Text

Wb 2019-301, SRO Written Exam (Delayed Release)
	ML19256B478
Person / Time
Site:	Watts Bar
Issue date:	09/13/2019
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/19-301, 50-391/19-301 50-390/OL-19, 50-391/OL-19
	Download: ML19256B478 (30)
	v • d • e

ML19256B478

87.

A.

Containment CSF - RED entry conditions met.

OR B.

Containment Hydrogen concentration greater than 4% by volume.

OR C.

1.

Containment pressure greater than 2.8 PSIG (Phase B)

AND 2.

Less than one full train of Containment Spray is operating per design for 15 minutes or longer.

HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.

HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).

Definitions RUPTURED: The condition of a steam generator in which primary-to-secondary leakage is of sufficient magnitude to require a safety injection.

IMMINENT: The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.

EXPLOSION: A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical reaction or over pressurization. A release of steam (from high energy lines or components) or an electrical component failure (caused by short circuits, grounding, arcing, etc.) should not automatically be considered an explosion. Such events may require a post-event inspection to determine if the attributes of an explosion are present.

SECURITY CONDITION: Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.

UNPLANNED: A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant transient. The cause of the parameter change may be known or unknown.

VISIBLE DAMAGE: Damage to a SAFETY SYSTEM train that is readily observable without measurements, testing, or analysis. The visual impact of the damage is sufficient to cause concern regarding the operability or reliability of the affected SAFETY SYSTEM train.

FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES.

Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.

HOSTILE FORCE: One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.

UNISOLABLE: An open or breached system line that cannot be isolated, remotely or locally.

FAULTED: The term applied to a steam generator that has a leak on the secondary side of sufficient size to cause an uncontrolled drop in steam generator pressure or the steam generator being completely depressurized.

PROTECTED AREA: The area which is encompassed by the security fence and to which access is controlled.

OWNER CONTROLLED AREA: The TVA-owned site property under the control of Site Security.

REFUELING PATHWAY: The reactor refueling cavity, spent fuel pool, or fuel transfer canal.

SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.

CONFINEMENT BOUNDARY: Spent Fuel Storage Canister consisting of Multi-Purpose Canister (MPC) shell, bottom base plate, MPC lid (including the vent and drain port cover plates), MPC closure ring, and associated welds.

FS1 - Loss or Potential Loss of ANY Two Barriers A.

ANY condition in the opinion of the Emergency Director that indicates Loss of the Containment Barrier.

A.

ANY condition in the opinion of the Emergency Director that indicates Potential Loss of the Containment Barrier.

A.

ANY condition in the opinion of the Emergency Director that indicates Loss of the Fuel Clad Barrier.

A.

ANY condition in the opinion of the Emergency Director that indicates Potential Loss of the Fuel Clad Barrier.

A. ANY condition in the opinion of the Emergency Director that indicates Loss of the RCS Barrier.

A.

ANY condition in the opinion of the Emergency Director that indicates Potential Loss of the RCS Barrier.

5.

Other Indications (Not Applicable) 6.

SED Judgment (1) Reading on ANY of the following radiation monitors greater than the reading shown for 15 minutes or longer:

OR (2) Dose assessment using actual meteorology indicates doses greater than 1,000 mrem TEDE or 5,000 mrem thyroid CDE at or beyond the site boundary.

OR (3) Field survey results indicate EITHER of the following at or beyond the site boundary:

Closed window dose rates greater than 1,000 mR/hr expected to continue for 60 minutes or longer.

Analyses of field survey samples indicate thyroid CDE greater than 5,000 mrem for one hour of inhalation.

EU1 -

Damage to a loaded canister CONFINEMENT BOUNDARY ALL MODES (1) Reading on ANY of the following radiation monitors greater than the reading shown for 15 minutes or longer:

OR (2) Dose assessment using actual meteorology indicates doses greater than 100 mrem TEDE or 500 mrem thyroid CDE at or beyond the site boundary.

