between Level 3 and Level 8
d. Stabilize RPV pressure below 1065 psig
e. Verify needed automatic actions:
  • Isolations
  • DG Start Terminus: RCIC isolation is attempted and Reactor is scrammed NOTES:

10

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Operator Actions Event No.(s): 10 Page 1 of 1

Description:

Radiation monitor fails to initiate an isolation Initiation: Following the steam leak into the secondary containment Cues: Annunciator 5050-7F, 5052-7F and AR/PR 1RIX-PR006A-D monitors alarms Time Position Applicants Actions or Behavior BOP Performs EOP actions as directed by SRO, CPS 5050-7F, 5052-7F, Hi Rad Initiation VG:

  • Report EOP-8 entry condition Critical Task
  • Shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation, step 8.3 Critical Task
  • Startup VG CPS 3319.01, Standby Gas, step 8.2.1 RO
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs entry into EOP-8 and EOP actions as entry conditions are met.

Critical Task

  • When fuel build exhaust is above 10 mrem/hr shutdown and isolate VF CPS 3404.01, Fuel Building Ventilation Critical Task
  • Startup VG CPS 3319.01, Standby Gas General:
  • On transient, positions himself as command authority on the unit.
  • Acknowledges immediate operator actions and directs subsequent actions.
  • Enforces OPS expectations and standards.
  • Contacts Shift Manager and recommends notifications.

Terminus:

  • RPV level stable and under control in required band
  • Reactor is Scrammed
  • Effort has been made to isolate RCIC steam lines
  • Failed automatic isolation and actuation (VF/VG) manually performed
  • Upon approval of lead examiner NOTES:

11

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to an IC with Pressure at 600 psig and rods and/or flow to match turnover
3. Load the lesson plan for this scenario
4. Place simulator in RUN
5. Select the B FWLC level instrument
6. Turn on and advance recorders
7. Reset SRM A drawer
8. Provide pull sheets: on step 25 rod 08-25 is at 12
9. Provide and ECP and RE instructions
10. Verify the AR/PR server is running and stabilize AR/PR
11. Verify TT alarm is reset
12. Verify Rod Drive pressure at 250#
13. Hang OOS tags per turnover on #2 SAC
14. Identify T/S issues associated with OOS and turnover
15. Verify simulator conditions match the turnover
16. Provide marked up CPS 3001.01 complete to step 8.2.5
17. Provide a marked up CPS 3002.01 complete to step 8.6
18. Provide a marked up CPS 9000.06D001 with stable heatup values
19. Fill out plant status and have Turnover Sheet ready for the crew
20. Provide pull sheets, REMA, Re instructions and Cram Instructions 12

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 08/24/09 08-01 Event Triggers and Role Play Event #

1. Test the Generator Emergency Seal Oil Pump
a. No trigger.
2. Uncoupled rod
a. Remote trigger 1 to remove the uncoupled malfunction once the rod is inserted to recouple
b. Role Play - Shift Manager - I will have WCS initiate AR/CR and take care of notifications. Proceed with pull to critical.
3. Withdraw Rods To criticality
a. No triggers
4. B SRM fails
a. Remote trigger 2 on request from lead evaluator
b. If SRM B drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
5. Vacuum Pump trip
a. Remote trigger 3 on request from lead evaluator
b. Role Play- Field operator
6. A SRM fails
a. Remote trigger 4 on request from lead evaluator
b. If SRM A drawer is checked report the reading at the drawer for period and scale are going up and down, trip and INOP lights are ON
c. Maintenance will need a work package to determine the extent of the problem with the SRM.
7. RCIC drain trap level high
a. Remote trigger 5 on request from lead evaluator
b. Role play - Field operator that the trap is lined up
8. RCIC unisolable steam leak
a. Remote trigger 6 on request from lead evaluator
b. If RCIC ATMs are checked they read 10 times higher than on the last 9000.01 reading.
c. Role play as personnel in the field (1) Heavy steam in RCIC room
d. If valve breakers are checked, no problems are found.
9. Reactor scrams on initiation of RPT/ARI
a. No triggers
b. After 2 minutes from scram announcement go to MCR as IMD.
10. Radiation monitor fails to initiate an isolation and start up VG.
a. No triggers
b. Remote trigger 7 after 3 minutes, when requested to S/D VF locally. Then report VF S/D locally.

