ML20302A251
| ML20302A251 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/26/2020 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML20302A251 (570) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 6/01/2020 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*
Conduct of Operations ADM-114, Manually Calculate D, R
[KA: G2.1.43 (4.1/4.3)] Shutdown Margin (25 min)
Conduct of Operations ADM-116, Determine Time for SFP to M, R
[KA: G2.1.25 (3.9/4.2)] Reach 200°F (20 min)
Equipment Control ADM-204, Perform SG Downcomer
[KA: G2.2.12 (3.7/4.1)] D, R Temperature Surveillance (15 min)
Radiological Control ADM-307, 1RIA-40 Setpoint Calculation
[KA: G2.3.5 (2.9/2.9)] N, S and Adjustment (25 min)
Emergency Plan N/A NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and 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 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 6/01/2020 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*
Conduct of Operations ADM-S111, Manually Calculate
[KA: G2.1.43 (4.1/4.3)] M, R Shutdown Margin and Determine any (30 min) Required Actions Conduct of Operations ADM-S112, Manually Calculate Core
[KA: G2.1.25 (3.9/4.2)] D, R Tilt Due to Loss of the OAC and (35 min) Determine Any Required Actions and Completion Times Equipment Control Admin-S203, Complete Plant
[KA: G2.2.18 (2.6/3.9)] D, R Configuration Sheet (Time to Core Boil)
(20 min) and Determine Any Required Actions Radiological Control ADM-S301, Determine RIA Setpoints
[KA: G2.3.6 (2.0/3.8)] D, R and Approval Level Required for GWD (25 min) Tank Release Emergency Plan
[KA G2.4.38 (2.4/4.4)] Admin-S407, Determine the M, R (15 min) Appropriate Emergency Action Level NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and 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 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 06/01/2020 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function
- a. RO-P404a, Align ECCS Suction to Emergency Sump EOP Encl. 5.12 (ECCS Suction Swap to RBES) A, EN, D, L, 3
[KA: EPE011 EA1.11 (4.2/4.2)] (10 min) S
- b. RO-607, Alignment of CT-5 per AP/48 N, S 6 AP/0/A/1700/048 (Loss of a Startup Transformer)
[KA: SYS062 A2.05 (2.9/3.3*)] (10 min)
- c. RO-306a, Perform Rule 5 (Main Steam Line Break)
A, EN, M, L, 4P EOP Rule 5 (Main Steam Line Break)
S
[KA: BW/E05 EA1.1 (4.2/4.2)] (10 min)
- d. RO-105, Perform Control Rod Movement PT for Grp 1 D, S 1 PT/1/A/0600/015 Encl. 13.2 (Control Rod Movement at Power)
[KA: SYS001 A4.08 (3.7/3.4)] (10 min)
[KA: SYS061 A2.04 (3.4/3.8)] (6 min)
[KA: SYS029 A2.03 (2.7/3.1)] (15 min)
[KA: APE069 AA1.01 (3.5/3.7)] (15 min)
- h. RO-203, Pressure Makeup to CFT D, S 2 OP/1/A/1104/001 Encl. 4.7 (Pressure Makeup to CFTs Using Nitrogen)
[KA: SYS006 A1.13 (3.5/3.7)] (10 min)
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. AO-501, Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl. 5,2 (Placing RB Hydrogen Analyzers in Service)
[KA: SYS028 A4.03 (3.1/3.3)] (12 min)
- j. AO-S404a, MS-87, MS-126 & MS-129 Isolation A, E, D, L 4S AP/0/A/1700/025 Encl. 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
[KA: SYS039 A4.01 (2.9/2.8)] (15 min)
- k. AO-802, Isolate HPSW and LPSW During an Auxiliary E, M 8 Building Flood AP/3/A/1700/030 (Auxiliary Building Flood) Enclosures 5.1 (HPSW AB Flood) and 5.2 (LPSW AB Flood)
[KA: BW/A07 AA2.2 (3.3/3.7)] (15 min)
@ 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/ 1/ 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 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 06/01/2020 Exam Level: RO SRO-I X SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function
- a. RO-P404a, Align ECCS Suction to Emergency Sump EOP Encl. 5.12 (ECCS Suction Swap to RBES) A, EN, D, L, 3
[KA: EPE011 EA1.11 (4.2/4.2)] (10 min) S
- b. RO-607, Alignment of CT-5 per AP/48 N, S 6 AP/0/A/1700/048 (Loss of a Startup Transformer)
[KA: SYS062 A2.05 (2.9/3.3*)] (10 min)
- c. RO-306a, Perform Rule 5 (Main Steam Line Break)
A, EN, M, L, 4P EOP Rule 5 (Main Steam Line Break)
S
[KA: BW/E05 EA1.1 (4.2/4.2)] (10 min)
- d. RO-105, Perform Control Rod Movement PT for Grp 1 D, S 1 PT/1/A/0600/015 Encl. 13.2 (Control Rod Movement at Power)
[KA: SYS001 A4.08 (3.7/3.4)] (10 min)
[KA: SYS061 A2.04 (3.4/3.8)] (6 min)
[KA: SYS029 A2.03 (2.7/3.1)] (15 min)
[KA: APE069 AA1.01 (3.5/3.7)] (15 min)
- h. N/A
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. AO-501, Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl. 5,2 (Placing RB Hydrogen Analyzers in Service)
[KA: SYS028 A4.03 (3.1/3.3)] (12 min)
- j. AO-S404a, MS-87, MS-126 & MS-129 Isolation A, E, D, L 4S AP/0/A/1700/025 Encl. 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
[KA: SYS039 A4.01 (2.9/2.8)] (15 min)
- k. AO-802, Isolate HPSW and LPSW During an Auxiliary E, M 8 Building Flood AP/3/A/1700/030 (Auxiliary Building Flood) Enclosures 5.1 (HPSW AB Flood) and 5.2 (LPSW AB Flood)
[KA: BW/A07 AA2.2 (3.3/3.7)] (15 min)
@ 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/ 1/ 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 ILT 20-1 NRC Exam Facility: Oconee Nuclear Station Date of Examination: 06/01/2020 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function
- a. RO-P404a, Align ECCS Suction to Emergency Sump EOP Encl. 5.12 (ECCS Suction Swap to RBES) A, EN, D, L, 3
[KA: EPE011 EA1.11 (4.2/4.2)] (10 min) S
- b. RO-607, Alignment of CT-5 per AP/48 N, S 6 AP/0/A/1700/048 (Loss of a Startup Transformer)
[KA: SYS062 A2.05 (2.9/3.3*)] (10 min)
- c. RO-306a, Perform Rule 5 (Main Steam Line Break)
A, EN, M, L, 4P EOP Rule 5 (Main Steam Line Break)
S
[KA: BW/E05 EA1.1 (4.2/4.2)] (10 min)
- d. N/A
- e. N/A
- f. N/A
- g. N/A
- h. N/A
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. AO-501, Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl. 5,2 (Placing RB Hydrogen Analyzers in Service)
[KA: SYS028 A4.03 (3.1/3.3)] (12 min)
- j. AO-S404a, MS-87, MS-126 & MS-129 Isolation A, E, D, L 4S AP/0/A/1700/025 Encl. 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
[KA: SYS039 A4.01 (2.9/2.8)] (15 min)
- k. N/A
@ 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/ 1/ 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
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE008 AK3.05 - Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)
QUESTION 1 B Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: (CFR 41.5,41.10 / 45.6 / 45.13)
ECCS termination or throttling criteria ..............................
Given the following Unit 1 conditions:
Time = 1200:
Reactor power = 100%
BOTH Main FDW Pumps trip PORV opens Time = 1205:
Reactor power = 26% slowly lowering PORV has failed open
- 1) In accordance with Rule 6 (HPI), the MAXIMUM power level at which HPI can be throttled is __(1)__.
- 2) The reason power level is used to determine if throttling HPI is appropriate is that it ensures __(2)__.
Which ONE of the following completes the statements above?
A. 1. 5%
- 2. Boron addition continues until power is less than 5%
B. 1. 1%
- 2. Boron addition continues until power is less than 1%
C. 1. 5%
- 2. sufficient core cooling exists until power level is low enough that HPI Forced cooling can remove the heat D. 1. 1%
- 2. sufficient core cooling exists until power level is low enough that HPI Forced cooling can remove the heat Monday, March 16, 2020 Page 1 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 1 B General Discussion Answer A Discussion Incorrect.
First part is incorrect. Plausible because 5% is the power level used in IMAs to determine if entry into Rule 1 is required.
Second part is correct. Not throttling HPI before power is <1% ensures continued Boron addition which will ensure adequate SDM.
Answer B Discussion Correct.
First part is correct. Per Rule 6 (HPI) with HPI Cooling NOT in progress ALL WR NIs must be less than or equal to 1%.
Second part is correct. Not throttling HPI before power is <1% ensures continued Boron addition which will ensure adequate SDM.
Answer C Discussion Incorrect.
First part is incorrect. Plausible because 5% is the power level used in IMAs to determine if entry into Rule 1 is required.
Second part is incorrect. Plausible because HPI is not being used as the source of cooling but reactivity control. The candidate may have a misconception that we do want to get power within the heat removal capability of the HPI system.
Answer D Discussion Incorrect.
First part is correct. Per Rule 6 (HPI) with HPI Cooling NOT in progress ALL WR NIs must be less than or equal to 1%.
Second part is incorrect. Plausible because HPI is not being used as the source of cooling but reactivity control. The candidate may have a misconception that we do want to get power within the heat removal capability of the HPI system.
Basis for meeting the KA Question requires knowledge of Rule 6 (HPI) and when HPI may be throttled for Pressurizer Vapor Space Accident. The failed open PORV meets the Pressurizer Vapor Space Accident part of the K/A.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 39 Q2 Development References Student References Provided ILT 39 Q2 EAP-UNPP Obj 10, 12 EAP-UNPP Attach 2 (Rule 6)
APE008 AK3.05 - Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)
Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: (CFR 41.5,41.10 / 45.6 / 45.13)
ECCS termination or throttling criteria ..............................
Remarks/Status Monday, March 16, 2020 Page 2 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination EPE011 EA1.02 - Large Break LOCA QUESTION 2 C Ability to operate and monitor the following as they apply to a Large Break LOCA: (CFR 41.7 / 45.5 / 45.6)
Reflux boiling sump level indicators ................................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
Current conditions:
SBLOCA occurs 1A and 1B SGs at the LOSCM setpoint
- 1) In order for boiler-condenser mode of heat transfer to occur, the RCS primary side water level will be __(1)__ the SG secondary side water level.
- 2) Based on the attached CETC trend, boiler-condenser heat transfer __(2)__
occurring.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED A. 1. above
- 2. is B. 1. above
- 2. is NOT C. 1. below
- 2. is D. 1. below
- 2. is NOT Monday, March 16, 2020 Page 3 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 2 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because it would be correct if asking about the secondary side water level as compared to the primary side water level.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because it would be correct if asking about the secondary side water level as compared to the primary side water level.
Second part is incorrect. Plausible for the candidate to think that boiler-condenser heat transfer is not occurring since CETCs are both rising and lowering.
Answer C Discussion CORRECT. For boiler-condenser heat transfer to occur, the primary side water level must be below the secondary side water level. The CETC indication on the provided reference is rising and lowering (saw tooth pattern), however the overall trend is lowering which indicates boiler-condenser heat transfer is occurring.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible for the candidate to think that boiler-condenser heat transfer is not occurring since CETCs are both rising and lowering.
Basis for meeting the KA Per NRC Chief on 1/03/20, a question concerning indications of boiler-condenser heat transfer/reflux boiling (i.e. handout with CETC saw tooth pattern) will be permissable to match the K/A since Oconee does not have reflux boiling sump level indicators.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided TA-AM1 Obj 16 CETC Trend LOSCM tab Rev 01 EPE011 EA1.02 - Large Break LOCA Ability to operate and monitor the following as they apply to a Large Break LOCA: (CFR 41.7 / 45.5 / 45.6)
Reflux boiling sump level indicators ................................
Remarks/Status 1/03/20 - Chief stated we could write question based on indications of reflux boiling (i.e. CETC saw tooth pattern).
Monday, March 16, 2020 Page 4 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE015/017 AK2.07 - Reactor Coolant Pump (RCP) Malfunctions QUESTION 3 D Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 / 45.7)
RCP seals ......................................................
Given the following conditions on U1:
Reactor Power = 73% stable 1B1 RCP 1B2 RCP UPPER Cavity Pressure 710 psig stable 1420 psig stable LOWER Cavity Pressure 1070 psig stable 2140 psig stable Which ONE of the following describes the required actions in accordance with AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation)?
A. Immediately trip 1B1 RCP B. Immediately trip 1B2 RCP C. Reduce reactor power to < 70% and then trip 1B1 RCP D. Reduce reactor power to < 70% and then trip 1B2 RCP Monday, March 16, 2020 Page 5 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 3 D General Discussion With RCS pressure at NOP (2155 psig) the normal cavity pressures would be ~1435 psig for the lower cavity and ~718 psig for the upper cavity.
Answer A Discussion Incorrect. Plausible if student thinks the requirements to shutdown RCP based upon middle seal dp are met in accordance with AP/16 since the difference between Upper and Lower Cavity pressure on 1B1 RCP is only 50% of the difference between the cavities on 1B2 RCP. The immediate trip portion is plausible since the power level of 73% is below the Loss of RCP runback setpoint of 74%
Answer B Discussion Incorrect. The immediate trip is plausible since the power level of 73% is below the Loss of RCP runback setpoint of 74%
Answer C Discussion Incorrect. Plausible if student thinks the requirements to shutdown RCP based upon middle seal dp are met in accordance with AP/16 since the difference between Upper and Lower Cavity pressure on 1B1 RCP is only 50% of the difference between the cavities on 1B2 RCP.
Answer D Discussion Correct. 1B2 RCP Lower seal cavity pressure is indicative of a lower seal failure (~15 psid), and AP/16 requires a maximum power of 70% to be able to secure the RCP.
Basis for meeting the KA Requires knowledge of RCP seal pressure indications that indicate a RCP Seal malfunction that would require a loss of RCS flow as a result of securing the pump.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2009B Q4 Development References Student References Provided 2009B Q4 AP/1/A/1700/016 Rev 37 PNS-CPS Obj: 08 APE015/017 AK2.07 - Reactor Coolant Pump (RCP) Malfunctions Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 / 45.7)
RCP seals ......................................................
Remarks/Status Monday, March 16, 2020 Page 6 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE022 AA2.01 - Loss of Reactor Coolant Makeup QUESTION 4 B Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: (CFR 43.5/ 45.13)
Whether charging line leak exists . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Given the following on Unit 2:
Initial conditions:
Reactor power = 100%
Current conditions:
Pressurizer level = 195 lowering LDST level = 78 lowering Which ONE of the following has occurred?
A. Line break downstream of 2HP-7 B. Line break downstream of 2HP-120 C. 2HP-14 has failed in the bleed position D. Loss of Instrument Air and Auxiliary Instrument Air to 2HP-5 Monday, March 16, 2020 Page 7 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 4 B General Discussion Answer A Discussion Incorrect. Plausible since a line break downstream of 2HP-7 would give many of the same indications as a line break downstream of 2HP-120 (Sump rates, RIA alarms, etc.). This break would result in a loss of makeup to the LDST and would therefore cause LDST level to lower.
However, 2HP-120 would still control Pzr level and it would remain unchanged.
Answer B Discussion Correct. With a line break downstream of 2HP-120, makeup to the pressurizer would be lost and pressurizer level would lower. 2HP-120 would see the lowering of Pzr level and try to provide additional makeup by opening further. As 2HP-120 opened further, LDST level would begin to lower since the amount of water entering the LDST would be unaffected by the failure.
Answer C Discussion Incorrect. Plausible since 2HP-14 failing in bleed would cause an overall loss of inventory and would lower LDST level. However 2HP-120 would still maintain Pzr level constant.
Answer D Discussion Incorrect. Plausible since the candidate must determine that a loss of air supply to 2HP-5 will result in the valve failing closed and then determine that 2HP-5 failing closed would result in a lowering of the water being added to the LDST and would therefore result in a lowering of LDST level. 2HP-120 would close and Pzr level would rise.
Basis for meeting the KA Requires diagnosing a line break downstream of the normal makeup valve.
Basis for Hi Cog HI cog since the candidate must analyze various component failures to determine the impact on both LDST and Pzr levels.
Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 40 Q4 Development References Student References Provided ILT 40 Q4 PNS-HPI Obj. 02 APE022 AA2.01 - Loss of Reactor Coolant Makeup Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: (CFR 43.5/ 45.13)
Whether charging line leak exists . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Remarks/Status Monday, March 16, 2020 Page 8 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE026 AK3.02 - Loss of Component Cooling Water (CCW)
QUESTION 5 A Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: (CFR 41.5,41.10 / 45.6 / 45.13)
The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS ...........................
Given the following Unit 1 conditions:
Reactor power = 100%
Inadvertent ES channel 6 actuation occurs Which ONE of the following will occur and why?
A. The operating CC pump will stop to prevent deadheading the pump B. RCP seal return is isolated to eliminate a containment leakage path C. Letdown will isolate to prevent reaching the letdown high temperature interlock D. LPSW cooling to ALL RCPs is isolated to prevent a subsequent water hammer Monday, March 16, 2020 Page 9 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 5 A General Discussion Answer A Discussion CORRECT. Upon receiving an ES Ch 6 signal, 1CC-8 will receive a closed signal. When 1CC-8 closes, the operating CC pump will stop to prevent it from operating at shutoff head.
Answer B Discussion Incorrect. Plausible because it would be correct for ES Channel 1 or 2.
Answer C Discussion Incorrect. Letdown will isolate because of the high temperature interlock, not to prevent it. Plausible because letdown will isolate upon losing CC on high temp and will isolate due to ES Ch 1 or 2.
Answer D Discussion Incorrect: ES Channel 6 will isolate LPSW to all RCPs. Plausible because LPSW-1054, 1062 will close on Channel 6 actuation. They also close to prevent a water hammer when LPSW is restored to the RBCUs following a LOOP.
Basis for meeting the KA Question requires knowledge of automatic actions for the CC system on an ES signal (inadvertent ES in this instance), one of which is 1CC-8 closing which causes the running CC pump to trip.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 2007 Q7 Development References Student References Provided ILT 2007 Q7 PNS-CC APE026 AK3.02 - Loss of Component Cooling Water (CCW)
Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: (CFR 41.5,41.10 / 45.6 / 45.13)
The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS ...........................
Remarks/Status Monday, March 16, 2020 Page 10 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE027 AK2.03 - Pressurizer Pressure Control System (PZR PCS) Malfunction QUESTION 6 A Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: (CFR 41.7 / 45.7)
Controllers and positioners ........................................
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 90%
1B Main Feedwater pump trips Current conditions:
Reactor power = 70% lowering RCS pressure = 2165 psig slowly lowering Pressurizer level = 228 inches slowly lowering Pressurizer temperature = 640°F slowly lowering Pressurizer heater bank 1 (Group A and K) is ON Pressurizer heater banks 2, 3, and 4 are in AUTO and are OFF The pressurizer is __(1)__ AND the pressurizer heater bank 2 __(2)__.
Which ONE of the following completes the statement above?
A. 1. subcooled
- 2. should be energized B. 1. subcooled
- 2. will energize at 2145 psig C. 1. saturated
- 2. should be energized D. 1. saturated
- 2. will energize at 2145 psig Monday, March 16, 2020 Page 11 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 6 A General Discussion Answer A Discussion CORRECT: Saturation temp for 2165 psig is approximately 648 degrees. With the Pzr at 640 degrees, it is clearly subcooled. Regarding the pressurizer level saturation circuitry, Psat must be 20 psig below actual RCS pressure before Bank 2 will energize and will not de-energize until Psat and RCS pressure (NR Med-selected RCS Pressure) are within 15 psig (5 psig dead band). Actual RCS pressure is 2165, Saturation for actual pzr temp of 640°F is about 2045 psig therefore Bank 2 should be energized.
Answer B Discussion Incorrect: First part is correct. Second part is incorrect. Plausible since 2145 is 20 psig below actual RCS pressure and if the 20 psig delta required for saturation circuit to be energized is mis-applied it could lead to this choice. Also, 2145 is setpoint for bank 3 therefore this would be correct if asking about bank 3.
Answer C Discussion Incorrect: First part is incorrect. Plausible since conditions in Pzr are consistent with the loss of FDWP runback. Lowering RCS pressure is occurring concurrently with lowering Pzr level, which is a normal response if the Pzr is saturated. Second part is correct.
Answer D Discussion Incorrect: First part is incorrect. Plausible since conditions in Pzr are consistent with the loss of FDWP runback. Lowering RCS pressure is occurring concurrently with lowering Pzr level, which is a normal response if the Pzr is saturated. Second part is incorrect. Plausible since 2145 is 20 psig below actual RCS pressure and if the 20 psig delta required for saturation circuit to be energized is mis-applied it could lead to this choice. Also, 2145 is setpoint for bank 3 therefore this would be correct if asking about bank 3.
Basis for meeting the KA Requires knowledge of how controllers for Pzr saturation circuit function and the ability to diagnose a malfunction of circuitry.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 44 Q8 Development References Student References Provided ILT 44 Q8 PNS-PZR Obj 13 APE027 AK2.03 - Pressurizer Pressure Control System (PZR PCS) Malfunction Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: (CFR 41.7 / 45.7)
Controllers and positioners ........................................
Remarks/Status Monday, March 16, 2020 Page 12 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination EPE029 EK2.06 - Anticipated Transient Without Scram (ATWS)
QUESTION 7 A Knowledge of the interrelations between the ATWS and the following: (CFR 41.7 / 45.7)
Breakers, relays, and disconnects ...................................
Given the following Unit 3 conditions:
Rule 1, (ATWS / Unanticipated Nuclear Power Production) has been initiated
- 1) In accordance with Rule 1, an operator will be dispatched to open the Unit 3 CRD 600V normal power supply breaker at 3X9 and alternate 600V power supply breaker at __(1)__ .
- 2) DSS will de-energize Control Rod Groups 1 - 7 at __(2)__ psig.
Which ONE of the following completes the statements above?
A. 1. 2X2
- 2. 2450 B. 1. 1X1
- 2. 2450 C. 1. 2X2
- 2. 2500 D. 1. 1X1
- 2. 2500 Monday, March 16, 2020 Page 13 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 7 A General Discussion Answer A Discussion CORRECT: The alternate power supply for U3 CRD breakers is 2X2.
When RCS pressure reaches 2450 psig, a DSS signal will be generated. DSS de-energizes the safety and regulating rods (Groups 1-7) by interrupting the gating current to the motors.
Answer B Discussion Incorrect: First part is incorrect because the alternate power supply for U3 CRD breakers is 2X2. It is plausible because if the question was asking about Unit 2, it would be correct.
Second part is correct because when RCS pressure reaches 2450 psig, a DSS signal will be generated. DSS de-energizes the safety and regulating rods (Groups 1-7) by interrupting the gating current to the motors.
Answer C Discussion Incorrect: First part is correct. The alternate power supply for U3 CRD breakers is 2X2.
Second part is incorrect. When RCS pressure reaches 2450 psig, a DSS signal will be generated. DSS de-energizes the safety and regulating rods (Groups 1-7) by interrupting the gating current to the motors. It is plausible because 2500 psig is the setpoint where the Code Safety valves open.
Answer D Discussion Incorrect: 1st part is incorrect because the alternate power supply for U3 CRD breakers is 2X2. It is plausible because if the question was asking about Unit 2, it would be correct.
Second part is incorrect. When RCS pressure reaches 2450 psig, a DSS signal will be generated. DSS de-energizes the safety and regulating rods (Groups 1-7) by interrupting the gating current to the motors. It is plausible because 2500 psig is the setpoint where the Code Safety valves open.
Basis for meeting the KA Question requires knowledge of the relationship between an ATWS condition and actions taken to open breakers to shutdown the reactor.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 16-1 Q8 Development References Student References Provided ILT 16-1 Q8 IC-RPS Obj 16/17 IC-CRI Obj 05 U3 Rule 1 Rev 03 EPE029 EK2.06 - Anticipated Transient Without Scram (ATWS)
Knowledge of the interrelations between the ATWS and the following: (CFR 41.7 / 45.7)
Breakers, relays, and disconnects ...................................
Remarks/Status Monday, March 16, 2020 Page 14 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination EPE038 2.4.6 - Steam Generator Tube Rupture (SGTR)
QUESTION 8 D EPE038 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)
Given the following Unit 1 conditions:
Reactor Power = 29% lowering Primary to secondary leakage in 1A SG Pzr level = 160 inches slowly lowering 1A HPI Pump operating 1HP-120 full open 1HP-5 closed In accordance with the EOP SGTR tab
- 2) The reactor __(2)__ required to be manually tripped at this time.
Which ONE of the following completes the statements above?
A. 1. will
- 2. is B. 1. will
- 2. is NOT C. 1. will NOT
- 2. is D. 1. will NOT
- 2. is NOT Monday, March 16, 2020 Page 15 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 8 D General Discussion Answer A Discussion Incorrect: First part is incorrect. 1RIA-59 &-60 (MS Line N-16 gamma detectors) are only accurate above 40% power. Below 40% they only provide a trend and can not be used to determine leakrate.
Second part is incorrect. The SGTR tab directs tripping the reactor when the leakrate is > HPI capacity (PZR level lowering with full HPI).
Plausible because AP/02 (RCS Leakage) would direct tripping the reactor if this was RCS leakage other than a SGTR.
Answer B Discussion Incorrect: First part is incorrect. 1RIA-59 &-60 (MS Line N-16 gamma detectors) are only accurate above 40% power. Below 40% they only provide a trend and can not be used to determine leakrate.
Second part is correct. The SGTR tab directs tripping the reactor when the leakrate is > HPI capacity (PZR level lowering with full HPI). Only one HPI pump is operating.
Answer C Discussion Incorrect: First part is correct. 1RIA-59 &-60 (MS Line N-16 gamma detectors) are only accurate above 40% power. Below 40% they only provide a trend and can not be used to determine leakrate.
Second part is incorrect. The SGTR tab directs tripping the reactor when the leakrate is > HPI capacity (PZR level lowering with full HPI).
Plausible because for the conditions given, AP/02 would direct tripping the reactor.
Answer D Discussion CORRECT: 1RIA-59 &-60 (MS Line N-16 gamma detectors) are only accurate above 40% power. Below 40% they only provide a trend and can not be used to determine leakrate.
The SGTR tab directs tripping the reactor when the leakrate is > HPI capacity (PZR level lowering with full HPI). With only one HPI pump operating, the reactor will not be manually tripped.
Basis for meeting the KA Requires knowledge of the method used to determine RCS leak rate along with the criteria and method used to shutdown the reactor in the EOP SGTR tab.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 2009 Q10 Development References Student References Provided ILT 2009 Q10 EAP-SGTR Obj 05 EOP SGTR tab Rev 0 EPE038 2.4.6 - Steam Generator Tube Rupture (SGTR)
EPE038 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 16 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE054 AK1.02 - Loss of Main Feedwater (MFW)
QUESTION 9 D Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): (CFR 41.8 / 41.10 /
45.3)
Effects of feedwater introduction on dry S/G .........................
Given the following Unit 2 conditions:
Loss of Heat Transfer has occurred Unit 2 TDEFWP is now available to feed the Steam Generators 2A SG level = 8 XSUR slowly lowering 2A SG pressure = 412 psig slowly lowering 2B SG level = 5 XSUR slowly lowering 2B SG pressure = 385 psig slowly lowering In accordance with Rule 7 (Steam Generator Feed Control), the MAXIMUM initial feed rate allowed to EACH Steam Generator is limited to __(1)__ gpm in order to prevent
__(2)__.
Which ONE of the following completes the statement above?
A. 1. 50
- 2. an RCS overcooling event B. 1. 50
- 2. damage to the Steam Generators C. 1. 100
- 2. an RCS overcooling event D. 1. 100
- 2. damage to the Steam Generators Monday, March 16, 2020 Page 17 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 9 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible under the misconception that the 100 gpm is a total flow limit instead of a limit to each SG.
Second part is incorrect. Plausible since quickly establishing a level in a dry steam generator can often result in an overcooling event and is a serious concern and would therefore be a plausible reason to limit flow to the SG since the amount of flow established correlates to the cooldown that results.
Answer B Discussion Incorrect. First part is incorrect. Plausible under the misconception that the 100 gpm is a total flow limit instead of a limit to each SG.
Second part is correct.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since quickly establishing a level in a dry steam generator can often result in an overcooling event and is a serious concern and would therefore be a plausible reason to limit flow to the SG since the amount of flow established correlates to the cooldown that results.
Answer D Discussion CORRECT: Rule 7 limits flow to each affected Steam Generator to 100 gpm if the SG is dry and does NOT have heat transfer established. With levels < 12 inches AND steam generator pressures lowering, there are no signs of heat transfer in the SG. The limit is there to protect the SG from damage.
Basis for meeting the KA Requires knowledge of the operational implications of not adhering to the flow limits established when feeding a dry SG with no heat transfer following a loss of MFDW.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 46 Q10 Development References Student References Provided ILT 46 Q10 EAP-LOHT Obj 18 EAP-LOHT Att. 3 Rule 7 U2 EOP Rule 7 Rev 03 APE054 AK1.02 - Loss of Main Feedwater (MFW)
Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): (CFR 41.8 / 41.10 /
45.3)
Effects of feedwater introduction on dry S/G .........................
Remarks/Status Monday, March 16, 2020 Page 18 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination EPE055 2.4.47 - Loss of Offsite and Onsite Power (Station Blackout)
QUESTION 10 B EPE055 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10
/ 43.5 / 45.12)
Given the following Unit 1 conditions:
Station Blackout occurred SSF has been activated U1 TDEFDWP is feeding both U1 SGs o 1A EFDW Flow = 325 gpm o 1B EFDW Flow = 330 gpm RCS NR Tc = 550°F slowly lowering MS Pressure = 1000 psig slowly lowering RCS Pressure = 1940 psig slowly lowering In accordance with Rule 7 (SG Feed Control), the reason EFDW Flow should INITIALLY be throttled is to ________.
Which ONE of the following completes the statement above?
A. maintain RCS NR Tc of 550 - 555°F B. raise RCS Pressure to 1950 - 2250 psig C. raise MS Pressure to approximately 1010 psig D. lower EFDW Flow below runout limit of 600 gpm Monday, March 16, 2020 Page 19 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 10 B General Discussion Answer A Discussion Incorrect. Plausible because Rule 7 directs establishing RCS NR Tc of 550 - 555 degrees after the RCS pressure band is established..
Answer B Discussion CORRECT. With an SSF Event and the TDEFDW pump feeding the SGs, Rule 7 directs feed as needed to Maintain RCS pressure band of 1950 - 2250 psig.
Answer C Discussion Incorrect. Plausible because MS pressure is below the normal stable post trip pressure of 1010 psig and lowering EFDW flow will allow pressure to rise to 1010 psig, but Rule 7 does not address this.
Answer D Discussion Incorrect. Plausible because if this was a MDEFDW pump, it would be correct.
Basis for meeting the KA Question requires the ability to recognize EFDW flow needs to be throttled in order to comply with Rule 7 requirements.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided EAP-BO Obj 06 EOP BO tab Rev 05 EOP Rule 7 Rev 03 EPE055 2.4.47 - Loss of Offsite and Onsite Power (Station Blackout)
EPE055 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10
/ 43.5 / 45.12)
Remarks/Status Monday, March 16, 2020 Page 20 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE056 AK1.01 - Loss of Offsite Power QUESTION 11 A Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: CFR 41.8 / 41.10 / 45.3)
Principle of cooling by natural convection ...........................
Time = 1200:
Unit 1 reactor power = 100%
EFPD = 400 Switchyard Isolation occurs Time = 1217:
- 1) At Time = 1217, natural circulation conditions __(1)__ been established.
- 2) IF steady state natural circulation is established, the RCS loop transit time will be approximately __(2)__ minutes.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED (above)
A. 1. have
- 2. 4 - 7 B. 1. have
- 2. 8 - 10 C. 1. have NOT
- 2. 4 - 7 D. 1. have NOT
- 2. 8 - 10 Monday, March 16, 2020 Page 21 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 11 A General Discussion Answer A Discussion CORRECT. During the transition from forced to natural circulation, the cold leg temperatures should remain near the saturation temperature for the existing OTSG pressure. The hot leg temperatures and CETCs will increase until a stable delta T between the hot and cold legs is established at 30-40°F. Loop transit time (the time for a pound of water to circulate around the RCS) which is normally about 12 seconds during 4-RCP operation will increase to approximately 4 - 7 minutes during steady-state natural circulation.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because Natural circulation requires approximately 10-15 minutes to become fully established under normal circumstances from a full power trip.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if the candidate uses Tave with either Th or Tc to calculate the delta T, it will appear correct.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if the candidate uses Tave with either Th or Tc to calculate the delta T, it will appear correct.
Second part is incorrect. Plausible because Natural circulation requires approximately 10-15 minutes to become fully established under normal circumstances from a full power trip.
Basis for meeting the KA Question requires knowledge of the operational implications of natural circulation, which is caused by a loss of offsite power.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 39 Q12 Development References Student References Provided ILT 39 Q12 TA-AM1 Obj 03, 05 APE056 AK1.01 - Loss of Offsite Power Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: CFR 41.8 / 41.10 / 45.3)
Principle of cooling by natural convection ...........................
Remarks/Status Monday, March 16, 2020 Page 22 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE057 2.4.50 - Loss of Vital AC Electrical Instrument Bus QUESTION 12 C APE057 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 / 43.5 / 45.3)
Given the following on Unit 1:
Initial conditions:
1SA-06/A-2 (EL Inverter 1DIC System Trouble) actuates Current conditions:
1SA-13/B-7 (Inverter 1DIC Output Voltage Low) actuated in the Equipment Room
- 1) 1SA-13/B-7 actuated when voltage lowered below a MAXIMUM of __(1)__ volts.
- 2) Manual transfer of the vital loads on 1KVIC to Regulated Power Panelboard (1KRA) will be performed using the __(2)__ on 1DIC Inverter.
Which ONE of the following completes the statements above?
A. 1. 72
- 2. Manual Bypass Switch B. 1. 72
- 2. Alternate Source to Load Pushbutton C. 1. 115
- 2. Manual Bypass Switch D. 1. 115
- 2. Alternate Source to Load Pushbutton Monday, March 16, 2020 Page 23 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 12 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because the low voltage alarm setpoint for the 1DIC Panelboard is 72 volts (statalarm 1SA-13/E-7).
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because the low voltage alarm setpoint for the 1DIC Panelboard is 72 volts (statalarm 1SA-13/E-7).
Second part is incorrect. Plausible since it would be correct for an Essential inverter.
Answer C Discussion CORRECT. 1SA-13/B-7 alarm setpoint is "AC output from inverter below 115 volts". The ARG directs the operator to manually transfer vital loads on 1KVIC to the Regulated Power Panelboard (1KRA) per OP/1/A/1107/004 (Operation of the Vital Bus, Computer, ICS and Auxiliary Inverters).
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since it would be correct for an Essential inverter.
Basis for meeting the KA Question requires knowledge of 1SA-13/B-7 (Inverter 1DIC Output Voltage Low) alarm setpoint and the actions required to transfer the loads on 1KVIC vital power panelboard to Regulated Power panelboard (1KRA).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 41 Q12 Development References Student References Provided ILT 41 Q12 1SA-13/B-7 Rev 03 EL-VPC Obj 03 OP/1/A/1107/004 Encl 4.21 Rev 43 APE057 2.4.50 - Loss of Vital AC Electrical Instrument Bus APE057 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 / 43.5 / 45.3)
Remarks/Status Monday, March 16, 2020 Page 24 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE058 AK1.01 - Loss of DC Power QUESTION 13 B Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power: (CFR 41.8 / 41.10 / 45.3)
Battery charger equipment and instrumentation .......................
Plant conditions:
1CA Battery Charger fails - output voltage = 0 VDC 1CA Battery voltage = 126 VDC 1DCB Bus voltage = 123 VDC Unit 2 DCA/DCB Bus voltage = 124 VDC Unit 3 DCA/DCB Bus voltage = 127 VDC Based on the above conditions, which ONE of the following will automatically supply power to 1DIA panelboard?
A. 1DCB Bus B. 1CA Battery C. Unit 2 DC Bus D. Unit 3 DC Bus Monday, March 16, 2020 Page 25 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 13 B General Discussion Answer A Discussion Incorrect. For the Vital DC system, the 1DCB bus is not aligned to the 1DCA bus. Plausible because 1DCB Bus is aligned to backup the essential inverters.
Answer B Discussion CORRECT: The voltage from 1CA battery is higher than the backup source (Unit 2 DC Bus). Unit 1CA battery will supply power.
Answer C Discussion Incorrect. Plausible because this would be correct if the Unit 2 DC bus voltage was higher than the 1CA battery voltage.
Answer D Discussion Incorrect. Unit 3's DC Bus is not connected to Unit 1. Plausible because unit 3 does backup Unit 1 in the SSF power scheme.
Basis for meeting the KA Requires knowledge of the operational implications of a failed battery charger and the operational impact of the loss of a Vital DC Battery Charger and the response by the Vital DC system Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 47 Q14 Development References Student References Provided ILT 47 Q14 EL-DCD Obj 04, 06 APE058 AK1.01 - Loss of DC Power Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power: (CFR 41.8 / 41.10 / 45.3)
Battery charger equipment and instrumentation .......................
Remarks/Status Monday, March 16, 2020 Page 26 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE062 AK3.01 - Loss of Nuclear Service Water QUESTION 14 D Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4, 41.8 / 45.7 )
The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
A and B LPSW pumps operating Current conditions:
A LPSW pump trips due to breaker failure Standby LPSW pump will NOT start AP/1/A/1700/024 (Loss of LPSW) initiated
- 1) 1LPSW-1121, 1122, 1123, and 1124 will close at a MAXIMUM LPSW header pressure of __(1)__ psig lowering.
- 2) The reason the above valves automatically close is to __(2)__.
Which ONE of the following completes the statements above?
A. 1. 25
- 2. prevent LPSW pump run out B. 1. 25
- 2. prevent water hammers in the LPSW system C. 1. 18
- 2. prevent LPSW pump run out D. 1. 18
- 2. prevent water hammers in the LPSW system Monday, March 16, 2020 Page 27 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 14 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because 25 psig is the pressure at which the valves will re-open. Second part is incorrect. Plausible because with low header pressure the LPSW pump would have high flow which could cause pump run out. But this is not the reason the valves were installed.
Answer B Discussion Incorrect. First part is incorrect. Plausible because 25 psig is the pressure at which the valves will re-open. Second part is correct.
Answer C Discussion Incorrect. First part is correct. Second part is incorrect. Plausible because with low header pressure the LPSW pump would have high flow which could cause pump run out. But this is not the reason the valves were installed.
Answer D Discussion CORRECT. 1LPSW-1121 thru 1124 close at 18 psig lowering to prevent water hammers in the LPSW system on pump restart.
Basis for meeting the KA Question requires knowledge of the automatic opening and closing of LPSW valves. Per NRC Chief - I agree that you could meet the K/A by writing a question that involves automatic valve actuations/isolations of the LPSW system at Oconee.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 45 Q16 Development References Student References Provided ILT 45 Q16 SSS-LPW Obj. 12 U1 AP/24 Rev 28 APE062 AK3.01 - Loss of Nuclear Service Water Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: (CFR 41.4, 41.8 / 45.7 )
The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers Remarks/Status NRC Chief: Regarding K/A 062AK3.01: I agree that you could meet the K/A by writing a question that involves automatic valve actuations/isolations of the LPSW system at Oconee.
Monday, March 16, 2020 Page 28 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE065 AA2.06 - Loss of Instrument Air QUESTION 15 A Ability to determine and interpret the following as they apply to the Loss of Instrument Air: (CFR: 43.5 / 45.13)
When to trip reactor if instrument air pressure is de-creasing ...........
Given the following Unit 1 conditions:
Reactor power = 100%
Instrument Air pressure = 85 psig lowering AP/1/A/1700/022 (Loss of Instrument Air) has been initiated
- 1) AP/22 directs an immediate manual Reactor trip if instrument air header pressure lowers to a MAXIMUM value of __(1)__ psig.
- 2) AP/22 directs tripping the Main FDW pumps immediately after tripping the Reactor because the controlling FDW valves fail __(2)__.
A. 1. 65
- 2. as is B. 1. 70
- 2. as is C. 1. 65
- 2. closed D. 1. 70
- 2. closed Monday, March 16, 2020 Page 29 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 15 A General Discussion Answer A Discussion CORRECT. AP/22 informs the operator that FDW control valves fail "As Is" at 65 psig and there is an IAAT step directing a manual trip of the Main FDW pumps and Rx if IA pressure reaches 65 psig.
Answer B Discussion Incorrect. First part is incorrect. Plausible since there are RCS letdown valves that fail closed at 70 psig IA pressure and are listed in AP/22.
Second part is correct.
Answer C Discussion Incorrect. First part is correct. Second part is incorrect. Plausible since most pneumatic valves do fail closed on loss of their air supply. If the valves failed closed, then the Main FDW pumps could not feed the SG, therefore tripping the Main FDW pumps for this reason is logical.
Answer D Discussion Incorrect. First part is incorrect. Plausible since there are RCS letdown valves that fail closed at 70 psig IA pressure and are listed in AP/22.
Second part is incorrect. Plausible since most pneumatic valves do fail closed on loss of their air supply. If the valves failed closed, then the Main FDW pumps could not feed the SG, therefore tripping the Main FDW pumps for this reason is logical.
Basis for meeting the KA Question requires knowledge of when to trip the reactor on a loss of Instrument Air.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 44 Q15 Development References Student References Provided ILT 44 Q15 AP/22 Rev 30 EAP-AP22 Obj 03 APE065 AA2.06 - Loss of Instrument Air Ability to determine and interpret the following as they apply to the Loss of Instrument Air: (CFR: 43.5 / 45.13)
When to trip reactor if instrument air pressure is de-creasing ...........
Remarks/Status Monday, March 16, 2020 Page 30 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE077 AA1.02 - Generator Voltage and Electric Grid Disturbances QUESTION 16 D Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8 )
Turbine / generator controls.......................................................
Given the following Unit 1 conditions:
Time = 0400:
Generator output = 850 MWe and 236 MVARs Time = 0415:
Generator output = 850 MWe and 338 MVARs
- 1) The change in Generator output from Time = 0400 to Time = 0415 is due to a change in __(1)__.
- 2) If the generator reaches the Underfrequency Maximum Allowable Time given in AP/1/A/1700/034 (Degraded Grid) the Main Turbine will __(2)__.
Which ONE of the following completes the statements above?
A. 1. Main Steam flow
- 2. require a manual trip B. 1. Main Steam flow
- 2. automatically trip C. 1. generator excitation voltage
- 2. require a manual trip D. 1. generator excitation voltage
- 2. automatically trip Monday, March 16, 2020 Page 31 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 16 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because the candidate could have the misconception that as steam flow increases so does MVARs.
Second part is incorrect. Plausible because the AP does have the operator monitor how long a low frequency conditions lasts and trip the unit if it does not trip automatically.
Answer B Discussion Incorrect. First part is incorrect. Plausible because the candidate could have the misconception that as steam flow increases so does MVARs.
Second part is correct.
Answer C Discussion Incorrect. First part is correct. Second part is incorrect. Plausible because the AP does have the operator monitor how long a low frequency conditions lasts and trip the unit if it does not trip automatically.
Answer D Discussion CORRECT. MVARs are increased by changing Generator output voltage. The Digital T/G control system monitors how long the unit operates in a low frequency condition and will trip the unit if the time limit is exceeded.
Basis for meeting the KA Question requires the ability to monitor the Turbine/Generator during Generator voltage and Grid disturbances and to ensure the Turbine/Generator is shutdown when conditions warrant.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 41 Q16 Development References Student References Provided ILT 41 Q16 EAP-AP/34 Obj. 4 STG-EHC Obj. 12 U1 AP/34 Rev 13 APE077 AA1.02 - Generator Voltage and Electric Grid Disturbances Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8 )
Turbine / generator controls.......................................................
Remarks/Status Monday, March 16, 2020 Page 32 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE05 EA1.1 - Excessive Heat Transfer QUESTION 17 D Ability to operate and / or monitor the following as they apply to the (Excessive Heat Transfer)
(CFR: 41.7 / 45.5 / 45.6)
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
1A Main Steam Line Break occurs Current conditions:
Reactor has tripped RCS Tave = 544°F slowly rising 1A SG Pressure = 0 psig 1B SG Pressure = 990 psig slowly rising Turbine bypass valves in Auto Reactor Building pressure = 0.2 psig stable
- 1) The TDEFWP is __(1)__.
- 2) The TDEFWP can be __(2)__.
Which ONE of the following completes the statements above?
A. 1. operating
- 2. secured with TDEFWP control switch ONLY after AFIS is reset B. 1. operating
- 2. secured with TDEFWP control switch before AFIS is reset C. 1. NOT operating
- 2. started with TDEFWP control switch ONLY after AFIS is reset D. 1. NOT operating
- 2. started with TDEFWP control switch before AFIS is reset Monday, March 16, 2020 Page 33 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 17 D General Discussion Answer A Discussion Incorrect: 1st part is incorrect. Plausible since 1FDW-315 is closed in first step of Rule 5. This makes it plausible that AFIS would not secure the TDEFWP so that it would be available to feed the B SG if needed. Second part is incorrect. Plausible since many components require manual action other than just turning the switch to re-position following a safety system actuation (ex: ES components).
Answer B Discussion Incorrect: 1st part is incorrect but plausible since 1FDW-315 is closed in first step of Rule 5. This makes it plausible that AFIS would not secure the TDEFWP so that it would be available to feed the B SG if needed. Second part is correct.
Answer C Discussion Incorrect: First part is correct. TDEFWP would not be operating. Second part is incorrect. Plausible since many components require manual action other than just turning the switch to reposition following a safety system actuation (ex: ES components).
Answer D Discussion CORRECT: With the switch in AUTO, MS-93 to the TDEFWP will close when receiving an AFIS signal. Going to RUN with the TDEFWP switch overrides the AFIS signal and allows the operator to restart the TDEFWP as necessary to feed Steam Generators without resetting the AFIS signal.
Basis for meeting the KA Requires the ability to monitor and operate the TDEFWP during an Excessive Heat Transfer event following AFIS actuation.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 46 Q17 Development References Student References Provided ILT 46 Q17 CF-EF Obj. 30 BWE05 EA1.1 - Excessive Heat Transfer Ability to operate and / or monitor the following as they apply to the (Excessive Heat Transfer)
(CFR: 41.7 / 45.5 / 45.6)
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Remarks/Status Monday, March 16, 2020 Page 34 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE10 EA2.2 - Post-Trip Stabilization QUESTION 18 C Ability to determine and interpret the following as they apply to the (Post-Trip Stabilization)
(CFR: 43.5, 45.13)
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
Given the following Unit 1 conditions:
Reactor tripped from 100% power ALL Control Rods fully inserted 1MS-10 (Main Steam Relief Valve) is stuck open Main Steam pressure is being reduced in an attempt to reseat 1MS-10 In accordance with Subsequent Actions of the EOP
- 1) Main Steam pressure will be reduced in __(1)__ psig increments.
Which ONE of the following completes the statements above?
A. 1. 10
- 2. 525 B. 1. 20
- 2. 525 C. 1. 10
- 2. 532 D. 1. 20
- 2. 532 Monday, March 16, 2020 Page 35 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 18 C General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since it is the RCS temperature associated with isolating a steam generator with a SGTR.
Answer B Discussion Incorrect. First part is incorrect. Plausible as it is the increments on the THP setpoint knob that is used to do the MS pressure reduction and is therefore a plausible choice.
Second part is incorrect. Plausible since it is the RCS temperature associated with isolating a steam generator with a SGTR.
Answer C Discussion CORRECT: EOP SA directs reducing Main Steam pressure in approximately 10 psig increments WITHOUT reducing RCS Temperature less than 532 degrees.
Answer D Discussion Incorrect. First part is incorrect. Plausible as it is the increments on the THP setpoint knob that is used to do the MS pressure reduction and is therefore a plausible choice.
Second part is correct.
Basis for meeting the KA Requires the knowledge of post trip stabilization methods for a stuck open steam valve and the minimum temperature limits that apply.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 46 Q18 Development References Student References Provided ILT 46 Q18 EAP-SA Obj 18 SA tab Rev 02 BWE10 EA2.2 - Post-Trip Stabilization Ability to determine and interpret the following as they apply to the (Post-Trip Stabilization)
(CFR: 43.5, 45.13)
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
Remarks/Status Monday, March 16, 2020 Page 36 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE037 AA1.10 - Steam Generator (S/G) Tube Leak QUESTION 19 B Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak: (CFR 41.7 / 45.5 / 45.6)
CVCS makeup tank level indicator ..................................
Given the following Unit 1 conditions:
Time = 0800:
Reactor power = 100%
1RIA-59 indicates 180 gpm stable CRS enters SGTR tab Time = 0810:
- 1) At Time = 0800, 1HP-26 __(1)__ be opened in accordance with AD-OP-ONS-0002 (Oconee Specific Abnormal Operations Guidance).
- 2) At Time = 0810, HPI pump suction is supplied by the __(2)__.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED (above)
A. 1. can
- 2. LDST B. 1. can
- 2. BWST C. 1. can NOT
- 2. LDST D. 1. can NOT
- 2. BWST Monday, March 16, 2020 Page 37 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 19 B General Discussion Answer A Discussion Incorrect. First part is correct. Second part is incorrect. Plausible because if LDST level were > 40 inches, it would be correct.
Answer B Discussion CORRECT. AD-OP-ONS-0002 states 'On a critical reactor, HP-26 should not be opened unless mitigating a SGTR. The LDST low level interlock opens HP-24 and 25 to align HPI suction to the BWST at 40 inches lowering LDST level.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if the 180 gpm were an RCS leak instead of a SGTR, it would be correct. Second part is incorrect. Plausible because if LDST level were > 40 inches, it would be correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if the 180 gpm were an RCS leak instead of a SGTR, it would be correct. Second part is correct.
Basis for meeting the KA Question requires the ability to monitor the LDST level indicator during a SGTR and determine HPI pump suction source based on the indicated level.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided AD-OP-ONS-0002 Rev 1 PNS-HPI Obj. 06 APE037 AA1.10 - Steam Generator (S/G) Tube Leak Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak: (CFR 41.7 / 45.5 / 45.6)
CVCS makeup tank level indicator ..................................
Remarks/Status Monday, March 16, 2020 Page 38 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE028 2.2.44 - Pressurizer (PZR) Level Control Malfunction QUESTION 20 B APE028 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)
Given the following Unit 2 conditions:
Initial conditions:
Reactor power = 100%
Pzr level Channel 3 is selected SASS in MANUAL Current conditions:
Pzr level Channel 3 fails to 100 inches
- 1) The operating HPI pump current (amps) will __(1)__.
- 2) In accordance with AD-OP-ALL-1000 (Conduct of Operations), the RO with concurrence from the CRS, __(2)__ select a valid Pzr level indication without a procedure in hand.
Which ONE of the following completes the statements above?
A. 1. rise
- 2. can NOT B. 1. rise
- 2. can C. 1. lower
- 2. can NOT D. 1. lower
- 2. can Monday, March 16, 2020 Page 39 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 20 B General Discussion Answer A Discussion Incorrect. First part is correct. With SASS in MANUAL, when Pzr level 3 fails low, 1HP-120 will open fully to attempt to raise indicated Pzr level to setpoint. This will cause HPI pump amps to rise.
Second part is incorrect. Plausible since procedures are required to be in hand almost all the time when operating in the Control Room or plant.
Answer B Discussion CORRECT. With SASS in MANUAL, when Pzr level 3 fails low, 1HP-120 will open fully to attempt to raise indicated Pzr level to setpoint..
This will cause HPI pump amps to rise. AD-OP-ALL-1000 (Conduct of Operations) states "written procedures are not necessary for situations where conditions exist which may require timely actions due to failure of automatic control systems or uncertain equipment status (e.g., taking manual control of hand/auto stations, position of selector switches).
Answer C Discussion Incorrect. First part is incorrect. Plausible if the candidate has a misconception on the relationship between pump amps and flow. (ie. If the question were asking about the operating pump discharge pressure, it would be correct).
Second part is incorrect. Plausible since procedures are required to be in hand almost all the time when operating in the Control Room or plant.
Answer D Discussion Incorrect. First part is incorrect. Plausible if the candidate has a misconception on the relationship between pump amps and flow. (ie. If the question were asking about the operating pump discharge pressure, it would be correct).
Second part is correct.
Basis for meeting the KA Question requires the ability to interpret the control room indication for Pzr level following a Pzr level control malfunction and the resultant effect on HPI pump operation (amps) and how directives affect plant and system conditions by allowing the operator to select a valid indication in a timely manner without acquiring a procedure.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 42 Q21 Development References Student References Provided ILT 42 Q21 AD-OP-ALL-1000 Rev 16 PNS-PZR Obj. 21 ADM-OMP Obj. 01 APE028 2.2.44 - Pressurizer (PZR) Level Control Malfunction APE028 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)
Remarks/Status Monday, March 16, 2020 Page 40 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE067 AK3.02 - Plant Fire On Site QUESTION 21 A Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 41.5,41.10 / 45.6 / 45.13)
Steps called out in the site fire protection plan, FPS manual, and fire zone manual .......................................
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Fire in Unit 1 Cable Room AP/1/A/1700/050, (Challenging Plant Fire) has been initiated Current conditions:
AP/50 Section 4G, (Unit 1 Control Room Evacuation) directs the OATC to perform Encl 5.5, (OATC Actions for Control Room Evacuation)
- 1) AP/50 Encl 5.5 will direct the OATC to take __(1)__.
- 2) The reason the above action is taken is to __(2)__.
Which ONE of the following completes the statements above?
A. 1. 1FDW-315 and 1FDW-316 to MANUAL and close
- 2. prevent spurious operation of 1FDW-315 and 1FDW-316 due to fire damage B. 1. 1FDW-315 and 1FDW-316 to MANUAL and close
- 2. ensure EFDW flow to the SGs can be controlled from the ASD Panel C. 1. 1A and 1B TBVs to HAND and control SG pressure from the ADVs
- 2. ensure natural circulation develops when the RCPs are secured D. 1. 1A and 1B TBVs to HAND and control SG pressure from the ADVs
- 2. maximize SG inventory prior to losing secondary pumps due to the fire Monday, March 16, 2020 Page 41 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 21 A General Discussion Answer A Discussion CORRECT: First part is correct. Encl 5.5 directs closing 1FDW 315 & 316.
Second part is correct. The concern is spurious operation caused by the fire.
Answer B Discussion Incorrect. First part is correct. Encl 5.5 directs closing 1FDW 315 & 316.
Second part is incorrect because the concern is spurious operation caused by the fire. It is plausible because the SGs will be fed from the ASDP during a control room evacuation not caused by a fire.
Answer C Discussion Incorrect: First part is incorrect because Encl 5.5 does not address the TBVs. It is plausible because if the fire were in the Turbine building were being performed, it could be correct..
Second part could be correct if it were a TB fire. RCPs are secured in the event and levels are raised to ensure NC occurs. SG pressure would have to be controlled to control Tc and therefore, natural circulation heat transfer.
Answer D Discussion Incorrect: First part is incorrect because Encl 5.5 does not address the TBVs. It is plausible because if the fire were in the Turbine building were being performed, it could be correct.
Second part is incorrect because this is not performed. It is plausible because it is correct for a Turbine Building Flood when you could potentially lose secondary pumps.
Basis for meeting the KA Question requires knowledge of the reason for steps in procedures used during plant fire.
Per the NRC Chief: I agree that you could meet the K/A by writing a question associated with AP/43 or AP/50. In general, I could accept testing operationally valid knowledge of any fire in the plant procedure used by licensed operators to meet this K/A.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 16-1 Q21 Development References Student References Provided ILT 16-1 Q21 AP/1/A/1700/050 Rev 05 EAP-AP/50 Obj 03 APE067 AK3.02 - Plant Fire On Site Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 41.5,41.10 / 45.6 / 45.13)
Steps called out in the site fire protection plan, FPS manual, and fire zone manual .......................................
Remarks/Status Per the NRC Chief Regarding K/A 067AK3.02: I agree that you could meet the K/A by writing a question associated with AP/43 or AP/50. In general, I could accept testing operationally valid knowledge of any fire in the plant procedure used by licensed operators to meet this K/A.
Monday, March 16, 2020 Page 42 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWA01 AK3.3 - Plant Runback QUESTION 22 D Knowledge of the reasons for the following responses as they apply to the (Plant Runback)
(CFR: 41.5 / 41.10, 45.6, 45.13)
Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
Given the following on Unit 1:
Initial conditions:
Reactor power = 100% stable Plant issue requires rapid shutdown AP/1/A/1700/029 (Rapid Unit Shutdown) initiated Current conditions:
CRS directs RO to depress MAXIMUM RUNBACK
- 1) In accordance with AP/29, __(1)__ Main FDW pump is the preferred pump to be shutdown first.
- 2) The reason the above Main FDW pump is the preferred pump to be shutdown first is because its discharge pressure trip setpoint is __(2)__ than that of the remaining Main FDW pump.
Which ONE of the following completes the statement above?
A. 1. 1A
- 2. higher B. 1. 1A
- 2. lower C. 1. 1B
- 2. higher D. 1. 1B
- 2. lower Monday, March 16, 2020 Page 43 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 22 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because 1A FDW pump could be the first pump shutdown if plant conditions warrant.
Second part is incorrect. Plausible because it would be correct for 1A FDW pump.
Answer B Discussion Incorrect. First part is incorrect. Plausible because 1A FDW pump could be the first pump shutdown if plant conditions warrant.
Second part is correct.
Answer C Discussion Incorrect.. First part is correct.
Second part is incorrect. Plausible because it would be correct for 1A FDW pump.
Answer D Discussion CORRECT. 1B FDW pump is the preferred pump to be shutdown first because 1A FDW pump has a higher discharge pressure trip setpoint.
Basis for meeting the KA Question requires knowledge of the reason the 1B Main FDW pump is the preferred pump to be shutdown first during a plant runback..
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided EAP-AP/29 Obj 03, 04 AP/1/A/1700/029 Rev 13 BWA01 AK3.3 - Plant Runback Knowledge of the reasons for the following responses as they apply to the (Plant Runback)
(CFR: 41.5 / 41.10, 45.6, 45.13)
Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
Remarks/Status Monday, March 16, 2020 Page 44 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWA04 AK2.2 - Turbine Trip QUESTION 23 C Knowledge of the interrelations between the (Turbine Trip) and the following:
(CFR: 41.7 / 45.7)
Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Given the following Unit 1 conditions:
Time = 1200:00:
Reactor power = 40%
PCB 20 and PCB 21, Generator Output Breakers OPEN Time = 1200:15:
Main Turbine trips At Time = 1202:00
- 2) reactor heat removal __(2)__ be from forced circulation.
Which ONE of the following completes the statements above?
A. 1. will
- 2. will B. 1. will
- 2. will NOT C. 1. will NOT
- 2. will D. 1. will NOT
- 2. will NOT Monday, March 16, 2020 Page 45 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 23 C General Discussion Answer A Discussion Incorrect. First part is incorrect because the condensate pumps will trip when the turbine trips. The FDW pumps will trip ~ 90 seconds later.
EFDW pumps will then start and feed the SGs. It is plausible because without the slow transfer of power when the turbine trips, it would be correct.
2nd part is correct. The RCPs will still be running.
Answer B Discussion Incorrect. First part is incorrect because the condensate pumps will trip when the turbine trips. The FDW pumps will trip ~ 90 seconds later.
EFDW pumps will then start and feed the SGs. It is plausible because without the slow transfer of power when the turbine trips, it would be correct.
Second part is incorrect because the RCPs will still be running. It is plausible because a slow transfer occurs which means that the RCP busses 1TA & 1TB will be without power for ~ 1.7 seconds. The breakers will remain closed however and the RCPs will remain operating when power returns.
Answer C Discussion CORRECT. First part is correct. The condensate pumps will trip when the turbine trips. The FDW pumps will trip ~ 90 seconds later. EFDW pumps will then start and feed the SGs.
2nd part is correct. A slow transfer of power occurs due to the Generator Output breakers being open when the turbine trips, which means that the RCP busses 1TA & 1TB will be without power for ~ 1.7 seconds. The RCP breakers will remain closed however and the RCPs will continue operating when power returns.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect because the RCPs will still be running. It is plausible because a slow transfer occurs which means that the RCP busses 1TA & 1TB will be without power for ~ 1.7 seconds. The breakers will remain closed however and the RCPs will remain operating when power returns.
Basis for meeting the KA Question requires knowledge of the interrelations between a Turbine trip and the heat removal systems of RCS and Emergency Feedwater.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 47 Q25 Development References Student References Provided ILT 47 Q25 EL-EPD Obj 30 AP/01 Rev 16 EAP-AP01 Obj 03 BWA04 AK2.2 - Turbine Trip Knowledge of the interrelations between the (Turbine Trip) and the following:
(CFR: 41.7 / 45.7)
Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Remarks/Status Monday, March 16, 2020 Page 46 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 23 C Monday, March 16, 2020 Page 47 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWA06 AK1.1 - Shutdown Outside Control Room QUESTION 24 D Knowledge of the operational implications of the following concepts as they apply to the (Shutdown Outside Control Room):
(CFR: 41.8 / 41.10 / 45.3)
Components, capacity, and function of emergency systems.
Given the following on Unit 3 Auxiliary Shutdown Panel:
3B HPI pump Remote/Local Selector in LOCAL position Unit 3 Turbine Bypass Valves in manual controlling SG pressure
- 2) The Unit 3 TBVs __(2)__ close if condenser vacuum lowers below 7 inches hg.
Which ONE of the following completes the statements above?
A. 1. will
- 2. will B. 1. will
- 2. will NOT C. 1. will NOT
- 2. will D. 1. will NOT
- 2. will NOT Monday, March 16, 2020 Page 48 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 24 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible since the HPI pump will start on an ES signal.
Second part is incorrect. Plausible because if the TBVs were in manual in the Control Room and auto at the ASDP, it would be correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible since the HPI pump will start on an ES signal.
Second part is correct.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if the TBVs were in manual in the Control Room and auto at the ASDP, it would be correct.
Answer D Discussion CORRECT. With the Remote/Local Selector in LOCAL at the ASDP, the 3B HPI pump will not auto start on low RCP seal injection flow.
When the TBVs are in manual at the ASDP, the 7 in hg vacuum interlock is defeated.
Basis for meeting the KA Question requires knowledge of the function of components at the Auxiliary Shutdown Panel.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided IC-ASP OBJ 04, 05 ICS-02 Obj 04 U3 AP/08 Rev 16 BWA06 AK1.1 - Shutdown Outside Control Room Knowledge of the operational implications of the following concepts as they apply to the (Shutdown Outside Control Room):
(CFR: 41.8 / 41.10 / 45.3)
Components, capacity, and function of emergency systems.
Remarks/Status Monday, March 16, 2020 Page 49 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE08 EK1.3 - LOCA Cooldown QUESTION 25 C Knowledge of the operational implications of the following concepts as they apply to the (LOCA Cooldown)
(CFR: 41.8 / 41.10 / 45.3)
Annunciators and conditions indicating signals, and remedial actions associated with the ((LOCA Cooldown)
Given the following Unit 1 conditions:
LOCA CD tab in progress ALL SCMs = 4ºF rising RCS pressure is controllable Statalarm 1SA-07/E-6 (ES LPI Bypass Permit) actuated
Which ONE of the following completes the statements above?
A. 1. 890
- 2. will B. 1. 890
- 2. will NOT C. 1. 865
- 2. will D. 1. 865
- 2. will NOT Monday, March 16, 2020 Page 50 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 25 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because 890 psig is where the permit resets. Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because 890 psig is where the permit resets. Second part is incorrect. Plausible because if RCS pressure were not controllable or if SCM = 0, then it would be correct.
Answer C Discussion CORRECT. Statalarm 1SA-07/E6 (ES LPI Bypass Permit) will actuate at an RCS pressure of 865 psig. The LOCA CD tab requires the following to be met to bypass the ES channels.
__ All SCMs > 0°F
__ ES Bypass Permit satisfied
__ RCS pressure controllable In this case all three conditions are met so the channels will be bypassed.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if RCS pressure were not controllable or if SCM = 0, then it would be correct.
Basis for meeting the KA Question requires knowledge of Annunciator actions taken during a LOCA cooldown.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 41 Q26 Development References Student References Provided ILT 41 Q26 1SA-7/E-6 Rev 14 EOP LOCA CD tab Rev 01 IC-ES Obj 05 BWE08 EK1.3 - LOCA Cooldown Knowledge of the operational implications of the following concepts as they apply to the (LOCA Cooldown)
(CFR: 41.8 / 41.10 / 45.3)
Annunciators and conditions indicating signals, and remedial actions associated with the ((LOCA Cooldown)
Remarks/Status Monday, March 16, 2020 Page 51 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE09 EA1.2 - Natural Circulation Operations QUESTION 26 A Ability to operate and / or monitor the following as they apply to the (Natural Circulation Cooldown)
(CFR: 41.7 / 45.5 / 45.6)
Operating behavior characteristics of the facility.
Given the following Unit 1 conditions:
Time = 1200:
Reactor power = 100%
1TA and 1TB lockout occurs Time = 1300:
EOP Forced Cooldown (FCD) tab in progress Natural Circulation cooldown is initiated In accordance with the EOP FCD tab, the crew is directed to
- 1) establish and maintain a cooldown rate of less than a MAXIMUM of 50°F per
__(1)__.
__(2)__ degrees SCM.
Which ONE of the following completes the statements above?
