ML12243A134
| ML12243A134 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/15/2012 |
| From: | Moore C M Operations Branch III |
| To: | Indiana Michigan Power Co |
| Shared Package | |
| ML11354A199 | List: |
| References | |
| ES-301-1 | |
| Download: ML12243A134 (32) | |
Text
DC Cook 2012 NRC Examination Revision 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: DC Cook Date of Examination:
7/23/2012 Examination Level: RO SRO Operating Test Number: NRC RO28 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations M-R 2012 NRC -A1a - SRO Review a Thermal Power Calculation KA 2.1.43 4.1/4.3 Conduct of Operations D-R 2012 NRC - A1b Determine Ultimate Heat Sink Temperature KA 2.1.7 4.4/4.7 Equipment Control P-D-R 2010-A2 2012 NRC - A2 - SRO Review Unit 2 LTOP Verification KA 2.2.42 3.9/4.6 Radiation Control D-S 2012 NRC - A3 Perform A Containment Purge Release K/A 2.3.11 3.8/4
.3 Emergency Procedures/Plan M-R 2012 NRC - A 4 - SRO Prepare Prompt NRC Notification Worksheet K/A 2.4.30 2.7/4.1 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 ( (N)ew or (M)odified from bank ( (P)revious 2 exams (
DC Cook 2012 NRC Examination Revision 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: DC Cook Date of Examination:
7/23/2012 Examination Level: RO SRO Operating Test Number: NRC RO28 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations M-R 2012 NRC - A1a - RO Perform a Thermal Power Calculation KA 2.1.43 4.1/4.3 Conduct of Operations D-R 2012 NRC - A1b Determine Ultimate Heat Sink Temperature KA 2.1.7 4.4/4.7 Equipment Control P-D-R 2008-A2 2012 NRC - A2 - RO Perform Unit 2 LTOP Verification KA 2.2.37 3.6/4.6 Radiation Control D-S 2012 NRC - A3 Perform A Containment Purge Release K/A 2.3.11 3.8/4.3 Emergency Procedures/Plan 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 ( (N)ew or (M)odified from bank ( (P)revious 2 exams (
DC Cook 2012 NRC Examination Revision 0 ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2 Facility:
DC Cook Date of Examination:
7/23/2012 Exam Level: RO SRO-I SRO-U Operating Test No.: NRC RO2 8 Control Room Systems
-I); (2 or 3 for SRO
-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a. 2012 NRC
-SIM01 - Perform RCCA Operability Check KA 014 A4.02 3.4/3.2 D-S 1 b. 2012 NRC
-SIM02 - Isolate SI Accumulators KA 006 A4.02 4.0/3.8 M-EN-L-S 2 c. 2012 NRC
-SIM03 - Perform SG Stop Valve Dump Valve Test KA 039 K4.05 3.7/3.7 D-P-S 2010 4S d. 2012 NRC
-SIM04 - Place Hydrogen Recombiner In Service KA 028 A4.01 4.0/4.0 D-L-S 5 e. 2012 NRC
-SIM05 - Restore RCP Bus 1A Power to Bus T11A KA 062 A4.07 3.1/3.1 D-EN-L-P-S 2008 6 f. 2012 NRC
-SIM06 - Control Room Vent Alignment for Unit 2 SI KA 072 A3.01 2.9/3.1 D-EN-S 7 g. 2012 NRC
-SIM07 - Respond to a Unit 2 Plant Air Header Leak (Alt. Path) KA 078 A3.01 3.1/3.2 A-N-S 8 h. 2012 NRC
-SIM08 - Respond to R
-19 SG Blowdown RMS Hi Alarm (Alt. Path) KA 068 A2.04 3.3/3.3 A-N-S 9 In-Plant Systems
-I); (3 or 2 for SRO
-U) i. 2012 NRC
-INP01 - Locally Control VCT Makeup Valve (QRV
-400) KA APE 068 AA1.08 4.2/4.2 E-D-P-R 2010 2 j. 2012 NRC
-INP02 - Restore an 'N' Train Battery Charger (Alt. Path) KA APE 058 AA1.01 3.4/3.5 A-D-E-R 6 k. 2012 NRC
-INP03 - Response to Waste Gas Panel Alarm
- Tk Full (Alt. Path) KA 071 A4.14 2.8/3.0 A-D-R 9 @ 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.
