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| number = ML101890750
| number = ML101890750
| issue date = 06/25/2010
| issue date = 06/25/2010
| title = Grand Gulf-2010-06-Final-Operating Test Outlines
| title = 2010-06-Final-Operating Test Outlines
| author name =  
| author name =  
| author affiliation = NRC/RGN-IV
| author affiliation = NRC/RGN-IV
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=Text=
=Text=
{{#Wiki_filter:ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Examination Level:   RO X     SRO Operating Test Number:
{{#Wiki_filter:ES-301                             Administrative Topics Outline                           Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION                               Date of Examination: 06/28/2010 Examination Level: RO       X SRO                                 Operating Test Number: 6/10 Administrative Topic           Type                    Describe activity to be performed (see Note)               Code*
6/10 Administrative Topic (see Note)
Perform 06-OP-1R20-W-0001-02, Attachment II of weekly AC/DC Lineup for ESF 21 Transformer Retest GJPM-OPS-ADMR91.00 Conduct of Operations                S; N K/A 2.1.20: 4.6 Review Cooldown Record GJPM-OPS-ADMR92.00 Conduct of Operations                R; N K/A2.1.25: 3.9 Determine Tagging Requirements & Prepare Tagout Tags Sheet for SRV B21-F047L Equipment Control                    R; M                        GJPM-OPS-ADMR93.00 K/A 2.2.13: 4.1 N/A Radiation Control Primary Containment Water Level Determination EOP Attachment 29 Emergency Procedures/Plan            R; M                        GJPM-OPS-ADMR94.00 K/A 2.4.21: 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
Type Code* Describe activity to be performed Conduct of Operations S; N  Perform 06-OP-1R20-W-0001-02, Attachment II of weekly AC/DC Lineup for ESF 21 Transformer Retest GJPM-OPS-ADMR91.00 K/A 2.1.20: 4.6 Conduct of Operations R; N  Review Cooldown Record GJPM-OPS-ADMR92.00 K/A2.1.25: 3.9 Equipment Control R; M  Determine Tagging Requirements & Prepare Tagout Tags Sheet for SRV B21-F047L GJPM-OPS-ADMR93.00 K/A 2.2.13: 4.1 Radiation Control N/A Emergency Procedures/Plan R; M  Primary Containment Water Level Determination EOP Attachment 29 GJPM-OPS-ADMR94.00 K/A 2.4.21: 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:         (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes) (N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected)
(N)ew or (M)odified from bank ( 1)
Revision 1 4/14/2010 E S-301 Administrative Topics Outline Form ES-301-1 Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  06/28/2010 Examination Level:  RO          SRO X Operating Test Number:
(P)revious 2 exams ( 1; randomly selected)
6/10 Administrative Topic (see Note)
Revision 1 4/14/2010
Type Code* Describe activity to be performed Conduct of Operations R; N  Determine Fire Watch Requirements GJPM-OPS-ADMS95.00 K/A 2.1.2: 4.4 Conduct of Operations R; M  Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available GJPM-OPS-ADMS96.00 K/A2.1.25: 4.2


Equipment Control  
ES-301                              Administrative Topics Outline                            Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION                              Date of Examination: 06/28/2010 Examination Level: RO              SRO X                          Operating Test Number: 6/10 Administrative Topic            Type                    Describe activity to be performed (see Note)                Code*
Determine Fire Watch Requirements GJPM-OPS-ADMS95.00 Conduct of Operations                R; N K/A 2.1.2: 4.4 Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available GJPM-OPS-ADMS96.00 Conduct of Operations                R; M K/A2.1.25: 4.2 Determine LCO Actions and Initiate a Manual LCO Tracking Report Equipment Control                     R; M                        GJPM-OPS-ADMS97.00 K/A 2.2.22: 4.7 Determine Protective Action Recommendations GJPM-OPS-ADMS88.00 Radiation Control                    R; M K/A 2.3.13: 3.8 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable GJPM-OPS-EAL27.00 Emergency Procedures/Plan            R; M K/A 2.4.41: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)


R; M Determine LCO Actions and Initiate a Manual LCO Tracking Report  GJPM-OPS-ADMS97.00 K/A 2.2.22: 4.7 Radiation Control R; M Determine Protective Action Recommendations GJPM-OPS-ADMS88.00 K/A 2.3.13: 3.8 Emergency Procedures/Plan
ES-301                            Control Room/In-Plant Systems Outline                              Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION                                    Date of Examination: 6/28/2010 Exam Level: RO X              SRO-I        SRO-U                        Operating Test No.: 6/10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function
: a. 201005/201001/295022 Operate CRD System/RCIS to Achieve                          S; L; M; A              1 Criticality and Commence Reactor Heatup
: b. 295030/223001 Raise Suppression Pool Level using HPCS                              S; M; A               5
: c. 217000 Restore RCIC to Standby following Steam Supply                                S; M                  2 Isolation
: d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal                          S; L; M                4 Stratification
: e. 262001 Align Buses 16AB and 17AC to ESF Transformer                                S; M; A                6
: f. 212000 Transfer RPS B to Normal Power Source and RPS A to                          S; M; A                7 Alternate Power Source
: g. 400000 Align CCW to FPCCU Heat Exchanger A                                          S; N; A                8
: h. 21272000 Perform Area Radiation Monitor Functional Test                              S; N                9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. 295016 Perform Remote Shutdown Panel Area Actions for Security                        E; N                7 Code Orange
: j. 295015 EP Attachment 22 - Locally Scram Control Rods                                R; E; D                1
: k. 295019 Install Nitrogen Bottle on ADS Air Supply                                    R; E; D                3
  @          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                    Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                              9/8/4 (E)mergency or abnormal in-plant                                                1/1/1 (EN)gineered safety feature                                                        - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                          1/1/1 (N)ew or (M)odified from bank including 1(A)                                    2/2/1 (P)revious 2 exams                                                                3 /  3 / 2 (randomly selected)
(R)CA                                                                            1/1/1 (S)imulator 5/6/2010


