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{{#Wiki_filter:2014 NRC SRO Written | {{#Wiki_filter:2014 NRC SRO Written Exam | ||
: 76. Given the following plant conditions: - The unit was operating at 100% power | |||
- A Reactor trip and a Safety Injection occurred due to low PRZ pressureCurrent conditions are: - All RCPs are off | - A Reactor trip and a Safety Injection occurred due to low PRZ pressureCurrent conditions are: - All RCPs are off | ||
- RVLIS Full Range is indicating 33% and stable | - RVLIS Full Range is indicating 33% and stable | ||
| Line 23: | Line 24: | ||
- PRZ pressure is 1360 psig and stable | - PRZ pressure is 1360 psig and stable | ||
- Containment pressure is 4.2 psig and rising - All SG NR levels are 45% and stable - Core Exit T/Cs are 755°F and stable | - Containment pressure is 4.2 psig and rising - All SG NR levels are 45% and stable - Core Exit T/Cs are 755°F and stable | ||
- RCS WR Hot Leg temperatures are 678°F and stableBased on these plant condtions, which ONE of the following completes the statementsbelow?A (1) | - RCS WR Hot Leg temperatures are 678°F and stableBased on these plant condtions, which ONE of the following completes the statementsbelow?A (1) break has occurred.To allow the injection of the RHR pumps, in accordance with EOP-FR-C.1, Responseto Inadequate Core Cooling, (2) is required to depressurize the RCS. | ||
(1) PRZ steam space (2) opening of the Reactor Head Vent valves (1) PRZ steam space (2) the depressuization of all intact SGs at maximum rate (1) RCS hot leg (2) opening of the Reactor Head Vent valves (1) RCS hot leg (2) the depressuization of all intact SGs at maximum rate A.B.C.D. Friday, October 31, 2014 10:24:05 AM 76 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 77. Given the following plant conditions: - 'A' RHR pump is under clearance | |||
- A Large Break LOCA occurred | - A Large Break LOCA occurred | ||
- The crew is implementing EOP-E-1, Loss of Reactor or Secondary Coolant, and areevaluating if the 'B' RHR train is capable of cold leg recirculation - 1SI-341, Low Head SI train B to cold leg, red and green lights are not lit Which ONE of the following completes the statements below? | - The crew is implementing EOP-E-1, Loss of Reactor or Secondary Coolant, and areevaluating if the 'B' RHR train is capable of cold leg recirculation - 1SI-341, Low Head SI train B to cold leg, red and green lights are not lit Which ONE of the following completes the statements below? | ||
The position of 1SI-341 can be determined by checking the status of the | The position of 1SI-341 can be determined by checking the status of the (1) | ||
. After the completion of ES-1.3, Transfer To Cold Leg Recirculation, the SIAccumulators are required to be isolated when (2) | |||
. (1) monitor light box (MLB-3B) (2) RCS pressure is below 1000 psig (1) monitor light box (MLB-3B) (2) at least two RCS Hot Leg temperatures are less than 390 | |||
°F (1) status light box (SLB-2) (2) RCS pressure is below 1000 psig (1) status light box (SLB-2) (2) at least two RCS Hot Leg temperatures are less than 390 | |||
°FA.B.C.D. Friday, October 31, 2014 10:24:05 AM 77 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 78. Given the following plant conditions: - The unit is cooling down and RHR pump 'A' was just placed in Shutdown CoolingModeSubsequently the following occurs: - PRZ level lowers rapidly | |||
- PRZ pressure lowers rapidly | - PRZ pressure lowers rapidly | ||
- RHR pump 'A' trips on overcurrent | - RHR pump 'A' trips on overcurrent | ||
- RCS tempurature is 352°F and risingWhich ONE of the following completes the statements below?PRZ level indicators 460 and | |||
- EDG 1B-SB is under clearance Subsequently, a loss of offsite power occursOne minute later DP-1A-SA is lost Which ONE of the following completes the statements below?Breaker indications are available on the MCB for | - RCS tempurature is 352°F and risingWhich ONE of the following completes the statements below?PRZ level indicators 460 and (1) are the Post Accident indicators that should beused to monitor PRZ level. Based on the conditions above, if ONE PRZ level channel of the Post Accidentindicators is NOT operable / available AND is unable to be restored the ACTIONrequired by Technical Specifation 3.3.3.6, Accident Monitoring Instrumentation, is to bein Hot Shutdown within (2) hours.(1) 461 (2) 6 hours(1) 461 (2) 12 hours (1) 462 (2) 6 hours (1) 462 (2) 12 hours A.B.C.D. Friday, October 31, 2014 10:24:05 AM 78 Rev. FINAL 2014 NRC SRO Written Exam | ||
: 79. Given the following plant conditions: - The unit is operating at 100% power | |||
- EDG 1B-SB is under clearance Subsequently, a loss of offsite power occursOne minute later DP-1A-SA is lost Which ONE of the following completes the statements below?Breaker indications are available on the MCB for (1) | |||
.The procedural action required based on the current plant conditions is to dispatch anoperator to (2) | |||
. (1) B-SB equipment ONLY (2) locally close breaker 106 (1) B-SB equipment ONLY (2) manually control EDG 1A-SA load / speed (1) BOTH A-SA and B-SB equipment (2) locally close breaker 106 (1) BOTH A-SA and B-SB equipment (2) manually control EDG 1A-SA load / speed A.B.C.D. Friday, October 31, 2014 10:24:05 AM 79 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 80. Given the following plant conditions: - The plant is operating at 100% power | |||
- Instrument Air is aligned in SEQUENCE 2 with all Air Compressors availableOver the next minute the following indications are observed: - ALB-002-8-5, Computer Alarm Air Systems | - Instrument Air is aligned in SEQUENCE 2 with all Air Compressors availableOver the next minute the following indications are observed: - ALB-002-8-5, Computer Alarm Air Systems | ||
- ALB-002-8-1, Instrument Air Low Press | - ALB-002-8-1, Instrument Air Low Press | ||
- Instrument Air pressure is 73 psig and slowly loweringAOP-017, Loss Of Instrument Air, is being performed. An AO reports the instrument line to the Condenser Steam Dump valves on the westside of the condenser has ruptured. Which ONE of the following (1) describes the expected operation of the Instrument AirCompressors AND (2) identifies the Attachment that should be performed? (1) 1A and 1B running ONLY (2) Attachment 2, Positioning MCB Controllers (1) 1A and 1B running ONLY (2) Attachment 3, Reducing Instrument Air Header Loads (1) 1A, 1B, and 1C running (2) Attachment 2, Positioning MCB Controllers (1) 1A, 1B, and 1C running (2) Attachment 3, Reducing Instrument Air Header | - Instrument Air pressure is 73 psig and slowly loweringAOP-017, Loss Of Instrument Air, is being performed. An AO reports the instrument line to the Condenser Steam Dump valves on the westside of the condenser has ruptured. Which ONE of the following (1) describes the expected operation of the Instrument AirCompressors AND (2) identifies the Attachment that should be performed? (1) 1A and 1B running ONLY (2) Attachment 2, Positioning MCB Controllers (1) 1A and 1B running ONLY (2) Attachment 3, Reducing Instrument Air Header Loads (1) 1A, 1B, and 1C running (2) Attachment 2, Positioning MCB Controllers (1) 1A, 1B, and 1C running (2) Attachment 3, Reducing Instrument Air Header Loads A.B.C.D. Friday, October 31, 2014 10:24:05 AM 80 Rev. FINAL 2014 NRC SRO Written Exam | ||
- EOP-E-0, Reactor Trip Or Safety Injection, is being implemented and SI has | : 81. Given the following plant conditions: - A Reactor Trip and Safety Injection has occured | ||
- EOP-E-0, Reactor Trip Or Safety Injection, is being implemented and SI has been resetThe current conditions are as follows: - RCS Pressure is 1500 psig and stable | |||
- PZR level is off scale low | - PZR level is off scale low | ||
- Subcooling is 3°F and improving | - Subcooling is 3°F and improving | ||
- Containment pressure 0.2 psig and rising - RM-1RR-3597, RHR Pump 1B, is in HIGH alarm and trending up - MLB-4A-SA-6-3 and MLB-4B-SB-6-3, RAB Equip C/D Sump Alert Lvl, status lights are lit - SG levels are: A = 23%, B = 24%, C = 15% | - Containment pressure 0.2 psig and rising - RM-1RR-3597, RHR Pump 1B, is in HIGH alarm and trending up - MLB-4A-SA-6-3 and MLB-4B-SB-6-3, RAB Equip C/D Sump Alert Lvl, status lights are lit - SG levels are: A = 23%, B = 24%, C = 15% | ||
- Total AFW flow has been reduced to 215 KPPHBased on this information, which ONE of the following procedures will be implementedwhen exiting EOP-E-0?EOP-FR-H.1, Response to Loss of Secondary Heat SinkEOP-ECA-1.2, LOCA Outside ContainmentEOP-ES-1.1, SI TerminationEOP-ES-1.2, Post LOCA Cooldown and | - Total AFW flow has been reduced to 215 KPPHBased on this information, which ONE of the following procedures will be implementedwhen exiting EOP-E-0?EOP-FR-H.1, Response to Loss of Secondary Heat SinkEOP-ECA-1.2, LOCA Outside ContainmentEOP-ES-1.1, SI TerminationEOP-ES-1.2, Post LOCA Cooldown and Depressurization A.B.C.D. Friday, October 31, 2014 10:24:05 AM 81 Rev. FINAL 2014 NRC SRO Written Exam | ||
: 82. Given the following plant conditions: - The unit is operating at 100% power | |||
- Control Bank D group step counters indicate 218 stepsSubsequently the following occurs: - Control Bank D Rod P-8 drops to 145 steps. | - Control Bank D group step counters indicate 218 stepsSubsequently the following occurs: - Control Bank D Rod P-8 drops to 145 steps. | ||
- It will take 3 hours to re-align rod P-8 with the Control Bank D rodsWhich ONE of the following statements describes (1) the MAXIMUM Thermal powerlevel the unit is required to maintain in accordance with Tech Spec 3.1.3.1, MovableControl Assemblies - Group Height, | - It will take 3 hours to re-align rod P-8 with the Control Bank D rodsWhich ONE of the following statements describes (1) the MAXIMUM Thermal powerlevel the unit is required to maintain in accordance with Tech Spec 3.1.3.1, MovableControl Assemblies - Group Height, One rod not within alignment limits, AND (2) theBasis for reducing Thermal Power? | ||
(2) Minimizes the effect of a Control Rod ejection accident.A.B.C.D. Friday, October 31, 2014 10:24:05 AM 82 Rev. FINAL 2014 NRC SRO Written | (Reference provided) (1) 85% (2) Provides assurance of fuel rod integrity during continued operation. (1) 85% (2) Minimizes the effect of a Control Rod ejection accident. (1) 75% (2) Provides assurance of fuel rod integrity during continued operation. (1) 75% | ||
- A sample of the 'A' GDT had been obtained to release the tank later todayWhich ONE of the following completes the statements below?In accordance with OST-2044, for a planned crane lift above the WGDTs theMAXIMUM time allowed to complete the crane lift AFTER GDT sampling and activity calculations are performed is within | (2) Minimizes the effect of a Control Rod ejection accident. | ||
- A fuel assembly has just been unlatched in the Containment Upender - The Fuel Handling SRO has reported that Refueling Cavity Level is rapidly lowering - The crew has entered and is implementing AOP-031, Loss of Refueling CavityIntegrity - The CRS has directed that the fuel assembly be returned to the Reactor VesselPrior to relatching the assembly, the following occurs: - ALL CNMT Ventilation Isolation radiation monitors have just gone into alarm - HP reports radiation levels on the Manipulator Crane of 154 mR/hr and risingIn accordance with AOP-031, what action must be taken in Containment? Place the fuel assembly in the Reactor Vessel and evacuate ONLY unnecessarypersonnel. Leave the fuel assembly in the upender and evacuate ONLY unnecessarypersonnel.Place the fuel assembly in the Reactor Vessel and evacuate ALL personnel. Leave the fuel assembly in the upender and evacuate ALL personnel. A.B.C.D. Friday, October 31, 2014 10:24:05 AM 84 Rev. FINAL 2014 NRC SRO Written | A.B.C.D. Friday, October 31, 2014 10:24:05 AM 82 Rev. FINAL 2014 NRC SRO Written Exam | ||
: 83. Given the following plant conditions: - A crane lift above the WGDTs is planned | |||
- A sample of the 'A' GDT had been obtained to release the tank later todayWhich ONE of the following completes the statements below?In accordance with OST-2044, for a planned crane lift above the WGDTs theMAXIMUM time allowed to complete the crane lift AFTER GDT sampling and activity calculations are performed is within (1) hours. In accordance with PLP-114, the concern with the amount of radioactivity in theWaste Gas System is based on not exceeding a MAXIMUM of (2) in theevent of an uncontrolled release as a result of a crane mishap over the GDT.(NOTE: The procedure titles are listed below) | |||
OST-2044, Radwaste Daily Operations Surveillance Test Modes: At All TimesPLP-114, Relocated Technical Specifications and Design Basis Requirements (1) 12 (2) 2 Rem exposure to the public (1) 12 (2) 0.5 Rem exposure to a radiation worker near the tank (1) 24 (2) 2 Rem exposure to the public (1) 24 (2) 0.5 Rem exposure to a radiation worker near the tank A.B.C.D. Friday, October 31, 2014 10:24:05 AM 83 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 84. Given the following plant conditions: - The unit is in Mode 6 with core offload in progress | |||
- A fuel assembly has just been unlatched in the Containment Upender - The Fuel Handling SRO has reported that Refueling Cavity Level is rapidly lowering - The crew has entered and is implementing AOP-031, Loss of Refueling CavityIntegrity - The CRS has directed that the fuel assembly be returned to the Reactor VesselPrior to relatching the assembly, the following occurs: - ALL CNMT Ventilation Isolation radiation monitors have just gone into alarm - HP reports radiation levels on the Manipulator Crane of 154 mR/hr and risingIn accordance with AOP-031, what action must be taken in Containment? Place the fuel assembly in the Reactor Vessel and evacuate ONLY unnecessarypersonnel. Leave the fuel assembly in the upender and evacuate ONLY unnecessarypersonnel.Place the fuel assembly in the Reactor Vessel and evacuate ALL personnel. Leave the fuel assembly in the upender and evacuate ALL personnel. | |||
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 84 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 85. Given the following plant conditions: - The unit was operating at 100% power | |||
- The plant experienced a LOCA several hours ago | - The plant experienced a LOCA several hours ago | ||
- Only one Containment Spray Pump is running due to actions taken by the crew inaccordance with EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation Subsequently, a transition has just been made to EOP-FR-Z.1, Response to HighContainment Pressure - Current Containment pressure is 14 psig and slowly lowering - RWST level is 47% and slowly lowering - 3 Containment Fan Coolers are available and runningWhich ONE of the following actions should be taken for the current plant conditions?Start the second Containment Spray Pump if Containment pressure does not lowerbelow 10 psig before exiting | - Only one Containment Spray Pump is running due to actions taken by the crew inaccordance with EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation Subsequently, a transition has just been made to EOP-FR-Z.1 | ||
Continue operation with one Containment Spray pump per EOP-ECA-1.1 unlessContainment pressure begins rising, then start the second pump.A.B.C.D. Friday, October 31, 2014 10:24:05 AM 85 Rev. FINAL 2014 NRC SRO Written | , Response to HighContainment Pressure - Current Containment pressure is 14 psig and slowly lowering - RWST level is 47% and slowly lowering - 3 Containment Fan Coolers are available and runningWhich ONE of the following actions should be taken for the current plant conditions?Start the second Containment Spray Pump if Containment pressure does not lowerbelow 10 psig before exiting EOP-FR-Z.1.Start the second Containment Spray Pump per EOP-FR-Z.1 since pressure isabove 10 psig. Continue operation with one Containment Spray pump per EOP-ECA-1.1unless Containment pressure exceeds 45 psig, then start the second pump. | ||
- Reactor Engineering is performing a flux map - OWP-RP-01, Reactor Protection, is in place for Loop B, Tavg/-T Channel II, dueto a failed bistable - Repair of Loop B, Tavg/-T Channel II, will not be completed for another 17 hours I&C discovers the bistables for Power Range channel N-41 are set higher than theallowable values of Technical Specifications and repairs will take 7 hoursWhich ONE of the following identifies the LEAST restrictive requirement that must becompleted for these conditions in accordance with OWP-RP-01 and TechnicalSpecifications?Bypass Power Range N-41 until repairs are completed on Loop B Tavg/-TPrepare to shutdown in 1 hour and be in Hot Shutdown within 6 hoursTrip the Power Range N-41 bistables after Loop B Tavg/-T is returned to servicePlace the unit in Hot Standby within 7 | Continue operation with one Containment Spray pump per EOP-ECA-1.1 unlessContainment pressure begins rising, then start the second pump. | ||
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 85 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 86. Given the following plant conditions: - The unit is operating at 100% power | |||
- Reactor Engineering is performing a flux map - OWP-RP-01, Reactor Protection, is in place for Loop B, Tavg/-T Channel II, dueto a failed bistable - Repair of Loop B, Tavg/-T Channel II, will not be completed for another 17 hours I&C discovers the bistables for Power Range channel N-41 are set higher than theallowable values of Technical Specifications and repairs will take 7 hoursWhich ONE of the following identifies the LEAST restrictive requirement that must becompleted for these conditions in accordance with OWP-RP-01 and TechnicalSpecifications?Bypass Power Range N-41 until repairs are completed on Loop B Tavg/-TPrepare to shutdown in 1 hour and be in Hot Shutdown within 6 hoursTrip the Power Range N-41 bistables after Loop B Tavg/-T is returned to servicePlace the unit in Hot Standby within 7 hours A.B.C.D. Friday, October 31, 2014 10:24:05 AM 86 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 87. Given the following plant conditions: - The plant was operating at 40% | |||
- 0600, A 15 gpm tube leak develops in the 'A' SG | - 0600, A 15 gpm tube leak develops in the 'A' SG | ||
- 0604, ALB 022-9-1, Start XFMR-B Lockout Trip Or Trouble, alarms - 0607, ALB-014-8-5, Computer Alarm Steam Generators, alarms - Computer Point ID ZMS1254A, 1MS-58 SG A PORV, indicates NOT SHUT - Attempts to shut 1MS-58 from the MCB are not successful - 0610, ALB-026-1-4, Annun Sys 1 Power Supply Failure, alarmsSubsequently the following occurs: - 0625, An AO reports 1MS-59, MS Line A PORV Isol Vlv, is stuck open | - 0604, ALB 022-9-1, Start XFMR-B Lockout Trip Or Trouble, alarms - 0607, ALB-014-8-5, Computer Alarm Steam Generators, alarms - Computer Point ID ZMS1254A, 1MS-58 SG A PORV, indicates NOT SHUT - Attempts to shut 1MS-58 from the MCB are not successful - 0610, ALB-026-1-4, Annun Sys 1 Power Supply Failure, alarmsSubsequently the following occurs: - 0625, An AO reports 1MS-59, MS Line A PORV Isol Vlv, is stuck open | ||
- 0630, 'A' SG tube leakage degrades and a Reactor Trip and Safety Injection are initiatedWhich ONE of the following identifies the FIRST required classification for theconditions above?(Reference provided) FU1.1 SU1.1 SU5.1 SU8.1A.B.C.D. Friday, October 31, 2014 10:24:05 AM 87 Rev. FINAL 2014 NRC SRO Written | - 0630, 'A' SG tube leakage degrades and a Reactor Trip and Safety Injection are | ||
initiatedWhich ONE of the following identifies the FIRST required classification for theconditions above?(Reference provided) | |||
FU1.1 SU1.1 SU5.1 SU8.1A.B.C.D. Friday, October 31, 2014 10:24:05 AM 87 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 88. Given the following plant conditions: - The unit was operating at 100% power | |||
- Containment Spray Pump 'A' is under clearance | - Containment Spray Pump 'A' is under clearance | ||
- 1A3-SA, cubicle 4A, Emerg MCC 1A34-SA Supply Brkr, is under clearance Subsequently a Service Water leak develops downstream of 1SW-91, CNMT FanCooler AH-2 Inlet CIV, which requires Service Water to be isolated. Which ONE of the following identifies (1) the impact of isolating Service Water to AH-2AND (2) a required action in accordance with Technical Specification 3.6.2.3,Containment Cooling System? (Reference provided) (1) Service Water is isolated to ONLY AH-2 1A-SA (2) restore the inoperable spray system to operable status within 72 hours or be inat least Hot Standby within the next 6 hours. (1) Service Water is isolated to ONLY AH-2 1A-SA (2) restore the inoperable train of fan coolers to operable status within 72 hours orbe in at least Hot Standby within the next 6 hours. (1) Service Water is isolated to BOTH AH-2 1A-SA and 1B-SA (2) restore the inoperable spray system to operable status within 72 hours or be inat least Hot Standby within the next 6 hours. (1) Service Water is isolated to BOTH AH-2 1A-SA and 1B-SA (2) restore the inoperable train of fan coolers to operable status within 72 hours orbe in at least Hot Standby within the next 6 hours.A.B.C.D. Friday, October 31, 2014 10:24:05 AM 88 Rev. FINAL 2014 NRC SRO Written | - 1A3-SA, cubicle 4A, Emerg MCC 1A34-SA Supply Brkr, is under clearance Subsequently a Service Water leak develops downstream of 1SW-91, CNMT FanCooler AH-2 Inlet CIV, which requires Service Water to be isolated. Which ONE of the following identifies (1) the impact of isolating Service Water to AH-2AND (2) a required action in accordance with Technical Specification 3.6.2.3,Containment Cooling System? (Reference provided) (1) Service Water is isolated to ONLY AH-2 1A-SA (2) restore the inoperable spray system to operable status within 72 hours or be inat least Hot Standby within the next 6 hours. (1) Service Water is isolated to ONLY AH-2 1A-SA (2) restore the inoperable train of fan coolers to operable status within 72 hours orbe in at least Hot Standby within the next 6 hours. (1) Service Water is isolated to BOTH AH-2 1A-SA and 1B-SA (2) restore the inoperable spray system to operable status within 72 hours or be inat least Hot Standby within the next 6 hours. (1) Service Water is isolated to BOTH AH-2 1A-SA and 1B-SA (2) restore the inoperable train of fan coolers to operable status within 72 hours orbe in at least Hot Standby within the next 6 hours. | ||
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 88 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 89. Given the following plant conditions: - The unit is operating at 85% power | |||
- The following annunciator is received in the Control Room: - ALB-002-7-2, Serv Wtr Pumps Discharge Low Press - Cooling Tower Basin Level is lowering rapidly - Service Water header pressure is 50 psig and loweringOne minute later the following conditions exist: - Service Water header pressure is 35 psig and rising | - The following annunciator is received in the Control Room: - ALB-002-7-2, Serv Wtr Pumps Discharge Low Press - Cooling Tower Basin Level is lowering rapidly - Service Water header pressure is 50 psig and loweringOne minute later the following conditions exist: - Service Water header pressure is 35 psig and rising | ||
