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{{#Wiki_filter:ES-301 Control Room/In-Plant Systems Outline Form ES-301-2  Facility:  Robinson    Date of Examination:  8/25/14  Exam Level:  RO SRO-I SRO-U Operating Test No.:      Control Room Systems@ (8 for RO); (7 for SRO-I, a-g); (2 or 3 for SRO-U, including 1 ESF)  System / JPM Title  Type Code*  Safety Function  a. Restore Control Power to SI Valves and Isolate Accumulators IAW EPP-008. EN, A, D, S 3  b. Fill Reactor Coolant Stand Pipe A,D, S 4P  c. Terminate an Inadvertent CV Spray Actuation  N, S 5  d. Perform an Emergency Boration IAW EOP-ES-0.1, using the RWST A, L, D, S 1  e. Remove N-44 from service IAW OWP-011 D, S 7  f. Respond to a Reactor trip and Turbine trip A, M, S 4S  g. Restore Normal Power after Loss of Startup Transformer D, S 6  h. Respond to a Loss of a Circulating Water Pump D, S 8  In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)  i. Trip the Reactor Locally as Outside Auxiliary Operator D, E 1  j. Local Control of S/G Level and Pressure during a Site Black Out D, E 4S  k. Locally align containment isolation valves following a Safety Injection R, D, E 5  @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes  Criteria for RO / SRO-I / SRO-U  (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator  4-6 / 4-6 / 2-3    -  /  -  /  system)  domly selected)
JPM A:  Restore Control Power to SI Valves and Isolate Accumulators IAW EPP-008. K/A 009 EA1.13:  Ability to operate and monitor the following as they apply to a small break LOCA:  ESFAS (009 Small Break LOCA)  The plant has been tripped due to a small break LOCA. The crew is in EPP-8 and they are at the point to restore control power to SI Valves and isolate or depressurize SI Accumulators. The candidate will be given a marked up copy of EPP-8 to this point. The candidate will then restore power to multiple SI Valves. After that they will verify SI Accumulator Discharge valves are shut. One valve will not be shut and they will then have to depressurize the accumulator to prevent it from discharging. Once the Accumulator is depressurized, the JPM will be complete.  (Bank JPM CR-069) (RO, SRO-I, SRO-U)  JPM B:  Fill Reactor Coolant Stand Pipe K/A 003 A4.05:  Ability to manually operate and/or monitor in the control room:  RCP seal leakage detection instrumentation. (003 Reactor Coolant Pump System (RCPS))  The plant will be at 100% power. The candidate will assume the watch. APP-001-C5, RCP STANDPIPE HI/LO LVL is in alarm. The candidate will use OP-101 Section 8.2 to refill the standpipe until APP-001-C5 is extinguished. RC-519B will not close which will force them to OP-103 to relieve the Hydraulic lock. Once RC-519B goes closed, the JPM will be complete.  (Bank JPM CR-111) (RO, SRO-I)  JPM C:  Terminate an Inadvertent CV Spray Actuation(New) K/A 026 A4.01:  Ability to manually operate and/or monitor in the control room:  CSS Controls. (026 Containment Spray System(CSS))  The plant will have just tripped. The candidate will take the watch while in EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, at step 9, Check CV Spray NOT Required. The candidate will verify that CV spray is not required but that it has actuated. The candidate will go through the actions to terminate CV Spray. Once CV Spray is terminated, the JPM will be complete. (RO, SRO-I, SRO-U, SRO-U)  JPM D:  Perform an Emergency Boration IAW EOP-ES-0.1 K/A 024 AA1.02/AA1.04:  Ability to operate and/or monitor the following as they apply to Emergency Boration:  Boric Acid Pump/Manual boration valve. (024 Emergency Boration)  The plant has tripped and the crew is in EOP-ES-0.1, REACTOR TRIP RESPONSE. The candidate will recognize that two control rods are stuck out and will need to emergency borate the RCS to cold shutdown. The candidate will attempt to borate via the BAST but this will not work. The candidate will then transition to borating from the RWST. Once the candidate has an emergency boration flow path from the RWST aligned, the JPM will be complete. (Bank JMP CR-054 ) (RO, SRO-I)  JPM E:  Remove N-44 from service IAW OWP-011 K/A 015 A4.03:  Ability to manually operate and/or monitor in the control room:  Trip Bypasses (015 Nuclear Instrumentation System(NIS))  The plant is at 100% power. The candidate will be directed to remove NI-44 from service IAW OWP-011. The candidate will get OWP-011 and remove NI-44 from service. Once the NI is removed from service, the JPM will be complete. (Bank JPM CR-009) (RO, SRO-I, SRO-U)