OR (3) Field survey results indicate EITHER of the following at or beyond the site boundary:

Closed window dose rates greater than 100 mR/hr expected to continue for 60 minutes or longer.

Analyses of field survey samples indicate thyroid CDE greater than 500 mrem for one hour of inhalation.

(1) Reading on ANY of the following radiation monitors greater than the reading shown for 15 minutes or longer:

OR (2) Dose assessment using actual meteorology indicates doses greater than 10 mrem TEDE or 50 mrem thyroid CDE at or beyond the site boundary.

OR (3) Analysis of a liquid effluent sample indicates a concentration or release rate that would result in doses greater than 10 mrem TEDE or 50 mrem thyroid CDE at or beyond the site boundary for one hour of exposure.

OR (4) Field survey results indicate EITHER of the following at or beyond the site boundary:

Closed window dose rates greater than 10 mR/hr expected to continue for 60 minutes or longer.

Analyses of field survey samples indicate thyroid CDE greater than 50 mrem for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of inhalation.

SS1 - Loss of all offsite and all onsite AC power to 6.9KV Shutdown Boards for 15 minutes or longer.

The SED should declare the Site Area Emergency promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

SS5 - Inability to shutdown the reactor causing a challenge to core cooling or RCS heat removal. MODE 1 (1) a. An automatic or manual trip did not shutdown the reactor.

AND

b. All manual actions to shutdown the reactor have been unsuccessful.

AND

c. EITHER of the following conditions exist:

Core Cooling CSF - RED Heat Sink CSF - RED NATURAL / DESTRUCTIVE FIRE/ CR EVACUATION TOXIC / FLAMMABLE SECURITY SED DISCRETION SYSTEM MALFUNCTIONS HAZARDS (1) Damage to a loaded canister CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading at the location specified in Table I-1 - ISFSI Dose Limits.

FISSION PRODUCT BARRIERS WATTS BAR HOT INITIATING CONDITIONS - MODES 1 3 - 4 NOTE: Multiple events could occur which result in the conclusion that exceeding the loss or potential loss thresholds is IMMINENT.

In IMMINENT loss situations use judgment and classify as if the thresholds are exceeded HG1 - HOSTILE ACTION resulting in loss of physical control of the facility.

(1) a. A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the Security Shift Supervisor.

AND

b. EITHER of the following has occurred:

1. ANY of the following safety functions cannot be controlled or maintained:

Reactivity control Core cooling RCS heat removal OR

2. Damage to spent fuel has occurred or is IMMINENT.

HG7 - Other conditions exist which in the judgment of the SED warrant declaration of a General Emergency.

(1) Other conditions exist which in the judgment of the SED indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

HS6 - Inability to control a key safety function from outside the Control Room.

(1) a. An event has resulted in plant control being transferred from the Control Room to the Auxiliary Control Room.

AND

b. Control of ANY of the following key safety functions is not reestablished within 15 minutes:

Reactivity control Core cooling RCS heat removal HS7 - Other conditions exist which in the judgment of the SED warrant declaration of a Site Area Emergency.

(1) Other conditions exist which in the judgment of the SED indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or, (2) that prevent effective access to equipment needed for the protection of the public.

Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

HS1 - HOSTILE ACTION within the PROTECTED AREA.

(1) A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the Security Shift Supervisor.

HA5 - Gaseous release impeding access to equipment necessary for normal plant operations, cooldown or shutdown.

If the equipment in the listed room or area was already inoperable or out of service before the event occurred, then no emergency classification is warranted.

(1) a. Release of a toxic, corrosive, asphyxiant or flammable gas into any Table H1 plant rooms or areas.

AND

b. Entry into the room or area is prohibited or impeded.

HA1 - HOSTILE ACTION within the OWNER CONTROLLED AREA OR Airborne attack threat within 30 minutes.

(1) A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the Security Shift Supervisor.

OR (2) A validated notification from NRC of an aircraft attack threat within 30 minutes of the site.

HA6 - Control Room evacuation resulting in transfer of plant control to alternate locations.