-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 - / - /
DC Cook 2012 NRC Examination Revision 0 ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2 Facility:
DC Cook Date of Examination:
7/23/2012 Exam Level: RO SRO-I SRO-U Operating Test No.: NRC RO2 8 Control Room Systems
-I); (2 or 3 for SRO
-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a. 2012 NRC
-SIM01 - Perform RCCA Operability Check KA 014 A4.02 3.4/3.2 D-S 1 b. 2012 NRC
-SIM02 - Isolate SI Accumulators KA 006 A4.02 4.0/3.8 M-EN-L-S 2 c. d. 2012 NRC
-SIM04 - Place Hydrogen Recombiner In Service KA 028 A4.01 4.0/4.0 D-L-S 5 e. 2012 NRC
-SIM05 - Restore RCP Bus 1A Power to Bus T11A KA 062 A4.07 3.1/3.1 D-EN-L-P-S 2008 6 f. 2012 NRC-SIM06 - Control Room Vent Alignment for Unit 2 SI KA 072 A3.01 2.9/3.1 D-EN-S 7 g. 2012 NRC
-SIM07 - Respond to a Unit 2 Plant Air Header Leak (Alt. Path) KA 078 A3.01 3.1/3.2 A-N-S 8 h. 2012 NRC
-SIM08 - Respond to R
-19 SG Blowdown RMS Hi Alarm (Alt. Path) KA 068 A2.04 3.3/3.3 A-N-S 9 In-Plant Systems
-I); (3 or 2 for SRO
-U) i. 2012 NRC
-INP01 - Locally Control VCT Makeup Valve (QRV
-400) KA APE 068 AA1.08 4.2/4.2 E-D-P-R 2010 2 j. 2012 NRC
-INP02 - Restore an 'N' Train Battery Charger (Alt. Path) KA APE 058 AA1.01 3.4/3.5 A-D-E-R 6 k. 2012 NRC
-INP03 - Response to Waste Gas Panel Alarm
- Tk Full (Alt. Path) KA 071 A4.14 2.8/3.0 A-D-R 9 @ 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.
-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 - / - /
DC Cook 2012 NRC Examination Revision 0 ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2 Facility:
DC Cook Date of Examination:
7/23/2012 Exam Level: RO SRO-I SRO-U Operating Test No.: NRC RO2 8 Control Room Systems
-I); (2 or 3 for SRO
-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a. b. 2012 NRC
-SIM02 - Isolate SI Accumulators KA 006 A4.02 4.0/3.8 M-EN-L-S 2 c. d. e. f. 2012 NRC
-SIM06 - Control Room Vent Alignment for Unit 2 SI KA 072 A3.01 2.9/3.1 D-EN-S 7 g. 2012 NRC
-SIM07 - Respond to a Unit 2 Plant Air Header Leak (Alt. Path) KA 078 A3.01 3.1/3.2 A-N-S 8 h. In-Plant Systems
-I); (3 or 2 for SRO-U) i. j. 2012 NRC
-INP02 - Restore an 'N' Train Battery Charger (Alt. Path) KA APE 058 AA1.01 3.4/3.5 A-D-E-R 6 k. 2012 NRC
-INP03 - Response to Waste Gas Panel Alarm
- Tk Full (Alt. Path) KA 071 A4.14 2.8/3.0 A-D-R 9 @ 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.
