Text

302 Final SRO Written Exam
	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)
	v • d • e

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 pressure Current 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 stable Based on these plant condtions, which ONE of the following completes the statements below?

A (1) break has occurred.

To allow the injection of the RHR pumps, in accordance with EOP-FR-C.1, Response to Inadequate Core Cooling, (2) is required to depressurize the RCS.

A. (1) PRZ steam space (2) opening of the Reactor Head Vent valves B. (1) PRZ steam space (2) the depressuization of all intact SGs at maximum rate C. (1) RCS hot leg (2) opening of the Reactor Head Vent valves D. (1) RCS hot leg (2) the depressuization of all intact SGs at maximum rate 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 are evaluating 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 SI Accumulators are required to be isolated when (2) .

A. (1) monitor light box (MLB-3B)

(2) RCS pressure is below 1000 psig B. (1) monitor light box (MLB-3B)

(2) at least two RCS Hot Leg temperatures are less than 390°F C. (1) status light box (SLB-2)

(2) RCS pressure is below 1000 psig D. (1) status light box (SLB-2)

(2) at least two RCS Hot Leg temperatures are less than 390°F 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 Cooling Mode Subsequently the following occurs:

- PRZ level lowers rapidly

- PRZ pressure lowers rapidly

- RHR pump 'A' trips on overcurrent

- RCS tempurature is 352°F and rising Which ONE of the following completes the statements below?

PRZ level indicators 460 and (1) are the Post Accident indicators that should be used to monitor PRZ level.

Based on the conditions above, if ONE PRZ level channel of the Post Accident indicators is NOT operable / available AND is unable to be restored the ACTION required by Technical Specifation 3.3.3.6, Accident Monitoring Instrumentation, is to be in Hot Shutdown within (2) hours.

A. (1) 461 (2) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. (1) 461 (2) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. (1) 462 (2) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. (1) 462 (2) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 occurs One 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 an operator to (2) .

A. (1) B-SB equipment ONLY (2) locally close breaker 106 B. (1) B-SB equipment ONLY (2) manually control EDG 1A-SA load / speed C. (1) BOTH A-SA and B-SB equipment (2) locally close breaker 106 D. (1) BOTH A-SA and B-SB equipment (2) manually control EDG 1A-SA load / speed 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 available Over 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 lowering AOP-017, Loss Of Instrument Air, is being performed.

An AO reports the instrument line to the Condenser Steam Dump valves on the west side of the condenser has ruptured.

Which ONE of the following (1) describes the expected operation of the Instrument Air Compressors AND (2) identifies the Attachment that should be performed?

A. (1) 1A and 1B running ONLY (2) Attachment 2, Positioning MCB Controllers B. (1) 1A and 1B running ONLY (2) Attachment 3, Reducing Instrument Air Header Loads C. (1) 1A, 1B, and 1C running (2) Attachment 2, Positioning MCB Controllers D. (1) 1A, 1B, and 1C running (2) Attachment 3, Reducing Instrument Air Header Loads 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 reset The 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 KPPH Based on this information, which ONE of the following procedures will be implemented when exiting EOP-E-0?

A. EOP-FR-H.1, Response to Loss of Secondary Heat Sink B. EOP-ECA-1.2, LOCA Outside Containment C. EOP-ES-1.1, SI Termination D. EOP-ES-1.2, Post LOCA Cooldown and Depressurization 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 steps Subsequently the following occurs:

- Control Bank D Rod P-8 drops to 145 steps.

- It will take 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to re-align rod P-8 with the Control Bank D rods Which ONE of the following statements describes (1) the MAXIMUM Thermal power level the unit is required to maintain in accordance with Tech Spec 3.1.3.1, Movable Control Assemblies - Group Height, One rod not within alignment limits, AND (2) the Basis for reducing Thermal Power?

(Reference provided)

A. (1) 85%

(2) Provides assurance of fuel rod integrity during continued operation.

B. (1) 85%

(2) Minimizes the effect of a Control Rod ejection accident.

C. (1) 75%

(2) Provides assurance of fuel rod integrity during continued operation.

D. (1) 75%

(2) Minimizes the effect of a Control Rod ejection accident.

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 today Which ONE of the following completes the statements below?

In accordance with OST-2044, for a planned crane lift above the WGDTs the MAXIMUM 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 the Waste Gas System is based on not exceeding a MAXIMUM of (2) in the event 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 Times PLP-114, Relocated Technical Specifications and Design Basis Requirements A. (1) 12 (2) 2 Rem exposure to the public B. (1) 12 (2) 0.5 Rem exposure to a radiation worker near the tank C. (1) 24 (2) 2 Rem exposure to the public D. (1) 24 (2) 0.5 Rem exposure to a radiation worker near the tank 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 Cavity Integrity

- The CRS has directed that the fuel assembly be returned to the Reactor Vessel Prior 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 rising In accordance with AOP-031, what action must be taken in Containment?

A. Place the fuel assembly in the Reactor Vessel and evacuate ONLY unnecessary personnel.

B. Leave the fuel assembly in the upender and evacuate ONLY unnecessary personnel.

C. Place the fuel assembly in the Reactor Vessel and evacuate ALL personnel.

D. Leave the fuel assembly in the upender and evacuate ALL personnel.

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 in accordance with EOP-ECA-1.1, Loss Of Emergency Coolant Recirculation Subsequently, a transition has just been made to EOP-FR-Z.1, Response to High Containment Pressure

- Current Containment pressure is 14 psig and slowly lowering

- RWST level is 47% and slowly lowering

- 3 Containment Fan Coolers are available and running Which ONE of the following actions should be taken for the current plant conditions?

A. Start the second Containment Spray Pump if Containment pressure does not lower below 10 psig before exiting EOP-FR-Z.1.

B. Start the second Containment Spray Pump per EOP-FR-Z.1 since pressure is above 10 psig.

C. Continue operation with one Containment Spray pump per EOP-ECA-1.1 unless Containment pressure exceeds 45 psig, then start the second pump.

D. Continue operation with one Containment Spray pump per EOP-ECA-1.1 unless Containment pressure begins rising, then start the second pump.

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, due to a failed bistable

- Repair of Loop B, Tavg/-T Channel II, will not be completed for another 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months I&C discovers the bistables for Power Range channel N-41 are set higher than the allowable values of Technical Specifications and repairs will take 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Which ONE of the following identifies the LEAST restrictive requirement that must be completed for these conditions in accordance with OWP-RP-01 and Technical Specifications?