A. 1. hour
- 2. 150 B. 1. hour
- 2. 200 C. 1. half hour
- 2. 150 D. 1. half hour
- 2. 200 Monday, March 16, 2020 Page 52 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 26 A General Discussion Answer A Discussion CORRECT. The FCD tab direction is to establish and maintain a cooldown rate of < 50 degrees per hour. The rate is reduced due to the RV Head lagging the remainder of the system. With a slower cooldown rate the probability of void formation in the head is minimized. Existing pressure is maintained until SCM is 150 degrees. The objective is to maintain RCS pressure high enough to prevent void formations in the system during C/D by providing a large saturation margin for the RCS. Maintaining pressure high also helps to promote flow through the RV Head Vents and therefore helps raise flow around the stagnant portions in the RV Head area to promote cooling in this area.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because 200 inches is the minimum Pzr level required by the FCD tab when the Natural Circ cooldown is commenced.
Answer C Discussion Incorrect. First part is incorrect. Plausible because 50 degrees per 1/2 hour is the Tech Spec cooldown rate when Tcold is 270 degrees and above.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because 50 degrees per 1/2 hour is the Tech Spec cooldown rate when Tcold is 270 degrees and above.
Second part is incorrect. Plausible because 200 inches is the minimum Pzr level required by the FCD tab when the Natural Circ cooldown is commenced.
Basis for meeting the KA Question requires knowledge of the operating behavior of the RCS and Reactor Vessel Head associated with void formation during a Natural Circ Cooldown and the operating parameters and direction given to minimize the impact.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided EAP-FCD Obj 06 EOP FCD tab BWE09 EA1.2 - Natural Circulation Operations Ability to operate and / or monitor the following as they apply to the (Natural Circulation Cooldown)
(CFR: 41.7 / 45.5 / 45.6)
Operating behavior characteristics of the facility.
Remarks/Status Monday, March 16, 2020 Page 53 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE13 EA2.2 - EOP Rules QUESTION 27 A Ability to determine and interpret the following as they apply to the (EOP Rules)
(CFR: 43.5 / 45.13)
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
Given the following Unit 1 conditions:
Time = 0400:
Reactor power = 100%
PSW inoperable Time = 0430:
ALL CBPs trip ALL Emergency FDW pumps fail to start in auto or manual Rule 3 in progress LOHT tab in progress RCS pressure = 2258 psig rising Pzr level = 381 inches rising
- 1) At Time = 0430, Rule 4 (Initiation of HPI Forced Cooling) __(1)__ required to be initiated.
- 2) IF Rule 4 is initiated, it will direct securing __(2)__.
Which ONE of the following completes the statements above?
A. 1. is
- 2. all but one RCP B. 1. is
- 2. one RCP/loop C. 1. is NOT
- 2. all but one RCP D. 1. is NOT
- 2. one RCP/loop Monday, March 16, 2020 Page 54 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 27 A General Discussion Answer A Discussion CORRECT. Rule 4 is initiated because Pzr level is greater than 375 inches. When implemented, Rule 4 secures all but one RCP.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because it is what the LOHT tab does prior to initiating Rule 4.
Answer C Discussion Incorrect. First part is incorrect. Plausible because RCS pressure has not yet reached 2300 psig. Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because RCS pressure has not yet reached 2300 psig.
Second part is incorrect. Plausible because it is what the LOHT tab does prior to initiating Rule 4.
Basis for meeting the KA Question requires the ability to adhere to Rule 4 by having knowledge of when to perform the Rule and the guidance contained within it.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 41 Q17 Development References Student References Provided ILT 41 Q17 EOP Rule 3 EOP Rule 4 EAP-LOHT (Rule 3) Obj 02 EAP-LOHT (Rule 4) Obj 01 BWE13 EA2.2 - EOP Rules Ability to determine and interpret the following as they apply to the (EOP Rules)
(CFR: 43.5 / 45.13)
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
Remarks/Status Monday, March 16, 2020 Page 55 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS003 A4.08 - Reactor Coolant Pump System (RCPS)
QUESTION 28 B Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
RCP cooling water supplies .......................................
Given the following Unit 1 conditions:
Reactor power = 68%
1A1 RCP secured per AP/1/A/1700/016 Section 4D (Loss of RCP Seal Return)
- 1) The EARLIEST time that AP/16 Section 4D directs closing the 1A1 RCP motor cooler inlet and outlet valves, 1LPSW-7&8, is __(1)__ after 1A1 RCP shutdown.
- 2) Individual valve position indication __(2)__ available for 1LPSW-7&8 on the control board.
Which ONE of the following completes the statements above?
A. 1. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- 2. is B. 1. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- 2. is NOT C. 1. immediately
- 2. is D. 1. immediately
- 2. is NOT Monday, March 16, 2020 Page 56 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 28 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because there are other valves in the control room that have only one switch to operate, but have individual position indication on the control board, such as HP-1/CC-1, HP-2/CC-2, PR-81/84, PR-87/90.
Answer B Discussion CORRECT. AP/16 Section 4D directs closing the associated RCP motor cooler inlet and outlet valves, 1LPSW-7&8, after the RCP has been shutdown >/= 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. 1LPSW-7&8 are both controlled by one switch with only one green and one red light for position indication on the control board. The operator has to use the OAC to check individual valve position.
Answer C Discussion Incorrect. First part is incorrect. Plausible because AP/16 Section 4C directs closing the RCP motor cooler inlet and outlet valves, 1LPSW-7&8, immediately after RCP shutdown if the RCP had a high oil level.
Second part is incorrect. Plausible because there are other valves in the control room that have only one switch to operate, but have individual position indication on the control board, such as HP-1/CC-1, HP-2/CC-2, PR-81/84, PR-87/90.
Answer D Discussion Incorrect. First part is incorrect. Plausible because AP/16 Section 4C directs closing the RCP motor cooler inlet and outlet valves, 1LPSW-7&8, immediately after RCP shutdown if the RCP had a high oil level.
Second part is correct.
Basis for meeting the KA Question requires the ability to operate and monitor the RCP motor cooling water supplies in the control room (1LPSW-7&8 valve switch and position indication).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided PNS-CPM Obj. 1 AP/1/A/1700/016 Rev 37 EAP-AP/16 Obj 04 SYS003 A4.08 - Reactor Coolant Pump System (RCPS)
Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
RCP cooling water supplies .......................................
Remarks/Status Monday, March 16, 2020 Page 57 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS004 K5.19 - Chemical and Volume Control System QUESTION 29 C Knowledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45.7)
Concept of SDM .................................................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
A group 2 safety rod drops fully into the core and cannot be moved AP/1/A/1700/001 (Unit Runback) initiated Current conditions:
Reactor power = 55%
Group 7 control rods = 30% withdrawn CRS directs the RO to utilize the control rod position curves in the COLR to determine if adequate SDM exists In accordance with TS 3.2.1 (Regulating Rod Position Limits), which ONE of the following is the required action, if any, related to SDM following the determination?
REFERENCE PROVIDED A. NO action required B. Initiate boration to exit Unacceptable Region within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Initiate boration to exit Unacceptable Region within 15 minutes D. Initiate boration to exit Unacceptable Region within 30 minutes Monday, March 16, 2020 Page 58 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 29 C General Discussion Answer A Discussion Incorrect. Plausible because if the candidate uses the Control Rod Position Setpoints No Inoperable Rod, 4 Pump Flow curve, it will appear correct.
Answer B Discussion Incorrect. Plausible because for this scenario, AP/01 directs verifying > 1% SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Answer C Discussion CORRECT. Per the Control Rod Position Setpoints 1 Inoperable Rod, 4 Pump Flow curve from the COLR, plotting 55% power with Group 7 control rods at 30% withdrawn is in the Unacceptable Region. Per TS 3.2.1 (Regulating Rod Position Limits), Condition B says if Regulating rod groups are positioned in the unacceptable region, initiate boration to restore SDM to within the limits specified in the COLR within 15 minutes.
Answer D Discussion Incorrect. Plausible because if QPT is greater than the transient limit and less than or equal to the maximum limit, TS 3.2.3 has a 30 minute completion time to reduce power 2% for each 1% of QPT greater than the steady state limit.
Basis for meeting the KA Question requires knowledge of time limits and actions required to utilize the CVCS (CBAST) to restore SDM when it is determined to not be met.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided COLR Rod Curves COLR Rod Curves ADM-TSS Obj. 3 TS 3.2.1 SYS004 K5.19 - Chemical and Volume Control System Knowledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45.7)
Concept of SDM .................................................
Remarks/Status Monday, March 16, 2020 Page 59 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS005 K5.02 - Residual Heat Removal System (RHRS)
QUESTION 30 A Knowledge of the operational implications of the following concepts as they apply the RHRS: (CFR: 41.5 / 45.7)
Need for adequate subcooling ......................................
Given the following Unit 1 conditions:
LOCA CD tab in progress Cooldown and de-pressurization in progress Core SCM = 6°F stable LPI piggyback supplying HPI pump suction LPI pump rooms are accessible In accordance with the LOCA CD tab
- 1) During the cooldown, LPI __(1)__ be aligned in a split flow arrangement with one train supplying HPI pump suction and the other train providing decay heat removal.
- 2) IF LPI is aligned in the split flow arrangement described above, the LPI train supplying the HPI pumps will take suction from the __(2)__.
Which ONE of the following completes the statements above?
A. 1. will
- 2. RBES B. 1. will
- 2. DHR drop line C. 1. will NOT
- 2. RBES D. 1. will NOT
- 2. DHR drop line Monday, March 16, 2020 Page 60 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 30 A General Discussion Answer A Discussion CORRECT. With Core SCM > 0, LPI will be aligned in a split flow arrangement during the cooldown. 1B LPI pump will take suction on the RBES and supply HPI pump suction while RCS pressure is still too high for the LPI pump to inject into the RCS when taking suction on the RBES. 1A LPI pump will take suction on the DHR drop line and inject into the RCS. 1A LPI pump will be able to inject into the RCS because of the higher pressure of the DHR drop line.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if it were the other LPI train (supplying decay heat removal), it would be correct.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if SCM = 0, it would be correct.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if SCM = 0, it would be correct.
Second part is incorrect. Second part is incorrect. Plausible because if it were the other LPI train (supplying decay heat removal), it would be correct.
Basis for meeting the KA Question requires knowledge of the need for subcooling to transition the LPI system from the ECCS mode to the Decay Heat Removal mode in the LOCA CD tab.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided EAP-LCD Obj R7 EOP LOCA CD tab Rev 0 SYS005 K5.02 - Residual Heat Removal System (RHRS)
Knowledge of the operational implications of the following concepts as they apply the RHRS: (CFR: 41.5 / 45.7)
Need for adequate subcooling ......................................
Remarks/Status Monday, March 16, 2020 Page 61 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS005 K6.03 - Residual Heat Removal System (RHRS)
QUESTION 31 C Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: (CFR: 41.7 / 45.7)
RHR heat exchanger ..............................................
Given the following Unit 2 conditions:
RCS cooldown in progress 2A LPI cooler isolated due to cooler leak
- 1) The LPI Decay Heat Removal mode that will be used for the INITIAL transition to LPI cooling is __(1)__.
- 2) The HIGHEST RCS pressure that will allow aligning LPI in the Normal Decay Heat Removal mode is __(2)__ psig.
Which ONE of the following completes the statements above?
A. 1. High Pressure
- 2. 115 B. 1. High Pressure
- 2. 220 C. 1. Switchover
- 2. 115 D. 1. Switchover
- 2. 220 Monday, March 16, 2020 Page 62 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 31 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because if the 2B LPI Cooler was isolated instead of the 2A, it would be correct.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because if the 2B LPI Cooler was isolated instead of the 2A, it would be correct.
Second part is incorrect. Plausible since it would be correct for Unit 3.
Answer C Discussion CORRECT. With the 2A LPI Cooler isolated, the LPI system will be aligned in the Switchover mode when LPI is placed in service during the cooldown. The Switchover mode will be used until RCS pressure is < 125 psig, at which time LPI can be placed in the Normal Decay Heat Removal (DHR) mode.
Answer D Discussion Incorrect. First part is correct. With the 2A LPI Cooler isolated, the LPI system will be aligned in the Switchover mode when LPI is placed in service during the cooldown.
Second part is incorrect. Plausible since it would be correct for Unit 3.
Basis for meeting the KA Question requires knowledge of the effect a loss of the 2A LPI cooler will have on the RHRS (LPI system).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 16-2 Q32 Development References Student References Provided ILT 16-2 Q32 PNS-LPI Obj 9, 13, 14 SYS005 K6.03 - Residual Heat Removal System (RHRS)
Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: (CFR: 41.7 / 45.7)
RHR heat exchanger ..............................................
Remarks/Status Monday, March 16, 2020 Page 63 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS006 K2.02 - Emergency Core Cooling System (ECCS)
QUESTION 32 D Knowledge of bus power supplies to the following: (CFR: 41.7)
Valve operators for accumulators ...................................
Which ONE of the following is the power supply for 3CF-2 (3B CFT Outlet)?
A. 3XC B. 3XL C. 3XN D. 3XP Monday, March 16, 2020 Page 64 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 32 D General Discussion Answer A Discussion Incorrect. Plausible since 3XC is also a 600V MCC that supplies other plant valves.
Answer B Discussion Incorrect. Plausible since 3XL is also a 600V MCC that supplies other plant valves.
Answer C Discussion Incorrect. Plausible since 3XN is also a 600V MCC that supplies other plant valves.
Answer D Discussion CORRECT. The power supply for 3CF-2 is 3XP MCC.
Basis for meeting the KA Question requires knowledge of the bus power supplies for valve operators on accumulators, which at Oconee are the Core Flood Tanks (CFT).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 18-1 Q34 Development References Student References Provided ILT 18-1 Q34 PNS-CF Obj 1 SYS006 K2.02 - Emergency Core Cooling System (ECCS)
Knowledge of bus power supplies to the following: (CFR: 41.7)
Valve operators for accumulators ...................................
Remarks/Status Monday, March 16, 2020 Page 65 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS007 A4.09 - Pressurizer Relief Tank/Quench Tank System (PRTS)
QUESTION 33 C Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
Relationships between PZR level and changing levels of the PRT and bleed holdup tank .....................................
Given the following Unit 1 conditions:
Reactor power = 100%
Leak through 1RC-66 (PORV) = 0.6 gpm Pzr level will __ (1) __ and initially Quench Tank __ (2) __ will rise.
Which ONE of the following completes the statement above?
A. 1. rise
- 2. level B. 1. rise
- 2. pressure C. 1. remain constant
- 2. level D. 1. remain constant
- 2. pressure Monday, March 16, 2020 Page 66 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 33 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because of the misconception that with a Pzr steam space leak Pzr level will rise.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because of the misconception that with a Pzr steam space leak Pzr level will rise.
Second part is incorrect. Plausible because steam is going into the QT.
Answer C Discussion CORRECT. 1HP-120 will mainatin Pzr level constant. QT level will rise from the condensed steam.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because steam is going into the QT.
Basis for meeting the KA Question requires knowledge of the relationship between Pzr and QT(PRT) levels.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 42 Q34 Development References Student References Provided ILT 42 Q34 PNS-PZR Obj 27 SYS007 A4.09 - Pressurizer Relief Tank/Quench Tank System (PRTS)
Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
Relationships between PZR level and changing levels of the PRT and bleed holdup tank .....................................
Remarks/Status Monday, March 16, 2020 Page 67 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS008 A3.03 - Component Cooling Water System (CCWS)
QUESTION 34 B Ability to monitor automatic operation of the CCWS, including: (CFR: 41.7 / 45.5)
All flow rate indications and the ability to evaluate the performance of this closed-cycle cooling system.. .................
Which ONE of the following will result in the Standby Component Cooling pump receiving an automatic start signal?
A. CRD Outlet HDR Flow = 136 gpm B. Component Cooling Total Flow = 568 gpm C. Component Cooling Pump Pressure = 95 psig D. ONE Main Feeder Bus de-energized for 21 seconds Monday, March 16, 2020 Page 68 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 34 B General Discussion Answer A Discussion Incorrect. Plausible because 136 gpm is below the interlock (138 gpm) to prevent energizing the CRDs.
Answer B Discussion CORRECT. The standby CC pump starts when total CC flow lowers to 575 gpm.
Answer C Discussion Incorrect. 95 psig is well below the normal system pressure of about 125 psig. A candidate could have the misconception that the standby pump started on low header pressure.
Answer D Discussion Incorrect. Plausible because it would be correct it BOTH MFBs were deenergized for greater than 20 seconds. MFB Monitior Panel would actuate and send a start signal to BOTH CC pumps.
Basis for meeting the KA Question requires the ability to monitor automatic operation of the CC System by knowing the flow rate that will cause the Standby CC pump to auto start.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 41 Q35 Development References Student References Provided ILT 41 Q35 PNS-CC Obj 15 SYS008 A3.03 - Component Cooling Water System (CCWS)
Ability to monitor automatic operation of the CCWS, including: (CFR: 41.7 / 45.5)
All flow rate indications and the ability to evaluate the performance of this closed-cycle cooling system.. .................
Remarks/Status Monday, March 16, 2020 Page 69 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS010 A1.04 - Pressurizer Pressure Control System (PZR PCS)
QUESTION 35 A Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: (CFR: 41.5 / 45.5)
Effects of temperature change during solid operation ..................
Given the following Unit 1 conditions:
Recovery from HPI Forced Cooling in progress Pzr level = 400 inches stable Lowest SCM = 33°F When the PORV is closed.
- 1) a one degree rise in temperature can raise RCS pressure a MAXIMUM of approximately __(1)__ psig.
Which ONE of the following completes the statements above?
A. 1. 100
- 2. HPI flow B. 1. 100
- 2. number of Pzr heaters energized C. 1. 180
- 2. HPI flow D. 1. 180
- 2. number of Pzr heaters energized Monday, March 16, 2020 Page 70 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 35 A General Discussion Answer A Discussion CORRECT. In solid plant operations, a 1 degree change in RCS temp = approximately a 100 psig change in RCS pressure. When recovering from HPI Forced Cooling with SCM > 0 degrees, RCS pressure control will be directly proportional to RCS temperature and HPI flow.
Answer B Discussion Incorrect. First part is correct. Second part is incorrect since the Pzr is subcooled. If the Pzr was saturated, it could be correct.
Answer C Discussion Incorrect. First part is incorrect. Plausible because 180 is the Pzr level setpoint for Abnormal Containment conditions.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because 180 is the Pzr level setpoint for Abnormal Containment conditions.
Second part is incorrect since the Pzr is subcooled. If the Pzr was saturated, it could be correct.
Basis for meeting the KA Question requires knowledge of the effects of temperature change during solid operation and the ability to predict changes in RCS pressure when operating the Pzr PCS controls (closing 1RC-66).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided EAP-HPI CD Obj 10 EOP Encl 5.40 Rev 1 SYS010 A1.04 - Pressurizer Pressure Control System (PZR PCS)
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: (CFR: 41.5 / 45.5)
Effects of temperature change during solid operation ..................
Remarks/Status Monday, March 16, 2020 Page 71 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS010 A4.01 - Pressurizer Pressure Control System (PZR PCS)
QUESTION 36 B Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
PZR spray valve .................................................
Given the following Unit 2 conditions:
Time = 0800:
Reactor power = 100%
Time = 0805:
FDW transient occurs RCS pressure peaked at 2210 psig
- 1) At Time = 0805, 2RC-1 __(1)__ open.
Which ONE of the following completes the statements above?
A. 1. is
- 2. 2.MAX B. 1. is
- 2. median select C. 1. is NOT
- 2. 2.MAX D. 1. is NOT
- 2. median select Monday, March 16, 2020 Page 72 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 36 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because it would be correct for the RCS high pressure trip signals in RPS.
Answer B Discussion CORRECT. The spray valve (RC-1) opens at 2205 psig and closes at 2155 psig. 2RC-1 is controlled by the ICS median selected narrow range (NR) RCS pressure signal.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if RCS pressure had only increased to 2200 psig, it would be correct.
Second part is incorrect. Plausible because it would be correct for the RCS high pressure trip signals in RPS.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if RCS pressure had only increased to 2200 psig, it would be correct.
Second part is correct.
Basis for meeting the KA Question requires the ability to monitor RC-1 (PZR spray valve) in the control room and whether the valve will be open or closed given values for RCS pressure. Also requires knowledge of how the controlling signal is generated.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided PNS-PZR Obj 06, 07 SYS010 A4.01 - Pressurizer Pressure Control System (PZR PCS)
Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
PZR spray valve .................................................
Remarks/Status Monday, March 16, 2020 Page 73 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS012 A2.06 - Reactor Protection System (RPS)
QUESTION 37 D Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)
Failure of RPS signal to trip the reactor .............................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
BOTH Main Feedwater Pumps trip Current conditions:
Reactor power = 57% slowly lowering
- 1) The correct sequence of activities directed by Rule 1 (ATWS) is to __(1)__.
Which ONE of the following completes the statements above?
A. 1. dispatch an operator to open the CRD breakers THEN align HPI injection from the BWST
- 2. NOT wear C. 1. align HPI injection from the BWST THEN dispatch an operator to open the CRD breakers
- 2. NOT wear Monday, March 16, 2020 Page 74 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 37 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible since opening the CRD breakers is an action directed by Rule 1 with the intent of remotely tripping the reactor. It is reasonable for the candidate to conclude the highest priority is to accomplish the reactor trip. Since opening the CRD breakers is done outside the control room and takes several minutes to accomplish it would be consistant with getting the reactor tripped to go ahead and get someone dispatched to open the breakers prior to aligning HPI injection.
Second part is incorrect. Plausible since the normal expectation is to wear Arc Flash PPE when operating a 600V breaker. Without the specific direction NOT to wear the PPE, the AO may take unnecessary time to don this PPE.
Answer B Discussion Incorrect. First part is incorrect. Plausible since opening the CRD breakers is an action directed by Rule 1 with the intent of remotely tripping the reactor. It is reasonable for the candidate to conclude the highest priority is to accomplish the reactor trip. Since opening the CRD breakers is done outside the control room and takes several minutes to accomplish it would be consistant with getting the reactor tripped to go ahead and get someone dispatched to open the breakers prior to aligning HPI injection.
Second part is correct.
Answer C Discussion Incorrect. First part is correct. HPI is aligned prior to dispatching an operator to open the CRD breakers.
Second part is incorrect. Plausible since the normal expectation is to wear Arc Flash PPE when operating a 600V breaker. Without the specific direction NOT to wear the PPE, the AO may take unnecessary time to don this PPE.
Answer D Discussion CORRECT. First part is correct. HPI is aligned prior to dispatching an operator to open the CRD breakers.
Second part is correct. Rule 1 does have the control room operator direct the AO NOT to wear Arc Flash PPE.
Basis for meeting the KA Question requires knowledge of Rule 1 and the guidance used to mitigate the consequences of a failure of the RPS to trip the reactor.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 39 Q67 Development References Student References Provided ILT 39 Q67 EAP-UNPP EOP Rule 1 Rev 3 SYS012 A2.06 - Reactor Protection System (RPS)
Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)
Failure of RPS signal to trip the reactor .............................
Remarks/Status Monday, March 16, 2020 Page 75 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS013 K6.01 - Engineered Safety Features Actuation System (ESFAS)
QUESTION 38 C Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7 / 45.5 to 45.8)
Sensors and detectors ............................................
Unit 3 plant conditions:
Reactor power = 100%
ES Analog Channel "C" WR RCS pressure signal fails LOW No fault signals are present ES Channels __(1)__ are in a __(2)__ logic.
Which ONE of the following completes the statement above?
A. 1) 1 - 4
- 2) 2 out of 2 B. 1) 1 - 6
- 2) 2 out of 2 C. 1) 1 - 4
- 2) 1 out of 2 D. 1) 1 - 6
- 2) 1 out of 2 Monday, March 16, 2020 Page 76 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 38 C General Discussion Answer A Discussion Incorrect: First part is correct.
Second part is incorrect. Plausible because it would be correct if the instrument failed HIGH or if a FAULT signal was present.
Answer B Discussion Incorrect: First part is incorrect. Plausible because it would be correct if RCS pressure fed into ES 1 - 6 like RB pressure.
Second part is incorrect. Plausible because it would be correct if the instrument failed HIGH or if a FAULT signal was present.
Answer C Discussion CORRECT: Unfaulted signals are compared to the two instrument signals from the other channels. The 2.MIN is calculated and used for comparison in two separate function comparators for HPI and LPI. When an individual channel's 2.MIN value is at the Comparator setpoint that trip function is sent as (1) of the 2 out of 3 inputs to the Voter.
Since all 6 Channels (both Subsystems) are processing the same inputs all 6 Instrument Channels 2.MIN should send the actuation signal to their respective Voters.
When the Voter receives a 2/3 Trip input from the Instrument Channels it will actuate the Output Modules and energize the RO relays to place associated components in their ES position. Therefore if 1 of the 2 remaining WR pressure inputs lowers to the setpoint, ES will actuate.
Answer D Discussion Incorrect: First part is incorrect. Plausible because it would be correct if RCS pressure fed into ES 1 - 6 like RB pressure.
Second part is correct.
Basis for meeting the KA Question requires knowledge of the effect of a failed WR RCS pressure instrument on the ES system.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 2007 Q51 Development References Student References Provided ILT 2007 Q51 IC-ES Obj 06 SYS013 K6.01 - Engineered Safety Features Actuation System (ESFAS)
Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7 / 45.5 to 45.8)
Sensors and detectors ............................................
Remarks/Status Monday, March 16, 2020 Page 77 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS022 A1.02 - Containment Cooling System (CCS)
QUESTION 39 D Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: (CFR: 41.5 / 45.5)
Containment pressure ............................................
Given the following Unit 3 conditions:
Time = 0800:
Reactor Power = 100%
Reactor Building average temperature = 120°F stable RBCUs 3B and 3C running in LOW Speed 3LPSW-18, 21, 24 are FULL OPEN for testing Time = 0830:
Inadvertent ES Channel 5 actuation
- 2) In accordance with TS 3.6.4 (Containment Pressure), the RB high pressure TS Limit is < __(2)__ psig.
Which ONE of the following completes the statements below?
A. 1. lower than
- 2. 2.45 B. 1. lower than
- 2. 1.2 C. 1. approximately the same as
- 2. 2.45 D. 1. approximately the same as
- 2. 1.2 Monday, March 16, 2020 Page 78 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 39 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because without the mixed speed circuit, it would be correct, since ES-5 starts the 3A RBCU.
Second part is incorrect. Plausible because the low TS limit for RB pressure is (-) 2.45 psig, not (+) 2.45 psig.
Answer B Discussion Incorrect. First part is incorrect. Plausible because without the mixed speed circuit, it would be correct, since ES-5 starts the 3A RBCU.
Second part is correct.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because the low TS limit for RB pressure is (-) 2.45 psig, not (+) 2.45 psig.
Answer D Discussion CORRECT. When ES Channel 5 actuates, it will send a start signal to 3A and 3B RBCUs and the Mixed Speed circuit will stop 3C RBCU. So, initially 2 RBCUs are operating in LOW speed and after ES Channel 5 actuates, there will still be only 2 RBCUs operating in LOW speed with no change in LPSW flow, so RB pressure will remain approximately the same.
The RB high pressure limit per TS 3.6.4 is 1.2 psig.
Basis for meeting the KA Question requires the ability to predict RB pressure response based on operating RBCUs.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 43 Q 54 Development References Student References Provided ILT 43 Q54 TS 3.6.4 PNS-RBC Obj 01 SYS022 A1.02 - Containment Cooling System (CCS)
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: (CFR: 41.5 / 45.5)
Containment pressure ............................................
Remarks/Status Monday, March 16, 2020 Page 79 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS026 A2.09 - Containment Spray System (CSS)
QUESTION 40 C Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Radiation hazard potential of BWST .................................
Given the following Unit 1 conditions:
The Reactor trips from 100% power due to a LBLOCA
- 1) EOP Encl. 5.1 (ES Actuation) directs initiation of Encl. 5.12 (ECCS Suction Swap to RBES) at a MAXIMUM level of __(1)__ feet in the BWST.
- 2) TSP (Trisodium Phosphate Dodecahydrate) is added to the RB Emergency Sump to allow RBS to __(2)__.
Which ONE of the following completes the statements above?
A. 1. 15
- 2. aid in keeping Iodine in solution, ultimately reducing offsite dose B. 1. 15
- 2. minimize hydrogen production from the boric acid reaction with Zircoloy C. 1. 19
- 2. aid in keeping Iodine in solution, ultimately reducing offsite dose D. 1. 19
- 2. minimize hydrogen production from the boric acid reaction with Zircoloy Monday, March 16, 2020 Page 80 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 40 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because during a LBLOCA, Encl 5.12 will direct securing HPI pumps at a level of 15 feet in the BWST.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because during a LBLOCA, Encl 5.12 will direct securing HPI pumps at a level of 15 feet in the BWST.
Second part is incorrect. Plausible since it does inhibit H2 production due to the boric acid reaction with Zinc and Aluminum.
Answer C Discussion CORRECT. EOP Encl. 5.1 (ES Actuation) states IAAT BWST level is less than or equal to 19 feet, then initiate Encl. 5.12 (ECCS Suction Swap to RBES). Encl. 5.12 will eventually direct isolation of the BWST when the appropriate level is reached. TSP is added to aid in keeping Iodine in solution to minimize dose from iodine in the RB atmosphere.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since it does inhibit H2 production due to the boric acid reaction with Zinc and Aluminum.
Basis for meeting the KA Per NRC Chief on 1/03/20, question concerning TSP and RBS water's effect on iodine in containment would be permissable to meet this K/A.
Question also requires knowledge of the procedural guidance in EOP Encl. 5.1 (ES Actuation) that directs the initiation of Encl 5.12 to swap LPI and RBS suction to the RBES and eventually isolate the BWST at the appropriate level.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 43 Q40 Development References Student References Provided ILT 43 Q40 PNS-RBS Obj 14 EAP-LOSCM Obj 12 EOP Encl 5.1 Rev. 01 SYS026 A2.09 - Containment Spray System (CSS)
Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Radiation hazard potential of BWST .................................
Remarks/Status 1/03/20 - Chief stated we could write question concerning TSP Baskets and RBS water effect in containment on iodine.
Monday, March 16, 2020 Page 81 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS039 A3.02 - Main and Reheat Steam System (MRSS)
QUESTION 41 C Ability to monitor automatic operation of the MRSS, including : (CFR: 41.5 / 45.5)
Isolation of the MRSS ............................................
Given the following Unit 3 conditions:
Initial conditions:
Reactor power = 100%
3MS-112 & 3MS-173, (SSRH 3A/3B Controls) are OPEN in MANUAL 3MS-77, 78, 80, 81, (MS to SSRH's) control switches in OPEN Current conditions:
Main Turbine trips
- 2) 3MS-77, 78, 80, 81 will __(2)__.
Which ONE of the following completes the statements above?
A. 1. remain open
- 2. remain open B. 1. remain open
- 2. close C. 1. close
- 2. remain open D. 1. close
- 2. close Monday, March 16, 2020 Page 82 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 41 C General Discussion Answer A Discussion Incorrect: First part is incorrect because 3MS-112/173 will close whether their control switch is in auto or manual when the reactor trips. It is plausible because the switch is in MANUAL.
Second part is correct. MS-77, 78, 80, 81 will remain open if their control switches are in open when the reactor trips.
Answer B Discussion Incorrect: First part is incorrect because 3MS-112/173 will close whether their control switch is in auto or manual when the reactor trips. It is plausible because the switch is in MANUAL.
Second part is incorrect because 3MS-77, 78, 80, 81 will remain open. It is plausible because 3MS-112/173 will close whether their control switch is in auto or manual when the reactor trips and this makes it reasonable to assume that 3MS-77, 78, 80, 81 will close also.
Answer C Discussion CORRECT. First part is correct. 3MS-112/173 will close whether their control switch is in auto or manual when the reactor trips.
Second part is correct. MS-77/78/80/81 will remain open if their control switches are in open when the reactor trips.
Answer D Discussion Incorrect: First part is correct. 3MS-112/173 will close whether their control switch is in auto or manual when the reactor trips.
Second part is incorrect because 3MS-77, 78, 80, 81 will remain open. It is plausible because 3MS-112/173 will close whether their control switch is in auto or manual when the reactor trips and this makes it reasonable to assume that 3MS-77, 78, 80, 81 will close also.
Basis for meeting the KA Question requires knowledge of automatic actions (Isolation) of the MSRs.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 16-1 Q43 Development References Student References Provided ILT 16-1 Q43 STG-MSR Obj 11 SYS039 A3.02 - Main and Reheat Steam System (MRSS)
Ability to monitor automatic operation of the MRSS, including : (CFR: 41.5 / 45.5)
Isolation of the MRSS ............................................
Remarks/Status Monday, March 16, 2020 Page 83 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS059 2.1.7 - Main Feedwater (MFW) System QUESTION 42 D SYS059 GENERIC Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13)
Given the following Unit 3 conditions:
Time = 04:00:00:
Reactor power = 70% stable 3A Main FDW Pump suction pressure = 236 psig lowering Time = 04:01:25:
3A Main FDW Pump suction pressure = 230 psig lowering At Time = 04:01:25:
- 1) 3A Main FDW pump __(1)__ tripped.
- 2) U3 Reactor power is __(2)__.
A. 1. has
- 2. stable at 65%
B. 1. has
- 2. lowering at 20% per minute C. 1. has NOT
- 2. stable at 70%
D. 1. has NOT
- 2. lowering at 20% per minute Monday, March 16, 2020 Page 84 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 42 D General Discussion Answer A Discussion Incorrect: First part is incorrect. Plausible because it would be correct if FDW pump suction pressure had been below 235 psig for 90 seconds.
Second part is incorrect. Plausible since the plant runs back to 65% power when a MFDW pump trips.
Answer B Discussion Incorrect: First part is incorrect. Plausible because it would be correct if FDW pump suction pressure had been below 235 psig for 90 seconds.
Second part is correct.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because it would be correct if FDW pump suction pressure had remained above 235 psig.
Answer D Discussion CORRECT. Conditions are met for a CBP/FDW Pump Low Suction Pressure runback (<235 psig; for >90 sec, MFDW pump trips; Runback rate = 20%/min.). When FDW pump suction pressure lowers below 235 psig, the plant runs back at 20% / min. In 90 seconds, if the suction pressure is still below 235 psig, the MFDW pump will trip. Only 85 secs have elapsed, therefore the runback is still in progress and the MFDW pump has not tripped.
Basis for meeting the KA Question requires the ability to evaluate the status of Main FDW and reactor power based on Main FDW pump suction pressure.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 42 Q45 Development References Student References Provided ILT 42 Q45 CF-FDW Obj 03 SYS059 2.1.7 - Main Feedwater (MFW) System SYS059 GENERIC Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 85 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS061 K1.02 - Auxiliary / Emergency Feedwater (AFW) System QUESTION 43 C Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: (CFR: 41.2 to 41.9 /
45.7 to 45.8)
MFW System ...................................................
Given the following on Unit 2:
Initial conditions:
Reactor power = 100%
Current conditions:
Both MFDW pumps trip Rule 3 in progress 2A EFDW flow = 95 gpm stable 2FDW-315 will NOT control in auto or manual
- 1) In accordance with EOP Encl. 5.27 (Alternate Methods for Controlling EFDW Flow) the 2A SG level will be controlled using __(1)__.
- 2) In accordance with Rule 7, 2A SG level will be controlled at a MINIMUM of __(2)__
inches.
Which ONE of the following completes the statements above?
A. 1. 2FDW-315 local operation
- 2. 25 B. 1. 2FDW-315 local operation
- 2. 30 C. 1. 2FDW-35 from Control Room
- 2. 25 D. 1. 2FDW-35 from Control Room
- 2. 30 Monday, March 16, 2020 Page 86 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 43 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because Encl 5.27 directs local operation of 2FDW-315 if the Startup valve cannot be used.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because Encl 5.27 directs local operation of 2FDW-315 if the Startup valve cannot be used.
Second part is incorrect. Plausible because 30 inches is the normal setpoint when feeding with EFDW with RCPs on.
Answer C Discussion CORRECT. If 2FDW-315 will not control in auto or manual, Rule 3 directs initiating Encl 5.27, which will direct feeding through the MFDW Startup Control valve (2FDW-35). Rule 7 says if the SG is being fed with a MFDW Startup control valve, Maintain level at 25 - 35 inches.
2FDW-35 auto setpoint is 25 inches.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because 30 inches is the normal setpoint when feeding with EFDW with RCPs on.
Basis for meeting the KA Question requires knowledge of feeding the SGs with Emergency FDW through a Main FDW control valve.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided EAP-LOHT Rule 3 Obj 04 EAP-LOHT Encl 5.27 Obj 12 EAP-LOHT Rule 7 Obj R27 U2 Rule 3 U2 Rule 7 U2 Encl 5.27 SYS061 K1.02 - Auxiliary / Emergency Feedwater (AFW) System Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: (CFR: 41.2 to 41.9 /
45.7 to 45.8)
MFW System ...................................................
Remarks/Status Monday, March 16, 2020 Page 87 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS061 K3.02 - Auxiliary / Emergency Feedwater (AFW) System QUESTION 44 B Knowledge of the effect that a loss or malfunction of the AFW will have on the following: (CFR: 41.7 / 45.6)
S/G ............................................................
Given the following Unit 1 conditions:
Time = 0400:
Reactor power = 100%
TDEFDW Pump OOS Switchyard Isolation occurs Time = 0403:
1A and 1B MDEFDW Pumps operating Power is lost to the Moore Controller HAND/AUTO Station for 1FDW-316 1B SG level will ______.
Which ONE of the following completes the statement above?
NO OPERATOR ACTIONS ARE TAKEN A. maintain at 30 inches B. maintain at 240 inches C. steadily lower to dryout D. steadily rise and overflow to the steam lines Monday, March 16, 2020 Page 88 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 44 B General Discussion Answer A Discussion Incorrect. Plausible because it would be correct if the RCPs were operating.
Answer B Discussion CORRECT. It reverts to the auto level control circuit and level will be maintained at 240 inches.
Answer C Discussion Incorrect. Plausible if applicant believes the valve would remain closed (as it is at full power).
Answer D Discussion Correct. Plausible if applicant assumes the failure mode is the same as for loss of power to the selected control train.
Basis for meeting the KA Question requires knowledge of the failure modes of FDW-316 and the effect on OTSG level.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 2007 Retest Q46 Development References Student References Provided ILT 2007 Retest Q46 CF-EF SYS061 K3.02 - Auxiliary / Emergency Feedwater (AFW) System Knowledge of the effect that a loss or malfunction of the AFW will have on the following: (CFR: 41.7 / 45.6)
S/G ............................................................
Remarks/Status Monday, March 16, 2020 Page 89 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS062 K3.01 - AC Electrical Distribution System QUESTION 45 C Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: (CFR: 41.7 / 45.6)
Major system loads ..............................................
Given the following Unit 2 conditions:
Reactor power = 100%
2TD Switchgear de-energizes Which ONE of the following remains available?
A. 2C RBCU B. 2B LPI pump C. 2B HPI pump D. 2A MD EFDW pump Monday, March 16, 2020 Page 90 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 45 C General Discussion Answer A Discussion Incorrect. Plausible because if 2TC or 2TE had de-energized, it would be correct.
Answer B Discussion Incorrect. Plausible because if 2TC or 2TE had de-energized, it would be correct.
Answer C Discussion CORRECT. 2B HPI pump is powered from 2TE switchgear.
Answer D Discussion Incorrect. Plausible because if 2TC or 2TE had de-energized, it would be correct.
Basis for meeting the KA Question requires knowledge of the effect a loss of 2TD 4160V Switchgear has on major system loads.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 2009B Q46 Development References Student References Provided ILT 2009B Q46 IC-ES Obj 28 SYS062 K3.01 - AC Electrical Distribution System Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: (CFR: 41.7 / 45.6)
Major system loads ..............................................
Remarks/Status Monday, March 16, 2020 Page 91 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS062 K4.01 - AC Electrical Distribution System QUESTION 46 C Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Bus lockouts ....................................................
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 22% power CT-1 Amps = 2000 Central Switchyard is energizing the STBY Buses PCB 17 (OCONEE WH. STARTUP TRANS. CT1 TIE) is open for maintenance Current conditions:
Yellow Bus lockout occurs Power to Unit 1 Main Feeder Buses will be supplied from ______ Transformer.
Which ONE of the following completes the statement above?
A. 1T B. CT-4 C. CT-5 D. CT-1 Monday, March 16, 2020 Page 92 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 46 C General Discussion Answer A Discussion Incorrect: Plausible if the candidate fails to recognize that the conditions given indicate 1T is not currently supplying power to the MFBs. If the auxiliaries had been swapped to 1T Transformer in the initial conditions, it would be correct.
Answer B Discussion Incorrect: Plausible since CT-4 would be the preferred source of power to the standby buses normally and if Central Switchyard was not energizing the Standby Buses in the initial conditions, it would be correct. However, since CT-5 is already supplying the Standby buses, CT-4 will not.
Answer C Discussion CORRECT: If the Red bus path is not available (PCB-17 open) and Central path is energizing the Standby Buses, this will be the power path.
Since the SL breakers are closed, the SK breakers can NOT close.
Answer D Discussion Incorrect: Plausible since CT-1could be energized via the RED bus if PCB-17 was closed/operable and this would be the first choice of power after a unit trip.
Basis for meeting the KA Question requires knowledge of the design of the AC Distribution System in order to know how power will be restored with the given plant status following a Yellow Bus Lockout.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 2009 Q46 Development References Student References Provided ILT 2009 Q46 EL-PSL Obj 07, 08 EL-EPD Obj 12, 13, 18 SYS062 K4.01 - AC Electrical Distribution System Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Bus lockouts ....................................................
Remarks/Status Monday, March 16, 2020 Page 93 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS063 K1.02 - DC Electrical Distribution System QUESTION 47 C Knowledge of the physical connections and/or cause-effect relationships between the DC electrical system and the following systems: (CFR:
41.2 to 41.9 / 45.7 to 45.8)
AC electrical system .............................................
Given the following Unit 1 conditions:
Reactor in MODE 3 1KX inverter DC Input breaker trips Power to 1KX Panelboard will be restored with the ________.
Which ONE of the following completes the statement above?
A. ASCO Switch B. Manual Bypass Switch C. Static Transfer Switch D. Inverter Bypass Switches Monday, March 16, 2020 Page 94 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 47 C General Discussion Answer A Discussion Incorrect. Plausible since the ASCO switch is an auto transfer to AC line, but only if the Static Transfer switch fails. The ASCO will swap to AC line in 0.5 to 1 sec.
Answer B Discussion Incorrect. Plausible because if this was a Vital Inverter, it would be correct.
Answer C Discussion CORRECT. The static transfer switch looks at the output voltage of the Inverter at two different locations. If the voltage at either one of these locations is lost, the static transfer switch will automatically swap the inverter to AC line within 1/4 cycle.
Answer D Discussion Incorrect. Plausible because the Inverter Bypass switches can be used to swap the Inverter output to AC Line, but not automatically.
Basis for meeting the KA Question requires knowledge of the physical connection between DC and AC power through the Essential Inverters.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 39 Q22 Development References Student References Provided ILT 39 Q22 EL-VPC Obj. 05 SYS063 K1.02 - DC Electrical Distribution System Knowledge of the physical connections and/or cause-effect relationships between the DC electrical system and the following systems: (CFR:
41.2 to 41.9 / 45.7 to 45.8)
AC electrical system .............................................
Remarks/Status Monday, March 16, 2020 Page 95 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS064 K4.01 - Emergency Diesel Generator (ED/G) System QUESTION 48 B Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Trips while loading the ED/G (frequency, voltage, speed) ...............
Given the following plant conditions:
Time = 0800:00:
KHU 1 generating to the grid KHU emergency start signal received Time = 0800:10:
KHU 1 speed = 183 rpm rising Time = 0800:35:
KHU 1 speed = 181 rpm lowering
- 1) KHU 1 __(1)__ Emergency Locked out (ELO).
- 2) KHU 2 __(2)__ shutdown when the KHU emergency start signal is RESET.
Which ONE of the following completes the statements above?
A. 1. has
- 2. will B. 1. has
- 2. will NOT C. 1. has NOT
- 2. will D. 1. has NOT
- 2. will NOT Monday, March 16, 2020 Page 96 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 48 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because the Anti-Pump circuit associated with ACB-1/2 will cause a KHU that was operating to the grid (ACB-1/2 OH breaker closed) when an Emergency Start is received to shutdown when reset, if its ACB-1/2 is open when RESET is pressed.
Answer B Discussion CORRECT: For KHUs, If an Emergency Start is present and the unit overspeeds to 180 RPM, then a 23 second timer starts. If the unit has not decreased to < 180 RPM within this 23 seconds, then an Emergency Lockout is generated.
Any KHU that was not operating to the grid prior to an Emergency Start will go through a normal start, parallel and tie to the grid when the RESET buttons are depressed.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it would be correct if KHU 1 speed lowered below 180 rpm within 23 seconds of the emergency start.
Second part is incorrect. Plausible because the Anti-Pump circuit associated with ACB-1/2 will cause a KHU that was operating to the grid (ACB-1/2 OH breaker closed) when an Emergency Start is received to shutdown when reset, if its ACB-1/2 is open when RESET is pressed when resetting following the Emergency Start Answer D Discussion Incorrect. First part is incorrect. Plausible because it would be correct if KHU 1 speed lowered below 180 rpm within 23 seconds of the emergency start.
Second part is correct.
Basis for meeting the KA Question requires knowledge of the overspeed trip associated with the Keowee Hydro Units (Oconee's Emergency Diesel Generator System) following an emergency start.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Development References Student References Provided EL-KHG Obj 08 SYS064 K4.01 - Emergency Diesel Generator (ED/G) System Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Trips while loading the ED/G (frequency, voltage, speed) ...............
Remarks/Status Monday, March 16, 2020 Page 97 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS073 K3.01 - Process Radiation Monitoring (PRM) System QUESTION 49 C Knowledge of the effect that a loss or malfunction of the PRM system will have on the following: (CFR: 41.7 / 45.6)
Radioactive effluent releases ......................................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
1A GWD tank release in progress 1RIA-38 OOS Current conditions:
Loss of power to 1RIA-37 RM-80 skid
- 1) 1GWD-4 (A GWD TANK DISCHARGE) will __(1)__.
- 2) Unit 1s Waste Gas Decay Tank discharge flow rate is monitored on __(2)__.
Which ONE of the following completes the statements above?
A. 1. remain open
- 2. 1VB1 B. 1. remain open
- 2. 1AB3 C. 1. automatically close
- 2. 1VB1 D. 1. automatically close
- 2. 1AB3 Monday, March 16, 2020 Page 98 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 49 C General Discussion Answer A Discussion Incorrect, First part is incorrect. Plausible because the candidate could have the misconception that a loss of power to the RIA will prevent the interlock from occurring. Second part is correct.
Answer B Discussion Incorrect, First part is incorrect. Plausible because the candidate could have the misconception that a loss of power to the RIA will prevent the interlock from occurring. Second part is incorrect. Plausible because this is the control room location for the GWD controls.
Answer C Discussion CORRECT. 1GWD-4 will close on loss of power to 1RIA-37. The flow rate is read on a recorder on 1VB1.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because this is the control room location for the GWD controls.
Basis for meeting the KA Question requires knowledge of the effect that a loss of power to a PRM (RIA-37) has on the radioactive effluent release (GWD).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 41 Q49 Development References Student References Provided ILT 41 Q49 RAD-RIA Obj 08, 15 SYS073 K3.01 - Process Radiation Monitoring (PRM) System Knowledge of the effect that a loss or malfunction of the PRM system will have on the following: (CFR: 41.7 / 45.6)
Radioactive effluent releases ......................................
Remarks/Status Monday, March 16, 2020 Page 99 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS076 K1.08 - Service Water System (SWS)
QUESTION 50 B Knowledge of the physical connections and/or cause- effect relationships between the SWS and the following systems: (CFR: 41.2 to 41.9 /
45.7 to 45.8)
RHR system ....................................................
gpm is reached.
- 2) The automatic runback described above will lower LPSW flow to the LPI Cooler to a MAXIMUM of __(2)__ gpm.
Which ONE of the following completes the statements above?
A. 1. 5900
- 2. 3000 B. 1. 5900
- 2. 5200 C. 1. 6000
- 2. 3000 D. 1. 6000
- 2. 5200 Monday, March 16, 2020 Page 100 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 50 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since 3000 gpm is the normal setpoint for the LPSW-251/252 controllers on the outlet of the LPI Coolers.
Answer B Discussion CORRECT. LPSW flow to the LPI coolers will automatically runback at 5900 gpm to a flow rate of 5200 gpm. Automatic runback prevents exceeding the LPI cooler shell design flow of 6000 gpm.
Answer C Discussion Incorrect. First part is incorrect. Plausible because 6000 gpm is the design flow for the LPI Coolers that the runback is there to prevent exceeding.
Second part is incorrect. Plausible since 3000 gpm is the normal setpoint for the LPSW-251/252 controllers on the outlet of the LPI Coolers.
Answer D Discussion Incorrect. First part is incorrect. Plausible because 6000 gpm is the design flow for the LPI Coolers that the runback is there to prevent exceeding.
Second part is correct.
Basis for meeting the KA Question requires knowledge of LPSW flow to LPI Cooler interlocks.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided SSS-LPW Obj 10 SYS076 K1.08 - Service Water System (SWS)
Knowledge of the physical connections and/or cause- effect relationships between the SWS and the following systems: (CFR: 41.2 to 41.9 /
45.7 to 45.8)
RHR system ....................................................
Remarks/Status Monday, March 16, 2020 Page 101 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS076 K2.01 - Service Water System (SWS)
QUESTION 51 B Knowledge of bus power supplies to the following: (CFR: 41.7)
Service water ....................................................
Which ONE of the following states all of the switchgear that can supply power to C LPSW pump?
A. 1TC ONLY B. 2TC ONLY C. 1TD ONLY D. 1TD or 2TD Monday, March 16, 2020 Page 102 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 51 B General Discussion Answer A Discussion Incorrect. Plausible because 1TC supplies power to A LPSW pump.
Answer B Discussion CORRECT. The power supply for the C LPSW pump is 2TC.
Answer C Discussion Incorrect. Plausible because 1TD is one of the power supplies to B LPSW pump.
Answer D Discussion Incorrect. Plausible because 1TD and 2TD are both power supplies for B LPSW pump.
Basis for meeting the KA Question requires knowledge of the power supply for one of the LPSW pumps.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 16-2 Q52 Development References Student References Provided ILT 16-2 Q52 IC-ES Obj 28 SYS076 K2.01 - Service Water System (SWS)
Knowledge of bus power supplies to the following: (CFR: 41.7)
Service water ....................................................
Remarks/Status Monday, March 16, 2020 Page 103 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS078 2.4.35 - Instrument Air System (IAS)
QUESTION 52 B SYS078 GENERIC Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13)
Given the following Unit 3 conditions:
Time = 0800:
3CC-8 fails closed due to loss of Instrument Air (IA)
AP/3/A/1700/020 (Loss of Component Cooling) initiated Time = 0803:
AO manually opened 3CC-8 (CC Return Outside Block)
Time = 0900:
IA restored to 3CC-8 AO has taken NO further action
- 1) At Time = 0803, both Unit 3 CC pumps __(1)__ operating.
- 2) At Time = 0900, 3CC-8 __(2)__ be operated from the Control Room.
Which ONE of the following completes the statements above?
A. 1. are
- 2. can B. 1. are
- 2. can NOT C. 1. are NOT
- 2. can D. 1. are NOT
- 2. can NOT Monday, March 16, 2020 Page 104 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 52 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because a candidate could assume that with IA restored the valve would now work from the CR. Also plausible since most valves do not have a Auto/Manual lever locally at the valve.
Answer B Discussion CORRECT. CC pumps will trip when CC-8 closes, and will automatically restart after it has been re-opened. When CC-8 has been manually opened, it cannot be operated from the Control Room until the local lever has been returned to auto.
Answer C Discussion Incorrect. First part is incorrect. Plausible because for Time = 0800, it is correct.
Second part is incorrect. Plausible because a candidate could assume that with IA restored the valve would now work from the CR. Also plausible since most valves do not have a Auto/Manual lever locally at the valve.
Answer D Discussion Incorrect. First part is incorrect. Plausible because for Time = 0800, it is correct.
Second part is correct.
Basis for meeting the KA Question requires knowledge of local operator tasks related to CC-8 during loss of IA to the valve and resultant operational effects related to CC pumps and whether or not 3CC-8 can be operated from the CR following manual operation.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 2010A Q55 Development References Student References Provided ILT 2010A Q55 AP/3/A/1700/020 Rev 13 PNS-CC Obj 13, 14 EAP-AP20 Obj. 04, 05 SYS078 2.4.35 - Instrument Air System (IAS)
SYS078 GENERIC Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 105 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS078 K4.01 - Instrument Air System (IAS)
QUESTION 53 A Knowledge of IAS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Manual/automatic transfers of control ...............................
Given the following plant conditions:
Time = 0400:
Backup IA Compressors in STBY1 Primary IA Compressor tripped Time = 0405:
Instrument Air pressure = 91 psig lowering At Time = 0405
- 1) Auxiliary IA Compressors are __(1)__.
- 2) Backup IA Compressors are __(2)__.
Which ONE of the following completes the statements above?
ASSUME NO OPERATOR ACTIONS A. 1. OFF
- 2. operating B. 1. OFF
- 2. OFF C. 1. operating
- 2. operating D. 1. operating
- 2. OFF Monday, March 16, 2020 Page 106 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 53 A General Discussion Answer A Discussion CORRECT. Backup IA compressors started at 93 psig and the AIA compressors are still off because they start at 88 psig.
Answer B Discussion Incorrect:. First part is correct. Second part is incorrect. The Backup IA Compressors are normally in STBY 1 and auto start at 93 psig lowering.
Plausible because it would be correct if the Backup IA Compressor switches were in STBY 2. In STBY 2 the auto start setpoint is 90 psig lowering.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it would be correct for the Sullair Service Air Compressors, which auto start at 95 psig lowering SA pressure. Second part is correct.
Answer D Discussion Incorrect:. First part is incorrect. Plausible because it would be correct for the Sullair Service Air Compressors, which auto start at 95 psig lowering SA pressure. Second part is incorrect. The Backup IA Compressors are normally in STBY 1 and auto start at 93 psig lowering.
Plausible because it would be correct if the Backup IA Compressor switches were in STBY 2. In STBY 2 the auto start setpoint is 90 psig lowering.
Basis for meeting the KA Question requires knowledge of which compressors will be controlling the IA System pressure and the transfer of control when the Primary IA Compressor trips. Per discussion with NRC Chief on 1/03/2020, this approach to the K/A is acceptable.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 48 Q54 Development References Student References Provided ILT 48 Q54 SSS-IA Obj 16 SYS078 K4.01 - Instrument Air System (IAS)
Knowledge of IAS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Manual/automatic transfers of control ...............................
Remarks/Status 1/03/20 - Chief stated we could write question associated with compressor auto starts (transfer control of the IA header to different compressors).
Monday, March 16, 2020 Page 107 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS103 A1.01 - Containment System QUESTION 54 C Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: (CFR: 41.5 / 45.5)
Containment pressure, temperature, and humidity .....................
Given the following Unit 1 conditions:
Time = 1300:
Reactor power = 100%
LBLOCA occurs RCS Pressure 40 psig and lowering RB Pressure 20 psig and rising Time = 1302:30:
At Time = 1302:30:
- 1) 1A, 1B, 1C RBCUs __(1)__.
- 2) 1A and 1B RBS pumps __(2)__.
Which ONE of the following completes the statement above?
REFERENCE PROVIDED (above)
A. 1. are operating correctly
- 2. should NOT be operating B. 1. should ALL be operating in LOW speed
- 2. should NOT be operating C. 1. are operating correctly
- 2. are operating correctly D. 1. should ALL be operating in LOW speed
- 2. are operating correctly Monday, March 16, 2020 Page 108 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 54 C General Discussion Answer A Discussion Incorrect: First part is correct.
Second part is incorrect. Plausible if the students associate the RBCU 3 minute time delay with the RBS pumps, since they perform the same safety function.
Answer B Discussion Incorrect: First part is incorrect. Plausible if the students believe that the time delay is 2 minutes, like it is for the ESV system.
Second part is incorrect. Plausible if the students associate the RBCU 3 minute time delay with the RBS pumps, since they perform the same safety function.
Answer C Discussion CORRECT: The RBCUs will stop when ES 5/6 actuate and will start 3 minutes later in LOW speed. The RBS pumps will start on ES 7/8 with no time delay.
Answer D Discussion Incorrect: First part is incorrect. Plausible if the students believe that the time delay is 2 minutes, like it is for the ESV system.
Second part is correct.
Basis for meeting the KA Question requires the ability to determine that with containment conditions changing (pressure/temperature due to LBLOCA), the RBCUs and RBS pumps are operating properly to lower RB pressure/temperature to prevent exceeding design limits in containment.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 44 Q90 Development References Student References Provided ILT 44 Q90 PNS-RBC Obj 01 PNS-BS Obj 06 SYS103 A1.01 - Containment System Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: (CFR: 41.5 / 45.5)
Containment pressure, temperature, and humidity .....................
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 109 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS103 A3.01 - Containment System QUESTION 55 B Ability to monitor automatic operation of the containment system, including: (CFR: 41.7 / 45.5)
Containment isolation ............................................
Given the following on Unit 2:
Initial conditions:
Reactor power = 100%
Current conditions:
RCS pressure = 1500 psig lowering RB pressure = 3.3 psig lowering
- 1) Reactor Building essential isolation valves __(1)__ closed.
- 2) In accordance with EOP Enclosure 5.1, (ES Actuation), a previously closed containment isolation valve will be opened by FIRST placing the associated
__(2)__.
Which ONE of the following completes the statements above?
A. 1. are
- 2. voter in OVERRIDE B. 1. are
- 2. ES Channel in MANUAL C. 1. are NOT
- 2. voter in OVERRIDE D. 1. are NOT
- 2. ES Channel in MANUAL Monday, March 16, 2020 Page 110 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 55 B General Discussion Answer A Discussion Incorrect: 1st part is correct. Since RB pressure is > 3 psig, both essential and non-essential RB isolation valves will be closed.
2nd part is incorrect because ES Channels are placed in MANUAL first. It is plausible because it would be correct if Channel 5 would not go to MANUAL.
Answer B Discussion CORRECT: 1st part is correct. Since RB pressure is > 3 psig, both essential and non-essential RB isolation valves will be closed.
2nd part is correct. ES Channels are placed in MANUAL first. As an example, EOP Encl. 5.1 directs first taking ES Channel 5 to MANUAL to open 2CC-7. If Channel 5 will not go to MANUAL then the ODD voter is placed in OVERRIDE.
Answer C Discussion Incorrect: 1st part is incorrect because with RB pressure > 3 psig, both essential and non-essential RB isolation valves will be closed. It is plausible because if RB pressure was < 3 psig, it would be correct.
2nd part is incorrect because ES Channels are placed in MANUAL first. It is plausible because it would be correct if Channel 5 would not go to MANUAL.
Answer D Discussion Incorrect: 1st part is incorrect because with RB pressure > 3 psig, both essential and non-essential RB isolation valves will be closed. It is plausible because if RB pressure was < 3 psig, it would be correct.
2nd part is correct. ES Channels are placed in MANUAL first. As an example, EOP Encl. 5.1 directs first taking ES Channel 5 to MANUAL to open 2CC-7. If Channel 5 will not go to MANUAL then the ODD voter is placed in OVERRIDE.
Basis for meeting the KA Question requires knowledge of automatic operation of the containment isolation valves.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 16-1 Q55 Development References Student References Provided ILT 16-1 Q55 IC-ES Obj 3, 7, 17 U2 EOP Encl 5.1 Rev 01 SYS103 A3.01 - Containment System Ability to monitor automatic operation of the containment system, including: (CFR: 41.7 / 45.5)
Containment isolation ............................................
Remarks/Status Monday, March 16, 2020 Page 111 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS001 2.1.23 - Control Rod Drive System QUESTION 56 A SYS001 GENERIC Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)
Given the following Unit 1 conditions:
OP/1/A/1105/019 (Control Rod Drive System) initiated Enclosure 4.15 (Recovery Of Dropped/Misaligned Safety Or Regulating Control Rod With Diamond in Automatic) in progress Step 2.4 states: IF affected rod is fully inserted, and Auto Latch and PI Alignment desired, perform the following:
2.4.1 Select LATCH AUTO.
- 2) During this control rod recovery, the __(2)__.
Which ONE of the following completes the statements above?
A. 1. will
- 2. Controlling CRD Group will maintain Rx power constant B. 1. will
- 2. Reactor Operator will insert the regulating rods to stop the rise in power C. 1. will NOT
- 2. Controlling CRD Group will maintain Rx power constant D. 1. will NOT
- 2. Reactor Operator will insert the regulating rods to stop the rise in power Monday, March 16, 2020 Page 112 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 56 A General Discussion Answer A Discussion CORRECT. First part is correct. The "LATCH AUTO" switch latches the rod and resets RPI to match API rod indication.
Second part correct. With the Diamond in automatic, the regulating control rods will maintain Rx power constant as the control rod is recovered.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if the Diamond was in manual, it would be correct.
Answer C Discussion Incorrect. First part is incorrect. It is plausible to believe that the switch only latches the rod because of the name "LATCH AUTO".
Second part correct. With the Diamond in automatic, the regulating control rods will maintain Rx power constant as the control rod is recovered.
Answer D Discussion Incorrect. First part is incorrect. It is plausible to believe that the switch only latches the rod because of the name "LATCH AUTO".
Second part is incorrect. Plausible because if the Diamond was in manual, it would be correct.
Basis for meeting the KA Requires knowledge of control rod position indication system and the ability to determine the desired component to operate to satisfy a specific procedure step to determine if API/RPI indications agree.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 39 Q58 Development References Student References Provided ILT 39 Q58 IC-CRI Obj 10, 11 SYS001 2.1.23 - Control Rod Drive System SYS001 GENERIC Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)
Remarks/Status Monday, March 16, 2020 Page 113 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS002 A1.07 - Reactor Coolant System (RCS)
QUESTION 57 C Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including : (CFR: 41.5 / 45.7)
Reactor differential temperature ...................................
Given the following on Unit 1:
Initial conditions:
Reactor power = 80% stable Diamond and FDW Masters in HAND CRS directs OATC to maintain Delta Tc 0°F +/- 2°F Current conditions:
1B1 RCP trips Crew performs Plant Transient Response AP/1/A/1700/001 (Unit Runback) initiated Delta Tc = +2.2°F and becoming more positive
- 1) The operator will have to manually re-ratio feedwater such that feed to the __(1)__
SG is raised.
- 2) In accordance with AP/01, the crew will initiate a power reduction to a MAXIMUM of
__(2)__ %.
Which ONE of the following completes the statements above?
A. 1. 1A
- 2. 65 B. 1. 1B
- 2. 65 C. 1. 1A
- 2. 74 D. 1. 1B
- 2. 74 Monday, March 16, 2020 Page 114 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 57 C General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because it would be correct for a MFDW pump trip.
Answer B Discussion Incorrect. First part is incorrect. Plausible because if delta Tc were negative, it would be correct.
Second part is incorrect. Plausible because it would be correct for a MFDW pump trip.
Answer C Discussion CORRECT. A positive delta Tc indicates 1A SG is hot. Therefore, the operator will need to raise FDW to the 1A SG and lower FDW to the 1B SG. With a loss of RCP, AP/01 directs a power reduction to less than or equal to 74%.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if delta Tc were negative, it would be correct.
Second part is correct.
Basis for meeting the KA Question requires the ability to predict changes in Reactor differential temperature (delta Tc) when operating the ICS controls.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 47 Q24 Development References Student References Provided ILT 47 Q24 EAP-AP/01 Obj 04 AP/01 Rev 16 ICS-03 (FDW) Obj 06 SYS002 A1.07 - Reactor Coolant System (RCS)
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including : (CFR: 41.5 / 45.7)
Reactor differential temperature ...................................
Remarks/Status Monday, March 16, 2020 Page 115 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS011 K5.10 - Pressurizer Level Control System (PZR LCS)
QUESTION 58 A Knowledge of the operational implications of the following concepts as they apply to the PZR LCS: (CFR: 41.5 / 45.7)
Indications of reactor vessel bubble .................................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
SBLOCA occurs Current conditions:
LOCA CD tab in progress RCS pressure = 805 psig stable RCS temperature = 530°F RB pressure = 3.1 psig rising Pzr level = 25 inches rising
- 1) Indicated Pzr level rising __(1)__ due to bubble formation in the reactor vessel head.
- 2) In accordance with the LOCA CD tab, 1RC-159/1RC-160 are opened when the Rx vessel head level lowers to a MAXIMUM of __(2)__ inches.
Which ONE of the following completes the statements above?
A. 1. is
- 2. 154 B. 1. is
- 2. 180 C. 1. is NOT
- 2. 154 D. 1. is NOT
- 2. 180 Monday, March 16, 2020 Page 116 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 58 A General Discussion Answer A Discussion CORRECT. The given parameters indicate a saturated RCS. As a bubble forms in the reactor vessel, Pzr level will rise due to the displaced water out of the vessel.
The LOCA CD tab will direct opening the RX vessel head vents when RV level is less than or equal to 154 inches.
Answer B Discussion Incorrect. First part is correct. Second part is incorrect. Plausible because 180 inches is the ACC PZR level when Rx Bldg pressure exceeds 3 psig.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if the RCS were not saturated, it would be correct. Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if the RCS were not saturated, it would be correct.
Second part is incorrect. Plausible because 180 inches is the ACC PZR level when Rx Bldg pressure exceeds 3 psig.