(1) An event has resulted in plant control being transferred from the Control Room to the Auxiliary Control Room.

HA7 - Other conditions exist which in the judgment of the SED warrant declaration of an Alert.

(1) Other conditions exist which in the judgment of the SED indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

HU2 - Seismic event greater than OBE levels.

(1) Seismic event greater than Operating Basis Earthquake (OBE) as indicated by Alarm Window 166-D, OBE SPECTRA EXCEEDED lit.

(1) a. A FIRE is NOT extinguished within 15 minutes of ANY of the following FIRE detection indications:

Report from the field (that is, visual observation).

Receipt of multiple (more than 1) fire alarms or indications.

Field verification of a single fire alarm.

AND

b. The FIRE is located within ANY Table H2 plant areas.

OR (2) a. Receipt of a single fire alarm (that is, no other indications of a FIRE).

AND

b. The FIRE is located within ANY Table H2 plant areas.

AND

c. The existence of a FIRE is not verified within 30-minutes of alarm receipt.

OR (3) A FIRE within the plant PROTECTED AREA not extinguished within 60-minutes of the initial report, alarm or indication.

OR (4) A FIRE within the plant PROTECTED AREA that requires firefighting support by an offsite fire response agency to extinguish.

HU4 - FIRE potentially degrading the level of safety of the plant.

The Emergency Director should declare the Unusual Event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

HU1 - Confirmed SECURITY CONDITION or threat.

HU7 - Other conditions exist which in the judgment of the SED warrant declaration of an NOUE.

(1) Other conditions exist which in the judgment of the SED indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

SG1 - Prolonged loss of all offsite and all onsite AC power to 6.9KV Shutdown Boards.

SS8 - Loss of ALL Vital DC Power for 15 minutes or longer.

(1) Indicated voltage is less than 105 VDC on ALL 125 VDC vital battery boards I, II, III, and IV for 15 minutes or longer.

SA5 - Automatic or manual trip fails to shutdown the reactor, and subsequent manual actions taken in the MCR are not successful in shutting down the reactor. MODE 1 (1) a. An automatic or manual trip did not shutdown the reactor.

AND b.Manual actions taken in the MCR are not successful in shutting down the reactor.

SA2 - UNPLANNED loss of Control Room indications for 15 minutes or longer with a significant transient in progress.

(1) a.

An UNPLANNED event results in the inability to monitor one or more of the following parameters from within the Control Room for 15 minutes or longer:

Reactor Power Pressurizer Level RCS Pressure Core Exit Temperature Level in at least one steam generator Steam Generator Aux. Feed Water Flow AND

b. ANY of the following transient events in progress:

Automatic or manual runback greater than 25% thermal reactor power Electrical load rejection greater than 25% full electrical load Reactor trip SI actuation (1) a. AC power capability is reduced to a single power source for 15 minutes or longer to EITHER:

1A and 1B 6.9KV Shutdown Boards

2A and 2B 6.9 KV Shutdown Boards AND

b. Any additional single power source failure will result in loss of ALL AC power to SAFETY SYSTEMS.

The SED should declare the Alert promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

SA1 - Loss of ALL but one AC power source to 6.9KV Shutdown Boards for 15 minutes or longer.

(1) Loss of ALL offsite AC power capability for 15 minutes or longer to EITHER:

1A and 1B 6.9 KV Shutdown Boards

2A and 2B 6.9 KV Shutdown Boards The SED should declare the Unusual Event promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

SU1 - Loss of ALL offsite AC power capability to 6.9KV Shutdown Boards for 15 minutes or longer.

SU2 - UNPLANNED loss of Control Room indications for 15 minutes or longer.

