ML101450206

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2010-06-DRAFT-Outlines Ops Test
ML101450206
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 06/25/2010
From: Garchow S
NRC Region 4
To:
Entergy Operations
References
50-416/10-301, ES-301, ES-301-1
Download: ML101450206 (26)
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Text

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 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)

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. 272000 Perform Area Radiation Monitor Functional Test S; N 9
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. 262001 Align Buses 16AB and 17AC to ESF Transformer 21 S; M; A 6 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

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. 272000 Perform Area Radiation Monitor Functional Test S; N 9
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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 06/28/2010 Exam Level: RO SRO-I SRO-U Operating Test No.: BACKUP JPMS 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 Control Rod Operability Surveillance S; M; A 1/7
b. 223002 Isolate Division 2 Valves following Failure to Auto Isolate S; N 5 c.

d.

e.

f.

g.

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 263000 Battery Charger Startup D 6 j.

k.

@ 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

ES-301 Transient and Event Checklist Form ES-301-5 Form 1 of 2 ** completed on form 2 of 2 Facility: GRAND GULF Date of Exam: 6/28/2010 Operating Test No.: 6/10 A E Scenarios P V P E 1 2 3 4 T M N I L O T CREW CREW CREW CREW N I T I C T POSITION POSITION POSITION POSITION A M A Y S A B S A B S A B S A B U L

N P R T O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RO 1 RX 1 1 1 1 0 X

SRO I NOR 1 1 1 1 1 I/C 3 2 1 6 4 4 2 SRO-U MAJ 1 2 2 5 2 2 1 TS 0 0 2 2 RO RX 1 1 1 1 0 NOR 1 1 2 1 1 1 SRO-I 2 X I/C 2 3 3 8 4 4 2 SRO-U MAJ 1 2 1 4 2 2 1 TS 2 2 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 SRO-I 1 X ** I/C 4 4 8 4 4 2 SRO-U MAJ 1 2 3 2 2 1 TS 2 2 4 0 2 2 RO 2 RX 1 1 1 1 0 X **

SRO-I NOR 1 1 1 1 1 I/C 2 3 5 4 4 2 SRO-U MAJ 2 1 3 2 2 1 TS 0 0 2 2 RO RX 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I 3 X ** I/C 3 3 6 4 4 2 SRO-U MAJ 1 2 3 2 2 1 TS 2 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

3/24/2010

ES-301 Transient and Event Checklist Form ES-301-5 Form 2 of 2 ** combined forms 1 & 2 Facility: GRAND GULF Date of Exam: 6/28/2010 Operating Test No.: 6/10 A E Scenarios P V P E 5 T M N I L O T CREW CREW CREW CREW N I T I C T POSITION POSITION POSITION POSITION A M A Y S A B S A B S A B S A B U L

N P R T O R T O R T O R T O M(*)

T E **

O C P O C P O C P O C P R I U RO 1 RX 1 1 1 0 X

SRO I NOR Transferred from form 1 1 1 1 1 I/C 6 4 4 2 SRO-U MAJ 5 2 2 1 TS 0 0 2 2 RO RX 1 1 1 0 NOR Transferred from form 1 2 1 1 1 SRO-I 2 X I/C 8 4 4 2 SRO-U MAJ 4 2 2 1 TS 2 0 2 2 RO RX 1 1 1 1 0 NOR Added to form 1 1 1 1 1 SRO-I 1 X I/C 4 12 4 4 2 SRO-U MAJ 1 4 2 2 1 TS 4 0 2 2 RO 2 RX 1 1 1 0 X

SRO-I NOR Added to form 1 1 1 1 1 I/C 2 7 4 4 2 SRO-U MAJ 1 4 2 2 1 TS 0 0 2 2 RO RX 1 1 1 0 NOR Added to form 1 1 1 1 1 SRO-I 3 X I/C 5 11 4 4 2 SRO-U MAJ 1 4 2 2 1 TS 2 4 0 2 2 Instructions:

3. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
4. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

3/24/2010

ES-301 Transient and Event Checklist Form ES-301-5 Facility: GRAND GULF Date of Exam: 6/28/2010 Operating Test No.: 6/10 A E Scenarios P V P E 6 Back Up T M N I L O T CREW CREW CREW CREW N I T I C T POSITION POSITION POSITION POSITION A M A Y S A B S A B S A B S A B U L

N P R T O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RO RX 1 1 1 0 NOR 1 1 1 1 1 SRO I I/C 3 3 1 4 4 2 SRO-U MAJ 1 1 1 2 2 1 TS 2 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

5. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
6. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

3/24/2010

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

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

1. Shift Reactor Recirc pump B to fast speed.
2. Withdraw control rods to raise power.
3. Respond to Fuel Handling Area Vent Exhaust Radiation Monitor failure.
4. Respond to ESF Transformer 11 lockout.
5. Respond to EHC fluid leak.
6. Respond to an ATWS.
7. Respond to a failure of SLC squib valves to actuate.
8. Respond to a failure of Fuel Zone Level indication Channel A.

