ML20268A322
| ML20268A322 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/07/2020 |
| From: | NRC Region 1 |
| To: | |
| Shared Package | |
| ML19105A186 | List: |
| References | |
| CAC 000500 | |
| Download: ML20268A322 (21) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Seabrook Station Date of Examination: 8/3/2020 Examination Level: RO SRO Operating Test Number: 2020 Administrative Topic (see Note) Type Describe activity to be performed Code*
NEW Determine License Status 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as Conduct of Operations R, N medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
RO IR: 3.3 NEW Transient Blended Makeup R, N 2.1.37, Knowledge of procedures, guidelines, or Conduct of Operations limitations associated with reactivity management.
RO IR: 4.3 NEW Evaluate SI Pump Data Sheet Equipment Control R, N 2.2.37 Ability to determine operability and/or availability of safety related equipment.
RO IR 3.6 NEW Determine Accumulated Dose in Support of Work Activities Radiation Control R, N 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
RO IR: 3.2 Emergency Plan - -
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 Facility: Seabrook Station Date of Examination: 8/3/2020 Examination Level: RO SRO Operating Test Number: 2020 Administrative Topic (see Note) Type Describe activity to be performed Code*
NEW Determine License Status 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as Conduct of Operations R, N medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
SRO IR: 3.8 NEW Approve Transient Blended Makeup Worksheet R, N Conduct of Operations 2.1.37, Knowledge of procedures, guidelines, or limitations associated with reactivity management.
SRO IR: 4.6 NEW Evaluate SI Pump Data Sheet and Determine AOT R, N Equipment Control 2.2.23 Ability to track Technical Specification limiting conditions for operations.
SRO IR: 4.6 NEW Increased Radiation Exposure Approval Radiation Control R, N 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
SRO IR: 3.7 E-Plan Classification Emergency Plan 2.4.41, Knowledge of the emergency action R, D level thresholds and classifications.
SRO IR: 4.6 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 Facility: Seabrook Station Date of Examination: 8/3/2020 Exam Level: RO SRO-I SRO-U Operating Test Number: 2020 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function
- a. Recover A Dropped Rod (APE 003 AA1.02 3.6/3.4) D, S 1
- b. SI Termination (013 A4.03 4.5/4.7) A, D, EN, P, 2 S
- c. Power Range NI Failure (015 A2.01 3.5/3.9) D, S 7
- d. Raise SI Accumulator Pressure (006 A1.13 3.5/3.7) D, S 3
- e. Transfer To Cold Leg Recirculation (TCA) (002 A2.01 4.3/4.4) A, D, S 4 Primary System
- f. Faulted DG Surveillance (064 A4.06 3.9/3.9) A, D, S 6
- g. SG Pressure Instrument Failure (059 A2.11 3.0/3.3) A, N, S 4 Secondary System
- h. Placing the Containment On-Line Purge (COP) System in Service D, P, S 8 (029 G2.1.31 4.6/4.3)
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Locally Establish Cooling Flow to RHR Heat Exchanger (APE 025 D, E, L, R 4 AK1.01 3.9/4.3, 005 K1.01 3.2/3.4, 005 K3.01 3.9/4.0)
Primary System
- k. Reset PCCW Pump High Temperature Trip (008 A2.01 3.3/3.6, A, D, E 8 APE026 AK3.03 4.0/4.2)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SRO-I/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (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 Facility: Seabrook Station Date of Examination: 8/3/2020 Exam Level: RO SRO-I SRO-U Operating Test Number: 2020 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function
- a. - - -
- b. SI Termination (013 A4.03 4.5/4.7) A, D, EN, P, 2 S
- c. Power Range NI Failure (015 A2.01 3.5/3.9) D, S 7
- d. Raise SI Accumulator Pressure (006 A1.13 3.5/3.7) D, S 3