JPM F:  Respond to a Reactor Trip and Turbine Trip K/A 007 EA1.07:  Ability to operate and monitor the following as they apply to a reactor trip: MT/G trip; verification that the MT/G has been tripped. (007 Reactor Trip)  The candidate will assume the watch at 100% power. The reactor will fail to automatically trip and the candidate will be required to depress either reactor trip pushbutton. The turbine will fail to trip. The candidate will be required to respond to the reactor trip IAW EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. The candidate will verify the reactor is tripped then respond to the turbine not being tripped. The candidate will attempt to run the turbine back, however, this will not work. The candidate will -E-0. Once these Immediate Actions are complete, the JPM is complete. (Bank JPM CR-085 modified) (RO, SRO-I, SRO-U)  JPM G:  Restore normal power after loss of startup transformer K/A 062 A4.01:  Ability to manually operate and/or monitor in the control room:  All breakers(including available switchyard) (062 AC Electrical Distribution System)  The plant will be shutdown due to a reactor trip and Safety Injection from a loss of the startup transformer. The candidate is directed by the CRS to perform OP-603 Section 6.4.1(with the exception of E-1, E-2, and 480V bus 4 and 4KV bus 5). The candidate will make multiple switch manipulations in order to restore power. Once power is restored, the JPM is complete.  (Bank JPM CR-28) (RO, SRO-I)  JPM H:  Respond to a Loss of a Circulating Water Pump K/A 075 A2.02:  Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Circulating Water Pumps (075 Circulating Water System)  The plant is at 50% power. The Candidate will be given the shift and told to respond tripped and take Immediate Actions of AOP-012, PARTIAL LOSS OF CONDENSER VACUUM OR CIRCULATING WATER PUMP TRIP. The candidate will then start Circulating  (Bank JPM CR-055) (RO)  JPM I:  Trip the Reactor Locally as Outside Auxiliary Operator(OAO). K/A  029 EA1.12:  Ability to operate and monitor the following as they apply to a ATWS:  M/G Set power supply and rector trip breakers. (O29 ATWS)  The plant is at 100% power with an ATWS in progress. As the OAO, the CRS has dispatched the candidate to 480V Busses 2B and 3 to trip the following breakers: ROD DRIVE MOTOR GENERATOR SET A and ROD DRIVE MOTOR GENERATOR SET B. The candidate will go to the 4Kv room and find 480V bus 2B and breaker 52/10B. The candidate will then open the breaker by depressing the trip pushbutton in the center of the cubicle door. The candidate will  find 480V bus 3 and breaker 52/14A in the 4Kv room. The candidate will then open the breaker by depressing the trip pushbutton in the center of the cubicle door. Once the breakers are open, the JPM will be complete. (RO, SRO-I, SRO-U)
JPM J:  Local Control of S/G Level and Pressure during a Site Black Out. K/A 061 A1.01/A1.02:  Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including:  S/G Level and S/G Pressure.  (061 Auxiliary/Emergency Feedwater(AFW) System)  The plant has experienced a loss of onsite and offsite power. EPP-1 has been implemented. S/G levels are currently 55%. The candidate will be directed by the CRS to perform Attachment 1 of EPP-1 which is Local Control of S/G Level and Pressure. The candidate will first go to the Pipe Jungle and open one of the V!-8A/B/ or C Steam Supply to the SDAFW Pump. Next, the candidate will go to the Secondary Control Panel area and manually throttle V2-14A/B/C to control S/G level between 60-68%. Next, the candidate will go to the Pipe Jungle and perform several valve manipulations to . Once the candidate has notified the Control Room that S/G level is under itrogen supplied for motive air, the JPM will be complete.  (RO, SRO-I, SRO-U)  JPM K:  Locally align containment isolation valves following a Safety Injection. K/A E02 EA1.1:  Ability to operate and / or monitor the following as they apply to the (SI Termination);  Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.  (E02 SI Termination)  A plant trip and Safety Injection have occurred. EPP-7 is currently being implemented and the CRS has directed the candidate to perform Attachment 2 of EPP-7, Realignment of Components following SI Termination for Inside AO. The candidate will have to go to several different locations inside the Auxiliary Building(RCA) and reset multiple valves in order to realign components necessary to terminate Safety Injection. Once the Control Room is notified that the attachment is complete, the JPM will be complete.  (RO, SRO-I)}}