R; M Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable GJPM-OPS-EAL27.00 K/A 2.4.41: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
ES-301                            Control Room/In-Plant Systems Outline                              Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION                                    Date of Examination: 6/28/2010 Exam Level: RO                SRO-I X      SRO-U                        Operating Test No.: 6/10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes) (N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected)  
System / JPM Title                                  Type Code*            Safety Function
: a. 201005/201001/295022 Operate CRD System/RCIS to Achieve                          S; L; M; A              1 Criticality and Commence Reactor Heatup
: b. 295030/223001 Raise Suppression Pool Level using HPCS                              S; M; A               5
: c. 217000 Restore RCIC to Standby following Steam Supply                                S; M                  2 Isolation
: d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal                          S; L; M                4 Stratification
: e. 262001 Align Buses 16AB and 17AC to ESF Transformer 21                              S; M; A                6
: f. 212000 Transfer RPS B to Normal Power Source and RPS A to                          S; M; A                7 Alternate Power Source
: g. 400000 Align CCW to FPCCU Heat Exchanger A                                          S; N; A                8
: h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. 295016 Perform Remote Shutdown Panel Area Actions for Security                        E; N                7 Code Orange
: j. 295015 EP Attachment 22 - Locally Scram Control Rods                                R; E; D                1
: k. 295019 Install Nitrogen Bottle on ADS Air Supply                                    R; E; D                3
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                   Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                              9/8/4 (E)mergency or abnormal in-plant                                                1/1/1 (EN)gineered safety feature                                                        - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                          1/1/1 (N)ew or (M)odified from bank including 1(A)                                    2/2/1 (P)revious 2 exams                                                               3 /  3 /  2 (randomly selected)
(R)CA                                                                            1/1/1 (S)imulator Revision 1 4/14/2010


E S-301 Control Room/In-Plant Systems Outline Form ES-301-25/6/2010    Facility:  GRAND GULF NUCLEAR STATION          Date of Examination:
Appendix D                           Scenario Outline                       Form ES-D-1 Scenario 2 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2           Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________
6/28/2010 Exam Level:  RO X    SRO-I        SRO-U        Operating Test No.:
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
6/10 Control Room Systems
: 1. Place the second Reactor Feed Pump (A) on the Master Level Controller.
@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
: 2. Raise reactor power by withdrawing control rods.
System / JPM Title Type Code*
: 3. Respond to a control rod drifting out.
Safety Function a. 201005/201001/295022 Operate CRD System/RCIS to Achieve Criticality and Commence Reactor Heatup S; L; M; A 1 b. 295030/223001 Raise Suppression Pool Level using HPCS S; M; A 5 c. 217000 Restore RCIC to Standby following Steam Supply Isolation S; M 2 d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal Stratification S; L; M 4 e. 262001 Align Buses 16AB and 17AC to ESF Transformer S; M; A  6 f. 212000 Transfer RPS B to Normal Power Source and RPS A to Alternate Power Source S; M; A 7 g. 400000 Align CCW to FPCCU Heat Exchanger A S; N; A 8 h. 21272000 Perform Area Radiation Monitor Functional Test S; N 9 In-Plant Systems
: 4. Respond to a spurious HPCS initiation followed by HPCS pump trip.
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: 5. Respond to loss of Service Transformers 11 and 21.
: i. 295016 Perform Remote Shutdown Panel Area Actions for Security Code Orange E; N 7 j. 295015 EP Attachment 22 - Locally Scram Control Rods R; E; D 1 k. 295019 Install Nitrogen Bottle on ADS Air Supply R; E; D 3 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
: 6. Respond to a trip of Division 1 Diesel Generator.
* Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path  (C)ontrol room (D)irect from bank  (E)mergency or abnormal in-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  (P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3 9 /  8 /  4  1 /  1 /  1  -  /  -  /  1 (control room system)    1 /  1 /  1  2 /  2 /  1  3 /  3 /  2 (randomly selected)  1 /  1 /  1 E S-301 Control Room/In-Plant Systems Outline Form ES-301-2Revision 1 4/14/2010 Facility:  GRAND GULF NUCLEAR STATION          Date of Examination:
: 7. Respond to LOCA in the Drywell.
6/28/2010 Exam Level:  RO        SRO-I X    SRO-U        Operating Test No.:
6/10 Control Room Systems
@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a. 201005/201001/295022 Operate CRD System/RCIS to Achieve Criticality and Commence Reactor Heatup S; L; M; A 1 b. 295030/223001 Raise Suppression Pool Level using HPCS S; M; A 5 c. 217000 Restore RCIC to Standby following Steam Supply Isolation S; M 2 d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal Stratification S; L; M 4 e. 262001 Align Buses 16AB and 17AC to ESF Transformer 21 S; M; A 6 f. 212000 Transfer RPS B to Normal Power Source and RPS A to Alternate Power Source S; M; A 7 g. 400000 Align CCW to FPCCU Heat Exchanger A S; N; A 8 h. N/A  In-Plant Systems
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. 295016 Perform Remote Shutdown Panel Area Actions for Security Code Orange E; N 7 j. 295015 EP Attachment 22 - Locally Scram Control Rods R; E; D 1 k. 295019 Install Nitrogen Bottle on ADS Air Supply R; E; D 3 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path  (C)ontrol room (D)irect from bank  (E)mergency or abnormal in-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  (P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3 9 /  8 /  4  1 /  1 /  1  -  /  -  /  1 (control room system)    1 /  1 /  1  2 /  2 /  1  3 /  3 /  2 (randomly selected)  1 /  1 /  1 Appendix D Scenario Outline Form ES-D-1 Scenario 2 REVISION 6/10/2010 SCENARIO 2 NUREG 1021 REVISION 9Rev 2 PAGE 1 of 3 Facility: GRAND GULF NUCLEAR STATION Scenario No.:
2 Op-Test No.:
06/10 Examiners: _________________________ Operators:__________________________
_________________________                  __________________________                    _________________________          __________________________
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:  
: 1. Place the second Reactor Feed Pump (A) on the Master Level Controller.  
: 2. Raise reactor power by withdrawing control rods.  
: 3. Respond to a control rod drifting out. 4. Respond to a spurious HPCS init iation followed by HPCS pump trip.  
: 5. Respond to loss of Se rvice Transformers 11 and 21.  
: 6. Respond to a trip of Division 1 Diesel Generator.  
: 7. Respond to LOCA in the Drywell.  
: 8. Respond to a failure Division 2 ECCS to automatically initiate.
: 8. Respond to a failure Division 2 ECCS to automatically initiate.
Initial Conditions:
Initial Conditions: Reactor Power is 50%.
Reactor Power is 50%.
INOPERABLE Equipment None Turnover:
INOPERABLE Equipment None Turnover:   The plant is at 50% power during startup.
The plant is at 50% power during startup. Reactor Recirc pumps are in fast speed with core flow 60%. Both Circ Water Pumps are in service. After assuming the shift, place RFP A on the Master Level Controller per IOI 03-1-01-2 step 5.16.1 and SOI 04-1-01-N21 section 4.6.4 immediately following turnover. Then, power ascension is to continue with withdrawing control rods in accordance with the Control Rod Movement Sequence per IOI 03-1-01-2 and the Reactivity Management Plan for startup. There is no out of service equipment, and EOOS is green. A Division 1 work week is in effect.
Reactor Recirc pumps are in fast speed with core flow 60%. Both Circ Water Pumps are in service. After assuming the shift, place RFP A on the Master Level Contro ller per IOI 03-1-01-2 step 5.16.1 and SOI 04-1-01-N21 section 4.6.4 imm ediately following turnover. Then, power ascension is to continue with withdrawing control rods in accordance with the Control Rod Movement Sequence per IOI 03-1-01-2 and the Reactivity Management Plan for startup. There is no out of service equipment, and EOOS is green. A Division 1 work week is in effect.  
REVISION 6/10/2010                    SCENARIO 2              NUREG 1021 REVISION 9 Rev 2                                PAGE 1 of 3