Basis for meeting the KA Question requires knowledge of the operational implications to Pzr level when a bubble forms in the reactor vessel head.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 16-2 Q21 Development References Student References Provided ILT 16-2 Q21 EAP-LCD Obj R10 EOP LOCA CD tab Rev 0 SYS011 K5.10 - Pressurizer Level Control System (PZR LCS)
Knowledge of the operational implications of the following concepts as they apply to the PZR LCS: (CFR: 41.5 / 45.7)
Indications of reactor vessel bubble .................................
Remarks/Status Monday, March 16, 2020 Page 117 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS014 A2.03 - Rod Position Indication System (RPIS)
QUESTION 59 A Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations : (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Dropped rod ....................................................
Given the following Unit 2 conditions:
Reactor power = 80%
0% light for Group 4 Rod 3 is lit AP/2/A/1700/001 (Unit Runback) initiated
- 1) The GROUP IN LIMIT light for Control Rod Group 4 will be __(1)__.
- 2) In accordance with AP/01, the operator __(2)__ change the rate of power reduction.
Which ONE of the following completes the statements above?
A. 1. ON
- 2. can B. 1. ON
- 2. can NOT C. 1. OFF
- 2. can D. 1. OFF
- 2. can NOT Monday, March 16, 2020 Page 118 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 59 A General Discussion Answer A Discussion CORRECT. If any control rod in the group is on the bottom, the Group In Limit light will be on. AP/01 states "IAAT it is desired to change the rate of power reduction, THEN adjust RATE SET on the Load Control Panel as desired. The dropped rod runback is the only ICS runback rate the operator can change with the LCP. The runback rate is 1% per minute. The operator can raise the rate above 1% per minute using the rate set on the LCP.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because it is correct for all the other ICS runbacks.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it would be logical to think that ALL control rods in the group would have to be at the in limit for the group in limit light to be lit.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it would be logical to think that ALL control rods in the group would have to be at the in limit for the group in limit light to be lit.
Second part is incorrect. Plausible because it is correct for all the other ICS runbacks.
Basis for meeting the KA Question requires the ability to predict the status of the GROUP IN LIMIT light following a dropped rod and use AP/01 to change the rate of power reduction, if desired, during the dropped rod runback.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 16-2 Q58 Development References Student References Provided ILT 16-2 Q58 IC-CRI Obj 07 U2 AP/01 ICS-01 Obj 03 SYS014 A2.03 - Rod Position Indication System (RPIS)
Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations : (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Dropped rod ....................................................
Remarks/Status Monday, March 16, 2020 Page 119 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS015 K2.01 - Nuclear Instrumentation System (NIS)
QUESTION 60 C Knowledge of bus power supplies to the following : (CFR: 41.7)
NIS channels, components, and interconnections ......................
The power supply for 1NI-2 Wide Range detector is _______.
A. KVIA B. KVIB C. KVIC D. KVID Monday, March 16, 2020 Page 120 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 60 C General Discussion Answer A Discussion Incorrect: Plausible since it would be correct for 1NI-1 and 1NI-5.
Answer B Discussion Incorrect: Plausible since it would be correct for 1NI-3 and 1NI-6.
Answer C Discussion CORRECT: KVIC is the power supply for 1NI-2.
Answer D Discussion Incorrect: Plausible since it would be correct for 1NI-4 and 1NI-8.
Basis for meeting the KA Requires knowledge of the bus power supplies for Nuclear Instruments.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 2009B Q58 Development References Student References Provided ILT 2009B Q58 IC-NI Obj 4 IC-RPS Obj 17 SYS015 K2.01 - Nuclear Instrumentation System (NIS)
Knowledge of bus power supplies to the following : (CFR: 41.7)
NIS channels, components, and interconnections ......................
Remarks/Status Monday, March 16, 2020 Page 121 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS029 A3.01 - Containment Purge System (CPS)
QUESTION 61 C Ability to monitor automatic operation of the Containment Purge System including: (CFR: 41.7 / 45.5)
CPS isolation ...................................................
RB Purge isolation valves 3PR-1, 3PR-2, 3PR-3, 3PR-4, 3PR-5, and 3PR-6 will ALL automatically close as a result of ______.
A. 3RIA-45 HIGH alarm B. 3RIA-46 HIGH alarm C. actuation of ES channels 1 and 2 D. actuation of ES channels 5 and 6 Monday, March 16, 2020 Page 122 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 61 C General Discussion Answer A Discussion Incorrect. Plausible since 3RIA-45 High alarm will close 3PR-2 thru 5. However it will NOT close 3PR-1&6.
Answer B Discussion Incorrect. Plausible since 3RIA-46 High alarm will close 3PR-2 thru 5. However it will NOT close 3PR-1&6.
Answer C Discussion CORRECT. 3PR 1 & 6 are on ES channel 1 and 3PR-2 thru 5 are on ES channel 2. Therefore ES 1&2 actuation will result in closing 3PR-1 thru 6.
Answer D Discussion Incorrect. Plausible since ES 5&6 do contain essential RB Isolation valves for various systems and components. However the Purge valves are all on ES 1&2.
Basis for meeting the KA Question requires knowledge of what will cause automatic operation (isolation) of the Containment Purge system valves. Knowing which valves should operate on a signal from ES 1&2 is an integral part of the ability to monitor automatic operation, especially since different valves operate based on what the initiating signal is (ex. RIA's only close PR 2-5).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 2009B Q60 Development References Student References Provided ILT 2009B Q60 PNS-RBP Obj 06 SYS029 A3.01 - Containment Purge System (CPS)
Ability to monitor automatic operation of the Containment Purge System including: (CFR: 41.7 / 45.5)
CPS isolation ...................................................
Remarks/Status Monday, March 16, 2020 Page 123 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS033 K1.02 - Spent Fuel Pool Cooling System (SFPCS)
QUESTION 62 A Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)
RHRS ..........................................................
Given the following Unit 1 conditions:
Reactor in MODE 6 Fuel Transfer Canal is full B Spent Fuel Cooling Pump aligned to Refueling Cooling Mode in accordance with OP/1/A/1102/015 (Filling and Draining FTC)
The B Spent Fuel Cooling Pump
- 1) suction will be from the __(1)__.
- 2) will discharge to the __(2)__.
Which ONE of the following completes the statements above?
A. 1. Decay Heat Drop Line
- 2. Spent Fuel Pool B. 1. Decay Heat Drop Line
- 2. Core Flood Nozzles C. 1. Spent Fuel Transfer Tube
- 2. Spent Fuel Pool D. 1. Spent Fuel Transfer Tube
- 2. Core Flood Nozzles Monday, March 16, 2020 Page 124 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 62 A General Discussion Answer A Discussion CORRECT. B SF Cooling pump is used by 1102/15 for Refueling Cooling Mode and it is aligned to take a suction from the DHR drop line and return the water to the Spent Fuel Pool.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since it would be correct regarding the LPI alignment while the SF system is in the Refueling Cooling Mode.
Answer C Discussion Incorrect. First part is incorrect. Plausible since the SF Transfer tubes do serve as a suction source for pumps (SSF RC Makeup pump).
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible since the SF Transfer tubes do serve as a suction source for pumps (SSF RC Makeup pump).
Second part is incorrect. Plausible since it would be correct regarding the LPI alignment while the SF system is in the Refueling Cooling Mode.
Basis for meeting the KA Requires knowledge of the shared suction line between LPI DHR and SF Cooling when aligned in the Refueling Cooling Mode.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 2009B Q61 Development References Student References Provided ILT 2009B Q61 FH-SFC Obj 12 OP/1/A/1102/015 Rev 94 SYS033 K1.02 - Spent Fuel Pool Cooling System (SFPCS)
Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)
RHRS ..........................................................
Remarks/Status Monday, March 16, 2020 Page 125 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS035 A4.05 - Steam Generator System (S/GS)
QUESTION 63 C Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
Level Control to enhance natural circulation ..........................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
Current conditions:
Condenser vacuum = 21 inches Hg stable 1TA and 1TB de-energized SG levels will be automatically controlled at ______.
Which ONE of the following completes the statement above?
A. 25 inches SUR B. 30 inches XSUR C. 50% OR D. 95% OR Monday, March 16, 2020 Page 126 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 63 C General Discussion Answer A Discussion Incorrect. Plausible because it would be correct if on Main FDW with RCPs operating.
Answer B Discussion Incorrect. Plausible because it would be correct if on EFDW with RCPs operating.
Answer C Discussion CORRECT. With 1TA and 1TB de-energized, the reactor will trip and all RCPs are lost. The Main FDW pumps will still be operating at 21 inches hg vacuum (trip setpoint is 19 inches hg). With Main FDW in operation, SG levels will be controlled at 50% OR for natural circulation.
Answer D Discussion Incorrect. Plausible because it would be the correct level with a loss of SCM and MFDW available.
Basis for meeting the KA Question requires the ability to monitor SGs for proper level during Natural Circulation.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 42 Q27 Development References Student References Provided ILT 42 Q27 CF-FDW Obj 11 SYS035 A4.05 - Steam Generator System (S/GS)
Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
Level Control to enhance natural circulation ..........................
Remarks/Status Monday, March 16, 2020 Page 127 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS041 K6.03 - Steam Dump System (SDS)/Turbine Bypass Control QUESTION 64 A Knowledge of the effect of a loss or malfunction on the following will have on the SDS: (CFR: 41.7 / 45.7)
Controller and positioners, including ICS, S/G, CRDS .................
Given the following Unit 2 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Reactor trip Trip Confirm signal NOT generated by the Diamond
- 1) The Turbine Load Status Flag is __(1)__.
- 2) The Turbine Bypass valves will control at __(2)__.
A. 1. false
- 2. setpoint B. 1. false
- 2. setpoint + 125 psig C. 1. true
- 2. setpoint D. 1. true
- 2. setpoint + 125 psig Monday, March 16, 2020 Page 128 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 64 A General Discussion Answer A Discussion CORRECT. The turbine LOAD status flag is always false below 10% CTPD. Turbine Header Pressure control after a reactor trip at setpoint
+125 psig when the Diamond control system receives a "trip confirm" signal from control rod drive breakers opening. Since the "Trip Confirm" signal was not generated the TBVs will control at setpoint.
Answer B Discussion Incorrect. First part correct. The turbine LOAD status flag is always false below 10% CTPD.
Second part is incorrect. Plausible since it would be correct if the "trip confirm" signal had been generated.
Answer C Discussion Incorrect. First part incorrect. The turbine LOAD status flag is false below 10% CTPD. Second part is correct.
Answer D Discussion Incorrect. First part incorrect. The turbine LOAD status flag is false below 10% CTPD. Second part is incorrect. Plausible since it would be correct if the "trip confirm" signal had been generated.
Basis for meeting the KA Requires knowledge of the effect of a failure of the Trip Confirm signal to be generated once the CRD breakers are open on operation of the ICS system (specifically control of the Turbine Bypass Valves).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 2009B Q63 Development References Student References Provided ILT 2009B Q63 ICS-02 Obj 04 SYS041 K6.03 - Steam Dump System (SDS)/Turbine Bypass Control Knowledge of the effect of a loss or malfunction on the following will have on the SDS: (CFR: 41.7 / 45.7)
Controller and positioners, including ICS, S/G, CRDS .................
Remarks/Status Monday, March 16, 2020 Page 129 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS045 K4.37 - Main Turbine Generator (MT/G) System QUESTION 65 B Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Automatic functions associated with turbine trip: reactor trip, station power switched to offsite source, air to extraction steam non-return valves removed ...................................
Given the following Unit 2 conditions:
Reactor shutdown from 100% in progress Main Turbine bearing oil leak occurs Reactor power = 28% stable
- 1) Based on the graph above, the EARLIEST time the Main Turbine will automatically trip is __(1)__.
- 2) After the Main Turbine has tripped, ICS will maintain Tave at approximately
__(2)__ degrees F.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED (above)
A. 1. 12:01
- 2. 579 B. 1. 12:01
- 2. 555 C. 1. 12:03
- 2. 579 D. 1. 12:03
- 2. 555 Monday, March 16, 2020 Page 130 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 65 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if reactor power was < 27.75%, it would be correct.
Answer B Discussion CORRECT. The Turbine will automatically trip at 8 psig lowering bearing oil pressure. The turbine to reactor trip is bypassed when power is less than or equal to 27.75%. The trip is armed at 29.75% rising. With a shutdown in progress and power at 28%, the turbine to reactor trip is not yet bypassed, so when the turbine trips the reactor will trip. Post trip RCS temperature is 555 degrees.
Answer C Discussion Incorrect. Plausible because it would be correct for a Main FDW pump trip.
Second part is incorrect. Plausible because if reactor power was < 27.75%, it would be correct.
Answer D Discussion Incorrect. Plausible because it would be correct for a Main FDW pump trip.
Second part is correct Basis for meeting the KA Question requires knowledge of automatic turbine trips and when the turbine to reactor trip is armed and bypassed.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED ILT 48 Q61 Development References Student References Provided STG-EHC Obj 12 IC-RPS Obj 06 SYS045 K4.37 - Main Turbine Generator (MT/G) System Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Automatic functions associated with turbine trip: reactor trip, station power switched to offsite source, air to extraction steam non-return valves removed ...................................
Remarks/Status Monday, March 16, 2020 Page 131 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.1 2.1.3 - GENERIC - Conduct of Operations QUESTION 66 A Conduct of Operations Knowledge of shift or short-term relief turnover practices. (CFR: 41.10 / 45.13)
In accordance with AD-OP-ALL-1000 (Conduct of Operations)
- 1) an operator requiring short term relief shall have adequate communication with the Control Room and be capable of responding to the Control Room within a MAXIMUM of __(1)__ minutes.
- 2) a watch station that is relieved for two hours __(2)__ required to be entered in the Narrative Log.
Which ONE of the following completes the statements above?
A. 1. 20
- 2. is B. 1. 20
- 2. is NOT C. 1. 60
- 2. is D. 1. 60
- 2. is NOT Monday, March 16, 2020 Page 132 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 66 A General Discussion Answer A Discussion CORRECT. During all cases the operator requiring short term relief shall have adequate communication with the Control Room and be capable of responding to the Control Room within 20 minutes. Whenever a watch station is relieved for greater than one hour, this information shall be entered in a Narrative Log Program, a formal turnover and shift turnover sheet will be completed, including the logs signed over.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if the time the watchstation was relieved was 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, it would be correct.
Answer C Discussion Incorrect. First part is incorrect. Plausible because AD-OP-ALL-1000 states 60 minutes as the maximum time that the SM or STA can provide short term relief to the CRS and RO positions.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because AD-OP-ALL-1000 states 60 minutes as the maximum time that the SM or STA can provide short term relief to the CRS and RO positions.
Second part is incorrect. Plausible because if the time the watchstation was relieved was 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, it would be correct.
Basis for meeting the KA Question requires knowledge of short term relief turnover practices.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided ADM-FSP Obj 15 AD-OP-ALL-1000 Rev 16 GEN2.1 2.1.3 - GENERIC - Conduct of Operations Conduct of Operations Knowledge of shift or short-term relief turnover practices. (CFR: 41.10 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 133 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.1 2.1.42 - GENERIC - Conduct of Operations QUESTION 67 C Conduct of Operations Knowledge of new and sepnt fuel movement procedures. (CFR: 41.10 / 43.7 / 45.13)
Given the following on Unit 1.
Initial conditions:
Mode 6 Defueling in progress 1RIA-6 (Spent Fuel Pool Area Monitor) = 4 mr/hr stable Current conditions:
1RIA-6 monitor power supply fuse blows 1RIA-6 local reading = 0 mr/hr 1RIA-6 View Node indication is magenta In accordance with OP/1/A/1502/007 (Operations Defueling/Refueling Responsibilities), Fuel Handling activities in the SFP can ______.
Which ONE of the following completes the statement above?
A. continue provided 1RIA-41 (SFP Gas) is operable B. continue because only the SFP Bridge area monitor is required C. NOT continue until a replacement monitor equivalent to 1RIA-6 is in use D. NOT continue until continuous RP coverage is present on the SFP Bridge Monday, March 16, 2020 Page 134 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 67 C General Discussion Answer A Discussion Incorrect. Plausible since 1RIA-41 is an RIA monitoring the SFP area.
Answer B Discussion Incorrect. Plausible since the SFP Bridge area monitor is required in order to move fuel in the SFP in addition to 1RIA-6 or the equivalent monitor.
Answer C Discussion CORRECT. Per OP/1/A/1502/007, if 1RIA-6 becomes inoperable, portable survey instrumentation must be used. The instrumentation shall have appropriate range and sensitivity to fully protect individuals involved in refueling operation until the permanent instrumentation is returned to service. Either 1RIA-6 or the equivalent monitor must be in service in order to move fuel.
Answer D Discussion Incorrect. Plausible because fuel handling does have to stop and continuous RP coverage is used in other cases, but it is not a substitute for 1RIA-6 or the equivalent monitor in accordance with OP/1/A/1502/007.
Basis for meeting the KA Question requires knowledge of spent fuel movement procedures (OP/1/A/1502/007).
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 2009 Q61 Development References Student References Provided ILT 2009 Q61 OP/1/A/1502/007 Rev 92 SLC 16.12.2 (5/03/07)
ADM-TSS Obj 03 GEN2.1 2.1.42 - GENERIC - Conduct of Operations Conduct of Operations Knowledge of new and sepnt fuel movement procedures. (CFR: 41.10 / 43.7 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 135 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.1 2.1.8 - GENERIC - Conduct of Operations QUESTION 68 A Conduct of Operations Ability to coordinate personnel activities outside the control room. (CFR: 41.10 / 45.5 / 45.12 / 45.13)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Blackout in progress An RO has initiated AP/0/A/1700/025 (Standby Shutdown Facility Emergency Operating Procedure)
Breaker transfer in the SSF is complete
- 1) In accordance with AP/25, the SSF RO __(1)__ required to initiate feed with the SSF Aux Service Water pump.
- 2) 1RC-4 will be closed by the switch in the __(2)__.
Which ONE of the following completes the statements above?
A. 1. is NOT
- 2. SSF control room B. 1. is NOT
- 2. Unit 1 control room C. 1. is
- 2. SSF control room D. 1. is
- 2. Unit 1 control room Monday, March 16, 2020 Page 136 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 68 A General Discussion Answer A Discussion CORRECT: The SSF RC makeup pump will be started and aligned to the RCP seals. The SSF Aux Service Water pump will NOT be used since the TDEFDW pump will feed the SGs. After the breaker swap, 1RC-4 can only be operated from the SSF control room.
Answer B Discussion Incorrect: First part is correct.
Second part is incorrect. Plausible because this is where 1RC-4 is normally operated from.
Answer C Discussion Incorrect: First part is incorrect. Plausible because it would be correct if the TDEFDW pump were not available.
Second part is correct.
Answer D Discussion Incorrect: First part is incorrect. Plausible because it would be correct if the TDEFDW pump were not available.
Second part is incorrect. Plausible because this is where 1RC-4 is normally operated from.
Basis for meeting the KA Question requires knowledge of actions taken outside of the control room.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 43 Q66 Development References Student References Provided ILT 43 Q66 EAP-SSF Obj 02, 13, 15 GEN2.1 2.1.8 - GENERIC - Conduct of Operations Conduct of Operations Ability to coordinate personnel activities outside the control room. (CFR: 41.10 / 45.5 / 45.12 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 137 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.2 2.2.4 - GENERIC - Equipment Control QUESTION 69 C Equipment Control (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)
Given the following Unit 1 conditions:
Core SCM = 0°F LOCA CD tab in progress CETCs = 395°F slowly lowering 1LP-103 (POST LOCA BORON DILUTE) will NOT open The LOCA CD tab will direct opening ______ when establishing Alternate post LOCA boron dilution flow.
Which ONE of the following completes the statement above?
A. 1LP-3 B. 1LP-19 C. 1LP-105 D. 1LP-104 Monday, March 16, 2020 Page 138 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 69 C General Discussion Answer A Discussion Incorrect: Plausible since 1LP-3 is in the normal DHR drop line, however the tap for the alternate PLBD flowpath is between 1LP-2 & 1LP-3. Therefore 1LP-3 is not required to be opened. Additional plausibility is added due to the fact that LP-3 is a valve required to be opened for Units 2 & 3.
Answer B Discussion Incorrect: Plausible since 1LP-19 would be correct for Units 2 & 3. However Unit 1 has a unique alternate path that does not use 1LP-19.
Answer C Discussion CORRECT: For Unit 1, another drain line and motor operated valve, 1LP-105, is installed below LP-1 and LP-2 to provide a second flow path to the Reactor Building Emergency Sump. The addition of 1LP-105 was required in this flow path due to the arrangement of the Decay Heat Drop Line on Unit 1. On Unit 1 the Drop Line does not drop straight to the suction of the LPI pumps as it does on units 2 and 3, but instead, curves back upwards before reaching the pumps, in effect, forming a loop seal. This would prevent a gravity drain path from the hot leg to the LPI pump suction header as it exists on Units 2 and 3 and requires using 1LP-105 for the alternate PLBD flowpath.
Answer D Discussion Incorrect: Plausible since 1LP-104 is a valve in the normal PLBD flowpath. However it is in series with 1LP-103. Therefore the failure of 1LP-103 to open renders 1LP-104 useless.
Basis for meeting the KA Question requires knowledge of design, procedural, and operational differences between units following a SBLOCA when aligning Post LOCA Boron Dilution flowpath. Due to differences in the routing of LPI piping, Unit 1 has a different alternate Post LOCA Boron dilution flowpath than does units 2 and 3. Unit 1 has LP-105 in its flowpath where Units 2 & 3 would use LP-19.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 2010A Q27 Development References Student References Provided ILT 2010A Q27 PNS-LPI Obj 07, 34 EOP LOCA CD Rev GEN2.2 2.2.4 - GENERIC - Equipment Control Equipment Control (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 139 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 69 C Monday, March 16, 2020 Page 140 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.2 2.2.43 - GENERIC - Equipment Control QUESTION 70 A Equipment Control Knowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5 / 45.13)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
1SA-15/A-2 (SU Source Volt Monitor Logic Test) actuated Current conditions:
I&E determines the alarm actuated due to a defective alarm relay Repairs will take 3 - 4 days The CRS directs you to remove the nuisance alarm from service In accordance with OP/0/A/1108/001 Encl. 4.17 (Evaluation for Removal of Statalarms/Control Room Indications)
- 1) Statalarm 1SA-15/A-2 is required to be added to the __(1)__ section of the Unit Turnover Sheet.
- 2) A CBWO or __(2)__ label is required to be placed on the statalarm window.
Which ONE of the following completes the statements above?
A. 1. Out of Normal Alarms
- 2. T/O Sheet B. 1. Out of Normal Alarms
- 2. OOS/I&E C. 1. Equipment Deficiencies
- 2. T/O Sheet D. 1. Equipment Deficiencies
- 2. OOS/I&E Monday, March 16, 2020 Page 141 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 70 A General Discussion Answer A Discussion CORRECT. Per OP/0/A/1108/001 Encl. 4.17, the Statalarm will be added to the "Out of Normal" section of the Unit Turnover Sheet and a "T/O Sheet" or "CBWO" label will be placed on the alarm window.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because it would be correct for removal of a Control Room indication.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it is correct for control room indication that is removed from service.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it is correct for control room indication that is removed from service.
Second part is incorrect. Plausible because it would be correct for removal of a Control Room indication.
Basis for meeting the KA Question requires knowledge of the process for tracking inoperable Statalarms.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 42 Q69 Development References Student References Provided ILT 42 Q69 OP/0/A/1108/001 Encl. 4.17 Rev 115 ADM-OMP Obj 01 GEN2.2 2.2.43 - GENERIC - Equipment Control Equipment Control Knowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 142 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.2 2.2.7 - GENERIC - Equipment Control QUESTION 71 B Equipment Control Knowledge of the process for conducting special or infrequent tests. (CFR: 41.10 / 43.3 / 45.13)
In accordance with AD-OP-ALL-0106 (Conduct of Infrequently Performed Tests or Evolutions) (IPTE)
- 1) A Shift Manager __(1)__ fill the role of the IPTE Manager.
- 2) Lowered RCS inventory __(2)__ considered an Infrequently Performed Test or Evolution.
A. 1. can
- 2. is B. 1. can NOT
- 2. is C. 1. can
- 2. is NOT D. 1. can NOT
- 2. is NOT Monday, March 16, 2020 Page 143 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 71 B General Discussion Answer A Discussion Incorrect: First part is incorrect. Plausible because the Shift Manager ensures required plant conditions are maintained during performance of IPTE and maintains responsibility for termination of any Tests or Evolutions which will or has placed the plant in an unacceptable condition for operation and monitors briefing of all Operational evolutions to ensure awareness and participation of operations team members.
Second part is correct.
Answer B Discussion CORRECT: The IPTE Manager must be senior to the Shift Manager. Entry into lowered inventory conditions is an activity listed on Attachment 3 that has been pre-screened as an IPTE.
Answer C Discussion Incorrect: First part is incorrect. Plausible because the Shift Manager ensures required plant conditions are maintained during performance of IPTE and maintains responsibility for termination of any Tests or Evolutions which will or has placed the plant in an unacceptable condition for operation and monitors briefing of all Operational evolutions to ensure awareness and participation of operations team members.
Second part is incorrect. Plausible since this is an activity performed every outage, and with three units at Oconee, it occurs with relative frequency and Standard Reactor Vessel Disassembly, Reassembly and associated lifting and rigging of Reactor components are NOT required to utilize the IPTE process.
Answer D Discussion Incorrect: First part is correct.
Second part is incorrect. Plausible since this is an activity performed every outage, and with three units at Oconee, it occurs with relative frequency and Standard Reactor Vessel Disassembly, Reassembly and associated lifting and rigging of Reactor components are NOT required to utilize the IPTE process.
Basis for meeting the KA Requires knowledge of the process for performing Infrequently Performed Tests or Evolutions.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory NEW Development References Student References Provided AD-OP-ALL-0106 Rev 4 GEN2.2 2.2.7 - GENERIC - Equipment Control Equipment Control Knowledge of the process for conducting special or infrequent tests. (CFR: 41.10 / 43.3 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 144 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.3 2.3.7 - GENERIC - Radiation Control QUESTION 72 A Radiation Control Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10)
An RWP that you are preparing to work under states the highest dose rate in a particular area (at 30 cm) is 325 mR/hr. As you travel to the work site, a flashing blue light is noted in the entry path to the area.
- 1) The RWP will designate the area as a __(1)__.
- 2) The flashing blue light indicates __(2)__.
A. 1. High Radiation Area
- 2. radiography is in progress B. 1. Radiation Area
- 2. radiography is in progress C. 1. High Radiation Area
- 2. the area has been designated as a Locked High Radiation Area D. 1. Radiation Area
- 2. the area has been designated as a Locked High Radiation Area Monday, March 16, 2020 Page 145 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 72 A General Discussion Answer A Discussion CORRECT. Dose rates from > 100 to < 1000 mR/hr at 30 cm is a HIGH radiation area. Posting requirement is 80 to < 800 mrem/hr at 30 cm.
(Posted at 80% value).
The flashing blue light signifies radiography in progress.
Answer B Discussion Incorrect. First part is incorrect. Plausible because it would be correct if the dose rate were < 100 mr/hr at 30 cm.
Second part is correct. The flashing blue light signifies radiography in progress.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because a flashing yellow light signifies a Locked High Radiation Area.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it would be correct if the dose rate were < 100 mr/hr at 30 cm.
Second part is incorrect. Plausible because a flashing yellow light signifies a Locked High Radiation Area.
Basis for meeting the KA Question requires knowledge of the different radiation areas and how an area would be designated on an RWP based on dose rate.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED ILT 45 Q73 Development References Student References Provided ILT 45 Q73 RAD-RPP Obj 10 AD-RP-ALL-0009, Attach 2 Rev 01 GEN2.3 2.3.7 - GENERIC - Radiation Control Radiation Control Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10)
Remarks/Status Monday, March 16, 2020 Page 146 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.4 2.4.2 - GENERIC - Emergency Procedures / Plan QUESTION 73 B Emergency Procedures / Plan Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 / 45.7 / 45.8)
Given the following Unit 1 conditions:
Reactor power = 100%
Which ONE of the following would require entry into the EOP?
A. Reactor power rises to 102%
B. Reactor Coolant System pressure rises to 2360 psig C. Group 2 Rod 6 Control Rod fully inserts into the core D. Reactor Coolant System leakage in the RB of 55 gpm Monday, March 16, 2020 Page 147 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 73 B General Discussion Answer A Discussion Incorrect. Plausible because it would be correct if power inceased above 105.5%. Also it is above the ICS limit of 101%.
Answer B Discussion Correct. A reactor trip will occur when RCS pressure reaches 2355 psig. If the RPS does not trip the reactor, the operator is required to per AD-OP-ONS-0002 Attachment 1 (Licensed Operator Memory Items). This would require entering the EOP.
Answer C Discussion Incorrect. Plausible because it would be correct if 2 control rods dropped into the core.
Answer D Discussion Incorrect. Plausible because it would be correct if RCS leakage were greeater then "Normal Makeup Capability". Also at this leak rate, a reactor shut down is required but not a reactor trip.
Basis for meeting the KA Question requires knowledge of system events/setpoints that would result in entry into the EOP.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 42 Q73 Development References Student References Provided ILT 42 Q73 AD-OP-ONS-0002 Attachment 1 Rev 1 GEN2.4 2.4.2 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 / 45.7 / 45.8)
Remarks/Status Monday, March 16, 2020 Page 148 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.4 2.4.26 - GENERIC - Emergency Procedures / Plan QUESTION 74 C Emergency Procedures / Plan Knowledge of facility protection requirements, including fire brigade andportable fire fighting equipment usage. (CFR: 41.10 / 43.5 / 45.12)
Given the following Unit 1 conditions:
Reactor power = 100%
1SA-3/B6 (FIRE ALARM) actuated Fire Alarm panel indication o point 0202071 (Unit 1 pipe trench room 348 North End) actuated o point 0202072 (Unit 1 pipe trench room 348 East Side) actuated AP/0/A/1700/043 (Fire Brigade Response Procedure) is in progress
- 1) MERT will be dispatched to the area __(1)__.
- 2) In accordance with AP/0/A/1700/043, if water is to be used for extinguishing the fire, a transformer mulsifyre is activated or a fire hydrant is opened to __(2)__.
Which ONE of the following completes the statements above?
A. 1. ONLY after the fire is confirmed
- 2. ensure HPSW pump minimum flow requirements are met B. 1. ONLY after the fire is confirmed
- 2. mitigate the pressure surge from any water hammer event that occurs upon HPSW pump start C. 1. at the same time as the fire brigade
- 2. ensure HPSW pump minimum flow requirements are met D. 1. at the same time as the fire brigade
- 2. mitigate the pressure surge from any water hammer event that occurs upon HPSW pump start Monday, March 16, 2020 Page 149 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 74 C General Discussion Answer A Discussion Incorrect. First part is incorrect because the MERT is sent with the fire brigade upon receiving two alarms in the same area. It is plausible because if it were only one alarm in the area, it would be correct.
Second part is correct. Per a note in AP/0/A/1700/043, minimum flow concerns of HPSW pumps can develop if a HPSW pump is operating with discharge flow < 1450 gpm.
Answer B Discussion Incorrect. First part is incorrect because MERT is sent with the fire bridge upon receiving two alarms in the same area. It is plausible because if it were only one alarm in the area, it would be correct.
Second part is incorrect because the step is performed to ensure HPSW pump minimum flow requirements are met. It is plausible because if a water hammer were to occur when the HPSW pump was started, having a mulsifyre or hydrant open could serve to relieve some of the pressure spike.
Answer C Discussion CORRECT. First part is correct. Per 1SA3/B-6, IAAT two or more detectors are in alarm in the same zone: Dispatch Fire brigade and MERT.
Second part is correct. Per a note in AP/0/1700/043, minimum flow concerns of HPSW pumps can develop if a HPSW pump is operating with discharge flow < 1450 gpm.
Answer D Discussion Incorrect. First part is correct. Per 1SA3/B-6, IAAT two or more detectors are in alarm in the same zone: Dispatch Fire brigade and MERT.
Second part is incorrect because the step is performed to ensure HPSW pump minimum flow requirements are met. It is plausible because if a water hammer were to occur when the HPSW pump was started, having a mulsifyre or hydrant open could serve to relieve some of the pressure spike.
Basis for meeting the KA Question matches the KA by requiring knowledge of requirements for dispatching fire brigade / MERT when receiving a fire alarm and knowledge of HPSW pump minimum flow requirements and actions taken to protect them when using water to extinguish a fire.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Memory BANK ILT 47 Q74 Development References Student References Provided ILT 47 Q74 AP/0/A/1700/043 Rev 10 EAP-AP43 Obj 04 GEN2.4 2.4.26 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of facility protection requirements, including fire brigade andportable fire fighting equipment usage. (CFR: 41.10 / 43.5 / 45.12)
Remarks/Status Monday, March 16, 2020 Page 150 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.4 2.4.34 - GENERIC - Emergency Procedures / Plan QUESTION 75 D Emergency Procedures / Plan Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5
/ 45.13)
Given the following Unit 2 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Control Room being evacuated due to chemical spill The CRS has implemented AP/2/A/1700/008 (Loss of Control Room)
In accordance with AP/08,
- 1) The RO is dispatched to the __(1)__.
- 2) RCS pressure will be controlled utilizing Pzr heater Bank 2 Groups __(2)__.
Which ONE of the following completes the statements above?
A. 1. Standby Shutdown Facility
- 2. B and C B. 1. Standby Shutdown Facility
- 2. B and D C. 1. Unit 2 Auxiliary Shutdown Panel
- 2. B and C D. 1. Unit 2 Auxiliary Shutdown Panel
- 2. B and D Monday, March 16, 2020 Page 151 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 75 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because the Standby Shutdown Facility is used for a fire that results in the loss of the control room.
Second part is incorrect. Plausible because PZR heater Group 2 Banks B and C are controlled from the SSF which would be used if the evacuation was due to a fire.
Answer B Discussion Incorrect. First part is incorrect. Plausible because the Standby Shutdown Facility is used for a fire that results in the loss of the control room..
Second part is correct. The ASDP uses PZR heater Bank 2 Groups B and D for RCS pressure control.
Answer C Discussion Incorrect. First part is correct. AP/08 directs going to the ASDP when evacuating the control room for any condition other than a fire. Second part is incorrect. Plausible because PZR heater Group 2 Banks B and C are controlled from the SSF which would be used If the evacuation was due to a fire.
Answer D Discussion CORRECT. First part is correct. AP/08 directs going to the ASDP when evacuating the control room for any condition other than a fire. Second part is correct. The ASDP uses PZR heater Bank 2 Groups B and D for RCS pressure control.
Basis for meeting the KA Question requires knowledge of RO action outside of the CR during an emergency and how RCS pressure will be controlled by that RO.
Basis for Hi Cog Basis for SRO only Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK ILT 43 Q74 Development References Student References Provided ILT 43 Q74 U2 AP 8 Rev 15 IC-ASP Obj 01 GEN2.4 2.4.34 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5
/ 45.13)
Remarks/Status Monday, March 16, 2020 Page 152 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination EPE009 EA2.34 - Small Break LOCA QUESTION 76 A Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 / 45.13)
Conditions for throttling or stopping HPI ............................
Given the following Unit 1 conditions:
Time = 0400:
Reactor power = 40%
SBLOCA occurs due to break on 1A hot leg ES Channels 1 - 8 actuated Core SCM = 0ºF EOP Enclosure 5.1 (ES Actuation) in progress Seal Inlet HDR Flow = 25 gpm HPI Flow Train A flow = 456 gpm HPI Flow Train B flow = 482 gpm
- 1) __(1)__ HPI header(s) is/are exceeding the HPI pump flow limits in accordance with Rule 6 (HPI Pump Throttling Limits).
- 2) In accordance with TS 3.5.2 (HPI) Bases, the MINIMUM number of HPI trains required to mitigate this event is __(2)__.
Which ONE of the following completes the statements above?
A. 1. BOTH
- 2. one B. 1. BOTH
- 2. two C. 1. ONLY 1B
- 2. one D. 1. ONLY 1B
- 2. two Monday, March 16, 2020 Page 153 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 76 A General Discussion Answer A Discussion CORRECT. Both headers have only one HPI pump operating and both are exceeding 475 gpm. The "A" header must include Seal Inlet Flow.
Both HPI pump flows will be throttled.
Per TS 3.5.2 Bases, one HPI train provides sufficient flow to mitigate most small break LOCAs. The exception is a cold leg break located on the discharge of the reactor coolant pumps, because some HPI injection will be lost out the break.
Since the break is on the 1A hot leg, only one train is required. Also, if the ADV flow path is operable for a steam generator, the safety analysis has demonstrated that only one HPI train is required to mitigate the consequences of a small break LOCA when THERMAL POWER is 50%
RTP (this includes cold leg breaks).
Answer B Discussion Incorrect.. First part is correct.
Second part is incorrect. Plausible because for a cold leg break on the discharge of the RCPs with reactor power > 50%, it would be correct.
Answer C Discussion Incorrect. First part is incorrect. Plausible because without adding Seal Inlet header flow, it appears correct.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because without adding Seal Inlet header flow, it appears correct.
Second part is incorrect. Plausible because for a cold leg break on the discharge of the RCPs with reactor power > 50%, it would be correct.
Basis for meeting the KA Question requires knowledge of conditions that would require throttling HPI during a Small Break LOCA. It also requires knowledge of the minimum number of HPI trains required to mitigate this event to maintain Safety Function.
Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions:
This question requires knowledge of TS 3.5.2 (HPI) bases.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 42 Q84 Development References Student References Provided ILT 42 Q84 EAP-LOSCM Obj 24 ADM-TSS Obj 04 Rule 6 Rev TS 3.5.2 Bases Rev. 04 EPE009 EA2.34 - Small Break LOCA Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 / 45.13)
Conditions for throttling or stopping HPI ............................
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 154 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE025 2.1.32 - Loss of Residual Heat Removal System (RHRS)
QUESTION 77 A APE025 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12)
Given the following Unit 1 conditions:
Time = 1000:
Mode 6 LPI aligned in Normal Decay Heat Removal mode 1A and 1B SGs in wet layup Fuel Transfer Canal flooded 1B LPI pump OOS Time = 1030:
The running LPI pump tripped and NO LPI pump can be started
- 1) At Time = 1000, OP/1/A/1104/004 (Low Pressure Injection System) directs operation of the __(1)__ LPI pump.
- 2) At Time = 1030, the CRS will initiate AP/1/A/1700/026 (Loss of Decay Heat Removal) Enclosure __(2)__ for heat removal.
Which ONE of the following completes the statements above?
A. 1. 1A
- 2. 5.7 (DHR Using SF Cooling)
B. 1. 1A
- 2. 5.18 (SSF Operation for Loss of DHR Events)
C. 1. 1C
- 2. 5.7 (DHR Using SF Cooling)
D. 1. 1C
- 2. 5.18 (SSF Operation for Loss of DHR Events)
Monday, March 16, 2020 Page 155 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 77 A General Discussion Answer A Discussion CORRECT. With the 1B LPI Pump OOS, the 1A LPI Pump is operated in Decay Heat Removal (DHR), if possible, per the LPI procedure since it would automatically restart when power was restored following a loss of power. With all LPI Pumps unavailable and the Transfer Canal flooded, AP/26 will initiate Encl. 5.7 (DHR Using SF Cooling).
Answer B Discussion Incorrect. The first part is correct. The A or B LPI Pump is operated in Decay Heat Removal (DHR), if possible, per the LPI procedure since these pumps automatically restart when power is restored following a loss of power.
Second part is incorrect. Plausible since this enclosure is utilized in other AP/26 paths when the Fuel Transfer Canal is not full and PSW is not available.
Answer C Discussion Incorrect. First part is incorrect. Plausible since it would be correct if the 1A LPI Pump were unavailable.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible since it would be correct if the 1A LPI Pump were unavailable.
Second part is incorrect. Plausible since this enclosure is utilized in other AP/26 paths when the Fuel Transfer Canal is not full and PSW is not available.
Basis for meeting the KA Per the NRC Chief on 1/03/20, a question concerning a setpoint, limit, or caution related to losing LPI pumps; or loss of inventory, and then an SRO decision point on procedures (procedure selection) will meet the intent of this K/A.
Basis for Hi Cog Basis for SRO only This question is SRO only per ES-401 Attachment 2 Clarification Guidance for SRO-only Questions due to the following:
It cannot be answered solely by using systems knowledge.
It cannot be answered solely by knowing immediate operator actions.
It cannot be answered solely by knowing entry conditions for Aps or direct entry to the EOP.
It cannot be answered solely by knowing the purpose or overall mitigation strategy of a procedure.
The question requires assessing plant conditions and then selecting the proper section of the procedure with which to proceed. 10 CFR 55.43(b)(5)
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 48 Q93 Development References Student References Provided ILT 48 Q93 EAP-AP26 Obj 04 AP/26 Rev 27 APE025 2.1.32 - Loss of Residual Heat Removal System (RHRS)
APE025 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12)
Remarks/Status 1/03/20 - Chief stated we could write question on any setpoint, limit, caution, loss of pumps or loss of inventory and then SRO decision point on procedures (procedure selection or TS Bases).
Monday, March 16, 2020 Page 156 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE040 2.4.21 - Steam Line Rupture QUESTION 78 D APE040 GENERIC Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5 / 45.12)
Given the following on Unit 2:
Initial conditions:
Reactor power = 100%
OAC ALARM, (2MS-93 Backup Nitrogen Press 1 LO-LO) is in alarm In-service Nitrogen bottle pressure for 2MS-93 (TD EFDWP STEAM SUPPLY TRIP VALVE) is 300 psig lowering Current conditions:
- 1) The LCO for TS 3.3.13, (Automatic Feedwater Isolation System (AFIS)) Digital Channels __(1)__ being met.
- 2) The AFIS circuitry provides protection against __(2)__ for MSLBs inside containment and provides protection against exceeding allowable thermal stresses on the steam generator tubes following a MSLB.
Which ONE of the following completes the statements above?
A. 1. is
- 2. an inadvertent return to criticality B. 1. is
- 2. exceeding containment design pressure C. 1. is NOT
- 2. an inadvertent return to criticality D. 1. is NOT
- 2. exceeding containment design pressure Monday, March 16, 2020 Page 157 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 78 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because if N2 pressure was > 770 psig, it would be correct. Additional plausibility is provided if the candidate confuses the N2 pressure with the steam supply pressure for the TD EFDW pump. Normal steam supply pressure is 300 psig and it would have to lower to 250 psig to be inoperable.
Second part is incorrect. Plausible because AFIS limits the overcooling. The overcooling adds positive reactivity. It is reasonable to think that a severe overcooling could produce an inadvertent return to criticality.
Answer B Discussion Incorrect. First part is incorrect. Plausible because if N2 pressure was > 770 psig, it would be correct. Additional plausibility is provided if the candidate confuses the N2 pressure with the steam supply pressure for the TD EFDW pump. Normal steam supply pressure is 300 psig and it would have to lower to 250 psig to be inoperable.
Second part is correct.
Answer C Discussion Incorrect. First part is correct. When N2 Accumulator pressure is < 770 psig, per OP/2/A/1106/006, Entry into TS 3.3.13 Condition A applies.
Second part is incorrect. Plausible because AFIS limits the overcooling. The overcooling adds positive reactivity. It is reasonable to think that a severe overcooling could produce an inadvertent return to criticality.
Answer D Discussion CORRECT. When N2 Accumulator pressure is < 770 psig, per OP/2/A/1106/006, Entry into TS 3.3.13 Condition A applies.
In accordance with TS 3.3.13 Bases, AFIS circuitry provides protection against exceeding containment design pressure.
Basis for meeting the KA Question requires knowledge of operability requirements for the TD EFDW pump as it relates to the Automatic Feedwater Isolation System (AFIS) and the design bases of AFIS as it relates to containment conditions following a Steam Line Rupture.
Basis for Hi Cog Basis for SRO only Question requires knowledge of the bases of TS 3.3.13 that is not system knowledge.
It cannot be answered solely by 1hr or less memory items.
It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits It does require knowledge from TS bases that is not solely systems knowledge Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 16-1 Q89 Development References Student References Provided ILT 16-1 Q89 CF-EF Obj 44, 50 ADM-TSS Obj 04 TS 3.3.13 Bases APE040 2.4.21 - Steam Line Rupture APE040 GENERIC Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5 / 45.12)
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 158 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 78 D Monday, March 16, 2020 Page 159 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE054 2.1.25 - Loss of Main Feedwater (MFW)
QUESTION 79 A APE054 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 / 43.5 / 45.12)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Both Main Feedwater Pumps trip
- 1) In accordance with B&W analysis, a MINIMUM of __(1)__ gallons per minute of Emergency Feedwater flow is required to limit the RCS pressure increase to below the design standard for this event.
- 2) In accordance with AD-OP-ONS-0001, Attachment 1 (NRC Event Notification Worksheet), a Non-Emergency 10 CFR 50.72 notification to the NRC is required in a MAXIMUM of __(2)__ hours.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED A. 1. 375
- 2. 4 B. 1. 375
- 2. 8 C. 1. 750
- 2. 4 D. 1. 750
- 2. 8 Monday, March 16, 2020 Page 160 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 79 A General Discussion Answer A Discussion CORRECT. 375 gpm of emergency feedwater is required to limit RCS pressure below the RCS Safety Limit of 2750 psig during a loss of all main feedwater only per the Emergency Feedwater DBD. A 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ENS notification to the NRC is required due to RPS actuation with the reactor critical.
Answer B Discussion Incorrect. First part is correct. 375 gpm of emergency feedwater is required to limit RCS pressure below the RCS Safety Limit of 2750 psig during a loss of all main feedwater only per the Emergency Feedwater DBD.
Second part is incorrect. Plausible since 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> would be correct for a RPS actuation with the reactor NOT critical.
Answer C Discussion Incorrect. First part is incorrect. Plausible since 750 gpm of emergency feedwater is the amount required to limit RCS pressure during an ATWS.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible since 750 gpm of emergency feedwater is the amount required to limit RCS pressure during an ATWS.
Second part is incorrect. Plausible since 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> would be correct for a RPS actuation with the reactor NOT critical.
Basis for meeting the KA Question requires the ability to interpret reference materials such as tables (Attachment 1, NRC Event Notification Worksheet) during a loss of Main Feedwater Basis for Hi Cog Basis for SRO only This question requires knowledge of AD-OP-ONS-0001 administrative requirements for NRC notifications. This knowledge is specifically linked to objective ADM-FSP 4 and CF-EF Obj. 47 and 49. These objectives are designated as SRO only in the table at the front of the lesson plans and the NRC notification is a task performed by SRO's only.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 44 Q79 Development References Student References Provided ILT 44 Q79 AD-OP-ONS-0001 Attachment 1 ADM-FSP Obj 4 CF-EF Obj 47 and 49 APE054 2.1.25 - Loss of Main Feedwater (MFW)
APE054 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 / 43.5 / 45.12)
Remarks/Status Monday, March 16, 2020 Page 161 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE056 AA2.33 - Loss of Offsite Power QUESTION 80 A Ability to determine and interpret the following as they apply to the Loss of Offsite Power: (CFR: 43.5 / 45.13)
ESF channels, A and B breaker-trip alarms, indicators and bus voltage indicators .........................................
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
Current conditions:
LOCA/LOOP occurs RB pressure = 10 psig rising ES 1-8 actuate
- 1) In accordance with TS 3.3.7 (Engineered Safeguards Protective System (ESPS)
Automatic Actuation Output Logic Channels) Bases, the large break LOCA analysis assumes FULL LPI flow does not occur until a MINIMUM of __(1)__ seconds after the LOCA/LOOP.
- 2) In accordance with TS 3.3.17 (Emergency Power Switching Logic (EPSL) Automatic Transfer Function) Bases, the LIMITING accident for the EPSL transfer functions
__(2)__ a MSLB inside containment along with a simultaneous loss of off-site power.
Which ONE of the following completes the statements above?
A. 1. 74
- 2. is NOT B. 1. 74
- 2. is C. 1. 142
- 2. is NOT D. 1. 142
- 2. is Monday, March 16, 2020 Page 162 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 80 A General Discussion Answer A Discussion CORRECT. The large break LOCA analyses assume Low Pressure Injection (LPI) flow starts in 38 seconds while full LPI flow does not occur until 36 seconds later, or 74 seconds total. The limiting accident for the EPSL transfer functions is a LOCA with a simultaneous loss of offsite power. The loss of offsite power is considered to occur coincident with ES actuation.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because ES is credited to mitigate the LOCA and MSLB events.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it would be correct if the question were asking for RB Spray instead of LPI.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it would be correct if the question were asking for RB Spray instead of LPI.
Second part is incorrect. Plausible because ES is credited to mitigate the LOCA and MSLB events.
Basis for meeting the KA Question requires knowledge of ES components (LPI) during a loss of off-site power and LOCA (full ES actuation), specifically the time allowed in the Safety Analysis for FULL LPI flow following a LOCA/LOOP.
Basis for Hi Cog Basis for SRO only Question requires knowledge of the bases of TS 3.3.7 and 3.3.17 that is not system knowledge.
It cannot be answered solely by 1hr or less memory items.
It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits It does require knowledge from TS bases that is not solely systems knowledge Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided ADM-TSS Electrical Obj 04 ADM-TSS I&C Obj 04 TS 3.3.7 Bases TS 3.3.17 Bases TS 3.6.5 Bases APE056 AA2.33 - Loss of Offsite Power Ability to determine and interpret the following as they apply to the Loss of Offsite Power: (CFR: 43.5 / 45.13)
ESF channels, A and B breaker-trip alarms, indicators and bus voltage indicators .........................................
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 163 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE04 EA2.2 - Inadequate Heat Transfer QUESTION 81 B Ability to determine and interpret the following as they apply to the (Inadequate Heat Transfer)
(CFR: 43.5 / 45.13)
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
Given the following Unit 1 conditions:
Time = 0400:
Reactor power = 100%
2SA-18/A-11, (TURBINE BSMT WATER LEVEL EMERGENCY HIGH) actuated AP/1/A/1700/010, (Turbine Building flood) initiated Time = 0430:
ALL CBPs, Main, and Emergency FDW pumps have tripped Protected Service Water (PSW) is NOT available
- 1) At Time = 0430, the CRS __(1)__ transfer to the LOHT tab.
- 2) The next method that will be used to remove decay heat is __(2)__.
Which ONE of the following completes the statements above?
A. 1. will NOT
- 2. initiation of HPI Forced Cooling B. 1. will NOT
- 2. feeding with the SSF ASW pump C. 1. will
- 2. initiation of HPI Forced Cooling D. 1. will
- 2. feeding with the SSF ASW pump Monday, March 16, 2020 Page 164 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 81 B General Discussion Answer A Discussion Incorrect. 1st part is correct. There is no step in the TBF tab including the Parallel Action page that directs going to the LOHT tab.
2nd part is incorrect. While both methods are IAAT steps in the TBF tab, at 0430 when the pumps trip, the IAAT step for lining up the SSF ASW pump becomes applicable. The IAAT step for performing HPI FC will not become applicable until the SGs dry out and RCS pressure increases to 2300 psig. It is plausible because steps do exist such that if SSF ASW is not available, it could be correct.
Answer B Discussion CORRECT. 1st part is correct. There is no step in the TBF tab including the Parallel Action page that directs going to the LOHT tab.
2nd part is correct. While both methods are IAAT steps in the TBF tab, at 0430 when the pumps trip, the IAAT step for lining up the SSF ASW pump becomes applicable. The IAAT step for performing HPI FC will not become applicable until the SGs dry out and RCS pressure increases to 2300 psig.
Answer C Discussion Incorrect. 1st part is incorrect because there no transfer to the LOHT tab from the TBF tab. It is plausible because criteria for performance of the LOHT tab has been met and the LOHT tab is a higher priority tab.
2nd part is incorrect. While both methods are IAAT steps in the TBF tab, at 0430 when the pumps trip, the IAAT step for lining up the SSF ASW pump becomes applicable. The IAAT step for performing HPI FC will not become applicable until the SGs dry out and RCS pressure increases to 2300 psig. It is plausible because steps do exist such that if SSF ASW is not available, it could be correct.
Answer D Discussion Incorrect. 1st part is incorrect because there no transfer to the LOHT tab from the TBF tab. It is plausible because criteria for performance of the LOHT tab has been met and the LOHT tab is a higher priority tab.
2nd part is correct. While both methods are IAAT steps in the TBF tab, at 0430 when the pumps trip, the IAAT step for lining up the SSF ASW pump becomes applicable. The IAAT step for performing HPI FC will not become applicable until the SGs dry out and RCS pressure increases to 2300 psig.
Basis for meeting the KA The question requires the candidate to evaluate plant conditions and determine that a LOHT and a TBF exist and then pick the appropriate procedure to mitigate the event.
Basis for Hi Cog Basis for SRO only NUREG 1021, ES 401, Attachment 2, E Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]
The applicants knowledge can be evaluated at the level of 10 CFR 55.43(b)(5) by ensuring that the additional knowledge of the procedures content is required to correctly answer the written test item, for example:
Knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 16-1 Q81 Development References Student References Provided ILT 16-1 Q81 EOP TBF tab EAP-TBF BWE04 EA2.2 - Inadequate Heat Transfer Ability to determine and interpret the following as they apply to the (Inadequate Heat Transfer)
(CFR: 43.5 / 45.13)
Monday, March 16, 2020 Page 165 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 81 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
B Remarks/Status Monday, March 16, 2020 Page 166 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination APE069 AA2.02 - Loss of Containment Integrity QUESTION 82 C Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5 / 45.13)
Verification of automatic and manual means of restoring integrity .......
Given the following on Unit 1:
Reactor startup is in progress Reactor in MODE 3 1FDW-104 (1B SG Shell Drain Block) is declared INOPERABLE and is deactivated to satisfy TS 3.6.3 (Containment Isolation Valves) Condition A
- 1) The Unit 1 startup __(1)__ continue into MODE 2.
- 2) If administrative controls are established to open 1FDW-104, the time that it is allowed to be open __(2)__ limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED A. 1. can
- 2. is B. 1. can NOT
- 2. is C. 1. can
- 2. is NOT D. 1. can NOT
- 2. is NOT Monday, March 16, 2020 Page 167 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 82 C General Discussion Answer A Discussion Incorrect. 1st part is correct.
2nd part is incorrect. When under administrative controls, the time that 1FDW-104 is open is not limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is plausible because if administrative controls were not in place, the required action for condition A would have to be completed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Answer B Discussion Incorrect. 1st part is incorrect. The startup may continue to Mode 2. It is plausible because there is not a note saying LCO 3.0.4 does not apply.
2nd part is incorrect. When under administrative controls, the time that 1FDW-104 is open is not limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is plausible because if administrative controls were not in place, the required action for condition A would have to be completed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Answer C Discussion CORRECT. Since TS 3.6.3 allows for unlimited operation once the Required Action is satisfied, entry into MODE 2 is allowed. LCO 3.0.4 states that:
When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Since continued operation is allowed, Mode change is allowed.
2nd part is correct. The TS Bases allows "intermittent" operation which is not limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Answer D Discussion Incorrect. First part is incorrect. The startup may continue to Mode 2. It is plausible because there is not a note saying LCO 3.0.4 does not apply.
2nd part is correct.
Basis for meeting the KA Question requires knowledge of TS administrative controls for inoperable containment isolation valves and whether or not the use of administrative controls is limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, which is a manual means of restoring and controlling containment integrity.
Basis for Hi Cog Basis for SRO only This question is SRO only because it requires knowledge of the TS Bases to analyze plant conditions in order to determine required actions and requires application of the generic rules of TS per Section 3.0.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 47 Q90 Development References Student References Provided ILT 47 Q90 TS 3.6.3 TS 3.6.3 TS 3.6.3 Bases ADM-TSS Obj. 02, 04, 05 APE069 AA2.02 - Loss of Containment Integrity Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5 / 45.13)
Verification of automatic and manual means of restoring integrity .......
Remarks/Status Preview Question - Changed out 2/18/2020.
Monday, March 16, 2020 Page 168 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWA02 2.1.20 - Loss of NNI-X QUESTION 83 D BWA02 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)
Given the following Unit 1 conditions:
Time = 1200:
Reactor power = 100%
Pressurizer temperature indicates as shown below Which ONE of the following describes ALL Tech Spec 3.3.8 (PAM Instrumentation)
Condition(s) that apply (if any) at Time = 1200?
REFERENCE PROVIDED A. NO Tech Spec 3.3.8 Condition applies B. Condition A ONLY C. Condition A, C, and H D. Condition A and C ONLY Monday, March 16, 2020 Page 169 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 83 D General Discussion This question requires an understanding that there are only two channels of Pressurizer temperature. One channel includes Pressurizer level 1 &
2 and the other channel is Pressurizer level 3. TS 3.3.8 requires both channels operable (per TS 3.3.8 Table 3.3.8-1. That means that either Pressurizer level 1 or 2 has to be operable as well as Pzr level 3 to meet the LCO requirments of TS 3.3.8. Additionally, Pzr temp A feeds both Pzr level 1 and 2 and Pzr temp B feeds Pzr level 3. This means that a loss of Pzr temp A renders both Pressurizer levels 1 and 2 inoperable and a loss of Pzr temp B renders Pzr level 3 inoperable.
Answer A Discussion Incorrect. Plausible because TS 3.3.8 does not specifically require Pzr temperature to be operable. If the candidate does not know TS bases information that requires the required pressurizer level channels to be temperature compensated, then this would be the choice made since the temperature instruments are not specifically listed as required instrumentation in TS 3.3.8.
Answer B Discussion Incorrect. Plausible since it would be correct if the candidate were to have the misconception that one of the temperatures being displayed was accurate. Believing that either temperature is correct for 100% power would lead to this choice.
Answer C Discussion Incorrect. Plausible since it is reasonable that when applying TS 3.3.8 to immediately go to Table 3.3.8-1 and enter the condition specified in the right hand column for the PAM instrument with an inoperability. Additionally, this would be correct if the inoperabilities continued beyond the 7 day Completion time of Condition C.
Answer D Discussion CORRECT. TS 3.3.8 requires that either Pzr level 1 or 2 AND Pzr level 3 be operable. Pressurizer temp A feeds Pzr level channels 1 & 2 and Pzr temp B feeds Pzr level channel 3. With Rx power at 100%, Pzr temp should be saturation temperature for normal pressure which is approximately 2155. That means Pzr temp should be reading approximately 647 degrees. With both Pzr temps being inaccurate, NO pressurizer levels are Operable. Therefore, Condition A AND C would apply.
Basis for meeting the KA Question requires the ability to interpret and utilize TS 3.3.8 due to the loss of NNI (Pzr level). Loss of Pzr level was given as an example that could be used on this question by the NRC Chief on 1/03/20.
Basis for Hi Cog Basis for SRO only This question is SRO in that it requires application of TS 3.3.8 and is not a direct lookup. Correct application of the spec cannot be performed based solely on systems knowledge.
This question cannot be answered Solely on 1 hr or less TS knowledge.
This question cannot be answered based on "above the line" TS information.
This question cannot be answered with TS Safety Limit information.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 45 Q92 Development References Student References Provided ILT 45 Q92 TS 3.3.8 TS 3.3.8 ADM-TSS Obj 05 BWA02 2.1.20 - Loss of NNI-X BWA02 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)
Remarks/Status 1/03/20 - Chief stated we could write a question on any of the non-nuclear instruments (i.e. Loss of PZR level).
Monday, March 16, 2020 Page 170 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE03 EA2.1 - Inadequate Subcooling Margin QUESTION 84 C Ability to determine and interpret the following as they apply to the (Inadequate Subcooling Margin)
(CFR: 43.5 / 45.13)
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Given the following Unit 1 conditions:
Time = 0800:
Reactor trip from 100% power Excessive Heat Transfer on 1A SG Rule 5 (Main Steam Line Break) initiated ALL SCMs = 0°F RCPs secured in accordance with Rule 2 (Loss of SCM)
Following initial entry into Subsequent Actions (SA), the procedural flowpath required for event mitigation is ______.
Which ONE of the following completes the statement above?
A. EHT, FCD, LOSCM B. LOSCM, EHT, SA C. LOSCM, EHT, FCD D. EHT, LOSCM, LOCA CD Monday, March 16, 2020 Page 171 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 84 C General Discussion Answer A Discussion Incorrect. Plausible since the EHT tab will be performed and it will direct a transfer to the FCD tab which has a parallel action page entry for LOSCM Answer B Discussion Incorrect. Plausible since the LOSCM tab will be enetered first and will direct a transfer to the EHT tab and the EHT tab would eventually direct a transfer to SA if no SG were isolated or had an unisolable steam leak.
Answer C Discussion CORRECT. Following initial entry into Subsequent Actions, the CRS will transfer to the LOSCM tab. The LOSCM tab will direct the CRS to transfer to the EHT tab since the loss of SCM is being caused by an EHT event. The EHT tab will eventually direct the CRS to transfer to the FCD tab to continue the plant cooldown.
Answer D Discussion Incorrect. Plausible since both the EHT and LOSCM tabs will be entered and the LOSCM tab does direct a transfer to the LOCA CD tab if required RCS makeup flow is not within normal makeup capability.
Basis for meeting the KA Question requires the ability to select appropriate procedures (EOP tabs) during a loss of SCM.
Basis for Hi Cog Basis for SRO only NUREG 1021, ES 401, Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)]
This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.
The EOP procedural transfers in this question are transfers embedded in the tabs.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided LOSCM tab Rev 01 EHT tab FCD tab EAP-EHT Obj 06 BWE03 EA2.1 - Inadequate Subcooling Margin Ability to determine and interpret the following as they apply to the (Inadequate Subcooling Margin)
(CFR: 43.5 / 45.13)
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Remarks/Status Monday, March 16, 2020 Page 172 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 84 C Monday, March 16, 2020 Page 173 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination BWE14 2.4.30 - EOP Enclosures QUESTION 85 A BWE14 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11)
Given the following Unit 3 conditions:
Time = 0800:
Reactor power = 100%
SBLOCA occurs MANUAL Reactor Trip initiated Time = 0801:
ALL SCMs = 0°F ES Channels 1 and 2 actuated LOSCM tab initiated Time = 0821:
ALL SCMs = 0°F 3RIA-57 indicates 100 R/hr slowly rising 3RIA-58 indicates 45 R/hr slowly rising
- 1) The current Emergency Plan Classification would be a/an __(1)__.
- 2) The MAXIMUM time allowed to notify the NRC per AD-EP-ALL-0111, (Control Room Activation of the ERO) is __(2)__.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED A. 1. Alert
- 2. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 1. Alert
- 2. 15 minutes C. 1. Site Area Emergency
- 2. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. 1. Site Area Emergency
- 2. 15 minutes Monday, March 16, 2020 Page 174 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 85 A General Discussion Answer A Discussion CORRECT. Per Table F-1 Fission Product Barrier Threshold Matrix, there is a Loss of the RCS Barrier. Any loss or potential loss of the RCS barrier is an Alert (FA1.1).
The NRC must be notified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following a classification.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because if it was asking about State and Local agencies, it would be correct.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if it had been 30 minutes since shutdown, it would be correct. If the candidate reads the wrong line in Table F-2, it would indicate a Loss of the Fuel Clad barrier. Loss of any 2 barriers is a SAE (FS1.1).
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if it had been 30 minutes since shutdown, it would be correct. If the candidate reads the wrong line in Table F-2, it would indicate a Loss of the Fuel Clad barrier. Loss of any 2 barriers is a SAE (FS1.1).
Second part is incorrect. Plausible because if it was asking about State and Local agencies, it would be correct.
Basis for meeting the KA Question requires knowledge of the Eplan and the classification when in the LOSCM tab of the EOP that requires reporting to State and Local agencies, and the NRC.
Basis for Hi Cog Basis for SRO only Question requires the applicant to evaluate plant conditions and make emergency classifications based on their evaluation. This is an SRO ONLY task.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 16-1 Q84 Development References Student References Provided ILT 16-1 Q84 Wallcharts CSD-EP-ONS-0101-02 Rev 000 AD-EP-ALL-0111 Rev 0 EAL Wallcharts rev 0 EAP-SEP Obj 18 BWE14 2.4.30 - EOP Enclosures BWE14 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11)
Remarks/Status Monday, March 16, 2020 Page 175 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS003 A2.02 - Reactor Coolant Pump System (RCPS)
QUESTION 86 C Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5/ 45.3 / 45/13)
Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP ...................
Given the following Unit 1 conditions:
Time = 0800:
Reactor in MODE 3 1A2 and 1B2 RCPs operating Time = 0805:
All SCMs = 25°F stable 1A2 RCP Motor Upper Guide Bearing temperature = 195°F slowly rising 1B2 RCP Motor Stator Temperature = 255°F slowly rising Time = 0810:
Pressurizer level = 200 inches stable RCS leakage = 190 gpm stable The operating RCP trips
- 1) At time = 0805, AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation) will direct tripping the __(1)__ RCP.
- 2) At time = 0810, the SRO should direct plant shutdown actions in accordance with the __(2)__ Cooldown tab of the EOP.
Which ONE of the following completes the statements above?
A. 1. 1B2
- 2. LOCA B. 1. 1B2
- 2. Forced C. 1. 1A2
- 2. LOCA D. 1. 1A2
- 2. Forced Monday, March 16, 2020 Page 176 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 86 C General Discussion Answer A Discussion Incorrect: The temp limit for motor stator is 300 degrees. 255 degrees is plausible since there are several ITC trip setpoints with temps less than 255 degrees (examples are Radial Bearing temps (225) and thrust bearing temps (195).
Second part is correct.
Answer B Discussion Incorrect: The temp limit for motor stator is 300 degrees. 255 degrees is plausible since there are several ITC trip setpoints with temps less than 255 degrees (examples are Radial Bearing temps (225) and thrust bearing temps (195).