- The Cooling Tower Basin Level is stable- The RAB AO reports that a large volume of water is gushing from the upstreamflange of 1SW-274, Header B Return To Normal Header valve Which ONE of the following completes the statements below? | - The Cooling Tower Basin Level is stable- The RAB AO reports that a large volume of water is gushing from the upstreamflange of 1SW-274, Header B Return To Normal Header valve Which ONE of the following completes the statements below? | ||
The leak is located in the | The leak is located in the (1) system. In accordance with Technical Specification 3.7.4, Emergency Service Water, the basesfor the Limiting Condition of Operation is to ensure that sufficient cooling capacity isavailable for continued operation of safety related equipment during (2) conditions. (1) Normal Service Water (2) normal AND accident (1) Normal Service Water (2) ONLY accident (1) Emergency Service Water (2) normal AND accident (1) Emergency Service Water (2) ONLY accident A.B.C.D. Friday, October 31, 2014 10:24:05 AM 89 Rev. FINAL 2014 NRC SRO Written Exam | ||
- Source range audible counts are unexpectedly rising - Annunciator ALB-013-2-1, Source Range High Flux Lvl at Shutdown, has gone intoalarm due to both NI-31 and NI-32 responsesWhich ONE of the following completes the statements below?The Containment local evacuation alarm | : 90. The following conditions are occurring with the unit in Mode 6 and refueling activities inprogress: | ||
- Spent Fuel Pool level is loweringWhich ONE of the following in accordance with AOP-041, Spent Fuel Pool Events,identifies (1) the FIRST action required to be taken to address the above conditionsAND (2) the basis for the action? (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water SourceAvailability. (2) To prevent loss of inventory that could result in elevated radiation levels in | - Source range audible counts are unexpectedly rising - Annunciator ALB-013-2-1, Source Range High Flux Lvl at Shutdown, has gone intoalarm due to both NI-31 and NI-32 responsesWhich ONE of the following completes the statements below?The Containment local evacuation alarm (1) actuated. Subsequently: - It was determined that both Source Range detectors were not responding correctlyTechnical Specifications requires the RCS boron concentration to be determined within (2) hours. (1) should be manually (2) 4 (1) should be manually (2) 12 (1) will be automatically (2) 4 (1) will be automatically (2) 12A.B.C.D. Friday, October 31, 2014 10:24:05 AM 90 Rev. FINAL 2014 NRC SRO Written Exam | ||
In accordance with AOP-005, Radiation Monitoring System | : 91. Given the following plant conditions: - A Reactor startup is in progress at 10 | ||
- The crew has stabilized the plant at 58% power - Fifteen minutes after stabilization, annunciator ALB 026-2-1, Gross Failed Fuel DetTrouble, alarmed - An RCS activity sample was taken with the following results:- Gross (beta-gamma) specific activity has been calculated to be 165/ | -8 amps in accordance with GP-004, ReactorStartup (Mode 3 To Mode 2) - Power Range N-42 instrument power fuse was found in the blown condition Which ONE of the following completes the statements below? | ||
- Annunciator ALB-009-4-3, Pressurizer Low Level Ltdn Secured and Htrs Off, hasalarmed due to a transmitter failureWhich ONE of the following completes the statements below regarding the systemfailure and Technical Specification requirements? 1CS-231, FK-122.1, Charging Flow demand has increased due to the failure of PRZ level transmitter | (1) is required to be implemented to remove Power Range N-42 from service. Continued power escalation into Mode 1 (2) allowed. (1) OWP-RP, Reactor Protection (2) is (1) OWP-RP, Reactor Protection (2) is NOT (1) OP-105, Excore Nuclear Instrumentation (2) is (1) OP-105, Excore Nuclear Instrumentation (2) is NOT A.B.C.D. Friday, October 31, 2014 10:24:05 AM 91 Rev. FINAL 2014 NRC SRO Written Exam | ||
- Today at 0800 an instrumentation failure has resulted in the crew enteringAOP-001, Malfunction of Rod Control and Indication System and placing the rodcontrol system to manualIn accordance with WCM-001, On-Line Maintenance Risk Management, which ONE ofthe following personel are RESPONSIBLE for assessing the impact on scheduled work and plant risk? STAWCC-SROWork Week ManagerShift Manager | : 92. Given the following plant conditions: - Spent Fuel Pool temperature is rising | ||
- Spent Fuel Pool level is loweringWhich ONE of the following in accordance with AOP-041, Spent Fuel Pool Events,identifies (1) the FIRST action required to be taken to address the above conditionsAND (2) the basis for the action? (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water SourceAvailability. (2) To prevent loss of inventory that could result in elevated radiation levels in the Spent Fuel Pool area. (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water SourceAvailability. (2) Adequate cooling to the Spent Fuel Pools will likely be provided through thefeed and bleed process. (1) Reduce Spent Fuel Pool temperature using Attachment 5, Aligning SFPCooling with Cross-Connected Pump and HX. (2) To prevent boiling of the Spent Fuel Pools that could result in boron plating onthe fuel assemblies. (1) Reduce Spent Fuel Pool temperature using Attachment 5, Aligning SFPCooling with Cross-Connected Pump and HX. (2) Adequate cooling to the Spent Fuel Pools will likely prevent boiling and theresultant lowering of water level. | |||
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 92 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 93. A release of WGDT 'E' is in progress.Subsequently: - REM-1WV-3546, WPB Stack 5 PIG Monitor has gone into HIGH ALARM - 3WG-229, WG Decay Tanks E&F To Plant Vent Valve, failed to shut Which ONE of the following completes the statement below? | |||
In accordance with AOP-005, Radiation Monitoring System (1) is required to beimplemented to stop the release in progress.In accordance with ODCM 3.3.3.11, Radioactive Gaseous Effluent MonitoringInstrumentation, (2) is (are) required to resume the release. | |||
(Reference provided) | |||
(1) OP-120.07, Section 7.1, Total Shutdown (2) the initiatation of the preplanned alternate method of monitoring the appropriateparameter(s) within 72 hours (1) OP-120.07, Section 7.1, Total Shutdown (2) samples, release rate calcs, and an Independent Verification of the valve line-up (1) OP-120.07, Section 8.37, Actions for a REM Monitor Alarm During a WasteGas Decay Tank Release (2) the initiatation of the preplanned alternate method of monitoring the appropriateparameter(s) within 72 hours (1) OP-120.07, Section 8.37, Actions for a REM Monitor Alarm During a WasteGas Decay Tank Release (2) samples, release rate calcs, and an Independent Verification of the valveline-up A.B.C.D. Friday, October 31, 2014 10:24:05 AM 93 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 94. Given the following plant information: - The unit was operating at 79% power when a Turbine runback occurred | |||
- The crew has stabilized the plant at 58% power - Fifteen minutes after stabilization, annunciator ALB 026-2-1, Gross Failed Fuel DetTrouble, alarmed - An RCS activity sample was taken with the following results:- Gross (beta-gamma) specific activity has been calculated to be 165/ | |||
E- Dose-equivalent I-131 specific activity (DEI) is 130 Ci/gmWhich ONE of the following conditions would (1) satisfy Technical Specificationsrequirements, AND (2) what is the basis for the requirement? (1) Be in Mode 3 with T avg <500°F within the following 6 hours. (2) To minimize the potential release of activity in the event of a SG Tube Rupture. (1) Be in Mode 3 with T avg <500°F within the following 6 hours. (2) To reduce the production of fission products until DEI is restored to the TechSpec required value of | |||
< 0.35 Ci/gm. (1) Reduce power below 50% within 3 hours. (2) To minimize the potential release of activity in the event of a SG Tube Rupture. (1) Reduce power below 50% within 3 hours. (2) To reduce the production of fission products until DEI is restored to the TechSpec required value of | |||
< 0.35 Ci/gm.A.B.C.D. Friday, October 31, 2014 10:24:05 AM 94 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 95. Given the following plant conditions: - The unit is operating at 100% power | |||
- Annunciator ALB-009-4-3, Pressurizer Low Level Ltdn Secured and Htrs Off, hasalarmed due to a transmitter failureWhich ONE of the following completes the statements below regarding the systemfailure and Technical Specification requirements? 1CS-231, FK-122.1, Charging Flow demand has increased due to the failure of PRZ level transmitter (1) | |||
. AND The Technical Specifications required acti on is to place the channel in the trippedcondition within (2) hours. (1) 459 (2) 4 (1) 460 (2) 4 (1) 459 (2) 6 (1) 460 (2) 6A.B.C.D. Friday, October 31, 2014 10:24:05 AM 95 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 96. Given the following plant conditions: - The unit is operating at 100% power | |||
- Today at 0800 an instrumentation failure has resulted in the crew enteringAOP-001, Malfunction of Rod Control and Indication System and placing the rodcontrol system to manualIn accordance with WCM-001, On-Line Maintenance Risk Management, which ONE ofthe following personel are RESPONSIBLE for assessing the impact on scheduled work and plant risk? STAWCC-SROWork Week ManagerShift Manager A.B.C.D. Friday, October 31, 2014 10:24:05 AM 96 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 97. Which ONE of the following satisfies the Technical Specification bases requirement foroff-site power distribution with the plant in Mode 1? The requirement can be satisfied by any two separate off-site transmission linesthat can power the SUTs.The requirement can ONLY be satisfied by two off-site transmission lines that feedthe SUTs directly (Cary, Regency Park and Cape Fear North).The requirement can ONLY be satisfied by the off-site transmission lines that do notfeed the respective North or South switchyard bus through a jumper.The requirement is satisfied as long as the switchyard alignment is such that poweris available from the off-site transmission network to both SUTs regardless of thenumber of transmission lines available. | |||
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 97 Rev. FINAL 2014 NRC SRO Written Exam | |||
: 98. Given the following plant conditions: - An employee was injured and contaminated | |||
- The employee was transported to Western WakeMed for treatment before he wasde-contaminated - Duke Energy is planning a news release for this eventWhich ONE of the following completes the statements below? | - The employee was transported to Western WakeMed for treatment before he wasde-contaminated - Duke Energy is planning a news release for this eventWhich ONE of the following completes the statements below? | ||
In accordance with AP-617, Reportability Determination And Notification, theEARLIEST required NRC notification of this event is within | In accordance with AP-617, Reportability Determination And Notification, theEARLIEST required NRC notification of this event is within (1) hours. In accordance with AOP-013, Fuel Handling Accident, (2) is the primaryradiological concern for fuel off-loaded more than 6 months ago because it will NOT bedetected by personal dosimetry or area radiation monitors.(Reference provided) | ||
____Position____Protection of large populations ONLY SEC-TSCProtection of large populations ONLY RCD | (1) 4 (2) Krypton-85 (1) 4 (2) Iodine-131 (1) 8 (2) Krypton-85 (1) 8 (2) Iodine-131 A.B.C.D. Friday, October 31, 2014 10:24:05 AM 98 Rev. FINAL 2014 NRC SRO Written Exam | ||
: 99. Which ONE of the following personnel are RESPONSIBLE for preparing and approvinga Batch Gaseous Effluent Permit in accordance with OP-120.07, Waste Gas Processing? | |||
Prepares Permit | |||
Approves Permit Chemistry Control Room Supervisor Chemistry Shift Manager Radiation Protection Control Room Supervisor Radiation Protection Shift Manager A.B.C.D. Friday, October 31, 2014 10:24:05 AM 99 Rev. FINAL 2014 NRC SRO Written Exam 100. Given the following plant conditions: - An event has occurred that has resulted in the activation of the EmergencyResponse Organization (ERO) - The Technical Support Center (TSC) has completed turnover from the MCR - A Maintenance Mechanic is standing by to enter the RAB to isolate a release inprogress. This will result in a dose of 11,400 mrem TEDE for the individual Which ONE of the following describes the dose limit basis for the type of entry ANDthe position that must approve the expected dose the Mechanic will receive inaccordance with PEP-330, Radiological Consequences? | |||
(NOTE: The titles for the positions are listed below) SEC-TSC Site Emergency Coordinator - Technical Support Center RCD Radiological Control Director | |||
_________Limit Basis__________ | |||
____Position____Protection of large populations ONLY SEC-TSCProtection of large populations ONLY RCD Protect valuable property AND large populations SEC-TSC Protect valuable property AND large populations RCD A.B.C.D.You have completed the test! Friday, October 31, 2014 10:24:05 AM 100 Rev. FINAL ANSWER KEY REPORTfor 2014 NRC SRO Written Exam Test Form: 0 Answers 0#ID12014 NRC RO 1B22014 NRC RO 2C 32014 NRC RO 3A 42014 NRC RO 4D 52014 NRC RO 5A 62014 NRC RO 6A 72014 NRC RO 7C 82014 NRC RO 8D 92014 NRC RO 9A 102014 NRC RO 10C 112014 NRC RO 11D 122014 NRC RO 12A 132014 NRC RO 13D 142014 NRC RO 14D 152014 NRC RO 15D 162014 NRC RO 16A 172014 NRC RO 17B 182014 NRC RO 18A 192014 NRC RO 19A 202014 NRC RO 20A 212014 NRC RO 21B 222014 NRC RO 22D 232014 NRC RO 23D 242014 NRC RO 24D 252014 NRC RO 25B 262014 NRC RO 26A 272014 NRC RO 27C 282014 NRC RO 28D 292014 NRC RO 29C 302014 NRC RO 30B 312014 NRC RO 31C 322014 NRC RO 32C 332014 NRC RO 33B 342014 NRC RO 34A 352014 NRC RO 35C 362014 NRC RO 36D 372014 NRC RO 37D 382014 NRC RO 38B 392014 NRC RO 39B 402014 NRC RO 40D 412014 NRC RO 41B 422014 NRC RO 42A 432014 NRC RO 43D 442014 NRC RO 44B 452014 NRC RO 45C 462014 NRC RO 46A 472014 NRC RO 47CFriday, October 31, 2014 10:26:10 AM 1 | |||
ANSWER KEY REPORTfor 2014 NRC SRO Written Exam Test Form: 0 Answers 0#ID482014 NRC RO 48D492014 NRC RO 49B 502014 NRC RO 50A 512014 NRC RO 51B 522014 NRC RO 52B 532014 NRC RO 53A 542014 NRC RO 54D 552014 NRC RO 55C 562014 NRC RO 56C 572014 NRC RO 57D 582014 NRC RO 58B 592014 NRC RO 59D 602014 NRC RO 60D 612014 NRC RO 61C 622014 NRC RO 62B 632014 NRC RO 63A 642014 NRC RO 64B 652014 NRC RO 65C 662014 NRC RO 66A 672014 NRC RO 67C 682014 NRC RO 68D 692014 NRC RO 69B 702014 NRC RO 70C 712014 NRC RO 71D 722014 NRC RO 72C 732014 NRC RO 73B 742014 NRC RO 74D 752014 NRC RO 75C 762014 NRC SRO 1B 772014 NRC SRO 2B 782014 NRC SRO 3A 792014 NRC SRO 4B 802014 NRC SRO 5D 812014 NRC SRO 6B 822014 NRC SRO 7C 832014 NRC SRO 8B 842014 NRC SRO 9D 852014 NRC SRO 10C 862014 NRC SRO 11D 872014 NRC SRO 12A 882014 NRC SRO 13C 892014 NRC SRO 14C 902014 NRC SRO 15C 912014 NRC SRO 16A 922014 NRC SRO 17B 932014 NRC SRO 18D 942014 NRC SRO 19AFriday, October 31, 2014 10:26:10 AM 2 | |||
ANSWER KEY REPORTfor 2014 NRC SRO Written Exam Test Form: 0 Answers 0#ID952014 NRC SRO 20C962014 NRC SRO 21C 972014 NRC SRO 22A 982014 NRC SRO 23A 992014 NRC SRO 24A 1002014 NRC SRO 25AFriday, October 31, 2014 10:26:10 AM 3 | |||
2014 NRC SRO Question 69 Reference | |||
AP-617 Rev. 35 Page 1 of 49 2014 NRC SRO Question 9 8 (23) Reference I INFORMATION USE HARRIS NUCLEAR PLANT PLANT OPERATING MANUAL VOLUME 1 PART 1 PROCEDURE TYPE: ADMINISTRATIVE PROCEDURE (AP) NUMBER: AP-617 TITLE: REPORTABILITY DETERMINATION AND NOTIFICATION AP-617 Rev. 35 Page 2 of 49 2014 NRC SRO Question 9 8 (23) Reference Table of Contents Section Page 1.0 PURPOSE ............................... | |||
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3 | |||
==2.0 REFERENCES== | ==2.0 REFERENCES== | ||
..................................................................................................... 4 3.0 DEFINITIONS/ABBREVIATIONS ......................................................................... 5 4.0 RESPONSIBILITIES............................................................................................. 6 5.0 PROCEDURE 5.1 Immediate Reportability ............................................................................. 7 5.2 Other Reports .......................................................................................... 11 6.0 DIAGRAMS/ATTACHMENTS Attachment 1 - Immediate Notification Requirements......................................... 12 Attachment 2 - Technical Specification and ODCM Special Reports.................. 22 Attachment 3 - Routine Reports ......................................................................... 26 Attachment 4 - Event Reports (Other than LERs)............................................... 29 Attachment 5 - One Hour Notifications - Sample Wording.................................. 38 Attachment 6 - SAMPLE Reactor Plant Event Notification Worksheet .............. 40 Attachment 7 - Reactor Plant Event Notification Worksheet............................... 41 Attachment 8 - Reportability Evaluation (REW) Worksheet ............................... 43 Revision Summary ....................................................................................................... 49 AP-617 Rev. 35 Page 3 of 49 2014 NRC SRO Question | ............................... | ||
AP-617 Rev. 35 Page 4 of 49 2014 NRC SRO Question | ................................ | ||
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...... 4 3.0 DEFINITIONS/ABBREVIATIONS ............................... | |||
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5 4.0 RESPONSIBILITIES............................... | |||
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6 5.0 PROCEDURE 5.1 Immediate Reportability ............................... | |||
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.............. | |||
7 5.2 Other Reports ............................... | |||
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11 6.0 DIAGRAMS/ATTACHMENTS Attachment 1 - Immediate Notification Requirements............................... | |||
.......... | |||
12 Attachment 2 - Technical Specification and ODCM Special Reports.................. | |||
22 Attachment 3 - Routine Reports ............................... | |||
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26 Attachment 4 - Event Reports (Other than LERs)............................... | |||
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29 Attachment 5 - One Hour Notifications - Sample Wording............................... | |||
... 38 Attachment 6 - SAMPLE Reactor Plant Event Notification Worksheet .............. | |||
40 Attachment 7 - Reactor Plant Event Notification Worksheet............................... | |||
41 Attachment 8 - Reportability Evaluation (REW) Worksheet ............................... | |||
43 Revision Summary ............................... | |||
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........ 49 AP-617 Rev. 35 Page 3 of 49 2014 NRC SRO Question 9 8 (23) Reference 1.0 PURPOSE R 1. This procedure provides guidance in determining NRC Reportability in the following areas: a. Events requiring verbal notification to the NRC via Emergency Telecommunication System (ETS) within one, four, eight, or twenty-four hours. b. Events requiring a written follow-up report to the NRC as a Licensee Event Report (LER) or as a Special Report. c. Scheduled Routine Reports required by Title 10 of the Code of Federal Regulations (CFR) or by the Operating License Technical Specifications; PLP-114, Relocated Technical Specifications and Design Basis Requirements; and the Offsite Dose Calculation Manual (ODCM). d. Event Reports (other than LERs) that are prepared on an as needed basis. e. Reportability evaluation for non-routine reports will be based on Condition Reports per Reference 2.3. 2. The reports listed in this procedure are regulatory requirements. The specific reference for each report is identified with each report on the applicable attachment. 3. Several specific reporting requirements are also addressed by other procedures: a. Immediate notifications of safeguards (security) related events related to the Physical Security of Special Nuclear Material as required by §73.71 (Reporting of Safeguards Events) will be classified per Reference 2.7. b. Reporting of events which result in the declaration of an emergency classification shall be in accordance with Emergency Plan and implementing procedures. c. Reporting of events regarding fish kills, hazardous substance releases, and oil spills shall be in accordance with Reference 2.17 for notification to appropriate Corporate, Local, State and Federal (non-NRC) agencies. d. Reporting of events regarding environmental violations shall be in accordance with this procedure and References 2.30 and 2.31 for notification to appropriate Corporate, Local, State and Federal (non-NRC) agencies. e. Reporting of events to insurers regarding certain fires or other losses shall be in accordance with Reference 2.32. f. Reporting of events regarding non-routine radioactive releases shall be in accordance with Reference 2.37 for notification to appropriate Corporate, Local, State and Federal (non-NRC) agencies. | |||
AP-617 Rev. 35 Page 4 of 49 2014 NRC SRO Question 9 8 (23) Reference 1.0 PURPOSE (continued) 4. This procedure provides instructions for the immediate notification to the NRC using the Emergency Telecommunication System (ETS) phone for non-emergency events that require such reporting according to §50.72, Technical Specifications and other § requirements. | |||
==2.0 REFERENCES== | ==2.0 REFERENCES== | ||