(1) An UNPLANNED event results in the inability to monitor one or more of the following parameters from within the Control Room for 15 minutes or longer:

Reactor Power Pressurizer Level RCS Pressure Core Exit Temperature Level in at least one steam generator Steam Generator Auxiliary Feed Water Flow The SED should declare the Unusual Event promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

SU3 - Reactor Coolant activity greater than TS allowable limits. MODES 1 and 2, and MODE 3 with RCS average temperature (Tavg) 500°F (1) Reactor coolant sample analysis results indicate ANY of the following:

Dose equivalent Iodine (I-131) greater than 0.265 µCi/gm for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

Dose Equivalent Iodine (I-131) greater than 14 µCi/gm.

RCS gross specific activity greater than 100/ µCi/gm.

SU4 - RCS Leakage for 15 minutes or longer.

(1) RCS unidentified or pressure boundary leakage greater than 10 gpm for 15 minutes or longer.

OR (2) RCS identified leakage greater than 25 gpm for 15 minutes or longer.

OR (3) Leakage from the RCS to a location outside containment greater than 25 gpm for 15 minutes or longer.

SU6 - Loss of all onsite or offsite communications capabilities.

The SED should declare the General Emergency promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

FG1 - Loss of ANY Two Barriers AND Loss or Potential Loss of Third Barrier FA1 - ANY Loss or ANY Potential Loss of EITHER Fuel Clad OR RCS Barrier Potential Loss Containment Barrier Not applicable Note: Containment High Range Radiation Monitors (HRRMs) are temperature sensitive and can be affected by both temperature induced currents and insulation resistance temperature effects. Following the initial increase in containment temperature the HRRM monitors can give erratic indication for up to 1 minute.

Steady state temperature effects on cable insulation resistance for the HRRM signal cable is dependent on containment temperature and could result in a shift in monitor output indication. (Caution:

Should the containment air return fans not start, containment temperatures could remain elevated resulting in potential false HRRM indicated readings.)

Loss A.

Containment radiation monitor reading greater than:

5.600 E+03 R/hr on 1-RM-90-271 or 272 OR 4.470 E+03 R/hr on 1-RM-90-273 or 274 OR 7.160 E+03 R/hr on 2-RM-90-271 or 272 OR 4.750 E+03 R/hr on 2-RM-90-273 or 274 Potential Loss Fuel Clad Barrier A.

Containment radiation monitor reading greater than:

3.320 E+02 R/hr on 1-RM-90-271 or 272 OR 2.650 E+02 R/hr on 1-RM-90-273 or 274 OR 3.790 E+02 R/Hr on 2-RM-90-271 or 272 OR 2.520 E+02 R/hr on 2-RM-90-273 or 274 OR B.

Coolant activity is greater than 300 µCi/gm dose equivalent I-131.

Not applicable Loss Potential Loss Loss Not applicable RCS Barrier A.

Containment radiation monitor reading greater than:

9.800 E+01 R/hr on 1-RM-90-271 or 272 OR 6.200 E+01 R/hr on 1-RM-90-273 or 274 OR 1.190 E+02 R/hr on 2-RM-90-271 or 272 OR 6.400 E+01 R/hr on 2-RM-90-273 or 274 A. Core Cooling CSF - RED Entry Conditions Met.

A. Core Cooling CSF -

ORANGE Entry Conditions Met.

OR B. Heat Sink CSF - RED Entry Conditions Met (If heat sink required).

A. Heat Sink CSF - RED Entry Conditions Met (If heat sink required).

1. RCS or SG Tube Leakage Not Applicable A. Core Cooling CSF -

ORANGE entry conditions met.

A.

An automatic or manual SI actuation is required by EITHER of the following:

1. UNISOLABLE RCS leakage OR

2. SG tube RUPTURE.

A.

Operation of a standby charging pump is required by EITHER of the following:

1. UNISOLABLE RCS leakage OR

2. SG tube leakage.

OR B. PTS CSF - RED entry conditions met.

A. A leaking or RUPTURED SG is FAULTED outside of containment.

Not Applicable

2. Inadequate Heat Removal Not Applicable Not Applicable A. Core Cooling CSF - RED entry conditions met for 15 minutes or longer.

3. RCS Activity / Containment Radiation The SED should declare the General Emergency promptly upon determining that 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months has been exceeded, or will likely be exceeded.