Second part is incorrect. Plausible since it would be correct if the leak rate were < 160 gpm.
Answer C Discussion
.CORRECT. The HI OAC alarm at 170 degrees for upper guide bearing temperature will direct referring to AP/16. The Immediate Trip Criteria (ITC) limit for the upper guide bearing temp is 195 degrees, therefore the ITC has been exceeded. Per AP/16, if in MODE 3 you trip the affected RCP. When the second RCP is lost the entry conditions are met for the EOP. The Subsequent Actions tab will assess if there is an RCS leak greater than normal makeup capability (about 160 gpm), and if so, the CRS will transfer to the LOCA CD tab to perform the plant cooldown.
This step will be reached prior to the transfer to Forced Cooldown when NC cooldown is desired.
Answer D Discussion Incorrect: First part is correct.
Second part is incorrect. Plausible since it would be correct if the leak rate were < 160 gpm.
Basis for meeting the KA Requires predicting the impact of the malfunctions on RCP operation and using AP/16 (Abnormal RCP Ops) to determine actions required to shutdown the RCP under the abnormal conditions and to determine which EOP tab will be entered based on the transfer steps in the SA tab.
Basis for Hi Cog Basis for SRO only Requires assessing plant conditions (the need to secure RCP bases on Immediate Trip Criteria) and then prescribing a section of a procedure (which cooldown section) with which to proceed. The correct answer requires detailed knowledge beyond major mitigation strategy of the Subsequent Actions tab.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 2009B Q86 Development References Student References Provided ILT 2009B Q86 AP/1/A/1700/016 EOP-SA tab EAP-LCD Obj R9 SYS003 A2.02 - Reactor Coolant Pump System (RCPS)
Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5/ 45.3 / 45/13)
Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP ...................
Remarks/Status Monday, March 16, 2020 Page 177 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS004 A2.12 - Chemical and Volume Control System QUESTION 87 A Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/ 43/5 / 45/3 / 45/5)
CIAS, SIAS .....................................................
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
Current conditions:
Core SCM = 0°F Rule 2 (Loss of SCM) is in progress 1HP-24 and 1HP-25 fail closed RCS pressure = 890 psig lowering RB pressure = 2.1 psig rising
- 1) In accordance with Rule 2, when the step to open 1HP-26 and 1HP-27 is reached, there will be __(1)__ LPI pump(s) operating in the piggyback alignment.
requirements.
Which ONE of the following completes the statements above?
A. 1. one
- 2. 3.5.2 High Pressure Injection (HPI)
B. 1. one
- 2. 3.5.3 Low Pressure Injection (LPI)
C. 1. two
- 2. 3.5.2 High Pressure Injection (HPI)
D. 1. two
- 2. 3.5.3 Low Pressure Injection (LPI)
Monday, March 16, 2020 Page 178 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 87 A General Discussion Answer A Discussion CORRECT. 1A and 1B LPI pumps are both started initially, but once the valve lineup is complete for piggyback, if two LPI pumps are running only to provide HPI pump suction, then one of the pumps is secured prior to opening 1HP-26 and 27.
The piping, instruments, valves and controls downstream of and including LP-15 and LP-16, are part of the HPI system and are subject to LCO 3.5.2 (High Pressure Injection system) requirements.
Answer B Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because LP-15 and 16 are LPI valves and per TS bases, as part of the LPI-HPI flow path, the piping, instruments, valves and controls upstream of LP-15 and LP-16 are part of the LPI system and are subject to LCO 3.5.3 (Low Pressure Injection system) requirements.
Answer C Discussion Incorrect. First part is incorrect. Plausible because if RCS pressure were less than LPI pump shutoff head (180 psig), it would be correct.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible because if RCS pressure were less than LPI pump shutoff head (180 psig), it would be correct.
Second part is incorrect. Plausible because LP-15 and 16 are LPI valves and per TS bases, as part of the LPI-HPI flow path, the piping, instruments, valves and controls upstream of LP-15 and LP-16 are part of the LPI system and are subject to LCO 3.5.3 (Low Pressure Injection system) requirements.
Basis for meeting the KA Question requires the ability to predict the impact of a malfunction of the SIAS (HP-24 and 25 failed closed) and procedure guidance used to mitigate the consequences.
Basis for Hi Cog Basis for SRO only Requires detailed procedure knowledge.
Requires knowledge of TS Bases that is required to determine which LCO covers 1LP-15 and 16 since a portion of the LPI-HPI flowpath is covered in LCO 3.5.3 (LPI) and a portion is covered in TS 3.5.2 (HPI).
Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 18-1 Q83 Development References Student References Provided ILT 18-1 Q83 EOP Rule 2 ADM-TSS Obj 04 TS 3.5.2 Bases SYS004 A2.12 - Chemical and Volume Control System Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/ 43/5 / 45/3 / 45/5)
CIAS, SIAS .....................................................
Remarks/Status Preview Question Contacted NRC Chief on 3/03/2020 concerning feedback from preview.
After describing that even though 1LP-15 and 16 have "LPI System" designations, they are considered a part of the "HPI System" in Tech. Spec.,
as described in TS 3.5.2 Bases, the Chief stated that no changes were required to the question at this time.
Monday, March 16, 2020 Page 179 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 87 A Monday, March 16, 2020 Page 180 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS012 2.2.25 - Reactor Protection System (RPS)
QUESTION 88 A SYS012 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)
Given the following Unit 1 conditions:
Initial conditions:
Reactor power = 100%
I&E performing Reactor Protective System (RPS) calibration procedure Current conditions:
The RCS Low Pressure trip setpoint is determined to be 1804 psig in 1A and 1B RPS Channels
- 2) In accordance with the bases of Tech Spec 3.3.1 (Reactor Protective System (RPS) Instrumentation), the 1A and 1B RCS Low Pressure Trip Functions are
__(2)__.
Which ONE of the following completes the statements above?
A. 1. 1810
- 2. operable B. 1. 1810
- 2. inoperable C. 1. 1800
- 2. operable D. 1. 1800
- 2. inoperable Monday, March 16, 2020 Page 181 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 88 A General Discussion Answer A Discussion CORRECT. The actual RPS trip setpoint for RCS Low pressure is 1810 psig. The low allowable value per TS 3.3.1 is 1800 psig. According to TS 3.3.1 Bases, when the trip setpoint is found to be incorrect, the trip functions are operable if the trip setpoint is within the allowable value.
Answer B Discussion Incorrect. First part is correct. Second part is incorrect.
Second part is incorrect. Plausible to believe the trip function is inoperable when the setpoint is found to be incorrect in the non-conservative direction, and if the setpoint was >10 psig non-conservative, it would be correct.
Answer C Discussion Incorrect. First part is incorrect. Plausible since 1800 is the allowable TS value.
Second part is correct.
Answer D Discussion Incorrect. First part is incorrect. Plausible since 1800 is the allowable TS value.
Second part is incorrect. Plausible to believe the trip function is inoperable when the setpoint is found to be incorrect in the non-conservative direction, and if the setpoint was >10 psig non-conservative, it would be correct.
Basis for meeting the KA Question requires knowledge of TS 3.3.1 Reactor Protection System (RPS) Bases.
Basis for Hi Cog Basis for SRO only This question requires application of Tech Specs and knowledge of Bases information.
It cannot be answered solely by 1hr or less memory items.
It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits It does require application of generic LCO requirements. 10 CFR 55.43(b)(2)
Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 18-1 Q87 Development References Student References Provided ILT 18-1 Q87 ADM-TSS Obj 04, 05 TS 3.3.1 TS 3.3.1 Bases SYS012 2.2.25 - Reactor Protection System (RPS)
SYS012 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)
Remarks/Status Monday, March 16, 2020 Page 182 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS022 A2.04 - Containment Cooling System (CCS)
QUESTION 89 D Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Loss of service water .............................................
Given the following Unit 3 plant conditions:
Reactor power = 100%
3XS3 de-energizes
- 1) Which ONE of the following would require immediate entry into LCO 3.0.3?
- 2) In accordance with LCO 3.0.3 Bases, the power reduction __(2)__ required to be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of LCO 3.0.3 entry.
A. 1. 3A RBS Pump declared inoperable
- 2. is B. 1. 3A RBS Pump declared inoperable
- 2. is NOT C. 1. 3C RBCU declared inoperable
- 2. is D. 1. 3C RBCU declared inoperable
- 2. is NOT Monday, March 16, 2020 Page 183 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 89 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible since RBS pumps are also part of TS 3.6.5 and it would be reasonable to assume that the ability of Containment spray and cooling systems to perform their safety function would be impeded with two of the major components inoperable. The misconception that the safety function is impeded would lead to deducing that 3.0.3 is required. Also plausible if the student confuses the power supply for 3BS-2, which is powered from 3XS5, and if 3BS-2 is inoperable, the 3B RBS train would be inoperable and TS 3.0.3 would apply.
Second part is incorrect. Plausible since LCO 3.0.3 states that Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; MODE 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />; and MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Answer B Discussion Incorrect. First part is incorrect. Plausible since RBS pumps are also part of TS 3.6.5 and it would be reasonable to assume that the ability of Containment spray and cooling systems to perform their safety function would be impeded with two of the major components inoperable. The misconception that the safety function is impeded would lead to deducing that 3.0.3 is required. Also plausible if the student confuses the power supply for 3BS-2, which is powered from 3XS5, and if 3BS-2 is inoperable, the 3B RBS train would be inoperable and TS 3.0.3 would apply.
Second part is correct. LCO 3.0.3 Bases states that upon entering LCO 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in unit operation. If at the end of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, corrective measures which would allow exiting LCO 3.0.3 are not complete, but there is reasonable assurance that corrective measures will be completed in time to still allow for an orderly unit shutdown, commencing a load decrease may be delayed until that time.
Answer C Discussion Incorrect. 3XS3 is the power supply for 3B RBCU. Therefore, 3B and 3C RBCUs would be inoperable. TS 3.6.5 Condition H of TS 3.6.5 requires immediate entry into LCO 3.0.3 with 2 RBCUs inoperable in MODE 1 or 2.
Second part is incorrect. Plausible since LCO 3.0.3 states that Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; MODE 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />; and MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Answer D Discussion CORRECT: 3XS3 is the power supply for 3B RBCU. Therefore, 3B and 3C RBCUs would be inoperable. TS 3.6.5 Condition H of TS 3.6.5 requires immediate entry into LCO 3.0.3 with 2 RBCUs inoperable in MODE 1 or 2. LCO 3.0.3 Bases states that upon entering LCO 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in unit operation. If at the end of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, corrective measures which would allow exiting LCO 3.0.3 are not complete, but there is reasonable assurance that corrective measures will be completed in time to still allow for an orderly unit shutdown, commencing a load decrease may be delayed until that time.
Basis for meeting the KA Requires predicting the impact that losing LPSW to one of the RBCUs will have on the operability of that RBCU as well as the impact on Containment. Once both RBCUs are determined inoperable the question requires the use of TS 3.6.5, LCO 3.0.3, and LCO 3.0.3 Bases to mitigate the consequences of the failure.
Basis for Hi Cog Basis for SRO only Requires an operability determination (done only by SROs) for the 3B RBCU. Requires applying LCO 3.0.3 requirements to specific system failures and determining actions required by LCO 3.0.3 to mitigate the failures. Specific SRO knowledge of time line for LCO 3.0.3 shutdown is required.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ILT 45 Q87 Development References Student References Provided ILT 45 Q87 TS 3.6.5 TS 3.6.5 Bases LCO 3.0.3 Bases ADM-TSS Obj 04 SYS022 A2.04 - Containment Cooling System (CCS)
Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Loss of service water .............................................
Monday, March 16, 2020 Page 184 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination Remarks/Status QUESTION 89 D Monday, March 16, 2020 Page 185 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS013 2.2.44 - Engineered Safety Features Actuation System (ESFAS)
QUESTION 90 D SYS013 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)
Given the following on Unit 1:
Initial conditions:
Reactor power = 100%
Current conditions:
LBLOCA occurs ES 1 - 8 actuated LOSCM tab in progress BOTH LPI trains in service
- 1) In accordance with the LOSCM tab, the MINIMUM LPI flow that requires the CRS to transfer to the LOCA Cooldown tab is __(1)__ gpm.
__(2)__ required to support OPERABILITY of an RBS train.
Which ONE of the following completes the statements above?
A. 1. 2900
- 2. is NOT B. 1. 2900
- 2. is C. 1. 3400
- 2. is NOT D. 1. 3400
- 2. is Monday, March 16, 2020 Page 186 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 90 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible since it would be correct if only one LPI train were in service.
Second part is incorrect. Plausible since RBS has its own flow indication, it is reasonable to believe that it would be used to protect the RBS pumps.
Answer B Discussion Incorrect. First part is incorrect. Plausible since it would be correct if only one LPI train were in service.
Second part is correct.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since RBS has its own flow indication, it is reasonable to believe that it would be used to protect the RBS pumps.
Answer D Discussion CORRECT. Per the LOSCM tab: If LPI flow train A plus LPI flow train B is 3400 gpm or greater, the direction is to GO TO LOCA CD tab. Per TS 3.5.3 (LPI) and 3.6.5 (RBS and RBC) Bases, the safety grade flow indicator of an LPI train is required to support OPERABILITY of the LPI and RBS trains to preclude NPSH or runout problems.
Basis for meeting the KA Question requires the ability to interpret control room indications (LPI flow) and understand EOP tab transfer criteria based on the flow indication and how inoperability of the indication affects plant and system conditions in accordance with TS.
Basis for Hi Cog Basis for SRO only Requires knowledge of an embedded transfer in the EOP, which is procedure selection, and also requires knowledge of Tech Spec Bases information.
It cannot be answered solely by 1hr or less memory items.
It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits It does require knowledge from TS bases that is not solely systems knowledge Job Level Cognitive Level QuestionType Question Source SRO Memory MODIFIED ILT 45 Q86 Development References Student References Provided ILT 45 Q86 LOSCM tab TS 3.5.3 Bases ADM-TSS Obj 04 SYS013 2.2.44 - Engineered Safety Features Actuation System (ESFAS)
SYS013 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)
Remarks/Status Monday, March 16, 2020 Page 187 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS034 2.1.30 - Fuel Handling Equipment System (FHES)
QUESTION 91 B SYS034 GENERIC Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)
Given the following Unit 2 conditions:
Mode 6 Defueling in progress Main Fuel Bridge is withdrawing a fuel assembly that is binding
- 1) In order to bypass the automatic stop in hoist upward movement, __(1)__ will be utilized on the Main Fuel Bridge.
- 2) In accordance with MP/0/A/1500/029 Enclosure 9.7 (Bypassing Rx Bridge Interlocks), authorization is required to be obtained from __(2)__ prior to bypassing the above interlock.
Options for (2) above:
A. Refueling SRO B. Reactor Engineer C. Fuel Handling Supervisor D. Fuel Handling Equipment Engineer Which ONE of the following completes the statements above?
A. 1. Overload Bypass TS-1
- 2. A and C ONLY B. 1. Overload Bypass TS-1
- 2. A, B, C, and D C. 1. Hoist Interlock Bypass TS-2
- 2. A and C ONLY D. 1. Hoist Interlock Bypass TS-2
- 2. A, B, C, and D Monday, March 16, 2020 Page 188 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 91 B General Discussion Answer A Discussion Incorrect. First part is correct. The Overload Bypass TS-1 bypasses automatic stop in hoist upward movement when ~2500 lbs overload is reached.
Second part is incorrect. Plausible because it is correct for the Bridge Left Bypass TS-3, Bridge Right Bypass TS-4, and Trolley Bypass TS-5.
Answer B Discussion CORRECT. The Overload Bypass TS-1 bypasses automatic stop in hoist upward movement when ~2500 lbs overload is reached.
Authorization is required from Refueling SRO, Reactor Engineer, Fuel Handling Supervisor, and the Fuel Handling Equipment Engineer to bypass the interlock.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it is also related to upward movement of the hoist, but it is tied to grapple fingers engaged/disengaged.
Second part is incorrect. Plausible because it is correct for the Bridge Left Bypass TS-3, Bridge Right Bypass TS-4, and Trolley Bypass TS-5.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it is also related to upward movement of the hoist, but it is tied to grapple fingers engaged/disengaged.
Second part is correct.
Basis for meeting the KA Requires knowledge of the operation of local controls (Interlock Bypass switches) on the Main Fuel Bridge and the authorization required to utilize them.
Basis for Hi Cog Basis for SRO only In accordance with "Clarification Guidance for SRO-only Questions", question requires knowledge of Fuel Handling procedures and Refueling SRO responsibilities such as authorizing the bypassing of Main Fuel Bridge interlocks.
Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided MP/0/A/1500/029 Rev 7 SYS034 2.1.30 - Fuel Handling Equipment System (FHES)
SYS034 GENERIC Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 189 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS056 A2.04 - Condensate System QUESTION 92 C Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Loss of condensate pumps .........................................
`
Given the following Unit 1 conditions:
Initial conditions:
Unit 1 TDEFDW pump is out of service A lightning strike in the switchyard causes a reactor trip Incorrect wiring in 4160v relays causes a slow transfer of power to CT-1 Transformer Rule 3 (Loss of Main or Emergency FDW) is in progress Current conditions:
Both MD EFDW pumps fail LOHT tab initiated ALL SCMs > 0°F
- 1) Condensate Booster Pump feed __(1)__ be established.
- 2) IF RCS temperature subsequently rises and results in core SCM = 0°F, the CRS is required to __(2)__.
Which ONE of the following completes the statements above?
A. 1. will
- 2. remain in the LOHT tab B. 1. will
- 2. transfer to the LOSCM tab C. 1. will NOT
- 2. remain in the LOHT tab D. 1. will NOT
- 2. transfer to the LOSCM tab Monday, March 16, 2020 Page 190 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 92 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because AP-11 will re-establish Condensate flow after the loss and regain of all 4160V switchgear (which was due to slow transfer to the startup transformer causing a load shed), however the EOP procedures do not allow CBP feed to be established once it has been lost.
Second part is correct, LOHT tab IAAT step 2 goes to step 4 which directs performing Rule 4, and with HPI FC parameters acceptable a transfer to HPI CD tab is made in step 6.
Answer B Discussion Incorrect. First part is incorrect. Plausible because AP-11 will re-establish Condensate flow after the loss and regain of all 4160V switchgear (which was due to slow transfer to the startup transformer causing a load shed), however the EOP procedures do not allow CBP feed to be established once it has been lost.
Second part is incorrect. Plausible because it would be correct if subcooling were 0°F due to any other reason than RCS heatup.
Answer C Discussion CORRECT. First part: EOP procedures do not allow CBP feed to be established once it has been lost due to the slow transfer of power to the startup transformer, even though condensate flow is restored by AP-11.
Second part: LOHT tab IAAT step 2 goes to step 4 which directs performing Rule 4, and with HPI FC parameters acceptable a transfer to HPI CD tab is made in step 6.
Answer D Discussion INCORRECT. First part is correct: EOP procedures do not allow CBP feed to be established once it has been lost due to the slow transfer of power to the startup transformer, even though condensate flow is restored by AP-11.
Second part is incorrect. Plausible because it would be correct if subcooling were 0°F due to any other reason than RCS heatup.
Basis for meeting the KA Requires the ability to predict the impact of a slow transfer to the startup transformer that will cause a loss of secondary pumps, including condensate pumps, and to use emergency procedures to mitigate the loss of condensate pumps.
Basis for Hi Cog Basis for SRO only SRO Only: 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 43 Q93 Development References Student References Provided ILT 43 Q93 EAP-LOHT Obj 04 EOP LOHT tab EL-EPD Obj 30 SYS056 A2.04 - Condensate System Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Loss of condensate pumps .........................................
Remarks/Status Monday, March 16, 2020 Page 191 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination SYS068 A2.04 - Liquid Radwaste System (LRS)
QUESTION 93 B Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operatios: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Failure of automatic isolation ......................................
Given the following Unit 3 conditions:
Initial conditions:
Reactor power = 100%
3RIA-54 (TBS) HIGH alarm is received Secondary AO reports Unit 3 TBS pumps are operating Current conditions:
CRS enters AP/3/A/1700/018 (Abnormal Release of Radioactivity)
- 1) In accordance with AP/18, the CRS __(1)__ dispatch an AO to open and white tag the TBS pump breakers.
- 2) In accordance with SLC 16.11.3 (Radioactive Effluent Monitoring Instrumentation),
Condition(s) __(2)__ is/are required to be entered.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED A. 1. will
- 2. F ONLY B. 1. will
- 2. B and F C. 1. will NOT
- 2. F ONLY D. 1. will NOT
- 2. B and F Monday, March 16, 2020 Page 192 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 93 B General Discussion Answer A Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because the SLC 16.11.3 COMMITMENT states the radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.3-1 shall be OPERABLE. When the candidate looks at Table 16.11.3-1 for RIA-54, Condition F is listed in the far right column. If the candidate does not read the heading for Table 16.11.3-1 properly, Condition B may be overlooked.
Answer B Discussion CORRECT. AP/18 will direct dispatching an AO to open and white tag the TBS pump breakers. Per Table 16.11.3-1 in SLC 16.11.3, RIA-54 being inoperable requires entering Conditions B and F.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it would be correct for a RIA-54 ALERT alarm.
Second part is incorrect. Plausible because the SLC 16.11.3 COMMITMENT states the radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.3-1 shall be OPERABLE. When the candidate looks at Table 16.11.3-1 for RIA-54, Condition F is listed in the far right column. If the candidate does not read the heading for Table 16.11.3-1 properly, Condition B may be overlooked.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it would be correct for a RIA-54 ALERT alarm.
Second part is correct.
Basis for meeting the KA Requires the ability to predict the impact of a failure of automatic isolation of the TB sump release following an RIA-54 HIGH alarm, and based on that prediction, use procedures (AP/18 and SLC 16.11.3) to mitigate the consequences of the failure.
Basis for Hi Cog Basis for SRO only Requires detailed procedure knowledge of AP/18 and application of required actions in SLC 16.11.3.
It cannot be answered solely by 1hr or less memory items.
It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EP-AP-18 Obj.5 SLC 16.11.3 ADM-TSS Obj. 5 U3 AP/18 SLC 16.11.3 SYS068 A2.04 - Liquid Radwaste System (LRS)
Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operatios: (CFR: 41.5 / 43.5 / 45.3 / 45.13)
Failure of automatic isolation ......................................
Remarks/Status Monday, March 16, 2020 Page 193 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.1 2.1.15 - GENERIC - Conduct of Operations QUESTION 94 C Conduct of Operations Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.
In accordance with AD-OP-ALL-0111 (Operations Communications)
- 1) If an EOP or AOP has an identified Deviation per AD-OP-ALL-1001 (Conduct of Abnormal Operations), then a/an __(1)__ can be used to inform the crew until the EOP or AOP is changed.
- 2) The LOWEST level of management that can approve Operations Supplemental Information Packages (OSIP) and Standing Instructions is the __(2)__ Manager.
Which ONE of the following completes the statements above?
A. 1. OSIP
- 2. Shift B. 1. OSIP
- 2. OPS C. 1. Standing Instruction
- 2. Shift D. 1. Standing Instruction
- 2. OPS Monday, March 16, 2020 Page 194 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 94 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible because OSIPs are used to distribute information to the Operations Department, but it is information that does not impact the operation of the plant, such as OE.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible because OSIPs are used to distribute information to the Operations Department, but it is information that does not impact the operation of the plant, such as OE.
Second part is incorrect. Plausible because the OPS manager can approve OSIPs and Standing Instructions, but the Shift Manager is the lowest level of approval.
Answer C Discussion CORRECT. Per AD-OP-ALL-0111 (Operations Communications), if an EOP or AOP has an identified Deviation per AD-OP-ALL-1001 (Conduct of Abnormal Operations), then a Standing Instruction can be used to inform the crew until the EOP or AOP is changed.
OSIPs and Standing Instructions are approved by Operations Management (Shift Manager or higher).
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible because the OPS manager can approve OSIPs and Standing Instructions, but the Shift Manager is the lowest level of approval.
Basis for meeting the KA Requires knowledge of administrative requirements for Standing Instructions and Operations Supplemental Information Packages (OSIP).
Basis for Hi Cog Basis for SRO only The approval of Standing Instructions and OSIPs is an SRO level task.
Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided AD-OP-ALL-0111 Rev 3 ADM-OMP Obj. 1e GEN2.1 2.1.15 - GENERIC - Conduct of Operations Conduct of Operations Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.
Remarks/Status Monday, March 16, 2020 Page 195 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.1 2.1.40 - GENERIC - Conduct of Operations QUESTION 95 D Conduct of Operations Knowledge of refueling administrative requirements. (CFR: 41.10 / 43.5 / 45.13)
Given the following Unit 2 conditions:
Initial conditions:
Time = 0100 Refueling in progress FTC level = 22 feet stable No water additions are being made to the system 2A LPI train is OPERABLE and in service 2B LPI train is OPERABLE Current conditions:
Time = 2300 Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel Assembly
- 1) In accordance with TS 3.9.4 (DHR and Coolant Circulation-High Water Level), the required DHR loop may not be in operation for a MAXIMUM of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per __(1)__
hour period.
Bases, ECCW __(2)__ required to support the DHR train.
Which ONE of the following completes the statements above?
A. 1. 12
- 2. is NOT B. 1. 12
- 2. is C. 1. 8
- 2. is NOT D. 1. 8
- 2. is Monday, March 16, 2020 Page 196 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 95 D General Discussion Answer A Discussion Incorrect: First part is incorrect but plausible because a normal shift is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Second part is incorrect but plausible since LPSW is required to remove Decay Heat. It is plausible to believe ECCW is not required since when the Reactor is in Modes 5 or 6, single failure criteria does not normally apply and siphon headers required by ECCW are not required unles there is some sort of failure.
Answer B Discussion Incorrect: First part is incorrect but plausible because a normal shift is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 2nd part is correct.
Answer C Discussion Incorrect: First part is correct. 2nd part is incorrect but plausible since LPSW is required to remove Decay Heat. It is plausible to believe ECCS is not required since when the Reactor is in Modes 5 or 6, sngle failure criteria does not normally apply and siphon headers required by ECCW are not required unles there is some sort of failure.
Answer D Discussion CORRECT. TS 3.9.4 (DHR and Coolant Circulation-High Water Level) is in effect as water level is 21.34 ft. This condition requires only 1 DHR loop to be operable and in service since the water can provide adequate backup decay heat removal. TS and Refueling procedures limits & precautions allow SRO to grant permission for the operating loop to be secured for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with adequate level.
The basis of TS 3.9.4 identifies both LPSW and ECCW as required to support DHR loop operability.
Basis for meeting the KA Requires knowledge of administrative and TS requirements related to refueling.
Basis for Hi Cog Basis for SRO only First part requires knowledge of procedures and limitations involved in core alterations, TS and Bases. Second part requires knowledge of the Bases of Tech Spec 3.9.4.
It cannot be answered solely by 1hr or less memory items.
It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits It does require knowledge from TS bases that is not solely systems knowledge Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT 45 Q95 Development References Student References Provided ILT 45 Q95 OP/2/A/1502/007 Rev 83 TS 3.9.4 TS 3.9.4 Bases ADM-TSS Obj 4, 5 GEN2.1 2.1.40 - GENERIC - Conduct of Operations Conduct of Operations Knowledge of refueling administrative requirements. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 197 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.2 2.2.17 - GENERIC - Equipment Control QUESTION 96 D Equipment Control Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. (CFR: 41.10 / 43.5 / 45.13)
Given the following Unit 3 conditions:
Reactor power = 100%
Maintenance personnel preparing to perform EMERGENT work encounter a sign stating Single Point Vulnerability (Trip Sensitive Components). They stop and notify the WCC SRO.
In accordance with AD-OP-ALL-0201 (Protected Equipment), EMERGENT work on or within 2 feet of SPVs is required to be approved by the ______.
A. WCC SRO ONLY B. Shift Manager ONLY C. WCC SRO and Site Duty Manager D. Shift Manager and Site Duty Manager Monday, March 16, 2020 Page 198 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 96 D General Discussion Answer A Discussion Incorrect. Plausible since the WCC SRO approves maintenance activities that are not on or within 2 feet of SPVs.
Answer B Discussion Incorrect. Plausible since the Shift Manager can approve work on Protected Equipment.
Answer C Discussion Incorrect. Plausible since the WCC SRO approves maintenance activities that are not on or within 2 feet of SPVs and the Shift Manager can approve work on Protected Equipment. Therefore, requiring both adds another layer of oversight.
Answer D Discussion CORRECT. Unscheduled (emergent) work on or within two feet of SPVs shall be approved by the Shift Manager and Site Duty Manager.
Basis for meeting the KA Requires knowledge of the process for managing maintenance activities during power operation.
Basis for Hi Cog Basis for SRO only Requires knowledge of Administrative requirements that are specific to the SRO position.
Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided ADM-FSP Obj. 15e AD-OP-ALL-0201 Rev 6 GEN2.2 2.2.17 - GENERIC - Equipment Control Equipment Control Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Preview Question - Modified 2/18/2020.
Monday, March 16, 2020 Page 199 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.2 2.2.20 - GENERIC - Equipment Control QUESTION 97 D Equipment Control Knowledge of the process for managing troubleshooting activities. (CFR: 41.10 / 43.5 / 45.13)
In accordance with IP/0/A/0100/001 (Controlling Procedure for Troubleshooting and Maintenance Activities)
- 1) the position designated to determine whether a Troubleshooting Plan is LOW or HIGH risk is __(1)__.
- 2) the LOWEST level of operations approval for a High Risk Troubleshooting Action Plan is the __(2)__ Manager.
Which ONE of the following completes the statements above?
A. 1. Shift Manager
- 2. OPS B. 1. Shift Manager
- 2. Shift C. 1. Unit/WCC SRO
- 2. Shift Monday, March 16, 2020 Page 200 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 97 D General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible since Troubleshooting actions are unexpected and have not been through the normal work planning review and approval process.
Second part is incorrect. Plausible since the OPS Manager approves Guidelines for Identifying Infrequently Performed Tests or Evolutions (IPTE).
Answer B Discussion Incorrect. First part is incorrect. Plausible since Troubleshooting actions are unexpected and have not been through the normal work planning review and approval process. Second part is correct.
Answer C Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since the OPS Manager approves Guidelines for Identifying Infrequently Performed Tests or Evolutions (IPTE).
Answer D Discussion CORRECT. The position designated to determine whether a Troubleshooting Plan is LOW or HIGH Risk is a UNIT/WCC SRO. Shift Manager approval is required for a High Risk Troubleshooting Action Plan.
Basis for meeting the KA Question requires knowledge of who determines if a Troubleshooting Plan is High risk and the approval level required for a High Risk Troubleshooting Plan.
Basis for Hi Cog Basis for SRO only Determining if a Troubleshooting Plan is high or low risk and the approval of a high risk Troubleshooting plan are both SRO level tasks.
Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided IP/0/A/0100/001 Rev 43 GEN2.2 2.2.20 - GENERIC - Equipment Control Equipment Control Knowledge of the process for managing troubleshooting activities. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 201 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.3 2.3.15 - GENERIC - Radiation Control QUESTION 98 A Radiation Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9)
Given the following Unit 3 conditions:
Fuel offload in progress A fuel cask has been dropped in the spent fuel pool causing fuel damage 3RIA-6 (Spent Fuel Pool Area Monitor) reaches the High Alarm setpoint
- 1) 3RIA-6 __(1)__ sound a local alarm.
- 2) The HIGHEST classification for this event is an __(2)__.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED DO NOT USE EMERGENCY COORDINATOR JUDGEMENT A. 1. does
- 2. Alert B. 1. does
- 2. Unusual Event C. 1. does NOT
- 2. Alert D. 1. does NOT
- 2. Unusual Event Monday, March 16, 2020 Page 202 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 98 A General Discussion Answer A Discussion CORRECT: 1st part is correct. A local alarm does go off when 3RIA-6 reaches the High Alarm setpoint.
2nd part is correct. This event will be classified as an Alert by the Abnormal Rad Levels RA2.2.
Answer B Discussion Incorrect: 1st part is correct. A local alarm does go off when 3RIA-6 reaches the High Alarm setpoint.
2nd part is incorrect because this event will be classified as an Alert. It is plausible because RIA-6 along with lowering water level meets the criteria for an Unusual Event.
Answer C Discussion Incorrect: 1st part is incorrect because a local alarm will actuate. It is plausible because RIA-41, Spent Fuel Pool Building Gas will NOT provide a local alarm.
2nd part is correct. This event will be classified as an Alert by the Abnormal Rad Levels RA2.2.
Answer D Discussion Incorrect: 1st part is incorrect because a local alarm will actuate. It is plausible because RIA-41, Spent Fuel Pool Building Gas will NOT provide a local alarm.
2nd part is incorrect because this event will be classified as an Alert. It is plausible because RIA-6 along with lowering water level meets the criteria for an Unusual Event.
Basis for meeting the KA Question requires the knowledge of Radiation monitoring systems including which RIAs provide local alarms. KA is met at the SRO level because it requires knowledge of the consequences of the radiation monitor system being in High Alarm (which is what requires the Alert classification).
Basis for Hi Cog Basis for SRO only Question requires the applicant to evaluate plant conditions and make emergency classifications based on their evaluation. Classification is an SRO only task. Classification is based on RIA-6 being in High alarm which ties this to the KA at the SRO level.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 48 Q97 Development References Student References Provided ILT 48 Q97 CSD-EP-ONS-0101-02 Rev 000 Wallcharts RAD-RIA Obj. 8 CSD-EP-ONS-0101-02 Rev 000 Wallcharts GEN2.3 2.3.15 - GENERIC - Radiation Control Radiation Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9)
Remarks/Status Monday, March 16, 2020 Page 203 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.4 2.4.11 - GENERIC - Emergency Procedures / Plan QUESTION 99 B Emergency Procedures / Plan Knowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)
Give the following Unit 3 conditions:
Initial conditions:
Reactor power = 100%
Fuel movement in Unit 3 Spent Fuel Pool Current conditions:
Unit 3 Spent Fuel Pool is damaged Estimated rate of SFP inventory loss is 600 gpm AP/3/A/1700/035 (Loss of SFP Cooling and/or Level) in progress
- 1) In accordance with AP/35, the use of lake water __(1)__ required to mitigate this event.
- 2) IF the use of lake water is required, it must be applied to the SFP within a MAXIMUM of__(2)__ hours.
Which ONE of the following completes the statements above?
A. 1. is
- 2. four B. 1. is
- 2. two C. 1. is NOT
- 2. four D. 1. is NOT
- 2. two Monday, March 16, 2020 Page 204 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 99 B General Discussion Answer A Discussion Incorrect. First part is correct. Second part is plausible because 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is a common time limit to complete actions.
Answer B Discussion CORRECT. With the SFP damaged and leakage > 500 gpm, lake water will be put on/in the SFP IAW AP/35. AP/35 states that the water must be applied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Answer C Discussion Incorrect. First part is incorrect. Plausible because it would be correct if leak rate were < 500 gpm. Second part is incorrect. Plausible because 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is a common time limit to complete actions.
Answer D Discussion Incorrect. First part is incorrect. Plausible because it would be correct if leak rate were < 500 gpm. Second part is correct.
Basis for meeting the KA Requires detailed knowledge of abnormal condition procedures (AP/35).
Basis for Hi Cog Basis for SRO only Requires detailed knowledge of AP/35. Requires knowledge of when to implement attachments and appendices (Enclosure 5.6), including how to coordinate these items with procedure steps.
Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT 43 Q84 Development References Student References Provided ILT 43 Q84 EAP-AP/35 AP/1-2/A/1700/035 GEN2.4 2.4.11 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)
Remarks/Status Monday, March 16, 2020 Page 205 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination GEN2.4 2.4.44 - GENERIC - Emergency Procedures / Plan QUESTION 100 C Emergency Procedures / Plan Knowledge of emergency plan protective action recommendations. (CFR: 41.10 / 41.12 / 43.5 / 45.11)
Given the following conditions:
A General Emergency has been declared The TSC, OSC, and EOF have NOT been activated In accordance with AD-EP-ALL-0111 (Control Room Activation of the ERO)
(1) The SM/Emergency Coordinator's responsibility of approving Protective Action Recommendations __(1)__ be delegated.
(2) Once activated, the EOF __(2)__ assume responsibility for notifications and Protective Action Recommendations.
Which ONE of the following completes the statements above?
A. 1. can
- 2. will B. 1. can
- 2. will NOT C. 1. can NOT
- 2. will D. 1. can NOT
- 2. will NOT Monday, March 16, 2020 Page 206 of 207
FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT20-1 ONS SRO NRC Examination QUESTION 100 C General Discussion Answer A Discussion Incorrect. First part is incorrect. Plausible since other responsibilities in the procedure can be delegated such as announcements, notifications, activation of ERONS and the procedure that was just superseded, RP/0/A/1000/002 (Control Room Emergency Coordinator Procedure), stated that all procedure steps and attachments in the procedure could be delegated unless otherwise specified.
Second part is correct.
Answer B Discussion Incorrect. First part is incorrect. Plausible since other responsibilities in the procedure can be delegated such as announcements, notifications, activation of ERONS and the procedure that was just superseded, RP/0/A/1000/002 (Control Room Emergency Coordinator Procedure), stated that all procedure steps and attachments in the procedure could be delegated unless otherwise specified.
Second part is incorrect. Plausible since the TSC, once the EOF is activated, will retain responsibility of evaluating, classifying, and declaring emergencies.
Answer C Discussion CORRECT. First part is correct. The responsibility of making Protective Action Recommendations can NOT be delegated.
Second part is correct. The EOF, once activated, assumes responsibility for notifications and protective Action Recommendations.
Answer D Discussion Incorrect. First part is correct.
Second part is incorrect. Plausible since the TSC, once the EOF is activated, will retain responsibility of evaluating, classifying, and declaring emergencies.
Basis for meeting the KA Question requires knowledge of SRO responsibilities for making protective action recommendations and notifications during implementation of the Emergency Plan.
Basis for Hi Cog Basis for SRO only Requires knowledge of the Emergency Plan and duties of the Emergency Coordinator and EOF, which are SRO tasks.
Job Level Cognitive Level QuestionType Question Source SRO Memory BANK Bank Question 7097 Development References Student References Provided CNS 2010 NRC Q100 EAP-SEP Obj 10 AD-EP-ALL-0111 Rev 0 GEN2.4 2.4.44 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of emergency plan protective action recommendations. (CFR: 41.10 / 41.12 / 43.5 / 45.11)
Remarks/Status Monday, March 16, 2020 Page 207 of 207
Appendix D Scenario Outline Form ES D-1 ILT 20-1 NRC Exam Facility: Oconee Scenario No.: 1 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________ SRO
________________________ ________________________ OATC
________________________ ________________________ BOP Initial Conditions:
- Reactor Power = 100%
Turnover:
- SASS is in manual for calibration
- AMSAC/DSS is bypassed for calibration
- CT-5 is OOS for maintenance
- OP/1/A/1106/002B Encl 4.13 in progress to restore 1B FWPT from Handjack Event Malfunction Event Event Type* Description No. No.
0a Override CT-5 OOS 0b Override AMSAC/DSS Bypassed 0c Override SASS in Manual 1 N: BOP, SRO Restore 1B FWPT Pump From Handjack 2 MPS090 C: OATC, SRO 1HP-120 Fails Closed 3 MCS004 I: OATC, SRO Controlling NR Tave Fails High 4 Override C: BOP, SRO 1B FWPT Low Oil Level 5 R: SRO, OATC (TS) Manual Power Reduction 6 Override C: BOP, SRO (TS) Recurring High Vibration on 1A RBCU 7 MEL170 SRO (TS) CT-1 Lockout MEL090 Switchyard Isolate 8 MEL180 M: ALL
- KHU-2 Emergency Lockout (CT-2)
Override
- TD EFDW Pump fails to start in Auto (CT-1)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam SCENARIO 1 EVENT
SUMMARY
Event 1: When the crew takes the shift, the SRO will direct the BOP to restore 1B FWPT from Handjack. Once proper operation of the FDW Pump Motor Gear Unit is verified, the 1B FWPT will be placed in automatic.
Event 2: 1HP-120 will fail closed which will cause RCS makeup to be lost. Pressurizer level will begin to decrease and Letdown Storage Tank level will begin to increase. Once the crew responds to the event and takes action to stabilize RCS makeup and letdown, 1HP-120 will be repaired and the crew will place the valve back in automatic and restore normal operation.
Event 3: Controlling Narrow Range Tave will fail high. FDW flow will increase and Control Rods will insert in an attempt to restore normal parameters. Once alarms are received, the crew will perform Plant Transient Response to stabilize the plant. The OATC will decrease Feedwater flow and the BOP will insert Control Rods, if needed, to restore the heat balance. Once the plant is stable, the SRO will enter AP/1/A/1700/028 (ICS Instrument Failures) and ensure the appropriate ICS stations are in manual and the BOP will perform an instrument surveillance for the failed instrument.
Event 4: The 1B FWPT low oil level Statalarm (1SA-8/B-6) will actuate. The CRS will initiate AP/1/A/1700/029 to shut down the 1B FWPT. The BOP will start the U1 FDWP Aux Oil Pumps and the FDWP Seal Injection Pumps prior to securing the 1B FWPT. The OATC will perform a manual power reduction to 65% to allow the BOP to secure the 1B FWPT.
Event 5: The OATC will perform a Power Reduction with the Diamond and Feedwater Masters in HAND. The power reduction will continue until < 65% to allow for securing the 1B FWPT.
Event 6: OAC alarm O1D1361 (RBCU Fan 1A Vib) will alarm and the BOP will refer to the OAC alarm response. The first time the alarm comes in, it will be reset using the OAC alarm response guidance. After the first alarm is reset, it will alarm again in 3 minutes. This time the alarm will not reset and the BOP must secure the 1A RBCU. The SRO will declare the 1A RBCU inoperable and enter TS 3.6.5 Required Actions.
Event 7: The CT-1 Transformer (Startup Transformer) will lockout causing PCB-17 and PCB-18 to trip open. This will require the SRO to enter TS 3.8.1.
Event 8: A Switchyard Isolation will occur and seconds later the Reactor will trip causing a Blackout.
The SRO will enter the Blackout Tab of the EOP. The Turbine Driven Emergency Feedwater Pump (TD EFDWP) will not automatically start which will require an operator to manually start the pump to restore heat removal from the core. Power will be restored in accordance with EOP Enclosure 5.38 (Restoration of Power) from Keowee Hydro Unit 1.
Page 2 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 1 Page 1 of 2 Event
Description:
Restore 1B FWPT From Handjack (N: BOP, SRO)
Time Position Applicants Actions or Behavior OP/1/A/1106/002 B Encl 4.13 Crew response:
SRO directs the BOP to restore 1B FWPT from Handjack per OP/1/A/1106/002 B Enclosure 4.13 BOP/SRO OP/1/A/1106/002 B Encl 4.13 (Taking 1B FDWPT Off Handjack) rev 40 NOTE: If both FDWPT(s) are in HAND changes in FDW valve P can cause CTP to change 2.1 IF in Mode 1 OR Mode 2, perform the following:
2.1.1 WHILE enclosure is in progress monitor the following indications:
- Appropriate ranged NIs
- Neutron error
- RCS Loop T (curve for "Loop T Vs Reactor Power" is in PT/1/A/0600/001)
- FDW Flow (curve for "Expected Feedwater Flow Per Header Vs Reactor Power" is in OP/0/A/1108/001) 2.2 Remove "T/O SHEET" CR tag from 1B MAIN FDW PUMP (ICS) station 2.3 Run 1B MAIN FDW PUMP (ICS) station to "HSS" (high speed stop)
NOTE: Operator should locally verify Motor Gear Unit moves smoothly from low speed stop and back to high speed stop 2.4 Perform the following:
2.4.1 Establish communication with Operator at 1B FDWPT 2.4.2 Run 1B MAIN FDW PUMP (ICS) to low speed stop 2.4.3 Run 1B MAIN FDW PUMP (ICS) to high speed stop
( 1/8" from hard stop) 2.4.4 Verify Motor Gear Unit operated smoothly through entire operation Booth Cue: When asked, state that the MGU operated smoothly through the entire operation.
2.5 Turn 1B FDWP HANDJACK switch to "OFF" This event is complete when the 1B FWPT is placed in Auto (Step 2.15), or as directed by the Lead Examiner.
Page 3 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 1 Page 2 of 2 Event
Description:
Restore 1B FWPT From Handjack (N: BOP, SRO)
Time Position Applicants Actions or Behavior OP/1/A/1106/002 B Encl 4.13 Crew response:
OP/1/A/1106/002 B Encl 4.13 BOP/SRO NOTE: Changes in FDW valve P will cause swings in CTP. Decreases in FDW valve P will cause CTP to decrease 2.6 IF Unit 1 is in Mode 1 or 2 AND both FDWPT ICS stations are in "HAND" (N/A)
NOTE:
- Motor Gear Unit control indicated by FDWPT speed and/or suction flow decreasing
- Two successful decreases verifies control with Motor Gear Unit 2.7 2.7 Decrease 1B MAIN FDW PUMP (ICS) until 1B FDWPT controlled by 1B MAIN FDW PUMP (ICS) station 2.8 Increase 1B FDWP Motor Speed Changer 2.9 Verify 1B FDWPT speed does NOT increase 2.10 Position 1B FDWP MOTOR SPEED CHANGER to 'FR' under "RAISE" until 1B FDWP MOTOR SPEED CHANGER is at "HSS" 2.11 After 1B FDWP MOTOR SPEED CHANGER reaches "HSS", hold 1B FDWP MOTOR SPEED CHANGER switch in 'FR' for 3 to 5 seconds to make all contacts 2.12 IF Unit 1 is in Mode 3: (N/A) 2.13 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT shutdown: (N/A)
NOTE: Changes in FDW valve P will cause swings in CTP. Decreases in FDW valve P will cause CTP to decrease 2.14 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT operating but NOT in auto: (N/A) 2.15 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT in auto:
2.15.1 Verify 1A MAIN FDW PUMP (ICS) in "AUTO" 2.15.2 Place 1B MAIN FDW PUMP (ICS) in "AUTO" 2.15.3 Verify ICS adjusts 1B FDWPT speed to balance suction flow 2.16 IF required, remove Turnover Sheet note for control of 1B FDWPT with Motor Speed Changer This event is complete when the 1B FWPT is placed in Auto (Step 2.15), or as directed by the Lead Examiner.
Page 4 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 2 Page 1 of 4 Event
Description:
1HP-120 Fails Closed (C: OATC, SRO)
Time Position Applicants Actions or Behavior Booth Cue: When directed by the Lead Examiner, call as the WCC SRO and request Battery 1CA voltage located on 1EB6. If asked, I&E needs the reading for data trending.
Plant Response:
- PZR level begins to decrease
- LDST level begins to increase
- Valve position demand for 1HP-120 will increase to the 100% demand value and valve position indication will indicate closed (green light)
- 1SA-02/ B-1 (HP LETDOWN TANK LEVEL HIGH/LOW) will illuminate after several minutes SRO Crew Response:
Examiner Note: If the 1HP-120 failure is recognized before the LDST Statalarm actuates, the SRO will make a direct entry into AP/14 (next page). Otherwise the crew may perform the ARG and OP below and enter AP/14 when the SRO determines the entry conditions are met.
BOP ARG 1SA-02/B-1 The crew may refer to ARG 1SA-02/B-1 (HP LETDOWN TANK LEVEL HIGH/LOW) and perform the required actions. rev 35 3.1 Instrument Failed:
3.1.1 Compare alternate channels to verify alarm validity:
- O1A1042 LDST LEVEL 1
- O1A1043 LDST LEVEL 2 3.2 Verify LDST pressure does not exceed LDST level/pressure operability requirement per OP/0/A/1108/001 (Curves and General Information).
3.3 IF High Level alarm is received:
3.3.1 Bleed as required by OP/1/A/1103/004 (Soluble Poison Concentration Control).
This event is complete when Step 4.457 of AP/14 is complete, or as directed by the Lead Examiner.
Page 5 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-2 Scenario No.: 1 Event No.: 2 Page 2 of 4 Event
Description:
1HP-120 Fails Closed (C: OATC, SRO)
Time Position Applicants Actions or Behavior OP/1/A/1103/004 Crew Response:
Examiner Note: The crew may perform Enclosure 4.8 as necessary to reduce inventory.
OP/1/A/1103/004 Enclosure 4.8 (Reducing RCS Inventory) rev 108 2.1 Verify HPI System operating 2.2 Ensure open 1CS-26 (LETDOWN TO RC BHUT) 2.3 Ensure open 1CS-41 (1A RC BHUT INLET) 2.4 Position 1HP-14 (LDST BYPASS) to BLEED 2.5 WHEN desired LDST level achieved, position 1HP-14 to NORMAL Examiner Note: The crew may initiate EOP Encl 5.5 for RCS inventory control due LDST level increase (page 41)
AP/1/A/1700/014 AP/1/A/1700/014 (Loss of Normal Makeup and/or RCP Seal Injection) rev 20 3.1 Verify HPI pump cavitation is indicated:
OATC/SRO
- Motor amps low or cycling
- Discharge pressure low or cycling RNO: GO TO Step 3.3 3.2 Stop affected HPI pump(s).
3.3 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:
A. Trip the Rx B. Stop all RCPs C. Initiate AP/25 (SSF EOP) 4.1 Announce AP entry using PA System 4.2 Verify either of the following is running:
__ 1A HPI Pump
__ 1B HPI Pump This event is complete when Step 4.457 of AP/14 is complete, or as directed by the Lead Examiner.
Page 6 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 2 Page 3 of 4 Event
Description:
1HP-120 Fails Closed (C: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/014 Crew Response:
AP/1/A/1700/014 4.3 Verify leak indicated by any of the following:
OATC/SRO
- Abnormal drop in LDST level
- 1RIA-32 (AUX BLDG GAS)
- 1RIA-45 (NORM VENT GAS)
- RB RIAs in alarm
- Abnormal rise in RBNS level
- Abnormal rise in LAWT or HAWT level RNO: 1. IF an HPI Pump is running, THEN GO TO Step 4.6
- 2. GO TO Step 4.458 4.6 Verify seal injection flow normal (~ 32 gpm) 4.7 Verify 1HP-120 operable in AUTO RNO: 1. Place 1HP-120 in HAND and attempt to maintain Pzr level in desired band (will NOT operate)
- 2. IF Pzr level CANNOT be maintained with 1HP-120, THEN GO TO Step 4.447.
4.447 Perform the following as necessary to maintain Pzr level > 200
- Close 1HP-6
- Throttle 1HP-7
(Unit 1 E Pen Rm. 2 SE 1HP-120) 4.449 WHEN 1HP-120 is repaired, THEN locally open 1HP-121 (RC Volume Control Outlet)
(Unit 1 E Pen Rm. 2 SE 1HP-120)
Examiner Note: After Step 4.449 and Lead Examiners direction, 1HP-120 will be repaired using time compression.
Booth Cue : When directed by Lead Examiner, Activate Timer 2A and call the crew and report that using time compression 1HP-120 has been repaired This event is complete when Step 4.457 of AP/14 is complete, or as directed by the Lead Examiner.
Page 7 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 2 Page 4 of 4 Event
Description:
1HP-120 Fails Closed (C: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/014 Crew Response:
OATC/SRO 4.450 Slowly re-establish flow through 1HP-120.
4.451 Place 1HP-120 in AUTO 4.452 Close 1HP-26 4.453 Verify 1HP-122 (RC VOLUME CONTROL BYPASS) throttled RNO: GO TO Step 4.455 Examiner Note: 1HP-6 may be open or closed based on the actions taken in Step 4.447.
4.455 Verify 1HP-6 open RNO: 1. Throttle 1HP-7 for 20 gpm letdown flow
- 2. Open 1HP-6 4.456 Adjust 1HP-7 for desired letdown 4.457 THEN EXIT this procedure This event is complete when Step 4.457 of AP/14 is complete, or as directed by the Lead Examiner.
Page 8 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 3 Page 1 of 4 Event
Description:
Controlling NR Tave Fails High (I: OATC, SRO)
Time Position Applicants Actions or Behavior Plant response:
- Controlling NR Tave digital display reads 587F
- Controlling Tave Chessell display reads 587F
- Control Rods will insert and FDW flow will increase
- RCS pressure will decrease Examiner Note: If Reactor power decreases below 85% during this event, the SRO will enter Tech Spec 3.10.1 Conditions A-E which all have a 7 day completion time (SSF OOS).
Crew response:
When the Statalarms are received, the crew should perform Plant Transient Response (PTR) to stabilize the plant OATC The OATC should:
- Communicate to the CRS the initial alarm (if applicable) followed by reactor power level and direction
- Place the appropriate ICS stations in manual (Diamond and both FDW Masters in this case) in manual if any of the following occur:
o NI power increasing above the pre-transient power level o Failed instrument is diagnosed o Invalid input exists and the CRS directs the ICS be placed in manual
- Remain focused on reactor power level and FDW response during the transient BOP Examiner Note: The OATC will have to reduce FDW in order to stabilize power below the pre-transient level.
The BOP should:
- Monitor plant response and verify operating limits NOT exceeded
- If ICS is placed in Manual, remain focused on RCS pressure, SG outlet SRO pressure and RCS inventory The SRO should:
- Refer to AP/28 (ICS Instrument Failures) (next page)
- Ensure Maintenance (FIN-24/SPOC) is contacted to repair the failed instrument This event is complete when the SRO reaches Step 6 of Section 4A or as directed by the Lead Examiner.
Page 9 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 3 Page 2 of 4 Event
Description:
Controlling NR Tave Fails High (I: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:
AP/1/A/1700/028 (ICS Instrument Failures) rev 24 4.1 Provide control bands as required (AD-OP-ONS-0002 Attachment 17)
OATC/SRO Attachment 17: rev 01
- 1. Plant Conditions Stable or TPB Pre-transient Conditions 1.1 The following bands are to be established during manual control of plant conditions (as needed) but may be adjusted by the CRS if required 1.1.1 NI Power +/- 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power - 1%
1.1.2 Current Tave +/- 2°F 1.1.3 Current SG Outlet Pressure +/- 10 PSIG (N/A) 1.1.4 Delta Tc 0oF +/- 2°F 4.2 Initiate notification of the following:
__ SM to reference the following:
- OMP 1-14 (Notifications)
__ STA 4.3 Verify a power transient 5% has occurred RNO: GO TO Step 4.5.
4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:
- OAC alarm video
- OAC display points
- Control Board indications
- Maintenance assistance, as needed This event is complete when the SRO reaches Step 6 of Section 4A or as directed by the Lead Examiner.
Page 10 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 3 Page 3 of 4 Event
Description:
Controlling NR Tave Fails High (I: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:
AP/1/A/1700/028 (ICS Instrument Failures)
OATC/SRO 4.6 GO TO the applicable section per the following table:
Section Failure 4A RCS Temperature AP/1/A/1700/028 Section 4A AP/1/A/1700/028 Section 4A (RCS Temperature Failure)
NOTE
- If Tave instrument circuit failed high, the following may have occurred depending on initial ICS station status:
- Unit to TRACK due to Rx Cross Limits
- Control Rod insertion
- Feedwater flow rising
- If Tave instrument circuit failed low, the following may have occurred depending on initial ICS station status:
- Unit to TRACK due to Rx Cross Limits
- Control Rod withdrawal
- Feedwater flow lowers
- Feedwater re-ratio
- 1. Ensure the following in HAND:
__ 1A FDW MASTER
__ 1B FDW MASTER
- 2. Ensure DIAMOND in MANUAL This event is complete when the SRO reaches Step 6 of Section 4A or as directed by the Lead Examiner.
Page 11 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 3 Page 4 of 4 Event
Description:
Controlling NR Tave Fails High (I: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/028 Section 4A Crew response:
- 3. Notify Maintenance to perform the following:
OATC/SRO
__ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).
__ Investigate and repair the failed RCS temperature instrumentation
- 4. PERFORM an instrumentation surveillance using applicable table in Encl.
5.2 (ICS Instrument Surveillances) for the failed instrument Examiner Note: This step will require the BOP to refer to Table 1 (RCS Temperature) of Enclosure 5.2 (next page) and determine if the surveillance for SR 3.4.1.2 can be met as it is written with the failed temperature instrument.
Based on plant response to the failure the BOP will determine either:
- The surveillance is not required to be met due to plant conditions (not steady state)
- The surveillance can be met as written
- The surveillance can NOT be met as written This information will be reported to the SRO when asked in Step 5.
- 5. Verify instrumentation surveillance in Encl. 5.2 (ICS Instrument Surveillances) was performed satisfactorily as written.
RNO: Initiate a Surveillance Evaluation in accordance with PT/1/A/0600/001 and OP/1/A/1105/014 (if needed)
- 6. WHEN notified by Maintenance that a valid RCS Tave and Delta Tc input have been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl.
(Placing ICS Stations To Auto)
This event is complete when the SRO reaches Step 6 of Section 4A or as directed by the Lead Examiner.
Page 12 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Page 13 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 4 Page 1 of 5 Event
Description:
1B FWPT Low Oil Level (C: BOP/SRO)
Time Position Applicants Actions or Behavior Plant response:
- Statalarm 1SA-8/B-6 FWPT B OIL LEVEL HIGH/LOW Booth Cue: If crew initiates AP/1/A/1700/052 Turbine Building Oil Leak/Fire, then call as the SM and notify the crew that U2 will perform the AP.
Crew response:
Refer to the Alarm Response Guide for LOW Level:
3.2.1 Manually trip 1B FWPT if oil level is 7 below normal Limits and Precautions of OP/1/A/1106/002 3.2.2 IF oil purifier is in operation, check for proper operation
- Refer to OP/1/A/1106/024 3.2.3 Check for leaking tank or oil lines. Bring oil level back to normal by adding oil.
3.2.4 IF tank OR oil lines are found to be leaking AND they CANNOT be repaired on line, reduce reactor power as necessary per OP/1/A/1102/004 (Operation at Power) 3.2.5 IF Loss of oil occurs, Open TBS Pump Breakers and contain oil due to Haz Mat concerns.
3.2.6 Shut down 1B FWPT per OP/1/A/1106/002 B (FDWPT Operation) and SRO/BOP repair leaks The SRO will enter AP/1/A/1700/029 to reduce Reactor power 65% to secure the 1B FWPT (next page)
Booth Cue: If an AO is sent to look at the 1B FWPT, report as an AO, that the oil level is 4 below normal and slowly lowering. The AO can see oil in the FWPT trenches.
Booth Cue: If Component Engineer contacted, recommend that the 1B FWPT be removed from service.
Booth Cue: If SM contacted, recommend reducing power with AP/1/A/1700/029 and then remove 1B FWPT from service.
SRO should direct BOP to secure the 1B FWPT once Reactor power has been reduced to 65%. Maintenance should be notified to investigate and repair the oil leak.
Note: The SRO may refer to RP/0/A/1000/017 (Spill Response)
Booth Cue: If asked, Unit 2 will implement RP/0/A/1000/017 (Spill Response)
Booth Cue: If asked, Unit 2 will open the TBS Pump breakers.
Booth Cue: If asked about the oil purifier, notify the crew that the purifier is on the 1A FWPT This event is complete when the 1B FWPT has been secured or when directed by the Lead Examiner.
Page 14 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 4 Page 2 of 5 Event
Description:
1B FWPT Low Oil Level (C: BOP/SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:
AP/1/A/1700/029 (Rapid Unit Shutdown) rev 13 BOP/SRO 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown)
(page 17) 4.2 Announce AP entry using the PA system 4.3 IAAT both of the following apply:
__ It is desired to stop power decrease
__ CTP > 18 %
THEN perform Steps 4.4 - 4.7 RNO: GO TO Step 4.8 4.8 Verify ICS in AUTO RNO: Initiate manual power reduction to desired power level Examiner Note: The SRO will give the OATC operating bands on Reactor OATC/SRO Power, Reduction Rate, Tave, and delta Tc for the power reduction. The OATC will reduce power by first lowering FDW and then inserting control rods as necessary.
GO TO Step 4.10 4.10 Verify both Main FDW pumps running NOTE
- 1B Main FDW Pump is the preferred pump to be shutdown first
- To lower 1B Main FDW Pump suction flow, bias is adjusted counter-clockwise
- To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise 4.11 Adjust bias for first Main FDW pump desired to be shutdown until suction flow is 1 x 106 lbm/hr less than remaining Main FDW pump suction flow 4.12 WHEN core thermal power is < 65% FP, THEN continue 4.13 IAAT both Main FDW pumps running, AND both of the following exist:
__ 1B Main FDW Pump is first pump to be shut down
__ Any of the following alarms actuate and remain in alarm:
- FWP B FLOW MINIMUM (1SA-16/A-3)
- FWP B FLOW BELOW MIN (1SA-16/A-4)
THEN trip 1B Main FDW Pump.
Booth Cue: If asked as an AO for 1B FWPT Oil Level, report level is 5 inches below normal and slowly lowering.
This event is complete when the 1B FWPT has been secured or when directed by the Lead Examiner.
Page 15 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 4 Page 3 of 5 Event
Description:
1B FWPT Low Oil Level (C: BOP/SRO)
Time Position Applicants Actions or Behavior OP/1/A/1106/002 B Enc 4.9 Crew response:
Examiner Note: Once Reactor Power < 65%, the crew may use SRO OP/1/A/1106/002 B Enc. 4.9 to secure the 1B FWPT, Rev 40 or the CRS may direct the RO to trip the 1B FWPT per guidance in AD-OP-ALL-1000 (Conduct of perations).
1.1 CTP DEMAND <65% power.
1.2 Review Limits and Precautions.
NOTE: Stopping 1B FDWPT first on Unit Shutdown preferred due to FDWPT discharge pressure trip setpoints.
2.1 IF this is first FDWPT to be shutdown:
___2.1.1 Verify 1SA-5/E-1 (FWPT / RX TRIP ALERT) NOT in alarm.
2.1.2 Position the following:
___A. Ensure 1FDW-53 (1A FDWP RECIRC CONTROL) in "MANUAL"
___B. Ensure Closed 1FDW-53 (1A FDWP RECIRC CONTROL)
___C. Ensure 1FDW-65 (1B FDWP RECIRC CONTROL) in "MANUAL"
___D. Ensure Closed 1FDW-65 (1B FDWP RECIRC CONTROL) 2.2 IF in FDW Heatup, perform the following:
___ 2.2.1 Ensure 1FDW-65 (1B FDWP RECIRC CONTROL) in "MANUAL".
___ Ensure Closed 1FDW-65 (1B FDWP RECIRC CONTROL)
___2.2.2 Ensure 1FDW-53 (1A FDWP RECIRC CONTROL) in MANUAL.
___ Throttle 1FDW-53 (1A FDWP RECIRC CONTROL) to establish
>2300 gpm.
2.3 Ensure running 1B FDWP AUXILIARY OIL PUMP 2.4 IF 1A FDWP is NOT isolated for maintenance, start 1A FDWP AUXILIARY OIL PUMP.
2.5 Place 1B MAIN FDW PUMP (ICS) in HAND.
2.6 Slowly run 1B MAIN FDW PUMP demand signal to minimum.
2.7 IF required, verify 1A FDWPT picks up load by observing FDWPT suction flow instruments.
2.8 Immediately trip 1B FDWPT from FW TURB 1B TRIP/RESET switch.
___ Verify closed 1B FDWPT HP stop valve
___ Verify closed 1B FDWPT LP stop valve This event is complete when the 1B FWPT has been secured or when directed by the Lead Examiner.
Page 16 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 4 Page 4 of 5 Event
Description:
1B FWPT Low Oil Level (C: BOP/SRO)
Time Position Applicants Actions or Behavior 2.9 WHEN 1B FDWPT reaches 0 speed:
___ Ensure 1B FDWP TURNING GEAR MOTOR starts BOP/SRO
___ Ensure 1B FDWP TURNING GEAR engages.
AP/1/A/1700/029 Enclosure 5.1 Crew response:
AP/29 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)
- 2. Start the following pumps:
__ 1A FDWP SEAL INJECTION PUMP
__ 1A FDWP AUXILIARY OIL PUMP
__ 1B FDWP AUXILIARY OIL PUMP
__ 1B FDWP SEAL INJECTION PUMP
- 3. WHEN CTP is 80%, THEN continue
- 4. Stop 1E1 HTR DRN PUMP
- 5. Place 1HD-254 switch to OPEN
- 6. Stop 1E2 HTR DRN PUMP
- 7. Place 1HD-276 switch to OPEN
- 8. Verify Turbine-Generator shutdown is required RNO: GO TO Step 20. (next page)
- 9. Place the following transfer switches to MAN:
__ 1TA AUTO/MAN
__ 1TB AUTO/MAN
- 10. Close 1TA SU 6.9 KV FDR
- 11. Verify 1TA NORMAL 6.9 KV FDR opens
- 12. Close 1TB SU 6.9 KV FDR
- 13. Verify 1TB NORMAL 6.9 KV FDR opens This event is complete when the 1B FWPT has been secured or when directed by the Lead Examiner.
Page 17 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 4 Page 5 of 5 Event
Description:
1B FWPT Low Oil Level (C: BOP/SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Enclosure 5.1 Crew response:
AP/29 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)
- 14. Place the following transfer switches to MAN:
__ MFB1 AUTO/MAN
__ MFB2 AUTO/MAN
- 15. Close E11 MFB1 STARTUP FDR
- 16. Verify N11 MFB1 NORMAL FDR opens
- 17. Close E21 MFB2 STARTUP FDR
- 18. Verify N21 MFB2 NORMAL FDR opens
- 19. Notify CR SRO that Unit auxiliaries have been transferred
- 20. IAAT 1SSH-9 is NOT closed, AND CTP is 75%, THEN throttle 1SSH-9 to Maintain Steam Seal Header pressure 2.5 - 4.5 psig
- 21. WHEN CTP 65%, THEN place the following in MANUAL and close:
__ 1FDW-53
__ 1FDW-65
- 22. IAAT load is 550 MWe, THEN perform Steps 23 - 24 Examiner Note: Once reactor power is < 65%, the CRS may direct the RO to trip the 1B FWPT for equipment protection, or he/she may direct securing the pump per OP/1/A/1106/002B (page 16). Either is acceptable.