Revision as of 03:26, 11 June 2018

Robinson Initial Exam 2014-301 Draft Admin Documents
ML15167A137
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 10/29/2014
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
50-261/14-301 50-261/14-301
Download: ML15167A137 (68)


Text

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Robinson Date of Examination: 8/25/14 Exam Level: RO SRO-I SRO-U Operating Test No.: Control Room Systems@ (8 for RO); (7 for SRO-I, a-g); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. Restore Control Power to SI Valves and Isolate Accumulators IAW EPP-008. EN, A, D, S 3 b. Fill Reactor Coolant Stand Pipe A,D, S 4P c. Terminate an Inadvertent CV Spray Actuation N, S 5 d. Perform an Emergency Boration IAW EOP-ES-0.1, using the RWST A, L, D, S 1 e. Remove N-44 from service IAW OWP-011 D, S 7 f. Respond to a Reactor trip and Turbine trip A, M, S 4S g. Restore Normal Power after Loss of Startup Transformer D, S 6 h. Respond to a Loss of a Circulating Water Pump D, S 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Trip the Reactor Locally as Outside Auxiliary Operator D, E 1 j. Local Control of S/G Level and Pressure during a Site Black Out D, E 4S k. Locally align containment isolation valves following a Safety Injection R, D, E 5 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 - / - / system) domly selected)

JPM A: Restore Control Power to SI Valves and Isolate Accumulators IAW EPP-008. K/A 009 EA1.13: Ability to operate and monitor the following as they apply to a small break LOCA: ESFAS (009 Small Break LOCA) The plant has been tripped due to a small break LOCA. The crew is in EPP-8 and they are at the point to restore control power to SI Valves and isolate or depressurize SI Accumulators. The candidate will be given a marked up copy of EPP-8 to this point. The candidate will then restore power to multiple SI Valves. After that they will verify SI Accumulator Discharge valves are shut. One valve will not be shut and they will then have to depressurize the accumulator to prevent it from discharging. Once the Accumulator is depressurized, the JPM will be complete. (Bank JPM CR-069) (RO, SRO-I, SRO-U) JPM B: Fill Reactor Coolant Stand Pipe K/A 003 A4.05: Ability to manually operate and/or monitor in the control room: RCP seal leakage detection instrumentation. (003 Reactor Coolant Pump System (RCPS)) The plant will be at 100% power. The candidate will assume the watch. APP-001-C5, RCP STANDPIPE HI/LO LVL is in alarm. The candidate will use OP-101 Section 8.2 to refill the standpipe until APP-001-C5 is extinguished. RC-519B will not close which will force them to OP-103 to relieve the Hydraulic lock. Once RC-519B goes closed, the JPM will be complete. (Bank JPM CR-111) (RO, SRO-I) JPM C: Terminate an Inadvertent CV Spray Actuation(New) K/A 026 A4.01: Ability to manually operate and/or monitor in the control room: CSS Controls. (026 Containment Spray System(CSS)) The plant will have just tripped. The candidate will take the watch while in EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, at step 9, Check CV Spray NOT Required. The candidate will verify that CV spray is not required but that it has actuated. The candidate will go through the actions to terminate CV Spray. Once CV Spray is terminated, the JPM will be complete. (RO, SRO-I, SRO-U, SRO-U) JPM D: Perform an Emergency Boration IAW EOP-ES-0.1 K/A 024 AA1.02/AA1.04: Ability to operate and/or monitor the following as they apply to Emergency Boration: Boric Acid Pump/Manual boration valve. (024 Emergency Boration) The plant has tripped and the crew is in EOP-ES-0.1, REACTOR TRIP RESPONSE. The candidate will recognize that two control rods are stuck out and will need to emergency borate the RCS to cold shutdown. The candidate will attempt to borate via the BAST but this will not work. The candidate will then transition to borating from the RWST. Once the candidate has an emergency boration flow path from the RWST aligned, the JPM will be complete. (Bank JMP CR-054 ) (RO, SRO-I) JPM E: Remove N-44 from service IAW OWP-011 K/A 015 A4.03: Ability to manually operate and/or monitor in the control room: Trip Bypasses (015 Nuclear Instrumentation System(NIS)) The plant is at 100% power. The candidate will be directed to remove NI-44 from service IAW OWP-011. The candidate will get OWP-011 and remove NI-44 from service. Once the NI is removed from service, the JPM will be complete. (Bank JPM CR-009) (RO, SRO-I, SRO-U)