Initial Conditions: Reactor Power is 31%.

INOPERABLE Equipment None Turnover:

The plant is at 31% power during startup. Reactor Recirc pump A has been shifted to fast speed. Power ascension is to continue with shifting Reactor Recirc pump B to fast speed in accordance with IOI 03-1-01-2 step 5.11.5 and SOI 04-1-01-B33.1.

Once Recirc is operating in fast speed at 67Mlm/hr, continue power ascension per 03-1-01-2. There is no out of service equipment and EOOS is green. A Division 1 work week is in effect.

REVISION 3/19/2010 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 1 of 18

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

Shift Reactor Recirc pump B to fast speed (IOI 03-1-01-2 step 5.11.5 and SOI 04-1-01-B33-1 section 4.2) 2 R (ACRO)

Withdraw control rods per Control Rod Movement Sequence Sheet to raise power.

3 di_1d17k612_sw I(BOP)

Respond to FHA Vent Exhaust Rad Monitor Inop failure (ARI 04-1-02-1H13-P601-19A-C9) (Tech Spec 3.3.6.2 &

TR 6.3.1) 4 r21134g C(BOP)

Respond to ESF Transformer 11 lockout (ONEPs 05 02-I-4 and 05-1-02-III-5)(Tech Spec 3.8.1) 5 tc095 C(ACRO)

Respond to a large Turbine EHC system fluid leak (ARI-04-1-02-P680-10A-B4) 6 c11164 @ 45 M (ALL)

Respond to an ATWS (EP-2A/3) 7 c41f004a_d C(BOP) c41f004b_d Respond to failure of SLC squib valves to actuate 8

ltb21n044c_c I(ACRO)

Respond to failure of Fuel Zone Level channel A indication.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 3/19/2010 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 2 of 18

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

- Hydraulic block ATWS occurs. Crew directs installation of EP Attachments 18, 19, and 20 and control rods are inserted by manual scram and/or normal rod insertion. Criteria is to give the highest priority, along with level and pressure control, to insert control rods by manual scram and/or normal rod insertion following installation of EP Attachments 18 and 19 (20 for normal rod insertion).

- ATWS with Reactor Power above 4% or Suppression Pool temperature cannot be maintained below 110°F. Crew will initiate Standby Liquid Control (SLC) with available SLC pumps as indicated by available indications. Criteria is to give the highest priority to start SLC pumps prior to exceeding 110°F Suppression Pool temperature or any primary containment design limits.

- Entry into EP2A step L8. Crew terminates and prevents all injection except boron, CRD, and RCIC per 02-S-01-27 Operations Philosophy.

Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criteria is to give the highest priority to terminate and prevent all injection except boron, CRD, and RCIC until reaching criteria specified in EP2A step L8.

REVISION 3/19/2010 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 3 of 18

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 in.
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%. Plans are to 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 3/19/2010 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 4 of 18

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 z021021_40_45 C(ACRO)

Respond to control rod 40-45 drift in (ONEP 05-1-02-IV-1 sections 2.2/3.2; Tech Spec 3.1.3) 4 e22052 C(BOP) 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 3/19/2010 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 5 of 18

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

- When reactor water level lowers to between -160 (TAF) and -191, the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criteria are to open at least seven SRVs before RPV level drops to -210.

- ECCS fails to initiate on high DW pressure or low RPV Level. Crew arms and depresses the appropriate ECCS MAN INIT pushbutton as evidenced by ECCS ACTUATED annunciator and logic light illuminated and/or manually re-energizes 15AA from ESF Transformer 12. Criteria are that the crew ensures ECCS pumps running and lined up for injection before Reactor pressure decreases to 300 psig.

REVISION 3/19/2010 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 6 of 18

Appendix D Simulator Operation Form ES-D-2 Scenario 3 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 3 Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________

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

1. Lower reactor power to 90% using Recirc Flow Control Valves.
2. Start RHR A in Suppression Pool Cooling.
3. Respond to failure of RHR Heat Exchanger A Bypass valve E12F048A.
4. Respond to trip of SSW A Cooling Tower Fan P41C003A.
5. Respond to failure of Heater Drain Tank level control and trip of both Heater Drain Pumps.
6. Respond to Feedwater Line A rupture in the drywell with inability to isolate.
7. Respond to failure of RCIC to automatically start.
8. Respond to ATWS below 4% power (four control rods stuck out).