Examiner Note: If Reactor power is reduced below 85% during this event, TS 3.10.1 will apply.
TS 3.10.1 STANDBY SHUTDOWN FACILITY Conditions A-E are applicable due to Reactor power being < 85% which makes the SSF inoperable Required Action: Restore SSF systems to OPERABLE status (7 days)
This event is complete when the 1B FWPT has been secured or when directed by the Lead Examiner.
Page 18 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 5 Page 1 of 1 Event
Description:
Manual Power Reduction (R: OATC, SRO) (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:
AP/1/A/1700/029 (Rapid Unit Shutdown) rev 13 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown)
(page 17) 4.2 Announce AP entry using the PA system 4.3 IAAT both of the following apply:
__ It is desired to stop power decrease
__ CTP > 18 %
THEN perform Steps 4.4 - 4.7 RNO: GO TO Step 4.8 4.8 Verify ICS in AUTO OATC/SRO RNO: Initiate manual power reduction to desired power level Examiner Note: The SRO will give the OATC operating bands on Reactor Power, Reduction Rate, Tave, and deltaTC for the power reduction. The OATC will reduce power by first lowering on FDW and then inserting control rods as necessary.
GO TO Step 4.10 4.10 Verify both Main FDW pumps running NOTE
- 1B Main FDW Pump is the preferred pump to be shutdown first
- To lower 1B Main FDW Pump suction flow, bias is adjusted counter-clockwise
- To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise 4.11 Adjust bias for first Main FDW pump desired to be shutdown until suction flow is 1 x 106 lbm/hr less than remaining Main FDW pump suction flow 4.12 WHEN core thermal power is < 65% FP, THEN continue 4.13 IAAT both Main FDW pumps running, AND both of the following exist:
__ 1B Main FDW Pump is first pump to be shut down
__ Any of the following alarms actuate and remain in alarm:
- FWP B FLOW MINIMUM (1SA-16/A-3)
- FWP B FLOW BELOW MIN (1SA-16/A-4)
THEN trip 1B Main FDW Pump.
BOOTH Cue: If asked as an AO for 1B FWPT Oil Level, report level is 5 inches below normal and slowly lowering.
This event is complete when the 1B FWPT has been secured or when directed by the Lead Examiner.
Page 19 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 6 Page 1 of 3 Event
Description:
Recurring Vibration on 1A RBCU (C: BOP, SRO) (TS)
Time Position Applicants Actions or Behavior Plant Response:
- OAC alarm O1D1361 (RBCU Fan 1A Vib)
Crew response:
- Refer to OAC ARG
- BOP will secure the 1A RBCU
- Contact engineering OAC Alarm O1D1361
- 1) Depress the RBCU OAC Vibration alarm reset pushbutton
- 2) If the alarm doesnt clear stop the RBCU
- 3) Notify Engineering for an evaluation Examiner Note: The crew may stop the 1A RBCU per the OAC alarm BOP response guide.
Examiner Note: There is a Limit & Precaution in OP/1104/015 that states if RBCU vibration alarms cannot be promptly cleared, immediately stop the affected RBCU.
Booth Cue: If the crew fails to start the 1B RBCU, contact the crew as the SM and request that the 1B RBCU be started in HIGH SPEED.
SRO should refer to TS 3.6.5 (page 22)
OP/1/A/1104/015 Enclosure 4.3 (RBCU Operation) rev 45
- 3. Stopping RBCU(s)
NOTE: When starting RBCUs or changing LPSW flows, RB pressure will change as RB temperature changes.
3.1 Verify RB pressure within limits of PT/1/A/0600/001 (Periodic Instrument Surveillance).
This event is complete when 1A RBCU is secured and 1B RBCU is started, or as directed by the Lead Examiner.
Page 20 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 6 Page 2 of 3 Event
Description:
Recurring Vibration on 1A RBCU (C: BOP, SRO) (TS)
Time Position Applicants Actions or Behavior OP/1/A/1104/015 Encl 4.3 Crew response:
3.2 Begin monitoring the following:
- RB pressure absolute pressure. (OAC Turn On 1RBPA).
- RB Temperature BOP NOTE: Stopping RBCUs can affect the following: RBCU bearing temperatures, RBCU vibration, RBNS level, 1RIA-47 level, RB pressure/temperature.
3.3 Place desired switch to OFF:
1A RBCU 1B RBCU 1C RBCU NOTE: When changing LPSW flows, RB pressure will change as RB temperature changes.
Each RBCU must have 550 gpm Inlet Flow or 750 gpm Outlet Flow to meet flow requirements of SLC 16.9.12.
3.4 Position valves as required for RB cooling:
1LPSW-18 (1A RBCU OUTLET) 1LPSW-21 (1B RBCU OUTLET) 1LPSW-24 (1C RBCU OUTLET)
- 4. Starting RBCUs NOTE: When starting RBCUs or changing LPSW flows, RB pressure will change as RB temperature changes.
4.1 Verify RB pressure within limits of PT/1/A/0600/001 (Periodic Instrument Surveillance).
4.2 Begin monitoring RB pressure absolute pressure (OAC Turn On 1RBPA).
4.3 IF personnel inside containment, announce over plant page that starting RBCU.
This event is complete when 1A RBCU is secured and 1B RBCU is started, or as directed by the Lead Examiner.
Page 21 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 6 Page 3 of 3 Event
Description:
Recurring Vibration on 1A RBCU (C: BOP, SRO) (TS)
Time Position Applicants Actions or Behavior OP/1/A/1104/015 Encl 4.3 Crew response:
NOTE: Starting RBCUs can affect the following: RBCU bearing temperatures, RBCU vibration, RBNS level, 1RIA-47 level, RB pressure/temperature.
BOP 4.4 Place desired switch to HIGH or LOW:
1A RBCU 1B RBCU 1C RBCU Examiner Note: The 1B RBCU should be placed in HIGH speed.
NOTE: When changing LPSW flows, RB pressure will change as RB temperature changes.
Each RBCU must have 550 gpm Inlet flow or 750 gpm Outlet Flow to meet flow requirements of SLC 16.9.12.
4.5 Position valves as required for RB cooling:
1LPSW-18 (1A RBCU OUTLET) 1LPSW-21 (1B RBCU OUTLET) 1LPSW-24 (1C RBCU OUTLET)
SRO should refer to TS 3.6.5 SRO TS 3.6.5 REACTOR BUILDING SPRAY AND COOLING TRAINS Condition B (7 days) Restore Reactor Building cooling train to OPERABLE status.
This event is complete when 1A RBCU is secured and 1B RBCU is started, or as directed by the Lead Examiner.
Page 22 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 7 Page 1 of 2 Event
Description:
CT-1 Lockout (SRO) (TS)
Time Position Applicants Actions or Behavior Plant response:
- 1SA-15/C-2 (EL SU SOURCE VOLT MONIT LOGIC UNDERVOLTAGE)
- SA-3/B-4 (Oconee White Startup Transformer CT1 Tie PCB 17)
- SA-3/C-4 (Startup Transformer CT1 PCB 18)
- CT-1 transformer will be de-energized
- PCB-17 and PCB-18 will trip open Crew response:
BOP The BOP will refer to Statalarm 1SA-15/C-2 Rev 06 3.1 IF the start-up source was carrying the unit load AND the start-up breakers tripped, verify that power is supplied from the standby source 3.2 Refer to EP/1/A/1800/001 (Emergency Operating Procedure) or AP/1/A/1700/011 (Recovery from Loss of Power) if required (N/A) 3.3 IF only one phase trips, perform the following: (N/A) 3.4 Refer to TS 3.8.1 3.5 Return to the normal (preferable) or start-up source of power as soon as conditions permit Examiner Note: If the crew trips the Reactor, Event 7 will auto actuate to initiate a Switchyard Isolation.
Booth Cue: If asked, U2 will perform the operability check of Keowee Hydro Unit.
Booth Cue: If the crew attempts to perform a KHU Operability Check, call as the SM and notify the crew that U2 will perform the Operability Check.
SRO Booth Cue: If asked, U2 will perform AP/0/A/1700/048 (Loss of Startup Transformer).
Booth Cue: If contacted as Transmission Dept. as to the reason for PCB-17 and 18 breaker trips, respond that investigation is in progress.
The SRO will refer to Tech Specs (next page)
This event is complete when the SRO has determined Tech Specs, or as directed by the Lead Examiner.
Page 23 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 7 Page 2 of 2 Event
Description:
CT-1 Lockout (SRO) (TS)
Time Position Applicants Actions or Behavior Crew response:
SRO The SRO will refer to Tech Specs TS 3.8.1 AC SOURCES - OPERATING Condition A (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) Perform SR 3.8.1.3 AND (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) Align the emergency startup bus to share another units startup transformer AND (36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />) Restore unit startup transformer to OPERABLE status and normal startup bus alignment OR (36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />) Designate one unit sharing the startup transformer to be shutdown This event is complete when the SRO has determined Tech Specs, or as directed by the Lead Examiner.
Page 24 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 1 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior Plant response:
- Switchyard Isolation occurs
- Main Turbine will trip causing a Reactor trip
- When the Reactor trips, a loss of power will occur due to KHU-2 lockout and CT-1 lockout Crew response:
- Crew may manually trip the reactor prior to reaching the RCS High Pressure setpoint
- SRO will direct the OATC to perform IMAs and the BOP to perform a symptom check IMMEDIATE MANUAL ACTIONS The SRO will direct the OATC to perform IMAs Rev 02 SRO 3.1 Depress REACTOR TRIP pushbutton OATC 3.2 Verify reactor power < 5% FP and lowering 3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed 3.5 Verify RCP seal injection available RNO: IF CC is unavailable, THEN immediately:
A. Stop all RCPs B. Notify CR SRO to initiate AP/25 SYMPTOM CHECK The SRO will direct the BOP to perform a Symptoms Check.
SRO Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear BOP Power Range NIs NOT decreasing Power Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation Rule 4, Initiation of HPI Forced Cooling of EFDW) (Inability to feed SGs and > 2300 psig, NDT limit reached, or PZR level > 375")
Uncontrolled Main steam line(s) Rule 5, Main Steam Line Break pressure decrease CSAE Off-gas alarms None (SGTR Tab is entered when Process monitor alarms (RIA-40, identified SG Tube Leakage > 25 gpm) 59,60),
Area monitor alarms (RIA-16/17)
This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 25 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 2 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior Crew response:
The SRO will direct the BOP to initiate AP/25 Examiner Cue: When the BOP attempts to proceed to the SSF, inform him/her that a Unit 2 RO will perform AP/25 actions The SRO will review the Subsequent Actions Tab Parallel Actions Page (page
- 42) which will require a transfer to the BO Tab.
BLACKOUT TAB Blackout Tab rev 05 The SRO will review the BO Tab Parallel Actions Page (page 41)
Examiner Note: When the Unit 2 CRS is notified to perform Unit 2 EOP Encl 5.42 (PSW Power and Pump Alignment), a booth instructor will enter the simulator to perform the enclosure. Performing this enclosure will have no effect on the outcome of the scenario.
Examiner Cue: If asked as Unit 2 to perform Parallel Actions Page steps for turning off lights and opening doors in the control room, respond that Unit 2 will perform the steps.
- 1. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (page 33)
- 2. Verify TDEFDWP feeding SGs
- 4. Verify two ROs available to perform Control Room actions
- 5. Ensure Encl 5.45 (PSW Feed and RCP Seals) in progress or complete
- 6. Notify one RO to perform Encl 5.38 (Restoration of Power) (page 35)
- 7. Verify any:
__ Any SG is being fed from Emergency FDW or PSW
__ SSF or PSW is available to feed SGs
- 8. Verify both:
__ Blackout exists on all three units
__ PSW Power NOT available RNO: GO TO Step 10 This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 26 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 3 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior BLACKOUT TAB Crew response:
- 10. Verify RCS temperature 550°F RNO: 1. Feed and steam available SGs, as necessary, to stabilize RCS P/T using one of the following:
__ TBVs
__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) to prepare to steam intact SGs
- 2. GO TO Step 13
- 11. Verify feeding SGs with TDEFDW pump
- 12. Feed available SGs as necessary to stabilize RCS P/T in bands prescribed by Rule 7 (SG Feed Control)
NOTE
- Feeding SGs with EFDW is desired above HPI Forced Cooling. If a feed source becomes available, step 13 should be performed prior to re-performing Rule 3
- 100 gpm could cause overcooling if adequate decay heat levels do NOT exist
- 13. IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 or another unit) becomes available, THEN perform Steps 14 - 18 RNO: GO TO Step 19 NOTE
- The EFW system operation is expected to last 2 - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during a three unit blackout without PSW power
- If battery power is lost and PSW power is not available, EFDW control will be lost
- 19. IAAT the SSF or PSW is available to feed SGs, AND EFDW from any source is insufficient to maintain stable RCS P/T, THEN perform one of the following:
__ Notify SSF operator that feeding SGs with SSF ASW is required (SSF CR x-2766)
__ Initiate Encl 5.45 (PSW Feed and RCP Seals) and feed SGs with PSW This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 27 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 4 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior BLACKOUT TAB Crew response:
- 20. IAAT power is restored to any of the following:
__ 1TC
__ 1TD
__ 1TE THEN GO TO Step 21
- 21. Ensure any SG is being fed or action is being taken per Step 13
- 22. Verify SSF activated
- 23. Communicate status of SG feed and seal injection to SSF operator using x-2766, radio, or plant page
- 24. Initiate AP/11 (Recovery from Loss of Power) (page 31)
- 25. GO TO Subsequent Actions tab (next page)
Examiner Note: The CRS may start over in the EOP when power is restored and re-perform IMAs and then transfer to Subsequent Actions. Either path is acceptable.
This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 28 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 5 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS TAB Crew response:
Subsequent Actions Tab rev 02 4.1 Verify all control rods in Groups 1 - 7 fully inserted 4.2 Verify Main FDW in operation 4.3 Verify either:
__ Main FDW overfeeding causing excessive temperature lowering
__ Main FDW underfeeding causing SG level lowering below setpoint RNO: GO TO Step 4.5 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8 RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:
__ TBVs
__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating 4.11 GO TO Step 4.14 4.14 Verify both are closed:
__ 1MS-17
__ 1MS-26 4.15 Verify ES is required RNO: 1. Initiate Encl 5.5 (Pzr and LDST Level Control) (page 43)
- 2. GO TO Step 4.17 4.17 Open:
__ PCB 20
__ PCB 21 This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 29 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 6 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS TAB Crew response:
Subsequent Actions Tab 4.18 Verify Generator Field Breaker open 4.19 Verify EXCITATION is OFF 4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure 90 psig 4.21 Verify ICS/NNI power available 4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized 4.23 Verify both SGs > 550 psig This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 30 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 7 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL))
Time Position Applicants Actions or Behavior AP/1/A/1700/011 Crew response:
AP/1/A/1700/011 (Recovery from Loss of Power) rev 59 4.1 Announce AP entry using OMP 1-18 placard 4.2 IAAT all exist:
__ 1KI energized
__ Pzr level > 80 [180 acc]
__ Pzr heaters are desired THEN ensure Pzr heaters in AUTO 4.3 Verify load shed of inverters was performed per Unit 1 EOP Encl (Load Shed of Inverters During SBO)
RNO: GO TO Step 4.9 4.9 Verify load shed has initiated as indicated by either of the following statalarms on:
__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)
__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.10 Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Channel (Channel 1 or 2) 4.11 Verify breakers closed:
__ 1TC INCOMING FDR BUS 1
__ 1TC INCOMING FDR BUS 2
__ 1TD INCOMING FDR BUS 1
__ 1TD INCOMING FDR BUS 2
__ 1TE INCOMING FDR BUS 1
__ 1TE INCOMING FDR BUS 2 4.12 Verify 1SA-15/E-6 (EL SWYD ISOLATION CONFIRMED CHNL A LOGIC) is OFF RNO: GO TO Step 4.15 4.15 Verify any Oconee unit receiving power form its normal source (1T, 2T, 3T)
RNO: GO TO Step 4.17 This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 31 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 8 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior AP/1/A/1700/011 Crew response:
AP/1/A/1700/011 (Recovery From Loss of Power) 4.17 Verify load shed was initiated as indicated by either of the following statalarms on:
__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)
__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.18 Verify ES has occurred RNO: GO TO Step 4.20 4.20 Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
- MFB UNDERVOLTAGE CHANNEL 1 RESET
- MFB UNDERVOLTAGE CHANNEL 2 RESET 4.21 Verify load shed signal reset as indicated by both of the following statalarms off:
__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)
__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE)
CAUTION Normal plant loads can overload the Auxiliary Transformer, CT-4, or CT-5 4.22 IAAT electrical loads are added, AND either MFB is energized by:
- CT-4
- CT-5
- Backcharged 1T THEN ensure transformer is within limits of the applicable enclosure:
Source Encl CT-4 5.1A CT-5 5.1B Transformer 1T 5.1C This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 32 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 9 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior RULE 3 Crew response:
EOP Rule 3 Rev 3
- 1. Verify loss of MFDW and/or EFDW was due to any of the following:
__ Turbine Building Flooding
__ Actions taken to increase SG level due to Turbine Building Flooding RNO: GO TO Step 3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW),
AND any of the following exist:
__ RCS pressure reaches 2300 psig OR NDT limit
__ Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)
CT-1 4. Start operable EFDW pumps, as required, to feed all intact SGs (BOUNDING CRITERIA: Supply Feedwater to SGs for heat removal to preclude initiation of HPI Forced Cooling)
- 5. Verify any EFDW pump operating
- 6. GO TO Step 38
- 38. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 39 - 43 RNO: GO TO Step 44
- 39. Place EFDW valve in MANUAL
- 40. Control EFDW flow with EFDW valve in MANUAL
- 41. GO TO Step 44
- 44. Verify any SCM 0°F CAUTION ATWS events may initially require throttling to prevent exceeding pump limits and additional throttling once the Rx is shutdown to prevent overcooling RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control),
THEN throttle EFDW, as necessary
- 45. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation) (next page)
- 46. WHEN directed by CRS, THEN EXIT This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 33 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 10 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.9 Crew response:
EOP Enclosure 5.9 (Extended EFDW Operation) Rev 01
- 1. Monitor EFDW parameters on EFW graphic display
- 2. IAAT UST level is < 4', THEN GO TO Step 120
- 8. Perform as required to maintain UST level > 7.5'
__ Makeup with demin water
__ Place CST pumps in AUTO
- 9. IAAT all exist:
__ Rapid cooldown NOT in progress
__ MD EFDWP operating for each available SG
__ EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK
- 10. Verify 1 TD EFDW PUMP operating
- 11. Start TD EFDWP BEARING OIL COOLING PUMP NOTE
- Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 is 10% open.
- If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.
- 12. Notify CR SRO to set priority based on the NOTE above and EOP activities This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 34 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 11 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.38 Crew response:
EOP Enclosure 5.38 (Restoration of Power) Rev 01
- 1. Verify power has been restored RNO: GO TO Step 3
- 3. Place 1HP-31 in HAND and reduce demand to 0
- 4. Close 1HP-21
- 5. Verify any of the following energized:
__ MFB1
__ MFB2 RNO: GO TO Step 8
- 8. Verify CT-1 indicates 4160 volts RNO: GO TO Step 18
- 18. Verify both Standby Bus #1 and Standby Bus #2 are de-energized (0 volts)
- 19. Verify both Keowee units operating RNO: 1. Emergency start Keowee units:
__ KEOWEE EMER START CHANNEL A
__ KEOWEE EMER START CHANNEL B
- 2. IF NO Keowee units are operating, THEN perform the following:
A. Notify Keowee operator to restore a Keowee unit to operable status B. GO TO Step 38 Examiner Note: Keowee Hydro Unit 1 will be operating This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 35 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 12 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.38 Crew response:
EOP Enclosure 5.38
- 20. Verify both Keowee units in Oconee Control (statalarms on):
__ UNIT 1 OCONEE CONTROL (2SA-17/E-1)
__ UNIT 2 OCONEE CONTROL (2SA-18/E-1)
RNO: Notify Keowee Operator to place both Keowee units Master Transfer switches to remote
- 21. Verify both Keowee units operating RNO: 1. IF UNIT 1 EMER FDR ACB 3 is closed, AND Unit 1 Keowee is NOT operating, THEN open UNIT 1 EMER FDR ACB 3
- 2. IF UNIT 2 EMER FDR ACB 4 is closed, AND Unit 2 Keowee is NOT operating, THEN open UNIT 2 EMER FDR ACB 4 CT-2 22. Ensure one of the following is closed for an operating Keowee unit:
Unit 1 Unit 2 UNIT 1 UNIT 2 EMER FDR EMER FDR ACB 3 ACB 4 (BOUNDING CRITERIA: Restore power from KHU-1 prior to completion of Enc. 5.38 of the EOP)
- 23. Verify 4160 volt power has been restored to the MFB
- 24. GO TO Step 35
- 35. Verify any of the following energized:
__ 1TC
__ 1TD
__ 1TE
- 37. EXIT this enclosure This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 36 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 13 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:
EOP Enclosure 5.45 (PSW Feed and RCP Seals) rev 06 NOTE While running this enclosure along with a loss of power to HPIPs, Rule 4 should not be performed until SG feed has been established from some source
- 1. Verify Unit 2 EOP Encl 5.42 (PSW Power and Pump Alignment) in progress or complete RNO: Notify Unit 2 to PERFORM Unit 2 EOP Encl 5.42 (PSW Power and Pump Alignment)
Examiner Note: Once an RO notifies Unit 2 to perform EOP Encl 5.42, a booth instructor will enter the simulator to perform the enclosure. This enclosure will have no effect on the outcome of the scenario.
- 2. WHEN the Unit 1 PSW 4KV POWER AVAILABLE light lit, THEN continue
- 3. Verify it is desired to power HPI from PSW RNO: GO TO Step 9 NOTE There is a 40 second time delay in the swap from Normal to PSW power on HPIPs
- 7. Perform the following:
A. Place 1B HPI PUMP POWER TRANSFER to PSW B. Do NOT wait for the PSW power light, continue This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 37 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 14 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:
EOP Enclosure 5.45
- 8. Place POWER TRANSFER switch to PSW on the following:
- 1RC-159/1RC-160
- 1RC-157/1RC-158
- 1RC-155/1RC-156
- 9. Position the switch for 1PSW-6 to open
- 12. Close 1HP-5
- 13. Close 1HP-21
- 14. IAAT it is desired to supply PSW SG feed, THEN GO TO Step 45
- 15. IAAT it is desired to supply RCP seals, THEN GO TO Step 58 (next page)
NOTE If RCS head vents, loop vents, or PORV have been opened, [acc] levels must be used
- 16. IAAT Pzr level 85" (165" acc), AND it is desired to power the Pzr heaters from PSW, THEN dispatch an operator to perform EOP Encl 5.46 (Aligning PZR Heaters From PSW)
- 17. IAAT notified that PSW is NO longer required, THEN GO TO Step 19
- 18. WHEN directed by CRS, THEN EXIT this enclosure This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 38 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 15 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:
EOP Enclosure 5.45
- 58. IAAT notified that SSF Feed has been established or is capable of feeding SGs, THEN simultaneously close the PSW control valves:
2300 psig, THEN PERFORM Step 46.
NOTE If RCS head vents, loop vents, or PORV have been opened, [acc] levels must be used
- 60. IAAT feeding SGs with PSW AND Tc 550 - 555°F, THEN while maintaining Tc 550 - 555°F, throttle the following valves to slowly raise SG levels to (No RCPs) 240"- 260" XSUR (270" - 290" acc):
NOTE ES may have actuated requiring manual control of HPI
- 61. Perform the following:
__ Close 1HP-139
__ Close 1HP-26
__ Open 1HP-24
- 62. Ensure 1HP-120 in manual with demand at zero
- 63. Verify BWST available based on Control Room level indication This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 39 of 52
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 1 Event No.: 8 Page 16 of 16 Event
Description:
Switchyard Isolate with Turbine trip (M: ALL)
Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:
EOP Enclosure 5.45 NOTE
- When the SSF and PSW are both supplying seals it may not be possible to get 30 - 35 gpm flow through 1HP-140
- 65. Throttle 1HP-140 to obtain as close to 30 - 35 gpm RCP Seal flow as possible NOTE RCS pressure higher than normal RCS operating pressure could restrict flow through 1HP-140
- 66. Maintain 30 - 35 gpm Seal Inlet Hdr Flow by throttling 1HP-140 as necessary NOTE If RCS head vents, loop vents, or PORV have been opened, [acc] levels must be used
- 67. IAAT Pzr level 85" (165" acc), AND it is desired to power the Pzr heaters from PSW, THEN dispatch an operator to perform EOP Encl 5.46 (Aligning Pzr Heaters from PSW)
- 68. Notify CRS PSW RCP seals have been established This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.
Page 40 of 52
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Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam CRITICAL TASKS CT-1 Start the TD EFDWP to supply Feedwater flow to the SGs for heat removal to preclude initiation of HPI Forced Cooling. (page 33)
CT-2 Restore power from Keowee Hydro Unit 1 prior to the completion of EOP Enclosure 5.38 (BWOG CT-3). VOL 3, III I-7, 8 (page 36)
Page 51 of 52
SAFETY: Take a Minute UNIT 0 (SM)
SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 0 Fuel Handling: No PSW Operable: Yes (CT-5 OOS)
UNIT STATUS (CRS)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 882 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration Required TS/SLC #
Date/Time Date/Time AMSAC/DSS Today/0300 7 Days SLC 16.7.2 Lee/Central Alt Pwr Path Today/0500 N/A SLC 16.8.6 Shift Turnover Items (CR SRO)
Primary
- SASS is in Manual for calibration Secondary
- AMSAC/DSS bypassed for calibration
- OP/1/A/1106/002 B Encl 4.13 in progress to restore 1B Main FDW Pump from Handjack
- Following turnover, the CRS will direct the BOP to restore the 1B MFDWP from the Handjack per OP/1/A/1106/002 B Enc. 4.13 beginning at Step 2.1.
- 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.
Electrical
Gp 7 Rod Position: Batch additions as required for volume RCS Boron 41 ppmB 90% Withdrawn control. (OATC)
Human Performance Emphasis (SM)
Procedure Use and Adherence
Appendix D Scenario Outline Form ES D-1 ILT 20-1 NRC Exam Facility: Oconee Scenario No.: 2 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________ SRO
________________________ ________________________ OATC
________________________ ________________________ BOP Initial Conditions:
- Reactor Power = 97%
Turnover:
- SASS is in Manual for calibration
- AMSAC/DSS is bypassed for calibration
- CT-5 OOS for maintenance
- PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power) in progress to test CV3 & CV4 Event Malfunction Event Event Type* Description No. No.
0a Override AMSAC/DSS Bypassed 0b Override SASS in Manual 0c Override CT-5 OOS 1 N: BOP, SRO Turbine Control Valve Movement PT (CV3 & CV4) 1A CC Pump Trips & Standby CC Pump Fails to Auto 2 MPS290 C: BOP, SRO Start (CT-1)
C: OATC, BOP, 3 Override Inadvertent ES Channel 3 Actuation SRO (TS) 4 MCS019 I: OATC, SRO Tc Controller Failure 5 C: BOP, SRO Oil Leak on Main Turbine 6 R: OATC, SRO (TS) Manual Power Reduction MPI290 ATWS (Loss of 1TA Switchgear) (CT-3)
MPI300 7 M: ALL
- Turbine Fails to Trip (CT-2)
MEL120
- 1HP-26 Fails Closed MPS140
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam SCENARIO 2 EVENT
SUMMARY
Event 1: When the crew takes the shift, the BOP will perform PT/1/A/0290/003 Enclosure 13.2 (Control Valve Movement At Power) to test Turbine Control Valves CV3 & CV4. Once the test is complete, the Turbine Bypass Valves (TBVs) will be closed, returned to automatic, and the Standby EHC pump will be secured and placed in automatic.
Event 2: The operating Component Cooling Pump (1A CC Pump) will trip and the Standby CC Pump (1B CC Pump) will fail to auto start. The BOP will reference an Alarm Response Guide which will direct manually starting the Standby CC Pump. Since there will be no CC flow until the Standby CC Pump is started, Letdown temperature will begin to increase and 1HP-5 will automatically close on high Letdown temperature (135°F). The SRO will then enter AP/1/A/1700/032 (Loss of Letdown) to restore Letdown.
Event 3: Engineered Safeguards (ES) Channel 3 will inadvertently actuate which will cause the 1A LPI Pump to start, 1LP-17 to open, and C LPSW Pump to start. Once the crew determines that the ES actuation is not valid, the SRO will enter AP/1/A/1700/042 (Inadvertent ES Actuation) to restore the ES components to normal operation. The SRO will enter TS 3.3.7 and TS 3.7.7.
Event 4: The Tc Controller will fail causing 1A Feedwater flow to increase and 1B Feedwater flow to decrease. Once alarms are received, the crew will perform Plant Transient Response to stabilize the plant. Once the plant is stable, the SRO will enter AP/1/A/1700/028 (ICS Instrument Failures) and ensure the appropriate ICS stations are in manual.
Event 5: A report will be made to the control room that there is a large oil leak on the Main Turbine and there is no way to isolate the leak without shutting down the oil system.
The SRO will enter an Abnormal Procedure to rapidly shut down the unit with ICS in manual in order to take the turbine offline.
Event 6: Due to ICS Stations being in MANUAL, the OATC will be required to perform a manual power reduction as a result of the Main Turbine Oil leak (Event 5).
Event 7: 1TA Switchgear will lockout and the Reactor will fail to trip automatically or manually (ATWS). The OATC will perform Rule 1 and the SRO will enter the UNPP tab of the EOP. The turbine will fail to trip using the Turbine Trip Pushbutton which will require the operator to lockout both EHC Pumps to prevent severe overcooling of the RCS.
1HP-26 will fail closed requiring 1HP-410 to be opened to allow full HPI flow from the BWST to borate the RCS and shutdown the Reactor.
Page 2 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 1 Page 1 of 3 Event
Description:
Turbine Control Valve Movement PT (N: BOP, SRO)
Time Position Applicants Actions or Behavior PT/1/A/0290/003 Crew response:
SRO directs the BOP to perform PT/1/A/0290/003 Encl. 13.2 to test CV3 & CV4 PT/1/A/0290/003 Encl 13.2 (Control Valve Movement at Power) rev 20 2.5 IF AT ANY TIME reactor/turbine trip OR significant transient occurs, ensure Turbine Bypass Valves to AUTOMATIC NOTE: CV3 & CV4 testing is combined into single test with CV3 ramping closed and CV4 opening. When CV3 is fully tested, CV4 is disc dumped at < 6 % open to complete test.
2.6 IF CV3 and CV4 test required:
2.6.1 Select "Control Valve 3 & 4 Test" 2.6.2 Verify the following:
___ "Test Permissive" is ON for CV3
___ "Test Permissive" is ON for CV4 2.6.3 Record CV3 and CV4 pretest positions:
- CV3 pretest position: ________ % Open
- CV4 pretest position: ________% Open 2.6.4 Select "Initiate CV3 and CV4 Test" 2.6.5 IF any of the following conditions occur, select "Abort CV3 &
CV4 Test" NI POWER changes > 2% (R.M.)
ICS Turbine Master trips to HAND (R.M.)
Turbine vibration > 10 mils for > 5 seconds CAUTION: If CV3 remains in the closed position with the Test Failed indication "ON", initiating Abort Test could result in a reactivity management event. (R.M.)
2.6.6 IF "Test Failed" is "ON" AND CV3 is NOT fully closed, select "Abort CV3 & CV4 Test" NOTE: If a Control Valve remains closed after it has disc-dump, it may start going open at any time (i.e. 1 min, 5 min, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). When the Control Valve starts going back open it will open at its normal rate.
No transients are expected during this scenario since the EHC Control System will simply continue with the test logic and return the Control Valve to its normal position at the normal controlled test rate.
This event is complete when the Standby EHC pump switch is placed in AUTO (step 2.9.5), or as directed by the Lead Examiner.
Page 3 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 1 Page 2 of 3 Event
Description:
Turbine Control Valve Movement PT (N: BOP, SRO)
Time Position Applicants Actions or Behavior PT/1/A/0290/003 Crew response:
PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power) 2.6.7 IF "Test Failed" is "ON" AND CV3 remained closed perform the following:
A. Do NOT select "Abort CV3 & CV4 Test" B. Notify WCC & Engineering that the (FASV) for the Control Valve under test is stuck in the energized state NOTE: Control Valves which are not in their normal position could result in asymmetrical loading on the Turbine bearings.
C. Monitor Turbine Vibrations closely if in this abnormal state 2.6.8 Perform EITHER for CV3:
A. Verify "Test Successful" indicated for CV3 B. IF "Test Successful" NOT indicated for CV3, verify CV3 moved towards closed position 2.6.9 Perform EITHER for CV4:
A. Verify "Test Successful" indicated for CV4 B. IF "Test Successful" NOT indicated for CV4, verify CV4 moved towards closed position NOTE:
- CV3 and CV4 test indicator resets after 20 seconds
- Test indicators reset is when "Test Permissive" is ON and all other Test Indicators are OFF 2.6.10 Verify CV3 test indicator reset 2.6.11 Verify CV4 test indicator reset 2.6.12 Verify CV3 within +/- 5.0% of pretest position 2.6.13 Verify CV4 within +/- 5.0% of pretest position 2.6.14 Perform the following:
Verify acceptance criteria met.
IF acceptance criteria NOT met, notify SRO.
Examiner Note: Steps 2.7 and 2.8 are not applicable.
2.9 Perform the following:
2.9.1 Ensure all Turbine Bypass Valves CLOSED (R.M.)
2.9.2 Verify CV-4 returns to its expected pre-test position (Reference step 2.4.1 or Encl 13.1 step 2.3.1)
This event is complete when the Standby EHC pump switch is placed in AUTO (step 2.9.5), or as directed by the Lead Examiner.
Page 4 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 1 Page 3 of 3 Event
Description:
Turbine Control Valve Movement PT (N: BOP, SRO)
Time Position Applicants Actions or Behavior PT/1/A/0290/003 Crew response:
PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power)
Examiner Note: CV-4 should return to 3% open.
2.9.3 IF either TBV in HAND, perform the following:
A. Determine the following:
- Reactor Trip Confirm. OAC point O1S1585 (K19 Reactor Trip Confirm True False
- THP setpoint. OAC point O1E2089 = _______ psig
- ICS Selected THP. OAC point O1E2088 = _______ psig B. IF O1S1585 (K19 Reactor Trip Confirm) is TRUE (CRDs tripped), perform the following:
- Calculate ICS Selected THP (O1E2088) minus 125 psig =
_____ psig
- On TURBINE MASTER adjust THP setpoint (O1E2089) to
~ calculated psig value in Step 1 above.
C. IF O1S1585 (K19 Reactor Trip Confirm) is FALSE (CRDs reset), on TURBINE MASTER adjust THP setpoint (O1E2089) to ~ ICS Selected THP (O1E2088).
CAUTION: TBVs placed in automatic with the controlling parameter and setpoint NOT matched can result in a significant transient and reactivity management event. (R.M.)
THE FOLLOWING STEP IS A CRITICAL STEP (C.S.)
D. WHEN proper TBV setpoint is established, ensure Turbine Bypass Valves positioned to AUTO:
- 1A TURBINE BYPASS VALVES (R.M.)
- 1B TURBINE BYPASS VALVES (R.M.)
2.9.4 Stop Standby EHC pump 2.9.5 Place Standby EHC pump control switch to "AUTO" 2.9.6 Make the following plant page announcement:
"Attention plant personnel. Attention plant personnel. Unit 1 Turbine Valve Movement test is now complete." (repeat)
Booth Cue: If AO is contacted to clear the Turbine Panel Alarm, acknowledge the request and ACTIVATE TIMER 1A.
This event is complete when the Standby EHC pump switch is placed in AUTO (step 2.9.5), or as directed by the Lead Examiner.
Page 5 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 2 Page 1 of 3 Event
Description:
1A CC Pump Trips & Standby CC Pump Fails to Auto Start (C: BOP, SRO)
Time Position Applicants Actions or Behavior Plant response:
- 1SA-2/C-1 (LETDOWN TEMPERATURE HIGH) Rev 34
- 1HP-5 (Letdown Isolation) will close due to high letdown temperature
- CC Total Flow Low
- Component Cooling Pressure Low Crew response:
Refer to ARG 1SA-9/B-1 OR 1SA-9/C-1 ARG 1SA-09/B-1 BOP ARG 1SA-09/B-1 3.1 IF ES 5 or 6 has actuated, (N/A) 3.2 IF 1CC-7 or 1CC-8 are closed, (N/A) 3.3 IF 1SA-09/C-1 is in alarm AND the Standby CC Pump did NOT start, perform the following:
3.3.1 Verify CC Surge Tank level > 12 CT-1 3.3.2 Start Standby CC Pump (Bounding Criteria: Prior to reaching 180°F on 2 CRDs) 3.4 IF NO CC Pumps are operating, Go To AP/20 (Loss of Component Cooling)
ARG 1SA-09/C-1 ARG 1SA-09/C-1 3.1 IF ES 5 or 6 has actuated, (N/A) 3.2 IF 1CC-7 or 1CC-8 are closed, (N/A) 3.3 IF Standby CC Pump did NOT start, perform the following:
CT-1 3.3.1 Verify CC Surge Tank level > 12 3.3.2 Start Standby CC Pump (Bounding Criteria: Prior to reaching 180°F on 2 CRDs) 3.4 IF NO CC Pumps are operating, Go To AP/20 (Loss of Component Cooling)
Examiner Note: Once the 1B CC pump is started, the SRO will refer to AP/32 (Loss of Letdown). (next page)
ARG 1SA-02/C-1 ARG 1SA-02/C-1 Rev 35 3.1 Decrease letdown flow using 1HP-7 (LETDOWN CONTROL) 3.2 IF 1HP-5 (LETDOWN CONTROL) closed due to temperature reaching setpoint, refer to AP/1/A/1700/032 (Loss of Letdown)
This event is complete when the Standby HPI Pump is placed back in Auto, or as directed by the Lead Examiner.
Page 6 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 2 Page 2 of 3 Event
Description:
1A CC Pump Trips & Standby CC Pump Fails to Auto Start (C: BOP, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/032 Crew response:
AP/1/A/1700/032 (Loss of Letdown) rev 07 4.1 Verify a total loss of letdown exists SRO/BOP 4.2 Place 1HP-120 in HAND and reduce demand to zero 4.3 Position the standby HPI pump switch to OFF CAUTION: RCP individual seal return valves will close if seal injection is
< 22 gpm with CC flow < 575 gpm.
4.4 Throttle 1HP-31 to establish 12 - 15 gpm SEAL INLET HDR FLOW NOTE: The running HPIP may operate below 65 gpm for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
HPIP time of operation below minimum flow is cumulative.
4.5 Verify HPI pump flow 65 gpm (30 gpm Recirc + ___ SI +___ MU)
RNO: Log beginning time for HPI pump flow below minimum 4.6 Initiate makeup to the LDST as required. (Using EOP Enclosure 5.5 or OP/1/A/1103/004 for batch additions) 4.7 Notify the OSM to reference OMP 1-14, Emergency Plan, and notify the STA 4.8 Verify 1HP-5 closed 4.9 Dispatch an operator to 1HP-5 to establish communication with the CR NOTE
- TS 3.4.9 applies when PZR level > 260" (corrected value for 285").
- Conditions where it is known that letdown CANNOT be restored do not require waiting until 260" to begin a rapid shutdown.
4.10 IAAT either of the following exist:
- PZR level > 260 inches AND letdown CANNOT be established
- Plant conditions exist such that letdown will NOT be restored THEN initiate unit shutdown per AP/29 (Rapid Unit Shutdown) 4.11 IAAT PZR level 375 inches, THEN trip Rx 4.12 Determine the cause of loss of letdown:
Actual LD Temperature high: GO TO Step 4.29 This event is complete when the Standby HPI Pump is placed back in Auto, or as directed by the Lead Examiner.
Page 7 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 2 Page 3 of 3 Event
Description:
1A CC Pump Trips & Standby CC Pump Fails to Auto Start (C: BOP, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/032 Crew response:
4.29 Notify FIN24 to initiate repairs on failed equipment 4.30 IAAT letdown can be re-established, THEN perform Steps 4.31 - 4.48 4.31 Place CC System in operation 4.32 Close 1HP-6 BOP 4.33 Close 1HP-7 4.34 Open 1HP-1, 1HP-2, 1HP-3, and 1HP-4 4.35 Verify letdown temperature < 135°F RNO: 1. Open 1HP-13
- 3. Verify NO deborating IXs in service
- 4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS 4.36 Open 1HP-5 4.37 Throttle open 1HP-7 to establish 20 gpm 4.38 WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL 4.39 Open 1HP-6 4.40 Adjust 1HP-7 to control desired letdown flow 4.41 Re-establish normal makeup through 1HP-120 4.42 Re-establish normal RCP seal injection flow 4.43 Position the standby HPI pump switch to AUTO Examiner Note: This concludes the event. It is not required to put Purification IX in service at step 4.44 4.44 Verify any purification IX in service RNO: IF purification IX operation is desired, THEN initiate OP/1/A/1103/004 B to establish desired IX operation 4.45 EXIT this procedure Examiner Note: When letdown is restored and PZR Level is returned to
~220 inches, the Unit may experience Low RCS Pressure and require a TS 3.4.1 entry (< 2125 psig).
SRO TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Condition A (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) Restore RCS DNB Paramater(s) to within limit This event is complete when the Standby HPI Pump is placed back in Auto, or as directed by the Lead Examiner.
Page 8 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 3 Page 1 of 5 Event
Description:
Inadvertent ES Channel 3 Actuation (C: OATC, BOP, SRO) (TS)
Time Position Applicants Actions or Behavior Plant response:
- 1A LPI Pump starts
- C LPSW Pump starts
- O1E0507 LPSW LEAKAGE ACCUMULATOR Level HIGH Crew response:
- The crew will determine that the ES actuation is not valid
ARG 1SA-01/C-10 ARG 1SA-01/C-10 (ES 3 TRIP) rev 15 BOP 3.1 Determine if ES condition exists (RCS pressure 550 psig OR RB pressure 3.0 psig) 3.2 IF RCS pressure is 550 psig OR RB pressure is 3.0 psig, Go To EP/1/A/1800/001 (Emergency Operating Procedure) 3.3 IF ES condition does NOT exist, Initiate AP/1/A/1700/042 (Inadvertent ES Actuation) 3.4 Refer to OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)
ARG 1SA-03/C-8 and C-9 ARG 1SA-03/C-8 (LP INJECTION LOOP A FLOW HIGH/LOW) Rev 65 3.1 High/Low Flow 3.1.1 IF in DHR, refer to AP/1/A/1700/026 (Loss of Decay Heat Removal) 3.1.2 IF NOT in DHR, refer to EP/1/A/1800/001 (Emergency Operating Procedure)
ARG 1SA-03/C-9 (LP INJECTION LOOP B FLOW HIGH/LOW) Rev 65 3.1 High/Low Flow 3.1.1 IF in DHR, refer to AP/1/A/1700/026 (Loss of Decay Heat Removal) 3.1.2 IF NOT in DHR, refer to EP/1/A/1800/001 (Emergency Operating Procedure)
This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.
Page 9 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 3 Page 2 of 5 Event
Description:
Inadvertent ES Channel 3 Actuation (C: OATC, BOP, SRO) (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/042 Crew response:
AP/1/A/1700/042 (Inadvertent ES Actuation) rev 04 4.1 Verify any of the following have inadvertently actuated: (N/A)
__ Diverse HPI
__ ES Channel 1
__ ES Channel 2 RNO: GO TO Step 4.4 4.4 Verify any of the following have inadvertently actuated: (N/A)
__ ES Channel 5
__ ES Channel 6 RNO: 1. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently actuated, AND it is desired to restore letdown, THEN initiate AP/42 Encl 5.2 (Letdown Restoration). (N/A)
- 2. GO TO Step 4.10 4.10 Close the following:
__ 1HP-24 (already closed)
__ 1HP-25 (already closed)
NOTE If personnel are available, progression should continue while Encl 5.1 (Required Operator Actions) is in progress.
4.11 Ensure AP/42 Encl 5.1 (Required Operator Actions) is in progress (page 12) 4.12 Verify any of the following have inadvertently actuated:
__ Diverse LPI (not actuated)
__ ES Channel 3
__ ES Channel 4 (not actuated) 4.13 Verify Diverse LPI has inadvertently actuated (N/A)
RNO: GO TO Step 4.15 OATC 4.15 Perform the following on all inadvertently actuated system(s):
__ Ensure ES CH-3 is in MANUAL
__ Ensure ES CH-4 is in MANUAL (N/A)
This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.
Page 10 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 3 Page 3 of 5 Event
Description:
Inadvertent ES Channel 3 Actuation (C: OATC, BOP, SRO) (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/042 Crew response:
AP/1/A/1700/042 (Inadvertent ES Actuation) 4.16 Verify LPI was aligned in decay heat removal mode prior to ES actuation OATC RNO: 1. Stop the following:
__ 1A LPI PUMP
__ 1B LPI PUMP (not operating)
- 2. Simultaneously close the following:
__ 1LP-17
__ 1LP-18 (already closed) 4.17 Verify the Rx is critical 4.18 Verify ICS in Auto 4.19 Verify control rods are outside the desired control band RNO: GO TO Step 4.21 4.21 Verify any of the following have inadvertently actuated:
__ ES Channel 1 (not actuated)
__ Diverse HPI (not actuated)
RNO: GO TO Step 4.24 4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary 4.25 Initiate logging TS/SLC Entry/Exit, as applicable, in accordance with Encl 5.4 (TS/SLC Requirements) (page 13) 4.26 WHEN all the following exist:
__ Reason for inadvertent ES Channel or Diverse HPI/LPI actuation has been resolved
__ ES Channel or Diverse HPI/LPI reset is desired
__ OSM concurs THEN continue This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.
Page 11 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 3 Page 4 of 5 Event
Description:
Inadvertent ES Channel 3 Actuation (C: OATC, BOP, SRO) (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/042 Encl 5.1 Crew response:
BOP AP/1/A/1700/042 Enclosure 5.1 (Required Operator Actions)
- 1. Initiate announcement of AP Entry using the PA system NOTE If channels are bypassed or in override, 1SA-1/A-10 (ES 1 Trip) and 1SA-1/B-10 (ES 2 Trip) will be off even though the channel may have actuated.
- 2. Verify any of the following have inadvertently actuated:
__ES Channel 1, 2, or Diverse HPI RNO: GO TO Step 5
- 5. Verify any of the following have inadvertently actuated:
__ ES Channel 7
__ ES Channel 8 RNO: GO TO Step 9
- 9. Perform the following:
A. Open the following to restore RB RIAs:
__ 1PR-7
__ 1PR-8
__ 1PR-9
__ 1PR-10 Examiner Note: The SRO may elect to NOT stop the RB RIA sample pump to prevent inadvertently entering TS 3.4.15 since ES Channel 3 actuation does not isolated the RB RIAs.
B. From the ENABLE CONTROLS screen on the RIA View Node, perform the following:
- 1) Select OFF for RB RIA sample pump
- 2) Start the RB RIA sample pump
- 10. Verify any of the following have inadvertently actuated:
__ Diverse HPI
__ ES Channel 1 RNO: GO TO Step 12
- 12. EXIT this enclosure This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.
Page 12 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 3 Page 5 of 5 Event
Description:
Inadvertent ES Channel 3 Actuation (C: OATC, BOP, SRO) (TS)
Time Position Applicants Actions or Behavior Tech Specs Crew response:
SRO TS 3.3.7 ESPS AUTOMATIC ACTUATION OUTPUT LOGIC CHANNELS Condition A (1hour) Place associated component(s) in ES configuration OR (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) Declare the associated component(s) inoperable TS 3.7.7 LOW PRESSURE SERVICE WATER SYSTEM (LPSW)
Condition B (7 days) Restore the LPSW WPS to OPERABLE status Examiner Note: If the RIA sample pump is turned off per AP/42 Encl. 5.1 step 9, TS 3.4.15 Condition B will be entered while the sample pump is off.
TS 3.4.15 RCS LEAKAGE DETECTION INSTRUMENTATION Condition B (Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) Analyze grab samples of the containment atmosphere OR (Once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) Perform SR 3.4.13.1 AND Restore required containment atmosphere radioactivity monitor to OPERABLE status This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.
Page 13 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 4 Page 1 of 3 Event
Description:
Tc Controller Failure (I: OATC, SRO)
Time Position Applicants Actions or Behavior Plant response:
- FDW flow will ratio incorrectly based on the failure
- A FDW flow will increase causing A loop TC to decrease
- B FDW flow will decrease causing B loop TC to increase
- This will cause actual TC to decrease (become more negative). Failure to correctly adjust FDW flow will result in QPT alarms.
Crew response:
When the Statalarms are received, the crew should perform Plant Transient Response (PTR) to stabilize the plant
- The OATC will place the Feedwater Masters and the Diamond to MANUAL and re-ratio feedwater using the Loop TC meters and/or OAC (RCS01) to return actual TC to near zero OATC The OATC should:
- Communicate to the CRS the initial alarm (if applicable) followed by reactor power level and direction
- Place the appropriate ICS stations in manual (Diamond and both FDW Masters in this case) in manual if any of the following occur:
o NI power increasing above the pre-transient power level o Failed instrument is diagnosed o Invalid input exists and the CRS directs the ICS be placed in manual
- Monitor plant response and verify operating limits NOT exceeded
- If ICS is placed in Manual, remain focused on RCS pressure, SG outlet pressure and RCS inventory SRO The SRO should:
- Refer to AP/28 (ICS Instrument Failures) (next page)
- Ensure Maintenance is contacted to repair the failed instrument This event is complete when the SRO reaches Step 4 of AP/28 Section 4F, or as directed by the Lead Examiner.
Page 14 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 4 Page 2 of 3 Event
Description:
Tc Controller Failure (I: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:
AP/1/A/1700/028 (ICS Instrument Failures) rev 24 4.1 Provide control bands as required (AD-OP-ONS-0002 Attachment 17)
OATC/SRO Attachment 17: rev 01
- 1. Plant Conditions Stable or TPB Pre-transient Conditions 1.1 The following bands are to be established during manual control of plant conditions (as needed) but may be adjusted by the CRS if required 1.1.1 NI Power +/- 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power - 1%
1.1.2 Current Tave +/- 2°F 1.1.3 Current SG Outlet Pressure +/- 10 PSIG (N/A) 1.1.4 Delta Tc 0oF +/- 2°F 4.2 Initiate notification of the following:
__ SM to reference the following:
- OMP 1-14 (Notifications)
__ STA 4.3 Verify a power transient 5% has occurred RNO: GO TO Step 4.5 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:
- OAC alarm video
- OAC display points
- Control Board indications
- Maintenance assistance, as needed This event is complete when the SRO reaches Step 4 of AP/28 Section 4F, or as directed by the Lead Examiner.
Page 15 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 4 Page 3 of 3 Event
Description:
Tc Controller Failure (I: OATC, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:
AP/1/A/1700/028 (ICS Instrument Failures)
OATC/SRO 4.6 GO TO the applicable section per the following table:
Section Failure 4F Delta Tc AP/1/A/1700/028 Section 4F (Delta Tc Failure)
NOTE
- This Section applies to Delta Tc controller failures. Tc input signal failures are addressed in Section 4A The following may occur when an ICS Delta Tc controller fails:
- Delta Tc controller may re-ratio loop feedwater flows
- Possible ICS RUNBACK
- 1. Ensure the following in HAND:
__ 1A FDW MASTER
__ 1B FDW MASTER
__ DELTA Tc CAUTION Total feedwater flow should be maintained constant while individual loop flows are adjusted to establish the desired Tc. Maintaining total FDW flow constant will prevent unwanted changes in reactor power.
- 2. Re-ratio feedwater flow, as required, to establish desired DELTA Tc while maintaining total feedwater flow constant
- 3. Notify Maintenance to perform the following:
__ Investigate and repair the failed Delta Tc controller
- 4. WHEN notified by Maintenance that Delta Tc controller has been repaired, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto)
This event is complete when the SRO reaches Step 4 of AP/28 Section 4F, or as directed by the Lead Examiner.
Page 16 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 5 Page 1 of 4 Event
Description:
Main Turbine Oil Leak (C: BOP, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Booth Cue: To initiate this event, call the Control Room on 4911 and inform them as follows: "This is the WCC SRO. There is an oil leak on the north end of the Unit 1 B LP turbine. There is not a way to isolate the leak without shutting down the oil system". IF asked, respond that a fire risk does exist.
Booth Cue: If needed, state that there is a significant amount of oil leaking from the LP turbine.
Booth Cue: If asked for Unit 2 to handle the Spill Response procedure, respond that "Unit 2 will perform the Spill Response procedure".
Booth Cue: If crew initiates AP/52 Turbine Bldg Oil Leak/Fire, call as the SM and say that "Unit 2 will perform AP/52".
Crew Response:
The SRO will initiate AP/29 (Rapid Unit Shutdown) in order to reduce power to BOP/SRO take the Main Turbine off line AP/1/A/1700/029 (Rapid Unit Shutdown) Rev 13 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) (page 19) 4.2 Announce AP entry using the PA system.
4.3 IAAT both of the following apply:
__ It is desired to stop power decrease.
__ CTP > 18%
THEN perform Steps 4.4 - 4.7 RNO: GO TO Step 4.8 4.8 Verify ICS in AUTO (ICS is NOT in Auto)
Examiner Note: Focus Brief opportunity.
RNO: 1. Initiate manual power reduction to desired power level. (page 21)
- 2. GO TO Step 4.10 Note: OATC reduces power by first reducing feedwater and then inserting control rods as necessary.
4.10 Verify both Main FDW pumps running:
NOTE
- 1B Main FDW Pump is the preferred to be shutdown first
- To lower 1B Main FDW Pump suction flow, bias is adjusted counter-clockwise.
- To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise.
This event is complete when Rx Power has decreased 10% AND Unit Auxiliaries have been transferred, or as directed by the Lead Examiner.
Page 17 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 5 Page 2 of 4 Event
Description:
Main Turbine Oil Leak (C: BOP, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 AP/1/A/1700/029 (Rapid Unit Shutdown)
BOP/SRO 4.11 Adjust bias for first Main FDW pump desired to be shutdown (1B) until its suction flow is 1 X 106 lbm/hr less than remaining Main FDW pump suction flow.
4.12 WHEN core thermal power is < 65% FP, THEN continue.
4.13 IAAT both Main FDW pumps running, AND both of the following exist:
__ 1B Main FDW Pump is first pump to be shut down.
__ Any of the following alarms actuate and remain in alarm:
- FWP B FLOW MINIMUM (1SA-16/A-3)
- FWP B FLOW BELOW MIN (1SA-16/A-4)
THEN trip 1B Main FDW Pump.
4.14 IAAT both Main FDW pumps running, AND both of the following exists:
__ 1A Main FDW pump is the first pump to be shut down
__ Any of the following alarms actuate and remain in alarm:
- FWP A FLOW MINIMUM (1SA-16/A-1)
- FWP A FLOW BELOW MIN (1SA-16/A-2)
THEN trip 1A Main FDW Pump 4.15 Verify Turbine-Generator shutdown is required.
4.16 Start the TURBINE TURNING GEAR OIL PUMP.
4.17 Start 1A through 1E TURBINE BRNG OIL LIFT PUMPS.
4.18 Start the TURBINE MOTOR SUCTION PUMP.
4.19 IAAT both of the following apply:
__ ICS in automatic
__ NI power is 18%
THEN deselect MAXIMUM RUNBACK. (does NOT apply) 4.20 Verify Turbine-Generator shutdown is required (it is required) 4.21 WHEN NI power 18% THEN depress turbine TRIP pushbutton This event is complete when Rx Power has decreased 10% AND Unit Auxiliaries have been transferred, or as directed by the Lead Examiner.
Page 18 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 5 Page 3 of 4 Event
Description:
Main Turbine Oil Leak (C: BOP, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Encl 5.1 AP/1/A/1700/029 Encl. 5.1 (Support Actions During Rapid Unit Shutdown)
- 2. Start the following pumps:
SRO/BOP
- 1A FDWP SEAL INJECTION PUMP
- 1A FDWP AUXILIARY OIL PUMP
- 1B FDWP AUXILIARY OIL PUMP
- 1B FDWP SEAL INJECTION PUMP
- 3. WHEN CTP is 80%, THEN continue.
- 4. Stop 1E1 HTR DRN PUMP.
- 5. Place 1HD-254 switch to OPEN.
- 6. Stop 1E2 HTR DRN PUMP.
- 7. Place 1HD-276 switch to OPEN.
- 8. Verify Turbine-Generator shutdown is required. (It is required)
- 9. Place the following transfer switches to MAN:
- 1TA AUTO/MAN
- 1TB AUTO/MAN
- 10. Close 1TA SU 6.9 KV FDR.
- 11. Verify 1TA NORMAL 6.9 KV FDR opens.
- 12. Close 1TB SU 6.9 KV FDR.
- 13. Verify 1TB NORMAL 6.9 KV FDR opens.
14 Place the following transfer switches to MAN:
- MFB1 AUTO/MAN
- MFB2 AUTO/MAN
- 15. Close E11 MFB1 STARTUP FDR.
- 16. Verify N11 MFB1 NORMAL FDR opens.
- 17. Close E21 MFB2 STARTUP FDR.
- 18. Verify N21 MFB2 NORMAL FDR opens This event is complete when Rx Power has decreased 10% AND Unit Auxiliaries have been transferred, or as directed by the Lead Examiner.
Page 19 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 5 Page 4 of 4 Event
Description:
Main Turbine Oil Leak (C: BOP, SRO)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Encl 5.1
- 19. Notify CR SRO that Unit auxiliaries have been transferred
- 20. IAAT 1SSH-9 is NOT closed, AND CTP is 75%, THEN throttle 1SSH-9 to maintain Steam Seal Header pressure 2.5 - 4.5 psig
- 21. WHEN CTP 65% THEN place the following in MANUAL SRO/BOP
__ 1FDW-53
__ 1FDW-65
- 22. IAAT load is 550 MWe, THEN perform Steps 23-24
- 23. Ensure the following are stopped:
__ 1A MSRH DRN PUMP
__ 1B MSRH DRN PUMP
- 26. IAAT load is 450 MWe, THEN perform Steps 27-30
- 27. Verify the 1C CBP operating
- 28. Stop the 1A and 1B CBPs
- 29. Place the control switch for one shutdown CBP in AUTO
- 31. WHEN 400 MWe, THEN stop the following pumps
__ 1D1 HTR DRN PUMP
__ 1D2 HTR DRN PUMP
- 32. WHEN 325 MWe, THEN verify two HWPs operating
- 33. WHEN 225 MWe, THEN stop all but one HWP
- 34. Place control switch for one idle HWP in AUTO
- 37. WHEN directed by CR SRO, THEN EXIT this enclosure This event is complete when Rx Power has decreased 10% AND Unit Auxiliaries have been transferred, or as directed by the Lead Examiner.
Page 20 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 6 Page 1 of 1 Event
Description:
Manual Power Reduction (R: OATC, SRO) (TS)
Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:
The SRO will initiate AP/29 (Rapid Unit Shutdown) to direct power reduction AP/1A/1700/029 (Rapid Unit Shutdown) rev 013 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) 4.2 Announce AP entry using the PA system.
4.3 IAAT both of the following apply:
__ It is desired to stop power decrease.
__ CTP > 18%
THEN perform Steps 4.4 - 4.7 RNO: GO TO Step 4.8 4.8 Verify ICS in AUTO (ICS is NOT in Auto)
Examiner Note: Focus Brief opportunity.
OATC RNO: 1. Initiate manual power reduction to desired power level.
- 2. GO TO Step 4.10 Examiner Note: OATC reduces power by first reducing feedwater and then inserting control rods as necessary. The CRS should give control bands for Power, Power reduction rate, RCS Tave, and RCS delta Tc.
Examiner Note: Once Reactor Power has been reduced to 85%, the crew SRO should announce SSF inoperability due to low decay heat.
TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF)
Conditions A-E are applicable due to Reactor power being < 85% which makes the SSF inoperable Required Action: Restore SSF systems to OPERABLE status (7 days)
Examiner Note: If Pressurizer level reaches 260 inches, TS 3.4.9 will apply.
TS 3.4.9 PRESSURIZER Condition A - Pressurizer water level not within limit.
Required Action: Restore level to within limit (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
This event is complete when Rx Power has decreased 10% AND Unit Auxiliaries have been transferred, or as directed by the Lead Examiner.
Page 21 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 7 Page 1 of 6 Event
Description:
ATWS (Loss of 1TA Switchgear) (M: ALL)
Time Position Applicants Actions or Behavior Plant Response:
- 1SA-1/A-7, B-7, C-7, D-7 (RCP/Flux Trip) 1TA lockout will occur. This will cause a loss of 6900V power to the 1A1 and 1B1 RCPs. RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power. The crew will attempt to manually trip the Reactor but it will not trip from the control room.
Crew Response:
Recognize the Reactor should have tripped and attempt to manually trip the Reactor in accordance with AD-OP-ONS-0002 Attachment 1 (< 3 RCPs OATC operating with Reactor power > 2%). Since the Reactor will not trip from the control room, the OATC will initiate Rule 1 while performing Immediate Manual Actions (IMAs) of the EOP.
IMMEDIATE MANUAL ACTIONS 3.1 Depress REACTOR TRIP pushbutton [Reactor will NOT trip]
OATC 3.2 Verify reactor power < 5% FP and lowering RNO: GO TO Rule 1 (ATWS/Unanticipated Nuclear Power Production)
The BOP will perform a symptom check.
BOP Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Power Range NIs NOT decreasing Power Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation Rule 4, Initiation of HPI Forced of EFDW) Cooling (Inability to feed SGs and >
2300 psig, NDT limit reached, or PZR level > 375")
Uncontrolled Main steam line(s) Rule 5, Main Steam Line Break pressure reduction CSAE Offgas alarms None (SGTR Tab is entered when Process monitor alarms (RIA-40, identified SG Tube Leakage > 25 59,60), gpm)
Area monitor alarms (RIA-16/17)
BOP will inform the SRO:
- No symptoms to report except that Power Range NIs are > 5%, OATC is performing Rule 1.
This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.
Page 22 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 7 Page 2 of 6 Event
Description:
ATWS (Loss of 1TA Switchgear) (M: ALL)
Time Position Applicants Actions or Behavior UNPP Tab Crew response:
Examiner Note: Rule 1 will direct the OATC to notify the CRS to go to the UNPP tab UNPP Tab rev 0 BOP/SRO 1. Ensure Rule 1 (ATWS/Unanticipated Nuclear Power Production) is in progress or complete (page 27)
- 2. Verify Main FDW is operating and in AUTO RNO: IF Main FDW is operating in MANUAL, THEN adjust Main FDW flow, as necessary to control RCS temperature
- 3. IAAT Main FDW is NOT operating, THEN:
A. Trip the turbine-generator B. Start all available EFDW pumps C. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete
- 4. IAAT all power range NIs are < 5% FP, THEN perform Steps 5 - 6 RNO: GO TO Step 7
- 5. Depress turbine TRIP pushbutton [the turbine will NOT trip from P/B]
- 6. Verify all turbine stop valves closed CT-2 RNO: Place both EHC pumps in PULL TO LOCK (BOUNDING CRITERIA: Lock out the EHC Pumps to trip the MT prior to entry into PTS conditions (cooldown to <400F at > 100F/hr))
- 7. Verify any wide range NI > 1% FP RNO: GO TO Step 16
- 8. Open 1RC-4
- 9. Verify 1HP-5 open
- 10. Maximize letdown using 1HP-7 while maintaining letdown temperature
< 120°F This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.
Page 23 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 7 Page 3 of 6 Event
Description:
ATWS (Loss of 1TA Switchgear) (M: ALL)
Time Position Applicants Actions or Behavior UNPP Tab Crew response:
UNPP Tab
- 11. Verify Main FDW available
- 12. Adjust Main FDW flow as necessary to control RCS temperature
- 13. Verify overcooling in progress [Over cooling is NOT in progress]
RNO: GO TO Step 16
- 16. Secure makeup to LDST
- 17. WHEN all wide range NIs are 1% FP, AND decreasing, THEN continue
- 18. Control RCS temperature as follows:
__ Tave 555°F- Adjust SG pressure as necessary to stabilize RCS temperature using either:
- Dispatch two operators to perform Encl 5.24 (Operation of the ADVs)
__ Tave > 555°F
- Utilize Rule 7 (SG Feed Control) to control SG feed rate as necessary to maintain cooldown rate within Tech Spec limits during the approach to the SG Level Control Point
- 20. WHEN RCS pressure < 2300 psig, THEN continue
- 21. Verify PORV closed
- 22. Adjust letdown flow as desired
- 23. Verify RCP seal injection available
- 24. GO TO Subsequent Actions (next page)
This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.