A. Bypass Power Range N-41 until repairs are completed on Loop B Tavg/-T B. Prepare to shutdown in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Hot Shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. Trip the Power Range N-41 bistables after Loop B Tavg/-T is returned to service D. Place the unit in Hot Standby within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 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, alarms Subsequently 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 initiated Which ONE of the following identifies the FIRST required classification for the conditions above?

(Reference provided)

A. FU1.1 B. SU1.1 C. SU5.1 D. SU8.1 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 Fan Cooler 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-2 AND (2) a required action in accordance with Technical Specification 3.6.2.3, Containment Cooling System?

(Reference provided)

A. (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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. (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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. (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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. (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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 lowering One 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 upstream flange 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 bases for the Limiting Condition of Operation is to ensure that sufficient cooling capacity is available for continued operation of safety related equipment during (2) conditions.

A. (1) Normal Service Water (2) normal AND accident B. (1) Normal Service Water (2) ONLY accident C. (1) Emergency Service Water (2) normal AND accident D. (1) Emergency Service Water (2) ONLY accident 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 in progress:

- Source range audible counts are unexpectedly rising

- Annunciator ALB-013-2-1, Source Range High Flux Lvl at Shutdown, has gone into alarm due to both NI-31 and NI-32 responses Which 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 correctly Technical Specifications requires the RCS boron concentration to be determined within (2) hours.

A. (1) should be manually (2) 4 B. (1) should be manually (2) 12 C. (1) will be automatically (2) 4 D. (1) will be automatically (2) 12 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, Reactor Startup (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.

A. (1) OWP-RP, Reactor Protection (2) is B. (1) OWP-RP, Reactor Protection (2) is NOT C. (1) OP-105, Excore Nuclear Instrumentation (2) is D. (1) OP-105, Excore Nuclear Instrumentation (2) is NOT 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 lowering Which 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 conditions AND (2) the basis for the action?

A. (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water Source Availability.

(2) To prevent loss of inventory that could result in elevated radiation levels in the Spent Fuel Pool area.

B. (1) Restore Spent Fuel Pool level using Attachment 4, SFP Makeup Water Source Availability.

(2) Adequate cooling to the Spent Fuel Pools will likely be provided through the feed and bleed process.

C. (1) Reduce Spent Fuel Pool temperature using Attachment 5, Aligning SFP Cooling with Cross-Connected Pump and HX.

(2) To prevent boiling of the Spent Fuel Pools that could result in boron plating on the fuel assemblies.

D. (1) Reduce Spent Fuel Pool temperature using Attachment 5, Aligning SFP Cooling with Cross-Connected Pump and HX.

(2) Adequate cooling to the Spent Fuel Pools will likely prevent boiling and the resultant lowering of water level.

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 be implemented to stop the release in progress.

In accordance with ODCM 3.3.3.11, Radioactive Gaseous Effluent Monitoring Instrumentation, (2) is (are) required to resume the release.

(Reference provided)

A. (1) OP-120.07, Section 7.1, Total Shutdown (2) the initiatation of the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. (1) OP-120.07, Section 7.1, Total Shutdown (2) samples, release rate calcs, and an Independent Verification of the valve line-up C. (1) OP-120.07, Section 8.37, Actions for a REM Monitor Alarm During a Waste Gas Decay Tank Release (2) the initiatation of the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. (1) OP-120.07, Section 8.37, Actions for a REM Monitor Alarm During a Waste Gas Decay Tank Release (2) samples, release rate calcs, and an Independent Verification of the valve line-up 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 Det Trouble, 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/gm Which ONE of the following conditions would (1) satisfy Technical Specifications requirements, AND (2) what is the basis for the requirement?

A. (1) Be in Mode 3 with Tavg <500°F within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(2) To minimize the potential release of activity in the event of a SG Tube Rupture.

B. (1) Be in Mode 3 with Tavg <500°F within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(2) To reduce the production of fission products until DEI is restored to the Tech Spec required value of < 0.35 Ci/gm.

C. (1) Reduce power below 50% within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

(2) To minimize the potential release of activity in the event of a SG Tube Rupture.

D. (1) Reduce power below 50% within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

(2) To reduce the production of fission products until DEI is restored to the Tech Spec required value of < 0.35 Ci/gm.

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, has alarmed due to a transmitter failure Which ONE of the following completes the statements below regarding the system failure 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 action is to place the channel in the tripped condition within (2) hours.

A. (1) 459 (2) 4 B. (1) 460 (2) 4 C. (1) 459 (2) 6 D. (1) 460 (2) 6 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 entering AOP-001, Malfunction of Rod Control and Indication System and placing the rod control system to manual In accordance with WCM-001, On-Line Maintenance Risk Management, which ONE of the following personel are RESPONSIBLE for assessing the impact on scheduled work and plant risk?

A. STA B. WCC-SRO C. Work Week Manager D. Shift Manager 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 for off-site power distribution with the plant in Mode 1?

A. The requirement can be satisfied by any two separate off-site transmission lines that can power the SUTs.

B. The requirement can ONLY be satisfied by two off-site transmission lines that feed the SUTs directly (Cary, Regency Park and Cape Fear North).

C. The requirement can ONLY be satisfied by the off-site transmission lines that do not feed the respective North or South switchyard bus through a jumper.

D. The requirement is satisfied as long as the switchyard alignment is such that power is available from the off-site transmission network to both SUTs regardless of the number of transmission lines available.

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 was de-contaminated

- Duke Energy is planning a news release for this event Which ONE of the following completes the statements below?

In accordance with AP-617, Reportability Determination And Notification, the EARLIEST required NRC notification of this event is within (1) hours.

In accordance with AOP-013, Fuel Handling Accident, (2) is the primary radiological concern for fuel off-loaded more than 6 months ago because it will NOT be detected by personal dosimetry or area radiation monitors.

(Reference provided)

A. (1) 4 (2) Krypton-85 B. (1) 4 (2) Iodine-131 C. (1) 8 (2) Krypton-85 D. (1) 8 (2) Iodine-131 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 approving a Batch Gaseous Effluent Permit in accordance with OP-120.07, Waste Gas Processing?

Prepares Permit Approves Permit A. Chemistry Control Room Supervisor B. Chemistry Shift Manager C. Radiation Protection Control Room Supervisor D. Radiation Protection Shift Manager 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 Emergency Response 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 in progress. 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 AND the position that must approve the expected dose the Mechanic will receive in accordance 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____

A. Protection of large populations ONLY SEC-TSC B. Protection of large populations ONLY RCD C. Protect valuable property AND large populations SEC-TSC D. Protect valuable property AND large populations RCD You have completed the test!