Appendix D Scenario Outline Form ES-D-1 Scenario 2 REVISION 6/10/2010 SCENARIO 2 NUREG 1021 REVISION 9Rev 2 PAGE 2 of 3 Event No. Malf. No.
Appendix D                               Scenario Outline                       Form ES-D-1 Scenario 2 Event       Malf. No.       Event                                  Event No.                        Type*                               Description 1                         N(BOP)
Event Type* Event Description 1   N(BOP)   Place Reactor Feed Pump A on the Master Level  
Place Reactor Feed Pump A on the Master Level Controller (IOI 03-1-01-2 step 5.16.1 and SOI 04-1                                          N21-1 section 4.6.4) 2                        R(ACRO)
Raise reactor power to approximately 55% by withdrawing control rods. (Control Rod Movement Sequence) 3    z161161_40_25      C(ACRO)
Respond to control rod 40-25 drift out (ONEP 05-1-02-IV-1 sections 2.2/3.2; Tech Spec 3.1.3) 4    e22052              C(SS) e22053                          Respond to a spurious HPCS initiation and HPCS pump trip (02-S-01-27 step 6.6.3, ARI 04-1-02-1H13-P601-16A-H3, Tech Spec 3.5.1) 5    r21133a            M(ALL) r21133b                          Respond to a trip of Service Transformers 11 and 21 (ONEPs 05-1-02-I-4, 05-1-02-I-1, 05-1-02-I-2; EP-2) 6    n41141a            C (BOP)
Respond to trip of Division 1 Diesel Generator (ONEP 05-1-02-I-4) 7 rr063a@4.92        M(ALL)
Respond to a LOCA in the drywell (EP-2, EP-3) 8 rr040f@0            I(ACRO) rr041f@100                      Respond to failure of Division 2 ECCS to automatically initiate (EN-OP-115)
* (N)ormal,  (R)eactivity,    (I)nstrument,  (C)omponent,  (M)ajor REVISION 6/10/2010                      SCENARIO 2              NUREG 1021 REVISION 9 Rev 2                                  PAGE 2 of 3