: 1. SEC-NGGC-2120, Use Storage and Protection of Safeguards and Other Limited Access Information 2. AP-611, Regulatory Correspondence (superseded by REG-NGGC-0016) 3. CAP-NGGC-0200, Condition Identification and Screening Process 4. REG-NGGC-0013, Evaluating and Reporting of Defects and Noncompliance in Accordance With 10 CFR 21 5. PEP-310, Notifications and Communications 6. AP-620, Licensee Event Report Development and Approval (superseded by REG-NGGC-0016) 7. SEC-NGGC-2147, Reporting of Safeguards and Fitness for Duty Events 8. SHNPP Operating License and Technical Specifications 9. NUREG 1022, Licensee Event Report System 10. NRC Inspection Procedure 61706, Core Thermal Power Evaluation 11. SP-014, Additional Surveillance/Compensatory Security Measures 12. ADM-NGGC-0201, Nuclear Task Management 13. RDC-NGGC-0001, NGG Standard Records Management Program 14. Offsite Dose Calculation Manual (ODCM) 15. PLP-114, Relocated Technical Specifications and Design Basis Requirements 16. FSAR, TMI Appendix Item II.K.3.3, Report on Safety and Relief Valve Failures and Challenges 17. PLP-500, Fish Kill Reporting, Hazardous Substances Release Notification, and Oil Spill Notification 18. NUREG 1460, Guide to NRC Reporting and Recordkeeping Requirements 19. Regulatory Guide 1.16, Reporting of Operating Information - Appendix A Technical Specifications AP-617 Rev. 35 Page 5 of 49 2014 NRC SRO Question | : 1. SEC-NGGC-2120, Use Storage and Protection of Safeguards and Other Limited Access Information 2. AP-611, Regulatory Correspondence (superseded by REG-NGGC-0016) 3. CAP-NGGC-0200, Condition Identification and Screening Process 4. REG-NGGC-0013, Evaluating and Reporting of Defects and Noncompliance in Accordance With 10 CFR 21 5. PEP-310, Notifications and Communications 6. AP-620, Licensee Event Report Development and Approval (superseded by REG-NGGC-0016) 7. SEC-NGGC-2147, Reporting of Safeguards and Fitness for Duty Events 8. SHNPP Operating License and Technical Specifications 9. NUREG 1022, Licensee Event Report System 10. NRC Inspection Procedure 61706, Core Thermal Power Evaluation 11. SP-014, Additional Surveillance/Compensatory Security Measures 12. ADM-NGGC-0201, Nuclear Task Management 13. RDC-NGGC-0001, NGG Standard Records Management Program 14. Offsite Dose Calculation Manual (ODCM) 15. PLP-114, Relocated Technical Specifications and Design Basis Requirements 16. FSAR, TMI Appendix Item II.K.3.3, Report on Safety and Relief Valve Failures and Challenges 17. PLP-500, Fish Kill Reporting, Hazardous Substances Release Notification, and Oil Spill Notification 18. NUREG 1460, Guide to NRC Reporting and Recordkeeping Requirements 19. Regulatory Guide 1.16, Reporting of Operating Information - Appendix A Technical Specifications AP-617 Rev. 35 Page 5 of 49 2014 NRC SRO Question 9 8 (23) Reference | ||
==2.0 REFERENCES== | ==2.0 REFERENCES== | ||
(continued) 20. Regulatory Guide 10.1, Compilation of Reporting Requirements for Persons Subject to NRC | |||
50.71(a) HESS As Specified 3 yrs prior to date when fracture toughness criteria would be exceeded As Specified in License Telephone report in lieu of LER for an invalid actuation of a system listed in 50.73(a)(2)(iv)(B), other than RPS actuation when critical Reassignment of Licensed Operator to position not requiring license 50.73(a)(1) 50.74(a) Operations Operations 60 Days 30 Days Termination of Licensed Operator 50.74(b) Operations 30 Days Hardware and software changes that affect transmitted data points identified in ERDS Data Point Library 50 App. E, Sec. VI.3.a Nuclear Info Systems Within 30 days after changes are completed Hardware and software changes (except data point modifications) that could affect transmission format and computer communication protocol to the ERDS 50 App. E, Sec. VI.3.b Nuclear Info Systems As soon as practicable and at least 30 days prior to making modification AP-617 Rev. 35 Page 34 of 49 2014 NRC SRO Question | 50.71(a) HESS As Specified 3 yrs prior to date when fracture toughness criteria would be exceeded As Specified in License Telephone report in lieu of LER for an invalid actuation of a system listed in 50.73(a)(2)(iv)(B), other than RPS actuation when critical Reassignment of Licensed Operator to position not requiring license 50.73(a)(1) 50.74(a) Operations Operations 60 Days 30 Days Termination of Licensed Operator 50.74(b) Operations 30 Days Hardware and software changes that affect transmitted data points identified in ERDS Data Point Library 50 App. E, Sec. VI.3.a Nuclear Info Systems Within 30 days after changes are completed Hardware and software changes (except data point modifications) that could affect transmission format and computer communication protocol to the ERDS 50 App. E, Sec. VI.3.b Nuclear Info Systems As soon as practicable and at least 30 days prior to making modification AP-617 Rev. 35 Page 34 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 6 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Test methods for supplemental fracture toughness tests 50 App. G Sec. III.B HESS Submitted and approved prior to testing Fracture Toughness 50 App G, Sec. IV.A.1 HESS 3 years before date when predicted fracture toughness will no longer satisfy App G Report of test results of specimens withdrawn from capsules (fracture toughness tests) 50 App H, Sec. IV HESS Within One Year of Withdrawal Report of effluents released in excess of one-half design objective exposure 50 App I, Sec. IV.A Environmental and Chemistry Within 30 Days from end of quarter (Special Report required by T.S. 3.11.4 satisfies this requirement) Reactor Building ILRT 50 App J, Option A, Sec. V.B TS 4.6.1.2 HESS 3 Months After Test (No time specified in regulation or TS) Certification of Medical Fitness 55.23 55.31 Training Upon Application Incapacitation Because of Disability or Illness 55.25 50.74(c) Operations 30 Days after learning of diagnosis Application for Operator License 55.31 Training As necessary Reapplication for Operator License 55.35 Training Two months after first denial, six months after second denial, two years after third and subsequent denials Conviction of a Felony for Licensed Operator 55.53(g) 73.71(b) Operations/ Security 30 Days Application for Operator License Renewal 55.57 Training As necessary Reports of Conditions of Part 70 License 70.32(b)(5) 75.36 Security As specified in license Changes in plan for Physical Protection of SNM in transit made without prior approval 70.32(d) Security 2 Months AP-617 Rev. 35 Page 35 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 7 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Accident notification report required by DOT on transportation of licensed material 71.5(a)(1)(iv) 49CFR171.15 & 16 Radiation Protection Carrier is to provide notice to DOT at the earliest practicable moment and written follow-up within 30 days Transportation Package Information 71.12(c)(3) 71.101(f) Radiation Protection Before first use (Note 1) Deviations related to Type B package for transport of radioactive material, specifically: significant reduction in effectiveness of Type B packaging during use defects with safety significance in Type B packaging after first use, or the means employed to repair the defects and prevent recurrence conditions of approval of certificate of compliance not observed in making a shipment 71.95 Radiation Protection Within 30 days (NOTE: requirement is for licensee to report) Advance notification of shipment of Irradiated Fuel, Nuclear Waste, or certain shipments of SNM 71.97(a) 73.37(b)(1) 73.72(a) 73.73(a) 73.74(a) Radiation Protection Before shipment (Note 2) Revision notice or cancellation notice for shipment of irradiated fuel, nuclear waste, or certain shipments of SNM 71.97(e) 71.97(f) 73.37(f) 73.72(a)(5) 73.73(b) 73.74(b) Radiation Protection Upon change/ cancellation (Note 2) Advance Notice and Approval of Routes for Shipment of Irradiated Fuel 73.37(b)(7) 73.37(f) Radiation Protection & Nuclear Operations Before shipment (Note 2) Theft or unlawful diversion or attempted theft or unlawful diversion of SNM or spent fuel 73.71 74.11 150.16(b) Security As required (See also 1 hour notifications and SEC-NGGC-2147) | ||
AP-617 Rev. 35 Page 36 of 49 2014 NRC SRO Question | AP-617 Rev. 35 Page 36 of 49 2014 NRC SRO Question 9 8 (23) Reference EVENT REPORTS (Other than LERs) Attachment 4 Sheet 8 of 9 SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Results of Trace Investigation of Lost or Unaccounted for Shipment of SNM Threat to or reduced effectiveness of physical security 73.71(a)74.11 Security 30 Days 73.71(d) Security 30 Days (See also 1 hour notifications and SEC- NGGC-2147) Nuclear Material Transfer (old Form DOE/NRC-741) | ||
Earthquake exceeding Operating Basis Earthquake values 74.15(a) 40.64(a) 70.54 150.16(a) 150.17(a) 100 App. A, Sec. V(A)(2) HESS Whenever transfer occurs (Note 6) HESS Prior to resuming operations Import or export of nuclear equipment or material Bodily injury or property damage from possession or use of radioactive material resulting in an indemnity claim 110 Radiation Protection 140.6(a) Radiation Protection Varies; see Part 110 As promptly as practical Change in proof of financial protection or other financial information filed with the NRC Termination of liability insurance policy used for financial protection (notification of renewal or other proof of financial protection) 140.15(e) Treasury Promptly 140.17(b) Treasury At least 30 days prior to termination Failure of High Integrity Container or Notification of Misuse of a High Integrity Container PLP-300 Radiation Protection Within 30 days of knowledge of the incident Cooling Tower Beacon Outage greater than 30 minutes or restoration from an outage greater than 30 minutes. (Note 8) [Note: The FAA is automatically informed of lighting outage on the communication and meteorological towers via a remote monitoring system] FAA Advisory Circular AC 70/7460-1K Operations Upon Discovery Level of radioactivity in onsite groundwater, exceeding the reporting levels of ODCM O.R. Table 3.12-2 for drinking water. CHE-NGGC-0057 Environmental and Chemistry Within 30 days of discovery AP-617 Rev. 35 Page 37 of 49 2014 NRC SRO Question | Earthquake exceeding Operating Basis Earthquake values 74.15(a) 40.64(a) 70.54 150.16(a) 150.17(a) 100 App. A, Sec. V(A)(2) HESS Whenever transfer occurs (Note 6) HESS Prior to resuming operations Import or export of nuclear equipment or material Bodily injury or property damage from possession or use of radioactive material resulting in an indemnity claim 110 Radiation Protection 140.6(a) Radiation Protection Varies; see Part 110 As promptly as practical Change in proof of financial protection or other financial information filed with the NRC Termination of liability insurance policy used for financial protection (notification of renewal or other proof of financial protection) 140.15(e) Treasury Promptly 140.17(b) Treasury At least 30 days prior to termination Failure of High Integrity Container or Notification of Misuse of a High Integrity Container PLP-300 Radiation Protection Within 30 days of knowledge of the incident Cooling Tower Beacon Outage greater than 30 minutes or restoration from an outage greater than 30 minutes. (Note 8) [Note: The FAA is automatically informed of lighting outage on the communication and meteorological towers via a remote monitoring system] FAA Advisory Circular AC 70/7460-1K Operations Upon Discovery Level of radioactivity in onsite groundwater, exceeding the reporting levels of ODCM O.R. Table 3.12-2 for drinking water. CHE-NGGC-0057 Environmental and Chemistry Within 30 days of discovery AP-617 Rev. 35 Page 37 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 9 of 9 EVENT REPORTS (Other than LERs) NOTES: 1. Development and use of a package will require special reporting requirements per §71.5, 71.95 and 71.101(f). 2. Notification to NRC received at least 10 days before transport of the shipment commences; see §73.72(a), 73.73(a), or 73.74(a) for additional details. State Governor(s) of states through which material is to be shipped shall also be notified by mail postmarked at least 7 days before shipment or by messenger 4 days prior to shipment. Notification of any subsequent schedule changes of greater than six (6) hours or cancellation of shipment shall also be made before the change (See §71.97(c) for additional notification to the Regional NRC Administrator). 3. Not used 4. Report not required if such reporting would duplicate information already submitted per other NRC reporting requirements. 5. When reporting exposure of an individual, the individual shall also be notified not later than the transmittal to the NRC. 6. §40.64(a) specifies next working day for transfers and 10 days for receipt of foreign origin source material. §150.16(a) and 150.17(a) specify within 10 days after material is received. 7. This report does not need to be routed for approval per Reference 2.2 since it is not correspondence to a regulatory agency. 8. Notify the DOT-FAA Flight Service Station at either 1-877-487-6867 or 1-800-992-7433. The following information will be required: a. Harris Nuclear Plant, caller name and telephone number b. Which Hyperbolic Cooling Tower Beacon Warning Lights (by compass orientation) are inoperable c. Location - Plant location is latitude 3538'01"N, longitude 7857'23"W and a distance of 16 miles Southwest of Raleigh d. Height - The Cooling Tower is 523 feet above ground level. The height of the Cooling Tower above sea level is 784 feet. e. Estimated return to service date Determine from the Flight Service Station the name of the individual contacted and when a follow-up call should be made. Document the notification and any required follow-up in an NCR with Licensing as the responsible organization. | ||
AP-617 Rev. 35 Page 38 of 49 2014 NRC SRO Question | AP-617 Rev. 35 Page 38 of 49 2014 NRC SRO Question 9 8 (23) Reference One Hour Notifications - Sample Wording for the Description Field (Licensing will review notifications for follow-up clarification as needed.) I.A. OPERATIONAL EVENTS -10 CFR 50.72 (b) (1) Technical Specification Deviations (10 CFR 50.54x) DEVIATION FROM TECHNICAL SPECIFICATIONS PER 10 CFR 50.54(x) Attachment 5 Sheet 1 of 2 At _ hrs license condition was deviated from per 10 CFR 50.54(x). This condition requires _. Discussion as to why the condition was not met, affect on the plant and when compliance was/will be restored. The NRC Resident Inspector was notified. Safety Limit Violation (TS 6.7.1) VIOLATION OF SAFETY LIMIT At hrs Technical Specification Safety Limit was violated when _. Immediate corrective actions were . Discussion as to the affect on the plant, additional planned actions, and any compensatory actions taken to assure safety. The NRC Resident Inspector was notified. I.B. RADIOLOGICAL EVENTS Radioactive Shipments Note: The time and date of the spent fuel shipment is safeguards information. Date and time of discovery is not safeguards but care should be taken not to link the event to arrival of the cask. Example: SURFACE CONTAMINATION ABOVE LIMITS Smearable contamination on a radioactive materials package, a used fuel shipping cask transported by rail, exceeded the limits of 10 CFR 71.47. There is no evidence of personnel contamination or spread of contamination beyond the rail car. There is no indication of increased exposure to the public as a result of this event. The NRC Resident Inspector was notified. Loss or Theft of Licensed Material/Radiological Sabotage (This example is for Loss only. Theft or Sabotage is reported using SEC-NGGC-2147.) LOCATION OF _ IS UNKNOWN How was loss of SNM discovered and what efforts to relocate are underway? What assurance is there that the lost SNM is under the control of a licensee (vs. the public) and that no personnel have been overexposed? The NRC Resident Inspector was notified. Region II (name) and the State of North Carolina have also been notified. | ||
AP-617 Rev. 35 Page 39 of 49 2014 NRC SRO Question | AP-617 Rev. 35 Page 39 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 5 Sheet 2 of 2 Exposure to Individuals or Releases PERSONNEL OVEREXPOSURE A worker received (internal/external) contamination resulting in an estimated total effective dose equivalent (TEDE) of _ Rem ( mSv). The individual had been doing what, where. How detected? What location on the body. What decontamination was performed to what result? What immediate corrective actions are being taken? The NRC Resident Inspector was notified Accidental Criticality in the Fuel Handling Building No example. This event is extremely rare. | ||
I.C. SECURITY EVENTS Security Events Reported per SEC-NGGC-2147. Security and Safeguards events are prepared by the Security Organization per SEC-NGGC- 2147. International Atomic Energy Agency (IAEA) Representative No example. This event is extremely rare. | I.C. SECURITY EVENTS Security Events Reported per SEC-NGGC-2147. Security and Safeguards events are prepared by the Security Organization per SEC-NGGC- 2147. International Atomic Energy Agency (IAEA) Representative No example. This event is extremely rare. | ||
I.D. FITNESS FOR DUTY FFD - NRC Employee No example. This event is extremely rare. | I.D. FITNESS FOR DUTY FFD - NRC Employee No example. This event is extremely rare. | ||
AP-617 Rev. 35 Page 40 of 49 2014 NRC SRO Question | AP-617 Rev. 35 Page 40 of 49 2014 NRC SRO Question 9 8 (23) Reference NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN # NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*, [2nd] 301-415-0550 and [3rd] 301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers. NOTIFICATION TIME 15:43 EDT FACILITY OR ORGANIZATION Harris Nuclear Plant UNIT 1 NAME OF CALLER John Caves CALL BACK # (919) 362-3636 EVENT TIME & ZONE 14:33 EDT EVENT DATE 09/18/2003 POWER/MODE BEFORE 100% Power, Mode 1 POWER/MODE AFTER 100% Power, Mode 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) | ||
Safe S/D Capab ility AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) | |||
RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) | |||
Control of Rad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D) | |||
Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED X 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) (xiii) Loss Comm/Asmt/Re sp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1) MATERIAL/ | |||
EXPOSURE B??? 8-Hr. Non-Emergency 10CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (identify) OTHER UNSPECIFIED REQMT. (see last column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back) As of 2:33 PM, EDT, more than 20% of the offsite emergency sirens were inoperable for greater than one hour due to loss of power caused by Hurricane Isabel. Currently 27 of 81 sirens are out of service. The State of North Carolina and all four counties within the 10-mile emergency planning zone were notified and are in stand-by to implement mobile route alerting if needed. At this time, Harris cannot estimate the time of siren recovery. This requires an 8-hour non-emergency notification per 10CFR 50.72(b)(3)(xiii) due to the loss of a significant portion of the offsite notification system. The NRC Senior Resident Inspector was informed. NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR YES (EXPLAIN ABOVE) X NO NOT UNDERSTOOD? NRC RESIDENT X STATE(s) X DID ALL SYSTEMS X YES NO FUNCTION AS REQUIRED? LOCAL X OTHER GOV AGENCIES X MODE OF OPERATION UNTIL CORRECTED: 1 ESTIMATE FOR RESTART DATE: ADDITIONAL INFO ON BACK YES X NO MEDIA/PRESS RELEASE X Attachment 6 Sheet 1 of 1 SAMPLE WORKSHEET | |||
SAARPS MPLX E AP-617 Rev. 35 Page 41 of 49 2014 NRC SRO Question | SAARPS MPLX E AP-617 Rev. 35 Page 41 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 7 Sheet 1 of 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN # NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*, [2nd] 301-415-0550 and [3rd] 301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers. NOTIFICATION TIME EST / EDT FACILITY OR ORGANIZATION Harris Nuclear Plant UNIT 1 NAME OF CALLER CALL BACK # 919 - EVENT TIME & ZONE EST / EDT EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) | ||
AP-617 Rev. 35 Page 45 of 49 2014 NRC SRO Question | Safe S/D Capab ility AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) | ||
AP-617 Rev. 35 Page 46 of 49 2014 NRC SRO Question | RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) | ||
AP-617 Rev. 35 Page 47 of 49 2014 NRC SRO Question | Control of Rad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D) | ||
AP-617 Rev. 35 Page 48 of 49 2014 NRC SRO Question | Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/Asmt/Re sp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1) MATERIAL/ | ||
EXPOSURE B??? 8-Hr. Non-Emergency 10CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (identify) OTHER UNSPECIFIED REQMT. (see last column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back) NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR YES (EXPLAIN ABOVE) NO NOT UNDERSTOOD? NRC RESIDENT STATE(s) DID ALL SYSTEMS YES NO FUNCTION AS REQUIRED? LOCAL OTHER GOV AGENCIES MODE OF OPERATION UNTIL CORRECTED: ESTIMATE FOR RESTART DATE: ADDITIONAL INFO ON BACK YES NO MEDIA/PRESS RELEASE AP-617 Rev. 35 Page 42 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 7 Sheet 2 of 2 RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanations should be covered in event description) LIQUID RELEASE GASEOUS RELEASE UNPLANNED RELEASE PLANNED RELEASE ONGOING TERMINATED MONITORED UNMONITORED OFFSITE RELEASE T. S. EXCEEDED RM ALARMS AREAS EVACUATED PERSONNEL EXPOSED OR CONTAMINATED OFFSITE PROTECTIVE ACTIONS RECOMMENDED *State release path in description Release Rate (Ci/sec) % T. S. LIMIT HOO GUIDE Total Activity (Ci) % T. S. LIMIT HOO GUIDE Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 uCi/sec 0.01 Ci Particulate 1 uCi/sec 1 mCi Liquid (excluding tritium and dissolved noble gases) 10 uCi/min 0.1 Ci Liquid (tritium) 0.2 Ci/min 5 Ci Total Activity PLANT STACK CONDENSER/AIR EJECTOR MAIN STEAM LINE SG BLOWDOWN OTHER RAD MONITOR READINGS ALARM SETPOINTS % T. S. LIMIT (if applicable) RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific details/explanations should be covered in event description) LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.) LEAK RATE: UNITS: gpm/gpd T.S. LIMITS: SUDDEN OR LONG-TERM DEVELOPMENT: LEAK START DATE TIME COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS: LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL: EVENT DESCRIPTION (continued from front) NRC HEADQUARTERS DUTY OFFICER CONTACTED: / / : AM/PM NAME DATE TIME AP-617 Rev. 35 Page 43 of 49 2014 NRC SRO Question 9 8 (23) Reference Reportability Evaluation (REW) Worksheet Notification Requirements Per 10CFR50.73 Reports NCR- (Ref. NUREG-1022) Attachment 8 Sheet 1 of 6 A Licensee Event Report (LER) is generally required for any event of the type described in this Attachment within 60 days after the discovery of the event. HNP shall report any applicable event if it occurred within three years of the date of discovery regardless of the plant mode or power level, and regardless of the significance of the structure, system, or component that initiated the event. I. Description of the Event AP-617 Rev. 35 Page 44 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 2 of 6 II. For each Reportability Evaluation, perform the following: Consult with or perform a pre-job briefing with Licensing. Using the details of the event, determine if the reporting category applies to this event. Mark the appropriate block Yes or No. If uncertain, gather more information to make the determination. Consult Licensing as needed. Reference NUREG-1022 as needed since it contains many examples that may aid in the determination. Complete the Reportable Evaluation Section to justify the conclusion that was reached based on known facts. Situation meets this condition? Reportable Event Yes No Plant Shutdown Required by Technical Specifications? The completion of any nuclear plant shutdown required by the HNP Technical Specifications. Yes No Operation or Condition Prohibited by Technical Specifications? Any operation or condition which was prohibited by the HNP Technical Specifications except when: a. The Technical Specification is administrative in nature; b. The event consisted solely of a case of a late surveillance test where the oversight was corrected, the test was performed, and the equipment was found to be capable of performing its specified safety functions; or c. The Technical Specification was revised prior to discovery of the event such that the operation or condition was no longer prohibited at the time of discovery of the event. Yes No Deviation from Technical Specifications? Any deviation from the HNP Technical Specifications authorized pursuant to section 50.54(x). | |||