Page 24 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 7 Page 4 of 6 Event
Description:
ATWS (Loss of 1TA Switchgear) (M: ALL)
Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS Tab Crew response:
Subsequent Actions Tab rev 02 4.1 Verify all control rods in Groups 1 - 7 fully inserted 4.2 Verify Main FDW in operation 4.3 Verify either:
__ Main FDW overfeeding causing excessive temperature lowering
__ Main FDW underfeeding causing SG level lowering below setpoint RNO: GO TO Step 4.5 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8 RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:
__ TBVs
__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating 4.11 GO TO Step 4.14 4.14 Verify both are closed:
__ 1MS-17
__ 1MS-26 4.15 Verify ES is required RNO: 1. Initiate Encl 5.5 (Pzr and LDST Level Control) (Page 28)
- 2. GO TO Step 4.17 4.17 Open:
__ PCB 20
__ PCB 21 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.
Page 25 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 7 Page 5 of 6 Event
Description:
ATWS (Loss of 1TA Switchgear) (M: ALL)
Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS Tab Crew response:
Subsequent Actions Tab 4.18 Verify Generator Field Breaker open 4.19 Verify EXCITATION is OFF 4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure 90 psig 4.21 Verify ICS/NNI power available 4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized 4.23 Verify both SGs > 550 psig 4.24 Verify Main FDW operating 4.25 Verify any RCP operating 4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete RNO: Ensure SGs approaching 25 - 35 [55 - 65 acc] S/U level 4.27 Place switches in CLOSE:
__ 1FDW-31
__ 1FDW-40 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.
Page 26 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 2 Event No.: 7 Page 6 of 6 Event
Description:
ATWS (Loss of 1TA Switchgear) (M: ALL)
Time Position Applicants Actions or Behavior RULE 1 Crew response:
Rule 1 OATC 1. Verify any Power Range NI 5% FP
- 2. Initiate manual control rod insertion to the IN LIMIT
- 3. Verify Main FDW is feeding the SGs
- 4. Notify CRS to GO TO UNPP tab (Page 23)
- 5. Open:
__ 1HP-24
__ 1HP-25
- 6. Ensure at least one operating:
__ 1A HPI PUMP
__ 1B HPI PUMP
- 7. Start 1C HPI PUMP
- 8. Open:
__ 1HP-26 [1HP-26 will NOT open]
__ 1HP-27 RNO: 1. IF 1HP-26 will NOT open, THEN open 1HP-410
A. Start the standby HPI pump B. Stop 1C HPI pump C. Open 1HP-409 CT-3 9. Dispatch one operator without wearing Arc Flash PPE to open 600V CRD breakers:
__ 1X9-5C (U-1 CRD Norm Fdr Bkr) (U1 Equipment Rm)
__ 2X1-5B (U-1 CRD Alternate Fdr Bkr) (T-3/Dd-28)
(BOUNDING CRITERIA: Take the Reactor subcritical prior to exiting the UNPP Tab (<1% on WR Nis))
Examiner Note: When the operator is dispatched to open CRD breakers, TIMER 7A will be activated to open the CRD breakers in 4 minutes.
- 10. Verify only two HPI pumps operating
- 11. EXIT This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.
Page 27 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control Rev 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.
- 1. __ Utilize the following as necessary to __ IF 1HP-26 will NOT open, maintain desired Pzr level: THEN throttle 1HP-410 to maintain
- 1A HPI Pump desired Pzr level.
- 1B HPI Pump
- 1HP-120 setpoint or valve demand
- 2. __ IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.
- 3. __ IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.
- 4. __ IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:
A. Open:
1CS-26 1CS-41 B. Position 1HP-14 to BLEED.
C. Notify SRO.
- 5. __ IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.
Page 28 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. __ IAAT 1C HPI PUMP is required, __ GO TO Step 10.
THEN perform Steps 7 - 9.
- 7. Open: 1. __ IF both BWST suction valves
- 1HP-25 following:
A. Start 1A LPI PUMP.
B. Start 1B LPI PUMP.
C. Open:
1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. GO TO Step 8.
A.__ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.
B.__ IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C. GO TO Step 9.
Page 29 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. Start 1C HPI PUMP. __ IF at least two HPI pumps are operating, THEN throttle 1HP-409 to maintain desired Pzr level.
- 9. Throttle the following as required to 1. IF at least two HPI pumps are operating, maintain desired Pzr level: AND 1HP-26 will NOT open,
__ 1HP-26 THEN throttle 1HP-410 to maintain desired Pzr level.
- 2. __ IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.
Page 30 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. __ IAAT LDST level CANNOT be __ GO TO Step 12.
maintained, THEN perform Step 11.
- 11. Perform the following: 1. __ IF both BWST suction valves
- Open 1HP-25.
B. Start 1B LPI PUMP.
C. Open:
1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 13.
- 2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP.
NOTE Maintaining Pzr level > 100 [180 acc] will ensure Pzr heater bundles remain covered.
12.__ Operate Pzr heaters as required to maintain heater bundle integrity.
Page 31 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. __ IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
- 14. __ IAAT two Letdown Filters are desired, THEN perform the following:
Open 1HP-17.
Open 1HP-18
- 15. IAAT all of the following exist: GO TO Step 35.
Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41}
- 16. Open: 1. __ Notify CR SRO that letdown CANNOT
__ 1CC-7 be restored due to inability to restart the
- 2. __ GO TO Step 35.
- 17. __ Ensure only one CC pump running.
- 18. __ Place the non-running CC pump in AUTO.
__ 1HP-1 close,
__ 1HP-2 THEN GO TO Step 21.
- 20. GO TO Step 23.
NOTE Verification of leakage requires visual observation of East Penetration Room.
- 21. Verify letdown line leak in East GO TO Step 23.
Penetration Room has occurred.
- 22. GO TO Step 35.
Page 32 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 23. __ Monitor for unexpected conditions while restoring letdown.
- 24. Verify both letdown coolers to be 1. __ IF 1A letdown cooler is to be placed in placed in service. service, THEN open:
1HP-1 1HP-3
- 2. __ IF 1B letdown cooler is to be placed in service, THEN open:
1HP-2 1HP-4
- 3. __ GO TO Step 26.
- 25. Open:
- 26. __ Verify at least one letdown cooler is Perform the following:
aligned. A. __ Notify CR SRO of problem.
B. __ GO TO Step 35.
- 27. __ Close 1HP-6.
- 28. __ Close 1HP-7.
- 29. __ Verify letdown temperature < 125°F. 1. __ Open 1HP-13.
- 2. Close:
1HP-8 1HP-9&11
- 3. __ IF any deborating IX is in service, THEN perform the following:
A. Select 1HP-14 to NORMAL.
B. Close 1HP-16.
- 4. __ Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Page 33 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 30. Open 1HP-5.
- 31. Adjust 1HP-7 for 20 gpm letdown.
- 32. WHEN letdown temperature is
< 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.
- 33. Open 1HP-6.
- 34. __ Adjust 1HP-7 to control desired letdown flow.
NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.
- 35. __ IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).
- 36. __ IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
A. __ Obtain SRO concurrence to reduce running HPI pumps.
B. Secure the desired HPI pumps.
C. __ Place secured HPI pump switch in AUTO, if desired.
- 37. IAAT all the following conditions exist:
Makeup from BWST NOT required LDST level > 55 All control rods inserted Cooldown Plateau NOT being used THEN close:
1HP-24 1HP-25 Page 34 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 38. Verify 1CS-48 (1A BHUT Recirc) has __ GO TO Step 40.
been closed to provide additional makeup flow to LDST.
- 39. __ WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:
A. __ Stop 1A BLEED TRANSFER PUMP.
B. __ Locally position 1CS-48 (1A BHUT Recirc) one turn open (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
C. Close 1CS-46.
D. __ Start 1A BLEED TRANSFER PUMP.
E. __ Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 - 110 psig discharge pressure.
F. __ Stop 1A BLEED TRANSFER PUMP.
- 40. Verify two Letdown Filters in service, __ GO TO Step 42.
AND only one Letdown filter is desired.
- 41. Perform one of the following:
Place 1HP-17 switch to CLOSE.
Place 1HP-18 switch to CLOSE.
- 42. __ WHEN directed by CR SRO, THEN EXIT this enclosure.
- *
- END * *
- Page 35 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Rule 6 Rev 03 HPI HPI Pump Throttling Limits
- HPI must be throttled to prevent violating the RV-P/T limit.
- HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.
- HPI must be throttled 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.
- Total HPI flow must be throttled 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.
- Total HPI flow must be throttled < 750 gpm when all the following exist:
- LPI suction is from the RBES
- piggyback is aligned
- either of the following exist:
- only one LPI pump operating
- HPI may be throttled under the following conditions:
HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress:
All the following conditions must exist: All the following conditions must exist:
- Core SCM > 0
- All WR NIs 1%
- CETCs decreasing
- Core SCM > 0
- Pzr level increasing
- Maintain 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Page 36 of 38
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam CRITICAL TASKS CT-1 Start Standby CC Pump prior to reaching 2 or more CRD temperatures of 180°F (page 6)
CT-2 Lockout EHC Pumps to trip the Main Turbine prior to entry into PTS conditions (cooldown to < 400°F at > 100°F/hour) (page 23)
CT-3 Prior to exiting the UNPP tab, take the Reactor subcritical (i.e. < 1% power on WR NIs) (page 27)
Page 37 of 38
SAFETY: Take a Minute UNIT 0 (SM)
SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No PSW Operable: Yes UNIT STATUS (CRS)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 97% Mode: 1 Mode: 1 Gross MWE: 829 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CRS)
Component/Train OOS Restoration TS/SLC #
Date/Time Required Date/Time AMSAC/DSS Today / 0300 7 Days SLC 16.7.2 LEE/CENTRAL Alternate Today / 0500 N/A SLC 16.8.6 Power Path Shift Turnover Items (CRS)
Primary
- SASS is in Manual for calibration
- Rx power 97% stable and ready to perform PT/1/A/0290/003 (Turbine Valve Movement) Encl 13.2 for CV3 & CV4 only. Encl. 13.2 (Control Valve Movement at Power) is in progress and complete up to Step 2.5
- Unit 1 will be maintaining 97% until Rx Engineering updates the maneuvering plan Secondary
- AMSAC/DSS bypassed for calibration
- 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.
Electrical
Gp 7 Rod Position: Batch additions as required for volume RCS Boron 43 ppmB 89% Withdrawn control. (OATC)
Human Performance Emphasis (SM)
Procedure Use and Adherence
Appendix D Scenario Outline Form ES D-1 ILT 20-1 NRC Exam Facility: Oconee Scenario No.: 3 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________ SRO
________________________ ________________________ OATC
________________________ ________________________ BOP Initial Conditions:
- Reactor Power = Critical below POAH Turnover:
- U1 RBNS level high. Lower RBNS level to ~3 per OP/1/A/1104/007 Encl 4.1
- Unit startup in progress. Raise Reactor power from below the POAH to 3.0% and place ICS in Auto per OP/1/A/1102/001 Encl 4.7 Event Malfunction Event Event Type* Description No. No.
1 Override C: BOP, SRO (TS) Pump the RBNS 2 R: OATC, SRO Raise Power to 3.0% and Place ICS in Auto 3 Override C: BOP, SRO 1B FWPT Auxiliary Oil Pump Trip 4 Override C: BOP, SRO (TS) A LPSW Pump OB Bearing Temperature High 5 SRO (TS) TD EFDWP Oil Sump Dry 6 Override C: OATC, SRO 1RC-1 (PZR Spray Valve) Fails Open MCR022 Two Dropped Control Rod(s) Requiring a Reactor 7 MCR028 C: OATC, SRO Trip Small Break LOCA that evolves into a Large Break MPS400 LOCA (CT-1, CT-3) 8 MPS400D M: ALL
- 1A LPI Pump Fails Override
- 1B LPI Pump Fails (requires 1C LPIP alignment) (CT-2)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam SCENARIO 3 EVENT
SUMMARY
Event 1: When the crew takes the shift, the SRO will direct the BOP will lower the level in the RBNS to ~ 3 inches using OP/1/A/1104/007 Enclosure 4.1. 1LWD-1 will fail open requiring TS 3.6.3 entry.
Event 2: The OATC will raise power from below the POAH to 3.0% and place ICS in automatic.
Event 3: The Auxiliary Oil Pump for the 1B FWPT will trip causing the Emergency Oil Pump to start. Per the Alarm Response Guide (ARG), the BOP will attempt to start the Auxiliary Oil Pump, which will fail. Shortly afterwards, the alarm for FWPT 1B Emergency Oil Pump Overload will alarm. This will require the candidate to attempt to start the Auxiliary Oil Pump. Not being able to start the pump, the ARG will direct the BOP to stop the Turning Gear Motor to prevent damaging the Feedwater Pump.
Event 4: An OAC alarm will indicate that the A LPSW pump Outboard Bearing temperature is high. The BOP will refer to the alarm response which will refer to OP/1/A/1104/010 (Low Pressure Service Water) to secure the pump. Enclosure 4.39 (LPSW Pump Operations) will be used to start the C LPSW pump and secure the A LPSW pump.
The SRO will refer to TS 3.7.7.
Event 5: The Work Control Center SRO will contact the control room stating that an AO reports that the Turbine Driven Emergency FDW Pump oil sump indicates no oil on the dipstick. The SRO should direct the OATC to place the TD EFDW pump switch in Pull To Lock (PTL). The SRO will enter TS 3.7.5 for an inoperable TD EFDW Pump and TS 3.3.14 once the TD EFDW switch is in Pull To Lock (PTL).
Event 6: The 1RC-1 (Pressurize Spray Valve) will fail open causing RCS pressure to unexpectedly decrease. The operator will be required to close 1RC-3 (Pressurizer Spray Block Valve) in order to stop the pressure decrease and prevent tripping the Reactor.
Event 7: Two control rods will drop into the core requiring a manual Reactor trip. Once the Reactor is manually tripped in accordance with AD-OP-ONS-0002 Attachment 1 (Licensed Operator Memory Items), Event 8 will automatically initiate.
Event 8: Upon receiving a Reactor Trip, a Small Break LOCA will develop. Following the completion of Rule 2, the leak evolves into a Large Break LOCA. The 1A and 1B LPI Pumps will fail requiring the operator to manually align and start the 1C LPI Pump to maintain core cooling.
Page 2 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 1 Page 1 of 1 Event
Description:
Lower RBNS level to ~ 3 inches (C: BOP, SRO)
Time Position Applicant's Actions or Behavior OP/1/A/1104/007 Encl 4.1 Crew response:
SRO directs the BOP to pump the Reactor Building Normal Sump to approximately 3 inches in accordance with OP/1/A/1104/007 Enclosure 4.1.
BOP OP/1/A/1104/007, Encl. 4.1 (Pumping RBNS to 1 inch) rev 30 2.1 Verify required to lower RBNS to 1 3.1 Verify MWHUT level adequate to receive waste volume.
3.2 Position the following:
RIA Alarms may be indicative of gas leakage.
If RBNS level was above 14" when pumps were started, a level increase following securing the RBNS pumps may occur.
During outages, it is desirable to maintain RBNS > 6 for shielding to decrease dose rates in RBNS area.
3.4 WHEN RBNS is at desired level OR at 1" (low level alarm), ensure the following:
3.5 IF required to close the valves, position the following:
SRO TS 3.6.3 (Containment Isolation Valves)
Condition A (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
AND (31 Days) Verify the affected penetration flow path is isolated.
This event is complete when CRS has evaluated TS 3.6.3, or when directed by the Lead Examiner.
Page 3 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 2 Page 1 of 2 Event
Description:
Increase Power to 3% and Place ICS in Auto (R: OATC, SRO)
Time Position Applicant's Actions or Behavior Examiner Note: During the power increase, the Unit 2 CRS will have oversight of the Control Room and the Unit 1 CRS will assume the role of the dedicated Reactivity SRO.
SRO Examiner Cue: If the crew asks whether they should increase power, respond as the SM and notify the crew to continue the power increase as directed on the Turnover sheet.
OP/1/A/1102/001 Encl 4.7 Crew Response:
- SRO directs the OATC to increase power to 3% using OP/1/A/1102/001 (Controlling Procedure for Unit Startup), Encl. 4.7, starting at step 3.38 OP/1/A/1102/001 (Controlling Procedure for Unit Startup) Encl. 4.7 Step 3.38 rev 317 NOTE:
- Point Of Adding Heat (POAH) is normally achieved from 0.05 to 0.15% power on Wide Range Indications
- When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, and SUR will decrease with OATC negative Moderator Temperature Coefficient
- Wide Range indications are used since Source Range NIs saturate 3.38 Begin reactor power increase to 0.5 - 1.0 % at 0.5 DPM SUR 3.39 WHEN above POAH, begin reactor power increase to 2.5 - 3.5%
3.40 WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215" to 225" PZR Level NOTE:
- TAVE error is blocked when on Low Level Limit and TAVE is
< setpoint
- Core reactivity effects are minimized with Rx in automatic 3.41 WHEN at 2.5 - 3.5 % Power, perform the following: (R.M.)
3.41.1 Ensure TURBINE MASTER Setpoint to 880-890 psig.
3.41.2 WHEN Turbine Header pressure has reached setpoint, perform the following:
A. Place DIAMOND to "AUTO" B. Place REACTOR MASTER to AUTO 3.42 Perform the following:
- Ensure complete Enclosure "Prior To Entry Into MODE 1" of PT/1/A/0630/001 (Mode Change Verification)
- Review mechanical maneuvering rates and allowable ramp rates in PT/0/A/1103/020 (Power Maneuvering Guidelines)
This event is complete when power is 3% and ICS is in Auto (Step 3.41), or when directed by the Lead Examiner.
Page 4 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 2 Page 2 of 2 Event
Description:
Increase Power to 3% and Place ICS in Auto (R: OATC, SRO)
Time Position Applicant's Actions or Behavior OP/1/A/1102/001 Encl 4.7 Crew Response:
OATC 3.43 IF AT ANY TIME all the following:
- All operable T Cold indications > 550°F
- SSF inoperable only due to low decay heat, Notify SM the SSF is Available for Unit 1 SM notified:______________________ Time/Date:_______________
3.44 Ensure acceptable point status for plant startup for MODE 1:
- OAC Alarm Screen Review
- OAC Point Processing Log
- Statalarms in alarm
- Statalarms removed from service This event is complete when power is 3% and ICS is in Auto (Step 3.41), or when directed by the Lead Examiner.
Page 5 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 3 Page 1 of 2 Event
Description:
1B FWPT Auxiliary Oil Pump Trip (C: BOP, SRO)
Time Position Applicant's Actions or Behavior Plant Response:
- 1SA-8/C-6 FWPT B EMERGENCY OIL PUMP RUN in alarm
- FWPT B Emergency Oil Pump starts Crew Response:
SRO/BOP SRO will direct the BOP to refer to 1SA-08/C-6 1SA-08/C-6 1SA-08/C-6 FWPT B EMERGENCY OIL PUMP RUN rev 39 3.1 Verify 1B FWPT Emergency Oil Pump is running 3.2 IF applicable, verify 1B FWPT is still on turning gear [It will be]
3.3 Try to restart 1B FWPT auxiliary oil pump [It will fail to start]
3.4 IF restart fails, notify Maintenance for repairs Examiner Note: Approximately 3 minutes after activating timer 3, the Emergency Oil Pump will trip and cause 1SA-08/C-7, (FWPT B EMERGENCY OIL PUMP OVERLOAD) to alarm.
Booth Cue: If dispatched as an AO to investigate 1B FWPT, once the EBOP has tripped, notify the crew that all oil pumps are off and the FWPT is on the turning gear. Report that the TG motor is much noisier than normal.
1SA-08/C-7 1SA-08/C-7 FWPT B EMERGENCY OIL PUMP OVERLOAD 3.1 IF available, start Auxiliary Oil Pump and stop Emergency Oil Pump 3.2 IF AOP is NOT available, stop Turning Gear Motor and Emergency Bearing Oil Pumps 3.3 Notify Maintenance for repairs 3.4 As soon as EBOP OR Auxiliary Oil Pump becomes available, start pump and place Turbine on Turning Gear This event is complete when Turning Gear Motor is secured, or as directed by the Lead Examiner.
Page 6 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 3 Page 2 of 2 Event
Description:
1B FWPT Auxiliary Oil Pump Trip (C: BOP, SRO)
Time Position Applicant's Actions or Behavior 1SA-08/E-6 Examiner Note: Bearing temperature alarms on 1B FWPT are due to loss of cooling since the oil pumps are secured. The alarms will take several minutes to come in after all lube oil pumps are secured.
1SA-08/E-6 FWPT B HP/LP BEARING DRAIN TEMPERATURE HIGH SRO/BOP 3.1 Verify bearing drain temperature is high using a surface pyrometer OR by feeling drain piping.
3.2 Manually open 1RCW-64 (FWPT Oil Cooler 1B Temperature Control Bypass) and regulate to control bearing oil temperature less that 180°F, avoiding any rapid change of oil temperature. Do NOT exceed 50°F T across bearing.
3.3 Check 1B FWPT bearing for excessive vibration.
3.4 IF the automatic temperature controller appears to be malfunctioning, operate the manual bypass until repairs can be completed.
3.5 IF Cooler appears to be dirty, valve in Spare Cooler.
3.6 Ensure that the supplemental temporary cooler for FWPT Oil Cooler 1B is installed AND placed in service, as needed, to control oil cooler discharge temperature per MP/0/A/3007/088 (Temporary Cooling of FDWPT Oil with Air Cooled Cooler).
3.7 IF bearing oil temperature CANNOT be maintained below 180°F, remove 1B FWPT from service per OP/1/A/1106/002 B (FDWPT Operation) and repair system.
3.8 Refer to OP/1/A/1102/004 (Operation at Power).
This event is complete when Turning Gear Motor is secured, or as directed by the Lead Examiner.
Page 7 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 4 Page 1 of 2 Event
Description:
A LPSW Pump OB Bearing Temperature High (C: BOP, SRO) (TS)
Time Position Applicant's Actions or Behavior Plant response:
- OAC Alarm O1A1336 (LPSW PUMP A OB BEARING TEMP)
Crew response:
BOP The BOP will refer to OAC alarm response for O1A1336 HI-HI - If non-emergency:
- 1) Refer to OP/1/A/1104/010 (Low Pressure Service Water) to remove 1A LPSW Pump from service
- 2) Refer to TS 3.7.7
- 3) Notify system engineer If emergency situation:
- 1) Evaluate removing the 1A LPSW Pump from service HI -
- 1) Display graphic for A LPSW pump and monitor temperature
- 2) Dispatch operator to check pump oil levels Booth Cue: If contacted as an AO and/or maintenance to investigate the A LPSW pump OB bearing temperature, wait 2 minutes and notify the crew that the A LPSW pump OB bearing temperature is very hot to the touch.
OP/1/A/1104/010 Enclosure 4.39 OP/1/A/1104/010 (Low Pressure Service Water) Enclosure 4.39 (LPSW Pump Operations rev 151 1.1 Review Limits and Precautions NOTE: LPSW Leakage Accumulator level is a function of LPSW System pressure. When an additional LPSW Pump is started, LPSW Leakage Accumulator level will increase and may exceed the limits of SR 3.7.7.1 until the pump swap is complete. As a result, momentary entry into TS 3.7.7 Condition 'B' may be necessary.
2.1 IF in MODE 1, 2, 3, OR 4, enter TS 3.7.7 Condition 'B' for the following:
__ Unit 1
__ Unit 2 This event is complete when the A LPSW pump is secured and C LPSW pump is started, or as directed by the Lead Examiner.
Page 8 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 4 Page 2 of 2 Event
Description:
A LPSW Pump OB Bearing Temperature High (C: BOP, SRO) (TS)
Time Position Applicant's Actions or Behavior OP/1/A/1104/010 Enclosure 4.39 Crew response:
OP/1/A/1104/010 (Low Pressure Service Water) Enclosure 4.39 (LPSW Pump Operations rev 151 BOP 2.2 Perform appropriate section as required 2.3 Notify CRS to evaluate exiting TS 3.7.7 Condition 'B'
- 5. To Swap LPSW Pumps 5.1 Start _____ LPSW Pump 5.2 Verify proper operation of LPSW Pump started 5.3 Stop _____ LPSW Pump TS 3.7.7 (LOW PRESSURE SERVICE WATER SYSTEM)
SRO Condition A (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) Restore required LPSW pump to OPERABLE status.
Condition B (7 days) Restore the LPSW WPS to OPERABLE status.
Examiner Note: The crew may decide to place the Standby LPSW Auto-Start Circuit in Disable which would require entry into TS 3.3.28. This is up to the discretion of the SRO.
TS 3.3.28 (LOW PRESSURE SERVICE WATER (LPSW) STANDBY PUMP AUTO-START CIRCUITRY Condition A (7 days) Restore LPSW standby pump auto-start circuitry to OPERABLE status.
This event is complete when the A LPSW pump is secured and C LPSW pump is started, or as directed by the Lead Examiner.
Page 9 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 5 Page 1 of 1 Event
Description:
TD EFDWP oil sump dry (SRO) (TS)
Time Position Applicant's Actions or Behavior Plant response:
Simulator Operator calls the Control Room as the WCC SRO and reports that the Basement AO found the Unit 1 TD EFDWP oil sump with no oil indicating on the dipstick. Report that the WCC and maintenance are investigating the situation to determine the cause of the problem. No oil has been found leaking from any equipment.
Crew response:
- SRO should make the decision to place TD EFDWP in Pull to Lock SRO TS 3.3.14 EMERGENCY FEEDWATER (EFW) PUMP INITIATION CIRCUITRY (applies when the TD EFDWP is placed in PTL)
Condition B - (Immediately) Declare the affected EFW pump inoperable TS 3.7.5 EMERGENCY FEEDWATER (EFW) SYSTEM Condition B - (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) Restore turbine driven EFW pump and EFW flow path to OPERABLE status
- Declare the affected EFWP inoperable Immediately
- SRO refer to TS 3.7.5 Condition B Restore TD EFDWP within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Booth Cue: If asked, inform crew that the TD EFDWP was placed on the oil purifier last shift.
Examiner Note: The SRO may direct an RO to place the TD EFDW pump in Pull-To-Lock per AD-OP-ALL-1000 Step 5.6.3.3.b 5.6.3 Common Tasks
- 3. Written procedures are not necessary for situations where:
- b. Prompt action is necessary to prevent the deterioration of plant conditions or components to a possibly unsafe or unstable level. If time permits, approval from the SM/CRS shall be obtained.
Booth Cue: If crew does not place TD EFDWP in PTL, then at direction of Lead Examiner, call as WCC SRO and direct the crew to place Unit 1 TDEFDWP switch in PTL per R&R.
This event is complete when the Tech Spec determination has been made or when directed by the Lead Examiner.
Page 10 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 6 Page 1 of 3 Event
Description:
Spray Valve Fails Open (C: OATC, SRO)
Time Position Applicant's Actions or Behavior AP/1/A/1700/044 Plant Response:
- 1RC-1 indicates open
- O1D1047 1RC-1 PZR Spray Control Valve Not Closed
- RCS pressure decreasing Crew Response:
- OATC should recognize that RCS pressure is below the Pzr Spray Valve setpoint (2155 psig) and attempt to close the Pzr Spray Valve (1RC-1).
SRO/OATC When this doesnt work, the OATC should close Pzr Spray Block Valve (1RC-3). These are Immediate Manual Actions from AP/44 Abnormal Pressurizer Pressure Control.
- SRO should enter AP/1/A/1700/044 AP/1/A/1700/044 Abnormal Pressurizer Pressure Control rev 04 Immediate Manual Actions 3.1 IAAT PORV is open, AND RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)), THEN close 1RC-4 (N/A) 3.2 IAAT RC pressure < 2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE (Wont close) 3.3 IAAT all the following conditions exist:
__ RC pressure < 2155 psig
__ RC pressure decreasing without a corresponding decrease in PZR level THEN close 1RC-3 Subsequent Actions 4.1 Announce AP entry using the PA system 4.2 GO TO the applicable step per the following table:
Failure Caused Step RCS Pressure Decrease 4.3 Increase 4.18 This event is complete when 1RC-3 is closed and RCS pressure is stable, or as directed by the Lead Examiner.
Page 11 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 6 Page 2 of 3 Event
Description:
Spray Valve Fails Open (C: OATC, SRO)
Time Position Applicant's Actions or Behavior AP/1/A/1700/044 Crew Response:
4.3 Verify 1RC-4 is closed SRO/OATC RNO: IF PORV is open, AND 1RC-4 has failed to close, THEN perform the following:
A. Dispatch an operator to open 1DIB Panelboard breaker #24 B. Manually trip the reactor C. Initiate AP/02 (Excessive RCS Leakage) 4.4 Verify 1RC-3 is closed NOTE 1RC-3 must NOT be allowed to be closed for 36 minutes at a time to avoid a thermal transient in piping between 1RC-3 and the PZR spray nozzle.
4.5 Position 1RC-3 as required to maintain RC pressure within desired band 4.6 GO TO Step 4.13 4.13 Verify PZR heaters maintaining RCS pressure within desired band 4.14 Notify SPOC to repair malfunctioning component This event is complete when 1RC-3 is closed and RCS pressure is stable, or as directed by the Lead Examiner.
Page 12 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 6 Page 3 of 3 Event
Description:
Spray Valve Fails Open (C: OATC, SRO)
Time Position Applicant's Actions or Behavior AP/1/A/1700/044 Crew Response:
4.15 Ensure requirements of following are met:
SRO/OATC
__ TS 3.4.1 (RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits)
__ TS 3.4.9 (Pressurizer)
__ TS 3.4.12 (Low Temperature Overpressure Protection System)
__ SLC 16.5.1 (Reactor Coolant System Vents) 4.16 WHEN repairs complete, THEN place following components in desired position for current plant conditions as determined by CR SRO:
__ 1RC-1
__ 1RC-3
__ 1RC-4
__ PZR heater bank #1
__ PZR heater bank #2
__ PZR heater bank #3
__ PZR heater bank #4 4.17 WHEN directed by CR SRO, THEN EXIT this procedure This event is complete when 1RC-3 is closed and RCS pressure is stable, or as directed by the Lead Examiner.
Page 13 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 7 Page 1 of 1 Event
Description:
Two Dropped Control Rod(s) Requiring a Reactor Trip (C: OATC, SRO)
Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Plant Response:
SRO/OATC
- Group 6 Rod 3 drops into the core
- Group 6 Rod 6 drops into the core
Crew Response:
- Crew should recognize 2 dropped control rods and trip the reactor in accordance with AD-OP-ONS-0002 (OCONEE SPECIFIC ABNORMAL OPERATIONS GUIDANCE)
Examiner Note: Event 8 will auto actuate when the Reactor is tripped.
If the crew does not recognize the 2nd dropped control rod, they will enter AP/1/A/1700/001 (Unit Runback)
AP/1/A/1700/001 (Unit Runback) rev16 NOTE
- If more than one runback condition exists, ICS will respond by selecting the fastest runback rate and the lowest load limit. The most limiting runback will be the one with the fastest runback rate and the shortest duration.
- It is possible for a FDWP to become unable to feed the SGs but not be tripped. In this case a signal would not be sent to RPS or the EFDWP start circuit.
4.1 GO TO the most limiting section per the following table:
4H Asymmetric Control Rod (1% / min to 55% power)
AP/1A/1700/001 Section 4H (Asymmetric Control Rod)
- 1. IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1.
- 2. IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx.
This event is complete when the Reactor is manually tripped, or as directed by the Lead Examiner.
Page 14 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 1 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Crew Response:
The SRO will direct the BOP to perform a Symptoms Check (AD-OP-ONS-SRO/BOP 0002)
Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Power Range NIs NOT decreasing Power Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation Rule 4, Initiation of HPI Forced of EFDW) Cooling (Inability to feed SGs and >
2300 psig, NDT limit reached, or PZR level > 375")
Uncontrolled Main steam line(s) Rule 5, Main Steam Line Break pressure decrease CSAE Offgas alarms None (SGTR Tab is entered when Process monitor alarms (RIA-40, identified SG Tube Leakage > 25 59,60), gpm)
Area monitor alarms (RIA-16/17)
After verifying IMAs, the SRO will transfer to the Subsequent Actions Tab and review the Parallel Action page. (page 28)
Examiner Note: Core SCM will indicate 0°F or superheated during this transient depending on when CFTs and LPI flow injects into the core. When the SRO reaches the decision point in the SA parallel action page, if superheated he should transfer to the Inadequate Core Cooling (ICC) tab (page 19) or if saturated, he should transfer to the Loss of Subcooling Margin (LOSCM) tab (next page).
The SRO will direct one of the ROs to perform Rule 2 (Loss of SCM) (page 23) and (Enclosure 5.1 (ES Actuation) (page 32)
Examiner Note: Following the completion of Rule 2, at Lead Examiners direction, the Small Break LOCA will transition to a Large Break LOCA.
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 15 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 2 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior LOSCM Tab Crew Response:
LOSCM Tab Rev. 01 SRO
- 1. Ensure Rule 2 (Loss of SCM) is in progress or complete.
- 2. Verify LOSCM caused by excessive heat transfer.
RNO: GO TO Step 4.
- 4. IAAT either exists:
THEN GO TO LOCA CD tab. (page 22)
- 5. Verify SSF activated per AP/25 with SSF RC Makeup required.
RNO: GO TO Step 7.
- 7. Verify all exist:
- NO RCPs operating
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 16 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 3 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior LOSCM Tab Crew Response:
LOSCM tab (continued) 8 GO TO Step 104.
104. Open 1AS-40 while closing 1MS-47.
105. Verify HPI forced cooling in progress.
RNO: Close 1RC-4 106. Close 1GWD-17, 1HP-1, 1HP-2, and 1RC-3 107. Verify either:
- Core superheated
- Rx vessel head level at 0 RNO: GO TO Step 109 OATC 109. IAAT BWST level is 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).
CAUTION If TDEFDWP is being used for SG feed, reducing SG pressure below 250 psig can result in reduced pumping capability 110. Maintain SG pressure < RCS pressure utilizing either:
__ TBVs BOP __ ADVs 111. Verify any SG available for feeding/steaming.
112. Initiate Encl 5.16 (SG Tube-to-Shell T Control).
113. Verify indications of SGTR exist.
RNO: GO TO Step 116 116. Verify HPI forced cooling in progress.
RNO: GO TO Step 118 This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 17 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 4 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior LOSCM Tab Crew Response:
NOTE If in boiler condenser cooling, the CETCs may have a saw tooth pattern, sometimes increasing and sometimes decreasing. The overall trend should be used to make this determination.
118. Verify CETCs trend decreasing.
119. Verify primary to secondary heat transfer is excessive.
RNO: GO TO Step 121 121. Verify indications of SGTR 25 gpm.
RNO: GO TO Step 123 123. Verify required RCS makeup flow within normal makeup capability.
RNO: GO TO LOCA CD tab (page 22)
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 18 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 5 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior ICC Tab Crew Response:
ICC Tab (ICC Parallel Actions on page 31) Rev. 02 SRO/OATC CAUTION ICC conditions should not exist unless multiple equipment and system failures have occurred. Some of the equipment used in this section may be the same equipment that has failed. It is expected that attempts to restore equipment operations will continue throughout this section. It is also expected that transition to OSAG will occur whenever conditions requiring the transition exist.
- 1. IAAT CETCs > 1200oF, THEN GO TO EG/1/A/OSAM/SAG-1 (Main Control Room Severe Accident Guideline Initial Response)
- 4. Open:
__ 1LP-21
__ 1LP-17
RNO: 1. IF 1C LPI Pump is operating, THEN GO TO Step 8.
- 2. Close 1LP-17.
- 6. Open:
__ 1LP-22
__ 1LP-18
RNO: 1. IF 1C LPI Pump is operating, THEN GO TO Step 8.
- 2. Close 1LP-18
- 8. Verify two LPI pumps operating.
RNO: IF LPI/HPI piggyback is aligned, THEN maximize total LPI flow by throttling HPI flow as follows: (N/A)
- 1C LPI pump only < 2900 gpm
- 1A or 1B LPI pump only < 3100 gpm This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 19 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 6 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Crew Response: ICC Tab
- 9. IAAT all exist:
__ 1C LPI Pump off
__ 1C LPI Pump available
__ LPI required
__ ECCS pump suction aligned to BWST
__ 1A LPI Pump unavailable
__ 1B LPI Pump unavailable THEN perform Steps 10-13.
RNO: GO TO Step 14
- 10. Open:
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7
__ 1LP-17
__ 1LP-18
__ 1LP-21
__ 1LP-22
RNO: GO TO Step 14
- 14. Verify open:
__ 1CF-1
__ 1CF-2 RNO: IF CFTs NOT isolated for nitrogen injection considerations, THEN open:
__ 1CF-1
__ 1CF-2
- 15. IAAT core SCM is 0°F, THEN GO TO LOCA CD tab (page 21)
Note: Core SCM will return to 0°F at some point after LPI flow has been established.
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 20 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 7 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Crew Response: ICC Tab
- 16. IAAT any injection sources available:
__ Full flow from at least one HPI pump exists
__ LPI available
__ CFTs available THEN perform Steps 17 - 19
- 17. Open:
__ 1RC-4
__ PORV
- 18. Locally close breakers (Unit 1 Cable Room):
- 19. Open:
__ 1RC-155
__ 1RC-156
__ 1RC-157
__ 1RC-158
__ 1RC-159
__ 1RC-160
- 20. Close:
__ 1GWD-17
__ 1HP-1
__ 1HP-2
__ 1RC-3
- 21. IAAT SSF-ASW is the only source available to feed SGs (N/A)
AND any of the following exists: (N/A - RNO GO TO Step 28)
__ Unit 1 EFDW available
__ EFDW aligned from another unit
__ Main FDW available THEN perform steps 23 - 27.
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 21 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 8 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior LOCA Cooldown Tab Crew Response:
LOCA COOLDOWN Tab Rev 0
- 1. IAAT BWST level is 19, THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).
- 2. Verify ES actuated.
- 3. GO TO Step 7.
- 7. Perform the following:
- Ensure all RBCUs in low speed.
- Open 1LPSW-18
- Open 1LPSW-21
- Open 1LPSW-24
- 8. Initiate Encl 5.35 (Containment Isolation).
- 9. Start all RB Aux fans.
- 10. IAAT either of the following exists:
- 11. Stop all RCPs
- 12. Dispatch an operator to perform the following:
__ Remove white tag and close 1XO-F5C (1CF-1 Bkr (1A CFT Outlet))
__ Remove white tag and close 1XP-F5C (1CF-2 Bkr (1B CFT Outlet))
__ Close 1XS2-F3D (1LP-104 Bkr (Post LOCA Boron Dilute))
- 15. IAAT Spent Fuel Cooling indicates:
__ Abnormal temperature increase
__ Abnormal level change
__ Abnormal SFC flow THEN initiate AP/35
- 18. Initiate Encl 5.36 (Equipment Alignment for Plant Shutdown).
- 19. Verify core SCM < 0°F.
- 20. WHEN CETCs are < 400°F, THEN continue this procedure.
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 22 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 9 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Rule 2 Examiner Note: Following the completion of Rule 2, at Lead Examiners direction, the Small Break LOCA will transition to a Large Break LOCA.
Crew Response:
Rule 2 LOSCM Rev 03 CT-1 1. IAAT all exist:
- Any SCM 0°F
- Rx power 1%
- 2 minutes elapsed since loss of SCM THEN perform Steps 2 and 3.
- 2. Stop all RCPs.
(Bounding Criteria: within 2 minutes of Loss of SCM)
- 4. Verify Blackout exists.
RNO: GO TO Step 6.
- 6. Open:
- 7. Start all available HPI pumps.
- 8. GO TO Step 13.
- 13. Open:
- 14. Verify at least two HPI pumps are operating using two diverse indications.
- 15. IAAT 2 HPI pumps operating, AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps 16-21.
RNO: GO TO Step 17 This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 23 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 10 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Rule 2
- 16. Open in the affected header:
SRO/BOP 1A Header 1B Header 1HP-410 1HP-409
- 17. IAAT flow limits are exceeded, Pump Operation Limit 1HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI Total flow of 950 pumps operating gpm (incl. seal with 1HP-409 open injection)
THEN perform Steps 18-20.
RNO: GO TO Step 21.
- 18. Place Diverse HPI in BYPASS.
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 24 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 11 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Rule 2
- 19. Perform both:
SRO/BOP
- 20. Throttle HPI to maximize flow flow limit.
- 22. Verify RCS pressure > 550 psig.
RNO: Ensure ES Channels 3 and 4 actuated.
- 23. IAAT either exists:
RNO: GO TO Step 35. (see next page)
Examiner Note: If the 1C LPI pump has not yet been started per EOP Encl 5.1, LPI flow will be < 2900 gpm and the RO will perform the RNO step and continue to Step 35 (next page). Once it is recognized that LPI flow is 2900 gpm, the RO will return to IAAT Step 23 and then continue to Step 24.
Examiner Note: If the 1C LPI pump has been started by this point, LPI flow will be 2900 gpm and the RO will continue to Step 24 below.
- 24. Perform the following:
- Place 1FDW-315 in MANUAL and close.
- Place 1FDW-316 in MANUAL and close.
- Place 1FDW-35 in HAND and close.
- Place 1FDW-44 in HAND and close.
- 25. Notify crew that performance of Rule 3 is NOT required due to LBLOCA.
- 26. WHEN directed by CRS, THEN EXIT This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 25 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 12 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Rule 2
- 35. IAAT TBVs are unavailable, THEN: (does NOT apply)
SRO/BOP A. Dispatch two operators to perform Encl 5.24 (Operation of ADVs)
B. Notify CRS that ADVs are being aligned for use
- 36. Verify 1SA-2/C-8 (AFIS HEADER A INITIATIED) lit RNO: Select OFF for both digital channels on AFIS HEADER A
- 37. Verify 1SA-2/D-8 (AFIS HEADER B INITIATIED) lit RNO: Select OFF for both digital channels on AFIS HEADER B
- 38. Verify any EFDW pump operating RNO: Place in MANUAL and close:
__ 1FDW-315
__ 1FDW-316
__ 1A MD EFDWP
__ 1B MD EFDWP
- 40. Verify any EFDW pump operating
- 41. Verify both SGs intact
- 42. Establish 300 gpm EFDW flow to each SG:
__ 1A SG
__ 1B SG
- 43. Verify both MD EFDWPs operating
- 44. Place 1 TD EFDW PUMP in PULL TO LOCK
- 45. Trip both Main FDW pumps
- 46. Place FDW block valve switches in CLOSE:
__ 1FDW-33
__ 1FDW-31
__ 1FDW-42
__ 1FDW-40 This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 26 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Op-Test No.: ILT 20-1 Scenario No.: 3 Event No.: 8 Page 13 of 13 Event
Description:
Small Break LOCA that evolves into a Large Break LOCA (M: ALL)
Time Position Applicant's Actions or Behavior Rule 2 NOTE SRO/BOP
- TS cooldown rates are 50°F/1/2 hr when Tcold 270°F and 25°F/1/2 hr when Tcold < 270°F
- 47. Begin feeding all available SGs to the appropriate SG Level Control Point in Rule 7 (SG Feed Control) using available feed sources:
EFDW/Main FDW
- 48. IAAT SG Level Control Point is reached, THEN maintain SG Level Control Point by feeding and steaming as necessary
- 49. Notify CRS of SG feed status CAUTION If 1 TD EFDW PUMP is being used for SG feed and Unit 1 is supplying the Auxiliary Steam header, reducing SG pressure below 250 psig can result in reduced pumping capacity.
< RCS pressure using either:
__ TBVs
__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) (PS)
- 51. Verify any Main FDW pump operating RNO: GO TO Step 58
- 58. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete
- 59. WHEN directed by CRS, THEN EXIT Booth Cue: Following the completion of Rule 2, at Lead Examiners direction, ACTIVATE TIMER 08A to initiate a Large Break LOCA.
This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.
Page 27 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Subsequent Actions EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS
- 2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT
{13}
- 4. Any SCM = 0°F GO TO LOSCM tab. LOSCM
- 5. Both SGs intentionally isolated to GO TO EHT tab.
stop excessive heat transfer
- 6. Loss of heat transfer (including LOHT loss of all Main and Emergency GO TO LOHT tab.
FDW)
- 7. Heat transfer is or has been GO TO EHT tab. EHT excessive
- 9. Turbine Building flooding NOT GO TO TBF tab. TBF caused by rainfall event
- 12. Power lost to all 4160V SWGR
- Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).
re-energized ROP
- IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.
- 13. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.
- 14. Individual available to make
- Announce plant conditions using notifications PA system.
- Notify SM to reference the E- NOTIFY Plan and AD-LS-ALL-0006 (Notification/Reportability Evaluation).
- IF required, THEN notify Security to implement comp.
actions for SSF degrade Page 28 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam CONDITION ACTIONS
- 2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT
{13}
- 6. Power lost to all 4160V SWGR
- Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).
re-energized ROP
- IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.
- 7. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.
- 8. Individual available to make
- Announce plant conditions using notifications PA system.
- Notify SM to reference the NOTIFY Emergency Plan and AD-LS-ALL-0006 (Notification/Reportability Evaluation).
Page 29 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam CONDITION ACTIONS
- 2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT
{13}
- 6. Power lost to all 4160V SWGR
- Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).
re-energized ROP
- IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.
- 7. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.
- 8. Individual available to make
- Announce plant conditions using notifications PA system.
- Notify SM to reference the NOTIFY Emergency Plan and AD-LS-ALL-0006 (Notification/Reportability Evaluation).
Page 30 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Page 31 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
Actuation Associated ES Setpoint Channel (psig) 1600 (RCS) 1&2 550 (RCS) 3&4 3 (RB) 1, 2, 3, 4, 5, & 6 10 (RB) 7&8
- 2. Verify all ES channels associated with NOTE actuation setpoints have actuated. Voter OVERRIDE extinguishes the TRIPPED light on the associated channels that have auto actuated. Pressing TRIP on channels previously actuated will reposition components that may have been throttled or secured by this Enclosure.
Depress TRIP on affected ES logic channels that have NOT previously been actuated.
- 3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1 - 2.
NOTE
- 5. Perform both:
- Voter OVERRIDE affects all channels of the Place ES CH 1 in MANUAL. affected ODD and/or EVEN channels.
- In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch.
Page 32 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. IAAT all exist:
Voter associated with ES channel is in OVERRIDE An ES channel is manually actuated Components on that channel require manipulation THEN depress RESET on the required channel.
- 7. Verify Rule 2 in progress or complete. GO TO Step 74.
- 8. Verify any RCP operating. GO TO Step 10.
- 9. Open:
1HP-20 1HP-21
- 10. IAAT ES Channels 5 or 6 is actuated, GO TO Step 16.
THEN perform Steps 11 - 15.
- 11. Perform the following for actuated NOTE channels:
- Voter OVERRIDE affects all channels of the Place ES CH 5 in MANUAL. affected ODD and/or EVEN channels.
- In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch.
- 12. Verify any RCP is operating. GO TO Step 16.
- 13. Open:
- 14. Ensure only one CC pump operating.
- 15. Ensure Standby CC pump in AUTO.
Page 33 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. IAAT ES Channels 3 & 4 are actuated, GO TO Step 54.
THEN GO TO Step 17.
- Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels.
- In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch.
CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. {6}
- 19. IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22}
shutoff head, THEN perform Steps 21 - 22.
- 21. Perform the following: 1. Stop 1A LPI PUMP.
Start 1A LPI PUMP.
- 22. Perform the following: 1. Stop 1B LPI PUMP.
Start 1B LPI PUMP.
Page 34 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 23. IAAT 1A and 1B LPI PUMPs are GO TO Step 26.
off / tripped, AND all exist:
RCS pressure < LPI pump shutoff head 1LP-19 closed 1LP-20 closed THEN perform Steps 24 - 25.
- 24. Open:
1LP-9 1LP-10 1LP-6 1LP-7 1LP-17 1LP-18 1LP-21 1LP-22
- 25. Start 1C LPI PUMP.
CT-2 (Bounding Criteria: Start 1C LPIP prior to
- 26. IAAT 1A LPI PUMP fails while reaching 700F CETC) operating, AND 1B LPI PUMP is operating, THEN close 1LP-17.
- 28. Start:
A OUTSIDE AIR BOOSTER FAN CT-3 (Bounding Criteria: Start Outside Air Booster Fans within 30 minutes of a LOCA for Control B OUTSIDE AIR BOOSTER FAN Room Habitability)
- 29. Notify Unit 3 to start:
3A OUTSIDE AIR BOOSTER FAN 3B OUTSIDE AIR BOOSTER FAN Page 35 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. Close 1HP-120.
- 32. Secure makeup to the LDST.
- 33. Verify all ES channel 1 - 4 components 1. IF 1HP-3 fails to close, are in the ES position. THEN close 1HP-1.
1HP-228 1HP-226 1HP-232 1HP-230
- 4. Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.
- 34. Verify Unit 2 turbine tripped. GO TO Step 37.
- 35. Close 2LPSW-139.
- 36. Verify total LPSW flow to Unit 2 LPI Reduce LPSW to Unit 2 LPI coolers to coolers 6000 gpm. obtain total LPSW flow 6000 gpm.
- 37. Close 1LPSW-139.
- 38. Place in FAIL OPEN:
1LPSW-251 FAIL SWITCH 1LPSW-252 FAIL SWITCH
- 39. Start all available LPSW pumps.
Page 36 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 40. Verify either: GO TO Step 42.
Three LPSW pumps operating Two LPSW pumps operating when Tech Specs only requires two operable
- 41. Open: IF both are closed:
1LPSW-4 1LPSW-4 1LPSW-5 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'.
- 42. IAAT BWST level 19', 1. Display BWST level using OAC Turn-on THEN initiate Encl 5.12 (ECCS Code "SHOWDIG O1P1600".
Suction Swap to RBES). 2. Notify crew of BWST level IAAT step.
- 44. Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.
- 45. IAAT ES channels 5 & 6 have GO TO Step 47.
actuated, THEN perform Step 46.
NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.
- 46. Verify all ES channel 5 & 6 Notify SRO to evaluate components NOT components are in the ES position. in ES position and initiate action to place in ES position if desired.
Page 37 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam EOP Enclosure 5.1 (ES Actuation) Rev. 01 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 47. IAAT ES channels 7 & 8 have actuated, GO TO Step 50.
THEN perform Steps 48 - 49.
- Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels.
- In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch.
- 49. Verify all ES channel 7 & 8 Notify SRO to evaluate components NOT components are in the ES position. in ES position and initiate action to place in ES position if desired.
- 50. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open.
- 51. Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary.
- 53. WHEN CR SRO approves, THEN EXIT.
Page 38 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam Rule 6 rev 03 EP/1/A/1800/001 0L HPI Page 1 of 1
- HPI must be throttled to prevent violating the RV-P/T limit.
- HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.
- HPI must be throttled 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.
- Total HPI flow must be throttled 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.
- Total HPI flow must be throttled < 750 gpm when all the following exist:
- LPI suction is from the RBES
- piggyback is aligned
- either of the following exist:
- only one LPI pump operating
- HPI may be throttled under the following conditions:
HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress:
All the following conditions must exist: All the following conditions must exist:
- Core SCM > 0
- All WR NIs 1%
- CETCs decreasing
- Core SCM > 0
- Pzr level increasing
- Maintain 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Page 39 of 41
Appendix D Required Operator Actions Form ES-D-2 ILT 20-1 NRC Exam CRITICAL TASKS CT-1 Stop RCPs within 2 minutes of a Loss of SCM (BWOG CT-1). (page 23)
CT-2 Start 1C LPIP prior to reaching 700°F CETCs. (page 20, 35)
CT-3 (BWOG CT-27) Implementation of Control Room Habitability Guidance.
Start the Outside Air Booster Fans within 30 minutes of a LOCA. Not performing this action could result in Control Room habitability issues. (page 35)
Page 40 of 41
SAFETY: Take a Minute UNIT 0 (SM)
SSF Operable: No KHU's Operable: U1 - OH, U2 - LCTs Operable: 2 Fuel Handling: No Yes for U2 and U3 UG UNIT STATUS (CRS)
Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: Below POAH Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CRS)
Component/Train OOS Restoration TS/SLC #
Date/Time Required Date/Time SSF 2 days ago / 0400 5 days / 0400 TS 3.10.1 Cond A,B,C,D,E Shift Turnover Items (CRS)
Primary
- After turnover, the BOP is to lower the RBNS to 3 inches per OP/1/A/1104/007, Encl. 4.1. Then OATC is to continue in OP/1/A/1102/001 Encl 4.7 to raise Rx power.
- Raise Reactor power to 3% per OP/1/A/1102/001 Encl. 4.7 beginning at step 3.38. Once Rx power is 3% and step 3.41 is complete, hold further power escalation and CRS return to oversight role until Rx Engineering updates the maneuvering plan.
- During the Reactor power escalation, Unit 2 CRS will assume the oversight role for Unit 1.
The Unit 1 CRS will provide dedicated Reactivity oversight.
Secondary
- 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.
Reactivity Management (CRS)
Gp 7 Rod Position: Batch additions as required per maneuvering plan RCS Boron 1865 ppmB 4% Withdrawn (OATC)
Human Performance Emphasis (SM)
Procedure Use and Adherence
(RO-P404a) Page 1 of 11 REGION II JOB PERFORMANCE MEASURE OCONEE RO-P404a Align ECCS Suction to the Emergency Sump Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: Yes Alt Path
Description:
_1LP-21 fails to close requiring 1A LPIP, 1A BS Pump to be secured and 1LP-19 closed_
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-P404a) Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Align ECCS Suction to the Emergency Sump Task Number :
Alternate Path: Yes Time Critical: No Validation Time: 10 minutes K/A Rating(s):
System: EPE011 K/A: EA1.11 Rating: 4.2/4.2 Task Standard: .12 ECCS Suction Swap to RBES is properly completed to align ECCS to the Emergency Sump.
References:
EOP Enclosure 5.12 ECCS Suction Swap to RBES Rev 00 EP/1/A/1800/001 LOCA CD Tab Rev 00 Tools/Equipment/Procedures Needed:
EOP Enclosure 5.12 ECCS Suction Swap to RBES Rev 00 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-P404a) Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 387 (JPM a files)
- 2. ENSURE clean copy of EOP Enc. 5.12 is available to the candidate
- 3. ENSURE BWST Level is on the OAC (Showdig O1P1600)
- 4. Place the simulator in RUN and allow BWST Level to update to 18.9 then go to FREEZE
- 5. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall IC-1
- 4. Perform Rule 2 and Enc. 5.1 actions to put the plant in the proper position
- 5. Insert LP01LP_LPITK0001TAZTLIL 19 to place BWST at 19 feet (15, 9, 6)
- 6. Ackowledge statalarms and place simulator in FREEZE
(RO-P404a) Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS A large break LOCA has occurred which is depleting the BWST INITIATING CUE The Control Room SRO directs you to align ECCS suction to the Emergency Sump per Enc.
5.12, ECCS Suction Swap to RBES, of the EOP.
(RO-P404a) Page 5 of 11 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Start:
__ 1A LPI PUMP
__ 1B LPI PUMP Enc. ___ SAT 5.12 STANDARD: Candidate locates control switches for 1A and 1B 1 LPI Pumps on 1UB2 and observes red ON lights Step are illuminated and pump amps indicated. ___ UNSAT 1
COMMENTS:
Verify either:
__ LPI FLOW TRAIN A plus LPI FLOW TRAIN B > 3400 gpm
__ Only one LPI header is operating, AND flow in that header is >
2900 gpm
___ SAT STANDARD: Candidate should determine that step is met since 2 2 LPI Flow A plus LPI Flow B is > 3400 gpm. Flow gauges are on 1UB2 ___ UNSAT COMMENTS:
GO TO Step 52.
STANDARD: GO TO Step 52 ___ SAT 3 3 COMMENTS: ___ UNSAT
(RO-P404a) Page 6 of 11 SEQ PROC DESCRIPTION STEP STEP WHEN BWST level is < 15', THEN stop all HPI pumps.
STANDARD: Candidate determines BWST level gauges on 1UB2, OAC point, or ICCM displays indicate < 15 feet, then the candidate will place the control switches for any operating HPIP in the trip position and observes red lights not illuminated CRITICAL STEP Examiner Cue: If needed, inform candidate that using time 4 52 compression BWST level will be lowered to < ___ SAT 15 feet and RB level will be increased ACTIVATE TIMER 1
___ UNSAT COMMENTS:
NOTE RB level of > 2 is expected when BWST level reaches 9.
WHEN BWST level < 9', AND RB level is rising, THEN continue procedure.
STANDARD: Candidate observes BWST level < 9 feet on 1UB2 guages, OAC point, or ICCM monitors.
___ SAT 5 53 Examiner Cue: If needed, inform candidate that using time compression BWST level will be lowered to < ___ UNSAT 9 feet and RB level will be increased ACTIVATE TIMER 2 COMMENTS:
(RO-P404a) Page 7 of 11 SEQ PROC DESCRIPTION STEP STEP Simultaneously open:
__ 1LP-19
__ 1LP-20 STANDARD: Candidate locates the control switches for 1LP-19 CRITICAL and 1LP-20 ('1A'/1B RX. BLDG. SUCTION) on STEP 1UB2 and rotates the switches in the OPEN direction. Observes red OPEN lights come on, and 6 54 green CLOSED lights go off. ___ SAT Note: The candidate should operate both valves at the same time.
___ UNSAT COMMENTS:
IAAT BWST level is < 6', THEN perform Steps 56 - 59.
STANDARD: Candidate verifies BWST level 6' using:
BWST level gauges on 1UB2, BWST level from the OAC, at 1UB1, 1UB2, or STA monitor.
ICCM monitors on 1UB1.
___ SAT When BWST level is 6' go to the IAAT step and 7 55 then perform Steps 56 through 59 Examiner Cue: If needed, inform candidate that using time ___ UNSAT compression BWST level will be lowered to <
6 feet and RB level will be increased ACTIVATE TIMER 3 COMMENTS:
(RO-P404a) Page 8 of 11 SEQ PROC DESCRIPTION STEP STEP Verify 1LP-19 open.
STANDARD: Locates the control switch for 1LP-19 on 1UB2 and ___ SAT observes red OPEN light illuminated.
8 56
___ UNSAT COMMENTS:
Verify 1LP-20 open.
STANDARD: Locates the control switch for 1LP-20 on 1UB2 and ___ SAT observes red OPEN light illuminated.
9 57
___ UNSAT COMMENTS:
Simultaneously close:
__ 1LP-21
__ *1LP-22 STANDARD: The candidate locates the control switches for 1LP-21 and 1LP-22 on 1UB2 and rotates them in the *CRITICAL CLOSE direction. STEP Examiner NOTE: 1LP-21 will not close.
10 58 Candidate recognizes that 1LP-21 did not close by ___ SAT observing green closed light off and red open light on.
___ UNSAT Continue to Step 58 RNO COMMENTS:
(RO-P404a) Page 9 of 11 SEQ PROC DESCRIPTION STEP STEP ALTERNATE PATH IF 1LP-21 fails to close, THEN:
A. __ Stop 1A LPI PUMP.
B. __ Stop 1A RBS PUMP.
C. __ Close 1LP-19.
STANDARD: Locates LPI Pump A control on 1UB2 and turns CRITICAL pump switch to off. Red light is observed off and STEP white light on.
58 Locates RB Spray Pump A control on 1UB2. RB 11 Spray Pump A switch is rotated to the OFF ___ SAT RNO position. Green OFF light is lit and the red RUN light is off.
___ UNSAT Locates 1LP-19 switch and rotates to the close position. Observes GREEN light lit and RED light off.
COMMENTS:
Dispatch an operator to close 1LP-28 (BWST Outlet) (East of Unit 1 BWST).
STANDARD: An operator is dispatched to close 1LP-28 (BWST CRITICAL Outlet) (East of Unit 1 BWST). STEP 12 59 COMMENTS: ___ SAT
___ UNSAT END OF TASK TIME STOP: ________
(RO-P404a) Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
4 Protects HPI pumps 6 Aligns LPI Pump suction to Reactor Building Emergency Sump.
10 Secures LPI Pump suction from the BWST.
11 1A LPI and 1A RBS pumps are secured to prevent damage.
12 Close 1LP-28 (BWST Isolation) - Isolates suction from the BWST.
a CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS A large break LOCA has occurred which is depleting the BWST INITIATING CUE The Control Room SRO directs you to align ECCS suction to the Emergency Sump per Enc.
5.12, ECCS Suction Swap to RBES, of the EOP.
(RO-607) Page 1 of 11 REGION II JOB PERFORMANCE MEASURE OCONEE RO-607 Alignment of CT-5 per AP/48 Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-607) Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Alignment of CT-5 per AP/48 Task Number :
Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s):
System: 062 K/A: A2.05 Rating: 2.9/3.3*
Task Standard:
Close SL1 and SL2 breakers and verify ~4160V on the standby busses. Place CT-5 transfer switches in AUTO.
References:
AP/0/A/1700/048 (Loss of a Startup Transformer)
Tools/Equipment/Procedures Needed:
AP/0/A/1700/048 (Loss of a Startup Transformer) Rev 00 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-607) Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 384 (RO-607)
- 2. ENSURE clean copy of AP/0/A/1700/048 available for the candidate
- 3. Place the simulator in RUN and acknowledge alarms then go to FREEZE
- 4. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall IC-1
- 2. Use browser malfunction menu under electrical to cause PCB 17 & 18 Lockout
- 3. Ackowledge statalarms and place simulator in FREEZE
(RO-607) Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 is 100% power A lockout of CT-1 has just occurred The Unit 1 CRS has entered AP/0/A/1700/048 (Loss of a Startup Transformer)
INITIATING CUE The Control Room SRO directs you to perform AP/0/A/1700/048 (Loss of a Startup Transformer).
(RO-607) Page 5 of 11 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP NOTE This procedure is normally performed by Unit 2 RO for any affected units CT transformer, unless directed otherwise by CRS.
Verify both:
- STBY BUS de-energized (0 Volts)
- Affected units generator online
___ SAT STANDARD: Candidate determines that the STBY BUS is de-energized by observing gauges on 2AB3.
1 4.1 Candidate determines that the affected units generator is online by observing MWATTs or output ___ UNSAT breaker postion on 1UB2.
Candidate continues to Step 2 COMMENTS:
Announce AP entry using the PA system STANDARD: Candidate announces the AP entry using any Control Room area phone ___ SAT Candidate continues to Step 3 2 4.2
___ UNSAT COMMENTS:
(RO-607) Page 6 of 11 SEQ PROC DESCRIPTION STEP STEP Verify CT-5 indicates 4160 volts
___ SAT STANDARD: Candidate verifies 4160 volts on CT-5 gauge on 1AB1 3 4.3 Candidate continues to Step 4 COMMENTS: ___ UNSAT Ensure the following open:
- SK1 CT-4 STBY BUS 1 FEEDER
- SK2 CT-4 STBY BUS 2 FEEDER STANDARD: Candidate determines that SK1 CT-4 STBY BUS 1
___ SAT FEEDER is open by observing the white light on 2AB3.
4 4.4 Candidate determines that SK2 CT-4 STBY BUS 2 FEEDER is open by observing the white light on ___ UNSAT 2AB3.
Candidate continues to Step 5 COMMENTS:
Initiate logging entry in TS 3.8.1 Condition D for all units in MODES 1-4 STANDARD: Candidate informs the SRO to initiate logging entry into TS 3.8.1 Condition D ___ SAT Candidate continues to Step 6 5 4.5 Examiner Cue: SRO has entered TS 3.8.1 Condition D
___ UNSAT COMMENTS:
(RO-607) Page 7 of 11 SEQ PROC DESCRIPTION STEP STEP Ensure the following in MAN:
- CT-5 Bus 1 AUTO/MAN
- CT-5 Bus 2 AUTO/MAN STANDARD: Candidate verifies CT-5 Bus 1 AUTO/MAN transfer ___ SAT 6 4.6 switch in MAN located on 2AB3.
Candidate verifies CT-5 Bus 2 AUTO/MAN transfer ___ UNSAT switch in MAN located on 2AB3.
Candidate continues to Step 7 COMMENTS:
Ensure the following switches in the CENTRAL position
- SL1 & SL2 TRIP INTERLOCK DEFEAT CH 1
- SL1 & SL2 TRIP INTERLOCK DEFEAT CH 2 STANDARD: Candidate verifies SL1 & SL2 TRIP INTERLOCK ___ SAT DEFEAT CH1 in CENTRAL located on 2AB3.
7 4.7 Candidate verifies SL1 & SL2 TRIP INTERLOCK DEFEAT CH2 in CENTRAL located on 2AB3. ___ UNSAT Candidate continues to Step 8 COMMENTS:
(RO-607) Page 8 of 11 SEQ PROC DESCRIPTION STEP STEP Close the following:
- SL1 CT-5 STBY BUS 1 FEEDER
- SL2 CT-5 STBY BUS 2 FEEDER CRITICAL STEP STANDARD: Candidate closes SL1 CT-5 STBY BUS 1 FEEDER located on 2AB3.
___ SAT 8 4.8 Candidate closes SL2 CT-5 STBY BUS 2 FEEDER located on 2AB3.
Candidate continues to Step 9 COMMENTS: ___ UNSAT Verify 4160 volts on the following:
- Standby Bus 1
- Standby Bus 2 STANDARD: Candidate determines that the STBY BUS is ___ SAT reading 4160 volts by observing gauges on 2AB3.
9 4.9 Candidate continues to Step 10 COMMENTS: ___ UNSAT
(RO-607) Page 9 of 11 SEQ PROC DESCRIPTION STEP STEP Notify all units CRS that the Standby Busses are powered from Central Substation via CT-5 STANDARD: Candidate notifies all 3 unit CRS about the Standby Busses being powered from Central Substation via
___ SAT CT-5 Candidate continues to Step 11 10 4.10 Examiner Cue: All Units CRS are notified
___ UNSAT COMMENTS:
Ensure the following in AUTO:
- CT-5 Bus 1 AUTO/MAN
- CT-5 Bus 2 AUTO/MAN CRITICAL STANDARD: Candidate places CT-5 Bus 1 AUTO/MAN transfer STEP switch in AUTO located on 2AB3.