Friday, October 31, 2014 10:24:05 AM 100 Rev. FINAL

ANSWER KEY REPORT for 2014 NRC SRO Written Exam Test Form: 0 Answers

ID 0 1 2014 NRC RO 1 B 2 2014 NRC RO 2 C 3 2014 NRC RO 3 A 4 2014 NRC RO 4 D 5 2014 NRC RO 5 A 6 2014 NRC RO 6 A 7 2014 NRC RO 7 C 8 2014 NRC RO 8 D 9 2014 NRC RO 9 A 10 2014 NRC RO 10 C 11 2014 NRC RO 11 D 12 2014 NRC RO 12 A 13 2014 NRC RO 13 D 14 2014 NRC RO 14 D 15 2014 NRC RO 15 D 16 2014 NRC RO 16 A 17 2014 NRC RO 17 B 18 2014 NRC RO 18 A 19 2014 NRC RO 19 A 20 2014 NRC RO 20 A 21 2014 NRC RO 21 B 22 2014 NRC RO 22 D 23 2014 NRC RO 23 D 24 2014 NRC RO 24 D 25 2014 NRC RO 25 B 26 2014 NRC RO 26 A 27 2014 NRC RO 27 C 28 2014 NRC RO 28 D 29 2014 NRC RO 29 C 30 2014 NRC RO 30 B 31 2014 NRC RO 31 C 32 2014 NRC RO 32 C 33 2014 NRC RO 33 B 34 2014 NRC RO 34 A 35 2014 NRC RO 35 C 36 2014 NRC RO 36 D 37 2014 NRC RO 37 D 38 2014 NRC RO 38 B 39 2014 NRC RO 39 B 40 2014 NRC RO 40 D 41 2014 NRC RO 41 B 42 2014 NRC RO 42 A 43 2014 NRC RO 43 D 44 2014 NRC RO 44 B 45 2014 NRC RO 45 C 46 2014 NRC RO 46 A 47 2014 NRC RO 47 C Friday, October 31, 2014 10:26:10 AM 1

ANSWER KEY REPORT for 2014 NRC SRO Written Exam Test Form: 0 Answers

ID 0 48 2014 NRC RO 48 D 49 2014 NRC RO 49 B 50 2014 NRC RO 50 A 51 2014 NRC RO 51 B 52 2014 NRC RO 52 B 53 2014 NRC RO 53 A 54 2014 NRC RO 54 D 55 2014 NRC RO 55 C 56 2014 NRC RO 56 C 57 2014 NRC RO 57 D 58 2014 NRC RO 58 B 59 2014 NRC RO 59 D 60 2014 NRC RO 60 D 61 2014 NRC RO 61 C 62 2014 NRC RO 62 B 63 2014 NRC RO 63 A 64 2014 NRC RO 64 B 65 2014 NRC RO 65 C 66 2014 NRC RO 66 A 67 2014 NRC RO 67 C 68 2014 NRC RO 68 D 69 2014 NRC RO 69 B 70 2014 NRC RO 70 C 71 2014 NRC RO 71 D 72 2014 NRC RO 72 C 73 2014 NRC RO 73 B 74 2014 NRC RO 74 D 75 2014 NRC RO 75 C 76 2014 NRC SRO 1 B 77 2014 NRC SRO 2 B 78 2014 NRC SRO 3 A 79 2014 NRC SRO 4 B 80 2014 NRC SRO 5 D 81 2014 NRC SRO 6 B 82 2014 NRC SRO 7 C 83 2014 NRC SRO 8 B 84 2014 NRC SRO 9 D 85 2014 NRC SRO 10 C 86 2014 NRC SRO 11 D 87 2014 NRC SRO 12 A 88 2014 NRC SRO 13 C 89 2014 NRC SRO 14 C 90 2014 NRC SRO 15 C 91 2014 NRC SRO 16 A 92 2014 NRC SRO 17 B 93 2014 NRC SRO 18 D 94 2014 NRC SRO 19 A Friday, October 31, 2014 10:26:10 AM 2

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ID 0 95 2014 NRC SRO 20 C 96 2014 NRC SRO 21 C 97 2014 NRC SRO 22 A 98 2014 NRC SRO 23 A 99 2014 NRC SRO 24 A 100 2014 NRC SRO 25 A Friday, October 31, 2014 10:26:10 AM 3

2014 NRC SRO Question 69 Reference 2014 NRC SRO Question 98 (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 1 of 49

2014 NRC SRO Question 98 (23) Reference Table of Contents Section Page 1.0 PURPOSE ............................................................................................................ 3

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 2 of 49

2014 NRC SRO Question 98 (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 3 of 49

2014 NRC SRO Question 98 (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 4 of 49

2014 NRC SRO Question 98 (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 5 of 49

2014 NRC SRO Question 98 (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 6 of 49

2014 NRC SRO Question 98 (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 7 of 49

2014 NRC SRO Question 98 (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 8 of 49

2014 NRC SRO Question 98 (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 9 of 49

2014 NRC SRO Question 98 (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 10 of 49

2014 NRC SRO Question 98 (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 11 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 1 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS 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)

ENS notification ENS notification ENS notification ENS notification Event or Condition Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 60-day LER Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Declaration of any 50.72(a)(1)(i)

Emergency Classes specified in the Emergency Plan Deviation from Tech Deviation from TS 50.73(a)(2)(i)(C)

Specs Authorized under authorized by

§50.54(x) 50.54(x)

[50.72(b)(1)]

Plant shutdown (S/D) Initiation of S/D required Completion of a S/D required by Tech Specs by Tech Specs required by Tech

[50.72(b)(2)(i)] Specs

[50.73(a)(2)(i)(A)]

Operation or Condition 50.73(a)(2)(i)(B)

Prohibited by Tech Specs (Note 10)

Degraded or Unanalyzed 50.72(b)(3)(ii) 50.73(a)(2)(ii)

Condition External Threat or 50.73(a)(2)(iii)

Hampering System Actuations Valid ECCS discharges Valid actuation of NRC 50.73(a)(2)(iv)(A) into Reactor Coolant listed systems system (50.72(b)(3)(iv)(A)

[50.72(b)(2)(iv)(A)] - RPS including reactor scram and trip RPS Actuations when - Containment Isolation Reactor is critical signals affecting CIVs in

[50.72(b)(2)(iv)(B)] more than one system or multiple MSIVs

- ECCS

- AFW

- Containment heat and depressurization systems

- Emergency AC electrical systems Event or Condition that 50.72(b)(3)(v) 50.73(a)(2)(v) could have prevented fulfillment of a safety 50.72(b)(3)(vi) 50.73(a)(2)(vi) function Common Cause 50.73(a)(2)(vii)