-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 - / - /
ES-301 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 07/23/2012 Operating Test No.:
Crew 1 A P P L I C A N T E V E N T T Y P E Scenarios NRC2012-0 1 NRC20 12-02 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SR O-I SRO-U RX 1 0 0 1 0 0 0 0 0 0 0 0 2 1 1 0 NOR 1 0 0 1 0 0 0 0 0 0 0 0 2 1 1 1 I/C 4 0 0 4 0 0 0 0 0 0 0 0 8 4 4 2 MAJ 1 0 0 1 0 0 0 0 0 0 0 0 2 2 2 1 TS 3 0 0 4 0 0 0 0 0 0 0 0 7 0 2 2 RO SRO-I SRO-U RX 1 0 0 0 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 0 0 1 0 0 0 0 0 0 1 1 1 1 I/C 2 0 0 0 2 0 0 0 0 0 0 4 4 4 2 MAJ 1 0 0 0 1 0 0 0 0 0 0 2 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 1 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 1 0 0 0 0 0 0 0 0 0 1 1 1 1 I/C 0 0 2 0 2 0 0 0 0 0 0 0 4 4 4 2 MAJ 0 0 1 0 1 0 0 0 0 0 0 0 2 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 NOR 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 I/C 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 2 MAJ 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 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 Sectio n 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 applicant's competence count toward the minimum requirements specified for the applicant's license level in the right
-hand columns
.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 07/23/2012 Operating Test No.:
Crew 2 A P P L I C A N T E V E N T T Y P E Scenarios NRC2012-0 1 NRC20 12-0 3 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SR O-I SRO-U RX 1 0 0 1 0 0 0 0 0 0 0 0 2 1 1 0 NOR 1 0 0 1 0 0 0 0 0 0 0 0 2 1 1 1 I/C 4 0 0 4 0 0 0 0 0 0 0 0 8 4 4 2 MAJ 1 0 0 2 0 0 0 0 0 0 0 0 3 2 2 1 TS 3 0 0 3 0 0 0 0 0 0 0 0 6 0 2 2 RO SRO-I SRO-U RX 1 0 0 0 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 0 0 1 0 0 0 0 0 0 1 1 1 1 I/C 2 0 0 0 2 0 0 0 0 0 0 4 4 4 2 MAJ 1 0 0 0 2 0 0 0 0 0 0 3 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 1 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 1 0 0 0 0 0 0 0 0 0 1 1 1 1 I/C 0 0 2 0 2 0 0 0 0 0 0 0 4 4 4 2 MAJ 0 0 1 0 2 0 0 0 0 0 0 0 3 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 NOR 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 I/C 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 2 MAJ 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 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 Sectio n 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 applicant's competence count toward the minimum requirements specified for the applicant's license level in the right
-hand columns
.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 07/23/2012 Operating Test No.:
Crew 3 A P P L I C A N T E V E N T T Y P E Scenarios NRC2012-0 1 NRC20 12-0 4 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SR O-I SRO-U RX 1 0 0 1 0 0 0 0 0 0 0 0 2 1 1 0 NOR 1 0 0 1 0 0 0 0 0 0 0 0 2 1 1 1 I/C 4 0 0 4 0 0 0 0 0 0 0 0 8 4 4 2 MAJ 1 0 0 1 0 0 0 0 0 0 0 0 2 2 2 1 TS 3 0 0 3 0 0 0 0 0 0 0 0 6 0 2 2 RO SRO-I SRO-U RX 1 0 0 0 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 0 0 1 0 0 0 0 0 0 1 1 1 1 I/C 2 0 0 0 2 0 0 0 0 0 0 4 4 4 2 MAJ 1 0 0 0 1 0 0 0 0 0 0 2 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 1 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 1 0 0 0 0 0 0 0 0 0 1 1 1 1 I/C 0 0 2 0 2 0 0 0 0 0 0 0 4 4 4 2 MAJ 0 0 1 0 1 0 0 0 0 0 0 0 2 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 NOR 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 I/C 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 2 MAJ 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 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 Sectio n 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 applicant's competence count toward the minimum requirements specified for the applicant's license level in the right