SG8 - Loss of all AC and Vital DC power sources for 15 minutes or longer.

(1) a.

Loss of ALL offsite and ALL onsite AC power for 15 minutes or longer to EITHER:

1A and 1B 6.9 KV Shutdown Boards

2A and 2B 6.9 KV Shutdown Boards AND

b. Indicated voltage is less than 105 VDC on ALL 125 VDC vital battery boards I, II, III, and IV for 15 minutes or longer.

The SED should declare the Site Area Emergency promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

The SED should declare the Alert promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.

SA9 - Hazardous event affecting SAFETY SYSTEMS needed for the current operating mode.

SU5 - Automatic or manual trip fails to shutdown the reactor. MODE 1 SU7 - Failure to isolate containment or loss of containment pressure control.

HU3 - Hazardous event.

(1) A tornado strike within the PROTECTED AREA.

OR (2) Internal room or area flooding of a magnitude sufficient to require manual or automatic electrical isolation of a SAFETY SYSTEM component needed for the current operating mode.

OR (3) Movement of personnel within the PROTECTED AREA is impeded due to an offsite event involving hazardous materials (for example, an offsite chemical spill or toxic gas release).

OR (4) A hazardous event that results in on-site conditions sufficient to prohibit the plant staff from accessing the site via personal vehicles.

OR (5) River reservoir level 673 feet as reported by River Operations.

OR (6) River Reservoir level at Stage I Flood Warning as reported by River Operations.

The SED should declare the Site Area Emergency promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents.

A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.

A.

Containment isolation is required AND EITHER of the following:

1. Containment integrity has been lost based on SED judgment.

OR

2. UNISOLABLE pathway from the containment to the environment exists.

OR B.

Indications of RCS leakage outside of containment.

Not applicable Not applicable Not applicable Not applicable ISFSI ATWS/RCS PARAMETERS /

SAFETY SYSTEMS ELECTRICAL /

CONTAINMENT COMMUNICATIONS /

MCR INDICATIONS RS2 - Spent fuel pool level at 724.94.

RADIOLOGICAL EFFLUENTS RA2 - Significant lowering of water level above, or damage to, irradiated fuel.

(1) Uncovery of irradiated fuel in the REFUELING PATHWAY.

OR (2) Damage to irradiated fuel resulting in a release of radioactivity from the fuel as indicated by alarm or elevated reading on ANY of the following radiation monitors:

OR (3) Lowering of spent fuel pool level to 734.44.

RS1 - Release of gaseous radioactivity resulting in offsite dose greater than 100 mrem TEDE or 500 mrem thyroid CDE.

RG1 - Release of gaseous radioactivity resulting in offsite dose greater than 1,000 mrem TEDE or 5,000 mrem thyroid CDE.

RA1 - Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE.

The SED should declare the Site Area Emergency promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes.

If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

RA3 - Radiation levels that impede access to equipment necessary for normal plant operations, cooldown or shutdown.

RU1 - Release of gaseous or liquid radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.

The SED should declare the Unusual Event promptly upon determining that 60 minutes has been exceeded, or will likely be exceeded.

If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 60 minutes.

If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

(1) Reading on ANY Table R1 effluent radiation monitor greater than listed values for 60 minutes or longer.

OR (2) Reading on ANY effluent radiation monitor greater than 2 times the alarm setpoint established by a current Liquid/Gaseous Release Permit for 60 minutes or longer.

OR (3) Sample analysis for a gaseous or liquid release indicates a concentration or release rate greater than 20 times the Effluent Concentration Limit for 60 minutes or longer.

RU2 - UNPLANNED loss of water level above irradiated fuel.

(1) a. UNPLANNED water level drop in the REFUELING PATHWAY as indicated by ANY of the following:

SFP Level HI/LO annunciator lit (128-A) AND SFP level less than 748' as indicated by 0-LI-78-42 and 0-LI-78-43.

Visual observation by plant personnel.