- e. Transfer To Cold Leg Recirculation (TCA) (002 A2.01 4.3/4.4) A, D, S 4 Primary System
- f. Faulted DG Surveillance (064 A4.06 3.9/3.9) A, D, S 6
- g. SG Pressure Instrument Failure (059 A2.11 3.0/3.3) A, N, S 4 Secondary System
- h. Placing the Containment On-Line Purge (COP) System in Service D, P, S 8 (029 G2.1.31 4.6/4.3)
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Locally Establish Cooling Flow to RHR Heat Exchanger (APE 025 D, E, L, R 4 AK1.01 3.9/4.3, 005 K1.01 3.2/3.4, 005 K3.01 3.9/4.0)
Primary System
- k. Reset PCCW Pump High Temperature Trip (008 A2.01 3.3/3.6, A, D, E 8 APE026 AK3.03 4.0/4.2)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SRO-I/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (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 Facility: Seabrook Station Date of Examination: 8/3/20 Exam Level: RO SRO-I SRO-U Operating Test Number: 2020 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function a.- - -
- b. SI Termination (013 A4.03 4.5/4.7) A, D, EN, P, 2 S
- c. Power Range NI Failure (015 A2.01 3.5/3.9) D, S 7 d.- - -
e.- - -
- f. - - -
- g. SG Pressure Instrument Failure (059 A2.11 3.0/3.3) A, N, S 4 Secondary System h.- - -
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Locally Establish Cooling Flow to RHR Heat Exchanger (APE 025 D, E, L, R 4 AK1.01 3.9/4.3, 005 K1.01 3.2/3.4, 005 K3.01 3.9/4.0)
Primary System
- j. - - -
- k. Reset PCCW Pump High Temperature Trip (008 A2.01 3.3/3.6, A, D, E 8 APE026 AK3.03 4.0/4.2)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SRO-I/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (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
Appendix D Scenario Outline Form ES-D-1 Facility: Seabrook Station Scenario No.: 1 Op-Test No.: 2020 Examiners: ___________________________ Operators: ____________________________
Initial Conditions: Intermediate range power equivalent at 10-8 Amps, boron concentration is 1653 ppm and CBD at 98 steps.
Turnover:
- No equipment out of service
- Increase power to 3% power range Critical Tasks:
- 1. Manually actuate SI before transitioning out of E-0.
- 2. Transfer to Cold Leg Recirculation before receiving the RWST empty alarm.
Event Event No. Malf. No. Event Type*
Description PSO R 1 BOP N Power increase to 3%
US N PSO I Pressurizer pressure controlling channel RC-PT-455 fails 2 trRCPR455 US I, TS low.
BOP I 3 trFWLT529 SG B controlling channel (FRBV) FW-LT-529 fails high.
US I, TS PSO M 4 mfRC048B BOP M RCS leak leads to large break LOCA in B hot leg.
US M BOP C Bus 5 deenergized, A EDG fails to auto start. BOP must 5 mfED031 US C manually start.
aet SW\A PSO C Running A train SW pump trips, standby fails to 6 SW Pump US C automatically start.
trip mfCBS004, PSO C 7 CBS pumps fail to automatically start.
005 US C
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Procedure flow path: OS1201.06, ON1235.03, OS1201.02, E-0, FR-Z.1, E-1
Appendix D Scenario Outline Form ES-D-1 Facility: Seabrook Station Scenario No.: 2 Op-Test No.: 2020 Examiners: ___________________________ Operators: ____________________________
Initial Conditions: 75% power. The core is at middle of life with a burnup of 10,000 MWD/MTU. Boron concentration is 1105 ppm and CBD is at 181 steps.
Turnover: The plant is at 75% power due to grid limitations. Power has been stable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Maintain current power. Swap A train SW pumps, from SW-P-41C to SW-P-41A.
Critical Tasks:
- 1. Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.
- 2. Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions:
Too high to maintain 60F of subcooling OR Too low causing Red or Orange path on the sub criticality and/or the integrity CSF.
Event Event Event Malf. No.
No. Type* Description BOP N 1 Swap A train SW pumps.