-hand columns
.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 07/23/2012 Operating Test No.:
Crew 4 A P P L I C A N T E V E N T T Y P E Scenarios NRC2012-02 NRC2012-03 NRC2012-04 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U RX 1 0 0 0 1 0 1 0 0 0 0 0 3 1 1 0 NOR 1 0 0 0 0 0 1 0 0 0 0 0 2 1 1 1 I/C 4 0 0 0 2 0 4 0 0 0 0 0 10 4 4 2 MAJ 1 0 0 0 2 0 1 0 0 0 0 0 4 2 2 1 TS 4 0 0 0 0 0 3 0 0 0 0 0 7 0 2 2 RO SRO-I SRO-U RX 0 1 0 1 0 0 0 0 0 0 0 0 2 1 1 0 NOR 0 0 0 1 0 0 0 0 1 0 0 0 2 1 1 1 I/C 0 2 0 4 0 0 0 0 1 0 0 0 7 4 4 2 MAJ 0 1 0 2 0 0 0 0 1 0 0 0 4 2 2 1 TS 0 0 0 3 0 0 0 0 0 0 0 0 3 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 1 0 0 0 0 1 1 1 0 NOR 0 0 1 0 0 1 0 0 0 0 0 0 2 1 1 1 I/C 0 0 2 0 0 2 0 2 0 0 0 0 6 4 4 2 MAJ 0 0 1 0 0 2 0 1 0 0 0 0 4 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 NOR 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 I/C 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 2 MAJ 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 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 applicant's competence count toward the minimum requirements specified for the applicant's license level in the right
-hand columns.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 07/23/2012 Operating Test No.:
Crew 5 A P P L I C A N T E V E N T T Y P E Scenarios NRC2012-0 2 NRC2012-0 3 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U RX 1 0 0 0 1 0 0 0 0 0 0 0 2 1 1 0 NOR 1 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 I/C 4 0 0 0 2 0 0 0 0 0 0 0 6 4 4 2 MAJ 1 0 0 0 2 0 0 0 0 0 0 0 3 2 2 1 TS 4 0 0 0 0 0 0 0 0 0 0 0 4 0 2 2 RO SRO-I SRO-U RX 0 1 0 0 0 0 0 0 0 0 0 0 1 1 1 0 NOR 0 0 0 0 0 1 0 0 0 0 0 0 1 1 1 1 I/C 0 2 0 0 0 2 0 0 0 0 0 0 4 4 4 2 MAJ 0 1 0 0 0 2 0 0 0 0 0 0 3 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 NOR 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 I/C 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 2 MAJ 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 2 2 RO SRO-I SRO-U RX 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 NOR 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 I/C 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 2 MAJ 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 TS 0 0 0 0 0 0 0 0 0 0 0 0 0 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 applicant's competence count toward the minimum requirements specified for the applicant's license level in the right
-hand columns.
Appendix D Scenario Outline Form ES-D-1 Revision 0 Facility: _Cook Plant Unit 1 & Unit 2_ Scenario No
- NRC2012-01 Op-Test No.: Crews 1, 2, & 3 Examiners:
_________________
Operators: ___________________
_________________
___________________
_________________
_______________
____ Initial Conditions:
IC- , 1-3% pwr, ppm Boron, GWD, °F Tavg, CBD @ steps, 0 MW Turnover: Start the Middle Condensate Booster Pump , Raise Power to 3
-4% for MFW Pump Start
-up Event No. Malf. No. Event Type* Event Description 1 N-BOP Start the Middle Condensate Booster Pump
. 2 R-RO Raise Power to 3-4% Power. 3 QLC451 @ 100 I-RO TS VCT Level Transmitter (QLC
-451) Fails HIGH. 4 ED07A C-RO TS PZR HTR Transformer Fails (11PHA Fails). 5 CLC10 to 0%
I-BOP Hotwell Level Transmitter CLC-10 Fails LOW.