13

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 4 REVISION 00 DEVELOPER: Tom Pickley REVIEWED BY:

Simulator Instructor APPROVED BY: /

Operations Date

Overview Makeup/Reject: All CPs except J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Yellow Reactor Operational Condition: Mode 1 Total Core Flow: _84.2 mlb/hr FCV Position: A: __86.6__% B: __87.3 _%

Reactor Power _95.8_% (<=100%) _3321_ MWt (<=3473) _1089_ Mwe Xenon: Stable RPV Level _35__ in Narrow Range RPV Pressure _1020_ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _75.5_ F (<=93.1 F)

Suppression Pool Level _ 19.2 ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _ 0.6 _ psi (0 to 1 psig)

Drywell to Containment dp: _ 0.6 _ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _ 104_ F (<=146.53 F)

Secondary Containment: _ 0.74 in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _26.4_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _66.6_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _ 109_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _ 256 _MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: HPCS and Div 1 & 2 Backup ADS Air Supply Comments: MDRFP is CO From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

Turnover This page contains the Turnover information not found in the Overview page.

1. Power, xenon and time in life Power was reduced to 80% for surveillance testing.
2. Status of Tagged Out Equipment MDRFP is OOS for coupling replacement
3. Shift conditions Day Shift Today
4. Weather Conditions Sunny and clear.
5. Thermal Limit Problems or concerns
6. LCOs in effect
7. Surveillances in progress Perform 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test.

8.

9. Evolutions planned for the shift
10. Risk Levels Yellow
11. Other

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Four Operating Test No.: 08-01 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

96% power, steady state.

MDRFP is CO for coupling replacement.

Turnover:

  • VC running for 9070.01, Control Room Hvac Air Filter Package Operability Test Run.
  • A Reduction in power will be requestred by dispatch.
  • Perform 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Event Malf. No. Event Type* Event No. Description 1 IO C-ATC Perform SDV Vent and Drain Valve test one valve fails TS-CRS 2 None R-ATC Reduce power with flow 3 IO C-ATC A RR FCV Drifts shut 4 VC01VC_VC0 C-BOP VC Makeup Train A Outlet DMPR fails shut during surveilance run.

6YA_MTVFA TS-CRS ILSP 5 None N-BOP Shift to the B VC train.

6 F041LTVFAI C-BOP SRV 41L Fails open, closes on first attempt to close LSP 7 YPXMALSE_ M-ALL Small break LOCA requiring an Emergency Depressurization.

527 8 YP_XMFTB_ M-ALL LPCS Pump fails to start on High Drywell Pressure 4106

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 10/13/2009

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Four Operating Test No.: 08-01 Narrative Summary Event # Description

1. The ATC will perform the SDV vent and drain valve test and one of the valves will indicate intermediate requiring TS entry
2. After shift turnover the Control Room staff will receive a phone call to reduce power for grid stability concerns.
3. The A Flow control valve will continue to drift shut slowly requiring the ATC to manually lock out the RR FCV. This may require the ATC to match flows after the transient.

4, 5. The ongoing VC train surveillance will have a damper failure causing TS entry and start of the opposite VC train

6. SRV 41L will inadvertantly open this valve is NON-ADS and NON-LLS requiring the BOP to take it to off and will not be available for the B/D.
7. Small break LOCA will get the crew into EOP-1 and EOP-6 the Reactor will require a blow down on Figure N PSP.
8. Manually start LPCS EOP 1,3,6 Critical tasks:
  • Blow Down when Figure N is exceeded.

Page 2 of 2 10/13/2009

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour.

(Plant power level) 96% Power/100% FCL CPS 3005.01 thru step 8.1.19 3328 MWt A-2, step 36 is complete 1092 MWe 84.5 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Existing LCOs, date of next surveillance None Surviellances or major maintenance VC running for 9070.01, Control Room HVAC Air Filter Package Operability Test Run 4 hrs 27 min into the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> run.

9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test for position indication only. Stroke times are not needed.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment MDRFP is CO for coupling replacement.

Comments, evolutions, problems, etc.

Online Safety is Yellow 9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test for position indication only. Stroke times are not needed.