AP-617 Rev. 35 Page 45 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 3 of 6 Situation meets this condition? Reportable Event Yes No System Actuation? Any event or condition that resulted in a manual or automatic actuation of any of the systems listed below, except when: a. The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; or b. The actuation was invalid and; (1) Occurred while the system was properly removed from service; or (2) Occurred after the safety function had been already completed. The systems to which the requirements above apply are: a. Reactor protection system (RPS) including reactor trip. b. General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). c. Emergency core cooling systems (ECCS) including: high-head and low-head injection systems and the low pressure injection function of residual (decay) heat removal systems. d. Auxiliary or Feedwater system. e. Containment heat removal and depressurization systems, including containment spray and fan cooler systems. f. Emergency ac electrical power systems, including emergency diesel generators (EDGs). g. Emergency service water systems. Yes No Common Cause Inoperability of Independent Trains or Channels? Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to: a. Shut down the reactor and maintain it in a safe shutdown condition, b. Remove residual heat, c. Control the release of radioactive material, or d. Mitigate the consequences of an accident. | |||
AP-617 Rev. 35 Page 46 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 4 of 6 Situation meets this condition? Reportable Event Yes No Event or Condition that Could Have Prevented Fulfillment of a Safety Function? Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to: a. Shut down the reactor and maintain it in a safe shutdown condition; b. Remove residual heat; c. Control the release of radioactive material; or d. Mitigate the consequences of an accident. Events covered above may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, individual component failures need not be reported if redundant equipment in the same system was operable and available to perform the required safety function. Yes No Single Cause that Could Have Prevented Fulfillment of the Safety Functions of Trains or Channels in Different Systems? Any event or condition that as a result of a single cause could have prevented the fulfillment of a safety function for two or more trains or channels in different systems that are needed to: a. Shut down the reactor and maintain it in a safe shutdown condition, b. Remove residual heat, c. Control the release of radioactive material, or d. Mitigate the consequences of an accident. Events covered above may include cases of procedural error, equipment failure, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacy. However, HNP is not required to report an event above if the event results from: a. A shared dependency among trains or channels that is a natural or expected consequence of the approved plant design; or b. Normal and expected wear or degradation. Yes No Degraded or Unanalyzed Condition? Any event or condition that resulted in: a. The condition of the nuclear power plant including its principal safety barriers, being seriously degraded; or b. The nuclear power plant being in an unanalyzed condition that significantly degraded plant safety. | |||
AP-617 Rev. 35 Page 47 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 5 of 6 Situation meets this condition? Reportable Event Yes No External Threat or Hampering? Any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear plant. Yes No Internal Threat or Hampering? Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases. Yes No Radioactive Release? Any airborne radioactive release that, when averaged over a time period of 1 hour, resulted in airborne radionuclide concentrations in an unrestricted area that exceeded 20 times the applicable concentration limits specified in appendix B to 10CFR20, table 2, column 1. Any liquid effluent release that, when averaged over a time period of 1 hour, exceeds 20 times the applicable concentrations specified in Appendix B to 10CFR20 table 2, column 2, at the point of entry into the receiving waters (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases. | |||
AP-617 Rev. 35 Page 48 of 49 2014 NRC SRO Question 9 8 (23) Reference III. Reportable Evaluation Attachment 8 Sheet 6 of 6 | |||
IV. Conclusion Based on the information above, this event: (check one) Does NOT meet the reportability requirements of 10 CFR 50.73. IS reportable to the NRC per the requirements of 10.CFR 50.73. | IV. Conclusion Based on the information above, this event: (check one) Does NOT meet the reportability requirements of 10 CFR 50.73. IS reportable to the NRC per the requirements of 10.CFR 50.73. | ||
AP-617 Rev. 35 Page 49 of 49 2014 NRC SRO Question | AP-617 Rev. 35 Page 49 of 49 2014 NRC SRO Question 9 8 (23) Reference Rev 35 processed with PRR 337339 Revision 35 Summary PRRs Incorporated: 283909, 310079, 329593, 337339, 654718 CRs Incorporated: 589278 (ENHN), 589282 (BREC), 613083 (CORR), 622683 (CORR), 634918 (CORR) [CR 613083] 2.0.42 new reference for NEI 07-07 [ENHN 589278, BREC 589282] Attachment 1 has been restructured/reordered from notification time to functional area. [PRR 329593, 337339] Attachment 1 NOTE 7 revised to add note for ERDS modem [PRR 283909, 329593] Attachment 1 NOTE 11 revised reference from 26.73(a)(2) to 26.719 [CR 613083, 622683] Attachment 1 NOTE 12 revised to add fleet interim guidance regarding NEI 07-07 [PRR 654718] Attachment 1 NOTE 12 revised to clarify information for oil spills [PRR 329593, 337339] Attachment 3 CDE Report Timing Of Response column revised from "By the end of the 1st month following each quarter" to "By the 21st day following each quarter" [PRR 310079] Attachment 3 and Attachment 4 revised to change "NAS" to "NOS" [CR 634918] Attachment 4 Cooling Tower Beacon Outage revised to add note the FAA is automatically informed. [PRR 329593] Attachment 7 revised to add "EST/EDT" to the No tification time block and Event Time & Zone block. | ||
2014 NRC SRO Question 93 (18) Reference 2014 NRC SRO Question 93 (18) Reference 2014 NRC SRO Question 93 (18) Reference 2014 NRC SRO Question 88 (13) Reference | 2014 NRC SRO Question 93 (18) Reference | ||
2014 NRC SRO Question 93 (18) Reference | |||
2014 NRC SRO Question 93 (18) Reference | |||
2014 NRC SRO Question 88 (13) Reference | |||
2014 NRC SRO Question 88 (13) Reference | |||
2014 NRC SRO Question 87 (12) Reference | |||
2014 NRC SRO Question 87 (12) Reference | |||
2014 NRC SRO Question 87 (12) Reference | |||
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2014 NRC SRO Question | 2014 NRC SRO Question 82 (7) Reference | ||
2014 NRC SRO Question 82 (7) Reference}} | |||
Revision as of 08:11, 1 July 2018
| ML14338A038 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/03/2014 |
| From: | NRC/RGN-II |
| To: | Carolina Power & Light Co |
| References | |
| 50-400/14-302 50-400/14-302 | |
| Download: ML14338A038 (89) | |
Text
2014 NRC SRO Written Exam
- 76. Given the following plant conditions: - The unit was operating at 100% power
- A Reactor trip and a Safety Injection occurred due to low PRZ pressureCurrent conditions are: - All RCPs are off
- RVLIS Full Range is indicating 33% and stable
- PRZ level is off scale high
- PRZ pressure is 1360 psig and stable
- Containment pressure is 4.2 psig and rising - All SG NR levels are 45% and stable - Core Exit T/Cs are 755°F and stable
- RCS WR Hot Leg temperatures are 678°F and stableBased on these plant condtions, which ONE of the following completes the statementsbelow?A (1) break has occurred.To allow the injection of the RHR pumps, in accordance with EOP-FR-C.1, Responseto Inadequate Core Cooling, (2) is required to depressurize the RCS.
(1) PRZ steam space (2) opening of the Reactor Head Vent valves (1) PRZ steam space (2) the depressuization of all intact SGs at maximum rate (1) RCS hot leg (2) opening of the Reactor Head Vent valves (1) RCS hot leg (2) the depressuization of all intact SGs at maximum rate A.B.C.D. Friday, October 31, 2014 10:24:05 AM 76 Rev. FINAL 2014 NRC SRO Written Exam
- 77. Given the following plant conditions: - 'A' RHR pump is under clearance
- A Large Break LOCA occurred
- The crew is implementing EOP-E-1, Loss of Reactor or Secondary Coolant, and areevaluating if the 'B' RHR train is capable of cold leg recirculation - 1SI-341, Low Head SI train B to cold leg, red and green lights are not lit Which ONE of the following completes the statements below?
The position of 1SI-341 can be determined by checking the status of the (1)
. After the completion of ES-1.3, Transfer To Cold Leg Recirculation, the SIAccumulators are required to be isolated when (2)
. (1) monitor light box (MLB-3B) (2) RCS pressure is below 1000 psig (1) monitor light box (MLB-3B) (2) at least two RCS Hot Leg temperatures are less than 390
°F (1) status light box (SLB-2) (2) RCS pressure is below 1000 psig (1) status light box (SLB-2) (2) at least two RCS Hot Leg temperatures are less than 390
°FA.B.C.D. Friday, October 31, 2014 10:24:05 AM 77 Rev. FINAL 2014 NRC SRO Written Exam
- 78. Given the following plant conditions: - The unit is cooling down and RHR pump 'A' was just placed in Shutdown CoolingModeSubsequently the following occurs: - PRZ level lowers rapidly
- PRZ pressure lowers rapidly
- RHR pump 'A' trips on overcurrent
- RCS tempurature is 352°F and risingWhich ONE of the following completes the statements below?PRZ level indicators 460 and (1) are the Post Accident indicators that should beused to monitor PRZ level. Based on the conditions above, if ONE PRZ level channel of the Post Accidentindicators is NOT operable / available AND is unable to be restored the ACTIONrequired by Technical Specifation 3.3.3.6, Accident Monitoring Instrumentation, is to bein Hot Shutdown within (2) hours.(1) 461 (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />(1) 461 (2) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (1) 462 (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (1) 462 (2) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> A.B.C.D. Friday, October 31, 2014 10:24:05 AM 78 Rev. FINAL 2014 NRC SRO Written Exam
- 79. Given the following plant conditions: - The unit is operating at 100% power
- EDG 1B-SB is under clearance Subsequently, a loss of offsite power occursOne minute later DP-1A-SA is lost Which ONE of the following completes the statements below?Breaker indications are available on the MCB for (1)
.The procedural action required based on the current plant conditions is to dispatch anoperator to (2)
. (1) B-SB equipment ONLY (2) locally close breaker 106 (1) B-SB equipment ONLY (2) manually control EDG 1A-SA load / speed (1) BOTH A-SA and B-SB equipment (2) locally close breaker 106 (1) BOTH A-SA and B-SB equipment (2) manually control EDG 1A-SA load / speed A.B.C.D. Friday, October 31, 2014 10:24:05 AM 79 Rev. FINAL 2014 NRC SRO Written Exam
- 80. Given the following plant conditions: - The plant is operating at 100% power
- Instrument Air is aligned in SEQUENCE 2 with all Air Compressors availableOver the next minute the following indications are observed: - ALB-002-8-5, Computer Alarm Air Systems
- ALB-002-8-1, Instrument Air Low Press
- Instrument Air pressure is 73 psig and slowly loweringAOP-017, Loss Of Instrument Air, is being performed. An AO reports the instrument line to the Condenser Steam Dump valves on the westside of the condenser has ruptured. Which ONE of the following (1) describes the expected operation of the Instrument AirCompressors AND (2) identifies the Attachment that should be performed? (1) 1A and 1B running ONLY (2) Attachment 2, Positioning MCB Controllers (1) 1A and 1B running ONLY (2) Attachment 3, Reducing Instrument Air Header Loads (1) 1A, 1B, and 1C running (2) Attachment 2, Positioning MCB Controllers (1) 1A, 1B, and 1C running (2) Attachment 3, Reducing Instrument Air Header Loads A.B.C.D. Friday, October 31, 2014 10:24:05 AM 80 Rev. FINAL 2014 NRC SRO Written Exam
- 81. Given the following plant conditions: - A Reactor Trip and Safety Injection has occured
- EOP-E-0, Reactor Trip Or Safety Injection, is being implemented and SI has been resetThe current conditions are as follows: - RCS Pressure is 1500 psig and stable
- PZR level is off scale low
- Subcooling is 3°F and improving
- Containment pressure 0.2 psig and rising - RM-1RR-3597, RHR Pump 1B, is in HIGH alarm and trending up - MLB-4A-SA-6-3 and MLB-4B-SB-6-3, RAB Equip C/D Sump Alert Lvl, status lights are lit - SG levels are: A = 23%, B = 24%, C = 15%
- Total AFW flow has been reduced to 215 KPPHBased on this information, which ONE of the following procedures will be implementedwhen exiting EOP-E-0?EOP-FR-H.1, Response to Loss of Secondary Heat SinkEOP-ECA-1.2, LOCA Outside ContainmentEOP-ES-1.1, SI TerminationEOP-ES-1.2, Post LOCA Cooldown and Depressurization A.B.C.D. Friday, October 31, 2014 10:24:05 AM 81 Rev. FINAL 2014 NRC SRO Written Exam
- 82. Given the following plant conditions: - The unit is operating at 100% power
- Control Bank D group step counters indicate 218 stepsSubsequently the following occurs: - Control Bank D Rod P-8 drops to 145 steps.
- It will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to re-align rod P-8 with the Control Bank D rodsWhich ONE of the following statements describes (1) the MAXIMUM Thermal powerlevel the unit is required to maintain in accordance with Tech Spec 3.1.3.1, MovableControl Assemblies - Group Height, One rod not within alignment limits, AND (2) theBasis for reducing Thermal Power?
(Reference provided) (1) 85% (2) Provides assurance of fuel rod integrity during continued operation. (1) 85% (2) Minimizes the effect of a Control Rod ejection accident. (1) 75% (2) Provides assurance of fuel rod integrity during continued operation. (1) 75%
(2) Minimizes the effect of a Control Rod ejection accident.
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 82 Rev. FINAL 2014 NRC SRO Written Exam
- 83. Given the following plant conditions: - A crane lift above the WGDTs is planned
- A sample of the 'A' GDT had been obtained to release the tank later todayWhich ONE of the following completes the statements below?In accordance with OST-2044, for a planned crane lift above the WGDTs theMAXIMUM time allowed to complete the crane lift AFTER GDT sampling and activity calculations are performed is within (1) hours. In accordance with PLP-114, the concern with the amount of radioactivity in theWaste Gas System is based on not exceeding a MAXIMUM of (2) in theevent of an uncontrolled release as a result of a crane mishap over the GDT.(NOTE: The procedure titles are listed below)
OST-2044, Radwaste Daily Operations Surveillance Test Modes: At All TimesPLP-114, Relocated Technical Specifications and Design Basis Requirements (1) 12 (2) 2 Rem exposure to the public (1) 12 (2) 0.5 Rem exposure to a radiation worker near the tank (1) 24 (2) 2 Rem exposure to the public (1) 24 (2) 0.5 Rem exposure to a radiation worker near the tank A.B.C.D. Friday, October 31, 2014 10:24:05 AM 83 Rev. FINAL 2014 NRC SRO Written Exam
- 84. Given the following plant conditions: - The unit is in Mode 6 with core offload in progress
- A fuel assembly has just been unlatched in the Containment Upender - The Fuel Handling SRO has reported that Refueling Cavity Level is rapidly lowering - The crew has entered and is implementing AOP-031, Loss of Refueling CavityIntegrity - The CRS has directed that the fuel assembly be returned to the Reactor VesselPrior to relatching the assembly, the following occurs: - ALL CNMT Ventilation Isolation radiation monitors have just gone into alarm - HP reports radiation levels on the Manipulator Crane of 154 mR/hr and risingIn accordance with AOP-031, what action must be taken in Containment? Place the fuel assembly in the Reactor Vessel and evacuate ONLY unnecessarypersonnel. Leave the fuel assembly in the upender and evacuate ONLY unnecessarypersonnel.Place the fuel assembly in the Reactor Vessel and evacuate ALL personnel. Leave the fuel assembly in the upender and evacuate ALL personnel.
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 84 Rev. FINAL 2014 NRC SRO Written Exam
- 85. Given the following plant conditions: - The unit was operating at 100% power
- The plant experienced a LOCA several hours ago
- Only one Containment Spray Pump is running due to actions taken by the crew inaccordance with EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation Subsequently, a transition has just been made to EOP-FR-Z.1
, Response to HighContainment Pressure - Current Containment pressure is 14 psig and slowly lowering - RWST level is 47% and slowly lowering - 3 Containment Fan Coolers are available and runningWhich ONE of the following actions should be taken for the current plant conditions?Start the second Containment Spray Pump if Containment pressure does not lowerbelow 10 psig before exiting EOP-FR-Z.1.Start the second Containment Spray Pump per EOP-FR-Z.1 since pressure isabove 10 psig. Continue operation with one Containment Spray pump per EOP-ECA-1.1unless Containment pressure exceeds 45 psig, then start the second pump.
Continue operation with one Containment Spray pump per EOP-ECA-1.1 unlessContainment pressure begins rising, then start the second pump.
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 85 Rev. FINAL 2014 NRC SRO Written Exam
- 86. Given the following plant conditions: - The unit is operating at 100% power
- Reactor Engineering is performing a flux map - OWP-RP-01, Reactor Protection, is in place for Loop B, Tavg/-T Channel II, dueto a failed bistable - Repair of Loop B, Tavg/-T Channel II, will not be completed for another 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> I&C discovers the bistables for Power Range channel N-41 are set higher than theallowable values of Technical Specifications and repairs will take 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />sWhich ONE of the following identifies the LEAST restrictive requirement that must becompleted for these conditions in accordance with OWP-RP-01 and TechnicalSpecifications?Bypass Power Range N-41 until repairs are completed on Loop B Tavg/-TPrepare to shutdown in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in Hot Shutdown within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sTrip the Power Range N-41 bistables after Loop B Tavg/-T is returned to servicePlace the unit in Hot Standby within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> A.B.C.D. Friday, October 31, 2014 10:24:05 AM 86 Rev. FINAL 2014 NRC SRO Written Exam
- 87. Given the following plant conditions: - The plant was operating at 40%
- 0600, A 15 gpm tube leak develops in the 'A' SG
- 0604, ALB 022-9-1, Start XFMR-B Lockout Trip Or Trouble, alarms - 0607, ALB-014-8-5, Computer Alarm Steam Generators, alarms - Computer Point ID ZMS1254A, 1MS-58 SG A PORV, indicates NOT SHUT - Attempts to shut 1MS-58 from the MCB are not successful - 0610, ALB-026-1-4, Annun Sys 1 Power Supply Failure, alarmsSubsequently the following occurs: - 0625, An AO reports 1MS-59, MS Line A PORV Isol Vlv, is stuck open
- 0630, 'A' SG tube leakage degrades and a Reactor Trip and Safety Injection are
initiatedWhich ONE of the following identifies the FIRST required classification for theconditions above?(Reference provided)
FU1.1 SU1.1 SU5.1 SU8.1A.B.C.D. Friday, October 31, 2014 10:24:05 AM 87 Rev. FINAL 2014 NRC SRO Written Exam
- 88. Given the following plant conditions: - The unit was operating at 100% power
- Containment Spray Pump 'A' is under clearance
- 1A3-SA, cubicle 4A, Emerg MCC 1A34-SA Supply Brkr, is under clearance Subsequently a Service Water leak develops downstream of 1SW-91, CNMT FanCooler AH-2 Inlet CIV, which requires Service Water to be isolated. Which ONE of the following identifies (1) the impact of isolating Service Water to AH-2AND (2) a required action in accordance with Technical Specification 3.6.2.3,Containment Cooling System? (Reference provided) (1) Service Water is isolated to ONLY AH-2 1A-SA (2) restore the inoperable spray system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be inat least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (1) Service Water is isolated to ONLY AH-2 1A-SA (2) restore the inoperable train of fan coolers to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> orbe in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (1) Service Water is isolated to BOTH AH-2 1A-SA and 1B-SA (2) restore the inoperable spray system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be inat least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (1) Service Water is isolated to BOTH AH-2 1A-SA and 1B-SA (2) restore the inoperable train of fan coolers to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> orbe in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 88 Rev. FINAL 2014 NRC SRO Written Exam
- 89. Given the following plant conditions: - The unit is operating at 85% power
- The following annunciator is received in the Control Room: - ALB-002-7-2, Serv Wtr Pumps Discharge Low Press - Cooling Tower Basin Level is lowering rapidly - Service Water header pressure is 50 psig and loweringOne minute later the following conditions exist: - Service Water header pressure is 35 psig and rising
- The Cooling Tower Basin Level is stable- The RAB AO reports that a large volume of water is gushing from the upstreamflange of 1SW-274, Header B Return To Normal Header valve Which ONE of the following completes the statements below?