JPM F: Respond to a Reactor Trip and Turbine Trip K/A 007 EA1.07: Ability to operate and monitor the following as they apply to a reactor trip: MT/G trip; verification that the MT/G has been tripped. (007 Reactor Trip) The candidate will assume the watch at 100% power. The reactor will fail to automatically trip and the candidate will be required to depress either reactor trip pushbutton. The turbine will fail to trip. The candidate will be required to respond to the reactor trip IAW EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. The candidate will verify the reactor is tripped then respond to the turbine not being tripped. The candidate will attempt to run the turbine back, however, this will not work. The candidate will -E-0. Once these Immediate Actions are complete, the JPM is complete. (Bank JPM CR-085 modified) (RO, SRO-I, SRO-U) JPM G: Restore normal power after loss of startup transformer K/A 062 A4.01: Ability to manually operate and/or monitor in the control room: All breakers(including available switchyard) (062 AC Electrical Distribution System) The plant will be shutdown due to a reactor trip and Safety Injection from a loss of the startup transformer. The candidate is directed by the CRS to perform OP-603 Section 6.4.1(with the exception of E-1, E-2, and 480V bus 4 and 4KV bus 5). The candidate will make multiple switch manipulations in order to restore power. Once power is restored, the JPM is complete. (Bank JPM CR-28) (RO, SRO-I) JPM H: Respond to a Loss of a Circulating Water Pump K/A 075 A2.02: Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Circulating Water Pumps (075 Circulating Water System) The plant is at 50% power. The Candidate will be given the shift and told to respond tripped and take Immediate Actions of AOP-012, PARTIAL LOSS OF CONDENSER VACUUM OR CIRCULATING WATER PUMP TRIP. The candidate will then start Circulating (Bank JPM CR-055) (RO) JPM I: Trip the Reactor Locally as Outside Auxiliary Operator(OAO). K/A 029 EA1.12: Ability to operate and monitor the following as they apply to a ATWS: M/G Set power supply and rector trip breakers. (O29 ATWS) The plant is at 100% power with an ATWS in progress. As the OAO, the CRS has dispatched the candidate to 480V Busses 2B and 3 to trip the following breakers: ROD DRIVE MOTOR GENERATOR SET A and ROD DRIVE MOTOR GENERATOR SET B. The candidate will go to the 4Kv room and find 480V bus 2B and breaker 52/10B. The candidate will then open the breaker by depressing the trip pushbutton in the center of the cubicle door. The candidate will find 480V bus 3 and breaker 52/14A in the 4Kv room. The candidate will then open the breaker by depressing the trip pushbutton in the center of the cubicle door. Once the breakers are open, the JPM will be complete. (RO, SRO-I, SRO-U)

JPM J: Local Control of S/G Level and Pressure during a Site Black Out. K/A 061 A1.01/A1.02: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: S/G Level and S/G Pressure. (061 Auxiliary/Emergency Feedwater(AFW) System) The plant has experienced a loss of onsite and offsite power. EPP-1 has been implemented. S/G levels are currently 55%. The candidate will be directed by the CRS to perform Attachment 1 of EPP-1 which is Local Control of S/G Level and Pressure. The candidate will first go to the Pipe Jungle and open one of the V!-8A/B/ or C Steam Supply to the SDAFW Pump. Next, the candidate will go to the Secondary Control Panel area and manually throttle V2-14A/B/C to control S/G level between 60-68%. Next, the candidate will go to the Pipe Jungle and perform several valve manipulations to . Once the candidate has notified the Control Room that S/G level is under itrogen supplied for motive air, the JPM will be complete. (RO, SRO-I, SRO-U) JPM K: Locally align containment isolation valves following a Safety Injection. K/A E02 EA1.1: Ability to operate and / or monitor the following as they apply to the (SI Termination); Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (E02 SI Termination) A plant trip and Safety Injection have occurred. EPP-7 is currently being implemented and the CRS has directed the candidate to perform Attachment 2 of EPP-7, Realignment of Components following SI Termination for Inside AO. The candidate will have to go to several different locations inside the Auxiliary Building(RCA) and reset multiple valves in order to realign components necessary to terminate Safety Injection. Once the Control Room is notified that the attachment is complete, the JPM will be complete. (RO, SRO-I)