Page 1 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Perform SDV Vent and Drain Valve test one valve fails Initiation: Following turnover Cues: Shift Turnover Time Position Applicants Actions or Behavior ATC

  • Simultaneously, depress and hold both:

Scram Disch Vol Vent V, and Scram Disch Vol DR V Test SW push-buttons, When the valves indicate closed, Release the Scram Disch Vol Vent V and Scram Disch Vol DR V Test Sw push-buttons

  • Report C11-F011 did not fully open BOP
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions
  • Directs the determination of C11-F011 position locally
  • Reports C11-F011 is in an intermediate position SRO
  • Directs the above actions
  • Declares C11-F011 Inop
  • Enters Tech Spec LCO 3.1.8 A.1 Isolate the Line in 7 days.

Terminus: Tech Specs have been entered.

Page 2 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Reduce power with flow Initiation: MISO calls requesting a power reduction to 90% within 30 minutes for Grid Stability.

Cues: Directed by SRO General Note Time Position Applicants Actions or Behavior Per CPS 3005.01, Unit Power Changes, step 8.2.8.

ATC

  • Reduce power with Flow to ~90%.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs actions listed above.
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.
  • Enforces OPS expectations and standards.

Terminus: Power change complete.

Note:

  • Denotes an action that should be performed.

o Denotes an action that may be performed.

Page 3 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

A RR FCV Drifts shut Initiation: Following the power change, and upon direction of Lead Examiner.

Cues:

Time Position Applicants Actions or Behavior ATC

  • Communicates that the A RR FCV is closing.
  • Locksout the A RR FCV by shutting down the HPU o Verifies the FCV motion stops.

o ATC may need to match recirc loop flows depending on the time the RRFCV gets locked out.

BOP

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO
  • Directs actions listed above.
  • Verifies that the RR loop flows are within Tech Spec limits:

-if less than 70% rated core flow then loop mismatch is limited to 10% of rated core flow (8.45mlbm/hr)

- if greater than or equal to 70% rated core flow then loop mismatch is limited to 5%

of rated core flow (4.225 mlbm/hr)

Terminus: The A RR FCV is locked out.

Page 4 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

VC Makeup Train A Outlet DMPR fails shut during surveilance run.

Initiation: Following the Tech Spec call and upon direction from the Lead Examiner.

Cues: Annunciator 5050-5D, Low Flow Downstream 0VC09SA Time Position Applicants Actions or Behavior BOP

  • References ARP Per CPS 5050-5D Low Flow Downstream 0VC09SA.
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO

  • Directs the above actions
  • Enforces OPS expectations and standards
  • Enters Tech Spec LCO 3.7.3 A.1 Restore VC subsystem in 7 days.

Terminus: 0VC05CA is off Page 5 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Shift to the B VC train.

Initiation: N/A Cues: Annunciator 5050-5D, Low Flow Downstream 0VC09SA Time Position Applicants Actions or Behavior ATC

  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

Per 3402.01P001, CV Train Shifting BOP

  • Direct Equipment Operator to perform local operations
  • Shut Locker Room EXH Fan ISOL DMPR 0VC69Y
  • Shut Locker Room EXH Fan ISOL DMPR 0VC70Y
  • Stop Cont Rm Trn A Supply Fan 0VC03CA
  • Start Cont Rm Trn B Supply Fan 0VC03CB
  • Open Locker Room EXH Fan ISOL DMPR 0VC69Y
  • Open Locker Room EXH Fan ISOL DMPR 0VC70Y
  • Direct Chiller Startup SRO
  • Directs the above actions
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: VC Train B is running Page 6 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 6 Page 1 of 1 Description SRV 41L Fails open, closes on first attempt to close Initiation: After VC train B is running and upon direction from the Lead Examiner.

Cues: Annunciator 5067-8L, SRV Monitoring System Trouble Time Position Applicants Actions or Behavior ATC

  • Assists in determination of which SRV is open
  • Monitors reactor to ensure operations remain within established bands
  • Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

BOP

  • Sounds the Containment Evacuation alarm
  • Place the switch for SRV 41L to OPEN and then back to OFF
  • Determine the SRV 41L is shut SRO
  • Enters 4009.01, Inadvertant Opening SRV
  • Directs the above actions
  • Enforces OPS expectations and standards
  • Determines SRV 41L is not required by Tech Specs.

Terminus: SRO has determined SRV 41L is not required by Tech Specs.