The leak is located in the (1) system. In accordance with Technical Specification 3.7.4, Emergency Service Water, the basesfor the Limiting Condition of Operation is to ensure that sufficient cooling capacity isavailable for continued operation of safety related equipment during (2) conditions. (1) Normal Service Water (2) normal AND accident (1) Normal Service Water (2) ONLY accident (1) Emergency Service Water (2) normal AND accident (1) Emergency Service Water (2) ONLY accident A.B.C.D. Friday, October 31, 2014 10:24:05 AM 89 Rev. FINAL 2014 NRC SRO Written Exam
- 90. The following conditions are occurring with the unit in Mode 6 and refueling activities inprogress:
- Source range audible counts are unexpectedly rising - Annunciator ALB-013-2-1, Source Range High Flux Lvl at Shutdown, has gone intoalarm due to both NI-31 and NI-32 responsesWhich ONE of the following completes the statements below?The Containment local evacuation alarm (1) actuated. Subsequently: - It was determined that both Source Range detectors were not responding correctlyTechnical Specifications requires the RCS boron concentration to be determined within (2) hours. (1) should be manually (2) 4 (1) should be manually (2) 12 (1) will be automatically (2) 4 (1) will be automatically (2) 12A.B.C.D. Friday, October 31, 2014 10:24:05 AM 90 Rev. FINAL 2014 NRC SRO Written Exam
- 91. Given the following plant conditions: - A Reactor startup is in progress at 10
-8 amps in accordance with GP-004, ReactorStartup (Mode 3 To Mode 2) - Power Range N-42 instrument power fuse was found in the blown condition Which ONE of the following completes the statements below?
(1) is required to be implemented to remove Power Range N-42 from service. Continued power escalation into Mode 1 (2) allowed. (1) OWP-RP, Reactor Protection (2) is (1) OWP-RP, Reactor Protection (2) is NOT (1) OP-105, Excore Nuclear Instrumentation (2) is (1) OP-105, Excore Nuclear Instrumentation (2) is NOT A.B.C.D. Friday, October 31, 2014 10:24:05 AM 91 Rev. FINAL 2014 NRC SRO Written Exam
- 92. Given the following plant conditions: - Spent Fuel Pool temperature is rising
- Spent Fuel Pool level is loweringWhich ONE of the following in accordance with AOP-041, Spent Fuel Pool Events,identifies (1) the FIRST action required to be taken to address the above conditionsAND (2) the basis for the action? (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water SourceAvailability. (2) To prevent loss of inventory that could result in elevated radiation levels in the Spent Fuel Pool area. (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water SourceAvailability. (2) Adequate cooling to the Spent Fuel Pools will likely be provided through thefeed and bleed process. (1) Reduce Spent Fuel Pool temperature using Attachment 5, Aligning SFPCooling with Cross-Connected Pump and HX. (2) To prevent boiling of the Spent Fuel Pools that could result in boron plating onthe fuel assemblies. (1) Reduce Spent Fuel Pool temperature using Attachment 5, Aligning SFPCooling with Cross-Connected Pump and HX. (2) Adequate cooling to the Spent Fuel Pools will likely prevent boiling and theresultant lowering of water level.
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 92 Rev. FINAL 2014 NRC SRO Written Exam
- 93. A release of WGDT 'E' is in progress.Subsequently: - REM-1WV-3546, WPB Stack 5 PIG Monitor has gone into HIGH ALARM - 3WG-229, WG Decay Tanks E&F To Plant Vent Valve, failed to shut Which ONE of the following completes the statement below?
In accordance with AOP-005, Radiation Monitoring System (1) is required to beimplemented to stop the release in progress.In accordance with ODCM 3.3.3.11, Radioactive Gaseous Effluent MonitoringInstrumentation, (2) is (are) required to resume the release.
(Reference provided)
(1) OP-120.07, Section 7.1, Total Shutdown (2) the initiatation of the preplanned alternate method of monitoring the appropriateparameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (1) OP-120.07, Section 7.1, Total Shutdown (2) samples, release rate calcs, and an Independent Verification of the valve line-up (1) OP-120.07, Section 8.37, Actions for a REM Monitor Alarm During a WasteGas Decay Tank Release (2) the initiatation of the preplanned alternate method of monitoring the appropriateparameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (1) OP-120.07, Section 8.37, Actions for a REM Monitor Alarm During a WasteGas Decay Tank Release (2) samples, release rate calcs, and an Independent Verification of the valveline-up A.B.C.D. Friday, October 31, 2014 10:24:05 AM 93 Rev. FINAL 2014 NRC SRO Written Exam
- 94. Given the following plant information: - The unit was operating at 79% power when a Turbine runback occurred
- The crew has stabilized the plant at 58% power - Fifteen minutes after stabilization, annunciator ALB 026-2-1, Gross Failed Fuel DetTrouble, alarmed - An RCS activity sample was taken with the following results:- Gross (beta-gamma) specific activity has been calculated to be 165/
E- Dose-equivalent I-131 specific activity (DEI) is 130 Ci/gmWhich ONE of the following conditions would (1) satisfy Technical Specificationsrequirements, AND (2) what is the basis for the requirement? (1) Be in Mode 3 with T avg <500°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (2) To minimize the potential release of activity in the event of a SG Tube Rupture. (1) Be in Mode 3 with T avg <500°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (2) To reduce the production of fission products until DEI is restored to the TechSpec required value of
< 0.35 Ci/gm. (1) Reduce power below 50% within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. (2) To minimize the potential release of activity in the event of a SG Tube Rupture. (1) Reduce power below 50% within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. (2) To reduce the production of fission products until DEI is restored to the TechSpec required value of
< 0.35 Ci/gm.A.B.C.D. Friday, October 31, 2014 10:24:05 AM 94 Rev. FINAL 2014 NRC SRO Written Exam
- 95. Given the following plant conditions: - The unit is operating at 100% power
- Annunciator ALB-009-4-3, Pressurizer Low Level Ltdn Secured and Htrs Off, hasalarmed due to a transmitter failureWhich ONE of the following completes the statements below regarding the systemfailure and Technical Specification requirements? 1CS-231, FK-122.1, Charging Flow demand has increased due to the failure of PRZ level transmitter (1)
. AND The Technical Specifications required acti on is to place the channel in the trippedcondition within (2) hours. (1) 459 (2) 4 (1) 460 (2) 4 (1) 459 (2) 6 (1) 460 (2) 6A.B.C.D. Friday, October 31, 2014 10:24:05 AM 95 Rev. FINAL 2014 NRC SRO Written Exam
- 96. Given the following plant conditions: - The unit is operating at 100% power
- Today at 0800 an instrumentation failure has resulted in the crew enteringAOP-001, Malfunction of Rod Control and Indication System and placing the rodcontrol system to manualIn accordance with WCM-001, On-Line Maintenance Risk Management, which ONE ofthe following personel are RESPONSIBLE for assessing the impact on scheduled work and plant risk? STAWCC-SROWork Week ManagerShift Manager A.B.C.D. Friday, October 31, 2014 10:24:05 AM 96 Rev. FINAL 2014 NRC SRO Written Exam
- 97. Which ONE of the following satisfies the Technical Specification bases requirement foroff-site power distribution with the plant in Mode 1? The requirement can be satisfied by any two separate off-site transmission linesthat can power the SUTs.The requirement can ONLY be satisfied by two off-site transmission lines that feedthe SUTs directly (Cary, Regency Park and Cape Fear North).The requirement can ONLY be satisfied by the off-site transmission lines that do notfeed the respective North or South switchyard bus through a jumper.The requirement is satisfied as long as the switchyard alignment is such that poweris available from the off-site transmission network to both SUTs regardless of thenumber of transmission lines available.
A.B.C.D. Friday, October 31, 2014 10:24:05 AM 97 Rev. FINAL 2014 NRC SRO Written Exam
- 98. Given the following plant conditions: - An employee was injured and contaminated
- The employee was transported to Western WakeMed for treatment before he wasde-contaminated - Duke Energy is planning a news release for this eventWhich ONE of the following completes the statements below?
In accordance with AP-617, Reportability Determination And Notification, theEARLIEST required NRC notification of this event is within (1) hours. In accordance with AOP-013, Fuel Handling Accident, (2) is the primaryradiological concern for fuel off-loaded more than 6 months ago because it will NOT bedetected by personal dosimetry or area radiation monitors.(Reference provided)
(1) 4 (2) Krypton-85 (1) 4 (2) Iodine-131 (1) 8 (2) Krypton-85 (1) 8 (2) Iodine-131 A.B.C.D. Friday, October 31, 2014 10:24:05 AM 98 Rev. FINAL 2014 NRC SRO Written Exam
- 99. Which ONE of the following personnel are RESPONSIBLE for preparing and approvinga Batch Gaseous Effluent Permit in accordance with OP-120.07, Waste Gas Processing?
Prepares Permit
Approves Permit Chemistry Control Room Supervisor Chemistry Shift Manager Radiation Protection Control Room Supervisor Radiation Protection Shift Manager A.B.C.D. Friday, October 31, 2014 10:24:05 AM 99 Rev. FINAL 2014 NRC SRO Written Exam 100. Given the following plant conditions: - An event has occurred that has resulted in the activation of the EmergencyResponse Organization (ERO) - The Technical Support Center (TSC) has completed turnover from the MCR - A Maintenance Mechanic is standing by to enter the RAB to isolate a release inprogress. This will result in a dose of 11,400 mrem TEDE for the individual Which ONE of the following describes the dose limit basis for the type of entry ANDthe position that must approve the expected dose the Mechanic will receive inaccordance with PEP-330, Radiological Consequences?
(NOTE: The titles for the positions are listed below) SEC-TSC Site Emergency Coordinator - Technical Support Center RCD Radiological Control Director
_________Limit Basis__________
____Position____Protection of large populations ONLY SEC-TSCProtection of large populations ONLY RCD Protect valuable property AND large populations SEC-TSC Protect valuable property AND large populations RCD A.B.C.D.You have completed the test! Friday, October 31, 2014 10:24:05 AM 100 Rev. FINAL ANSWER KEY REPORTfor 2014 NRC SRO Written Exam Test Form: 0 Answers 0#ID12014 NRC RO 1B22014 NRC RO 2C 32014 NRC RO 3A 42014 NRC RO 4D 52014 NRC RO 5A 62014 NRC RO 6A 72014 NRC RO 7C 82014 NRC RO 8D 92014 NRC RO 9A 102014 NRC RO 10C 112014 NRC RO 11D 122014 NRC RO 12A 132014 NRC RO 13D 142014 NRC RO 14D 152014 NRC RO 15D 162014 NRC RO 16A 172014 NRC RO 17B 182014 NRC RO 18A 192014 NRC RO 19A 202014 NRC RO 20A 212014 NRC RO 21B 222014 NRC RO 22D 232014 NRC RO 23D 242014 NRC RO 24D 252014 NRC RO 25B 262014 NRC RO 26A 272014 NRC RO 27C 282014 NRC RO 28D 292014 NRC RO 29C 302014 NRC RO 30B 312014 NRC RO 31C 322014 NRC RO 32C 332014 NRC RO 33B 342014 NRC RO 34A 352014 NRC RO 35C 362014 NRC RO 36D 372014 NRC RO 37D 382014 NRC RO 38B 392014 NRC RO 39B 402014 NRC RO 40D 412014 NRC RO 41B 422014 NRC RO 42A 432014 NRC RO 43D 442014 NRC RO 44B 452014 NRC RO 45C 462014 NRC RO 46A 472014 NRC RO 47CFriday, October 31, 2014 10:26:10 AM 1
ANSWER KEY REPORTfor 2014 NRC SRO Written Exam Test Form: 0 Answers 0#ID482014 NRC RO 48D492014 NRC RO 49B 502014 NRC RO 50A 512014 NRC RO 51B 522014 NRC RO 52B 532014 NRC RO 53A 542014 NRC RO 54D 552014 NRC RO 55C 562014 NRC RO 56C 572014 NRC RO 57D 582014 NRC RO 58B 592014 NRC RO 59D 602014 NRC RO 60D 612014 NRC RO 61C 622014 NRC RO 62B 632014 NRC RO 63A 642014 NRC RO 64B 652014 NRC RO 65C 662014 NRC RO 66A 672014 NRC RO 67C 682014 NRC RO 68D 692014 NRC RO 69B 702014 NRC RO 70C 712014 NRC RO 71D 722014 NRC RO 72C 732014 NRC RO 73B 742014 NRC RO 74D 752014 NRC RO 75C 762014 NRC SRO 1B 772014 NRC SRO 2B 782014 NRC SRO 3A 792014 NRC SRO 4B 802014 NRC SRO 5D 812014 NRC SRO 6B 822014 NRC SRO 7C 832014 NRC SRO 8B 842014 NRC SRO 9D 852014 NRC SRO 10C 862014 NRC SRO 11D 872014 NRC SRO 12A 882014 NRC SRO 13C 892014 NRC SRO 14C 902014 NRC SRO 15C 912014 NRC SRO 16A 922014 NRC SRO 17B 932014 NRC SRO 18D 942014 NRC SRO 19AFriday, October 31, 2014 10:26:10 AM 2
ANSWER KEY REPORTfor 2014 NRC SRO Written Exam Test Form: 0 Answers 0#ID952014 NRC SRO 20C962014 NRC SRO 21C 972014 NRC SRO 22A 982014 NRC SRO 23A 992014 NRC SRO 24A 1002014 NRC SRO 25AFriday, October 31, 2014 10:26:10 AM 3
2014 NRC SRO Question 69 Reference
AP-617 Rev. 35 Page 1 of 49 2014 NRC SRO Question 9 8 (23) Reference I INFORMATION USE HARRIS NUCLEAR PLANT PLANT OPERATING MANUAL VOLUME 1 PART 1 PROCEDURE TYPE: ADMINISTRATIVE PROCEDURE (AP) NUMBER: AP-617 TITLE: REPORTABILITY DETERMINATION AND NOTIFICATION AP-617 Rev. 35 Page 2 of 49 2014 NRC SRO Question 9 8 (23) Reference Table of Contents Section Page 1.0 PURPOSE ...............................
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3
2.0 REFERENCES
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...... 4 3.0 DEFINITIONS/ABBREVIATIONS ...............................
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5 4.0 RESPONSIBILITIES...............................
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6 5.0 PROCEDURE 5.1 Immediate Reportability ...............................
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7 5.2 Other Reports ...............................
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11 6.0 DIAGRAMS/ATTACHMENTS Attachment 1 - Immediate Notification Requirements...............................
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12 Attachment 2 - Technical Specification and ODCM Special Reports..................
22 Attachment 3 - Routine Reports ...............................
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26 Attachment 4 - Event Reports (Other than LERs)...............................
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29 Attachment 5 - One Hour Notifications - Sample Wording...............................
... 38 Attachment 6 - SAMPLE Reactor Plant Event Notification Worksheet ..............
40 Attachment 7 - Reactor Plant Event Notification Worksheet...............................
41 Attachment 8 - Reportability Evaluation (REW) Worksheet ...............................
43 Revision Summary ...............................
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........ 49 AP-617 Rev. 35 Page 3 of 49 2014 NRC SRO Question 9 8 (23) Reference 1.0 PURPOSE R 1. This procedure provides guidance in determining NRC Reportability in the following areas: a. Events requiring verbal notification to the NRC via Emergency Telecommunication System (ETS) within one, four, eight, or twenty-four hours. b. Events requiring a written follow-up report to the NRC as a Licensee Event Report (LER) or as a Special Report. c. Scheduled Routine Reports required by Title 10 of the Code of Federal Regulations (CFR) or by the Operating License Technical Specifications; PLP-114, Relocated Technical Specifications and Design Basis Requirements; and the Offsite Dose Calculation Manual (ODCM). d. Event Reports (other than LERs) that are prepared on an as needed basis. e. Reportability evaluation for non-routine reports will be based on Condition Reports per Reference 2.3. 2. The reports listed in this procedure are regulatory requirements. The specific reference for each report is identified with each report on the applicable attachment. 3. Several specific reporting requirements are also addressed by other procedures: a. Immediate notifications of safeguards (security) related events related to the Physical Security of Special Nuclear Material as required by §73.71 (Reporting of Safeguards Events) will be classified per Reference 2.7. b. Reporting of events which result in the declaration of an emergency classification shall be in accordance with Emergency Plan and implementing procedures. c. Reporting of events regarding fish kills, hazardous substance releases, and oil spills shall be in accordance with Reference 2.17 for notification to appropriate Corporate, Local, State and Federal (non-NRC) agencies. d. Reporting of events regarding environmental violations shall be in accordance with this procedure and References 2.30 and 2.31 for notification to appropriate Corporate, Local, State and Federal (non-NRC) agencies. e. Reporting of events to insurers regarding certain fires or other losses shall be in accordance with Reference 2.32. f. Reporting of events regarding non-routine radioactive releases shall be in accordance with Reference 2.37 for notification to appropriate Corporate, Local, State and Federal (non-NRC) agencies.
AP-617 Rev. 35 Page 4 of 49 2014 NRC SRO Question 9 8 (23) Reference 1.0 PURPOSE (continued) 4. This procedure provides instructions for the immediate notification to the NRC using the Emergency Telecommunication System (ETS) phone for non-emergency events that require such reporting according to §50.72, Technical Specifications and other § requirements.
2.0 REFERENCES
- 1. SEC-NGGC-2120, Use Storage and Protection of Safeguards and Other Limited Access Information 2. AP-611, Regulatory Correspondence (superseded by REG-NGGC-0016) 3. CAP-NGGC-0200, Condition Identification and Screening Process 4. REG-NGGC-0013, Evaluating and Reporting of Defects and Noncompliance in Accordance With 10 CFR 21 5. PEP-310, Notifications and Communications 6. AP-620, Licensee Event Report Development and Approval (superseded by REG-NGGC-0016) 7. SEC-NGGC-2147, Reporting of Safeguards and Fitness for Duty Events 8. SHNPP Operating License and Technical Specifications 9. NUREG 1022, Licensee Event Report System 10. NRC Inspection Procedure 61706, Core Thermal Power Evaluation 11. SP-014, Additional Surveillance/Compensatory Security Measures 12. ADM-NGGC-0201, Nuclear Task Management 13. RDC-NGGC-0001, NGG Standard Records Management Program 14. Offsite Dose Calculation Manual (ODCM) 15. PLP-114, Relocated Technical Specifications and Design Basis Requirements 16. FSAR, TMI Appendix Item II.K.3.3, Report on Safety and Relief Valve Failures and Challenges 17. PLP-500, Fish Kill Reporting, Hazardous Substances Release Notification, and Oil Spill Notification 18. NUREG 1460, Guide to NRC Reporting and Recordkeeping Requirements 19. Regulatory Guide 1.16, Reporting of Operating Information - Appendix A Technical Specifications AP-617 Rev. 35 Page 5 of 49 2014 NRC SRO Question 9 8 (23) Reference
2.0 REFERENCES
(continued) 20. Regulatory Guide 10.1, Compilation of Reporting Requirements for Persons Subject to NRC Regulations 21. IE Information Notice No. 83-34, Event Notification Information Worksheet 22. IE Information Notice No. 85-62, Backup Telephone Numbers to the NRC Operations Center 23. IE Information Notice No. 85-78, Event Notification 24. Letter HELD-H-278, Zimmerman to Beatty et al., March 31, 1987 25. SAF-SUBS-00033, Employee Incident Investigations 26. PLP-201, Emergency Plan 27. EPM-400, Public Notification and Alerting System 28. ESR 95-00745, Deletion of "Fail indicator circuits for CT Beacons" 29. U.S. Department of Transportation, Federal Aviation Administration Advisory Circular AC 70/7460-1K 30. EMP-001, NPDES Permit Monitoring 31. National Pollutant Discharge Elimination System (NPDES) Permit Number NC0039586, North Carolina Department of Environment and Natural Resources, Division of Water Quality 32. PLP-105, Insurance Programs at Harris Nuclear Plant 33. NEI Position Statement: Guidance to Licensees on Complying with the Licensed Power Limit (NRC ADAMS Accession No. ML081750537) 34. NRC Memorandum titled "Discussion of 'Licensed Power Level'", Jordan, E.L., Division of Reactor Operations Inspection, Aug. 22, 1980 35. PLP-300, Process Control Program 36. AD-SY-ALL-0401, Fitness For Duty Program 37. CHE-NGGC-0057, Groundwater Protection Program 38. PLP-717, Equipment Important To Emergency Preparedness and ERO Response 39. REG-NGGC-0016, Regulatory Correspondence & LER Development 40. CR 580945, Oct. 3, 2012 Notice of Violation for EOF 41. FPP-013, Fire Protection-Minimum Requirements, Mitigating Actions and Surveillance Requirements 42. NEI 07-07, Ground Water Protection Initiative Voluntary Communications 3.0 DEFINITIONS/ABBREVIATIONS 1. Code of Federal Regulations - CFR 2. Equipment Inoperable Record - EIR 3. Emergency Response Facility Information System - ERFIS AP-617 Rev. 35 Page 6 of 49 2014 NRC SRO Question 9 8 (23) Reference 3.0 DEFINITIONS/ABBREVIATIONS (continued) 4. Emergency Telecommunication System - ETS 5. Engineered Safety Feature - ESF 6. Licensee Event Report (LER) - A written report conforming to the format and content requirements of §50.73 and NUREG 1022. 7. National Oceanic and Aeronautic Administration - NOAA 8. Nuclear Regulatory Commission - NRC 9. Offsite Dose Calculation Manual - ODCM 10. Operating License - OL 11. Reactor Protection System - RPS 12. Safety Parameter Display System - SPDS 13. Solid State Protection System - SSPS 14. Emergency Notification System - ENS 15. Health Physics Network - HPN 4.0 RESPONSIBILITIES 1. The Shift Manager (SM): a. Determining immediate NRC reportability, and b. Making appropriate notifications. 2. The Supervisor - Licensing/Regulatory Programs: a. Confirming the correctness of immediate reportability determinations. b. Determining need for reports to other outside agencies. c. Generating related reports as required. 3. The Superintendent - Security (or On-duty Security Supervisor): a. Evaluating security related events in accordance with Reference 2.7 b. Informing the SM when a security related event must be reported to the NRC.