US N PSO C CC-P-11A trips and the standby fails to automatically start. PSO 2 mfCC008 US C, TS must manually start.
BOP C SW-P-41A trips. Standby fails to auto start, trips when manually 3 mfSW001 US C, TS started. Manual TA is necessary.
PSO C 4 mfSG001B 30 gpm B SG tube leak US C, TS PSO R 5 Down power to <50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
PSO M During down power, B SG degrades into a 500 gpm tube rupture 6 mfSG001B BOP M requiring start of second charging pump, tripping the reactor and US M actuating SI.
PSO C Automatic T signal on Train B fails to actuate. PSO must 7 mfRPS012 US C manually actuate train B T signal.
BOP C B MSIV cannot be closed. Other MSIVs must be closed and c/d 8 svMSV88 US C shifted to ASDVs.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Procedure flow path: OS1211.04, OS1216.01, OS1227.02, OS1231.04, E-0, E-3
Appendix D Scenario Outline Form ES-D-1 Facility: Seabrook Station Scenario No.: 3 Op-Test No.: 2020 Examiners: ___________________________ Operators: ____________________________
Initial Conditions: 100% power, no equipment is out of service. The core is at middle of life with a burnup of 10,000 MWD/MTU. Boron concentration is 1045 ppm and CBD is at 230 steps.
Turnover: The plant is in a post-contingency back down to 800 MWel net. Pre-brief ISO down power before taking the watch.
Critical Tasks:
- 1. Restore power to Bus 6 via SEPS before placing equipment in pull-to-lock in step 6 of ECA-0.0.
- 3. Start the motor driven EFW pump before transitioning to FR-H.1.
Event Event Event Malf. No.
No. Type* Description BOP I 1 trFWLT553 C SG Level controlling channel FW-LT-553 fails low.
US I, TS PSO C 2 ctRCPK455A Pressurizer Master Pressure Controller set point fails high.
US C PSO R 3 BOP N ISO down power to 800 MWel net in 30 minutes.
US N During ISO down power, NSO reports a loss of oil from the B CBS 4 US TS pump.
mfED038 PSO M Loss of Offsite Power, A EDG failure to start (auto or manual), B 5 mfED031 BOP M EDG starts then trips on low lube oil pressure.
mfED034 US M PSO C Once Bus 6 power is restored from SEPs, no PCCW pump will 6 mfCC013 US C start automatically and must be manually started.
Turbine driven EFW pump trips. The motor driven EFW pump fails BOP C 7 mfFW052 to start automatically and must be manually started once Bus 6 is US C energized.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Procedure flow path: OS1231.04, OS1227.02, E-0, ECA-0.0, E-0, ES-0.1
ES-401 PWR Examination Outline Form ES-401-2 Facility: Seabrook Date of Exam: August 2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total
- 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency and Abnormal Plant 2 1 2 2 N/A 1 2 N/A 1 9 2 2 4 Evolutions Tier Totals 4 5 5 4 5 4 27 5 5 10 1 2 3 2 3 2 2 3 3 2 3 3 28 2 3 5 2.
Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 0 1 2 3 Systems Tier Totals 3 3 3 4 3 3 4 4 3 4 4 38 3 5 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As
- These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
- These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
Decay power as a function of time 000007 (EPE 7; BW E02&E10; CE E02) 5 3.3 1 Reactor Trip, Stabilization, Recovery / 1 000009 (EPE 9) Small Break LOCA / 3 3 S/Gs 3.0 2 Ability to interpret reference materials such as 000015 (APE 15) Reactor Coolant Pump 2.1.25 graphs, monographs and tables which contain 3.9 3 Malfunctions / 4 performance data.
Proper amperage of running LPI/decay heat 000025 (APE 25) Loss of Residual Heat 1 removal/RHR pump(s) 2.7 4 Removal System / 4 000026 (APE 26) Loss of Component 1 CCW temperature indications 3.1 5 Cooling Water / 8 Ability to verify system alarm setpoints and 000027 (APE 27) Pressurizer Pressure 2.4.50 operate controls identified in the alarm response 4.2 6 Control System Malfunction / 3 manual.