Candidate places CT-5 Bus 2 AUTO/MAN transfer
___ SAT 11 4.11 switch in AUTO located on 2AB3.
COMMENTS:
___ UNSAT END OF TASK TIME STOP: ________
(RO-607) Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
8 This step is required to energize the Standby Busses from CT-5. If performed incorrectly the busses will remain de-energized.
11 This step is required to provide undervoltage protection for SL1 and SL2 breakers. If performed incorrectly the breakers will not open under degraded voltage conditions.
b CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 is 100% power A lockout of CT-1 has just occurred The Unit 1 CRS has entered AP/0/A/1700/048 (Loss of a Startup Transformer)
INITIATING CUE The Control Room SRO directs you to perform AP/0/A/1700/048 (Loss of a Startup Transformer).
(RO-306a) Page 1 of 11 REGION II JOB PERFORMANCE MEASURE OCONEE RO-306a Perform Rule 5 for EHT Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: Yes Alt Path
Description:
_ES-2 fails to go to Manual, which will require placing the EVEN Voters in Override Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-306a) Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Perform Rule 5 for EHT Task Number :
Alternate Path: Yes Time Critical: No Validation Time: 10 minutes K/A Rating(s):
System: BW/E05 K/A: EA1.1 Rating: 4.2/4.2 Task Standard:
Close SL1 and SL2 breakers and verify ~4160V on the standby busses. Place CT-5 transfer switches in AUTO.
References:
EP/1/A/1800/001 Rule 5 (Main Steam Line Break) Rev 03 Tools/Equipment/Procedures Needed:
EP/1/A/1800/001 Rule 5 (Main Steam Line Break) Rev 03 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-306a) Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 390 (RO-306a)
- 2. ENSURE clean copy of Rule 5 available for the candidate
- 3. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall IC-1
- 2. AOR: On the soft panel, select ES-2 AUTO pushbutton as being selected
- 3. Insert a Main Steam Line Break on 1A SG (15%)
- 4. Freeze the simulator following the Reactor Trip
(RO-306a) Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 was operating at 100% power The reactor has just tripped following a Main Steam Line Break on the 1A SG Immediate Manual Actions (IMAs) and Symptoms Check are complete INITIATING CUE The Control Room SRO directs you to perform Rule 5 for excessive heat transfer on the 1A SG
(RO-306a) Page 5 of 11 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Perform on the affected headers:
Select OFF for 1A MD EFDWP. Select OFF for 1B MD EFDWP.
Trip both Main FDWPTs. Trip both Main FDWPTs. ___ SAT
- Place 1FDW-33 switch to Place 1FDW-42 switch to Rule CLOSE. CLOSE. ___ UNSAT 5 *Place 1FDW-31 switch to Place 1FDW-40 switch to 1 CLOSE. CLOSE.
Step Close 1PSW-22. Close 1PSW-24.
1 Close 1PSW-23. Close 1PSW-25.
STANDARD: Candidate should perform the isolation steps for the 1A SG ONLY. The A Header isolations are located on 1UB1.
COMMENTS:
Verify 1 TD EFDW PUMP operating.
STANDARD: Candidate verifies that the 1TD EFDW Pump is not running by looking at status lights and discharge ___ SAT pressure on 1UB1.
2 2 Candidate continues to Step 2 RNO.
___ UNSAT COMMENTS:
(RO-306a) Page 6 of 11 SEQ PROC DESCRIPTION STEP STEP IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5.
STANDARD: Candidate verifies that the 1B MDEFDWP is running using red lights and flow or discharge ___ SAT pressure on 1UB1 and proceeds to Step 5 2
3 RNO ___ UNSAT COMMENTS:
Verify 1B SG is an affected SG.
STANDARD: Candidate verifies that 1A SG is the affected SG by looking at Steam Pressure and proceeds to the RNO. ___ SAT 4 5 COMMENTS: ___ UNSAT GO TO Step 7 STANDARD: Candidate goes to Step 7 ___ SAT 5
5 RNO COMMENTS: ___ UNSAT
(RO-306a) Page 7 of 11 SEQ PROC DESCRIPTION STEP STEP WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either:
__ TBVs
__ Dispatch two operators to perform Encl 5.24 (Operation of the
___ SAT ADVs). (PS)
STANDARD: Candidate determines that overcooling has stopped by either observing stable RCS temperature or by ___ UNSAT 6 7 verifying that the 1A SG is dry (<12 inches) and not being fed (1UB1). Candidate should then adjust steaming of 1B SG by rotating the setpoint knob on the ICS Turbine Master in the counter-clockwise direction to cause 1B TBVs to open.
COMMENTS:
CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled WHEN all exist:
__ Core SCM > 0°F
__ Rx Power < 1%
___ SAT
__ Pzr level increasing 7 8 THEN continue. ___ UNSAT STANDARD: Candidate verifies Core SCM on or above the ICCM Monitors, verifies Rx Power on WR or PR meters, and verifies PZR level on the dixons. All indications are on 1UB1.
COMMENTS:
(RO-306a) Page 8 of 11 SEQ PROC DESCRIPTION STEP STEP Verify ES HPI actuated.
STANDARD: Candidate verifies that ES HPI has actuated on looking at Statalarms (1SA-1), ES channel ___ SAT indications under the plexiglass cover, or by looking 8 9 at the AUTO/MANUAL lights.
___ UNSAT COMMENTS:
Place Diverse HPI in BYPASS CRITICAL STEP STANDARD: Candidate pushes Diverse HPI BYPASS pushbutton on 1UB1 and verifies status light 9 10 changes and Statalarm (1SA-1) comes in. ___ SAT COMMENTS:
___ UNSAT Perform both:
- CRITICAL
__ Place ES CH 2 in MANUAL. STEP STANDARD: Candidate pushes MANUAL pushbutton for ES CH 1 on 1UB2 and verifies AUTO light (blue) goes out. ___ SAT 10 11 Candidate pushes MANUAL pushbutton for ES CH 2 and it fails to go to MANUAL. Candidate
___ UNSAT then proceeds to step 11 RNO.
COMMENTS:
(RO-306a) Page 9 of 11 SEQ PROC DESCRIPTION STEP STEP ALTERNATE PATH IF ES CH 2 fails to go to MANUAL, THEN place EVEN voter in CRITICAL OVERRIDE. STEP STANDARD: Candidate determines that ES CH 2 failed to go to MANUAL (blue AUTO light still lit) and presses the ___ SAT 11 EVEN Voter OVERRIDE pushbutton on 1UB2. This 11 will clear the statalarm for ES CH 2 actuation on RNO 1SA-1. ___ UNSAT COMMENTS:
Perform the following to stabilize RCS P/T:
__ Throttle HPI.*
__ Reduce 1HP-120 setpoint to control at >100 [180 acc]. *CRITICAL STEP
__ Adjust steaming of unaffected SG as necessary to maintain CETCs constant.
___ SAT STANDARD: Candidate throttles HPI to prevent thermal shock by securing 1C HPIP and verifying either red lights have gone out or amps have gone to 0. Candidate ___ UNSAT then closes 1HP-26 and verifies that the green light is lit and red light is out. Candidate adjusts the 12 12 thumbwheel (setpoint) on 1HP-120 to >100 inches
(>25% on the dial). Candidate will adjust TURBINE MASTER thumbwheel (setpoint) to stabilize CETCs constant COMMENTS:
END OF TASK TIME STOP: ________
(RO-306a) Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 This step is required to isolate the correct SG. Isolating the wrong SG will lead to a LOHT 9 This step is required to gain manual control of HPI to allow throttling 10 This step is required to gain manual control of HPI to allow throttling 11 This step is required to gain manual control of HPI to allow throttling 12 This step is required to prevent thermal shock conditions due to low RCS Temperature and high RCS Pressure
c CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 was operating at 100% power The reactor has just tripped following a Main Steam Line Break on the 1A SG Immediate Manual Actions (IMAs) and Symptoms Check are complete INITIATING CUE The Control Room SRO directs you to perform Rule 5 for excessive heat transfer on the 1A SG
(RO-105) Page 1 of 10 REGION II JOB PERFORMANCE MEASURE OCONEE RO-105 Perform Control Rod Movement PT for Group 1 Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-105) Page 2 of 10 REGION II JOB PERFORMANCE MEASURE Task Title : Perform Control Rod Movement PT for Group 1 Task Number :
Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s):
System: 001 K/A: A4.08 Rating: 3.7/3.4 Task Standard:
Perform Control Rod Movement PT for Group 1 in accordance with PT/1/A/0600/015 Enc. 13.2 (Control Rod Movement at Power)
References:
PT/1/A/0600/015 Control Rod Movement Rev 29 OP/1/A/1102/004 A ICS Operation Rev 14 Tools/Equipment/Procedures Needed:
PT/1/A/0600/015 Control Rod Movement Rev 29 OP/1/A/1102/004 A ICS Operation Rev 14 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-105) Page 3 of 10 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 385 (JPM d)
- 2. ENSURE Control Room reactivity rope in place
- 3. ENSURE clean copy of Rod Movement PT Enc. 13.2 available for student
- 4. Place the simulator in RUN and acknowledge alarms then go to FREEZE
- 5. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall IC-1
- 2. Perform PT/1/A/0600/015 up through Step 3.2 of Enc. 13.2
- 3. Ackowledge statalarms and place simulator in FREEZE
(RO-105) Page 4 of 10 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 at 100% power PT/1/A/0600/015 (Control Rod Movement) in progress for Group 1 ONLY 3.2 (Control Rod Movement at Power) complete up to Step 3.3 INITIATING CUE The CRS directs you to complete Enc. 13.2 (Control Rod Movement PT) for Group 1 beginning at Step 3.3.
(RO-105) Page 5 of 10 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP IF AT ANY TIME contingency actions directed by CRS, perform Section 4 (Contingency Actions)
STANDARD: Candidate circles the IAAT step and moves on to Enc. Step 3.4 ___ SAT 13.2 1
Step COMMENTS: ___ UNSAT 3.3 NOTE: When operating switches on Diamond, maintain switch depressed until light indication changes state.
Perform the following: (R.M.) *CRITICAL
- Ensure SEQ OR is ON.* STEP
- Ensure SAFETY RODS OUT BYPASS is ON.*
- Ensure RUN is ON. ___ SAT
- Ensure SINGLE SELECT SWITCH selected to ALL.
___ UNSAT STANDARD: Candidate will select the pushbuttons on the Rod 2 3.4 Control panel until the indication is lit for SEQ OR, SAFETY RODS OUT BYPASS, and RUN controls (1UB1). The SINGLE SELECT SWITCH is turned to ALL.
COMMENTS:
(RO-105) Page 6 of 10 SEQ PROC DESCRIPTION STEP STEP NOTE: CRD Groups 1-6 are required to be >95% withdrawn for Shutdown Margin Calculation at Power enclosure of PT/1/A/1103/015 (Reactivty Balance Procedure) to be valid. ___ SAT IF AT ANY TIME any CRD Group 1-6 reaches 95% during insertion, stop inserting associated group.
___ UNSAT 3 3.5 STANDARD: Candidate monitors Group 1 rods for 95% and stops inserting as necessary COMMENTS:
Perform the following to test CRD Group 1:
Ensure GROUP SELECT SWITCH to 1. CRITICAL STEP STANDARD: Candidate rotates GROUP SELECT SWITCH to 1.
4 3.6.1 ___ SAT COMMENTS:
___ UNSAT Ensure Group 1 CONTROL ON lights are ON. (PI panel)
STANDARD: Candidate determines that the Group 1 CONTROL ON lights are ON (PI panel). ___ SAT 5 3.6.2 COMMENTS: ___ UNSAT
(RO-105) Page 7 of 10 SEQ PROC DESCRIPTION STEP STEP NOTE: 1SA-2/C/10 CRD Safety Rods Not at Upper Limit will alarm when Safety Groups are inserted.
Control rods should NOT be left inserted. Rod withdrawal should commence immediately after insertion is complete. CRITICAL STEP Perform the following:
A. Insert CRD Group 1.
___ SAT B. WHEN all 100% lights OFF, stop insertion.
C. Withdraw Group 1 to 100% until CRD TRAVEL "Out" light OFF. ___ UNSAT STANDARD: Candidate inserts CRD Group 1 using the Joy 6 3.6.3 Stickon the Diamond.
Monitor the 100% lights on the PI Panel and when they are OFF (or any rod reaches 95%), stop inserting.
Withdraw Group 1 to 100% using Joy Stick until the CRD TRAVEL Out light is OFF.
COMMENTS:
Verify all 100% lights are ON for Group 1. (PI Panel)
STANDARD: Candidate determines that all 100% lights are ON for Group 1 (PI Panel)
___ SAT 7 3.6.4 COMMENTS:
___ UNSAT
(RO-105) Page 8 of 10 SEQ PROC DESCRIPTION STEP STEP Verify unit is stable STANDARD: Monintor reactor power, Tave, and RCS pressure to determine that the unit is stable. ___ SAT 8 3.6.5 COMMENTS: ___ UNSAT NOTE: When operating switches on Diamond, maintain switch depressed until light indication changes state.
Perform the following: (R.M.)
CRITICAL
- Ensure SEQ is ON. STEP
- Ensure GROUP SELECT SWITCH to OFF.
___ SAT
- Ensure SAFETY RODS OUT BYPASS is OFF.
___ UNSAT STANDARD: Depress the SEQ/SEQ OR pushbutton and verity the SEQ light is lit.
9 3.14 Rotate the GROUP SELECT SWITCH to OFF Depress the SRO BYPASS switch and verity the light is OFF.
Examiner Cue: Another RO will complete this procedure.
COMMENTS:
END OF TASK TIME STOP: ________
(RO-105) Page 9 of 10 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
2 Step is required to test Group 1 4 Step is required to test Group 1 6 Step is required to test Group 1 9 Step is required to return the system to Normal operation
d CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 at 100% power PT/1/A/0600/015 (Control Rod Movement) in progress for Group 1 ONLY 3.2 (Control Rod Movement at Power) complete up to Step 3.3 INITIATING CUE The CRS directs you to complete Enc. 13.2 (Control Rod Movement PT) for Group 1 beginning at Step 3.3.
(RO-S408) Page 1 of 9 REGION II JOB PERFORMANCE MEASURE OCONEE RO-S408 Feed Both SGs with one MD EFDW pump Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-S408) Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title : Feed Both SGs with one MD EFDW pump Task Number :
Alternate Path: No Time Critical: No Validation Time: 6 minutes K/A Rating(s):
System: 061 K/A: A2.04 Rating: 3.4/3.8 Task Standard:
Feed both SGs with only operable MD EFDWP
References:
EOP Enclosure 5.9 Extended EFDW Operation Rev 01 EP/1/A/1800/001 Rule 3 Rev 03 Tools/Equipment/Procedures Needed:
EOP Enclosure 5.9 Extended EFDW Operation Rev 01 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-S408) Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 391 (JPM e files)
- 2. ENSURE copy of EOP Enc. 5.9 in progress at Step 3 is available to the candidate
- 3. Adjust setpoint of 1HP-120 to ~25% (100 inches)
- 4. Place the simulator in RUN and acknowledge alarms then go to FREEZE
- 5. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall IC-1
- 2. Insert failures of the TD EFDWP (MSS330), the 1B MD EFDWP, and both MFDWPS (MSS010, MSS020)
- 3. Adjust 1HP-120 setpoint to ~25% (100 inches)
- 4. Ackowledge statalarms and place simulator in FREEZE
(RO-S408) Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS The Reactor has tripped. The 1B MD EFDW Pump failed to start in AUTO or MANUAL and the TD EFDWP tripped. Enclosure 5.9 (Extended EFDW Operations) is in progress up to step 3.
The CRS directs you to feed both SGs per step 3.
INITIATING CUE Continue in EOP Enclosure 5.9, beginning at step 3, to feed both SGs with the 1A MD EFDWP.
(RO-S408) Page 5 of 9 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP
__ IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 4 - 7.
STANDARD: Student determines that it is desired to feed both SGs with the 1A MD EFDW pump from the cue Enc. sheet. ___ SAT 5.9 1
Step Continues to Step 4 ___ UNSAT 3
COMMENTS:
Place EFDW control valve on SG with NO EFDW flow to MANUAL and closed:
1A SG 1B SG 1FDW-315 1FDW-316* *CRITICAL STEP STANDARD: Student determines 1B SG has no EFDW flow and places 1FDW-316 controller in manual and adjusts
___ SAT valve demand to 0% or less such that the valve closes. Confirms closed by observing green closed light lit and red open lit extinguished.
2 4 ___ UNSAT Continues to Step 5 COMMENTS:
(RO-S408) Page 6 of 9 SEQ PROC DESCRIPTION STEP STEP Locally open:
__ 1FDW-313 (1A EFDW Line Disch To1A S/G X-Conn) (T-1, 1' N of M-16,18' up)
__ 1FDW-314 (1B EFDW Line Disch To1B S/G X-Conn) (T-1, 3' S of M-24,10' up)
- CRITICAL STEP STANDARD: Student dispatches an Operator via phone or radio to locally open 1FDW-313 and 1FDW-314.
___ SAT BOOTH CUE: When contacted to open 1FDW-313 and 1FDW-314, ACTIVATE TIMER 01 ___ UNSAT 3 5 Report back to control room operator that:
Using Time Compression, 1FDW-313 and 1FDW-314 are open.
Continues toStep 6 COMMENTS:
__ Ensure a MD EFDWP is operating.
STANDARD: Student observing control board indications determines that the 1A MD EFDW pump is operating.
___ SAT 4 6 Continue to Step 7
___ UNSAT COMMENTS:
(RO-S408) Page 7 of 9 SEQ PROC DESCRIPTION STEP STEP Throttle EFDW control valve on SG with NO EFDW flow to establish appropriate level per Rule 7 (SG Feed Control):
1A SG 1B SG 1FDW-315 1FDW-316*
STANDARD: Student will throttle open 1FDW-316 to establish flow to the 1B SG. The student will limit total *CRITICAL EFDW flow to < 600 gpm which is the Rule 7 limit STEP (Table 3) for one MDEFDWP. The student will raise level in the 1B SG towards 30 inches per Table 4. ___ SAT 5 7 EVALUATOR NOTE: Critical step is met when EFDW flow to ___ UNSAT the 1B SG is established and SG level is rising toward 30.
COMMENTS:
END TASK TIME STOP: ________
(RO-S408) Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
2 Required to gain positive control of EFDW flow to the 1B SG 3 Required to establish heat transfer in the 1B SG 5 Required to establish heat transfer in the 1B SG
e CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS The Reactor has tripped. The 1B MD EFDW Pump failed to start in AUTO or MANUAL and the TD EFDWP tripped. Enclosure 5.9 (Extended EFDW Operations) is in progress up to step 3.
The CRS directs you to feed both SGs per step 3.
INITIATING CUE Continue in EOP Enclosure 5.9, beginning at step 3, to feed both SGs with the 1A MD EFDWP.
(RO-804a) Page 1 of 15 REGION II JOB PERFORMANCE MEASURE OCONEE RO-804a Place RB Purge in Operation Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: Yes Alt Path
Description:
_Purge fan fails to trip on HIGH 1RIA-45 interlock ________________
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-804a) Page 2 of 15 REGION II JOB PERFORMANCE MEASURE Task Title : Place RB Purge in Operation Task Number :
Alternate Path: Yes Time Critical: No Validation Time: 15 minutes K/A Rating(s):
System: 029 K/A: A2.03 Rating: 2.7/3.1 Task Standard:
The Reactor Building Purge is placed in operation correctly and manually terminated upon receiving the 1RIA-45 High alarm
References:
PT/1/A/0230/001 (Radiation Monitor Check) Rev 176 OP/1/A/1102/014 (RB Purge System) Rev 47 Tools/Equipment/Procedures Needed:
PT/1/A/0230/001 (Radiation Monitor Check) Enc. 13.8 (RIA-45 and RIA-46 Setpoints for Unit 1 RB Purge Operation OP/1/A/1102/014 (RB Purge System) Enc. 4.1 (RB Purge Release) and Enc. 4.2 (RB Purge Sample Request)
(Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-804a) Page 3 of 15 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 389 (JPM f files)
- 2. ENSURE RB pressure ~ 0 psig
- 3. ENSURE in progress copy of the purge procedures available for the candidate
- 5. Place the simulator in RUN and acknowledge alarms then go to FREEZE
- 6. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall shutdown IC of ~130F and 60 psig
- 2. AOR: insert PVXARL1SRMX1TVSP 0 to block 1RIA-45 trip functions
- 3. Create a timer with RMORACT 1 to allow overriding RIAs. Insert RM45OVER 960 to match 1RIA-45 count rate at the beginning of the purge. Enter RM45OVER 92283 ramp 45 to raise 1RIA-45 beyond the HIGH alarm after 45 seconds.
(RO-804a) Page 4 of 15 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS 1A LPI Suction Temperature = 130°F RC Low Range pressure = 62 psig No GWD or LWD releases are in progress RB Hatch is CLOSED Continuous release is NOT in progress RB Purge startup is in progress using OP/1/A/1102/014 (RB Purge System), .1 (RB Purge Release)
INITIATING CUE The CRS directs you to place the RB Purge in operation at 1/3 Station Limit using OP/1/A/1102/014 Enclosure 4.1 starting at Step 3.8
(RO-804a) Page 5 of 15 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP 3.8 Perform the following:
3.8.1 Ensure one of the following:*
__ 1A RB AUX FAN is Off.
__ 1B RB AUX FAN is Off.
3.8.2 Ensure "T/O Sheet" CR Tag on 1A RB AUX FAN.
3.8.3 Ensure "T/O Sheet" CR Tag on 1B RB AUX FAN.
3.8.4 Ensure note on Turnover sheet: "If RB Purge Fan is operating, 1A RB Aux Fan OR 1B RB Aux Fan should be off."
- CRITICAL STANDARD: *Candidate rotates the control switch for the 1A or 1B RB Aux Fan to the STOP position and verifies the green off STEP light is on and the red on light is off.
Candidate ensures a T/O Sheet tag is on the 1A and 1B 1 3.8 ___ SAT RB AUX Fan switches (not critical).
Candidate states that he/she would place a note on the Turnover sheet as stated above (not critical). ___ UNSAT Examiner Cue: If asked as the SRO, inform the candidate that the 1A RB Aux Fan should be secured.
Examiner Cue: If the candidate tries to put a note on the turnover sheet, inform him/her that another RO has placed the note on the turnover sheet.
COMMENTS:
NOTE: Completion of Step 3.9 establishes an appropriate vent path during Fuel Movement Operations with any Transfer Tube open per the Shutdown Protection Plan. This prevents FTC and SFP level variations caused by differential pressures between RB and SFP. CRITICAL STEP 3.9 Perform the following:
3.9.1 Open 1PR-1 (RB PURGE OUTLET (RB)).
2 3.9 ___ SAT STANDARD: Candidate rotates 1PR-1 switch located on 1AB3 to the open position and verifies the red open light lit and green closed light off.
___ UNSAT COMMENTS:
(RO-804a) Page 6 of 15 SEQ PROC DESCRIPTION STEP STEP 3.9 Perform the following:
3.9.2 Open 1PR-2 (RB PURGE OUTLET (PR)). CRITICAL STEP STANDARD: Candidate rotates 1PR-2 switch located on 1AB3 to the open position and verifies the red open light lit and green closed light off.
3 3.9 ___ SAT COMMENTS:
___ UNSAT 3.9 Perform the following:
3.9.3 Ensure closed 1PR-3 (RB PURGE FLOW). (Bailey Controller)
STANDARD: Candidate ensures 1PR-3 is closed by rotating the Bailey Controller knob until the position indication indicates zero ___ SAT demand located on 1AB3.
4 3.9
___ UNSAT COMMENTS:
3.9 Perform the following:
NOTE: It may take several minutes for the air to bleed off 1PR-3.
3.9.4 Verify 1PR-3 closed using alternate indication.
STANDARD: Candidate verifies 1PR-3 is closed on the Component ___ SAT Status Panel and/or the switch located under the 5 3.9 Component Status Panel both located on 1VB-2.
Candidate may also verify 1PR-3 is closed by using the ___ UNSAT OAC graphic display.
COMMENTS:
(RO-804a) Page 7 of 15 SEQ PROC DESCRIPTION STEP STEP 3.9 Perform the following:
3.9.5 WHILE RB Purge operating, monitor unit vent RIAs.
STANDARD: Candidate monitors Unit Vent RIAs (RIA-43, 44, 45, &
- 46) using the RIA View Node located on 1VB3 or by using the OAC while the RB Purge is operating.
___ SAT 6 3.9 COMMENTS:
___ UNSAT 3.9 Perform the following:
3.9.6 Perform the following:
NOTE: When 1PR-3 (RB PURGE OUTLET SWITCH) is positioned to open, 1PR-3 will remain in the closed position since 1PR-3 Bailey Controller is closed.
A. Position 1PR-3 (RB PURGE OUTLET SWITCH) to open.
B. Throttle 1PR-3 (RB PURGE FLOW) to > 60% demand on Bailey Controller.
CRITICAL STANDARD: Candidate rotates 1PR-3 switch to the open position STEP located on 1VB2.
Candidate rotates the knob on 1PR-3 Bailey Controller in 7 3.9 the increase direction until the controller indicates > 60%
___ SAT demand located on 1AB3.
COMMENTS: ___ UNSAT
(RO-804a) Page 8 of 15 SEQ PROC DESCRIPTION STEP STEP 3.10 IF required to operate the RB Purge Fan, perform the following:
3.10.1 Perform one of the following:
A. Perform the following:
B. Ensure the following: (Not Applicable)
NOTE:
Entry into AP/1-2/A/1700/35 NOT required if SFP level changes are evaluated and stabilizes.
- There is 20 second time delay to open the dampers before the Purge starts.
3.10.2 Start RB Purge Fan.
NOTE:
- Interlock may trip Purge if 1PR-3 demand is < 35%.
- Operating 1PR-3 slowly allows time for the valve to respond
- CRITICAL to demand changes.
STEP 3.10.3 Ensure 1PR-3 (RB PURGE FLOW) (Bailey Controller) adjusted to < recommended release rate.
8 3.10 ___ SAT STANDARD: *Candidate opens 1PR-4, 1PR-5, and 1PR-6 by rotating the control switches to the open position located on 1AB3 and verify the red open lights are on and the green
___ UNSAT closed lights are off.
- Candidate starts the RB Purge Fan by rotating the switch to the start position located on 1AB3 and verify the red on light is on and green off light is off.
Candidate ensures 1PR-3 is adjusted to < the recommended release rate as read on Chessel Misc.
System Recorder 1 located on 1VB1 or the OAC.
Examiner Cue: If asked about opening the RB Equipement Hatch, respond that opening the Hatch is not desired.
Examiner Note: 1RIA-45 counts will begin rising when the purge fan is started and will exceed the HIGH setpoint but the interlock function will not occur.
COMMENTS:
(RO-804a) Page 9 of 15 SEQ PROC DESCRIPTION STEP STEP
[ALTERNATE PATH]
The following Statalarms will actuate:
- 1SA-08/B-9 (Process Monitor Radiation High)
Examiner Note: The candidate may refer to one or both ARGs. If 1SA-08/D-9 is selected, the SEQ Step 9 will be performed and that will end the task. If 1SA-08/B-9 is selected, then SEQ Steps 10-13 will be performed CRITICAL and that will end the task. Either Step 9 or 13 is STEP Critical but not both.
Refer to 1SA-08/D-9 (RM Reactor Building Purge Discharge Inhibit)
___ SAT 3.1 Ensure auto action has taken place 3.2 Observe Reactor Building RIAs and evacuate personnel as it becomes necessary ___ UNSAT 3.3 Determine cause of inhibit and correct 9 10 STANDARD: Candidate determines that the automatic actions have NOT taken place and using ARG guidance performs the following:
- Stops the RB Purge Fan
- Closes 1PR-2
- Closes 1PR-3
- Closes 1PR-4
- Closes 1PR-5 Candidate verifies that the green lights are on and the red lights are off.
COMMENTS:
END OF TASK
(RO-804a) Page 10 of 15 SEQ PROC DESCRIPTION STEP STEP 1SA-08/B-9 3.1 Perform one of the following:
3.1.1 Determine radiation monitors in alarm.
3.1.2 IF Radiation Monitoring data from the PMC System is NOT in service, refer to OP/1/A/1103/026, (Loss of Sorrento Radiation Monitor).
3.2 IF 1SA-08/B-10 (Process Monitor Fault) has occurred for the same monitor, Go To the ARG for 1SA-08/B-10 (Process Monitor Fault).
{3}
3.3 IF 1RIA-40 alarms, Go To the appropriate procedure:
- < 25 gpm (36,000 gpd) - AP/1/A/1700/031 (Primary To Secondary Leakage)
- 25 gpm (36,000 gpd) - EP/1/A/1800/001 (Emergency Operating Procedure) 3.4 IF any of the following RIAs have valid alarms, Go To AP/1/A/1700/018 (Abnormal Release of Radioactivity).
RIA RIA-31 1RIA-35 1RIA-39
___ UNSAT 1RIA-45, 46 1RIA-49A 1RIA-50 STANDARD: Determine 1RIA-45 is in HIGH alarm Determine that Radiation Monitoring data from the PMC System is in service Determine 1SA-08/B-10 (Process Monitor Fault) is NOT in alarm Determine 1RIA-40 is NOT is alarm Determine 1RIA-45 is in alarm and Go To AP/1/A/1700/018 (Abnormal Release of Radioactivity).
Examiner Cue: If candidate notifies CRS to GO TO AP/18, then inform the candidate the CRS directs them to perform AP/18 COMMENTS:
(RO-804a) Page 11 of 15 SEQ PROC DESCRIPTION STEP STEP Perform the following:
__ At the discretion of the CRS, make a PA announcement of the event including any necessary precautions to be observed.
__ Notify Shift Manager to reference the following:
- Emergency Classification procedure.
- AD-LS-ALL-0006 (Notification/reportability Evaluation)
- OMP 1-14 (Notifications)
STANDARD: Candidate notifies the SM to reference: ___ SAT AP18
- Emergency Classification procedure 11
- AD-LS-ALL-0006 (Notification/reportability 4.1 Evaluation) ___ UNSAT
- OMP 1-14 (Notifications)
Examiner cue: Notify the candidate that another operator will make the PA announcement.
COMMENTS:
(RO-804a) Page 12 of 15 SEQ PROC DESCRIPTION STEP STEP GO TO appropriate sections for any monitors in High or Alert alarm:
Section Monitor 4A RIA-31 4B 1RIA-32 4C 1RIA-35 4D 1RIA-39 4E 1RIA-41 4F 1RIA-42
___ SAT 4G 1RIA-45 or 1RIA-46 12 4.2 4H 1RIA-47, 1RIA-48, 1RIA-49, or ___ UNSAT 1RIA-49A 4I 1RIA-50 4J 1RIA-54 STANDARD: Candidate determines that 1RIA-45 is in High alarm and proceeds to Section 4G COMMENTS:
(RO-804a) Page 13 of 15 SEQ PROC DESCRIPTION STEP STEP IAAT 1RIA-45 or 1RIA-46 reaches the High set point, THEN ensure automatic actions occurred:
A. __ RB PURGE FAN secured.
B. __ 1PR-2 closed.
C. __ 1PR-3 closed.
D. __ 1PR-4 closed. CRITICAL E. __ 1PR-5 closed. STEP STANDARD: Candidate determines that 1RIA-45 is in High alarm and ___ SAT performs the following:
- Stops the RB Purge fan
- Closes 1PR-2 ___ UNSAT Sec
- Closes 1PR-3 13
- Closes 1PR-4 4G
- Closes 1PR-5 Candidate verifies that green lights are on and red lights are off.
Examiner Cue: Another operator will continue this procedure COMMENTS:
END OF TASK TIME STOP: ________
(RO-804a) Page 14 of 15 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 This step is required to prevent tripping 1XR incoming feeder breaker.
2 This step is required to establish RB Purge flow.
3 This step is required to establish RB Purge flow.
7 This step is required to establish desired RB Purge flow.
8 This step is required to start the RB Purge fan.
9 or 13 One of these steps is required to stop the RB Purge fan and isolate the flowpath.
f CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS RCS temperature = 130°F RCS pressure = 62 psig No GWD or LWD releases are in progress RB Hatch is CLOSED Continuous release is NOT in progress RB Purge startup is in progress using OP/1/A/1102/014 (RB Purge System), .1 (RB Purge Release)
INITIATING CUE The CRS directs you to place the RB Purge in operation at 1/3 Station Limit using OP/1/A/1102/014 Enclosure 4.1 starting at Step 3.8
(RO-505a) Page 1 of 11 REGION II JOB PERFORMANCE MEASURE OCONEE RO-505a PERFORM EOP ENCLOSURE 5.35 Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: Yes Alt Path
Description:
_1HP-20 fails to close requiring 1HP-228, 226, 232, 230 to be closed to isolate containment_
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-505a) Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Perfom EOP Enclosure 5.35 Task Number :
Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):
System: APE069 K/A: AA1.01 Rating: 3.5/3.7 Task Standard:
Perform EOP Enc. 5.35 (Containment Isolation) correctly
References:
EP/1/A/1800/001 (Unit 1 Emergency Operating Procedure) Enc. 5.35 (Containment Isolation) Rev 01 Tools/Equipment/Procedures Needed:
EP/1/A/1800/001 (Unit 1 Emergency Operating Procedure) Enc. 5.35 (Containment Isolation) Rev 01 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-505a) Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 388 (JPM g)
- 2. ENSURE a clean copy of EOP Enc. 5.35 is available
- 3. Place the simulator in RUN and acknowledge alarms then go to FREEZE
- 4. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
(RO-505a) Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 Reactor tripped from 100% power due to a loss of all RCPs.
RCS leak of 190 gpm occurred as result of the trip.
EOP LOCA CD tab is in progress.
ES Actuation has NOT occurred.
INITIATING CUE The Control Room SRO directs you to perform EOP Enclosure 5.35 (Containment Isolation)
(RO-505a) Page 5 of 11 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Verify Encl 5.1 (ES Actuation) is in progress or complete.
ENC STANDARD: Candidate determines that ES has NOT actuated ___ SAT from the Initial Conditions and continues to Step 1 5.35 RNO.
1 Step ___ UNSAT 1 COMMENTS:
(RO-505a) Page 6 of 11 SEQ PROC DESCRIPTION STEP STEP
1GWD-1GWD-13 12 1LWD-1 1LWD-2 1CS-5 1CS-6 *CRITICAL 1PR-1 1PR-2 STEP 1PR-6 1PR-3 1PR-4 ___ SAT 1PR-5 1PR-7* 1PR-8* ___ UNSAT 1PR-9* 1PR-10*
2 1RC-6 RNO 1FDW-1FDW-106 105 1FDW-1FDW-108 107 1FDW-103 1FDW-104 STANDARD: Candidate rotates the switches in the closed direction for 1HP-3, 1HP-4, 1PR-7, 1PR-8, 1PR-9, and 1PR-10 and verifies green lights on, red lights off on the control board OR closed indication on the Component Staus Panel, OR closed indication on the OAC, for each of the valves listed above.
COMMENTS:
(RO-505a) Page 7 of 11 SEQ PROC DESCRIPTION STEP STEP
- 4. IF 1HP-5 fails to close, THEN close:
__1HP-7
__1HP-6
___ SAT STANDARD: Candidate determines that 1HP-3, 1HP-4, and 1 1HP-5 are closed by observing the green closed 3 lights on and red lights off on the control board OR RNO ___ UNSAT closed indication on the Component Staus Panel, OR closed indication on the OAC.
COMMENTS:
Verify all RCPs off.
STANDARD: Candidate determines that all RCPs are off by ___ SAT verifying red lights off and white lights on, and/or 4 2 verifying 0 amps indicated.
___ UNSAT COMMENTS:
Stop both CC pumps.
STANDARD: Candidate rotates CC Pump switches to trip and ___ SAT verifies green lights on, red lights off.
5 3
___ UNSAT COMMENTS:
(RO-505a) Page 8 of 11 SEQ PROC DESCRIPTION STEP STEP Close the following ES operated RB isolation valves:
ES Chan 1 ES Chan 2 1HP-20 *1HP-21 ES Chan 5 ES Chan 6
- 1CC-7 *1CC-8 *CRITICAL
- 1LPSW-15 *1LPSW-15 STEP
All other valves in the table close properly as indicated by green lights on and red lights off. ___ UNSAT Candidate proceeds to Step 4 RNO.
Examiner NOTE: 1HP-20 will not close COMMENTS:
[ALTERNATE PATH]
IF 1HP-20 fails to close, THEN close all the following:
__1HP-228
__1HP-226 CRITICAL
__1HP-232 STEP
__1HP-230 4
7 ___ SAT RNO STANDARD: Candidate closes all 4 valves evidenced by all green lights on and red lights off.
___ UNSAT COMMENTS:
(RO-505a) Page 9 of 11 SEQ PROC DESCRIPTION STEP STEP Rotate switches to the closed position for the following components:
__ 1LPSW-1054
__ 1LPSW-1055
__ 1LPSW-1061 CRITICAL
__ 1LPSW-1062 STEP 8 5 STANDARD: Candidate rotates the above switches to the closed ___ SAT position located on 1VB3.
Examiner Note: Either 1LPSW-1054 or 1LPSW-1055 and 1LPSW-1061 or 1LPSW-1062 must be closed ___ UNSAT to satisfy the critical step.
COMMENTS:
Verify the following components indicate closed:
__ 1LPSW-1054
__ 1LPSW-1055
__ 1LPSW-1061
__ 1LPSW-1062
___ SAT 9 6 STANDARD: Candidate verifies the above valves indicate closed by observing the green lights on and red lights off ___ UNSAT on 1VB3.
COMMENTS:
EXIT this enclosure.
___ SAT STANDARD: Candidate exits the enclosure 10 7 COMMENTS: ___ UNSAT END TASK TIME STOP: ________
(RO-505a) Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
2 This step is critical to isolate the Reactor Building.
6 This step is critical to isolate the Reactor Building.
7 This step is critical since 1HP-20 is failed open 1HP-228, 226, 232, 230 must be closed to isolate this pathway.
8 This step is critical to isolate the Reactor Building.
g CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 Reactor tripped from 100% power due to a loss of all RCPs.
RCS leak of 190 gpm occurred as result of the trip.
EOP LOCA CD tab is in progress.
ES Actuation has NOT occurred.
INITIATING CUE The Control Room SRO directs you to perform EOP Enclosure 5.35 (Containment Isolation)
(RO-203) Page 1 of 9 REGION II JOB PERFORMANCE MEASURE OCONEE RO-203 PRESSURE MAKEUP TO CFT Administrative: No Classroom/Simulator/Plant: Simulator Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(RO-203) Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title : Pressure Makeup to CFT Task Number :
Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s):
System: 006 K/A: A1.13 Rating: 3.5/3.7 Task Standard:
Use OP/1/A/1104/001 (Core Flooding System) to increase 1A CFT pressure to ~600 (595-605) psig
References:
OP/1/A/1104/001 (Core Flooding System) Rev 82 Tools/Equipment/Procedures Needed:
OP/1/A/1104/001 (Core Flooding System) Enc. 4.7 (Pressure Makeup to CFTs Using Nitrogen)
(Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(RO-203) Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS Directions with IC:
- 1. RECALL IC: 386 (JPM h files)
- 2. ENSURE copy of OP/1/A/1104/001 Enc. 4.7 in progress at Step 2.1 is available
- 3. Place the simulator in RUN to allow 1A CFT Pressure to update and then go to FREEZE
- 4. Go to RUN when directed by the Lead Examiner
====================================================================
Directions without an IC:
- 1. Recall IC-1
- 4. Ackowledge statalarms and place simulator in FREEZE
(RO-203) Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 is operating at 100% power Core Flood Tank low pressure Statalarm actuated OP/1/A/1104/001 (Core Flooding System) Enclosure 4.7 (Pressure Makeup To CFTs Using Nitrogen) is in progress INITIATING CUES The CR SRO directs you to pressurize the 1A CFT to 600 (595-605) psig beginning at Step 2.1 of Enclosure 4.7
(RO-203) Page 5 of 9 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Notify operator to open 1N-137 (CFTs Supply). (A-2-Hallway)
STANDARD: The candidate directs an AO to open 1N-137, CRITICAL communicate when the valve is open, and standby for STEP further instruction.
Booth Cue: When contacted, ACTIVATE TIMER 1 and inform student that 1N-137 is OPEN and you are standing by ___ SAT for further instructions.
1 2.1 COMMENTS: ___ UNSAT IF required to increase pressure in 1A CFT:
STANDARD: Determine that 1A CFT is has low pressure by observing either:
The computer point for Core Flood Tank 1A on the Operator Aid Computer.
OR 1A Core Flood Tank pressure gauge located on 1VB2.
___ SAT OR Statalarm 1SA-8/A-11 (CF TANK A PRESS HIGH/LOW) 2 2.2 Continue to step 2.2.1 ___ UNSAT COMMENTS:
(RO-203) Page 6 of 9 SEQ PROC DESCRIPTION STEP STEP NOTE: TS 3.6.3 Condition 'B' requires penetration flow path to be isolated within one hour. A check valve with flow secured through the valve is considered operable.
Enter Technical Specification 3.6.3 Condition 'A' and 'B'.
___ SAT STANDARD: Candidate notifies the CRS to enter Technical Specification 3.6.3 Condition 'A' and 'B'.
3 2.2.1 Examiner Cue: Inform candidate that Tech Spec 3.6.3 Conditions A ___ UNSAT and B have been entered and step 2.2.1 can be signed off as complete.
COMMENTS:
Open 1N-298 (N2 FILL CORE FLOOD TANK 1A).
CRITICAL STEP STANDARD: Open 1N-298 (N2 FILL CORE FLOOD TANK 1A) located on 1VB2. Verify RED OPEN indicating light lit; Green CLOSED light off.
4 2.2.2 ___ SAT COMMENTS:
___ UNSAT IF 1N-128 (CFT 1A Supply) is closed, throttle 1N-128 (CFT 1A Supply) for a rate of 100 psig per 15 minutes ( 6.6 psig/min). (A-4-409)
STANDARD: Determine 1N-128 is NOT closed. ___ SAT Continue to Step 2.2.4.
5 2.2.3 Examiner Cue: If asked, inform candidate that 1N-128 is NOT closed.
___ UNSAT COMMENTS:
(RO-203) Page 7 of 9 SEQ PROC DESCRIPTION STEP STEP Monitor 1A CFT pressure.
STANDARD: Observe computer point or pressure gauge for 1A Core ___ SAT Flood Tank on 1VB2 and verify Core Flood Tank 6 2.2.4 pressure is increasing.
___ UNSAT COMMENTS:
IF AT ANY TIME ES actuation occurs, close 1N-298 (N2 FILL CORE FLOOD TANK 1A).
___ SAT STANDARD: Determine ES actuation has not occurred by observing:
7 2.2.5 Statalarm Panel 1SA-1 Alarms 10 and 11 on rows A thru D NOT in alarm
___ UNSAT COMMENTS:
IF AT ANY TIME 1N-298 fails to close, notify operator to close 1N-137 (CFTs Supply). (A-2-Hallway).
___ SAT STANDARD: Acknowledges the IAAT step to notify an operator to 8 2.2.6 close 1N-137 if 1N-298 fails to close.
___ UNSAT COMMENTS:
WHEN pressurization of 1A CFT complete, close 1N-298 (N2 FILL CORE FLOOD TANK 1A). CRITICAL STEP STANDARD: Close the 1N-298 located on 1VB2 when Core Flood Tank pressure is approximately 600 psig (595 to 605 psig). Verify CFT pressure stops increasing. ___ SAT 9 2.2.7 COMMENTS:
___ UNSAT END TASK TIME STOP: ________
(RO-203) Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 1N-137 must be opened to supply Nitrogen to pressurize the CFT.
4 1N-298 must be opened to supply Nitrogen to pressurize the CFT.
9 1N-298 must be closed to prevent over pressurizing the CFT.
h CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 is operating at 100% power Core Flood Tank low pressure Statalarm actuated OP/1/A/1104/001 (Core Flooding System) Enclosure 4.7 (Pressure Makeup To CFTs Using Nitrogen) is in progress INITIATING CUES The CR SRO directs you to pressurize the 1A CFT to 600 (595-605) psig beginning at Step 2.1 of Enclosure 4.7
AO-501 i Page 1 of 13 REGION II JOB PERFORMANCE MEASURE AO-501 PLACE THE REACTOR BUILDING HYDROGEN ANALYZER IN SERVICE Administrative: No Classroom/Simulator/Plant: Plant Alternate Path: No Alt Path Failure:
Time Critical: No Time Critical Criteria:
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
AO-501 i Page 2 of 13 REGION II JOB PERFORMANCE MEASURE Task
Title:
Place the 1A Reactor Building Hydrogen Analyzer In Service Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 12 minutes K/A Rating(s):
System: 028 K/A: A4.03 Rating: 3.1/3.3 Task Standard:
Reactor Building Hydrogen Analyzers are placed in service by procedure within 90 minutes.
References:
EP/1/A/1800/001 EOP Enclosure 5.2, Placing RB Hydrogen Analyzers in Service Tools/Equipment/Procedures Needed:
EOP Enclosure 5.2 Placing RB Hydrogen Analyzers in Service Rev. 001
=========================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
AO-501 i Page 3 of 13 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None
AO-501 i Page 4 of 13 READ TO OPERATOR DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS A LOCA has occurred on Unit 1.
Engineered Safeguards Channels 1 and 2 have actuated. .1 (ES Actuation) of the EOP is in progress.
The 1A and 1B RB Hydrogen Analyzer Trains are aligned in the standby mode.
INITIATING CUES The Control Room SRO directs you to place both trains of the RB Hydrogen Analyzers in service on Unit 1 per EOP Enclosure 5.2 (PS), (Placing RB Hydrogen Analyzers in Service).
AO-501 i Page 5 of 13 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP NOTE Hydrogen analyzer (RP) panels are located in A-6-602, Vent Equipment Rm, col Q73 West.
At 1A H2 ANALYZER (RP), perform the following:
__ Ensure POWER ON light is on
__ Position H2 DUAL RANGE SW to H2 0 -10% Range
__ Position FUNCTION SELECTOR switch to SAMPLE Depress the OFF button for the following:
__ 1PR-83 (BYP TO POST AC 1SV220)
__ 1PR-86 (BYP TO POST AC 1SV221)
STANDARD: Red "Power On" light on remote panel is verified to be ON at the Remote RB Hydrogen Analyzer Panel (Train A).
Examiner Cue: Indication is as you see it.
___ SAT H2 DUAL RANGE Sw. on the Remote Panel is verified to be positioned to the "0-10%" scale.
1 1 Examiner Cue: Indication is as you see it.
FUNCTION SELECTOR SWITCH on the Remote Panel ___ UNSAT is verified to be positioned in the "SAMPLE" position.
Examiner Cue: Indication is as you see it.
At the remote panel, the "OFF" button is pushed for the following valves:
__ 1PR-83 (BYP TO POST AC 1SV220)
__ 1PR-86 (BYP TO POST AC 1SV221)
Examiner Cue: OFF button is depressed and indications are as you see them.
COMMENTS:
AO-501 i Page 6 of 13 SEQ PROC DESCRIPTION STEP STEP At 1B H2 ANALYZER (RP), perform the following:
__ Ensure POWER ON light is on
__ Position H2 DUAL RANGE SW to H2 0 -10% Range
__ Position FUNCTION SELECTOR switch to SAMPLE Depress the OFF button for the following:
__ 1PR-89 (BYP TO POST AC 1SV222)
__ 1PR-92 (BYP TO POST AC 1SV223)
STANDARD: Red "Power On" light on remote panel is verified to be ON at the Remote RB Hydrogen Analyzer Panel (Train B).
Examiner Cue: Indication is as you see it.
H2 DUAL RANGE Sw. on the Remote Panel is verified to be positioned to the "0-10%" scale. ___ SAT Examiner Cue: Indication is as you see it.
FUNCTION SELECTOR SWITCH on the Remote Panel 2 2 is verified to be positioned in the "SAMPLE" position.
___ UNSAT Examiner Cue: Indication is as you see it.
At the remote panel, the "OFF" button is pushed for the following valves:
__ 1PR-89 (BYP TO POST AC 1SV222)
__ 1PR-92 (BYP TO POST AC 1SV223)
Examiner Cue: OFF button is depressed and indications are as you see them.
COMMENTS:
AO-501 i Page 7 of 13 SEQ PROC DESCRIPTION STEP STEP Notify the Control Room to perform the following:
__ Open 1PR-87 and 1PR-90 CRITICAL STANDARD: Unit 1 Control Room personnel are notified to open 1PR- STEP 81, 1PR-84, 1PR-87, and 1PR-90 to align the Reactor Building Hydrogen Analyzer to the Reactor Building.
Examiner Cue: After notification has been made, indicate to student ___ SAT 3 3 that the red OPEN indication lights for all four valves located at the Remote Panel are ON and green lights are off.
___ UNSAT COMMENTS:
AO-501 i Page 8 of 13 SEQ PROC DESCRIPTION STEP STEP NOTE When ANALYZE is selected, the indication will go up scale, possibly causing a HIGH HYDROGEN ALARM in the Analyzer Panel, the Remote Panel, and the Control Room. It should return down scale to the correct reading in 3 minutes.
At 1A H2 ANALYZER (RP), perform the following:
__ Position SAMPLE VALVE SEL SW to PR-71 (Top Of Containment Sample).
__ Position OFF / STANDBY / ANALYZE switch to ANALYZE.
__ Depress REMOTE SELECTOR pushbutton to ensure control is from the Remote Panel.
STANDARD: The SAMPLE VALVE SEL switch is positioned to PR-71.
Examiner Cue: Point to the Sample Valve Selector Switch and state switch is in the PR-71 position and the red light is illuminated. CRITICAL STEP The OFF / STANDBY / ANALYZE switch is placed to the ANALYZE position.
Examiner Cue: Point to the Off/Standby/Analyze Switch and state the switch is in Analyze position. The Hydrogen ___ SAT 4 4 Concentration Meter reads approximately 3%
hydrogen and the Yellow COMMON ALARM Light and Yellow HIGH HYDROGEN ALARM Lights are ON.
The REMOTE SELECTOR Pushbutton is depressed.
___ UNSAT Examiner Cue: Pushbutton is depressed.
Examiner Cue: Inform candidate that using time compression approximately three minutes have elapsed.
Examiner Cue: Inform the candidate that the Hydrogen Concentration Meter indicating 0% hydrogen concentration.
Examiner Cue: Inform the candidate that the High alarm is extinguished and the Common alarm is still illuminated.
COMMENTS:
AO-501 i Page 9 of 13 SEQ PROC DESCRIPTION STEP STEP NOTE When ANALYZE is selected, the indication will go up scale, possibly causing a HIGH HYDROGEN ALARM in the Analyzer Panel, the Remote Panel, and the Control Room. It should return down scale to the correct reading in 3 minutes.
At 1B H2 ANALYZER (RP), perform the following:
__ Position SAMPLE VALVE SEL SW to PR-76 (Top Of Containment Sample).
__ Position OFF / STANDBY / ANALYZE switch to ANALYZE.
__ Depress REMOTE SELECTOR pushbutton to ensure control is from the Remote Panel.
STANDARD: The SAMPLE VALVE SEL switch is positioned to PR-76.
Examiner Cue: Point to the Sample Valve Selector Switch and state switch is in the PR-76 position and the red light is illuminated. CRITICAL STEP The OFF / STANDBY / ANALYZE switch is placed to the ANALYZE position.
Examiner Cue: Point to the Off/Standby/Analyze Switch and state the switch is in Analyze position. The Hydrogen ___ SAT 5 5 Concentration Meter reads approximately 3%
hydrogen and the Yellow COMMON ALARM Light and Yellow HIGH HYDROGEN ALARM Lights are ON.
The REMOTE SELECTOR Pushbutton is depressed.
___ UNSAT Examiner Cue: The Remote Selector Pushbutton is depressed.
Examiner Cue: Inform candidate that using time compression approximately three minutes have elapsed.
Examiner Cue: Inform the candidate that the Hydrogen Concentration Meter is indicating 0% hydrogen concentration.
Examiner Cue: Inform the candidate that the High alarm is extinguished and the Common alarm is still illuminated.
COMMENTS:
AO-501 i Page 10 of 13 SEQ PROC DESCRIPTION STEP STEP IAAT either RB Hydrogen Analyzer Train indicates < 2.25% Hydrogen, AND the meter reading stabilizes, THEN push the ALARM RESET pushbutton to reset the COMMON ALARM on appropriate train:
__ 1A RB Hydrogen Analyzer Train
__ 1B RB Hydrogen Analyzer Train CRITICAL STANDARD: The ALARM RESET Pushbutton is depressed for both STEP trains.
Examiner Cue: Indicate that the Hydrogen reading is 0 percent on both trains. ___ SAT 6 6 Examiner Cue: Indicate to student that both yellow alarm lights are out after the ALARM RESET Pushbutton is depressed for each train. ___ UNSAT COMMENTS:
WHEN HIGH HYDROGEN alarm has been reset on both 1A and 1B RB Hydrogen Analyzer Trains, THEN notify Unit 1 Control Room that 1A and 1B Hydrogen Analyzer Trains are in service.
___ SAT STANDARD: Phone/radio is located and control room personnel are notified that the RB Hydrogen Analyzers are in service.
Examiner Cue: Indicate to student that Unit 1 Control Room has
___ UNSAT 7 7 been notified that 1A and 1B Hydrogen Analyzer Trains are in service.
COMMENTS:
AO-501 i Page 11 of 13 SEQ PROC DESCRIPTION STEP STEP EXIT this enclosure.
___ SAT STANDARD: The enclosure is exited.
8 8 COMMENTS: ___ UNSAT END TASK TIME STOP: ________
AO-501 i Page 12 of 13 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
3 This step opens the block valves to the 1A and 1B H2 analyzers.
4 This step starts the Analyzer pump and the sampling process for the 1A H2 Analyzer.
5 This step starts the Analyzer pump and the sampling process for the 1B H2 Analyzer.
6 This step is required to enable the Control Room to detect an increase in H2 concentration.
i CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS A LOCA has occurred on Unit 1.
Engineered Safeguards Channels 1 and 2 have actuated. .1 (ES Actuation) of the EOP is in progress.
The 1A and 1B RB Hydrogen Analyzer Trains are aligned in the standby mode.
INITIATING CUES The Control Room SRO directs you to place both trains of the RB Hydrogen Analyzers in service on Unit 1 per EOP Enclosure 5.2 (PS), (Placing RB Hydrogen Analyzers in Service).
AO-S404a k Page 1 of 9 REGION II JOB PERFORMANCE MEASURE AO-S404a MS-87, MS-126 & MS-129 ISOLATION Administrative: No Classroom/Simulator/Plant: Plant Alternate Path: Yes Alt Path Failure: 1MS-125 will not close Time Critical: No Time Critical Criteria:
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
AO-S404a k Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task
Title:
MS-87, MS-126 & MS-129 Isolation Task Number:
Alternate Path: Yes Time Critical: No Validation Time: 15 min K/A Rating(s):
System: SYS039 K/A: A4.01 Rating: 2.9/2.8 Task Standard:
1MS-87, 1MS126 & 1MS-129 are isolated in accordance with AP/0/A/1700/025 Enclosure 5.13
References:
AP/0/A/1700/025 (SSF Emergency Operating Procedure) Rev 64 Tools/Equipment/Procedures Needed:
AP/0/A/1700/025 Enclosure 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
(Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
AO-S404a k Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None
AO-S404a k Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS The SSF has been activated for a Challenging Fire that occurred in the Unit 1 Control Room SSF RCMU and SSF ASW feed have been established for Unit 1 AP/0/A/1700/025 (SSF Emergency Operating Procedure) is in progress and Step 4.27 directs an operator to perform Enclosure 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
INITIATING CUE The CRS directs you to perform AP/25 Enclosure 5.13 for Unit 1 only
AO-S404a k Page 5 of 9 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP NOTE
- Each affected units *MS-87, *MS-126 & *MS-129 must be isolated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- Perform steps on affected unit only Locally close the following on the affected units:
__ *1MS-86 (MS To TD EFDWP Control Inlet Block)
(T-3/NW of D-15)
__ 2MS-86 (MS To TD EFDWP Control Inlet Block)
(T-1/12' E of C-38)
- CRITICAL
__ 3MS-86 (MS To EFDWPT Control Inlet Block) STEP (T-1/12' E of C-52) 1 1 ___ SAT STANDARD: Candidate determines that Unit 1 is the affected unit from the initial conditions and locates 1MS-86 and simulates rotating the handwheel clockwise to a hard
___ UNSAT stop.
Examiner Cue: Inform candidate that the valve is closed following handwheel rotation in the clockwise direction.
COMMENTS:
AO-S404a k Page 6 of 9 SEQ PROC DESCRIPTION STEP STEP Locally close the following on the affected units:
__ 1MS-125 (MS To Aux Steam Inlet Block) (T-3/L-15)
__ 2MS-125 (MS To Aux Steam Control Inlet Blk)
(T-3/Between L-40 & M-40)
__ 3MS-125 (MS To Aux Steam Control Inlet Block) (T-3/K-55)
STANDARD: Candidate determines that Unit 1 is the affected unit from the initial conditions and locates 1MS-125 and ___ SAT attempts to operate the valve.
2 2 Examiner Cue: After the candidate attempts to operate ___ UNSAT 1MS-125, state that the valve handwheel will NOT move.
Candidate continues to Step 2 RNO.
COMMENTS:
ALTERNATE PATH IF the affected unit's *MS-125 will NOT close, THEN close the following on the affected units:
__ *1MS-127 (MS To Aux Steam Control Outlet Block)
(T-3/Between L-15 & M-15)
__ 2MS-127 (MS To Aux Steam Control Outlet Block) (T-3/L-40)
__ 3MS-127 (MS To Aux Steam Control Outlet Block) *CRITICAL (T-3/Between K-55 & K-56) STEP 2 STANDARD: Candidate determines that Unit 1 is the affected unit 3 ___ SAT RNO from the initial conditions and locates 1MS-127 and simulates rotating the handwheel clockwise to a hard stop
___ UNSAT Examiner Cue: Inform candidate that the valve is closed following handwheel rotation in the clockwise direction.
COMMENTS:
AO-S404a k Page 7 of 9 SEQ PROC DESCRIPTION STEP STEP Locally close the following on the affected units:
__ *1MS-128 (MS To Aux Steam Regulator Inlet Block) (T-3/M-15)
__ 2MS-128 (MS To Aux Steam Regulator Inlet Block)
(T-3/Between L-40 & M-40)
__ 3MS-128 (MS To Aux Steam Regulator Inlet Blk) (T-3/K-55)
- CRITICAL STEP STANDARD: Candidate determines that Unit 1 is the affected unit from the initial conditions and locates 1MS-128 and 4 3 simulates rotating the handwheel clockwise to a hard ___ SAT stop.
Examiner Cue: Inform candidate that the valve is closed following handwheel rotation in the clockwise ___ UNSAT direction.
COMMENTS:
EXIT this enclosure STANDARD: Candidate exits the enclosure.
Examiner Cue: Inform candidate that the task is complete. ___ SAT 5 4 COMMENTS:
___ UNSAT END TASK TIME STOP: ________
AO-S404a k Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 This step is required to help ensure RCS overcooling does not occur which could interrupt natural circulation while SSF ASW is feeding the SGs.
3 This step is required to help ensure RCS overcooling does not occur which could interrupt natural circulation while SSF ASW is feeding the SGs.
4 This step is required to help ensure RCS overcooling does not occur which could interrupt natural circulation while SSF ASW is feeding the SGs.
k CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS The SSF has been activated for a Challenging Fire that occurred in the Unit 1 Control Room SSF RCMU and SSF ASW feed have been established for Unit 1 AP/0/A/1700/025 (SSF Emergency Operating Procedure) is in progress and Step 4.27 directs an operator to perform Enclosure 5.13 (*MS-87, *MS-126 & *MS-129 Isolation)
INITIATING CUE The CRS directs you to perform AP/25 Enclosure 5.13 for Unit 1 only
AO-802 k Page 1 of 11 REGION II JOB PERFORMANCE MEASURE AO-802 ISOLATE HPSW AND LPSW DURING AN AB FLOOD Administrative: No Classroom/Simulator/Plant: Plant Alternate Path: No Alt Path Failure:
Time Critical: No Time Critical Criteria:
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
AO-802 k Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Isolate HPSW and LPSW during an AB Flood Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):
System: BW/A07 K/A: AA2.2 Rating: 3.3/3.7 Task Standard:
Isolate portions of the HPSW and LPSW systems during an AB Flood using AP/3/A/1700/030 Auxiliary Building Flood
References:
AP/3/A/1700/030 Auxiliary Building Flood Rev 20 Tools/Equipment/Procedures Needed:
AP/3/A/1700/030 Enc 5.1 (HPSW AB Flood Isolation) and Enc 5.2 (LPSW AB Flood Isolation)
=========================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
AO-802 k Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None
AO-802 k Page 4 of 11 READ TO OPERATOR DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS All 3 units are at 100% power Unit 3 Auxiliary Building flooding is occurring The source of flood water has not yet been determined INITIATING CUES The Control Room Supervisor directs you to perform AP/3/A/1700/030 Encl. 5.1 (HPSW AB Flood Isolation) AND Encl. 5.2 (LPSW AB Flood Isolation)
AO-802 k Page 5 of 11 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Examiner Note: If candidate performs Enclosure 5.2 first, it begins 1
on SEQ Step 6.
IAAT the source of flooding is isolated, THEN notify Control Room.
STANDARD: The candidate notes the source of flooding is not isolated.
__SAT 5.1 Examiner Cue: If asked, flooding is still occurring.
2 Step Candidate continues to step 2. __UNSAT 1
COMMENTS:
NOTE Keys for valve locks are available in any Emergency Equipment cabinet.
Close HPSW-959 (HPSW SUPPLY TO FLOW LIMITER BLOCK VALVE) (T-1/M-21 south, west of RCW Heat Exchangers).
STANDARD: The candidate locates and closes HPSW-959 rotating it in the clockwise direction until it stops.
CRITICAL Examiner Note: Operators would normally carry keys to these STEP locks.
3 2 Examiner Cue: When the candidate simulates rotating the hand __SAT wheel in the clockwise direction, inform the candidate that the valve is fully clockwise and on the hard stop. __UNSAT Candidate continues to step 3.
COMMENTS:
AO-802 k Page 6 of 11 SEQ PROC DESCRIPTION STEP STEP Notify Control Room HPSW isolation is complete.
STANDARD: The candidate notifies the Unit 3 Control Room that HPSW isolation is complete.
Examiner Cue: Notify candidate that U3 Control Room has been
__SAT notified.
4 3 Candidate continues to step 4.
__UNSAT COMMENTS:
EXIT this enclosure.
STANDARD: The candidate EXITS Enc 5.1 and proceeds to Enc 5.2
__SAT 5 4 COMMENTS:
__UNSAT IAAT the source of flooding is isolated, THEN notify Control Room.
STANDARD: The candidate notes the source of flooding is not isolated.
ENC Examiner Cue: If asked, flooding is still occurring. __SAT 5.2 6
Candidate continues to step 2.
Step
__UNSAT 1
COMMENTS:
AO-802 k Page 7 of 11 SEQ PROC DESCRIPTION STEP STEP Close 3LPSW-844 (Aux Bldg AHU Supply) (T-1/M-46, 6 SE).
STANDARD: The candidate locates and closes 3LPSW-844 by rotating it in the clockwise direction until it stops.
Examiner Cue: When the candidate simulates rotating the hand wheel in the clockwise direction, inform the CRITICAL candidate that the valve is fully clockwise and on STEP the hard stop.
7 2 Candidate continues to step 3. __SAT COMMENTS: __UNSAT Close 3LPSW-770 (Aux Bldg AHU Supply) (T-1/M-46, 8 S).
STANDARD: The candidate locates and closes 3LPSW-770 by rotating it in the clockwise direction until it stops.
Examiner Cue: When the candidate simulates rotating the hand CRITICAL wheel in the clockwise direction, inform the STEP candidate that the valve is fully clockwise and on the hard stop.
8 3
__SAT Candidate continues to step 4.
COMMENTS: __UNSAT
AO-802 k Page 8 of 11 SEQ PROC DESCRIPTION STEP STEP Open 3LPSW-501 (Unit 3 AHU return to Storm Drains) (T-1/L-47, NW 12 up on chain).
STANDARD: The candidate locates and opens 3LPSW-501 by rotating it in the counter-clockwise direction until it stops.
Examiner Cue: When the candidate simulates rotating the hand wheel in the counter-clockwise direction, inform
__SAT the candidate that the valve is fully counter-9 4 clockwise and on the hard stop.
__UNSAT Candidate continues to step 5.
COMMENTS:
IAAT 3LPSW-501 (Unit 3 AHU return to Storm Drains) is open, THEN close 3LPSW-500 (Unit 3 AHU return to CCW Discharge) (T-1/L-47, NW 12 up on chain)
STANDARD: The candidate locates and closes 3LPSW-500 by rotating it in the clockwise direction until it stops.
CRITICAL Examiner Cue: When the candidate simulates rotating the hand STEP wheel in the clockwise direction, inform the candidate that the valve is fully clockwise and on 10 5 the hard stop. __SAT Candidate continues to step 6.
__UNSAT COMMENTS:
AO-802 k Page 9 of 11 SEQ PROC DESCRIPTION STEP STEP Notify Control Room of the following:
__LPSW Turbine Building isolation status
__Monitor operating HPI pump motor temperatures STANDARD: The candidate contacts the control room by phone or radio and informs them that Turbine Building LPSW is isolated and to Monitor operating HPI pump motor temperatures
__SAT Examiner Cue: Notify candidate that U3 Control Room has been 11 6 notified.
__UNSAT Candidate continues to step 7.
COMMENTS:
EXIT this enclosure.