Controller (IOI 03-1-01-2 step 5.16.1 and SOI 04-1 N21-1 section 4.6.4) 2 R(ACRO)  Raise reactor power to approximately 55% by
Appendix D                            Scenario Outline                    Form ES-D-1 Scenario 2 Critical Tasks
    -   Open at least seven SRVs before RPV level drops to -210 Fuel Zone Range.
    -   Manually initiate Division 2 ECCS prior to RPV pressure going below 300 psig.
REVISION 6/10/2010                    SCENARIO 2          NUREG 1021 REVISION 9 Rev 2                                 PAGE 3 of 3


withdrawing control rods. (Control Rod Movement Sequence)  
Appendix D                          Simulator Operation                      Form ES-D-2 Scenario 5 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 5          Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
: 1. Raise reactor power to 100% using Recirc Flow Control Valves.
: 2. Respond to failure of RPS RPV Level Transmitter A.
: 3. Respond to Thyristor Voltage Regulator (TVR) trip to manual.
: 4. Respond to Recirc Pump A trip.
: 5. Respond to Thermal Hydraulic Instability.
: 6. Respond to a failure of the Reactor Mode Switch to initiate Scram.
: 7. Respond to Hydraulic Block ATWS above 4% power.
: 8. Respond to a SLC piping rupture.
Initial Conditions: Reactor Power is 90%.
INOPERABLE Equipment None Turnover:
The plant is at 90% power. Reactor power is to be raised to 100%. Pre-conditioning conditions are established for 100% power operation. There is no out of service equipment and EOOS is green. A Division 1 work week is in effect.
REVISION 6/10/2010                    SCENARIO 5            NUREG 1021 REVISION 9 Rev 2                                PAGE 1 of 3


3  z161161_40_25 C(ACRO) Respond to control rod 40-25 drift out (ONEP 05-1-02-IV-1 sections 2.2/3.2; Tech Spec 3.1.3)
Appendix D                              Simulator Operation                      Form ES-D-2 Scenario 5 Event        Malf. No.        Event                        Event No.                          Type*                      Description 1                          R(ACRO)
Raise reactor power to 100% using Recirc Flow Control Valves (IOI 03-1-01-2 Attachment VIII) lt b21n080a_b        C(ACRO) 2                                      Respond to failure of RPS RPV Level Transmitter A. (ARI 04-1-02-1H13-P6804A2-D4; 5A-C1; 7A-A2; Tech Spec 3.3.1.1; 3.3.6.1; TR3.1.5).
3    n41102                C(BOP)
Respond to TVR trip from Automatic to Manual (ARI 04-1-02-1H13-P680-9A-C15, SOI 04-1                                          N40-1 section 5.2) (GGNS Scram 10/2008) 4    rr012a                C(BOP)
Respond to trip of Recirc Pump A (ARI 04-1                                          P680-3A-B4, ONEP 05-1-02-III-3; Tech Spec 3.4.1) 5    rr165 @ 5 - 100      C(ACRO) over 5 minutes                  Respond to Thermal Hydraulic Instability (ONEP c71162                            05-1-02-III-3, 05-1-02-I-1, 05-1-02-I-2) 6    di_1c71m602          C(ACRO)
RUN                              Respond to a failure of the Reactor Mode Switch to scram the Reactor. (EN-OP-115) 7 c11164 @ 30          M(ALL)
Respond to ATWS to insert control rods with power above 4% (EP-2A) 8 c41263 @ 60          C (BOP)
Respond to leak in SLC piping (EP-2A)
* (N)ormal,    (R)eactivity,  (I)nstrument,  (C)omponent,    (M)ajor REVISION 6/10/2010                      SCENARIO 5                NUREG 1021 REVISION 9 Rev 2                                    PAGE 2 of 3


4  e22052 e22053  C(SS)   Respond to a spurious HPCS initiation and HPCS pump
Appendix D                        Simulator Operation                    Form ES-D-2 Scenario 5 Critical Tasks
    -   When Thermal Hydraulic Instability is observed, inserts a manual scram.
    -  Insert control rods by manual scram and/or normal rod insertion via RCIS.
REVISION 6/10/2010                  SCENARIO 5              NUREG 1021 REVISION 9 Rev 2                              PAGE 3 of 3


trip (02-S-01-27 step 6.6.
Appendix D                         Simulator Operation                       Form ES-D-2 Scenario 6 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 6         Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________
3, ARI 04-1-02-1H13-P601-
Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:
 
: 1. Raise reactor power to 85% using Recirc Flow Control Valves.
16A-H3, Tech Spec 3.5.1) 5  r21133a r21133b  M(ALL)  Respond to a trip of Service Transformers 11 and 21 (ONEPs 05-1-02-I-4, 05 02-I-1, 05-1-02-I-2; EP-2) 6  n41141a C (BOP)  Respond to trip of Division 1 Diesel Generator (ONEP 05-1-02-I-4) 7  rr063a@4.92
: 2. Place the third Condensate and Condensate Booster Pump in service.
 
: 3. Respond to APRM A failed upscale.
M(ALL)  Respond to a LOCA in t he drywell (EP-2, EP-3) 8  rr040f@0 rr041f@100 I(ACRO)  Respond to failure of Division 2 ECCS to automatically
: 4. Respond to trip of ESF Transformer11.
 
: 5. Respond to a loss of Main Condenser Vacuum.
initiate (EN-OP-115) *  (N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajor
: 6. Respond to a LOCA with reduced injection systems.
 