Cooldown of RCS to specified temperature 000038 (EPE 38) Steam Generator Tube 36 4.3 7 Rupture / 3 MFW line break depressurizes the S/G (similar to 000054 (CE E06) Loss of Main Feedwater 1 a steam line break) 4.1 8
/4 Natural circulation cooling 000055 (EPE 55) Station Blackout / 6 2 4.1 9 Knowledge of the operational implications of 000056 (APE 56) Loss of Offsite Power / 6 2.4.20 EOP warnings, cautions, and notes. 3.8 10 Actions contained in EOP for loss of vital ac 000057 (APE 57) Loss of Vital AC 1 electrical instrument bus 4.1 11 Instrument Bus / 6 That a loss of dc power has occurred; verification 000058 (APE 58) Loss of DC Power / 6 1 that substitute power sources have come on line 3.7 12 The valve lineups necessary to restart the SWS 000062 (APE 62) Loss of Nuclear Service 3 while bypassing the portion of the system 2.6 13 Water / 4 causing the abnormal condition Actions contained in EOP for loss of instrument 000065 (APE 65) Loss of Instrument Air / 8 8 air 3.7 14 Voltage regulator controls 000077 (APE 77) Generator Voltage and 3 3.8 15 Electric Grid Disturbances / 6 Facility's heat removal systems, including (W E04) LOCA Outside Containment / 3 2 primary coolant, emergency coolant, the decay 3.8 16 heat removal systems and relations between the proper operation of these systems to the operation of the facility.
Components and functions of control and safety (BW E04; W E05) Inadequate Heat 1 systems, including instrumentation, signals, 3.7 17 TransferLoss of Secondary Heat Sink / 4 interlocks, failure modes and automatic and manual features.
Manipulation of controls required to obtain (W E11) Loss of Emergency Coolant 3 desired operating results during abnormal, and 3.8 18 Recirculation / 4 emergency situations.
Proper actions to be taken if the automatic safety 000007 (EPE 7; BW E02&E10; CE E02) 2 functions have not taken place 4.6 76 Reactor Trip, Stabilization, Recovery / 1 Conditions necessary for recovery when accident 000011 (EPE 11) Large Break LOCA / 3 8 reaches stable phase 3.9 77 Limitations on LPI flow and temperature rates of 000025 (APE 25) Loss of Residual Heat 5 change 3.5 78 Removal System / 4 Ability to diagnose and recognize trends in an 000026 (APE 26) Loss of Component 2.4.47 accurate and timely manner utilizing the 4.2 79 Cooling Water / 8 appropriate control room reference material.
Knowledge of emergency plan protective action 000056 (APE 56) Loss of Offsite Power / 6 2.4.44 recommendations. 4.4 80
ES-401 3 Form ES-401-2 (W E04) LOCA Outside Containment / 3 2.4.18 Knowledge of the specific bases for EOPs. 4.0 81 K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
000001 (APE 1) Continuous Rod Withdrawal / 1 1 Bank select switch 3.5 19 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 2 Interlocks associated with fuel 2.9 20 handling equipment 000037 (APE 37) Steam Generator Tube Leak / 3 2 Leak rate vs. pressure drop 3.5 21 000051 (APE 51) Loss of Condenser Vacuum / 4 2 Conditions requiring reactor 3.9 22 and/or turbine trip 000032 (APE 32) Loss of Source Range Nuclear 4 Satisfactory source- 3.1 23 Instrumentation / 7 range/intermediate-range overlap 000076 (APE 76) High Reactor Coolant Activity / 9 1 Process radiation monitors 2.6 24 (BW E08; W E03) LOCA CooldownDepressurization / 4 1 Components and functions of 3.6 25 control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
(CE A11**; W E08) RCS OvercoolingPressurized Thermal 1 Facility operating 3.4 26 Shock / 4 characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.