AP-617 Rev. 35 Page 7 of 49 2014 NRC SRO Question 9 8 (23) Reference 5.0 PROCEDURE 5.1 Immediate Reportability 1. The Shift Manager (SM) determines that an event requires immediate notification (per Attachment 1), or the Superintendent - Security (or On- duty Security Supervisor) informs the SM that an event requires notification to the NRC. 2. The SM prepares or assigns an individual to prepare the Reactor Plant Event Notification Worksheet (Attachment 7). Event Notification Worksheets for Safeguard/Security events are normally prepared by the Security Organization. 3. The Event Description narrative should be as short and concise as possible while conveying a clear description of the event. Attachment 5 may be used for developing one-hour notifications. Attachment 6 is a completed sample Worksheet. 4. The initial part of the Event Description should state: a. The initial conditions of the plant or affected systems prior to event occurrence. b. The actual event and direct cause, if known. c. The current conditions of the plant or affected systems Example - Plant was in Mode 1 at 50% reactor power and increasing load. At 1000, the reactor was manually tripped following a loss of both main feedwater pumps caused by feedwater regulating valve oscillations. The plant is stable in Mode 3 at normal temperature and pressure. 5. The balance of the Event Description should contain known specific details of precursor events which led to the reportable event, including the time of each event. Report only known facts; do not speculate. Example - Feedwater regulating valve oscillations occurred when placing valves into automatic control. The A and B feedwater regulating valves had been successfully placed in automatic at 0950 and were controlling normally. When the C valve was placed in automatic at 0958, large oscillations were noted in the "C" valve followed by oscillations in the "A" and "B" valves. During the oscillation, the condensate booster pump tripped on low flow resulting in tripping of the feed pump. The reactor was manually tripped prior to receipt of a steam generator low water level signal.
AP-617 Rev. 35 Page 8 of 49 2014 NRC SRO Question 9 8 (23) Reference 5.1 Immediate Reportability (continued) 6. The Event Description should include a statement of the proper functioning or failure to function of safety systems and the safety significance of an event, if such a determination is possible. If possible, also include two or three compensatory actions taken to assure safety. The Shift Technical Advisor may assist the SM in making such a determination. Example - All safety systems functioned as expected (or list equipment which failed to function as expected). "AFW automatically actuated to provide continued decay heat removal. Compensatory actions to assure safety include-" 7. The SM: a. Reviews the Event Notification Worksheet. b. Makes changes if necessary. c. Approves it for release. 8. If time permits, the SM shall contact the General Manager - Harris Plant and the NRC Resident Inspector, and Licensing/Regulatory Programs and provide them the information contained in the notification. 9. The SM notifies the NRC by giving the approved Event Notification Worksheet to an available individual to telecopy the Worksheet to the NRC via the fax number (301-816-5151, may be confirmed via EPL-001). NOTE: The NRC electronically records notifications. 10. When the approved Event Notification Worksheet has been sent, contact the NRC Operations Center Duty Officer by performing either of the following: a. Pick up the receiver on the Emergency Telecommunication System Telephone and dial the NRC Operations Center Duty Officer via one of the numbers located on the phone label, in EPL-001, or on the Event Notification Worksheet. OR b. If desired, use a normal telephone line to call the NRC Operations Center Duty Officer via one of the numbers located on the phone label, in EPL-001, or on the Event Notification Worksheet.
AP-617 Rev. 35 Page 9 of 49 2014 NRC SRO Question 9 8 (23) Reference 5.1 Immediate Reportability (continued) 11. When the Duty Officer responds: a. Caller says, "THIS IS THE HARRIS NUCLEAR PLANT. THIS IS A NOTIFICATION OF (appropriate event classification from worksheet). HAVE YOU RECEIVED A TELECOPY OF THIS NOTIFICATION?" b. If response is "No", have an available individual perform Step 5.1.9 again while continuing with this step. c. The caller gives the information on the Event Notification Worksheet and repeats information when requested. d. The notification should be read in its entirety. e. The caller should respond to any requests for additional information that can be answered accurately, or if the caller is not able to accurately respond to the Duty Officer's requests, the caller shall write down the request and inform the Duty Officer that this information will be delivered in a follow up notification. f. The caller should record questions asked, responses provided and if follow up is necessary on a separate sheet of paper and attach it to the Event Notification Worksheet. 12. If the Duty Officer has not received a telecopy after the notification has been completed, the caller shall request the Duty Officer to read back the notification and, if necessary, correct any errors. 13. The caller records the Event Notification Number, name of the individual contacted and time of contact on the Event Notification Worksheet. 14. The caller informs the Duty Officer that the caller is signing off. The Duty Officer may request to stay on and leave the line open. If this occurs, the caller should comply. A replacement caller may be necessary to stay on the phone. 15. If additional information is provided to the Duty Officer beyond the initial Event Notification Worksheet, notify the General Manager - Harris Plant, the NRC Resident Inspector, and Licensing/Regulatory Programs of the additional information provided.
AP-617 Rev. 35 Page 10 of 49 2014 NRC SRO Question 9 8 (23) Reference 5.1 Immediate Reportability (continued) 16. Follow up Notifications. In addition to making the required initial notifications, during the course of the event IMMEDIATELY report: a. Any further degradation in the level of safety of the plant or other worsening plant conditions, including those that require the declaration of any of the Emergency Classes, if such a declaration has not been previously made. b. The results of ensuing evaluations or assessments of plant conditions. c. The effectiveness of response or protective measures taken. d. Information related to plant behavior that is not understood. 17. Notify Site Communications, or if there is no response, Corporate Communications Media Line of this Reactor Plant Event Notification Worksheet. If after hours leave a message for the on call person. (See EPL-001 for contact numbers). 18. Event Notification Worksheets which have been designated "Safeguards Information" in accordance with the provision of References 2.1 and 2.7 shall be returned to Security after the notification has been made with no further dissemination. 19. The Event Notification Worksheet should be sent to Licensing/Regulatory Programs; this does not apply to "Security" Notifications. 20. Licensing/Regulatory Programs will also evaluate if follow up notification is required for clarification, retraction or other. The below criteria should be considered: a. Clarity for public docket (not extremely technical) b. Minimize inflammatory jargon - be precise and factual c. Provides perspective and mitigating conditions 21. Licensing/Regulatory Programs will initiate ARs to track generation of follow up reports. 22. Licensing/Regulatory Programs will forward a copy of the Event Notification Worksheet to the ICES Coordinator within five working days for entry into the ICES database.
AP-617 Rev. 35 Page 11 of 49 2014 NRC SRO Question 9 8 (23) Reference 5.2 Other Reports Licensing/Regulatory Programs shall perform the following: 1. Reportability determinations for Steps 2 through 6 below shall be completed expeditiously. Reports should be confirmed as tracked by an AR. 2. Evaluate the condition for reportability as a Special Report under Technical Specification Section 6.9.2 per Attachment 2. 3. Evaluate the condition for reportability as an LER using Reference 2.9. Development of the LER is per Reference 2.6. As indicated in §50.73(a)(1), invalid actuations, other than Reactor Protection System actuations when the reactor is critical, may be reported by telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of a written LER. CAUTION Evaluation for §21 Reportability may not be substituted for reporting pursuant to §50.73. Actual reporting per §21 may be performed using an LER per §50.73 and Ref. 2.6. 4. Evaluate the condition for potential reportability under §21 per Reference 2.4. 5. Evaluate the condition for reportability via a Routine Report per Attachment 3. 6. Evaluate the condition for reportability via an Event Report (other than LER) per Attachment 4. 6.0 DIAGRAMS/ATTACHMENTS Attachment 1 - Immediate Notification Requirements Attachment 2 - Technical Specification and ODCM Special Reports Attachment 3 - Routine Reports Attachment 4 - Event Reports (Other than LERs) Attachment 5 - One Hour Notifications - Sample Wording Attachment 6 - SAMPLE Reactor Plant Event Notification Worksheet Attachment 7 - Reactor Plant Event Notification Worksheet Attachment 8 - Reportability Evaluation (REW) Worksheet AP-617 Rev. 35 Page 12 of 49 2014 NRC SRO Question 9 8 (23) Reference IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 1 of 10 The following tables are divided into sections based upon the functional areas for reporting the respective events as follows: I. Operational Events (50.72 and 50.73 reports) Event or Condition ENS notification Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ENS notification within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ENS notification Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 60-day LER Declaration of any Emergency Classes specified in the Emergency Plan 50.72(a)(1)(
i) Deviation from Tech Specs Authorized under §50.54(x) Deviation from TS authorized by 50.54(x) [50.72(b)(1)] 50.73(a)(2)(i)(C) Plant shutdown (S/D) required by Tech Specs Initiation of S/D required by Tech Specs [50.72(b)(2)(i)] Completion of a S/D required by Tech Specs [50.73(a)(2)(i)(A)] Operation or Condition Prohibited by Tech Specs (Note 10) 50.73(a)(2)(i)(B) Degraded or Unanalyzed Condition 50.72(b)(3)(ii) 50.73(a)(2)(ii) External Threat or Hampering 50.73(a)(2)(iii) System Actuations Valid ECCS discharges into Reactor Coolant system [50.72(b)(2)(iv)(A)] RPS Actuations when Reactor is critical [50.72(b)(2)(iv)(B)] Valid actuation of NRC listed systems (50.72(b)(3)(
iv)(A) - RPS including reactor scram and trip - Containment Isolation signals affecting CIVs in more than one system or multiple MSIVs - ECCS - AFW - Containment heat and depressurization systems - Emergency AC electrical systems 50.73(a)(2)(iv)(A) Event or Condition that could have prevented fulfillment of a safety function 50.72(b)(3)(v) 50.72(b)(3)(vi) 50.73(a)(2)(v) 50.73(a)(2)(vi) Common Cause Inoperability of independent trains or channels 50.73(a)(2)(vii) Radioactive Releases (Notes 3 & 8) Airborne radioactive release [50.73(a)(2)(viii)(A)] Liquid Effluent release [50.73(a)(2)(viii)(B)] (continued on next page)
AP-617 Rev. 35 Page 13 of 49 2014 NRC SRO Question 9 8 (23) Reference IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 2 of 10 Event or Condition ENS notification Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS notification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ENS notification within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ENS notification Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 60-day LER Loss of Emergency Preparedness Capabilities (Note 7) 50.72(b)(3)(xiii) Single Cause that could have prevented fulfillment of the Safety Functions of trains or channels in different systems 50.73(a)(2)(ix)(A) 50.73(a)(2)(ix)(B) News Release or Notifications of other Government Agency (Notes 9, 12, &13) 50.72(b)(2)(xi) Transport of a Contaminated Person Offsite 50.72(b)(3)(xii) Internal Threat or Hampering 50.73(a)(2)(x) Safety Limit Violation TS 6.7.1 Violation of Operating License Condition (Note 10) OL Section 2.G 10 CFR 50.73 Fatality or Hospitalization (Note 13) 50.72(b)(2)(xi)
AP-617 Rev. 35 Page 14 of 49 2014 NRC SRO Question 9 8 (23) Reference IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 3 of 10 II. RADIOLOGICAL EVENTS Event or Condition Notification Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Notification Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Notification Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Follow-up Report Radioactive Shipments (Note 1) Note 1a §20.1906(d)(1)
§71.87(i) Note 1b §20.1906(d)(2)
§71.47 Note 1c §73.71(b)(2) §73 Appendix G §73.71(a)(5) Loss or Theft of Licensed Material/Radiological Sabotage (Note 2) Note 2a §20.2201(a)(1)(
i) §20.2201(d) Note 2b §74.11 §150.16(b) §73.71(a) Note 2c §73.71(a) Note 2d §30.55(c) Note 2e §40.64(c) §150.17(c) Note 2a 30 Day Note 2b 60 Day or 15 Day Note 2c None Note 2d 15 Day Note 2e 15 Day Exposure to Individuals or Releases (Note 3) Note 3a §20.2202(a)(1)
Note 3b §20.2202(a)(2)
§50.72(b)(2)(
iv) Note 3a LER Note 3b LER Accidental Criticality (Note 4) Note 4 §70.52(a) Radiological Exposure/Release (Note 8) Note 8 §20.2202(b) Note 8 30 Day Unusual or Important Environmental Events (Note 9) OL App. B, 4.1 PLP-500 50.72 (see Note 12) Note 9d PLP-500 Note 9f PLP-500 Otherwise ESS determines Note 9d 30 Day III. SECURITY EVENTS/FITNESS FOR DUTY Event or Condition Notification Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Notification Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Follow-up Report Security Events per SEC- NGGC-2147. (Notes 5 and 11) Note 5 §75.7 §75.6 §75.7 Note 11a §26.719 Note 11b §26.719 Note 11c App. A to Part 26 B.2.8(e)(5) Note 5 None Note 11a None Note 11b None Note 11c Non-docketed correspondence FFD - NRC Employee (Note 6) Note 6 §26.27(d) International Atomic Energy Agency (IAEA) Representative (Note 5) Note 5 §75.7 §75.6 §75.7 FFD Program Events (Note 11) Note 11a §26.719 Note 11b §26.719 Note 11c App. A to Part 26 B.2.8(e)(5) Note 11a None Note 11b None Note 11c Non-docketed correspondence AP-617 Rev. 35 Page 15 of 49 2014 NRC SRO Question 9 8 (23) Reference NOTES IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 4 of 10 NOTIFICATION REFERENCE WRITTEN FOLLOW-UP 1. RADIOACTIVE SHIPMENTS a) Removable contamination from a received package containing radioactive material in excess of the limits specified in §71.87(i). The involved RP Supervisor shall immediately notify the final delivery carrier. §20.1906(d)(1) §71.87(i) b) Radiation levels from a received package of radioactive material in excess of the limits specified in §71.47. The involved RP Supervisor shall immediately notify the final delivery carrier. §20.1906(d)(2) §71.47 c) Security related events with respect to the transport of special nuclear material are handled via SEC-NGGC-2147. Security threats or theft of licensed material shall be reported to site Security personnel. §73.71(b)(2) §73 Appendix G §73.71(a)(5) 2. LOSS OR THEFT OF LICENSED MATERIAL/ RADIOLOGICAL SABOTAGE Note: Theft and Sabotage are Security Events handled by SEC-NGGC-2147. Any loss or theft or attempted theft of: a) Licensed material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in Appendix C to §20.1000-§20.2401 under such circumstances that it appears that an exposure could result to persons in unrestricted areas, §20.2201(a)(1)(i) §20.2201(d) 30-Day Written Report required per §20.2201(b) b) Any Special Nuclear Material or spent fuel, (theft - See SEC- NGGC-2147) §74.11 §150.16(b) §73.71(a) 60-Day Written Report required per §73.71(a) or (b) - See SEC-NGGC- 2147 15-Day Written Report may be required per §150 c) Recovery of or accounting for loss of any shipment of Special Nuclear Material or spent fuel §73.71(a) d) Greater than 10 curies of tritium at any one time or 100 curies in one calendar year, or §30.55(c) 15-Day Written Report required e) More than 15 pounds of uranium or thorium at any one time or more than 150 pounds in one calendar year. §40.64(c) §150.17(c) 15-Day Written Report required AP-617 Rev. 35 Page 16 of 49 2014 NRC SRO Question 9 8 (23) Reference NOTES IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 5 of 10 NOTIFICATION REFERENCE WRITTEN FOLLOW-UP 3. EXPOSURE TO INDIVIDUALS OR RELEASES Any event involving by-product, source or Special Nuclear Material that may have caused or threatens to cause: a) An individual to receive: 1) A total effective dose equivalent of 25 Rem 2) An eye dose equivalent of 75 Rem 3) A shallow-dose equivalent to the skin or extremities of 250 Rad 4) An intake of 5 ALI in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> §20.2202(a)(1) LER required by §50.73(a)(2)(viii), (a)(2)(ix) and §20.2203 b) Release of radioactive material in excess of Technical Specification Instantaneous Limits shall be declared an emergency in accordance with PEP-310. The reporting requirements of PEP-310 shall take precedence over the less restrictive times for reporting requirements of §20.2202 and §50.72(b)(2) for releases. §20.2202(a)(2) §50.72(b)(2)(iv) LER required by §50.73(a)(2)(viii), (a)(2)(ix) and §20.2203 4. ACCIDENTAL CRITICALITY Accidental criticality of special nuclear material. §70.52(a) None 5. SECURITY EVENTS Note: Reporting of Security Events (Including Safeguards and Fitness-For-Duty Events) is per SEC- NGGC-2147. Notify site Security personnel. INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA) REPRESENTATIVE Individual claiming to be an IAEA representative who is not accompanied by an NRC employee and has no prior confirmation of credentials in writing. Notification is by telephone to Director, Office of Nuclear Reactor Regulation §75.7
§75.6 and §75.7 None 6. FITNESS FOR DUTY - NRC EMPLOYEE Notification of NRC employee's unfitness for duty. Per §26.27(d), the appropriate Regional Administrator must be notified immediately by telephone. During other than normal working hours, the NRC Operations Center must be notified. §26.27(d) None AP-617 Rev. 35 Page 17 of 49 2014 NRC SRO Question 9 8 (23) Reference IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 6 of 10 NOTE : PLP-717, Equipment Important To Emergency Preparedness and ERO Response, Attachment 2, Essential ERO Equipment and Compensatory Measures, contains guidance on determining immediate reportability. Other Technical Specification and ODCM reporting requirements may apply and are located in Attachment 2 of this (AP-617) procedure. [CR 580945 CAPR] NOTES NOTIFICATION REFERENCE WRITTEN FOLLOW-UP 7. LOSS OF EMERGENCY RESPONSE CAPABILITY §50.72(b)(3)(xiii) None Any event that results in a major loss of assessment capability, offsite response capability, or communications capability (e.g., significant portion of Control Room indication, Emergency Telecommunication System, or offsite notification system). This may include loss of any of the following: a) Emergency Response Facilities b) Radiation Monitors and Plant Equipment used in identification of Emergency Action Levels c) Computers and Telecommunications including: 1. Selective Signaling 2. NRC Emergency Telecommunication System 3. Emergency Response Data System [In the event of a failure of the NRC supplied onsite ERDS modem, the NRC should be notified via phone number 301-816-5100 with: 1) the name of the contact at location of failure, 2) phone number of contact, 3) location of contact, and 4) any other information that would expedite repair] 4. PABX telephone system 5. Plant PA System 6. Corporate Telephone Communication System (Voicenet) and the Commercial Telephone System 7. Satellite Phones 8. Sound Powered Phone System 9. HNP Emergency Notification (Everbridge) System 10. Emergency Response Facility Information System (ERFIS)
- 11. Safety Parameter Display System (SPDS) 12. Dose Assessment Software (RASCAL) d) Sirens and Tone Alert Radios Use PLP-717, Attachment 2 in determination of immediate reportability.