AND b.UNPLANNED rise in area radiation levels as indicated by ANY of the following radiation monitors:

The SED should declare the General Emergency promptly upon determining that 60 minutes has been exceeded, or will likely be exceeded.

RG2 - Spent fuel pool level cannot be restored to at least 724.94 for 60 minutes or longer.

(1)

Spent fuel pool level cannot be restored to at least 724.94' for 60 minutes or longer.

(1)

Lowering of spent fuel pool level to 724.94'.

The SED should declare the Alert promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes.

If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until results from a dose assessment using actual meteorology are available.

If the equipment in the listed room or area was already inoperable or out of service before the event occurred, then no emergency classification is warranted.

ALERT SITE AREA EMERGENCY The SED should declare the General Emergency promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes.

If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

GENERAL EMERGENCY NATURAL / DESTRUCTIVE (1) a. An automatic trip did not shutdown the reactor.

AND

b. A subsequent manual action taken in the MCR is successful in shutting down the reactor.

OR (2) a. A manual trip did not shutdown the reactor.

AND

b. EITHER of the following:

A subsequent manual action taken in the MCR is successful in shutting down the reactor.

A subsequent automatic trip is successful in shutting down the reactor.

If the affected SAFETY SYSTEM train was already inoperable or out of service before the hazardous event occurred, then this emergency classification is not warranted.

If the hazardous event only resulted in VISIBLE DAMAGE, with no indications of degraded performance to at least one train of a SAFETY SYSTEM, then this emergency classification is not warranted.

(1) A SECURITY CONDITION that does not involve a HOSTILE ACTION as reported by the Security Shift Supervisor.

OR (2) Notification of a credible security threat directed at WBN.

OR (3) A validated notification from the NRC providing information of an aircraft threat.

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY (1) Loss of ALL Table C3 Onsite communications capability affecting the ability to perform routine operations.

OR (2) Loss of ALL Table C3 Offsite communication capability affecting the ability to perform offsite notifications.

OR (3) Loss of ALL Table C3 NRC communication capability affecting the ability to perform NRC notifications.

EPIP-1 R51, Attachment 1 WBN Hot Condition ICs/EALs (1) a. Failure of containment to isolate when required by an actuation signal.

AND

b. ALL required penetrations are not closed within 15 minutes of the actuation signal.

OR (2) a. Containment pressure greater than 2.8 psig (Phase B).

AND

b. Less than one full train of Containment Spray is operating per design for 15 minutes or longer.

4.

Containment Integrity or Bypass 0-RM-90-101 0-RM-90-102 0-RM-90-103 1,2-RM-90-112A or B Aux Building Vent Gas Monitor Fuel Pool Unit 2 Side Fuel Pool Unit 1 Side Upper Containment, (A-Particulate, B-Gas) 1,2-RM-90-130 or 131 Containment Purge Exhaust y = gamma 0n1 = neutron Hi Storm FW Location COC 1032 Amendment 0 Top of the OVERPACK Side of the OVERPACK Table I ISFSI Dose Limits 60 mR/hr ( + 0n1) 600 mR/hr ( + 0n1)

Table H1 -

Safe Operation & Shutdown Rooms/Areas Aux. BLDG.

Elevation Room MODE Elev 772 Electrical Board Room 1A 3, 4, 5 Electrical Board Room 1B 3, 4, 5 Electrical Board Room 2A 3, 4, 5 Electrical Board Room 2B 3, 4, 5 Elev 757 6.9 KV and 480V SD Bd Room A 3, 4, 5 6.9 KV and 480V SD Bd Room B 3, 4, 5 Elev 713 1A RHR HX Room 3, 4, 5 1B RHR HX Room 3, 4, 5 2A RHR HX Room 3, 4, 5 2B RHR HX Room 3, 4, 5 CCS Pump Area 3, 4, 5 Elev 676 1A RHR Pump Room 3, 4, 5 1B RHR Pump Room 3, 4, 5 2A RHR Pump Room 3, 4, 5 2B RHR Pump Room 3, 4, 5 (1) a. The occurrence of ANY of the following hazardous events:

Seismic event (earthquake)

Internal or external flooding event

High winds or tornado strike

FIRE

EXPLOSION

River reservoir level less than 666 feet as reported by River Operations

River reservoir level at Stage II flood warning as reported by River Operations

Other events with similar hazard characteristics as determined by the SED AND

b. 1. Event damage has caused indications of degraded performance on one train of a SAFETY SYSTEM needed for the current operating mode.