(W E15) Containment Flooding / 5 2.1.23 Ability to perform specific 4.3 27 system and integrated plant procedures during all modes of plant operation.
000003 (APE 3) Dropped Control Rod / 1 3 Dropped rod, using in-core/ex- 3.8 82 core instrumentation in-core or loop temperature measurements 000028 (APE 28) Pressurizer (PZR) Level Control 1 PZR level indicators and 3.6 83 Malfunction / 2 alarms 000068 (APE 68; BW A06) Control Room Evacuation / 8 2.4.27 Knowledge of fire in the plant 3.9 84 procedures.
(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 Ability to interpret control room 4.4 85 2.2.44 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions K/A Category Point Totals: 1 2 2 1 2/2 1/2 Group Point Total: 9/4
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
003 (SF4P RCP) Reactor Coolant 1 RCPS 3.1 28 Pump Protection of ion exchangers (high 004 (SF1; SF2 CVCS) Chemical and 3 letdown temperature will isolate ion 2.8 29 Volume Control exchangers) 004 (SF1; SF2 CVCS) Chemical and 8 Hydrogen control in RCS 2.8 30 Volume Control 005 (SF4P RHR) Residual Heat 3 RHR heat exchanger 2.5 31 Removal 006 (SF2; SF3 ECCS) Emergency 1 RCS 4.1 32 Core Cooling 007 (SF5 PRTS) Pressurizer 2 Abnormal pressure in the PRT 2.6 33 Relief/Quench Tank 007 (SF5 PRTS) Pressurizer 2 Method of forming a steam bubble in the 3.1 34 Relief/Quench Tank PZR Operation of the surge tank, including the 008 (SF8 CCW) Component Cooling 2 associated valves and controls 2.9 35 Water Ability to perform without reference to 010 (SF3 PZR PCS) Pressurizer 2.4.49 procedures those actions that require 4.6 36 Pressure Control immediate operation of system components and controls.
010 (SF3 PZR PCS) Pressurizer 1 Pressure detection systems 2.7 37 Pressure Control 012 (SF7 RPS) Reactor Protection 1 DNB 3.3 38 Knowledge of limiting conditions for 013 (SF2 ESFAS) Engineered 2.2.22 operations and safety limits. 4.0 39 Safety Features Actuation SWS/cooling system 022 (SF5 CCS) Containment Cooling 1 3.5 40 026 (SF5 CSS) Containment Spray 1 Containment spray pumps 3.4 41 061 (SF4S AFW) 2 AFW electric drive pumps 3.7 42 Auxiliary/Emergency Feedwater 039 (SF4S MSS) Main and Reheat 4 Emergency feedwater pump turbines 3.8 43 Steam RCS 039 (SF4S MSS) Main and Reheat 5 3.6 44 Steam Feed Pump speed, including normal 059 (SF4S MFW) Main Feedwater 7 control speed for ICS 2.5 45 Knowledge of annunciators alarms, 061 (SF4S AFW) 2.4.31 indications or response procedures 4.2 46 Auxiliary/Emergency Feedwater Significance of D/G load limits 062 (SF6 ED AC) AC Electrical 1 3.4 47 Distribution Effect on instrumentation and controls of 062 (SF6 ED AC) AC Electrical 3 switching power supplies 2.5 48 Distribution 063 (SF6 ED DC) DC Electrical 3 Battery discharge rate 3.0 49 Distribution 064 (SF6 EDG) Emergency Diesel 1 AC distribution system 4.1 50 Generator
ES-401 6 Form ES-401-2 073 (SF7 PRM) Process Radiation 2 Detector failure 2.7 51 Monitoring 076 (SF4S SW) Service Water 2 Emergency heat loads 3.7 52 078 (SF8 IAS) Instrument Air 1 Pressure gauges 3.1 53 103 (SF5 CNT) Containment 3 Phase A and B isolation 3.5 54 103 (SF5 CNT) Containment 1 Containment isolation 3.9 55 Problems associated with RCP motors, 003 (SF4P RCP) Reactor Coolant 3 including fault motors and current, 3.1 86 Pump winding and bearing temperature problems Knowledge of system set points, 007 (SF5 PRTS) Pressurizer 2.4.2 interlocks and automatic actions 4.6 87 Relief/Quench Tank associated with EOP entry conditions.