6 RX11D @100%
C-BOP TS SG PORV Controller Failure
. 7 ED01 ED25 E D 0 3A EG06 B M Loss of All AC Power
. 1CD EDG Trip. 8 EG08A C-BOP 1AB EDG Speed Governor Failure. 9 FW48C C-BOP TD AFW Pump Fails to AUTO start
. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Revision 0 The BOP is directed to start the Middle Condensate Booster Pump (CBP). The operator will place the Middle CBP in service in accordance with the normal operating procedure.
The Crew is directed to raise power to 3-4% for MFW Pump Start
-up. The third event will involve the VCT Level instrument (QLC
-451) failing HIGH. This will result in the VCT High Level alarm. The RO will be required to perform a manual makeup to the RCS. The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
A failure of the PZR HTR Bus 11PHA will occur. The PZR SCR heater control will need to be transferred to 11PHC. The crew should also refer to Technical Specifications
. Then the Hotwell Level Transmitter CLC
-10 fails L OW. The low failure will cause the Condensate Makeup valve (CRV
-55) to fully open and the Condensate Letdown Valve (CRV
-155) to fully close causing a rise in actual hotwell level. The BOP will be required to take manual control of the Hotwell Level Controller and return hotwell level to a normal band. The non failed hotwell level input may be selected for subsequent auto control. The next event will involve the failure of the SG #14 PORV Controller. Th e controller will fail causing PORV 1
-MRV-243 to fully open. This will also cause Reactor power to slightly rise. The BOP will need to take manual action to close the PORV and the US will need to declare the associated radiation monitor inoperable.
The Major event is a loss of all AC power. The reactor will trip. Failure of the EDGs will require entry into ECA-0.0 actions. Failure of the TDAFW Pump to auto start will require a manual start to restore feedwater flow. The crew will be required to take actions to restore Emergency Power (EP). The crew should transition to ECA-0.1 once power has been restored to one Safeguards Bus. The scenario will terminate when the crew has restored emergency power and transitioned to ECA
-0.1 or ECA
-0.2. Critical Tasks Establish AFW (Start TDAFWP)
Restore Emergency Power to Safeguards Bus
Procedures E-0, Reactor Trip or Safety Injection ECA-0.0, Loss of All AC Power
Revision 0 Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: NRC2012-02 Op-Test No.: Crews 1, 4, & 5 Examiners:
_________________
Operators:
___________________
_________________
___________________
_________________
___________________
Initial Conditions: IC
- ,100% pwr; ppm Boron, GWD, °F Tav g, CBD @ steps, 1107 MW Turnover: Lower SI Accumulator Pressure and then lower power to 95% for water box cleaning Event No. Malf. No. Event Type* Event Description 1 N BOP Lower SI Accumulator #3 Pressure to Within Notification Limits.
2 R RO Lower Turbine and Reactor Power
. 3 NLP151 @ 0% I-RO TS Controlling Pressurizer Level Channel (NLP
-151) Fails LOW. 4 RH09B C-BOP T S West RHR Pump Suction Strainer Cap Leak. 5 RC17C to 50% C-RO TS Pressurizer PORV NRV
-153 Open s. 6 FFC220 @ 4E6 I-BOP TS SG #2 Feed Flow Instrument (FFC
-220) Fails HIGH.
7 RC01D to 20% over 5 min ramp M Loop 4 Cold Leg Primary Coolant System Leak I n side Containment.
8 101ICM305 C-ALL Loss of Recirc Sump Capability. 9 RP13A RP13B RP14A C-BOP Phase A Train A & B Fails to Automatically Actuate. Phase A Train A Fails to Manually Actuate. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Event Summary (NRC2012-02) Revision 0 The BOP is directed to Lower SI Accumulator Pressure to within limits. After the SI Accumulator Pressure has been restored, the crew is required to respond to various events.
If required, the crew will be directed by the Shift Manager to lower power.