Inoperability of independent trains or channels Radioactive Releases Airborne radioactive (Notes 3 & 8) 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 12 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 2 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS ENS notification ENS notification ENS notification ENS notification Event or Condition Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 60-day LER Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Loss of Emergency 50.72(b)(3)(xiii)

Preparedness Capabilities (Note 7)

Single Cause that could 50.73(a)(2)(ix)(A) have prevented fulfillment of the Safety Functions of 50.73(a)(2)(ix)(B) trains or channels in different systems News Release or 50.72(b)(2)(xi)

Notifications of other Government Agency (Notes 9, 12, &13)

Transport of a 50.72(b)(3)(xii)

Contaminated Person Offsite Internal Threat or 50.73(a)(2)(x)

Hampering Safety Limit Violation TS 6.7.1 Violation of Operating OL Section 2.G 10 CFR 50.73 License Condition (Note 10)

Fatality or Hospitalization 50.72(b)(2)(xi)

(Note 13)

AP-617 Rev. 35 Page 13 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 3 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS II. RADIOLOGICAL EVENTS Notification Within Notification Within Notification Within Event or Condition Follow-up Report 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Radioactive Note 1a §20.1906(d)(1)

Shipments (Note 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 Note 2a §20.2201(a)(1)(i) Note 2a 30 Day Licensed §20.2201(d) Note 2b 60 Day or Material/Radiological Note 2b §74.11 15 Day Sabotage (Note 2) §150.16(b) Note 2c None

§73.71(a) Note 2d 15 Day Note 2c §73.71(a) Note 2e 15 Day Note 2d §30.55(c)

Note 2e §40.64(c)

§150.17(c)

Exposure to Note 3a §20.2202(a)(1) Note 3a LER Individuals or Note 3b §20.2202(a)(2) Note 3b LER Releases (Note 3) §50.72(b)(2)(iv)

Accidental Criticality Note 4 §70.52(a)

(Note 4)

Radiological Note 8 §20.2202(b) Note 8 30 Day Exposure/Release (Note 8)

Unusual or Important OL App. B, 4.1 Note 9d PLP-500 Note 9d 30 Day Environmental Events PLP-500 Note 9f PLP-500 (Note 9) 50.72 (see Note 12) Otherwise ESS determines III. SECURITY EVENTS/FITNESS FOR DUTY Notification Within Notification Within Event or Condition Follow-up Report 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Security Events per SEC- Note 5 §75.7 Note 5 None NGGC-2147. §75.6 Note 11a None (Notes 5 and 11) §75.7 Note 11b None Note 11a §26.719 Note 11c Non-docketed Note 11b §26.719 correspondence Note 11c App. A to Part 26 B.2.8(e)(5)

FFD - NRC Employee Note 6 §26.27(d)

(Note 6)

International Atomic Note 5 §75.7 Energy Agency (IAEA) §75.6 Representative (Note 5) §75.7 FFD Program Events Note 11a §26.719 Note 11a None (Note 11) Note 11b §26.719 Note 11b None Note 11c App. A to Part 26 Note 11c Non-docketed B.2.8(e)(5) correspondence AP-617 Rev. 35 Page 14 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 4 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS NOTES NOTIFICATION REFERENCE WRITTEN FOLLOW-UP

1. RADIOACTIVE SHIPMENTS a) Removable contamination from a received §20.1906(d)(1) package containing radioactive material in excess §71.87(i) of the limits specified in §71.87(i). The involved RP Supervisor shall immediately notify the final delivery carrier.

b) Radiation levels from a received package of §20.1906(d)(2) radioactive material in excess of the limits §71.47 specified in §71.47. The involved RP Supervisor shall immediately notify the final delivery carrier.

c) Security related events with respect to the §73.71(b)(2) transport of special nuclear material are handled §73 Appendix G via SEC-NGGC-2147. Security threats or theft of §73.71(a)(5) licensed material shall be reported to site Security personnel.

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 §20.2201(a)(1)(i) 30-Day Written Report to or greater than 1,000 times the quantity §20.2201(d) required per §20.2201(b) 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, b) Any Special Nuclear Material or spent fuel, (theft - See SEC- 60-Day Written Report NGGC-2147) required per §73.71(a) or

§74.11 (b) - See SEC-NGGC-

§150.16(b) 2147

§73.71(a) 15-Day Written Report may be required per

§150 c) Recovery of or accounting for loss of any shipment §73.71(a) of Special Nuclear Material or spent fuel d) Greater than 10 curies of tritium at any one time or §30.55(c) 15-Day Written Report 100 curies in one calendar year, or required e) More than 15 pounds of uranium or thorium at any §40.64(c) 15-Day Written Report one time or more than 150 pounds in one calendar §150.17(c) required year.

AP-617 Rev. 35 Page 15 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 5 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS NOTES 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: §20.2202(a)(1) LER required by

§50.73(a)(2)(viii),

1) A total effective dose equivalent of 25 Rem (a)(2)(ix) and §20.2203

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months b) Release of radioactive material in excess of §20.2202(a)(2) LER required by Technical Specification Instantaneous Limits shall §50.72(b)(2)(iv) §50.73(a)(2)(viii),

be declared an emergency in accordance with (a)(2)(ix) and §20.2203 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.

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) §75.7 None 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 §75.6 and §75.7 Nuclear Reactor Regulation

6. FITNESS FOR DUTY - NRC EMPLOYEE Notification of NRC employees unfitness for duty. §26.27(d) None 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.

AP-617 Rev. 35 Page 16 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 6 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS 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 §50.72(b)(3)(xiii) None CAPABILITY 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 17 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 7 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS NOTES 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Env. Prot. Plan, Local, State & Federal environmental impact causally related to plant (Operating License Agency Notifications operation. Examples are: Appendix B) defined in PLP-500 Section 4.1, require NRC notification and PLP-500 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 50.72 (See Note 12) a) Excessive bird impaction ESS determines If event is significant and threshold not reportable to a Local, State, or Federal b) Onsite plant or animal disease outbreak ESS determines agency, a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months NRC threshold notification may still be required per Env. Prot.

c) Mortality or unusual occurrence of Endangered ESS determines Plan.

