ML101890750
| 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 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
- 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
@ 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
- 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
@ 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.
- 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.
- 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.
REVISION 6/10/2010 SCENARIO 5 NUREG 1021 REVISION 9 Rev 2 PAGE 3 of 3
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.
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 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.
REVISION 6/10/2010 SCENARIO 6 NUREG 1021 REVISION 9 Rev 2 PAGE 3 of 3