010 (SF3 PZR PCS) Pressurizer 1 Heater failures 3.6 88 Pressure Control Knowledge of the organization of the 026 (SF5 CSS) Containment Spray 2.4.5 operating procedures network for normal, 4.3 89 abnormal, and emergency evolutions.
Knowledge of the parameters and logic 073 (SF7 PRM) Process Radiation 2.4.21 used to assess the status of safety 4.6 90 Monitoring functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. l K/A Category Point Totals: 2 3 2 3 2 2 3 3/2 2 3 3/3 Group Point Total: 28/5
ES-401 7 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
001 (SF1 CRDS) Control Rod Drive 64 Reason for withdrawing shutdown group: 3.3 56 to provide adequate shutdown margin 011 (SF2 PZR LCS) Pressurizer 6 3.3 57 Level Control Letdown isolation 028 (SF5 HRPS) Hydrogen 1 3.4 58 Recombiner and Purge Control Hydrogen concentration 041 (SF4S SDS) Steam 2 2.7 59 Dump/Turbine Bypass Control Cooldown valves 045 (SF 4S MTG) Main Turbine 17 2.7 60 Generator Malfunction of electrohydraulic control 055 (SF4S CARS) Condenser Air 1 2.5 61 Removal Main condenser 014 (SF1 RPI) Rod Position 2.2.37 Ability to determine operability and/or 3.6 62 Indication availability of safety related equipment 072 (SF7 ARM) Area Radiation 4 3.3 63 Monitoring Control room ventilation 033 (SF8 SFPCS) Spent Fuel 1 2.5 64 Cooling Temperature control valves 086 Fire Protection 4 Fire, smoke and heat detectors 2.6 65 034 (SF8 FHS) Fuel-Handling 1 Dropped fuel element 4.4 91 Equipment 072 (SF7 ARM) Area Radiation 2.4.4 Ability to recognize abnormal indications 4.7 92 Monitoring for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
079 (SF8 SAS**) Station Air 2.4.6 Knowledge symptom based EOP 4.7 93 mitigation strategies.
K/A Category Point Totals: 1 0 1 1 1 1 1 1/1 1 1 1/2 Group Point Total: 10/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Seabrook Date of Exam: August 2020 Category K/A # Topic RO SRO-only IR # IR #
Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, 2.7 66 2.1.15 Operations memos, etc.
Ability to make accurate, clear and concise logs, records, 2.1.18 status boards and reports. 3.6 67
- 1. Conduct of Operations Knowledge of how to conduct system lineups, such as valves, 2.1.29 breakers, switches, etc. 4.0 94 Subtotal 2 1 Ability to recognize system parameters that are entry-level 2.2.42 conditions for Technical Specifications 3.9 68 2.2.35 Ability to determine Technical Specification Mode of Operation. 3.6 69
- 2. Equipment Control Knowledge of the process for managing maintenance 2.2.17 activities during power operations. 3.8 95 Knowledge of less than one hour technical specification 2.2.39 action statements for systems. 4.5 96 Subtotal 2 2 2.3.11 Ability to control radiation releases. 3.8 70 Knowledge of radiological safety principles pertaining to 2.3.12 licensed operator duties 3.2 71 2.3.5 Ability to use radiation monitoring systems 2.9 72
- 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or 3.7 97 emergency conditions.