STANDARD: The candidate EXITS Enc 5.2 and returns CUE Sheet to examiner
__SAT 12 7 COMMENTS:
__UNSAT END OF TASK TIME STOP: ________
AO-802 k Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
3 Step ensures proper isolation of HPSW leak.
7 Step ensures proper isolation of LPSW leak.
8 Step ensures proper isolation of LPSW leak.
10 Step ensures proper isolation of LPSW leak.
k CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS All 3 units are at 100% power Unit 3 Auxiliary Building flooding is occurring The source of flood water has not yet been determined INITIATING CUES The Control Room Supervisor directs you to perform AP/3/A/1700/030 Encl. 5.1 (HPSW AB Flood Isolation) AND Encl. 5.2 (LPSW AB Flood Isolation)
ADM-114 1.1R Page 1 of 12 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-114 Manually Calculate Shutdown Margin To be performed on the same day as SRO ADM-S111 Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
ADM-114 1.1R Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task
Title:
Manually Calculate Shutdown Margin Task Number:
Alternate Path: No Time Critical: No Validation Time: 25 minutes K/A Rating(s):
System: Gen K/A: 2.1.43 Rating: (4.1/4.3)
Task Standard: Shutdown Margin agrees with attached example
References:
PT/1/A/1103/015 (Reactivity Balance Procedure (Unit 1)) Rev 79 Tools/Equipment/Procedures Needed:
PT/1/A/1103/015 (Reactivity Balance Procedure (Unit 1)) Rev 79 Calculator Straight Edge (ruler or transparency paper)
=========================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
ADM-114 1.1R Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
ADM-114 1.1R Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 has been shutdown for 15 days for leak repair. The following conditions exist:
- Cycle burnup = 300 EFPD
- RCS temperature = 300°F
- Control Rod Group 1 at 0% withdrawn
- Control Rod Group 8 at 35% withdrawn
- The RHOCALC program is NOT available INITIATING CUES
- 1) The CRS directs you to perform the Original manual calculation of SDM using PT/1/A/1103/015, Reactivity Balance Procedure.
- The calculation is NOT being performed for a Control Rod Trip Time test.
- Determine Differential Boron Worth, if required, to five (5) decimal places for calculations.
- Determine Temperature Coefficient, if required, to five (5) decimal places for calculations.
- Express your final answer of SDM to three (3) decimal places.
CALCULATED SDM:_________________
ADM-114 1.1R Page 5 of 12 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP This enclosure must be performed twice - the second is the separate verification. Indicate whether this is the original or the verification.
STANDARD: Candidate checks Original Calculation ___ SAT
___ UNSAT 1 2.1 COMMENTS:
Enter the conditions for which this calculation is effective:
Core Burnup:_____EFPD RCS Temperature_____°F CRD Grp 1 Posn:_____%wd CRD Grp8 Posn:_____%wd NOTE: The Xe/Sm time interval is normally 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. However, any time interval may be used. This time interval is only required if credit is to be taken for Xenon/Samarium.
___ SAT Xenon/Samarium time interval valid from:
Date/Time:________to Date/Time:________
___ UNSAT 2 2.2 STANDARD: Candidate enters the following data:
Core Burnup:_300_EFPD RCS Temperature_300_°F CRD Grp 1 Posn:__0__%wd CRD Grp8 Posn:__35_%wd Candidate marks N/A for Xenon/Samarium date/time.
COMMENTS:
ADM-114 1.1R Page 6 of 12 SEQ PROC DESCRIPTION STEP STEP Obtain reference Shutdown Boron Concentration using the effective Burnup and RCS Temp from Step 2.2 by performing one of the following:
CRITICAL
- Enclosure 13.10 (Shutdown Boron Concentration vs. Burnup STEP (Group 1 @ 0% wd)) if CRD Groups 1-7 are at 0% wd OR
- Enclosure 13.11 (Shutdown Boron Concentration vs Burnup ___ SAT (Group 1 @ 50% wd)) if CRD Group 1 is at 50% and Group 2-7 are at 0% wd
______ppmB ___ UNSAT positive 3 2.3 STANDARD: Candidate references Enclosure 13.10 curve on page 1 or Table on page 2 for 300F and 300 EFPD and determines that shutdown boron is:
1305 ppmB (1300-1310)
COMMENTS:
Adjust for non-referenced conditions as follows:
STANDARD: Candidate should determine from the INITIAL ___ SAT CONDITIONS that no adjustments are required.
Steps 2.4.1 through 2.4.4 are N/A 2.4.1
___ UNSAT 4 to
2.4.4 COMMENTS
Sum steps 2.4.1 + 2.4.2 + 2.4.3 + 2.4.4 = _____
STANDARD: Candidate should determine sum is 0 (zero) ___ SAT 5 2.4.5 ___ UNSAT COMMENTS:
ADM-114 1.1R Page 7 of 12 SEQ PROC DESCRIPTION STEP STEP Obtain boron concentration adjustment by dividing Step 2.4.5 by Differential Boron Worth from Enc. 13.8 (Differential Worth vs Burnup)
___ SAT STANDARD: Candidate should determine sum is 0 (zero) 6 2.4.6 ___ UNSAT COMMENTS:
If Group 8 is NOT at its nominal postion as noted in Enc. 13.14 (Required Group 8 Position and Designed Cycle Length), subtract 50 ppmB from step 2.4.6 STANDARD: Candidate determines that step is N/A ___ SAT 7 2.4.7 ___ UNSAT COMMENTS:
Determine required shutdown boron concentration as follows:
Subtract Step 2.4.7 (IF Step 2.4.7 applicable) or Step 2.4.6 (IF Step 2.4.7 NOT applicable) from Step 2.3 to obtain the required Boron concentration for 1.00% K/K shutdown margin (assumes worst rod stuck out):
___ UNSAT 8 2.5.1 1305 ppmB - 0 ppmB = 1305 ppmB (1300 - 1310)
COMMENTS:
ADM-114 1.1R Page 8 of 12 SEQ PROC DESCRIPTION STEP STEP Obtain minimum RCS Boron Concentration for SSF operability from Enclosure 13.19 (Minimum RCS Boron Concentration to Maintain SSF Operability) using the Minimum Xenon from the effective time period:
Minimum RCS Boron for SSF operability = _____ppmB ___ SAT STANDARD: Candidate references Enclosure 13.19 curve on page 1 or Table on page 2 for 300 EFPD and No Xenon ___ UNSAT 9 2.5.2 and determines that Minimum RCS Boron is:
991 ppmB (980 - 1000)
COMMENTS:
Determine the minimum RCS Boron Concentration by recording the GREATER of Step 2.5.1 or Step 2.5.2:
Minimum RCS Shutdown Boron Concentration = _____ppmB ___ SAT STANDARD: Candidate determines that Step 2.5.1 (1305) is greater than Step 2.5.2 (991) ___ UNSAT 10 2.5.3 Minimum RCS Shutdown Boron Concentration =
1305 ppmB COMMENTS:
If desired, calculate actual shutdown margin as follows:
Record actual RCS conditions:
- RCS Temperature_____°F
___ UNSAT STANDARD: Candidate records Actual RCS Boron Concentration 11 2.6.1 (1425 ppm) and RCS Temperature (300°F)
COMMENTS:
ADM-114 1.1R Page 9 of 12 SEQ PROC DESCRIPTION STEP STEP Calculate the B10 corrected boron concentration by subtracting the 100 ppmB B10 depleation penalty from the measured boron concentration in Step 2.6.1:
- (Step 2.6.1) ___ppmB - 100 ppmB (B10 penalty) = ___ppmB CRITICAL STEP STANDARD: Candidate determines that step 2.6.1 (1425 ppmB) -
100 ppmB = 1325 ppmB
___ SAT 1325 ppmB
___ UNSAT COMMENTS:
12 2.6.2 Subtract the required Boron concentration in Step 2.5.1 from the actual Boron concentration in Step 2.6.2:
- (Step 2.6.2)____ppmB - (Step 2.5.1)____ppmB = ____ppmB CRITICAL STEP STANDARD: Candidate determines that step 2.6.1 (1325 ppmB) -
Step 2.5.1 (1305 ppmB) = 20 ppmB
___ SAT 20 ppmB (15 to 25 ppmB)
COMMENTS: ___ UNSAT 13 2.6.3
ADM-114 1.1R Page 10 of 12 SEQ PROC DESCRIPTION STEP STEP Calculate the actual shutdown margin by multiplying Step 2.6.3 by the Differential Boron Worth from Enc. 13.8 (Differential Boron Worth vs. Burnup) and subtracting 1.00% K/K: CRITICAL
- ((Step 2.6.3) ____ppmB * (Enc 13.8) ____%K/K/ppmB) - STEP 1.00% K/K = ____% K/K
___ SAT STANDARD: Candidate determines that step 2.6.3 (20 ppmB)
- Enc 13.8 value (-.00814% K/K) - 1.00% K/K = -
14 2.6.4 1.163% K/K ___ UNSAT
-1.163% K/K (-1.122% to -1.204% K/K)
COMMENTS:
TIME STOP: ________
ADM-114 1.1R Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
3 Step is required to calculate SDM 12 Step is required to calculate SDM 13 Step is required to calculate SDM 14 Step is required to calculate SDM
1.1R CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 has been shutdown for 15 days for leak repair. The following conditions exist:
- Cycle burnup = 300 EFPD
- RCS temperature = 300°F
- Control Rod Group 1 at 0% withdrawn
- Control Rod Group 8 at 35% withdrawn
- The RHOCALC program is NOT available INITIATING CUES
- 2) The CRS directs you to perform the Original manual calculation of SDM using PT/1/A/1103/015, Reactivity Balance Procedure.
- The calculation is NOT being performed for a Control Rod Trip Time test.
- Determine Differential Boron Worth, if required, to five (5) decimal places for calculations.
- Determine Temperature Coefficient, if required, to five (5) decimal places for calculations.
- Express your final answer of SDM to three (3) decimal places.
CALCULATED SDM:_________________
(ADM-116) R1.2 Page 1 of 10 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-116 Determine Time for SFP to Reach 200°F Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(ADM-116) R1.2 Page 2 of 10 REGION II JOB PERFORMANCE MEASURE Task Title : Determine time for SFP to reach 200°F Task Number :
Alternate Path: No Time Critical: No Validation Time: 15 min K/A Rating(s):
System: Gen K/A: 2.1.25 Rating: 3.9/4.2 Task Standard:
Tables in AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) are used to determine total time required for SFP temperature to reach 200ºF
References:
AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) Rev 24 Tools/Equipment/Procedures Needed:
AP/1-2/A/1700/035 Encl. 5.4 (Unit 1-2 SFP Time to Reach 180ºF, 200 ºF) Rev 24 (Note: Below this line is used only for Initial NRC Exams)
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Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(ADM-116) R1.2 Page 3 of 10 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
(ADM-116) R1.2 Page 4 of 10 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS
- Unit 1 is at 100% stable
- Unit 1 EFPD = 278
- Unit 2 EFPD = 35
- Unit 2 was operating at 100% when it experienced a Unit blackout
- SSF has been activated for Unit 2
- Unit 2 RCMUP is aligned and operating
- 2HP-426 is being cycled to maintain Pressurizer Level as directed by AP/25
- AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) has been initiated
- Unit 1 & 2 SFP level = 0.0 ft stable
- Unit 1 & 2 SFP temperature = 105ºF INITIATING CUES CRS has directed you to utilize AP/35 Enclosure 5.4 and determine the time for Unit 1&2 SFP to reach 200 ºF. Document your answer below.
Time for Unit 1&2 SFP to reach 200 ºF = _______________
(ADM-116) R1.2 Page 5 of 10 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Refer to tables A, B, and C below.
Only one row from one table below applies Check the row in Table A, B, or C that applies to current conditions, and then use Tables listed on subsequent pages of Enc. 5.4, as CRITICAL directed, to calculate SFP heat up times. STEP STANDARD: Candidate selects Table B and then chooses to use
___ SAT Table 11 based upon:
- SSF Event in progress for U1 or U2 with Unit letdown going to SFP ___ UNSAT
- U1 and U2 each have 177 Fuel Assemblies in RB COMMENTS:
1 1-3
(ADM-116) R1.2 Page 6 of 10 SEQ PROC DESCRIPTION STEP STEP NOTE
- Steps 4 and 5 below are used to determine Time (days). Time (days) is the number of days since Reactor shutdown associated with the most recent batch of Spent Fuel discharged to the SFP.
- Steps 7 and 8 provide guidance on how to round off current SFP temperature and Time (days), as determined by steps 4 or 5 and Step 6; to the most conservative value.
IF any:
- U1 is in a Refueling Shutdown Outage ___ SAT
- U2 is in a Refueling Shutdown Outage THEN perform following:
___ UNSAT A. IF either Unit has discharged fuel to U1-2 SFP during current Refueling outage, THEN: Time (days) = Total number of days 2 4 elapsed since first Fuel Assembly dischared to U1-2 SFP.
B. IF NO Unit has discharged fuel to U1-2 SFP during current Refueling outage, THEN: Time (days) = (Determine U1 and U2 Core EFPD. Use smaller of the two numbers.) + 20 Days STANDARD: Candidate determines step 4 is N/A and proceeds to step 5 COMMENTS:
IF U1 and U2 are NOT in a Refueling outage, THEN: Time (Days) =
(Determine U1 and U2 Core EFPD. Use smaller of the two numbers.) CRITICAL
+ 20 Days. STEP STANDARD: Candidate selects the Unit with the lower EFPD (Unit 2, ___ SAT 3 5 EFPD = 35) and adds 20.
35 + 20 = 55 days
___ UNSAT COMMENTS:
(ADM-116) R1.2 Page 7 of 10 SEQ PROC DESCRIPTION STEP STEP NOTE Initial SFP temperatures in the tables are given as Actual SFP Temperatures; instrument uncertainty needs to be considered when using these tables. This is accomplished by adding +1°F to the Indicated SFP temperature reading prior to entering tables to CRITICAL determine time to reach the various temperatures covered by the STEP tables.
Actual SFP Temperature = Indicated SFP Temperature _______ +1°F ___ SAT (instrument uncertainty).
4 6
___ UNSAT STANDARD: Candidate refers to the cue sheet and determines indicated SFP temperature = 105°F. Candidate adds 1°F to 105°F and determines Actual (corrected) SFP temperature = 106°F.
COMMENTS:
IF Actual SFP temperature is between values in table, THEN use higher temperature in table.
STANDARD: Candidate determines that the actual SFP Temperature CRITICAL of 106°F is between the 105°F and 110°F columns and STEP uses the higher (110°F) column
___ SAT COMMENTS:
5 7 ___ UNSAT
(ADM-116) R1.2 Page 8 of 10 SEQ PROC DESCRIPTION STEP STEP IF Actual Time (days) is between times in table, THEN use shorter time in Table CRITICAL STEP STANDARD: Candidate determines that the Time in Days (55 Days) is between the 54 and 57 rows and uses the lower (54 6 8 days) row ___ SAT COMMENTS: ___ UNSAT Determine the time for U1 & U2 SFP to reach 200°F based upon Table 11.
CRITICAL STANDARD: Candidate reads Table 11 using 110°F SFP STEP Temperature and 54 Days and determines the time required to reach 200°F is 9.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Table ___ SAT 7
11 COMMENTS:
___ UNSAT END TASK TIME STOP: ________
(ADM-116) R1.2 Page 9 of 10 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 Step is required to determine the time to reach 200°F 3 Step is required to determine the time to reach 200°F 4 Step is required to determine the time to reach 200°F 5 Step is required to determine the time to reach 200°F 6 Step is required to determine the time to reach 200°F 7 Step is required to determine the time to reach 200°F
R1.2 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS
- Unit 1 is at 100% stable
- Unit 1 EFPD = 278
- Unit 2 EFPD = 35
- Unit 2 was operating at 100% when it experienced a Unit blackout
- SSF has been activated for Unit 2
- Unit 2 RCMUP is aligned and operating
- 2HP-426 is being cycled to maintain Pressurizer Level as directed by AP/25
- AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) has been initiated
- Unit 1 & 2 SFP level = 0.0 ft stable
- Unit 1 & 2 SFP temperature = 105ºF INITIATING CUES CRS has directed you to utilize AP/35 Enclosure 5.4 and determine the time for Unit 1&2 SFP to reach 200 ºF. Document your answer below.
Time for Unit 1&2 SFP to reach 200 ºF = _______________
(ADM-204) 2R Page 1 of 9 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-204 Perform SG Downcomer Temperature Surveillance Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(ADM-204) 2R Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title : Perform SG Downcomer Temperatue Surveillance Task Number :
Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):
System: Gen K/A: 2.2.12 Rating: 3.7/4.1 Task Standard:
Perform SG Downcomer Temperature Surveillance by procedure for the 1A (ONLY) SG and determine that the surveillance requirement is NOT met for either of the specified computer points
References:
OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl 4.1 (Mode 1 & 2) and Encl.
4.19 (Channel Check Of OTSG Downcomer Temperatures) Rev 48 SLC 16.7.5 Steam Generator Overfill Protection Rev 11/15/12 Tools/Equipment/Procedures Needed:
OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)
OAC Screen capture image for SG information SLC 16.7.5 Steam Generator Overfill Protection (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(ADM-204) 2R Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
(ADM-204) 2R Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 Reactor power = 75%
OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) in progress.
INITIATING CUE The CRS directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) component check for the 1A SG Downcomer Temperature on page 6 of 17. Document your results below.
(ADM-204) 2R Page 5 of 9 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Verify All SG Downcomer Temperature computer points agree within 3°F of each other.
IF All SG Downcomer Temperatures DO NOT agree within 3°F of CRITICAL each other, then perform Enclosure 4.19, (Channel Check Of OTSG STEP Downcomer Temperatures).
___ SAT STANDARD: Candidate observes OAC computer points on the handout provided.
O1E2008 - 528.87°F ___ UNSAT O1E2009 - 538.97°F Enc 1 O1E2012 - 532.77°F 4.1 O1E2013 - 533.63°F Determines that the above OAC points do NOT agree within 3°F of each other, and continues to Enclosure 4.19, (Channel Check of OTSG Downcomer Temperatures).
COMMENTS:
Determine saturation temperature for 1A OTSG based on power level and 1A OTSG outlet pressure as follows:
Step 3.1.1 Determine 1A OTSG outlet pressure using any one of the following ___ SAT computer points:
- O1E2281 - 885 psig
- O1E2283 - 885 psig ___ UNSAT Enc
- O1E2031 - 885 psig 2 4.19
- O1E2032 - 885 psig
3.1.1 STANDARD
Using the OAC handout, determines that 1A OTSG pressure is 885 psig.
COMMENTS:
(ADM-204) 2R Page 6 of 9 SEQ PROC DESCRIPTION STEP STEP Using table in Section 4, determine the 1A OTSG saturation temperature based on power level and 1A OTSG Outlet Pressure obtained in step 3.1.1.
____________ 1A OTSG saturation temperature CRITICAL STEP STANDARD: Candidate determines that 1A OTSG saturation temperature is 533.45°F (533.4 - 533.5°F) by using the table in section 4. ___ SAT Examiner Note: Candidate must interpolate the values in Table ___ UNSAT
- 4. One way to do this is to determine the values at 75% power for 880 (532.8) and 890 (534.1).
3 3.1.2 534.1 - 532.8 = 1.3 1.3 divided by 10 = .13
.13 x 5 = 0.65 (1A SG Outlet press = 885) 0.65 + 532.8 = 533.45°F (Add to value for 880)
COMMENTS:
Compare O1E2008 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2:
___ SAT STANDARD: Candidate compares OAC point O1E2008 (528.87°F) to value calculated in step 3.1.2 (533.45°F).
___ UNSAT COMMENTS:
4 3.1.3
(ADM-204) 2R Page 7 of 9 SEQ PROC DESCRIPTION STEP STEP IF O1E2008 SG Lower Downcomer Temperature Loop A is NOT within + 4.9°F of the 1A OTSG saturation temperature, then enter CRITICAL Condition A of SLC 16.7.5 for OTSG overfill protection system STEP inoperable.
___ SAT STANDARD: Candidate determines that O1E2008 SG Lower 5 3.1.4 Downcomer Temperature Loop A (528.87°F) is within ___ UNSAT
+/- 4.9°F (difference is 4.58°F) of the 1A OTSG saturation temperature (533.45°F), and the step is N/A.
COMMENTS:
Compare O1E2009 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2
___ SAT STANDARD: Candidate compares OAC point O1E2009 (538.97°F) ___ UNSAT 6 3.1.5 to value calculated in step 3.1.2 (533.45°F).
COMMENTS:
IF O1E2009 SG Lower Downcomer Temperature Loop A is NOT within +/- 4.9°F of the 1A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system CRITICAL inoperable. STEP STANDARD: Candidate determines that O1E2009 SG Lower Downcomer Temperature Loop A (538.97) is NOT ___ SAT within +/- 4.9°F (difference is 5.52°F) of the 1A OTSG 7 3.1.6 saturation temperature (533.45°F), and entry into ___ UNSAT Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable is required.
COMMENTS:
END TASK TIME STOP: ________
(ADM-204) 2R Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 Step is required to complete the surveillance.
3 Step is required to complete the surveillance.
5 Step is required to complete the surveillance.
7 Determining that the computer points in Step 3.1.6 are out of the allowable band is critical to ensure that SLC 16.7.5 Condition A is entered.
2R CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 Reactor power = 75%
OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) in progress.
INITIATING CUE The CRS directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) component check for the 1A SG Downcomer Temperature on page 6 of 17. Document your results below.
ADM-307 3R Page 1 of 12 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-307 1RIA-40 Setpoint Calculation and Adjustment Administrative: Yes Classroom/Simulator/Plant: Simulator Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
ADM-307 3R Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task
Title:
1RIA-40 Setpoint Calculation and Adjustment Task Number:
Alternate Path: No Time Critical: No Validation Time: 25 min K/A Rating(s):
System: Gen K/A: 2.3.5 Rating: (2.9/2.9)
Task Standard:
1RIA-40 Setpoint calculations agree with the attached example and 1RIA-40 Alert and High setpoints are entered correctly into the RIA View Node
References:
PT/0/A/0230/001 Radiation Monitor Check Rev 176 Tools/Equipment/Procedures Needed:
PT/0/A/0230/001 Radiation Monitor Check Enc. 13.3 (1RIA-40 Setpoints)
PT/0/A/0230/001 Radiation Monitor Check Enc. 13.4 (1RIA-40 Setpoints and Primary to Secondary Leak Rate Calculations)
Calculator
=========================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
ADM-307 3R Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. RECALL IC-392
- 2. VERIFY 1RIA-40 counts = 87 cpm
- 3. Provide candidate with Encl. 13.3 and 13.4 of PT/0/A/0230/001.
- 4. Place simulator in RUN IF IC is unavailable, set RMORACT to 1 and RM40OVER to 259.5
ADM-307 3R Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 is at 100% Reactor Power 1RIA-40 is available U1 CSAEs are in service
- 1A CSAE flow: 12 ft3/min
- 1B CSAE flow: 15.5 ft3/min
- 1C CSAE flow: 13.5 ft3/min AP/1/A/1700/031 (Primary to Secondary Leakage) is NOT in effect RP reports reportable activity present in CSAE offgas:
- CSAE Ar-41: 2.13 E-6 µCi/ml Primary Chemistry reports the following sample results:
- RCS Xe-133: 0.289 µCi/ml
- RCS Ar-41: 0.372 µCi/ml INITIATING CUES The CRS directs you to perform PT/0/A/0230/001 Encl. 13.3 (1RIA-40 Setpoints).
NOTE: Calculation of Primary to Secondary Leak Rate is NOT required.
ADM-307 3R Page 5 of 12 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Determine 1RIA-40 High and Alert setpoints from one of the following:
- Enclosure 13.4 (1RIA-40 Setpoints and Primary To Secondary Leak Rate Calculations)
- AP/1/A/1700/031 (Primary To Secondary Leakage)
___ SAT Encl.
1 13.3 STANDARD: Candidate selects Enclosure 13.4 per the Initial 2.1 Conditions ___ UNSAT COMMENTS:
Verify one of the following:
- CSAEs are in service
- CSAEs are ready to be placed in service
___ SAT Encl.
2 13.4 STANDARD: Candidate determines that CSAEs are in service per the 1.1 Initial Conditions ___ UNSAT COMMENTS:
1RIA-40 available
___ SAT STANDARD: Candidate determines that 1RIA-40 is available from 3 1.2 Initial Conditions
___ UNSAT COMMENTS:
AP/1/A/1700/031 (Primary to Secondary Leakage) NOT in effect.
___ SAT STANDARD: Candidate should determine from the INITIAL 4 1.3 CONDITIONS that AP/31 is not in effect
___ UNSAT COMMENTS:
ADM-307 3R Page 6 of 12 SEQ PROC DESCRIPTION STEP STEP Enclosure 13.3 (1RIA-40 Setpoints) in progress STANDARD: The candidate started Enclosure 13.3 based upon SRO direction. ___ SAT 5 1.4 COMMENTS: ___ UNSAT IF RP reports NO reportable activity present in CSAE offgas:
STANDARD: Candidate should determine that step is N/A based upon Initial Conditions
___ SAT 6 2.1 COMMENTS:
___ UNSAT IF RP reports reportable activity present in CSAE offgas:
Record current RCS and CSAE sample results:
From Primary Chemistry: RCS Ar-41:_____µCi/ml From RP: CSAE Ar-41:_____µCi/ml STANDARD: Candidate should determine RCS Ar-41 is 0.372 µCi/ml and CSAE Ar-41 is 2.13 E-6 µCi/ml from Initial ___ SAT 2.2 Conditions 7 &
2.2.1 ___ UNSAT COMMENTS:
ADM-307 3R Page 7 of 12 SEQ PROC DESCRIPTION STEP STEP Identify 1RIA-40 current value count rate from view node: _____CPM STANDARD: Candidate determines 87 CPM from RIA View Node. ___ SAT 8 2.2.2 COMMENTS: ___ UNSAT Perform the following calculations:
- 1RIA-40 Setpoints per Section 3
- Primary To Secondary Leak Rate per Section 4 STANDARD: Candidate will perform Section 3 to determine setpoints. ___ SAT 9 2.2.3 Section 4 is not required to be performed per the cue sheet.
___ UNSAT COMMENTS:
Perform one of the following as required to obtain CSAE flow ft3/min
- If all three CSAE readings on scale (< 20 scfm (ft3/min),
calculate CSAE flow ft3/min as follows:
Total Unit 1 CSAE flow provided from operator rounds =
________ft3/min + ________ft3/min + ________ft3/min = _____ft3/min CSAE 1A CSAE 1B CSAE 1C Total CRITICAL 3
CSAE flow ft /min = Total Unit 1 CSAE flow provided from Operator STEP rounds + 21 ft3/min 10 3.1 CSAE flow ft3/min = _____________ ft3/min ___ SAT STANDARD: Candidate adds offgas flows (12 + 15.5 + 13.5) to 21 ___ UNSAT and gets 62 ft3/min CSAE flow ft3/min = 62 ft3/min COMMENTS:
ADM-307 3R Page 8 of 12 SEQ PROC DESCRIPTION STEP STEP Perform the following equations:
CRITICAL STEP 11 3.2 STANDARD: Candidate performs the following: ___ SAT Alert Setpoint = (87 CPM) X (0.372 µCi/ml) X (4.61 E-4 ft3/min)
(62 ft3/min) (2.13 E-6 µCi/ml) ___ UNSAT Alert Setpoint = 112.977 (112 - 114)
High Setpoint = (87 CPM) X (0.372 µCi/ml) X (2.77 E-3 ft3/min)
(62 ft3/min) (2.13 E-6 µCi/ml)
High Setpoint = 678.845 (678 - 682)
COMMENTS:
Record 1RIA-40 setpoints on Enclosure 13.3 (1RIA-40 Setpoints)
STANDARD: Candidate records the Alert setpoint (112 - 114) and the High setpoint (678 - 682) on Step 2.2 of Encl. 13.3
___ SAT Examiner Cue: If the candidate starts to perform Section 4 of Enc.
12 3.3 13.4, inform them that another RO will perform Section 4. ___ UNSAT COMMENTS:
ADM-307 3R Page 9 of 12 SEQ PROC DESCRIPTION STEP STEP
______ Approve calculated Alert setpoint.
SRO STANDARD: Candidate proceeds to step 2.4 Encl. ___ SAT 13.3 Examiner Cue: Inform the candidate that the SRO agrees with 13 whatever they decide.
2.3
___ UNSAT COMMENTS:
______ Approve calculated High setpoint.
SRO STANDARD: Candidate proceeds to step 2.5
___ SAT Examiner Cue: Inform the candidate that the SRO agrees with 14 2.4 whatever they decide.
___ UNSAT COMMENTS:
Record 1RIA-40 Alert as found setpoint: ________________ CPM STANDARD: Candidate records the 1RIA-40 as found Alert setpoint from the RIA view node COMMENTS: ___ SAT 15 2.5 ___ UNSAT
ADM-307 3R Page 10 of 12 SEQ PROC DESCRIPTION STEP STEP Insert 1RIA-40 Alert setpoint recorded in Step 2.2.
CRITICAL STANDARD: Candidate inserts the 1RIA-40 Alert setpoint (112 - STEP 114) in the Enable Controls screen Alert box for 1RIA-40 and depresses ENTER. ___ SAT 16 2.6 COMMENTS:
___ UNSAT Record 1RIA-40 High as found setpoint: ________________ CPM
___ SAT STANDARD: Candidate records the 1RIA-40 as found High setpoint from the RIA view node 17 2.7 ___ UNSAT COMMENTS:
Insert 1RIA-40 High setpoint recorded in Step 2.2.
CRITICAL STANDARD: Candidate inserts the 1RIA-40 High setpoint (678 - STEP 682) in the Enable Controls screen High box for 1RIA-40 and depresses ENTER. ___ SAT 18 2.8 COMMENTS:
___ UNSAT Perform a manual source check.
STANDARD: Candidate selects manual source check on the Enable Controls screen for 1RIA-40 and depresses ENTER. ___ SAT 19 2.9 COMMENTS: ___ UNSAT END TASK TIME STOP: ________
ADM-307 3R Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
10 Step is required to calculate 1RIA-40 setpoint 11 Step is required to calculate 1RIA-40 setpoint 16 Step is required to enter the new 1RIA-40 Alert setpoint 18 Step is required to enter the new 1RIA-40 High setpoint
3R CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 is at 100% Reactor Power 1RIA-40 is available U1 CSAEs are in service
- 1A CSAE flow: 12 ft3/min
- 1B CSAE flow: 15.5 ft3/min
- 1C CSAE flow: 13.5 ft3/min AP/1/A/1700/031 (Primary to Secondary Leakage) is NOT in effect RP reports reportable activity present in CSAE offgas:
- CSAE Ar-41: 2.13 E-6 µCi/ml Primary Chemistry reports the following sample results:
- RCS Xe-133: 0.289 µCi/ml
- RCS Ar-41: 0.372 µCi/ml INITIATING CUES The CRS directs you to perform PT/0/A/0230/001 Encl. 13.3 (1RIA-40 Setpoints).
NOTE: Calculation of Primary to Secondary Leak Rate is NOT required.
(ADM-S111) 1.1S Page 1 of 12 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-S111 Manually Calculate Shutdown Margin and Determine Any Required Actions To be performed on the same day as RO ADM-114 Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(ADM-S111) 1.1S Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task Title : Manually Calculate Shutdown Margin and Determine Any Required Actions Task Number :
Alternate Path: No Time Critical: No Validation Time: 30 minutes K/A Rating(s):
System: Gen K/A: 2.1.43 Rating: 4.1/4.3 Task Standard:
Shutdown margin calculation agrees with attached example and determination is made that TS 3.1.1 A must be entered.
References:
PT/1/A/1103/015 (Reactivity Balance Procedure (Unit 1)) Rev 79 Tools/Equipment/Procedures Needed:
PT/1/A/1103/015 (Reactivity Balance Procedure (Unit 1)) Rev 79 TS 3.1.1 Rev 374 Calculator Straight Edge (ruler or transparency paper)
(Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(ADM-S111) 1.1S Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
(ADM-S111) 1.1S Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 has been shutdown for 15 days for leak repair. The following conditions exist:
- Cycle burnup = 300 EFPD
- RCS temperature = 300°F
- Control Rod Group 1 at 0% withdrawn
- Control Rod Group 8 at 35% withdrawn
- The RHOCALC program is NOT available INITIATING CUES
- 1) The CRS directs you to perform the Original manual calculation of SDM using PT/1/A/1103/015, Reactivity Balance Procedure.
- 2) Evaluate the calculated SDM and determine all Tech Specs and SLCs that apply, if any, including all/any REQUIRED ACTIONS and COMPLETION TIMES.
-The calculation is NOT being performed for a Control Rod Trip Time test.
-Determine Differential Boron Worth, if required, to five (5) decimal places for calculations.
-Determine Temperature Coefficient, if required, to five (5) decimal places for calculations.
-Express your final answer of SDM to three (3) decimal places.
SDM: _____________
IF required:
TS/SLC: ___________
- Required Action: __________________
- Completion Time: __________________
(ADM-S111) 1.1S Page 5 of 12 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP This enclosure must be performed twice - the second is the separate verification. Indicate whether this is the original or the verification.
STANDARD: Candidate checks Original Calculation ___ SAT 1 2.1 COMMENTS:
___ UNSAT Enter the conditions for which this calculation is effective:
Core Burnup:_____EFPD RCS Temperature_____°F CRD Grp 1 Posn:_____%wd CRD Grp 8 Posn:_____%wd NOTE: The Xe/Sm time interval is normally 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. However, any time interval may be used. This time interval is only required if credit is to be taken for Xenon/Samarium.
Xenon/Samarium time interval valid from:
___ SAT Date/Time:________to Date/Time:________
___ UNSAT STANDARD: Candidate enters the following data:
Core Burnup:_300_EFPD RCS Temperature_300_°F CRD Grp 1 Posn:__0__%wd CRD Grp 8 Posn:__35_%wd 2 2.2 Candidate marks N/A for Xenon/Samarium date/time.
COMMENTS:
(ADM-S111) 1.1S Page 6 of 12 SEQ PROC DESCRIPTION STEP STEP Obtain reference Shutdown Boron Concentration using the effective Burnup and RCS Temp from Step 2.2 by performing one of the following:
- Enclosure 13.10 (Shutdown Boron Concentration vs. Burnup CRITICAL (Group 1 @ 0% wd)) if CRD Groups 1-7 are at 0% wd STEP OR
- Enclosure 13.11 (Shutdown Boron Concentration vs Burnup ___ SAT (Group 1 @ 50% wd)) if CRD Group 1 is at 50% and Group 2-7 are at 0% wd
______ppmB ___ UNSAT positive 3 2.3 STANDARD: Candidate references Enclosure 13.10 curve on page 1 or Table on page 2 for 300F and 300 EFPD and determines that shutdown boron is:
1305 ppmB (1300-1310)
COMMENTS:
Adjust for non-referenced conditions as follows:
___ SAT STANDARD: Candidate should determine from the INITIAL CONDITIONS that no adjustments are required. Steps 2.4.1 2.4.1 through 2.4.4 are N/A ___ UNSAT 4 to
2.4.4 COMMENTS
Sum steps 2.4.1 + 2.4.2 + 2.4.3 + 2.4.4 = _____
STANDARD: Candidate should determine sum is 0 (zero) ___ SAT 5 2.4.5 COMMENTS: ___ UNSAT
(ADM-S111) 1.1S Page 7 of 12 SEQ PROC DESCRIPTION STEP STEP Obtain boron concentration adjustment by dividing Step 2.4.5 by Differential Boron Worth from Enc. 13.8 (Differential Worth vs Burnup)
___ SAT STANDARD: Candidate should determine sum is 0 (zero)
___ UNSAT 6 2.4.6 COMMENTS:
If Group 8 is NOT at its nominal postion as noted in Enc. 13.14 (Required Group 8 Position and Designed Cycle Length), subtract 50 ppmB from step 2.4.6
___ SAT STANDARD: Candidate determines that step is N/A
___ UNSAT 7 2.4.7 COMMENTS:
Determine required shutdown boron concentration as follows:
Subtract Step 2.4.7 (IF Step 2.4.7 applicable) or Step 2.4.6 (IF Step 2.4.7 NOT applicable) from Step 2.3 to obtain the required Boron concentration for 1.00% K/K shutdown margin (assumes worst rod stuck out): ___ SAT
- Step 2.3 ppmB - Step 2.4.6 ppmB = _____ppmB
___ UNSAT 8 2.5.1 STANDARD: Determine the required boron is:
1305 ppmB - 0 ppmB = 1305 ppmB (1300 - 1310)
COMMENTS:
(ADM-S111) 1.1S Page 8 of 12 SEQ PROC DESCRIPTION STEP STEP Obtain minimum RCS Boron Concentration for SSF operability from Enclosure 13.19 (Minimum RCS Boron Concentration to Maintain SSF Operability) using the Minimum Xenon from the effective time period:
Minimum RCS Boron for SSF operability = _____ppmB
___ SAT STANDARD: Candidate references Enclosure 13.19 curve on page 1 or Table on page 2 for 300 EFPD and No Xenon and determines that Minimum RCS Boron is: ___ UNSAT 9 2.5.2 991 ppmB (980 - 1000)
COMMENTS:
Determine the minimum RCS Boron Concentration by recording the GREATER of Step 2.5.1 or Step 2.5.2:
Minimum RCS Shutdown Boron Concentration = _____ppmB
___ SAT STANDARD: Candidate determines that Step 2.5.1 (1305) is greater than Step 2.5.2 (991)
___ UNSAT 10 2.5.3 Minimum RCS Shutdown Boron Concentration =
1305 ppmB COMMENTS:
If desired, calculate actual shutdown margin as follows:
Record actual RCS conditions:
- RCS Temperature_____°F STANDARD: Candidate records Actual RCS Boron Concentration ___ UNSAT 11 2.6.1 (1385 ppm) and RCS Temperature (300°F)
COMMENTS:
(ADM-S111) 1.1S Page 9 of 12 SEQ PROC DESCRIPTION STEP STEP Calculate the B10 corrected boron concentration by subtracting the 100 ppmB B10 depleation penalty from the measured boron concentration in Step 2.6.1: CRITICAL
- (Step 2.6.1) ___ppmB - 100 ppmB (B10 penalty) = ___ppmB STEP STANDARD: Candidate determines that step 2.6.1 (1385 ppmB) - ___ SAT 100 ppmB = 1285 ppmB 1285 ppmB ___ UNSAT 12 2.6.2 COMMENTS:
Subtract the required Boron concentration in Step 2.5.1 from the actual Boron concentration in Step 2.6.2:
CRITICAL
- (Step 2.6.2)____ppmB - (Step 2.5.1)____ppmB = ____ppmB STEP STANDARD: Candidate determines that step 2.6.1 (1285 ppmB) -
___ SAT Step 2.5.1 (1305 ppmB) = -20 ppmB
-20 ppmB (-15 to -25 ppmB)
___ UNSAT 13 2.6.3 COMMENTS:
(ADM-S111) 1.1S Page 10 of 12 SEQ PROC DESCRIPTION STEP STEP Calculate the actual shutdown margin by multiplying Step 2.6.3 by the Differential Boron Worth from Enc. 13.8 (Differential Boron Worth vs. CRITICAL Burnup) and subtracting 1.00% K/K: STEP
- ((Step 2.6.3) ____ppmB * (Enc 13.8) ____%K/K/ppmB) -
1.00% K/K = ____% K/K
___ SAT STANDARD: Candidate determines that step 2.6.3 (-20 ppmB)
- Enc 13.8 value (-.00814% K/K) - 1.00% K/K = -.837% ___ UNSAT 14 2.6.4 K/K
-.837% K/K (-.879% to -.795% K/K)
COMMENTS:
Evaluate the calculated SDM CRITICAL STEP STANDARD: Candidate determines that TS LCO 3.1.1 is NOT met since SDM of -.795 to -.879 is less than 1% as required by the COLR. ___ SAT REQUIRED ACTION: Initiate boration to restore SDM to within limit with a COMPLETION TIME of 15 ___ UNSAT TS 15 Minutes per TS 3.1.1 Condition A
3.1.1 COMMENTS
END OF TASK TIME STOP: ________
(ADM-S111) 1.1S Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
3 Step is required to calculate SDM 12 Step is required to calculate SDM 13 Step is required to calculate SDM 14 Step is required to calculate SDM 15 Step is required to determine corrective actions based upon not meeting SDM
1.1S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 has been shutdown for 15 days for leak repair. The following conditions exist:
- Cycle burnup = 300 EFPD
- RCS temperature = 300°F
- Control Rod Group 1 at 0% withdrawn
- Control Rod Group 8 at 35% withdrawn
- The RHOCALC program is NOT available INITIATING CUES
- 1) The CRS directs you to perform the Original manual calculation of SDM using PT/1/A/1103/015, Reactivity Balance Procedure.
- 2) Evaluate the calculated SDM and determine all Tech Specs and SLCs that apply, if any, including all/any REQUIRED ACTIONS and COMPLETION TIMES.
-The calculation is NOT being performed for a Control Rod Trip Time test.
-Determine Differential Boron Worth, if required, to five (5) decimal places for calculations.
-Determine Temperature Coefficient, if required, to five (5) decimal places for calculations.
-Express your final answer of SDM to three (3) decimal places.
SDM: _____________
IF required:
TS/SLC: _________________
- Required Action: ____________________________
- Completion Time: ___________________________
(ADM-S112) 1.2S Page 1 of 9 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-S112 Manually Calculate Core Tilt Due to Loss of the OAC and Determine Any Required Actions and Completion Times Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(ADM-S112) 1.2S Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title : Manually Calculate Core Tilt Due to Loss of the OAC and Determine Any Required Actions and Completion Times Task Number :
Alternate Path: No Time Critical: No Validation Time: 35 minutes K/A Rating(s):
System: Gen K/A: 2.1.25 Rating: 3.9/4.2 Task Standard: Calculate Core Tilt by procedure within +/- 0.02% of the values given on the key.
Determine calculated tilt values exceeds the limits in the COLR and determine the correct TS Required Actions and Completion Times.
References:
PT/0/A/1103/019 Backup Incore Detector System Rev 07 OP/1/A/1105/014 Control Room Instrumentation Operation and Information Rev 48 PT/1/A/0600/001 Periodic Instrument Surveillance Rev 342 Unit 1 COLR Cycle 31 Rev 01 TS 3.2.3 QPT Tools/Equipment/Procedures Needed:
PT/0/A/1103/019 Backup Incore Detector System OP/1/A/1105/014 Control Room Instrumentation Operation and Information PT/1/A/0600/001 Periodic Instrument Surveillance Unit 1 COLR Cycle 31 TS 3.2.3 QPT Calculator (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(ADM-S112) 1.2S Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
(ADM-S112) 1.2S Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 has been operating at 100% power for 4 days. The following conditions exist:
- On the OAC the Computer Reactor Calculation Package for Incore Detector data calculations is OOS
- Backup Incore Chart Recorder "A" points are ALL operable
- Backup Incore Chart Recorder B is OOS
- 1NI-7 has just failed
- All Controls Rods are normal
- The CRS has verified per OP/1/A/1105/014, Control Room Instrumentation Operation And Information, (Encl. 4.13, Reactor Parameter information; Step 3.2.4) that Axial Imbalance and QPT surveillances must be performed using the Backup Incore Detectors.
- PT/1/A/1103/019, (Backup Incore Detector System) in progress:
Enclosure 13.3 (Axial Power Imbalance Calculation Sheet) has been calculated and verified.
Enclosure 13.4 (Quadrant Power Tilt Calculation Sheet) has been calculated but NOT verified.
INITIATING CUES
- 1) The CRS directs you, as the verifier, to calculate quadrant power tilt using PT/1/A/1103/019, Backup Incore Detector System, Enclosure 13.4 (Quadrant Power Tilt Calculation Sheet) using the attached data sheet.
- 2) Evaluate the calculated quadrant power tilt and determine all Tech Specs and SLCs that apply, if any, including all/any REQUIRED ACTIONS and COMPLETION TIMES.
QPT: _______________________
IF required:
TS/SLC: _____________________
- Required Action(s): ______________________
- Completion Time(s): _____________________
(ADM-S112) 1.2S Page 5 of 9 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Using Enclosure 13.2 (Required Backup Recorder Points for Calculating Quadrant Power Tilt) choose an acceptable set of recorder points for which all points are operable, AND record the point identifications (recorder, detector location) in the tables below. ___ SAT Enc STANDARD: Candidate fills in table on Enc. 13.4 with Recorder and 1 13.4 Core Location. SEE ATTACHED KEY 2.1 ___ UNSAT COMMENTS:
Record the backup recorder readings (R) on the blanks provided below.
CRITICAL STEP STANDARD: Candidate fills in table on Enc. 13.4 with Recorder and Core Location. SEE ATTACHED KEY 2 2.2 ___ SAT COMMENTS:
___ UNSAT Calculate quadrant power tilt as indicate below:
STANDARD: Candidate performs calculations using data from the Table. SEE ATTACHED KEY WX Quadrant = 2.07% CRITICAL STEP XY Quadrant = 5.14%
YZ Quadrant = -3.93%
3 2.3 ___ SAT ZW Quadrant = -3.28%
Examiner Note: Answers must be within + 0.02%
___ UNSAT COMMENTS:
(ADM-S112) 1.2S Page 6 of 9 SEQ PROC DESCRIPTION STEP STEP Determine any TS required actions and completion times.
STANDARD: Refer to the COLR and determine that Quadrant Power Tilt Setpoints are as follows: CRITICAL
- Backup Incore Steady State (30-100) = 2.58 STEP
- Backup Incore Transient (30-100) = 3.63
- Backup Incore Maximum (>0) = 10.07 Refer to TS 3.2.3 (Quadrant Power Tilt) and determine ___ SAT that the highest positive tilt is 5.14% and is above the Transient limit but less than the Maximum limit.
___ UNSAT TS 3.2.3 Condition D must be entered REQUIRED ACTION: Reduce THERMAL POWER to
< 60% of the ALLOWABLE THERMAL POWER with a COMPLETION TIME of 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />sAND...Reduce nuclear overpower trip setpoints, based on flux and flux/flow imbalance to < 65.5% of the ALLOWABLE THERMAL POWER.
TS 4
COLR COMMENTS:
END OF TASK TIME STOP: ________
(ADM-S112) 1.2S Page 7 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
2 Data must be entered correctly to ensure the proper tilt is calculated.
3 Calculation must be performed correctly to determine the tilt value.
4 Required to determine TS actions and completion times.
1.2S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 has been operating at 100% power for 4 days. The following conditions exist:
- On the OAC the Computer Reactor Calculation Package for Incore Detector data calculations is OOS
- Backup Incore Chart Recorder "A" points are ALL operable
- Backup Incore Chart Recorder B is OOS
- 1NI-7 has just failed
- All Controls Rods are normal
- The CRS has verified per OP/1/A/1105/014, Control Room Instrumentation Operation And Information, (Encl. 4.13, Reactor Parameter information; Step 3.2.4) that Axial Imbalance and QPT surveillances must be performed using the Backup Incore Detectors.
- PT/1/A/1103/019, (Backup Incore Detector System) in progress:
Enclosure 13.3 (Axial Power Imbalance Calculation Sheet) has been calculated and verified.
Enclosure 13.4 (Quadrant Power Tilt Calculation Sheet) has been calculated but NOT verified.
INITIATING CUES
- 1) The CRS directs you, as the verifier, to calculate quadrant power tilt using PT/1/A/1103/019, Backup Incore Detector System, Enclosure 13.4 (Quadrant Power Tilt Calculation Sheet) using the attached data sheet.
- 2) Evaluate the calculated quadrant power tilt and determine all Tech Specs and SLCs that apply, if any, including all/any REQUIRED ACTIONS and COMPLETION TIMES.
QPT: _______________________
IF required:
TS/SLC: _____________________
- Required Action(s): ______________________
- Completion Time(s): _____________________
1.2S BACKUP INCORE CHART A Point # % Location 1 132.7 G09-L2 2 138.0 G09-L4 3 133.3 G09-L6 4 145.6 E09-L2 5 145.3 E09-L4 6 142.5 E09-L6 7 128.8 G05-L2 8 133.8 G05-L6 9 126.3 M07-L2 10 122.9 M07-L6 11 127.5 K11-L2 12 122.2 K11-L6 13 144.4 F13-L2 14 145.0 D05-L2 15 143.1 F13-L4 16 142.5 C06-L2 17 144.5 C06-L6 18 133.6 F13-L6 19 133.8 O10-L6 20 135.5 L03-L6 21 136.1 L03-L2 22 135.6 D05-L6 23 133.8 O10-L2 24 142.5 D05-L4
ADM-S203 2S Page 1 of 8 REGION II JOB PERFORMANCE MEASURE ADM S203 COMPLETE PLANT CONFIGURATION SHEET (TIME TO CORE BOIL) AND DETERMINE ANY REQUIRED ACTIONS Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
ADM-S203 2S Page 2 of 8 REGION II JOB PERFORMANCE MEASURE Task
Title:
Complete Plant Configuration Sheet (Time to Core Boil) and Determine Any Required Actions Task Number:
Alternate Path: No Time Critical: No Validation Time: 20 minutes K/A Rating(s):
System: GEN K/A: 2.2.18 Rating: 2.6/3.9 Task Standard:
Tables in OP/0/A/1108/001 A are used to determine Total Loss of DHR Time to Boil is less than 16 minutes and that the RB Equipment Hatch must be closed
References:
OP/0/A/1108/001 A (Reactor Core and SFP Loss of Cooling Heatup Tables) Enclosure 4.1 (Total Loss of DHR Time to Boil) Rev 07 SD 1.3.5 (Shutdown Protection Plan) Attachment 9.2 (Plant Configuration Sheet) Rev 39 Tools/Equipment/Procedures Needed:
OP/0/A/1108/001 A (Reactor Core and SFP Loss of Cooling Heatup Tables) Enclosure 4.1 (Total Loss of DHR Time to Boil) Rev 07 SD 1.3.5 (Shutdown Protection Plan) Attachment 9.2 (Plant Configuration Sheet) Rev 39 (Note: Below this line is used only for Initial NRC Exams)
=========================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
ADM-S203 2S Page 3 of 8 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
ADM-S203 2S Page 4 of 8 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS
- Unit 1 was shutdown on 12/01 at 0400
- Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2 is being prepared for this shift
- LPI aligned for Normal Decay Heat Removal INITIATING CUE Current Date/Time: 12/03 at 0615 The CRS instructs you to determine the Time To Core Boil utilizing OP/0/A/1108/001 A, (Reactor Core and SFP Loss of Cooling Heatup Tables), and perform any required actions based on the results, in accordance with Site Directive 1.3.5 (Shutdown Protection Plan) .2. Document your answers below.
Time to Core Boil: _______________________
Required Action (if any): ______________________________
ADM-S203 2S Page 5 of 8 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Refer to Enclosure 4.1 of OP/0/A/1108/001 A.
Choose the correct Table CRITICAL STEP STANDARD: Refer to enclosure 4.1 of OP/0/A/1108/001 A, Table
___ SAT 9 (Initial Temp = 120ºF) (24-120 Hours); Time to 1 Boiling, Min. table.
___ UNSAT COMMENTS:
Determine the number of hours the reactor has been shutdown.
STANDARD: Candidate determines the reactor has been shut CRITICAL down for 50 Hours: STEP
- shutdown 12/01 at 0400
- current date/time is 12/03 at 0615 ___ SAT
- 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> and 15 minutes (rounded down to most recent whole hour)
___ UNSAT EXAMINER NOTE: For tables that have time since Rx was 2
shut down measured in hours, select the most recent whole hour (per Encl. 4.1, step 1.5)
Time (Hours since S/D) = 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> COMMENTS:
ADM-S203 2S Page 6 of 8 Determine time to boil.
CRITICAL STANDARD: Candidate determines time to boil is 15.7 minutes STEP by using 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> and 70 inches on LT-5.
- LT-5 level is 76 inches per Attachment ___ SAT 9.2.A
- Next lower level is 70 inches 3 ___ UNSAT EXAMINER NOTE: If RCS level is at some point between the columns provided, use the column for the next lower level (per Encl. 4.1, step 1.4)
COMMENTS:
Ensure equipment hatch is closed.
CRITICAL STEP STANDARD: Candidate determines the equipment hatch must be closed since the Configuration Sheet indicates that the Equipment Hatch is Open and time to Core Boil ___ SAT is less than 16 minutes.
4
___ UNSAT COMMENTS:
END TASK TIME STOP: ________
ADM-S203 2S Page 7 of 8 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 Required to determine the time for core boil.
2 Required to determine the time for core boil.
3 Required to determine the time for core boil.
4 Required to determine actions required as a result of the time to core boil
2S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS
- Unit 1 was shutdown on 12/01 at 0400
- Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2 is being prepared for this shift
- LPI aligned for Normal Decay Heat Removal INITIATING CUE Current Date/Time: 12/03 at 0615 The CRS instructs you to determine the Time To Core Boil utilizing OP/0/A/1108/001 A, (Reactor Core and SFP Loss of Cooling Heatup Tables), and perform any required actions based on the results, in accordance with Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2. Document your answers below.
Time to Core Boil: _______________________
Required Action (if any): ______________________________
ADM-S301 3S Page 1 of 11 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-S301 Determine RIA Setpoints and Approval Level Required for GWD Tank Release Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: No Time Critical Criteria: ________________________________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
ADM-S301 3S Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Determine RIA Setpoints and Approval Level Required for GWD Tank Release Task Number :
Alternate Path: No Time Critical: No Validation Time: 25 min K/A Rating(s):
System: GEN K/A: 2.3.6 Rating: 2.0/3.8 Task Standard:
Determine setpoints for 1RIA-37, 1RIA-38, and 1RIA-45 and determine the GWD Tank release requires approval from the Shift Manager (SM) due to 2 GWRs at 1/3 Station Limit.
References:
OP/1-2/1104/018 (GWD System) Rev. 78 PT/0/A/0230/001 (Radiation Monitor Check) Rev. 176 Tools/Equipment/Procedures Needed:
OP/1-2/A/1104/018 Encl. 4.9 (GWD Tank Release) Rev. 78 OP/1-2/A/1104/018 Encl. 4.10 (GWD Tank Sample Request) Rev. 78 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
ADM-S301 3S Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS N/A
ADM-S301 3S Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Unit 1 in Mode 1 at 100% power Unit 2 in Mode 1 at 100% power Unit 3 in Mode 5 with RB Purge in progress at 1/3 Station Limit OP/1-2/A/1104/018 Encl. 4.9 (GWD Tank Release) in progress at step 3.1 for release of A GWD Tank.
Steps for prior to GWD Tank release in PT/1-2/A/0230/002 (GWD Tank Release) are complete.
1RIA-37 background reading = 425 cpm 1RIA-38 background reading = 24 cpm A GWD Tank pressure = 70 psig GWD piping is purged INITIATING CUE
- 1. Continue in OP/1-2/A/1104/018 Encl. 4.9 beginning at step 3.1 to determine the setpoints for 1RIA-37, 1RIA-38, and 1RIA-45. Another operator will input the setpoints, once determined, into the RIAs as required by the procedure.
Document your answers below:
1RIA-37 Setpoints 1RIA-38 Setpoints 1RIA-45 Setpoints Alert: Alert: Alert:
High: High: High:
- 2. Determine the approval level required to release A GWD Tank in accordance with OP/1-2/A/1104/018 (GWD System).
Document your answer below:
Approval level required to release A GWD Tank. __________________
ADM-S301 3S Page 5 of 11 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Determine any other GWR(s) in progress at station:
Releases in Progress Release Rate of Station Limit Unit 1 __ Yes __ No ________________________ ___ SAT Unit 2 __ Yes __ No ________________________
Unit 3 __ Yes __ No ________________________
___ UNSAT 1 3.1 STANDARD: Candidate determines a release is in progress on Unit 3 at 1/3 Station Limit from the cue sheet.
COMMENTS:
Perform steps for prior to GWD Tank release in PT/1-2/A/0230/002 (GWD Tank Release).
___ SAT STANDARD: Candidate determines steps for prior to GWD Tank release in PT/1-2/A/0230/002 (GWD Tank 2 3.2 Release) are complete from the cue sheet.
___ UNSAT COMMENTS:
Ensure RIA setpoints adjusted for GWD Tank release per RIA-45 Setpoints For Unit 1&2 GWD Tank Release enclosure of PT/0/A/0230/001 (Radiation Monitor Check). CRITICAL STEP STANDARD: Candidate determines the setpoints for 1RIA-45 as follows:
ALERT: 4.66 E4 CPM ___ SAT 3 3.3 HIGH: 1.40 E5 CPM
___ UNSAT COMMENTS:
ADM-S301 3S Page 6 of 11 SEQ PROC DESCRIPTION STEP STEP Perform the following on Enclosure 4.10 (GWD Tank Sample Request):
3.4.1 Record Initial GWD Tank Pressure AND GWD Tank Volume 3.4.2 Record Start Date AND Time 3.4.3 Record background readings for 1RIA-37 AND 1RIA-38
___ SAT STANDARD: Determine A GWD tank pressure is 70 psig by referring to the cue sheet and record on Enclosure 4.10. ___ UNSAT Determine GWD Tank Volume is 6300 Ft3 (6200
- 6400) by using the curve in OP/1108/001 (General Curves and Information) and record on Enclosure 4.10.
Determine background readings for 1RIA-37 &
1RIA-38 by referring to the cue sheet and record on Enclosure 4.10.
- 1RIA-37 Background reading is 425 or 4.25E2 4 3.4 cpm
- 1RIA-38 Background reading is 24 or 2.4E1 cpm Continue to Step 3.5 COMMENTS:
ADM-S301 3S Page 7 of 11 SEQ PROC DESCRIPTION STEP STEP Record recommended 1RIA-37 and 38 Alert and High setpoints from Enclosure 4.10 (GWD Tank Sample Request):
- 1RIA-38 3.82 E2 cpm above background
___ UNSAT STANDARD: Obtain this information from the sample request and record in the procedure.
5 3.5 Continue to Step 3.6 COMMENTS:
NOTE: If N2 was added to the most recently released GWD tank until 1RIA-37 indicated < 700 cpm, OR if the tanks radioactivity was
< 2.1E-05µCi/ml when it was released, the GWD piping is considered purged.
IF 1RIA-37 is out-of-service OR GWD piping NOT purged, verify the following per Enclosure 4.10 (GWD Tank Sample Request): ___ SAT
- Independent Data Entry Checks completed
- Independent Sample agrees with initial sample ___ UNSAT STANDARD: Determine step does not apply and N/A the step.
6 3.6 Continue to Step 3.7 Examiner Cue: If asked, inform the candidate that the GWD piping is purged.
COMMENTS:
ADM-S301 3S Page 8 of 11 SEQ PROC DESCRIPTION STEP STEP NOTE: If N2 was added to the most recently released GWD tank until 1RIA-37 indicated < 700 cpm, OR if the tanks radioactivity was
< 2.1E-05µCi/ml when it was released, the GWD piping is considered purged.
IF GWD piping purged, calculate actual setpoints as follows: CRITICAL STEP 3.7.1 IF 1RIA-37 Operable, calculate Alert and High setpoints as follows:
___ SAT 4.25E2 cpm + 4.68E5 = 4.68E5 cpm 1RIA-37 Add to background' 1RIA-37 background value from Step 3.5 Alert and High ___ UNSAT 7 3.7 alarm setpoints STANDARD: Calculate set points using formula above.
(4.68E5 to 4.69E5)
Continue to Step 3.8 COMMENTS:
IF 1RIA-38 Operable, calculate Alert and High setpoints as follows:
CRITICAL 2.4E1 cpm + 3.82E2 = 4.06E2 cpm STEP 1RIA-38' Add to background' 1RIA-38 background value from Step 3.5 Alert and High ___ SAT alarm setpoints 8 3.8 STANDARD: Calculate set points using formula above (4.06E2). ___ UNSAT COMMENTS:
ADM-S301 3S Page 9 of 11 SEQ PROC DESCRIPTION STEP STEP Determine approval level required for the release of A GWD Tank.
CRITICAL STEP STANDARD: Candidate determines the approval level for 2 GWRs in progress at 1/3 Station Limit each is the ___ SAT SM.
9 ___ UNSAT COMMENTS:
END OF TASK TIME STOP: ________
ADM-S301 3S Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
3 This step is required to determine the setpoints for 1RIA-45.
7 This step is required to determine the setpoints for 1RIA-37.
8 This step is required to determine the setpoints for 1RIA-38.
9 This step is required to determine the approval level required for the release.
3S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS Unit 1 in Mode 1 at 100% power Unit 2 in Mode 1 at 100% power Unit 3 in Mode 5 with RB Purge in progress at 1/3 Station Limit OP/1-2/A/1104/018 Encl. 4.9 (GWD Tank Release) in progress at step 3.1 for release of A GWD Tank.
Steps for prior to GWD Tank release in PT/1-2/A/0230/002 (GWD Tank Release) are complete.
1RIA-37 background reading = 425 cpm 1RIA-38 background reading = 24 cpm A GWD Tank pressure = 70 psig GWD piping is purged INITIATING CUE
- 1. Continue in OP/1-2/A/1104/018 Encl. 4.9 beginning at step 3.1 to determine the setpoints for 1RIA-37, 1RIA-38, and 1RIA-45. Another operator will input the setpoints, once determined, into the RIAs as required by the procedure.
Document your answers below:
1RIA-37 Setpoints 1RIA-38 Setpoints 1RIA-45 Setpoints Alert: Alert: Alert:
High: High: High:
- 2. Determine the approval level required to release A GWD Tank in accordance with OP/1-2/A/1104/018 (GWD System).
Document your answer below:
Approval level required to release A GWD Tank. __________________
(ADM-S407) 4S Page 1 of 7 REGION II JOB PERFORMANCE MEASURE OCONEE ADM-S407 Determine the Appropriate Emergency Action Level Administrative: Yes Classroom/Simulator/Plant: Classroom Alternate Path: No Alt Path
Description:
Time Critical: Yes Time Critical Criteria: _15 minutes to classify_____________________________________
Prepared By: Date:
EP Review By: Date:
Reviewed By: Date:
Approved By: Date:
(ADM-S407) 4S Page 2 of 7 REGION II JOB PERFORMANCE MEASURE Task Title : Determine the Appropriate Emergency Action Level Task Number :
Alternate Path: No Time Critical: Yes Validation Time: 15 minutes K/A Rating(s):
System: Gen K/A: 2.4.38 Rating: 2.4/4.4 Task Standard: Appropriate classification is made within 15 minutes
References:
CSD-EP-ONS-0101-02 (WALLCHART) Rev 000 AD-EP-ALL-0101 Emergency Classification Rev 1 CSD-EP-ONS-0101-01 Bases Rev 000 Tools/Equipment/Procedures Needed:
CSD-EP-ONS-0101-02 (WALLCHART) Rev 000 AD-EP-ALL-0101 Emergency Classification Rev 1 CSD-EP-ONS-0101-01 Bases Rev 000 (Note: Below this line is used only for Initial NRC Exams)
===================================================================
Candidate: __________________________________ Time Start: _______________
NAME Time Finish: ______________
Performance Rating: SAT ______ UNSAT ______ Performance Time: _________
Examiner: ______________________________ ___________________________________/_________
NAME SIGNATURE DATE
=========================================================================
Comments
(ADM-S407) 4S Page 3 of 7 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS
- 1. N/A
(ADM-S407) 4S Page 4 of 7 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Time: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago:
- The Oconee County Sheriff reported that a large group of anti-nukes had assembled at the Visitor Center CURRENT CONDITIONS
- Unit 1 shutting down from 100% at 2%/min due to 35 gpm SGTR
- Unit 1 reactor power = 65% lowering
- Units 2 and 3 at 100% power
- Unit 1 Main Turbine spuriously trips
- Unit 1 Reactor fails to trip automatically
- OATC trips Unit 1 Reactor while performing IMAs
- Security Shift Supervisor notifies the SM that security is responding to armed adversaries in the vicinity of the KHU Main Transformer
- Keowee personnel report no visible damage to the KHUs INITIATING CUE The CRS directs you to determine the appropriate Emergency Action Level, per the above information Inform the examiner when you have made the classification THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment as the basis for classifying the event Operator Note: Complete ALL blanks below.
OPERATOR NAME: ____________________________________________________
EAL CLASSIFICATION: (Include EAL #)___________________________________________
(ADM-S407) 4S Page 5 of 7 START TIME: _______
SEQ PROC DESCRIPTION STEP STEP Determine the Emergency Action Level STANDARD: Candidate refers to the EAL Wallchart Hazards (H) and Security (1) and determines that HA1.1 (A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CRITICAL Security Shift Supervision. STEP ALERT (HA1.1) 1
___ SAT COMMENTS: ___ UNSAT END OF TASK TIME STOP: ________
(ADM-S407) 4S Page 6 of 7 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #
1 This step is required for the candidate to utilize the EAL Wallchart and determine the conditions meet an Alert classification within 15 minutes.
4S READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS Time: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago:
- The Oconee County Sheriff reported that a large group of anti-nukes had assembled at the Visitor Center CURRENT CONDITIONS
- Unit 1 shutting down at 2%/min due to 35 gpm SGTR
- Unit 1 reactor power = 65% lowering
- Units 2 and 3 at 100% power
- Unit 1 Main Turbine trips
- Unit 1 Reactor fails to trip automatically
- OATC trips Unit 1 Reactor while performing IMAs
- Security Shift Supervisor notifies the SM that security is responding to armed adversaries in the vicinity of the KHU Main Transformer
- Keowee personnel report no visible damage to the KHUs INITIATING CUE The CRS directs you to determine the appropriate Emergency Action Level, per the above information Inform the examiner when you have made the classification THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment as the basis for classifying the event Operator Note: Complete ALL blanks below.
OPERATOR NAME: ____________________________________________________
EAL CLASSIFICATION: (Include EAL #)___________________________________________