Appendix D Scenario Outline Form ES-D-1 Scenario 2  REVISION 6/10/2010 SCENARIO 2 NUREG 1021 REVISION 9Rev 2 PAGE 3 of 3 Critical Tasks
- Open at least seven SRVs before RPV level drops to -210" Fuel Zone Range. 
- Manually initiate Division 2 ECCS prior to RPV pressure going below 300
 
psig.
Appendix D Simulator Operation Form ES-D-2 Scenario 5    Facility: GRAND GULF NUCLEAR STATION Scenario No.:
5 Op-Test No.:
06/10  Examiners:  _________________________ Operators:__________________________                    _________________________                  __________________________
_________________________          __________________________
 
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
: 1. Raise reactor power to 100% using Recirc Flow Control Valves.
: 2. Respond to failure of RPS RPV Level Transmitter A.
: 3. Respond to Thyristor Voltage Regulator (TVR) trip to manual.
: 4. Respond to Recirc Pump A trip.
: 5. Respond to Thermal Hydraulic Instability.
: 6. Respond to a failure of the Reac tor Mode Switch to initiate Scram.
: 7. Respond to Hydraulic Block ATWS above 4% power.
: 8. Respond to a SLC piping rupture.
 
Initial Conditions:
Reactor Power is 90%. 
 
INOPERABLE Equipment None  Turnover:    The plant is at 90% power. Reactor power is to be raised to 100%. Pre-conditioning conditions are established for 100% power operation. There is no out of service equipment and EOOS is green. A Divis ion 1 work week is in effect.
REVISION 6/10/2010 SCENARIO 5 NUREG 1021 REVISION 9Rev 2 PAGE 1 of 3
 
Appendix D Simulator Operation Form ES-D-2 Scenario 5  REVISION 6/10/2010 SCENARIO 5 NUREG 1021 REVISION 9Rev 2 PAGE 2 of 3 Event No. Malf. No.
Event Type* Event Description 1  R(ACRO)  Raise reactor power to 100% using Recirc Flow Control Valves (IOI 03-1-01-2 Attachment VIII) 2  lt b21n080a_b C(ACRO)  Respond to failure of RPS RPV Level Transmitter A. (ARI 04-1-02-1H13-P6804A2-D4; 5A-C1; 7A-A2; Tech Spec 3.3.1.1; 3.3.6.1; TR3.1.5).
3  n41102 C(BOP)  Respond to TVR trip from Automatic to Manual (ARI 04-1-02-1H13-P680-9A-C15, SOI 04-1 N40-1 section 5.2) (GGNS Scram 10/2008)
 
4  rr012a C(BOP)  Respond to trip of Recirc Pump A (ARI 04-1 P680-3A-B4, ONEP 05-1-02-II I-3; Tech Spec 3.4.1) 5  rr165 @  5 - 100 over 5 minutes c71162  C(ACRO)
Respond to Thermal Hydraulic Instability (ONEP 05-1-02-III-3, 05-1 I-1, 05-1-02-I-2) 6  di_1c71m602 RUN  C(ACRO)  Respond to a failure of the Reactor Mode Switch to scram the Reactor. (EN-OP-115) 7  c11164 @ 30
 
M(ALL)  Respond to ATWS to insert control rods with power above 4% (EP-2A) 8  c41263 @ 60
 
C (BOP)  Respond to leak in SLC piping (EP-2A) *  (N)ormal,    (R)eactivity,    (I)nstrument,    (C)omponent,    (M)ajor
 
Appendix D Simulator Operation Form ES-D-2 Scenario 5  REVISION 6/10/2010 SCENARIO 5 NUREG 1021 REVISION 9Rev 2 PAGE 3 of 3 Critical Tasks
- When Thermal Hydraulic Instability is observed, inserts a manual scram.
- Insert control rods by manual scram and/or normal rod insertion via RCIS. 
 
Appendix D Simulator Operation Form ES-D-2 Scenario 6    Facility: GRAND GULF NUCLEAR STATION Scenario No.:
6 Op-Test No.:
06/10   Examiners: _________________________ Operators:__________________________                     _________________________                  __________________________
_________________________          __________________________
 
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:  
: 1. Raise reactor power to 85% using Recirc Flow Control Valves.  
: 2. Place the third Condensate and Conde nsate Booster Pump in service.  
: 3. Respond to APRM A failed upscale.  
: 4. Respond to trip of ESF Transformer11. 5. Respond to a loss of Main Condenser Vacuum.  
: 6. Respond to a LOCA wit h reduced injection systems.  
: 7. Respond to failure of RCIC to auto start.
: 7. Respond to failure of RCIC to auto start.
Initial Conditions:
Initial Conditions: Reactor Power is 80%.
Reactor Power is 80%.  
INOPERABLE Equipment None Turnover:
 
The plant is at 80% power. Reactor power is to be raised to 85%. Pre-conditioning conditions are established for 100% power operation.
INOPERABLE Equipment None Turnover:   The plant is at 80% power. Reactor power is to be raised to 85%. Pre-conditioning conditions are established for 100% power operation. Condensate Pump B and Condensate Booster Pump B pre-start checks are  
Condensate Pump B and Condensate Booster Pump B pre-start checks are complete.
 
complete.  
 