Species threshold d) Fish Kills Local and State 30-Day Follow-up written Notifications defined report required per Env.

in PLP-500 Prot. Plan Subsection 5.4.2 e) Increase in nuisance organisms or conditions ESS determines threshold f) Unanticipated or emergency discharge of waste Local and State water or chemical substances Notifications defined in PLP-500 g) Damage to vegetation resulting from cooling tower ESS determines drift deposition threshold h) Station outage or failure of any cooling water ESS determines intake or service water system components due to threshold bio-fouling by Corbicula (Asiatic Clam)

AP-617 Rev. 35 Page 18 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 8 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS NOTES NOTIFICATION REFERENCE WRITTEN FOLLOW-UP

10. VIOLATION OF OPERATING LICENSE CONDITIONS a) Any event resulting in the plant operating in a OL Section 2.G 60-day LER required per manner which violates the SHNPP Facility 10 CFR 50.73 and 10 Operating License, Section 2.C: CFR 50.4(e)

(1) Intentionally raising power above 2948 MWt NEI Position (100%) for any period of time. Statement: Guidance to Licensees on (2) Failure to reduce thermal power to less than or Complying with the equal to 2948 MWt when the 2-hour average Licensed Power Limit exceeds 2948 MWt. (NRC ADAMS Accession No.

(3) Permitting the core thermal power 8-hour ML081750537) 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.

b) A failure to comply with the following OL Section 2.G 60-day LER required per administrative requirements (See Note 1): 10 CFR 50.73 and 10 CFR 50.4(e)

1) Deviation from the requirements of the OL Section 2.C.2 Environmental Protection Plan;

2) Failure to comply with anti-trust conditions of OL Section 2.C.3 Appendix C to OL;

3) Failure to comply with new fuel storage OL Section 2.C.10 requirements.

AP-617 Rev. 35 Page 19 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 9 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS NOTES 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 §26.719 None protected area.

b) Any acts by any person licensed under §55, or by §26.719 None 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.

c) False positive error on a blind performance test App. A to Part 26 Non-docketed specimen when error is determined to be B.2.8(e)(5) correspondence to NRC administrative. Reference 2.35 FFD coordinator AP-617 Rev. 35 Page 20 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 1 Sheet 10 of 10 IMMEDIATE NOTIFICATION REQUIREMENTS NOTES

12. OFF SITE NOTIFICATION HAS BEEN OR W ILL BE MADE Any event or situation, related to the health and safety §50.72(b)(2)(xi) of the public or onsite personnel, or protection of the Reference 2.42 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.)

13. FATALITY OR HOSPITALIZATION a) See SAF-SUBS-00033 and contact the Site Safety SAF-SUBS-00033 See Note 12 for NRC Representative required 4-hour notification b) OSHA must be notified within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of an injury or fatality related to elevators.

AP-617 Rev. 35 Page 21 of 49

2014 NRC SRO Question 98 (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 TS [ODCM] RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE Leak or boron deposit found during inspection O.L. NRC Order HESS 60 days after returning the dated 2/11/03 plant to operation Moderator Temperature Coefficient more 3.1.1.3 HESS 10 Days positive than specified limits Remote Shutdown Monitoring Instrument 3.3.3.5.a Maint 14 Days inoperable for greater than 60 days Radiation Monitors, Pressurizer Safety Valve 3.3.3.6 Maint or IT (and 14 Days Position Indicators or Subcooling Margin Engineering for Monitors inoperable for greater than 7 days. Rad. Monitors)

(Also see OW P-ERFIS)

PORV/RCS Vents used to mitigate RCS 3.4.9.4 Operations 30 Days pressure transient at low temperature An ECCS actuation and injection of water into 3.5.2, 3.5.3 Operations 90 Days (See Note 3) the Reactor Coolant System (See Note 2)

Change to Sample Plan Used for Snubber 3.7.8 HESS Before Implementation Functional Testing PLP-106 Att. 4 AP-617 Rev. 35 Page 22 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 2 Sheet 2 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS TS [ODCM] RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE Radioactive Material in Liquid Holdup Tanks 3.11.1.4 Environmental Include in Annual exceeding limits and Chemistry Radioactive Effluent Release Report Use of non-preferred Incore Detectors when 4.2.4.2 HESS 30 Days evaluating QPTR (Bases)

Abnormal degradation of Containment Vessel 4.6.1.6.2 HESS 15 Days structure detected during required inspections Sealed Source leakage test results 4.7.9.3 Radiation Annually if removable Protection contamination greater than 0.005 µCi detected Greater than 30 total rods or 10 rods per fuel 5.3.1 HESS 30 Days Following Start-up assembly replaced with filler rods or vacancies during any single refueling.

Safety Limit Violation. 6.7.1 Operations 14 Days Startup Report following: 6.9.1.1 HESS 90 Days Following Resumption of Commercial

1) License amendment to increase power level. Operations or Completion of Startup Test Program, or

2) Installation of fuel of different design or 9 months after Initial manufacturer. Criticality, whichever is earliest. Supplementary

3) Modifications that significantly alter the reports required each nuclear, thermal or hydraulic characteristics 3 months.

of the unit.

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 Environmental Before implementation of EPP Section 3.1 and Chemistry change AP-617 Rev. 35 Page 23 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 2 Sheet 3 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS TS [ODCM] RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE Proposed changes/renewal application for T.S. Appendix B Environmental At time of submittal to the NPDES Permit EPP Section 3.2 and Chemistry permitting agency Changes to/renewal of NPDES Permit or State T.S. Appendix B Environmental 30 Days after Certification EPP Section 3.2 and Chemistry change/renewal Stay of NPDES Permit or State Certification T.S. Appendix B Environmental 30 Days following stay EPP Section 3.2 and Chemistry Unusual or Important Environmental Events T.S. Appendix B Environmental 30 Days after event. (Note EPP Sections 4.1 and Chemistry 4) See also 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 5.4.2 notifications Seismic Monitoring Instrument inoperable for PLP-114 Maint 10 Days greater than 30 days Actuation of Seismic Monitoring Instruments PLP-114 HESS 14 Days during seismic event greater than or equal to 0.01g (See Note 1)

Meteorological Monitoring Instrument inoperable PLP-114 Maint 10 Days for greater than 7 days Metal Impact Monitoring System Channel(s) PLP-114 Maint 10 Days inoperable for greater than 30 days.

Explosive gas monitoring instrument inoperable PLP-114 Maint 30 Days for greater than 30 days. (Note: No time specified in PLP-114)

Area Temperatures exceeding PLP-114, PLP-114 HESS & 30 Days Attachment 4 limits by more than 30ºF, or for Operations greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months A calculated dose to a member of the public from [3.11.1.2] Environmental 30 Days the release of radioactive materials in liquid and Chemistry effluents to an unrestricted area exceeding limits Radioactive liquid waste being discharged [3.11.1.3] Environmental 30 Days without treatment and in excess of limits and any and Chemistry portion of the liquid radwaste treatment system & Operations not in operation Calculated air dose in gaseous effluent [3.11.2.2] Environmental 30 Days exceeding limits in areas at or beyond site and Chemistry boundary AP-617 Rev. 35 Page 24 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 2 Sheet 4 of 4 TECHNICAL SPECIFICATION AND ODCM SPECIAL REPORTS TS [ODCM] RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE Calculated dose to a member of the public from [3.11.2.3] Environmental 30 Days a release of gaseous effluents containing and Chemistry Iodine 131, Iodine 133, tritium and radionuclides in particulate form with half-lifes greater than eight days exceeding the limits.

