ML101890750

2010-06-Final-Operating Test Outlines

ML101890750
Person / Time
Site:	Grand Gulf
Issue date:	06/25/2010
From:	NRC Region 4
To:
References
50-416/10-301
Download: ML101890750 (13)

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 (see Note)

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) (N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected)

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:

6/10 Administrative Topic (see Note)

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

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

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.

• 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)

E S-301 Control Room/In-Plant Systems Outline Form ES-301-25/6/2010 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 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

@ (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 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:

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.

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 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.

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.

Event Type* Event 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 e22053 C(SS) 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 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

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

initiate (EN-OP-115) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

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.

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 Divis ion 1 work week is in effect.

REVISION 6/10/2010 SCENARIO 6 NUREG 1021 REVISION 9Rev 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).

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) (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

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

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

- Restore and maintain RPV level above

-191" using available injection systems.