Initial Conditions: Reactor Power is 100%.

INOPERABLE Equipment None Turnover:

The plant is at rated power. Reactor power is to be reduced to 90% immediately following turnover in order to perform 06-OP-1C11-M-0001, Control Rod Operability.

When power has been reduced to 90% and before commencing 06-OP-1C11-M-0001, place RHR A in Suppression Pool Cooling to lower Suppression Pool temperature to 80°F. SSW A is in standby. There is no out of service equipment and EOOS is green. A Division 1 work week is in effect.

REVISION 3/19/2010 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 7 of 18

Appendix D Simulator Operation Form ES-D-2 Scenario 3 Event Malf. No. Event Event No. Type* Description 1 R(ACRO)

Lower reactor power to 90% using Recirc Flow Control Valves (06-OP-1C11-M-0001, IOI 03-1 2 Attachment VIII) 2 N(BOP)

Start RHR A in Suppression Pool Cooling. (SOI 04-1-01-E12-1 section 5.2) 3 e12188h C(BOP)

Respond to failure of RHR Heat Exchanger A Bypass valve E12F048A (ARI 04-1-02-1H13-P601-20A-H6, TS 3.6.1.7, 3.6.2.3) 4 p870_1a_b_1 C(BOP) lo_1p41r701h Respond to trip of SSW A Cooling Tower Fan lo_1p41m600 P41C003A (ARI 04-1-02-P870-1A-B1, TS 3.7.1) a_g lo_1p41m600 a_r di_1p41m600 a

5 ltn23n079_a C(ACRO)

Respond to failure of Heater Drain Tank dump (level) control and trip of both Heater Drain Pumps (ONEP 05-1-02-V-5, ARI-04-1-02-P680-1A-A7,A8) 6 fw171a M (ALL) b21f065a_i Respond to Feedwater Line A rupture in the drywell rr063a@4 with inability to isolate (ONEPs 05-1-02-V-7, 05 02-I-1) 7 e51043 I(ACRO)

Respond to failure of RCIC to automatically start (EN-OP-115).

8 z022022_24_ C (ALL) 09 Respond to ATWS below 4% power due to four z022022_40_ control rods stuck out (EP-2A) 57 z022022_56_

25 z022022_08_

41

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 3/19/2010 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 8 of 18

Appendix D Simulator Operation Form ES-D-2 Scenario 3 Critical Tasks

- When it is determined that reactor water level cannot be restored and maintained above -191, the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criteria are to give the highest priority to open at least seven SRVs when reactor water level drops to -191 and available injection systems are incapable of raising reactor water level.

- Reactor pressure decreases to MSCP. Crew commences and slowly raises injection utilizing available EP-2A Table 4 and/or Table 5 systems with RPV level restored and maintained to greater than -191". Criteria are to give the highest priority to restore RPV level greater than -191".

REVISION 3/19/2010 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 9 of 18

Appendix D Scenario Outline Form ES-D-1 Scenario 4 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 4 Op-Test No.: 06/10 Examiners: _________________________ Operators:__________________________

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

1. Withdraw control rods to raise RPV pressure.
2. Respond to a Control Rod drift out.
3. Respond to an IRM B failure upscale.
4. Respond to a failure of the Startup Level Control Valve - closed.
5. Respond to a steam leak in RCIC Steam Piping.
6. Respond to a failure of RCIC to isolate.
7. Respond to a Station Blackout.

Initial Conditions: Reactor Power is 5%.

INOPERABLE Equipment None Turnover:

CREW TURNOVER The plant is at 5% power during startup. Continue control rod withdrawal to support RPV Pressurization to rated pressure. Reactor Feed Pump A is on Startup Level Control. Steam Jet Air Ejector A is out of service. RPV pressure is 400 psig. RPV pressure has been stable for the past hour. 03-1-01-1 is complete to step 6.2.13d.

Control Rod movement is on step 125a There is no out of service equipment, and EOOS is green. A Division 1 work week is in effect.

REVISION 3/19/2010 SCENARIO 4 NUREG 1021 REVISION 9 PAGE 10 of 18

Appendix D Scenario Outline Form ES-D-1 Scenario 4 Event Malf. No. Event Event No. Type* Description 1 R (ACRO)

Withdraw control rod IAW Control Rod Movement Sequence sheet to raise RPV Pressure.