Untreated radioactive gaseous waste discharged [3.11.2.4] Environmental 30 Days in excess of limits and any portion of the and Chemistry gaseous radwaste treatment system not in & Operations operation.

Calculated dose from release of radioactive [3.11.4] Environmental 30 Days material in liquid or gaseous effluents, to a and Chemistry member of the public in excess of limits.

Level of radioactivity, as a result of plant effluent [3.12.1] Environmental 30 Days in a specified location, exceeding the reporting and Chemistry levels of ODCM O.R. Table 3.12-2 when averaged over any calendar quarter.

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 25 of 49

2014 NRC SRO Question 98 (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 REGULATORY RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE Annual Operating Report T.S. 6.9.1.2 Lic / Reg Prog Before 3/1 Annual Radiological T.S. 6.9.1.3 Environmental Before 5/1 Environmental Operating O.R. 3.12.1 and Chemistry Report 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 Annual Environmental Env. Prot. Plan 5.4.1 Environmental Before 5/1 Operating Report and Chemistry Annual Radioactive Effluent T.S. 3.11.1.4 Environmental Before 5/1 Release Report T.S. 6.9.1.4 and Chemistry 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)

AP-617 Rev. 35 Page 26 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 3 Sheet 2 of 3 ROUTINE REPORTS 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.

REGULATORY RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE st 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 §19.13(b) ESS Rad Annually Dose Report (To employee) Services (See Note 1 above) (Dosimetry)

Annual Exposure Report §20.2206(b) Lic / Reg Prog Annually, by for Individual Monitoring April 30th Semiannual Fitness for Duty §26.71(d) Nuclear Within 60 days of Program Performance Data Operations the end of each 6-Analysis Report month reporting period (Jan-June and July-Dec)

ECCS evaluation model changes §50.46(a)(3) NFM&SA Annually or errors where sum of absolute magnitudes of changes results in PCT change 50ºF Changes to QA Program which §50.54(a)(3) NOS In accordance with do not reduce commitments §50.71(e)

Insurance and Financial §50.54(w)(3) Nuclear Annually, on April 1 Security Annual Report Operations In-service Inspection Summary §50.55a (ASME HESS 90 days after Section XI IWA- completion of 6230) inspections FSAR Update, facility changes, §50.59(b) Lic / Reg Prog Six months tests, and experiments §50.71(e) following each conducted without prior approval refueling outage.

Interval not to exceed 24 months between updates AP-617 Rev. 35 Page 27 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 3 Sheet 3 of 3 ROUTINE REPORTS REGULATORY RESP TIMING OF SUBJECT REFERENCE UNIT RESPONSE Annual Financial Report, §50.71(b) Nuclear Upon issuance of the including certified financial Operations report (Normally statements April 30)

Status of Decommissioning §50.75(f) Nuclear March 31, 1999 and Funding Operations 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 §55.45(b)(5)(ii) Training Every 4 years on uncorrected performance anniversary of test failures and schedule for certification correction Material Status Reports (old §74.13(a)(1) HESS 30 days after Forms DOE/NRC-742 and §70.53(a)(1) March 31 and 742(c)) §40.64(b) September 30

§150.17(b) NOTE: 40.64 and 150.17 require statement of foreign origin source material.

QA Program for §71.101 Nuclear Every 5 Years.

Transportation of Operations Docket 71-0345 Radioactive Material Packages Financial Protection - §140.21 Nuclear Annually, on Guarantee of payment of Operations anniversary date on deferred premiums which indemnity agreement is effective (Normally April 30)

AP-617 Rev. 35 Page 28 of 49

2014 NRC SRO Question 98 (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.

10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Report to former radiation worker of 19.13(c) Radiation Upon request; within 30 workers exposure to radiation Protection days from request or 30 (Note 7) days after exposure has been determined Radiation Exposure Data to 19.13(d) Radiation Upon overexposure Individual-Overexposure Protection (Note 5)

(Note 7)

Radiation Exposure Data to 19.13(e) ESS Rad Upon request at Terminating Employees Services termination (Note 7) (Dosimetry)

Bioassay Services to Determine 20.1204(c) Radiation As requested by NRC Exposure Protection Report of planned special exposure 20.1206(f) Radiation Within 30 days following 20.2204 Protection planned special exposure Report to individual of planned 20.1206(g) Radiation Within 30 days from special exposure (Note 7) Protection planned special exposure Respiratory Protection Program 20.1703(d) Radiation 30 Days prior to Equipment not certified by Protection equipment usage NIOSH/MSA Theft or loss of licensed material 20.2201(a)(1)(ii) Radiation 30 Days (by ETS) greater than 10 times Appendix C 20.2201(b) Protection quantities Radiation 30 Days (written Protection follow-up)

Additional information on theft or 20.2201(d) Radiation 30 Days loss Protection AP-617 Rev. 35 Page 29 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 2 of 9 EVENT REPORTS (Other than LERs) 10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Reports of Overexposures/ 20.2203 Radiation 30 Days (Note 5)

Excessive Levels and 40CFR190 Protection Concentrations ODCM O.R.

3.11.4 Missing W aste Shipment Trace 20 App. G, Radiation 2 weeks after Investigation Sec. III.E Protection completion of Investigation Interim evaluation report of identified 21.21(a)(2) Lic / Reg Prog Within 60 days of deviation or failure to comply (when discovery evaluation cannot be completed within 60 days of discovery)

Failure to Comply or Existence of a 21.21(c)(1) & Lic / Reg Prog 2 days, written follow-up Defect (Refer to AP-616) (d)(3) within 30 days FFD testing more conservative than 26 App. A, Human Res Within 60 days of

§26 requirements Sec. A.1.1(2) implementing change FFD - Unsatisfactory performance 26 App. A, Human Res 30 days testing of a certified laboratory Sec. B.2.8 (e)(4)

Reports required as condition of 30.34(e)(4) Radiation As specified in license Parts 30-35 licenses (By-product Protection Material)

Renewal or non-renewal of Parts 30.36 Radiation 30 Days prior to 30-35 licenses Protection expiration Notification of byproduct (Part 30) or 30.36(d) Radiation Within 60 days SNM (Part 70) license expiration or 70.38(d) Protection cessation of principal activities Amendment to Part 30-35 License 30.38 Radiation As Required Protection Failure of or damage to shielding, 31.5(c)(5) Radiation 5 Days (5 Day report on-off mechanism or indicator; Protection required per Byproduct detection of removable radioactive Materials License in lieu material of 30 day requirement)

Transfer of device to specific or 31.5(c)(8) Radiation 30 Days general licensee 31.5(c)(9)(i) Protection Leaking of sealed radiographic 34.27(d) Licensed 5 Days source Radiographer AP-617 Rev. 35 Page 30 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 3 of 9 EVENT REPORTS (Other than LERs) 10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Incidents involving radiographic 34.101(a) Licensed Within 30 days of equipment: Radiographer occurrence

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.