AND

2. EITHER of the following:

Event damage has caused indications of degraded performance to a second train of the SAFETY SYSTEM needed for the current operating mode, or

Event damage has resulted in VISIBLE DAMAGE to a second train of the safety system needed for the current operating mode.

Table H2 Fire Areas Reactor Building Auxiliary Building Turbine Building IPS Control Building Diesel Generator Bldgs.

Table C3 Communications Capability System Onsite Offsite NRC Plant Radio X

Plant Page X

All telephone Lines (Private and Commercial)

X X

X ENS - Emergency X

X HPN - Health Physics X

X Satellite Phones X

X Network Notification System 0-RM-90-101 Aux Building Vent Gas Monitor 0-RM-90-102 Fuel Pool Unit 2 Side 0-RM-90-103 Fuel Pool Unit 1 Side 1, 2-RM-90 -130 or 131 Containment Purge Exhaust 1, 2-RM 112 A or B Upper Containment, (A-Particulate, B -Gas)

Loss Potential Loss Loss Potential Loss Loss Potential Loss Fuel Clad Barrier RCS Barrier Containment Barrier (1) Dose rate greater than 15 mR/hr in EITHER of the following areas requiring continuous occupancy:

Control Room (0-RM-90-135)

Central Alarm Station (by survey)

OR (2) An UNPLANNED event results in radiation levels that prohibit or impede access to any Table H1 plant rooms or areas. (Modes 3, 4, & 5)

(1) Loss of ALL offsite and ALL onsite AC power for 15 minutes or longer to EITHER of the following:

1A and 1B 6.9 KV Shutdown Boards

2A and 2B 6.9 KV Shutdown Boards 1.a. Loss of ALL offsite and ALL onsite AC power to EITHER of the following:

1A and 1B 6.9 KV Shutdown Boards

2A and 2B 6.9 KV Shutdown Boards.

AND

b. EITHER of the following:

Restoration of at least one AC emergency bus in less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is not likely.

Core Cooling CSF - RED.

(1) These unit values are based on flow rates through one PORV of 970,000 lb/hr at 1185 psig, 600 degrees F. Before using these values, ensure a release to the environment is ongoing (e.g., PORV).

The SED should declare the Unusual Event promptly upon determining that 15 minutes has been exceeded, or will likely be exceeded.

UNUSUAL EVENT 3/3 FG1 - Loss of ANY Two Barriers AND Loss or Potential Loss of Third Barrier YES FS1 - Loss or Potential Loss of ANY Two Barriers 1/2 FA1 - ANY Loss or ANY Potential Loss of EITHER Fuel Clad OR RCS Barrier 2/3 (1) These unit values are based on flow rates through one PORV of 970,000 lb/hr at 1185 psig, 600 degrees F.

Before using these values, ensure a release to the environment is ongoing (e.g., PORV).

NOTE:

Refer to SA9 under the RCS Parameter /Safety Systems Column Under System Malfunctions to evaluate System Damage.

No Loss of at least 2 Barriers?