Ability to comply with radiation work permit requirements during 2.3.7 normal or abnormal conditions 3.6 98 Subtotal 3 2 Knowledge of EOP entry conditions and immediate action 2.4.1 steps. 4.6 73 2.4.11 Knowledge of abnormal condition procedures. 4.0 74 Ability to verify that the alarms are consistent with the plant 2.4.46 conditions. 4.2 75
- 4. Emergency Procedures/Plan 2.4.17 Knowledge of EOP terms and definitions. 4.3 99 Knowledge of local auxiliary operator tasks during emergency 2.4.35 and the resultant operational effects 4.0 100 Subtotal 3 2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 Rejected Emergency and Abnormal Plant Evolutions associated with Babcock and Wilcox (BW) and Combustion Engineering (CE) reactors - Seabrook is a Westinghouse design.
2/1 Rejected 025 (SF5 ICE) Ice Condenser - Seabrook does not have an ice condenser installed.
2/2 Rejected 027 (SF5) CIRS Containment Iodine Removal System - system does not exist at Seabrook 2/2 Rejected 016 (SF7) NNI Nonnuclear Instrumentation System
- system does not exist at Seabrook ALL Rejected generics 2.2.3 and 2.2.4 as Seabrook is a single unit site 1/1 RO question #5 K/A is not valid at Seabrook as CRDMs are not cooled by Component Cooling Water. Randomly reselected A1.01.
APE 026 A1.04 1/1 RO question #18 Cannot write a discriminating question of appropriate level of difficulty. Randomly reselected K3.3 E11 K3.4 1/2 RO question #19 The switches referred to in this K/A are not used in this APE.
Cannot write an operationally valid question. Randomly APE 001 A1.04 reselected A1.01 2/1 RO question #40 Seabrook uses a closed cooling water system to cool containment. This K/A is not specific and does not resemble 022 K1.02 systems at Seabrook, so an operationally valid question cannot be written. Randomly reselected K1.01 2/1 RO question #54 Cannot write an operationally valid question regarding emergency containment entry. Randomly reselected A2.03 103 A2.05 2/2 RO question #58 Containment pressure monitoring in HRPS does not lend itself to many discriminating questions. Randomly selected 028 A1.02 A1.01 for more discriminating value.
2/2 RO question #62 This system does not contain operability or availability of SR equipment; therefore it is not a match for the generic K/A 056 Condensate G2.2.37. Randomly reselected system 014 Rod Position Indication as a replacement for Condensate.
2/2 RO question #64 For K2.01 (knowledge of bus power supplies..), the importance rating for nearly all Tier 2 Group 2 systems is less 075 K2.01 than 2.5. Cannot write an operationally valid question or the current K/A and system combination. Randomly reselected 033 Spent Fuel Pool Cooling, A3.01
ES-401 Record of Rejected K/As Form ES-401-4 3 RO question #74 Seabrook has no emergency procedure or plan for loss of all annunciators. They address this issue with a procedure for G2.4.32 the loss of the power bus. The K/A doesnt lend itself to many discriminating questions of value. Randomly reselected 2.4.11.
1/1 SRO question #77 Cannot write an operationally valid question for A2.07 in large break LOCA. Randomly reselected A2.08 A2.07 1/1 SRO question #80 This generic K/A does not pair well with loss of offsite power.
Cannot write a discriminating question. Randomly reselected G2.4.41 G2.4.44 1/2 SRO question #84 This generic K/A discusses PAMS. There are no PAMS instrumentation outside of the control room. Randomly G2.4.3 reselected G2.4.27 2/1 SRO question #89 This generic K/A does not pair well with containment spray.
Cannot write a discriminating question. Randomly reselected G2.4.9 G2.4.5 1/2 RO question #23 CR Evacuation has already been sampled for the SRO exam
- 84, so this topic is oversampled. Randomly reselected APE A2.10 32 Loss of Source Range Nuclear Instrumentation, A2.04 2/2 RO question #60 Cannot write a valid, discriminating question. Randomly reselected A2.17 A2.12 2/1 RO question #42 This topic is oversampled. Also, cannot write a discriminating question of sufficient difficulty. Randomly reselected 061 026 Containment Auxiliary/Emergency Feedwater, K2.02 Spray 2/1 RO question #29 The topic of gas in the RCS is already being tested by question #30. This topic is oversampled. Randomly K4.01 reselected K4.03