While reducing power, the controlling Pressurizer Level channel NLP
-151 fails LOW. Charging flow control valve (QRV
-251) opens to raise charging flow which causes actual pressurizer level to rise. Pressurizer water level low alarm comes in, a letdown isolation occurs, and all pressurizer heaters will de
-energize. The RO will need to take manual control of the Pressurizer Level controller and restore level. The crew should implement the AOP, stabilize the plant, trip bistables, select an operable channel, and restore level control to auto.
While the RO is restoring letdown, leakage on the RHR pump suction piping will require the BOP to isolate the RHR pump.
After the Crew has addressed the Tech Specs for RHR, the Pressurizer PORV NRV153 will fail partially open. This results in Actual RCS pressure lowering. The RO will be required to take manual actions to isolate the PORV (close block valve) and restore normal pressure conditions.
When the RCS Pressure has been restored a HIGH failure of #
2 Steam Generator Feed Flow instrument (FFC-220) will occur. This will result in a lowering feedwater flow to #2 SG with corresponding SG level lowering. The BOP will be required to take manual control of FRV
-220. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
When the SG level has stabilized, a Large Break LOCA will occur requiring a Reactor Trip and SI. On the Trip, the breaker for IC M-305 will be discovered to be without power, resulting in a Loss of Emergency Coolant Recirculation capability. On the SI, the auto Phase A Isolation will also fail requiring manual alignment of Phase A equipment. The crew should progress through E
-0, E-1, and ECA-1.1. The scenario will terminate once a transition has been made back to E-1.
Critical Tasks Initiate/Isolate Phase A Isolate RWST Outflow Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant ECA-1.1, Loss of Emergency Coolant Recirculation
Revision 0 Appendix D Scenario Outline Form ES-D-1 Facility:
Cook Plant Unit 1 & Unit 2 Scenario No.:
NRC2012-03 Op-Test No.: Crews 2, 4, & 5 Examiners:
_________________
Operators:___________________
_________________
___________________
_________________
___________________
Initial Conditions
- IC- , 80 % pwr, ppm Boron, GWD, °F Tav g, CBD @ steps, MW Turnover: Swap TACW Pumps, West CCP is OOS for Oil Change this shift. Pump has been OOS for 2 Hours. Event No. Malf. No. Event Type* Event Description 1 N-BOP Swap Turbine Aux Cooling Water (TACW) Pump s. 2 NTP 240 @ 6 2 0 I-RO TS RCS Cold Leg Temperature Instrument (NTP
-240) Fails HIGH
. 3 MFC1 3 0 @ 4E6 over 20 sec I-BOP TS #3 SG Steam Flow Transmitter (MFC
-1 30) Fails HIGH. 4 101BAP1 C-RO TS Boric Acid Pump Fails
. 5 R-RO Lower Reactor Power and Turbine Load (Optional)
. 6 FW05A C-BOP East Main Feed Pump Trip
. 7 FW05B M West Main Feed Pump Trip
. 8 MS01D @ 20 2 min Ramp M Steam Line Break Inside Containment (#
3 SG). 9 a RP16B RP17B C-RO CTS Train B
- Fails to Actuate (AUTO/MANUAL)
. 9b RP19J C-RO RPS Relay K626-X3 Failure (East CTS Pump Fails to Start). * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Event Summary (NRC2012-03) Revision 0 The Crew is directed to start West TACW pump and stop East TACW Pump. The RCS Loop 4 Cold Leg Temperature instrument (NTP
-240) fails HIGH. This will result in the AUTO insertion of control rods and a lower trip setpoint value for OPT and OTT. The RO will be required to take manual control of rods to stop insertion. The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
After the crew has addressed the RCS temperature instrument
, the #3 SG Steam Flow instrument (MFC
-1 30) fail s HIGH. This will result in the opening of #
-2 30) to raise feedwater flow. The BOP will be required to take manual control and regulate FRV
-2 30. The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
The running Boric Acid Pump Breaker will trip
. This results in a temporary loss of VCT make
-up capability. The RO will be required to take manual actions to align the standby Boric Acid Pump and start it in slow
s peed. Next a rapid power reduction is performed based on a report of an Oil leak on the East Main feed Pump.