2 Z161161_28_45 C (ACRO)

Respond to Control Rods 28-45 drift out. (ONEP 05 02-IV-1 section 2.3 and 3.2)(Tech Spec 3.1.3) 3 c51004b I (ACRO)

Respond to IRM B Failure Upscale (ARI 04-1-02-1H13-P680-7A-A8; A9) (Tech Spec/TR 3.3.1.1 & 3.3.2.1; TR 3.1.5) 4 fw124 @ 0 ramp C (ACRO) over 150 sec. Respond to Startup Level Control Valve failure full closed (ONEPs 05-1-02-V-7) 5 e51050@ 10 M (ALL)

Respond to a RCIC Steam Leak upstream of E51-F045 (ARI-04-1-02-P601 Various)(EP-4 / EP-2) 6 e51187a C (BOP) e51187b Respond to a failure of RCIC to automatically isolate (ARI 04-1-02-1H13-P601 21A-C1; D1; EP-4; EN-OP-115) 7 r21135 M (ALL) n41140a Respond to a Station Blackout (ONEP 05-1-02-I-4) n41140b rr063b@ 0.2 e22052

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 3/19/2010 SCENARIO 4 NUREG 1021 REVISION 9 PAGE 11 of 18

Appendix D Scenario Outline Form ES-D-1 Scenario 4 Critical Tasks

- A primary system is discharging outside primary containment and area temperatures, radiation levels, or water levels are above max safe values.

Crew shuts down the reactor. Criteria are to give the highest priority to shutdown the reactor when a primary system is discharging outside primary containment and area temperatures, radiation levels, or water levels cannot be maintained below their max safe values.

- Station Blackout has occurred. Crew restores power to at least 1 ESF bus with sufficient systems to maintain the core in a safe shutdown configuration. Criteria are to give the highest priority to align power to at least 1 ESF bus with sufficient equipment to maintain safe shutdown conditions.

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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 HPCS Jockey Pump trip.
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.

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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) di_1e22m611_stop C(BOP) 2 lo_1e22m611_r off Respond to a trip of HPCS Jockey Pump. (ARI 04-lo_1e22m611_g off 1-02-1H13-P601 16A-E4, H5; Tech Spec 3.5.1).

lo_1e22m611_a on lo_1e22ads2 on p601_16a_h_5 on p601_16a_e_4 on 3 n41102 C(ACRO)

Respond to TVR trip from Automatic to Manual (ARI 04-1-02-1H13-P680-9A-C15, SOI 04-1 N40-1 section 5.2) 4 rr012a C(ACRO)

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 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)

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

- Thermal Hydraulic Instability is observed. Crew inserts manual reactor scram as observed by control rods inserted and scram annunciators received. Criteria are to give the highest priority to insert a manual scram.

- Hydraulic block ATWS occurs. Crew directs installation of EP Attachments 18, 19, and 20 and control rods are inserted by manual scram and/or normal rod insertion. Criteria is to give the highest priority, along with level and pressure control, to insert control rods by manual scram and/or normal rod insertion following installation of EP Attachments 18 and 19 (20 for normal rod insertion).

- ATWS with Reactor Power above 4% or Suppression Pool temperature cannot be maintained below 110°F. Crew will initiate Standby Liquid Control (SLC) with available SLC pumps as indicated by available indications. Criteria is to give the highest priority to start SLC pumps prior to exceeding 110°F Suppression Pool temperature or any primary containment design limits.

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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 B/U 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 bus LCC 15BA5.
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.

REVISION 3/9/2010 SCENARIO 6 NUREG 1021 REVISION 9 PAGE 16 of 18

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 r21142v C(BOP)

Respond to trip of bus LCC 15BA5. (ARI 04-1 1H13-P864-1A-F3, ONEP 05-1-02-I-4; SOI 04 01-R21-15; OSP 02-S-01-17; Tech Spec 3.8.7; Various) 5 fw163a @ 5 C(ACRO) ramp to 100 Respond to a loss of Main Condenser Vacuum over 10 (ONEP 05-1-02-V-8) minutes 6 rr063a@ 10 M(ALL) over 2 minutes Respond to a LOCA with reduced injection e22159a 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 3/9/2010 SCENARIO 6 NUREG 1021 REVISION 9 PAGE 17 of 18

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

- When reactor water level lowers to between -160 (TAF) and -191, the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criteria are to open at least seven SRVs before RPV level drops to -210.

- Emergency depressurization is performed. Crew injects with available systems and observes RPV level trend up. Criteria are to give the highest priority to restore and maintain RPV level above -191 using available injection systems..

REVISION 3/9/2010 SCENARIO 6 NUREG 1021 REVISION 9 PAGE 18 of 18

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