Condensate Cleanup is ready for the third Condensate and Booster Pump operation.
Condensate Cleanup is ready for the third Condensate and Booster Pump operation.
IOI 03-1-01-2 Attachment II step 6.6 is complete. There is no out of service equipment and EOOS is green. A Divis ion 1 work week is in effect.
IOI 03-1-01-2 Attachment II step 6.6 is complete. There is no out of service equipment and EOOS is green. A Division 1 work week is in effect.
REVISION 6/10/2010 SCENARIO 6 NUREG 1021 REVISION 9Rev 2 PAGE 1 of 3  
REVISION 6/10/2010                 SCENARIO 6             NUREG 1021 REVISION 9 Rev 2                               PAGE 1 of 3
 
Appendix D Simulator Operation Form ES-D-2 Scenario 6  REVISION 6/10/2010 SCENARIO 6 NUREG 1021 REVISION 9Rev 2 PAGE 2 of 3 Event No. Malf. No.
Event Type* Event Description 1  R(ACRO)  Raise reactor power to 85% using Recirc Flow
 
Control Valves (IOI 03-1-01-2 Attachment II) 2    N(BOP)  Place the third Conde nsate and Condensate Booster Pump in service. (SOI 04-1-01-N19-1


section 4.3).
Appendix D                            Simulator Operation                      Form ES-D-2 Scenario 6 Event      Malf. No.      Event                          Event No.                      Type*                        Description 1                        R(ACRO)
3 c51009a C(ACRO) Respond to APRM A failed upscale (ARI 04-1 P680-5A-A11; B10; Tech Spec/TR 3.3.1.1; TR 3.3.2.1) 4 r21134g C(BOP)   Respond to trip of ESF Transformer 11. (ARI 04-1-02-1H13-P807 4A-B2; E6
Raise reactor power to 85% using Recirc Flow Control Valves (IOI 03-1-01-2 Attachment II) 2                        N(BOP)
-, ONEP 05-1-02-I-4; Tech Spec 3.8.1) (S OER 10-1 Large Power Transformer Reliability) 5 fw163a @ 5 ramp to 100 over 1 4 minutes C(ACRO)   Respond to a loss of Main Condenser Vacuum (ONEP 05-1-02-V-8) 6 rr063a@ 10 over 2 minutes M(ALL) Respond to a LOCA with reduced injection systems. (EP-2/3) 7 e51043 C(ACRO) Respond to failure of RCI C to auto start (EP-2; SOI 04-1-01-E51-1) *   (N)ormal,    (R)eactivity,   (I)nstrument,   (C)omponent,    (M)ajor  
Place the third Condensate and Condensate Booster Pump in service. (SOI 04-1-01-N19-1 section 4.3).
3     c51009a           C(ACRO)
Respond to APRM A failed upscale (ARI 04-1                                         P680-5A-A11; B10; Tech Spec/TR 3.3.1.1; TR 3.3.2.1) 4     r21134g           C(BOP)
Respond to trip of ESF Transformer 11. (ARI 04-1-02-1H13-P807 4A-B2; E6-, ONEP 05-1-02-I-4; Tech Spec 3.8.1) (SOER 10-1 Large Power Transformer Reliability) 5     fw163a @ 5         C(ACRO) ramp to 100                      Respond to a loss of Main Condenser Vacuum over 14                          (ONEP 05-1-02-V-8) minutes 6     rr063a@ 10         M(ALL) over 2 minutes                  Respond to a LOCA with reduced injection systems. (EP-2/3) 7 e51043             C(ACRO)
Respond to failure of RCIC to auto start (EP-2; SOI 04-1-01-E51-1)
* (N)ormal,    (R)eactivity, (I)nstrument, (C)omponent,    (M)ajor REVISION 6/10/2010                    SCENARIO 6                NUREG 1021 REVISION 9 Rev 2                                  PAGE 2 of 3


Appendix D Simulator Operation Form ES-D-2 Scenario 6 REVISION 6/10/2010 SCENARIO 6 NUREG 1021 REVISION 9Rev 2 PAGE 3 of 3 Critical Tasks  
Appendix D                       Simulator Operation                     Form ES-D-2 Scenario 6 Critical Tasks
- Reduce RPV Pressure to within capabilit y of Condensate or Low Pressure ECCS to allow RPV level restoration.  
    -   Reduce RPV Pressure to within capability of Condensate or Low Pressure ECCS to allow RPV level restoration.
   - Restore and maintain RPV level above  
    -   Restore and maintain RPV level above -191 using available injection systems.
-191" using available injection systems.}}
REVISION 6/10/2010                SCENARIO 6            NUREG 1021 REVISION 9 Rev 2                              PAGE 3 of 3}}

Latest revision as of 22:28, 11 March 2020

2010-06-Final-Operating Test Outlines
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Issue date: 06/25/2010
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Examination Level: RO X SRO Operating Test Number: 6/10 Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform 06-OP-1R20-W-0001-02, Attachment II of weekly AC/DC Lineup for ESF 21 Transformer Retest GJPM-OPS-ADMR91.00 Conduct of Operations S; N K/A 2.1.20: 4.6 Review Cooldown Record GJPM-OPS-ADMR92.00 Conduct of Operations R; N K/A2.1.25: 3.9 Determine Tagging Requirements & Prepare Tagout Tags Sheet for SRV B21-F047L Equipment Control R; M GJPM-OPS-ADMR93.00 K/A 2.2.13: 4.1 N/A Radiation Control Primary Containment Water Level Determination EOP Attachment 29 Emergency Procedures/Plan R; M GJPM-OPS-ADMR94.00 K/A 2.4.21: 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Revision 1 4/14/2010