Shield Building Exhaust, 1-RM-90-400 UNIT 1 UNIT 2 Condenser Vacuum Exhaust, 1-RM-90-256 SG Discharge, 1-RM-90-421 thru -424 (1)

Shield Building Exhaust, 2-RM-90-400 SG Discharge, 2-RM-90-421 thru -424 (1)

Condenser Vacuum Exhaust, 2-RM-90-256 1.90 E +08 Ci/s 5.32 E +05 mR/hr 1.01 E +04 mR/hr 1.90 E +08 Ci/s 6.37 E +03 mR/hr 7.10 E +05 mR/hr UNIT 2 Shield Building Exhaust, 1-RM-90-400 UNIT 1 Auxiliary Building Vent, 0-RM-90-101B Condenser Vacuum Exhaust, 1-RM-90-256 SG Discharge, 1-RM-90-421 thru -424 (1)

Shield Building Exhaust, 2-RM-90-400 Auxiliary Building Vent, 0-RM-90-101B SG Discharge, 2-RM-90-421 thru -424 (1)

Condenser Vacuum Exhaust, 2-RM-90-256 1.90 E +07 Ci/s 3.25 E +06 cpm 5.32 E +04 mR/hr 1.01 E +03 mR/hr 1.90 E +07 Ci/s 3.25 E +06 cpm 6.37 E +02 mR/hr 7.10 E +04 mR/hr Table R1 Gaseous Effluent Shield Building Exhaust, 1,2 - RM 400 1.95 E+05 µCi/s Auxiliary Building Vent, 0 - RM 101B 3.33 E+04 cpm Service Building Vent, 0 - RM 132B 9.38 E+05 cpm Condenser Vacuum Exhaust, 1 - RM 255/256 5.46 E+02 mR/hr Condenser Vacuum Exhaust, 2 - RM 255 7.12 E+02 mR/hr Condenser Vacuum Exhaust, 2 - RM 256 7.29 E+02 mR/hr RRRI ICS Screen SG Discharge 1-RM-90-421 thru -424(1) 1.04 E+01 mR/hr Table R1 ICS Screen 4RM2 Liquid Effluent - Cond Demin in use Radwaste Monitor, 0 -RM 122 1.42 E+06 cpm SGBD, 1-RM-90-120/121 8.13 E+05 cpm SGBD, 2-RM 120/121 4.73 E+05 cpm Condensate Demin, 0-RM-90-225 1.42 E+06 cpm Turbine Bldg Sump, 0 -RM-90-212 9.32 E+03 cpm Liquid Effluent - S/G Blowdown - NO Treatment or Dilution Radwaste Monitor, 0 -RM 122 4.50 E+04 cpm SGBD, 1-RM-90-120/121 4.50 E+04 cpm SGBD, 2 -RM-90-120/121 1.93 E+04 cpm Condensate Demin, 0 -RM 225 4.50 E+04 cpm Turbine Bldg Sump, 0 -RM 212 6.21 E+04 cpm Liquid Effluent -

Radwaste Monitor, 0-RM-90-122 3.73 E+06 cpm SGBD, 1-RM-90-120/121 2.14 E+06 cpm SGBD, 2-RM-90-120/121 9.20 E+05 cpm Condensate Demin, 0 -RM 225 3.73 E+06 cpm Turbine Bldg Sump, 0 - RM-90-212 2.58 E+04 cpm Cond Demin NOT in use, SGBD with Dilution Shield Building Exhaust, 1-RM-90-400 UNIT 1 UNIT 2 Auxiliary Building Vent, 0-RM-90-101B Condenser Vacuum Exhaust, 2-RM-90-255 Condenser Vacuum Exhaust, 1-RM-90-255/256 SG Discharge, 1-RM-90-421 thru -424 (1)

Shield Building Exhaust, 2-RM-90-400 Auxiliary Building Vent, 0-RM-90-101B SG Discharge, 2-RM-90-421 thru -424 (1)

Condenser Vacuum Exhaust, 2-RM-90-256 Service Building Vent, 0-RE-90-132B 1.90 E +06 Ci/s 3.25 E +05 cpm 5.32 E +03 mR/hr 1.01 E +02 mR/hr 1.90 E +06 Ci/s 3.25 E +05 cpm 6.93 E +03 mR/hr 6.37 E +01 mR/hr 7.10 E +03 mR/hr 9.14 E +06 cpm Service Building Vent, 0-RM-90-132B 9.14 E +06 cpm

Answer Key

ML19256B478

Text

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