AP-617 Rev. 35 Page 18 of 49 2014 NRC SRO Question 9 8 (23) Reference NOTES IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 7 of 10 NOTIFICATION REFERENCE WRITTEN FOLLOW-UP 8. RADIOLOGICAL EXPOSURE/RELEASE §20.2202(b) 30-Day Written Report Required per §20.2203 Any event involving licensed material possessed by the licensee that may have caused or threatens to cause an individual to receive, in a period of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: a) A total effective dose equivalent > 5 Rem; or b) An eye dose equivalent > 15 Rem; or c) A shallow-dose equivalent to the skin or extremities> 50 Rem; or d) An intake of > 1 ALI. 9. UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS Any event that indicates or could result in significant environmental impact causally related to plant operation. Examples are: a) Excessive bird impaction b) Onsite plant or animal disease outbreak c) Mortality or unusual occurrence of Endangered Species d) Fish Kills e) Increase in nuisance organisms or conditions f) Unanticipated or emergency discharge of waste water or chemical substances g) Damage to vegetation resulting from cooling tower drift deposition h) Station outage or failure of any cooling water intake or service water system components due to bio-fouling by Corbicula (Asiatic Clam) Env. Prot. Plan, (Operating License Appendix B) Section 4.1, and PLP-500 ESS determines threshold ESS determines threshold ESS determines threshold Local and State Notifications defined in PLP-500 ESS determines threshold Local and State Notifications defined in PLP-500 ESS determines threshold ESS determines threshold Local, State & Federal Agency Notifications defined in PLP-500 require NRC notification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 50.72 (See Note 12) If event is significant and not reportable to a Local, State, or Federal agency, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> NRC notification may still be required per Env. Prot. Plan. 30-Day Follow-up written report required per Env. Prot. Plan Subsection 5.4.2 AP-617 Rev. 35 Page 19 of 49 2014 NRC SRO Question 9 8 (23) Reference NOTES IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 8 of 10 NOTIFICATION 10. VIOLATION OF OPERATING LICENSE CONDITIONS REFERENCE WRITTEN FOLLOW-UP a) Any event resulting in the plant operating in a manner which violates the SHNPP Facility Operating License, Section 2.C: OL Section 2.G 60-day LER required per 10 CFR 50.73 and 10 CFR 50.4(e) (1) Intentionally raising power above 2948 MWt (100%) for any period of time. (2) Failure to reduce thermal power to less than or equal to 2948 MWt when the 2-hour average exceeds 2948 MWt. (3) Permitting the core thermal power 8-hour average to exceed 2948 MWt. (4) Failure to take prudent action prior to a pre- planned evolution that could cause a power increase to exceed 2948 MWt (example: Scheduled securing of a Heater Drain Pump without first reducing power to accommodate the expected power increase. A short term increase in transient power above 2948 MWt following a boron dilution is not included if actions to reduce power are taken in a reasonable time following the dilution reactivity transient). Note: No actions are allowed that would intentionally raise core thermal power above 2948 MWt for any period of time. Small, short-term fluctuations in power that are not under the direct control of a license reactor operator or result from actions taken for a different purpose (example: temperature control) are not considered intentional. NEI Position Statement: Guidance to Licensees on Complying with the Licensed Power Limit (NRC ADAMS Accession No. ML081750537) b) A failure to comply with the following administrative requirements (See Note 1): OL Section 2.G 60-day LER required per 10 CFR 50.73 and 10 CFR 50.4(e) 1) Deviation from the requirements of the Environmental Protection Plan; OL Section 2.C.2 2) Failure to comply with anti-trust conditions of Appendix C to OL; OL Section 2.C.3 3) Failure to comply with new fuel storage requirements. OL Section 2.C.10 AP-617 Rev. 35 Page 20 of 49 2014 NRC SRO Question 9 8 (23) Reference NOTES IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 9 of 10 NOTIFICATION REFERENCE WRITTEN FOLLOW-UP 11. FITNESS FOR DUTY PROGRAM EVENTS Note: Reporting of Security Events (Including Safeguards and Fitness-For-Duty Events) is per SEC-NGGC- 2147. Notify site Security personnel. a) Sale, use, or possession of illegal drugs within the protected area. §26.719 None b) Any acts by any person licensed under §55, or by any supervisory personnel assigned to perform duties within the scope of §26 1) Involving the sale, use, or possession of a controlled substance, 2) Resulting in a confirmed positive test on such persons, 3) Involving use of alcohol within the protected area, or 4) Resulting in a determination of unfitness for scheduled work due to the consumption of alcohol. §26.719 None c) False positive error on a blind performance test specimen when error is determined to be administrative. App. A to Part 26 B.2.8(e)(5) Reference 2.35 Non-docketed correspondence to NRC FFD coordinator AP-617 Rev. 35 Page 21 of 49 2014 NRC SRO Question 9 8 (23) Reference NOTES IMMEDIATE NOTIFICATION REQUIREMENTS Attachment 1 Sheet 10 of 10 12. OFF SITE NOTIFICATION HAS BEEN OR W ILL BE MADE Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an onsite fatality or inadvertent release of radioactively contaminated materials. For Tritium Spills If a liquid spill or leak to the environment exceeding the following criterion has entered or has the potential to enter groundwater: Spill or leak that exceeds or may have exceeded 100 gallons from a source containing licensed material, OR Any spill or leak, regardless of volume or activity, deemed by the licensee to warrant voluntary communication, Then, make informal notification to state/local offices before the end of the next business day. Provide a copy of the information to NEI via email at GW_Notice@nei.org. Notification to the NRC should begin prior to notifying the first state/local official or the press, if possible, but no later than four hours after commencing communications with state/local officials or the press. The approval by the Site Vice president (or designee) of a written communication plan and a completed communication message for state/local official as part of the NEI 07-07 Ground Water Protection Initiative, or a formal press release is the initiating event for an NRC Event Notification under 10 CFR 50.72 (b)(2)(xi). For Oil Spills Oil spills greater than 25 gallons on land, oil spills on navigable waters or shorelines within 100 feet of the water, or oil spills that require notification to the National Response Center as determined by PLP-500.) §50.72(b)(2)(xi) Reference 2.42 13. FATALITY OR HOSPITALIZATION a) See SAF-SUBS-00033 and contact the Site Safety Representative b) OSHA must be notified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of: 1) Workplace Fatality 2) Workplace incident with 3 or more personnel hospitalized c) North Carolina requires a call to the Dept. of Labor, Elevator Division, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of an injury or fatality related to elevators. SAF-SUBS-00033 See Note 12 for NRC required 4-hour notification AP-617 Rev. 35 Page 22 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 2 Sheet 1 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS A Special Report may be identified from CRs, EIRs, declared emergencies or as the result of equipment inspections. The following steps shall be performed when it appears that a Special Report is required. 1. The Supervisor - Licensing/Regulatory Programs shall be notified of the event if this has not already occurred via a CR or EIR. 2. The Supervisor - Licensing/Regulatory Programs shall inform the General Manager - Harris Plant and applicable unit manager(s) of the need for a special report. 3. The Supervisor - Licensing/Regulatory Programs shall assign action items to the responsible units per Reference 2.12 to provide input for the required reports. 4. Completed reports shall be routed for approval per Reference 2.2. 5. A copy of the completed special report shall be provided to the Secretary - PNSC for review at a subsequent PNSC meeting. 6. The special report shall be transmitted as a QA Record. REPORTING REQUIREMENTS SUBJECT TS [ODCM] REFERENCE RESP UNIT TIMING OF RESPONSE Leak or boron deposit found during inspection O.L. NRC Order dated 2/11/03 HESS 60 days after returning the plant to operation Moderator Temperature Coefficient more positive than specified limits 3.1.1.3 HESS 10 Days Remote Shutdown Monitoring Instrument inoperable for greater than 60 days 3.3.3.5.a Maint 14 Days Radiation Monitors, Pressurizer Safety Valve Position Indicators or Subcooling Margin Monitors inoperable for greater than 7 days. (Also see OWP-ERFIS) 3.3.3.6 Maint or IT (and Engineering for Rad. Monitors) 14 Days PORV/RCS Vents used to mitigate RCS pressure transient at low temperature 3.4.9.4 Operations 30 Days An ECCS actuation and injection of water into the Reactor Coolant System (See Note 2) 3.5.2, 3.5.3 Operations 90 Days (See Note 3) Change to Sample Plan Used for Snubber Functional Testing 3.7.8 PLP-106 Att. 4 HESS Before Implementation AP-617 Rev. 35 Page 23 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 2 Sheet 2 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS SUBJECT TS [ODCM] REFERENCE RESP UNIT TIMING OF RESPONSE Radioactive Material in Liquid Holdup Tanks exceeding limits 3.11.1.4 Environmental and Chemistry Include in Annual Radioactive Effluent Release Report Use of non-preferred Incore Detectors when evaluating QPTR 4.2.4.2 (Bases) HESS 30 Days Abnormal degradation of Containment Vessel structure detected during required inspections 4.6.1.6.2 HESS 15 Days Sealed Source leakage test results 4.7.9.3 Radiation Protection Annually if removable contamination greater than 0.005 µCi detected Greater than 30 total rods or 10 rods per fuel assembly replaced with filler rods or vacancies during any single refueling. 5.3.1 HESS 30 Days Following Start-up Safety Limit Violation. 6.7.1 Operations 14 Days Startup Report following: 1) License amendment to increase power level. 2) Installation of fuel of different design or manufacturer. 3) Modifications that significantly alter the nuclear, thermal or hydraulic characteristics of the unit. 6.9.1.1 HESS 90 Days Following Resumption of Commercial Operations or Completion of Startup Test Program, or 9 months after Initial Criticality, whichever is earliest. Supplementary reports required each 3 months. Change to Core Operating Limits Report 6.9.1.6.4 HESS Upon issuance; must be submitted no later than the date of implementation. Steam Generator Tube Inspection Report 6.9.1.7 HESS Within 180 days after initial entry into Hot Shutdown following completion of an inspection performed in accordance with TS 6.8.4.l. Special Reports 6.9.2 As Assigned As Requested Unreviewed Environmental Question T.S. Appendix B EPP Section 3.1 Environmental and Chemistry Before implementation of change AP-617 Rev. 35 Page 24 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 2 Sheet 3 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS SUBJECT TS [ODCM] REFERENCE RESP UNIT TIMING OF RESPONSE Proposed changes/renewal application for NPDES Permit T.S. Appendix B EPP Section 3.2 Environmental and Chemistry At time of submittal to the permitting agency Changes to/renewal of NPDES Permit or State Certification T.S. Appendix B EPP Section 3.2 Environmental and Chemistry 30 Days after change/renewal Stay of NPDES Permit or State Certification T.S. Appendix B EPP Section 3.2 Environmental and Chemistry 30 Days following stay Unusual or Important Environmental Events T.S. Appendix B EPP Sections 4.1 and 5.4.2 Environmental and Chemistry 30 Days after event. (Note 4) See also 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notifications Seismic Monitoring Instrument inoperable for greater than 30 days PLP-114 Maint 10 Days Actuation of Seismic Monitoring Instruments during seismic event greater than or equal to 0.01g (See Note 1) PLP-114 HESS 14 Days Meteorological Monitoring Instrument inoperable for greater than 7 days PLP-114 Maint 10 Days Metal Impact Monitoring System Channel(s) inoperable for greater than 30 days. PLP-114 Maint 10 Days Explosive gas monitoring instrument inoperable for greater than 30 days. PLP-114 Maint 30 Days (Note: No time specified in PLP-114) Area Temperatures exceeding PLP-114, Attachment 4 limits by more than 30ºF, or for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> PLP-114 HESS & Operations 30 Days A calculated dose to a member of the public from the release of radioactive materials in liquid effluents to an unrestricted area exceeding limits [3.11.1.2] Environmental and Chemistry 30 Days Radioactive liquid waste being discharged without treatment and in excess of limits and any portion of the liquid radwaste treatment system not in operation [3.11.1.3] Environmental and Chemistry & Operations 30 Days Calculated air dose in gaseous effluent exceeding limits in areas at or beyond site boundary [3.11.2.2] Environmental and Chemistry 30 Days AP-617 Rev. 35 Page 25 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 2 Sheet 4 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS SUBJECT TS [ODCM] REFERENCE RESP UNIT TIMING OF RESPONSE Calculated dose to a member of the public from a release of gaseous effluents containing Iodine 131, Iodine 133, tritium and radionuclides in particulate form with half-lifes greater than eight days exceeding the limits. [3.11.2.3] Environmental and Chemistry 30 Days Untreated radioactive gaseous waste discharged in excess of limits and any portion of the gaseous radwaste treatment system not in operation. [3.11.2.4] Environmental and Chemistry & Operations 30 Days Calculated dose from release of radioactive material in liquid or gaseous effluents, to a member of the public in excess of limits. [3.11.4] Environmental and Chemistry 30 Days Level of radioactivity, as a result of plant effluent in a specified location, exceeding the reporting levels of ODCM O.R. Table 3.12-2 when averaged over any calendar quarter. [3.12.1] Environmental and Chemistry 30 Days NOTES: 1. Refer to the following TS Surveillance Requirements following any seismic event: 4.3.3.3.2 and 4.4.5.3.c.2 2. Refer to the following TS Surveillance Requirements following any safety injection actuation: 4.4.5.3.c.1, 4.4.5.3.c.3, 4.4.5.3.c.4, 4.4.6.2.2.d, and 4.5.2.g.1 3. LER also required (see Reference 2.6). The information required by the Special Report exceeds the requirements of the LER. 4. Events requiring reports to other government agencies shall be reported per those requirements in lieu of the Environmental Protection Plan. A copy of the report shall be sent to the NRC.
AP-617 Rev. 35 Page 26 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 3 Sheet 1 of 3 ROUTINE REPORTS The SHNPP Technical Specifications, ODCM, §20 and §50 require that reports be provided to the NRC at routine intervals. The following steps apply to routine reports: 1. The Supervisor - Licensing/Regulatory Programs shall establish action items per Reference 2.12 for these reports. 2. As applicable, the responsible unit and Licensing/Regulatory Programs shall establish standard formats for a routine report. 3. Routine reports shall be routed for approval per Reference 2.2. 4. Routine reports shall be transmitted as a QA record. NOTE: TS = Technical Specification OR = ODCM Operational Requirement SUBJECT REGULATORY REFERENCE RESP UNIT TIMING OF RESPONSE Annual Operating Report T.S. 6.9.1.2 Lic / Reg Prog Before 3/1 Annual Radiological Environmental Operating Report T.S. 6.9.1.3 O.R. 3.12.1 O.R. Table 3.12-1 O.R. Table 4.12-1 O.R. 4.12.2 O.R. 3.12.3 O.R. 4.12.3 Environmental and Chemistry Before 5/1 Annual Environmental Operating Report Env. Prot. Plan 5.4.1 Environmental and Chemistry Before 5/1 Annual Radioactive Effluent Release Report T.S. 3.11.1.4 T.S. 6.9.1.4 T.S. 6.14.c ODCM App. F.3 O.R. Table 4.11-1 O.R. 3.12.1 O.R. Table 3.12-1 O.R. 3.12.2 O.R. 3.3.3.10 O.R. 3.3.3.11 §50.36a(a)(2) Environmental and Chemistry Before 5/1 AP-617 Rev. 35 Page 27 of 49 2014 NRC SRO Question 9 8 (23) Reference st ROUTINE REPORTS Attachment 3 Sheet 2 of 3 NOTE 1: This report does not need to be routed for approval per Reference 2.2 since it is not correspondence to a regulatory agency. SUBJECT REGULATORY REFERENCE RESP UNIT TIMING OF RESPONSE Consolidated Data Entry (CDE) FSAR Section 1.8 Lic / Reg Prog By the 21 day of Report (Reg. Guide 1.16) each quarter Individual Worker Radiation Dose Report (To employee) (See Note 1 above) §19.13(b) ESS Rad Services (Dosimetry) Annually Annual Exposure Report for Individual Monitoring §20.2206(b) Lic / Reg Prog Annually, by April 30th Semiannual Fitness for Duty Program Performance Data Analysis Report §26.71(d) Nuclear Operations Within 60 days of the end of each 6- month reporting period (Jan-June and July-Dec) ECCS evaluation model chan ges or errors where sum of absolute magnitudes of changes results in PCT change 50ºF §50.46(a)(3) NFM&SA Annually Changes to QA Program which do not reduce commitments §50.54(a)(3) NOS In accordance with §50.71(e) Insurance and Financial Security Annual Report §50.54(w)(3) Nuclear Operations Annually, on April 1 In-service Inspection Summary §50.55a (ASME Section XI IWA- 6230) HESS 90 days after completion of inspections FSAR Update, facility changes, tests, and experiments conducted without prior approval §50.59(b) §50.71(e) Lic / Reg Prog Six months following each refueling outage. Interval not to exceed 24 months between updates AP-617 Rev. 35 Page 28 of 49 2014 NRC SRO Question 9 8 (23) Reference ROUTINE REPORTS Attachment 3 Sheet 3 of 3 SUBJECT REGULATORY REFERENCE RESP UNIT TIMING OF RESPONSE Annual Financial Report, including certified financial statements §50.71(b) Nuclear Operations Upon issuance of the report (Normally April 30) Status of Decommissioning Funding §50.75(f) Nuclear Operations March 31, 1999 and at least once every two years thereafter (frequency becomes annual when the plant is within 5 years of projected end of operation or when the plant is involved in mergers or acquisitions). Simulator - Report of uncorrected performance test failures and schedule for correction §55.45(b)(5)(ii) Training Every 4 years on anniversary of certification Material Status Reports (old Forms DOE/NRC-742 and 742(c)) §74.13(a)(1) §70.53(a)(1) §40.64(b) §150.17(b) HESS 30 days after March 31 and September 30 NOTE: 40.64 and 150.17 require statement of foreign origin source material. QA Program for Transportation of Radioactive Material Packages §71.101 Nuclear Operations Every 5 Years. Docket 71-0345 Financial Protection - Guarantee of payment of deferred premiums §140.21 Nuclear Operations Annually, on anniversary date on which indemnity agreement is effective (Normally April 30)
AP-617 Rev. 35 Page 29 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 1 of 9 EVENT REPORTS (Other than LERs) Title 10 of the Code of Federal Regulations and other requirements require that reports be provided to the NRC and other regulatory agencies based on the occurrence of specific events. The following instructions apply to these events (unless otherwise noted): 1. The responsible unit shall determine if written procedures should be prepared to implement the reporting requirement. 2. When written reports are required to be submitted to the NRC, the General Manager - Harris Plant and the Supervisor - Licensing/Regulatory Programs shall be informed. 3. Completed reports shall be routed for approval per Reference 2.2. 4. The event report shall be transmitted as a QA Record. SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Report to former radiation worker of worker's exposure to radiation (Note 7) 19.13(c) Radiation Protection Upon request; within 30 days from request or 30 days after exposure has been determined Radiation Exposure Data to Individual-Overexposure (Note 7) 19.13(d) Radiation Protection Upon overexposure (Note 5) Radiation Exposure Data to Terminating Employees (Note 7) 19.13(e) ESS Rad Services (Dosimetry) Upon request at termination Bioassay Services to Determine Exposure 20.1204(c) Radiation Protection As requested by NRC Report of planned special exposure 20.1206(f) 20.2204 Radiation Protection Within 30 days following planned special exposure Report to individual of planned special exposure (Note 7) 20.1206(g) Radiation Protection Within 30 days from planned special exposure Respiratory Protection Program Equipment not certified by NIOSH/MSA 20.1703(d) Radiation Protection 30 Days prior to equipment usage Theft or loss of licensed material greater than 10 times Appendix C quantities 20.2201(a)(1)(ii) 20.2201(b) Radiation Protection Radiation Protection 30 Days (by ETS) 30 Days (written follow-up) Additional information on theft or loss 20.2201(d) Radiation Protection 30 Days AP-617 Rev. 35 Page 30 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 2 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Reports of Overexposures/ Excessive Levels and Concentrations 20.2203 40CFR190 ODCM O.R. 3.11.4 Radiation Protection 30 Days (Note 5) Missing Waste Shipment Trace Investigation 20 App. G, Sec. III.E Radiation Protection 2 weeks after completion of Investigation Interim evaluation report of identified deviation or failure to comply (when evaluation cannot be completed within 60 days of discovery) 21.21(a)(2) Lic / Reg Prog Within 60 days of discovery Failure to Comply or Existence of a Defect (Refer to AP-616) 21.21(c)(1) & (d)(3) Lic / Reg Prog 2 days, written follow-up within 30 days FFD testing more conservative than §26 requirements 26 App. A, Sec. A.1.1(2) Human Res Within 60 days of implementing change FFD - Unsatisfactory performance testing of a certified laboratory 26 App. A, Sec. B.2.8 (e)(4) Human Res 30 days Reports required as condition of Parts 30-35 licenses (By-product Material) 30.34(e)(4) Radiation Protection As specified in license Renewal or non-renewal of Parts 30-35 licenses 30.36 Radiation Protection 30 Days prior to expiration Notification of byproduct (Part 30) or SNM (Part 70) license expiration or cessation of principal activities 30.36(d) 70.38(d) Radiation Protection Within 60 days Amendment to Part 30-35 License 30.38 Radiation Protection As Required Failure of or damage to shielding, on-off mechanism or indicator; detection of removable radioactive material 31.5(c)(5) Radiation Protection 5 Days (5 Day report required per Byproduct Materials License in lieu of 30 day requirement) Transfer of device to specific or general licensee 31.5(c)(8) 31.5(c)(9)(i) Radiation Protection 30 Days Leaking of sealed radiographic source 34.27(d) Licensed Radiographer 5 Days AP-617 Rev. 35 Page 31 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 3 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Incidents involving radiographic equipment: unintentional disconnection of the source assembly from the control cable. inability to retract the source assembly to its fully shielded position and secure it in this position. failure of any component (critical to safe operation of the device) to properly perform its intended function. 34.101(a) Licensed Radiographer Within 30 days of occurrence Licensee identified information which has significant implications for public health and safety or the common defense and security 50.9(b) 30.9(b) 40.9(b) 70.9(b) 71.7(b) Lic / Reg Prog As necessary (Note 4); §70.9(b) specifies within two working days of identifying the information Change to the LOCA analysis which results in a change to the Peak Clad Temperature 50.46(a)(3) NFM&SA If 50ºF, then include in the annual report. If >50ºF, then 30 days. Changes in QA Program which reduce commitments 50.54(a) NOS Before implementation Request for Written Information 50.54(f) As Specified As Requested Changes to Operator Requalification Program which decreases scope, time allotted or frequency of conducting portions of the program 50.54(i-1) Training Before Implementation Changes in Security Plan, Guard Training and Qualification Plan, or Safeguards Contingency Plan made without prior approval 50.54(p) 70.32(g) Security Before implementation if changes reduce effectiveness of plan; otherwise, within two months after change. NOTE: §70.32(g) specifies within 60 days for safeguards contingency plan.