ES-301 Administrative Topics Outline Form ES-301-1 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Examination Level: RO SRO X Operating Test Number: 6/10 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Fire Watch Requirements GJPM-OPS-ADMS95.00 Conduct of Operations R; N K/A 2.1.2: 4.4 Determine Plant Safety Index Risk Color with the EOOS Risk Monitor Not Available GJPM-OPS-ADMS96.00 Conduct of Operations R; M K/A2.1.25: 4.2 Determine LCO Actions and Initiate a Manual LCO Tracking Report Equipment Control R; M GJPM-OPS-ADMS97.00 K/A 2.2.22: 4.7 Determine Protective Action Recommendations GJPM-OPS-ADMS88.00 Radiation Control R; M K/A 2.3.13: 3.8 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable GJPM-OPS-EAL27.00 Emergency Procedures/Plan R; M K/A 2.4.41: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 6/28/2010 Exam Level: RO X SRO-I SRO-U Operating Test No.: 6/10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. 201005/201001/295022 Operate CRD System/RCIS to Achieve S; L; M; A 1 Criticality and Commence Reactor Heatup
b. 295030/223001 Raise Suppression Pool Level using HPCS S; M; A 5
c. 217000 Restore RCIC to Standby following Steam Supply S; M 2 Isolation
d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal S; L; M 4 Stratification
e. 262001 Align Buses 16AB and 17AC to ESF Transformer S; M; A 6
f. 212000 Transfer RPS B to Normal Power Source and RPS A to S; M; A 7 Alternate Power Source
g. 400000 Align CCW to FPCCU Heat Exchanger A S; N; A 8
h. 21272000 Perform Area Radiation Monitor Functional Test S; N 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. 295016 Perform Remote Shutdown Panel Area Actions for Security E; N 7 Code Orange
j. 295015 EP Attachment 22 - Locally Scram Control Rods R; E; D 1
k. 295019 Install Nitrogen Bottle on ADS Air Supply R; E; D 3

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator 5/6/2010

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 6/28/2010 Exam Level: RO SRO-I X SRO-U Operating Test No.: 6/10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. 201005/201001/295022 Operate CRD System/RCIS to Achieve S; L; M; A 1 Criticality and Commence Reactor Heatup
b. 295030/223001 Raise Suppression Pool Level using HPCS S; M; A 5
c. 217000 Restore RCIC to Standby following Steam Supply S; M 2 Isolation
d. 202001 Rapid Restart of Recirc Pump A to Mitigate Thermal S; L; M 4 Stratification
e. 262001 Align Buses 16AB and 17AC to ESF Transformer 21 S; M; A 6
f. 212000 Transfer RPS B to Normal Power Source and RPS A to S; M; A 7 Alternate Power Source
g. 400000 Align CCW to FPCCU Heat Exchanger A S; N; A 8
h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. 295016 Perform Remote Shutdown Panel Area Actions for Security E; N 7 Code Orange
j. 295015 EP Attachment 22 - Locally Scram Control Rods R; E; D 1
k. 295019 Install Nitrogen Bottle on ADS Air Supply R; E; D 3

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator Revision 1 4/14/2010

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2 Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Place the second Reactor Feed Pump (A) on the Master Level Controller.
2. Raise reactor power by withdrawing control rods.
3. Respond to a control rod drifting out.
4. Respond to a spurious HPCS initiation followed by HPCS pump trip.
5. Respond to loss of Service Transformers 11 and 21.
6. Respond to a trip of Division 1 Diesel Generator.
7. Respond to LOCA in the Drywell.
8. Respond to a failure Division 2 ECCS to automatically initiate.

Initial Conditions: Reactor Power is 50%.

INOPERABLE Equipment None Turnover:

The plant is at 50% power during startup. Reactor Recirc pumps are in fast speed with core flow 60%. Both Circ Water Pumps are in service. After assuming the shift, place RFP A on the Master Level Controller per IOI 03-1-01-2 step 5.16.1 and SOI 04-1-01-N21 section 4.6.4 immediately following turnover. Then, power ascension is to continue with withdrawing control rods in accordance with the Control Rod Movement Sequence per IOI 03-1-01-2 and the Reactivity Management Plan for startup. There is no out of service equipment, and EOOS is green. A Division 1 work week is in effect.

REVISION 6/10/2010 SCENARIO 2 NUREG 1021 REVISION 9 Rev 2 PAGE 1 of 3

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Event Malf. No. Event Event No. Type* Description 1 N(BOP)

Place Reactor Feed Pump A on the Master Level Controller (IOI 03-1-01-2 step 5.16.1 and SOI 04-1 N21-1 section 4.6.4) 2 R(ACRO)

Raise reactor power to approximately 55% by withdrawing control rods. (Control Rod Movement Sequence) 3 z161161_40_25 C(ACRO)

Respond to control rod 40-25 drift out (ONEP 05-1-02-IV-1 sections 2.2/3.2; Tech Spec 3.1.3) 4 e22052 C(SS) e22053 Respond to a spurious HPCS initiation and HPCS pump trip (02-S-01-27 step 6.6.3, ARI 04-1-02-1H13-P601-16A-H3, Tech Spec 3.5.1) 5 r21133a M(ALL) r21133b Respond to a trip of Service Transformers 11 and 21 (ONEPs 05-1-02-I-4, 05-1-02-I-1, 05-1-02-I-2; EP-2) 6 n41141a C (BOP)

Respond to trip of Division 1 Diesel Generator (ONEP 05-1-02-I-4) 7 rr063a@4.92 M(ALL)

Respond to a LOCA in the drywell (EP-2, EP-3) 8 rr040f@0 I(ACRO) rr041f@100 Respond to failure of Division 2 ECCS to automatically initiate (EN-OP-115)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 6/10/2010 SCENARIO 2 NUREG 1021 REVISION 9 Rev 2 PAGE 2 of 3

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Critical Tasks

- Open at least seven SRVs before RPV level drops to -210 Fuel Zone Range.

- Manually initiate Division 2 ECCS prior to RPV pressure going below 300 psig.