Page 7 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Operator Actions Event No.(s): 7&8 Page 1 of 2

==

Description:==

Small break LOCA requiring an Emergency Depressurization and LPCS Pump fails to start on High Drywell Pressure Initiation: After SRV 41L is shut and upon direction of Lead Examiner Cues: Rising Drywell Pressure Time Position Applicants Actions or Behavior ATC

  • Places the Mode Switch in S/D
  • Carries out Scram Choreography by reporting Mode Switch in Shutdown, Power is Rod status is Reactor Power is and trend Reactor pressure is and trend Reactor level is and trend Any EOPs with entry conditions (EOP-1, 6)

Per CPS 4100.01, Reactor Scram

  • Turn Mode Switch to SHUTDOWN Verify reactor power is lowering Verify SHUTDOWN CRITERIA met
  • IF RPV level is rising with 2 feed pumps operating
  • THEN Secure 1 Feed Pump and control RPV water level Level 3 to Level 8.
  • Verify Turbine and Generator trip when required
  • Performs EOP actions as directed by SRO.

Carries out Scram Choreography by:

BOP

  • Making an Announcement Reactor Scram MDRFP may start Evacuate the RCIC room Evacuate the Containment
  • Starts Drywell Mixers, as directed.

Critical Task

o Monitors the start of the ECCS Systems on High Drywell Pressure.

  • Determines LPCS did not start and manually starts LPCS Critical Task
  • Operates ECCS Systems as needed, to control RPV Water Level, Level 3 to Level 8
  • Initiates ADS Page 8 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Event No.(s): 8&9 Page 2 of 2 Time Position Applicants Actions or Behavior SRO

  • Carries out Scram Choreography by performing an Update:

Entering EOP-1 and 6 Entering Scram Off-Normal Transient Annunciator Response is authorized Enters EOP-1, RPV Control, and directs the following:

  • Determines Mode Switch is in SHUTDOWN.
  • Determines Shutdown Criteria is met.
  • Directs control of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs.
  • Directs maintaining RPV Level, Level 3 to Level 8 by using Preferred Injection Systems.

Enters EOP-6, Primary Containment Control, and directs the following:

  • Starting Mixers Critical Task

Enters EOP-3, Emergency RPV Depressurization, when Figure N is exceeded.

Critical Task

  • Directs initiation of ADS
  • Directs opening other SRVs until 7 are open May direct the isolation of RT and/or RR.
  • Enforces OPS expectations and standards
  • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: 7 SRVs are open, level band of 3 to 8 is established and upon direction of Lead Examiner.

Critical Tasks

Page 9 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed
2. Reset to IC for this scenario (Verify/Adjust Power to 96% with flow).
3. Load lesson plan for this scenario
4. Place simulator in RUN
5. Verify the AR/PR server is running and stabilize AR/PR
6. Verify VC A is running for 9070.01
7. Verify RCIC Flow Controller is set at 620 psig.
8. Ensure the correct number of CPs are in service.
9. Make sure CRD drive water D/P is in the expected range
10. Verify correct Control Rod Move Sheets in P680 Book and the correct Cram array are used
11. Turn on and advance recorders
12. Hang OOS tags per turnover
13. Identify T/S issues associated with OOS and turnover
14. Verify simulator conditions match the turnover
15. Provide copies of the following:

9070.01, Control Room Hvac Air Filter Package Operability Test Run.

9012.01, Scram Discharge Volume Vent and Drain Valve Operability Test Page 10 of 11

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 8/24/09 08-01 Event Triggers and Role Play Event #

1. Perform SDV Vent and Drain Valve test one valve fails
a. On a Trigger
b. Roll play:

(1) Equipment Operator: Report all SDV are closed.

(2) Equipment Operator: Report C11-F011 is intermediate at end of test.

2. Reduce power
a. No Trigger
b. Role play: As the MISO call requesting a power reduction to 90% within 30 minutes for Grid Stability.
3. RR FCV Fails shut
a. Remote 1
b. Role play: None
4. VC Makeup Train A Outlet DMPR fails shut during surveilance run
a. Remote 2
b. Role play: The A 0VC05CA Fan is making noise and vibrating.
5. Shift to the B VC train
a. Pending Page
b. Role play: Equipment Operator Perform Local operations Report the backdraft dampers are shut when asked by the CR.

Start VC Chiller

6. SRV 41L Fails open, closes on first attempt to close intermittent.
a. Remote 3
b. Role Play: None
7. Small break LOCA requiring an Emergency Depressurization.
a. Remote 4
b. Role play: None.
8. LPCS Pump fails to start on High Drywell Pressure
a. None
b. Role play: None Page 11 of 11
Retrieved from "https://kanterella.com/w/index.php?title=ML100710757&oldid=2559174"