AP-617 Rev. 35 Page 32 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 4 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Changes in emergency plan or implementing procedures made without prior approval 50.54(q) 50 App E(V) Emerg Prep Before implementation if changes reduce effectiveness of plan, otherwise within 30 days after change Notification of safe and stable condition of reactor and no significant risk to public health and safety 50.54(w)(4)(ii) Emerg Prep After attaining safe and stable condition (following an accident with costs >$100 million) Cleanup plan for decontaminating reactor to permit resumption of operation or commencement of decommissioning 50.54(w)(4)(ii) Emerg Prep Within 30 days of notification that reactor is in safe and stable condition (following an accident with costs >$100 million) Plan for management of and notification of significant change in the proposed waste management program (of irradiated fuel at the reactor, after expiration of license and until transferred to DOE) 50.54(bb) Lic / Reg Prog Within 2 years after cessation of operation or 5 years before expiration of OL and after making change in program Filing of petition for bankruptcy (Title 11 of US Code) 50.54(cc)(1) 30.34(h) 40.41(f) 70.32(a)(9)(i) Lic / Reg Prog Immediately following filing Notification that conformance to a certain Code required by Section XI of the ASME B&PV Code and Addenda for inservice test is impractical 50.55a(f)(5) (iii) HESS After identifying problem Determination that a pump or valve test required by Section XI of the ASME B&PV Code and Addenda is impractical and not included in the revised inservice test program 50.55a(f)(5) (iv) HESS No later than 12 months after expiration of initial 120-month period of operation, and each subsequent 120-mo. period of operation during which the test is determined to be impractical AP-617 Rev. 35 Page 33 of 49 2014 NRC SRO Question 9 8 (23) Reference EVENT REPORTS (Other than LERs) Attachment 4 Sheet 5 of 9 SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Notification that conformance to a certain Code required by Section XI of the ASME B&PV Code and Addenda for inservice inspection is impractical 50.55a(g)(5) (iii) HESS After identifying problem Determination that a pump or valve test required by Section XI of the ASME B&PV Code and Addenda is impractical and not included in the revised inservice inspection program 50.55a(g)(5) (iv) HESS No later than 12 months after expiration of initial 120-month period of operation, and each subsequent 120-mo. period of operation during which the test is determined to be impractical Updated assessment of projected value for RTPTS for reactor vessel beltline materials - after significant change in projected value of RTPTS or change in facility's operating expiration date 50.61(b)(1) HESS After change Plan for thermal annealing of reactor vessel Reports required as a condition of license 50.66
50.71(a) HESS As Specified 3 yrs prior to date when fracture toughness criteria would be exceeded As Specified in License Telephone report in lieu of LER for an invalid actuation of a system listed in 50.73(a)(2)(iv)(B), other than RPS actuation when critical Reassignment of Licensed Operator to position not requiring license 50.73(a)(1) 50.74(a) Operations Operations 60 Days 30 Days Termination of Licensed Operator 50.74(b) Operations 30 Days Hardware and software changes that affect transmitted data points identified in ERDS Data Point Library 50 App. E, Sec. VI.3.a Nuclear Info Systems Within 30 days after changes are completed Hardware and software changes (except data point modifications) that could affect transmission format and computer communication protocol to the ERDS 50 App. E, Sec. VI.3.b Nuclear Info Systems As soon as practicable and at least 30 days prior to making modification AP-617 Rev. 35 Page 34 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 6 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Test methods for supplemental fracture toughness tests 50 App. G Sec. III.B HESS Submitted and approved prior to testing Fracture Toughness 50 App G, Sec. IV.A.1 HESS 3 years before date when predicted fracture toughness will no longer satisfy App G Report of test results of specimens withdrawn from capsules (fracture toughness tests) 50 App H, Sec. IV HESS Within One Year of Withdrawal Report of effluents released in excess of one-half design objective exposure 50 App I, Sec. IV.A Environmental and Chemistry Within 30 Days from end of quarter (Special Report required by T.S. 3.11.4 satisfies this requirement) Reactor Building ILRT 50 App J, Option A, Sec. V.B TS 4.6.1.2 HESS 3 Months After Test (No time specified in regulation or TS) Certification of Medical Fitness 55.23 55.31 Training Upon Application Incapacitation Because of Disability or Illness 55.25 50.74(c) Operations 30 Days after learning of diagnosis Application for Operator License 55.31 Training As necessary Reapplication for Operator License 55.35 Training Two months after first denial, six months after second denial, two years after third and subsequent denials Conviction of a Felony for Licensed Operator 55.53(g) 73.71(b) Operations/ Security 30 Days Application for Operator License Renewal 55.57 Training As necessary Reports of Conditions of Part 70 License 70.32(b)(5) 75.36 Security As specified in license Changes in plan for Physical Protection of SNM in transit made without prior approval 70.32(d) Security 2 Months AP-617 Rev. 35 Page 35 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 7 of 9 EVENT REPORTS (Other than LERs) SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Accident notification report required by DOT on transportation of licensed material 71.5(a)(1)(iv) 49CFR171.15 & 16 Radiation Protection Carrier is to provide notice to DOT at the earliest practicable moment and written follow-up within 30 days Transportation Package Information 71.12(c)(3) 71.101(f) Radiation Protection Before first use (Note 1) Deviations related to Type B package for transport of radioactive material, specifically: significant reduction in effectiveness of Type B packaging during use defects with safety significance in Type B packaging after first use, or the means employed to repair the defects and prevent recurrence conditions of approval of certificate of compliance not observed in making a shipment 71.95 Radiation Protection Within 30 days (NOTE: requirement is for licensee to report) Advance notification of shipment of Irradiated Fuel, Nuclear Waste, or certain shipments of SNM 71.97(a) 73.37(b)(1) 73.72(a) 73.73(a) 73.74(a) Radiation Protection Before shipment (Note 2) Revision notice or cancellation notice for shipment of irradiated fuel, nuclear waste, or certain shipments of SNM 71.97(e) 71.97(f) 73.37(f) 73.72(a)(5) 73.73(b) 73.74(b) Radiation Protection Upon change/ cancellation (Note 2) Advance Notice and Approval of Routes for Shipment of Irradiated Fuel 73.37(b)(7) 73.37(f) Radiation Protection & Nuclear Operations Before shipment (Note 2) Theft or unlawful diversion or attempted theft or unlawful diversion of SNM or spent fuel 73.71 74.11 150.16(b) Security As required (See also 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notifications and SEC-NGGC-2147)
AP-617 Rev. 35 Page 36 of 49 2014 NRC SRO Question 9 8 (23) Reference EVENT REPORTS (Other than LERs) Attachment 4 Sheet 8 of 9 SUBJECT 10 CFR Reference or (other) RESP UNIT TIMING OF RESPONSE Results of Trace Investigation of Lost or Unaccounted for Shipment of SNM Threat to or reduced effectiveness of physical security 73.71(a)74.11 Security 30 Days 73.71(d) Security 30 Days (See also 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notifications and SEC- NGGC-2147) Nuclear Material Transfer (old Form DOE/NRC-741)
Earthquake exceeding Operating Basis Earthquake values 74.15(a) 40.64(a) 70.54 150.16(a) 150.17(a) 100 App. A, Sec. V(A)(2) HESS Whenever transfer occurs (Note 6) HESS Prior to resuming operations Import or export of nuclear equipment or material Bodily injury or property damage from possession or use of radioactive material resulting in an indemnity claim 110 Radiation Protection 140.6(a) Radiation Protection Varies; see Part 110 As promptly as practical Change in proof of financial protection or other financial information filed with the NRC Termination of liability insurance policy used for financial protection (notification of renewal or other proof of financial protection) 140.15(e) Treasury Promptly 140.17(b) Treasury At least 30 days prior to termination Failure of High Integrity Container or Notification of Misuse of a High Integrity Container PLP-300 Radiation Protection Within 30 days of knowledge of the incident Cooling Tower Beacon Outage greater than 30 minutes or restoration from an outage greater than 30 minutes. (Note 8) [Note: The FAA is automatically informed of lighting outage on the communication and meteorological towers via a remote monitoring system] FAA Advisory Circular AC 70/7460-1K Operations Upon Discovery Level of radioactivity in onsite groundwater, exceeding the reporting levels of ODCM O.R. Table 3.12-2 for drinking water. CHE-NGGC-0057 Environmental and Chemistry Within 30 days of discovery AP-617 Rev. 35 Page 37 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 4 Sheet 9 of 9 EVENT REPORTS (Other than LERs) NOTES: 1. Development and use of a package will require special reporting requirements per §71.5, 71.95 and 71.101(f). 2. Notification to NRC received at least 10 days before transport of the shipment commences; see §73.72(a), 73.73(a), or 73.74(a) for additional details. State Governor(s) of states through which material is to be shipped shall also be notified by mail postmarked at least 7 days before shipment or by messenger 4 days prior to shipment. Notification of any subsequent schedule changes of greater than six (6) hours or cancellation of shipment shall also be made before the change (See §71.97(c) for additional notification to the Regional NRC Administrator). 3. Not used 4. Report not required if such reporting would duplicate information already submitted per other NRC reporting requirements. 5. When reporting exposure of an individual, the individual shall also be notified not later than the transmittal to the NRC. 6. §40.64(a) specifies next working day for transfers and 10 days for receipt of foreign origin source material. §150.16(a) and 150.17(a) specify within 10 days after material is received. 7. This report does not need to be routed for approval per Reference 2.2 since it is not correspondence to a regulatory agency. 8. Notify the DOT-FAA Flight Service Station at either 1-877-487-6867 or 1-800-992-7433. The following information will be required: a. Harris Nuclear Plant, caller name and telephone number b. Which Hyperbolic Cooling Tower Beacon Warning Lights (by compass orientation) are inoperable c. Location - Plant location is latitude 3538'01"N, longitude 7857'23"W and a distance of 16 miles Southwest of Raleigh d. Height - The Cooling Tower is 523 feet above ground level. The height of the Cooling Tower above sea level is 784 feet. e. Estimated return to service date Determine from the Flight Service Station the name of the individual contacted and when a follow-up call should be made. Document the notification and any required follow-up in an NCR with Licensing as the responsible organization.
AP-617 Rev. 35 Page 38 of 49 2014 NRC SRO Question 9 8 (23) Reference One Hour Notifications - Sample Wording for the Description Field (Licensing will review notifications for follow-up clarification as needed.) I.A. OPERATIONAL EVENTS -10 CFR 50.72 (b) (1) Technical Specification Deviations (10 CFR 50.54x) DEVIATION FROM TECHNICAL SPECIFICATIONS PER 10 CFR 50.54(x) Attachment 5 Sheet 1 of 2 At _ hrs license condition was deviated from per 10 CFR 50.54(x). This condition requires _. Discussion as to why the condition was not met, affect on the plant and when compliance was/will be restored. The NRC Resident Inspector was notified. Safety Limit Violation (TS 6.7.1) VIOLATION OF SAFETY LIMIT At hrs Technical Specification Safety Limit was violated when _. Immediate corrective actions were . Discussion as to the affect on the plant, additional planned actions, and any compensatory actions taken to assure safety. The NRC Resident Inspector was notified. I.B. RADIOLOGICAL EVENTS Radioactive Shipments Note: The time and date of the spent fuel shipment is safeguards information. Date and time of discovery is not safeguards but care should be taken not to link the event to arrival of the cask. Example: SURFACE CONTAMINATION ABOVE LIMITS Smearable contamination on a radioactive materials package, a used fuel shipping cask transported by rail, exceeded the limits of 10 CFR 71.47. There is no evidence of personnel contamination or spread of contamination beyond the rail car. There is no indication of increased exposure to the public as a result of this event. The NRC Resident Inspector was notified. Loss or Theft of Licensed Material/Radiological Sabotage (This example is for Loss only. Theft or Sabotage is reported using SEC-NGGC-2147.) LOCATION OF _ IS UNKNOWN How was loss of SNM discovered and what efforts to relocate are underway? What assurance is there that the lost SNM is under the control of a licensee (vs. the public) and that no personnel have been overexposed? The NRC Resident Inspector was notified. Region II (name) and the State of North Carolina have also been notified.
AP-617 Rev. 35 Page 39 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 5 Sheet 2 of 2 Exposure to Individuals or Releases PERSONNEL OVEREXPOSURE A worker received (internal/external) contamination resulting in an estimated total effective dose equivalent (TEDE) of _ Rem ( mSv). The individual had been doing what, where. How detected? What location on the body. What decontamination was performed to what result? What immediate corrective actions are being taken? The NRC Resident Inspector was notified Accidental Criticality in the Fuel Handling Building No example. This event is extremely rare.
I.C. SECURITY EVENTS Security Events Reported per SEC-NGGC-2147. Security and Safeguards events are prepared by the Security Organization per SEC-NGGC- 2147. International Atomic Energy Agency (IAEA) Representative No example. This event is extremely rare.
I.D. FITNESS FOR DUTY FFD - NRC Employee No example. This event is extremely rare.
AP-617 Rev. 35 Page 40 of 49 2014 NRC SRO Question 9 8 (23) Reference NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN # NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*, [2nd] 301-415-0550 and [3rd] 301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers. NOTIFICATION TIME 15:43 EDT FACILITY OR ORGANIZATION Harris Nuclear Plant UNIT 1 NAME OF CALLER John Caves CALL BACK # (919) 362-3636 EVENT TIME & ZONE 14:33 EDT EVENT DATE 09/18/2003 POWER/MODE BEFORE 100% Power, Mode 1 POWER/MODE AFTER 100% Power, Mode 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A)
Safe S/D Capab ility AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B)
RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C)
Control of Rad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D)
Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED X 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) (xiii) Loss Comm/Asmt/Re sp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1) MATERIAL/
EXPOSURE B??? 8-Hr. Non-Emergency 10CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (identify) OTHER UNSPECIFIED REQMT. (see last column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back) As of 2:33 PM, EDT, more than 20% of the offsite emergency sirens were inoperable for greater than one hour due to loss of power caused by Hurricane Isabel. Currently 27 of 81 sirens are out of service. The State of North Carolina and all four counties within the 10-mile emergency planning zone were notified and are in stand-by to implement mobile route alerting if needed. At this time, Harris cannot estimate the time of siren recovery. This requires an 8-hour non-emergency notification per 10CFR 50.72(b)(3)(xiii) due to the loss of a significant portion of the offsite notification system. The NRC Senior Resident Inspector was informed. NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR YES (EXPLAIN ABOVE) X NO NOT UNDERSTOOD? NRC RESIDENT X STATE(s) X DID ALL SYSTEMS X YES NO FUNCTION AS REQUIRED? LOCAL X OTHER GOV AGENCIES X MODE OF OPERATION UNTIL CORRECTED: 1 ESTIMATE FOR RESTART DATE: ADDITIONAL INFO ON BACK YES X NO MEDIA/PRESS RELEASE X Attachment 6 Sheet 1 of 1 SAMPLE WORKSHEET
SAARPS MPLX E AP-617 Rev. 35 Page 41 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 7 Sheet 1 of 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN # NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*, [2nd] 301-415-0550 and [3rd] 301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers. NOTIFICATION TIME EST / EDT FACILITY OR ORGANIZATION Harris Nuclear Plant UNIT 1 NAME OF CALLER CALL BACK # 919 - EVENT TIME & ZONE EST / EDT EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A)
Safe S/D Capab ility AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B)
RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C)
Control of Rad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D)
Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/Asmt/Re sp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1) MATERIAL/
EXPOSURE B??? 8-Hr. Non-Emergency 10CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (identify) OTHER UNSPECIFIED REQMT. (see last column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back) NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR YES (EXPLAIN ABOVE) NO NOT UNDERSTOOD? NRC RESIDENT STATE(s) DID ALL SYSTEMS YES NO FUNCTION AS REQUIRED? LOCAL OTHER GOV AGENCIES MODE OF OPERATION UNTIL CORRECTED: ESTIMATE FOR RESTART DATE: ADDITIONAL INFO ON BACK YES NO MEDIA/PRESS RELEASE AP-617 Rev. 35 Page 42 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 7 Sheet 2 of 2 RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanations should be covered in event description) LIQUID RELEASE GASEOUS RELEASE UNPLANNED RELEASE PLANNED RELEASE ONGOING TERMINATED MONITORED UNMONITORED OFFSITE RELEASE T. S. EXCEEDED RM ALARMS AREAS EVACUATED PERSONNEL EXPOSED OR CONTAMINATED OFFSITE PROTECTIVE ACTIONS RECOMMENDED *State release path in description Release Rate (Ci/sec) % T. S. LIMIT HOO GUIDE Total Activity (Ci) % T. S. LIMIT HOO GUIDE Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 uCi/sec 0.01 Ci Particulate 1 uCi/sec 1 mCi Liquid (excluding tritium and dissolved noble gases) 10 uCi/min 0.1 Ci Liquid (tritium) 0.2 Ci/min 5 Ci Total Activity PLANT STACK CONDENSER/AIR EJECTOR MAIN STEAM LINE SG BLOWDOWN OTHER RAD MONITOR READINGS ALARM SETPOINTS % T. S. LIMIT (if applicable) RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific details/explanations should be covered in event description) LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.) LEAK RATE: UNITS: gpm/gpd T.S. LIMITS: SUDDEN OR LONG-TERM DEVELOPMENT: LEAK START DATE TIME COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS: LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL: EVENT DESCRIPTION (continued from front) NRC HEADQUARTERS DUTY OFFICER CONTACTED: / / : AM/PM NAME DATE TIME AP-617 Rev. 35 Page 43 of 49 2014 NRC SRO Question 9 8 (23) Reference Reportability Evaluation (REW) Worksheet Notification Requirements Per 10CFR50.73 Reports NCR- (Ref. NUREG-1022) Attachment 8 Sheet 1 of 6 A Licensee Event Report (LER) is generally required for any event of the type described in this Attachment within 60 days after the discovery of the event. HNP shall report any applicable event if it occurred within three years of the date of discovery regardless of the plant mode or power level, and regardless of the significance of the structure, system, or component that initiated the event. I. Description of the Event AP-617 Rev. 35 Page 44 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 2 of 6 II. For each Reportability Evaluation, perform the following: Consult with or perform a pre-job briefing with Licensing. Using the details of the event, determine if the reporting category applies to this event. Mark the appropriate block Yes or No. If uncertain, gather more information to make the determination. Consult Licensing as needed. Reference NUREG-1022 as needed since it contains many examples that may aid in the determination. Complete the Reportable Evaluation Section to justify the conclusion that was reached based on known facts. Situation meets this condition? Reportable Event Yes No Plant Shutdown Required by Technical Specifications? The completion of any nuclear plant shutdown required by the HNP Technical Specifications. Yes No Operation or Condition Prohibited by Technical Specifications? Any operation or condition which was prohibited by the HNP Technical Specifications except when: a. The Technical Specification is administrative in nature; b. The event consisted solely of a case of a late surveillance test where the oversight was corrected, the test was performed, and the equipment was found to be capable of performing its specified safety functions; or c. The Technical Specification was revised prior to discovery of the event such that the operation or condition was no longer prohibited at the time of discovery of the event. Yes No Deviation from Technical Specifications? Any deviation from the HNP Technical Specifications authorized pursuant to section 50.54(x).
AP-617 Rev. 35 Page 45 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 3 of 6 Situation meets this condition? Reportable Event Yes No System Actuation? Any event or condition that resulted in a manual or automatic actuation of any of the systems listed below, except when: a. The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; or b. The actuation was invalid and; (1) Occurred while the system was properly removed from service; or (2) Occurred after the safety function had been already completed. The systems to which the requirements above apply are: a. Reactor protection system (RPS) including reactor trip. b. General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). c. Emergency core cooling systems (ECCS) including: high-head and low-head injection systems and the low pressure injection function of residual (decay) heat removal systems. d. Auxiliary or Feedwater system. e. Containment heat removal and depressurization systems, including containment spray and fan cooler systems. f. Emergency ac electrical power systems, including emergency diesel generators (EDGs). g. Emergency service water systems. Yes No Common Cause Inoperability of Independent Trains or Channels? Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to: a. Shut down the reactor and maintain it in a safe shutdown condition, b. Remove residual heat, c. Control the release of radioactive material, or d. Mitigate the consequences of an accident.
AP-617 Rev. 35 Page 46 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 4 of 6 Situation meets this condition? Reportable Event Yes No Event or Condition that Could Have Prevented Fulfillment of a Safety Function? Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to: a. Shut down the reactor and maintain it in a safe shutdown condition; b. Remove residual heat; c. Control the release of radioactive material; or d. Mitigate the consequences of an accident. Events covered above may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, individual component failures need not be reported if redundant equipment in the same system was operable and available to perform the required safety function. Yes No Single Cause that Could Have Prevented Fulfillment of the Safety Functions of Trains or Channels in Different Systems? Any event or condition that as a result of a single cause could have prevented the fulfillment of a safety function for two or more trains or channels in different systems that are needed to: a. Shut down the reactor and maintain it in a safe shutdown condition, b. Remove residual heat, c. Control the release of radioactive material, or d. Mitigate the consequences of an accident. Events covered above may include cases of procedural error, equipment failure, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacy. However, HNP is not required to report an event above if the event results from: a. A shared dependency among trains or channels that is a natural or expected consequence of the approved plant design; or b. Normal and expected wear or degradation. Yes No Degraded or Unanalyzed Condition? Any event or condition that resulted in: a. The condition of the nuclear power plant including its principal safety barriers, being seriously degraded; or b. The nuclear power plant being in an unanalyzed condition that significantly degraded plant safety.
AP-617 Rev. 35 Page 47 of 49 2014 NRC SRO Question 9 8 (23) Reference Attachment 8 Sheet 5 of 6 Situation meets this condition? Reportable Event Yes No External Threat or Hampering? Any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear plant. Yes No Internal Threat or Hampering? Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases. Yes No Radioactive Release? Any airborne radioactive release that, when averaged over a time period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, resulted in airborne radionuclide concentrations in an unrestricted area that exceeded 20 times the applicable concentration limits specified in appendix B to 10CFR20, table 2, column 1. Any liquid effluent release that, when averaged over a time period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, exceeds 20 times the applicable concentrations specified in Appendix B to 10CFR20 table 2, column 2, at the point of entry into the receiving waters (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases.
AP-617 Rev. 35 Page 48 of 49 2014 NRC SRO Question 9 8 (23) Reference III. Reportable Evaluation Attachment 8 Sheet 6 of 6
IV. Conclusion Based on the information above, this event: (check one) Does NOT meet the reportability requirements of 10 CFR 50.73. IS reportable to the NRC per the requirements of 10.CFR 50.73.
AP-617 Rev. 35 Page 49 of 49 2014 NRC SRO Question 9 8 (23) Reference Rev 35 processed with PRR 337339 Revision 35 Summary PRRs Incorporated: 283909, 310079, 329593, 337339, 654718 CRs Incorporated: 589278 (ENHN), 589282 (BREC), 613083 (CORR), 622683 (CORR), 634918 (CORR) [CR 613083] 2.0.42 new reference for NEI 07-07 [ENHN 589278, BREC 589282] Attachment 1 has been restructured/reordered from notification time to functional area. [PRR 329593, 337339] Attachment 1 NOTE 7 revised to add note for ERDS modem [PRR 283909, 329593] Attachment 1 NOTE 11 revised reference from 26.73(a)(2) to 26.719 [CR 613083, 622683] Attachment 1 NOTE 12 revised to add fleet interim guidance regarding NEI 07-07 [PRR 654718] Attachment 1 NOTE 12 revised to clarify information for oil spills [PRR 329593, 337339] Attachment 3 CDE Report Timing Of Response column revised from "By the end of the 1st month following each quarter" to "By the 21st day following each quarter" [PRR 310079] Attachment 3 and Attachment 4 revised to change "NAS" to "NOS" [CR 634918] Attachment 4 Cooling Tower Beacon Outage revised to add note the FAA is automatically informed. [PRR 329593] Attachment 7 revised to add "EST/EDT" to the No tification time block and Event Time & Zone block.
2014 NRC SRO Question 93 (18) Reference
2014 NRC SRO Question 93 (18) Reference
2014 NRC SRO Question 93 (18) Reference
2014 NRC SRO Question 88 (13) Reference
2014 NRC SRO Question 88 (13) Reference
2014 NRC SRO Question 87 (12) Reference
2014 NRC SRO Question 87 (12) Reference
2014 NRC SRO Question 87 (12) Reference
2014 NRC SRO Question 87 (12) Reference
2014 NRC SRO Question 82 (7) Reference
2014 NRC SRO Question 82 (7) Reference