Licensee identified information which 50.9(b) Lic / Reg Prog As necessary (Note 4);

has significant implications for public 30.9(b) §70.9(b) specifies within health and safety or the common 40.9(b) two working days of defense and security 70.9(b) identifying the 71.7(b) information Change to the LOCA analysis which 50.46(a)(3) NFM&SA If 50ºF, then include in results in a change to the Peak Clad the annual report. If Temperature >50ºF, then 30 days.

Changes in QA Program which 50.54(a) NOS Before implementation reduce commitments Request for Written Information 50.54(f) As Specified As Requested Changes to Operator Requalification 50.54(i-1) Training Before Implementation Program which decreases scope, time allotted or frequency of conducting portions of the program Changes in Security Plan, Guard 50.54(p) Security Before implementation if Training and Qualification Plan, or 70.32(g) changes reduce Safeguards Contingency Plan made effectiveness of plan; without prior approval otherwise, within two months after change.

NOTE: §70.32(g) specifies within 60 days for safeguards contingency plan.

AP-617 Rev. 35 Page 31 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 4 of 9 EVENT REPORTS (Other than LERs) 10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Changes in emergency plan or 50.54(q) Emerg Prep Before implementation if implementing procedures made 50 App E(V) changes reduce without prior approval effectiveness of plan, otherwise within 30 days after change Notification of safe and stable 50.54(w)(4)(ii) Emerg Prep After attaining safe and condition of reactor and no stable condition significant risk to public health and (following an accident safety with costs >$100 million)

Cleanup plan for decontaminating 50.54(w)(4)(ii) Emerg Prep Within 30 days of reactor to permit resumption of notification that reactor operation or commencement of is in safe and stable decommissioning condition (following an accident with costs

>$100 million)

Plan for management of and 50.54(bb) Lic / Reg Prog Within 2 years after notification of significant change in cessation of operation or the proposed waste management 5 years before program (of irradiated fuel at the expiration of OL and reactor, after expiration of license after making change in and until transferred to DOE) program Filing of petition for bankruptcy (Title 50.54(cc)(1) Lic / Reg Prog Immediately following 11 of US Code) 30.34(h) filing 40.41(f) 70.32(a)(9)(i)

Notification that conformance to a 50.55a(f)(5) HESS After identifying problem certain Code required by Section XI (iii) of the ASME B&PV Code and Addenda for inservice test is impractical Determination that a pump or valve 50.55a(f)(5) HESS No later than 12 months test required by Section XI of the (iv) after expiration of initial ASME B&PV Code and Addenda is 120-month period of impractical and not included in the operation, and each revised inservice test program subsequent 120-mo.

period of operation during which the test is determined to be impractical AP-617 Rev. 35 Page 32 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 5 of 9 EVENT REPORTS (Other than LERs) 10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Notification that conformance to a 50.55a(g)(5) HESS After identifying problem certain Code required by Section XI (iii) of the ASME B&PV Code and Addenda for inservice inspection is impractical Determination that a pump or valve 50.55a(g)(5) HESS No later than 12 months test required by Section XI of the (iv) after expiration of initial ASME B&PV Code and Addenda is 120-month period of impractical and not included in the operation, and each revised inservice inspection program subsequent 120-mo.

period of operation during which the test is determined to be impractical Updated assessment of projected 50.61(b)(1) HESS After change value for RTPTS for reactor vessel beltline materials - after significant change in projected value of RT PTS or change in facilitys operating expiration date Plan for thermal annealing of reactor 50.66 HESS 3 yrs prior to date when vessel fracture toughness criteria would be exceeded Reports required as a condition of 50.71(a) As Specified As Specified in License license Telephone report in lieu of LER for 50.73(a)(1) Operations 60 Days an invalid actuation of a system listed in 50.73(a)(2)(iv)(B), other than RPS actuation when critical Reassignment of Licensed Operator 50.74(a) Operations 30 Days to position not requiring license Termination of Licensed Operator 50.74(b) Operations 30 Days Hardware and software changes that 50 App. E, Sec. Nuclear Info Within 30 days after affect transmitted data points VI.3.a Systems changes are completed identified in ERDS Data Point Library Hardware and software changes 50 App. E, Sec. Nuclear Info As soon as practicable (except data point modifications) that VI.3.b Systems and at least 30 days could affect transmission format and prior to making computer communication protocol to modification the ERDS AP-617 Rev. 35 Page 33 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 6 of 9 EVENT REPORTS (Other than LERs) 10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Test methods for supplemental 50 App. G Sec. III.B HESS Submitted and approved fracture toughness tests prior to testing Fracture Toughness 50 App G, Sec. HESS 3 years before date IV.A.1 when predicted fracture toughness will no longer satisfy App G Report of test results of specimens 50 App H, Sec. IV HESS Within One Year of withdrawn from capsules (fracture Withdrawal toughness tests)

Report of effluents released in 50 App I, Sec. IV.A Environmental Within 30 Days from end excess of one-half design objective and Chemistry of quarter (Special exposure Report required by T.S. 3.11.4 satisfies this requirement)

Reactor Building ILRT 50 App J, Option A, HESS 3 Months After Test Sec. V.B (No time specified in TS 4.6.1.2 regulation or TS)

Certification of Medical Fitness 55.23 Training Upon Application 55.31 Incapacitation Because of Disability 55.25 Operations 30 Days after learning of or Illness 50.74(c) 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 55.53(g) Operations/ 30 Days Operator 73.71(b) Security Application for Operator License 55.57 Training As necessary Renewal Reports of Conditions of Part 70 70.32(b)(5) Security As specified in license License 75.36 Changes in plan for Physical 70.32(d) Security 2 Months Protection of SNM in transit made without prior approval AP-617 Rev. 35 Page 34 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 7 of 9 EVENT REPORTS (Other than LERs) 10 CFR Reference RESP TIMING OF SUBJECT or (other) UNIT RESPONSE Accident notification report required 71.5(a)(1)(iv) Radiation Carrier is to provide by DOT on transportation of licensed 49CFR171.15 & 16 Protection notice to DOT at the material earliest practicable moment and written follow-up within 30 days Transportation Package Information 71.12(c)(3) Radiation Before first use 71.101(f) Protection (Note 1)