(Optional if reactivity change is required
- note next event also involves a reactivity change which may be combined with this reactivity change)
A trip of the East Main Feed Pump will result in a rapid power reduction to less than 60%
(if not already performed.) The RO will be required to control reactivity while the BOP monitors SG levels.
The main event will involve a trip of the remaining MFW pump. A Steam Line Break will cause SG #3 to blow down inside Containment. The BOP will be required to isolate the main steam lines.
A SSPS failure results in failure of Train B (West) CTS and a failure of the K626-X3 relay which prevents the auto start of the East CTS pump. The crew will perform the actions of E
-0 to verify the SI actions and then transition to E-2. The scenario will terminate when the crew has completed isolation of the faulted SG in E-2. Critical Tasks Actuate Containment Spray Isolate the Faulted Steam Generator Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation
Revision 0 Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: NRC2012-04 Op-Test No.: Crews 3 & 4 Examiners:
_________________
Operators:___________________
_________________
___________________
___________
______ ___________________
Initial Conditions:
IC- , 45-50% pwr; ppm Boron, GWD, °F Tavg, CBD @ steps, MW Turnover:
Complete shutdown of FW Pump for repairs.
NRV-153 PZR PORV is isolated for leakage. Event No. Malf. No. Event Type* Event Description 1 N-BOP Complete Shutdown of Idle FW Pump.
2 NI10 B to 0% I-RO TS Power Range Channel NI
-4 2 fails LOW. 3 MPP240 to 1200 over 10 Sec I-BOP TS SG Pressure Channel MPP
-240 Fails HIGH. 4 RC24D to 50% C-RO TS SG No. 4 Tube Leak of 5 gpm Requiring Shutdown
. 5 R-RO Shutdown the Reactor
. 6 RX24G to 99% C-BOP FRV-240 Feedwater Control Valve Controller Fails OPEN in Auto.
7 RC23D to 60% (400 gpm) Ramp Time 5:00 Min M SG No. 4 Tube Rupture
. 8a 101XCR101 101XCR 103 Global C-BOP Train B Instrument Air to Containment XCR
-101 & XCR 103 Failure(Fail to Reopen After SI Reset)
. 8b RC17B 0% - Preload C-RO PZR PORV NRV
-152 Fails to Open
. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Event Summary (NRC2012-04) Revision 0 The plant is at 50% power and the BOP is directed to complete the shutdown of the idle FW pump.
After the crew completed the FW pump shutdown, a failure of the Power Range NI
-4 2 will occur. The RO should identify the NI
-4 2 failure. The crew will need to address this failure with the Abnormal Operating Procedure and address Technical Specifications.
The next event will involve the SG Pressure Channel MPP
-240 fails high. The BOP will be required to take manual control SG 4 Feedwater Regulating Valve FRV
-240 to stabilize level. The crew will address the failure with the Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore automatic control.
After the pressure channel; a SG 4 Tube Leakage of 5 gpm, will require a shutdown per the Abnormal Operating Procedure.
After the crew has begun the shutdown, the Feed Regulating Valve FRV
-240 on SG 4 will fail to 99% in Auto. The BOP will need to take manual control and maintain SG level during the ramp.
The SG tube leak will become worse requiring a Reactor Trip and Safety Injection. The crew should manually trip the reactor and initiate SI. The crew will progress through E
-0 and transition to E
-3. The crew will progress through E
-3 and discover that Instrument Air can not be restored to Containment because the Train B Isolation Valves will not re
-open. This will complicate the RCS Depressurization. The scenario will be terminated once the RCS has been depressurized and the SI pumps have been stopped.
Critical Tasks Isolate Ruptured SG RCS Cooldown Depressurize RCS
Procedures E-0 Reactor Trip or Safety Injection E-3 Steam Generator Tube Rupture