REVISION 6/10/2010 SCENARIO 2 NUREG 1021 REVISION 9 Rev 2 PAGE 3 of 3

Appendix D Simulator Operation Form ES-D-2 Scenario 5 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 5 Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Raise reactor power to 100% using Recirc Flow Control Valves.
2. Respond to failure of RPS RPV Level Transmitter A.
3. Respond to Thyristor Voltage Regulator (TVR) trip to manual.
4. Respond to Recirc Pump A trip.
5. Respond to Thermal Hydraulic Instability.
6. Respond to a failure of the Reactor Mode Switch to initiate Scram.
7. Respond to Hydraulic Block ATWS above 4% power.
8. Respond to a SLC piping rupture.

Initial Conditions: Reactor Power is 90%.

INOPERABLE Equipment None Turnover:

The plant is at 90% power. Reactor power is to be raised to 100%. Pre-conditioning conditions are established for 100% power operation. There is no out of service equipment and EOOS is green. A Division 1 work week is in effect.

REVISION 6/10/2010 SCENARIO 5 NUREG 1021 REVISION 9 Rev 2 PAGE 1 of 3

Appendix D Simulator Operation Form ES-D-2 Scenario 5 Event Malf. No. Event Event No. Type* Description 1 R(ACRO)

Raise reactor power to 100% using Recirc Flow Control Valves (IOI 03-1-01-2 Attachment VIII) lt b21n080a_b C(ACRO) 2 Respond to failure of RPS RPV Level Transmitter A. (ARI 04-1-02-1H13-P6804A2-D4; 5A-C1; 7A-A2; Tech Spec 3.3.1.1; 3.3.6.1; TR3.1.5).

3 n41102 C(BOP)

Respond to TVR trip from Automatic to Manual (ARI 04-1-02-1H13-P680-9A-C15, SOI 04-1 N40-1 section 5.2) (GGNS Scram 10/2008) 4 rr012a C(BOP)

Respond to trip of Recirc Pump A (ARI 04-1 P680-3A-B4, ONEP 05-1-02-III-3; Tech Spec 3.4.1) 5 rr165 @ 5 - 100 C(ACRO) over 5 minutes Respond to Thermal Hydraulic Instability (ONEP c71162 05-1-02-III-3, 05-1-02-I-1, 05-1-02-I-2) 6 di_1c71m602 C(ACRO)

RUN Respond to a failure of the Reactor Mode Switch to scram the Reactor. (EN-OP-115) 7 c11164 @ 30 M(ALL)

Respond to ATWS to insert control rods with power above 4% (EP-2A) 8 c41263 @ 60 C (BOP)

Respond to leak in SLC piping (EP-2A)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 6/10/2010 SCENARIO 5 NUREG 1021 REVISION 9 Rev 2 PAGE 2 of 3

Appendix D Simulator Operation Form ES-D-2 Scenario 5 Critical Tasks

- When Thermal Hydraulic Instability is observed, inserts a manual scram.

- Insert control rods by manual scram and/or normal rod insertion via RCIS.

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Appendix D Simulator Operation Form ES-D-2 Scenario 6 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 6 Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Raise reactor power to 85% using Recirc Flow Control Valves.
2. Place the third Condensate and Condensate Booster Pump in service.
3. Respond to APRM A failed upscale.
4. Respond to trip of ESF Transformer11.
5. Respond to a loss of Main Condenser Vacuum.
6. Respond to a LOCA with reduced injection systems.
7. Respond to failure of RCIC to auto start.

Initial Conditions: Reactor Power is 80%.

INOPERABLE Equipment None Turnover:

The plant is at 80% power. Reactor power is to be raised to 85%. Pre-conditioning conditions are established for 100% power operation.

Condensate Pump B and Condensate Booster Pump B pre-start checks are complete.

Condensate Cleanup is ready for the third Condensate and Booster Pump operation.

IOI 03-1-01-2 Attachment II step 6.6 is complete. There is no out of service equipment and EOOS is green. A Division 1 work week is in effect.

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Appendix D Simulator Operation Form ES-D-2 Scenario 6 Event Malf. No. Event Event No. Type* Description 1 R(ACRO)

Raise reactor power to 85% using Recirc Flow Control Valves (IOI 03-1-01-2 Attachment II) 2 N(BOP)

Place the third Condensate and Condensate Booster Pump in service. (SOI 04-1-01-N19-1 section 4.3).

3 c51009a C(ACRO)

Respond to APRM A failed upscale (ARI 04-1 P680-5A-A11; B10; Tech Spec/TR 3.3.1.1; TR 3.3.2.1) 4 r21134g C(BOP)

Respond to trip of ESF Transformer 11. (ARI 04-1-02-1H13-P807 4A-B2; E6-, ONEP 05-1-02-I-4; Tech Spec 3.8.1) (SOER 10-1 Large Power Transformer Reliability) 5 fw163a @ 5 C(ACRO) ramp to 100 Respond to a loss of Main Condenser Vacuum over 14 (ONEP 05-1-02-V-8) minutes 6 rr063a@ 10 M(ALL) over 2 minutes Respond to a LOCA with reduced injection systems. (EP-2/3) 7 e51043 C(ACRO)

Respond to failure of RCIC to auto start (EP-2; SOI 04-1-01-E51-1)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 6/10/2010 SCENARIO 6 NUREG 1021 REVISION 9 Rev 2 PAGE 2 of 3

Appendix D Simulator Operation Form ES-D-2 Scenario 6 Critical Tasks

- Reduce RPV Pressure to within capability of Condensate or Low Pressure ECCS to allow RPV level restoration.

- Restore and maintain RPV level above -191 using available injection systems.

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