Deviations related to Type B 71.95 Radiation Within 30 days (NOTE:

package for transport of radioactive Protection requirement is for material, specifically: licensee to report)

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 Advance notification of shipment of 71.97(a) Radiation Before shipment Irradiated Fuel, Nuclear Waste, or 73.37(b)(1) Protection (Note 2) certain shipments of SNM 73.72(a) 73.73(a) 73.74(a)

Revision notice or cancellation 71.97(e) Radiation Upon change/

notice for shipment of irradiated fuel, 71.97(f) Protection cancellation nuclear waste, or certain shipments 73.37(f) (Note 2) of SNM 73.72(a)(5) 73.73(b) 73.74(b)

Advance Notice and Approval of 73.37(b)(7) Radiation Before shipment Routes for Shipment of Irradiated 73.37(f) Protection & (Note 2)

Fuel Nuclear Operations Theft or unlawful diversion or 73.71 Security As required (See also attempted theft or unlawful diversion 74.11 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months notifications and of SNM or spent fuel 150.16(b) SEC-NGGC-2147)

AP-617 Rev. 35 Page 35 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 4 Sheet 8 of 9 EVENT REPORTS (Other than LERs)

SUBJECT 10 CFR Reference RESP TIMING OF or (other) UNIT RESPONSE Results of Trace Investigation of 73.71(a)74.11 Security 30 Days Lost or Unaccounted for Shipment of SNM Threat to or reduced effectiveness of 73.71(d) Security 30 Days physical security (See also 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months notifications and SEC-NGGC-2147)

Nuclear Material Transfer (old Form 74.15(a) HESS Whenever transfer DOE/NRC-741) 40.64(a) occurs 70.54 (Note 6) 150.16(a) 150.17(a)

Earthquake exceeding Operating 100 App. A, Sec. HESS Prior to resuming Basis Earthquake values V(A)(2) operations Import or export of nuclear 110 Radiation Varies; see Part 110 equipment or material Protection Bodily injury or property damage 140.6(a) Radiation As promptly as practical from possession or use of Protection radioactive material resulting in an indemnity claim Change in proof of financial 140.15(e) Treasury Promptly protection or other financial information filed with the NRC Termination of liability insurance 140.17(b) Treasury At least 30 days prior to policy used for financial protection termination (notification of renewal or other proof of financial protection)

Failure of High Integrity Container or PLP-300 Radiation Within 30 days of Notification of Misuse of a High Protection knowledge of the Integrity Container incident Cooling Tower Beacon Outage FAA Advisory Operations Upon Discovery greater than 30 minutes or Circular AC restoration from an outage greater 70/7460-1K 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]

Level of radioactivity in onsite CHE-NGGC-0057 Environmental Within 30 days of groundwater, exceeding the and Chemistry discovery reporting levels of ODCM O.R. Table 3.12-2 for drinking water.

AP-617 Rev. 35 Page 36 of 49

2014 NRC SRO Question 98 (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 353801N, longitude 785723W 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 37 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 5 Sheet 1 of 2 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)

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 38 of 49

2014 NRC SRO Question 98 (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 39 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 6 Sheet 1 of 1 SAMPLE WORKSHEET 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 FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #

Harris Nuclear Plant 1 John Caves (919) 362-3636 15:43 EDT EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER 14:33 EDT 09/18/2003 100% Power, Mode 1 100% Power, Mode 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AINC SIT/AAEC ALERT (i) TS Required S/D ASHU (v)(D) Accident Mitigation AIND ALE/AAEC SAMPLE 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/Resp ACOM X

ARPS PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

Invalid Specified System Actuation AINV MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10CFR 50.72(b)(3)

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 NRC RESIDENT X NOT UNDERSTOOD?

STATE(s) X DID ALL SYSTEMS X YES NO LOCAL X FUNCTION AS REQUIRED?

OTHER GOV AGENCIES X ADDITIONAL INFO ON BACK MODE OF OPERATION ESTIMATE FOR MEDIA/PRESS RELEASE X UNTIL CORRECTED: 1 RESTART DATE:

YES X NO AP-617 Rev. 35 Page 40 of 49

2014 NRC SRO Question 98 (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 FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #

Harris Nuclear Plant 1 919 -

EST / EDT EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER EST / EDT EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AINC SIT/AAEC ALERT (i) TS Required S/D ASHU (v)(D) Accident Mitigation AIND ALE/AAEC 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) (xiii) Loss Comm/Asmt/Resp ACOM ARPS PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

Invalid Specified System Actuation AINV MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10CFR 50.72(b)(3)

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 NRC RESIDENT NOT UNDERSTOOD?

STATE(s) DID ALL SYSTEMS YES NO LOCAL FUNCTION AS REQUIRED?

OTHER GOV AGENCIES ADDITIONAL INFO ON BACK MODE OF OPERATION ESTIMATE FOR MEDIA/PRESS RELEASE UNTIL CORRECTED: RESTART DATE: YES NO AP-617 Rev. 35 Page 41 of 49

2014 NRC SRO Question 98 (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. HOO GUIDE Total Activity (Ci) % T. S. LIMIT HOO GUIDE LIMIT 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 10 uCi/min 0.1 Ci dissolved noble gases)

Liquid (tritium) 0.2 Ci/min 5 Ci Total Activity PLANT STACK CONDENSER/AIR MAIN STEAM SG OTHER EJECTOR LINE BLOWDOWN 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 42 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 8 Sheet 1 of 6 Reportability Evaluation (REW) Worksheet Notification Requirements Per 10CFR50.73 Reports NCR-(Ref. NUREG-1022)

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 43 of 49

2014 NRC SRO Question 98 (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 Reportable Event condition?

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 44 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 8 Sheet 3 of 6 Situation meets this Reportable Event condition?

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 45 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 8 Sheet 4 of 6 Situation meets this Reportable Event condition?

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 46 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 8 Sheet 5 of 6 Situation meets this Reportable Event condition?

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 47 of 49

2014 NRC SRO Question 98 (23) Reference Attachment 8 Sheet 6 of 6 III. Reportable Evaluation 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 48 of 49

2014 NRC SRO Question 98 (23) Reference Revision 35 Summary Rev 35 processed with PRR 337339 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 Notification time block and Event Time & Zone block.

AP-617 Rev. 35 Page 49 of 49

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

ML14338A038

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