DCL-09-020, Updated Emergency Plan Implementing Procedures
| ML090990433 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/30/2009 |
| From: | Persky M Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DCL-09-020 | |
| Download: ML090990433 (124) | |
Text
PacificGas and ElectricCompany' Diablo Canyon Power Plant P.0. Box 56 Avila Beach, CA 93424 March 30, 2009 PG&E Letter DCL-09-020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Emergency Plan Implementing Procedure Update
Dear Commissioners and Staff:
In accordance with Section V, "Implementing Procedures," of 10 CFR 50, Appendix E, enclosed are updated Emergency Plan (E-Plan) Implementing Procedures (EPIPs) for Diablo Canyon Power Plant, Units 1 and 2, as indicated in the Enclosure.
As provided under 10 CFR 50.54(q), the changes have been made without prior NRC approval since they do not decrease the effectiveness of the E-Plan. The revised EPIPs continue to meet the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E. The procedure changes are identified by revision bars in the right margin.
This update does not contain privacy/proprietary information in accordance with NRC Generic Letter 81-27. There are no new commitments in this submittal.
If there are questions regarding this update, please contact me at (805) 545-6275.
Sincerely, Mark S. ersky Manager - Emergerncy Seoices ddm/1345/50197009 Enclosure cc: Alan B. Wang, NRC Project Manager cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Senior Emergency Preparedness Inspector (RGN-IV/DRS)
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- San Onofre - South Texas Project
- Wotf Creek
Enclosure PG&E Letter DCL-09-020 DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table of Contents - Emergency Plan Implementing Procedures Volume 1A (OM10.ID1 only), Volume 1B (OM10.DC1 only), and Volume 3B Proc. No. Rev. Title OM10.ID1 8 Maintaining Emergency Preparedness OM10.DC1 4 Emergency Preparedness Drills and Exercises EP G-1* 38 Emergency Classification and Emergency Plan Activation EP G-2 32 Interim Emergency Response Organization EP G-3 50 Emergency Notification of Off-Site Agencies EP G-4 22 Assembly and Accountability EP G-5 11 Evacuation of Nonessential Site Personnel EP R-2* 27 Release of Airborne Radioactive Materials Initial Assessment EP R-3 8C Release of Radioactive Liquids EP R-7 15A Off-Site Transportation Accidents EP OR-3 6B Emergency Recovery EP RB-1 5B Personnel Dosimetry EP RB-2 6 Emergency Exposure Guides EP RB-3 6 Stable Iodine Thyroid Blocking EP RB-4 4A Access to and Establishment of Controlled Areas Under Emergency Conditions EP RB-5 6 Alternate Personnel Decontamination Facilities EP RB-8 21 Instructions for Field Monitoring Teams EP RB-9* 13 Calculation of Release Rate EP RB-10 14 Protective Action Recommendations EP RB-11 12 Emergency Offsite Dose Calculations EP RB-12 7 Plant Vent Iodine and Particulate Sampling During Accident Conditions EP RB-14 8A Core Damage Assessment Procedure EP RB-14A 1A Initial Detection of Core Damage EP RB-15 11 Post Accident Sampling System EP RB-16* 2 Operating Instructions for the EARS Computer Program EP EF-1 36 Activation and Operation of the Technical Support Center EP EF-2 28 Activation and Operation of the Operational Support Center EP EF-3 31 Activation and Operation of the Emergency Operations Facility EP EF-4 16 Activation of the Off-Site Emergency Laboratory EP EF-9 10 Backup Emergency Response Facilities EP EF-10 9 Activation and Operation of the Joint Media/Information Center
- Procedure included in this submittal
ISSUED FOR USE BY: DATE:_ _ EXPIRES:_ ___
DIABLO CANYON POWER PLANT 4 EP G-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE UN"T Rev. 38 UNITS tPage 1 of 24 Emergency Classification and Emergency Plan Activation 02/26/09 Effective Date QUALITY RELATED Table of Contents p
- 1. S C O P E ................................................................................. ................... . . 1
- 2. DISCUSSION ............................................. 1
- 3. R ESPO NS IBILITIES ................................................................................... 3
- 4. PREREQUISITES .......... ................................ 3
- 5. PRECAUTIONS AND LIMITATIONS .......................................................... 3
- 6. IN ST R UCT IO NS ......................................................................................... 4
- 7. R EC O R D S .................................................................................................. 4
- 8. REFE RENCES .............................................................................................. 5 ATTACHMENTS:
- 1. Definitions ............................................... 6
- 2. Emergency Action Level Matrix ................................................................. 11
- 1. SCOPE 1.1 This procedure describes accident classification guidelines and Emergency Plan activation responsibilities.
1.2 This procedure provides guidance for classifying emergency events.
1.2.1 For emergency classification, see Attachment 2, "Emergency Action Level Matrix."
1.2.2 For protective action recommendations, see EP RB-10, "Protective Action Recommendations."
1.2.3 For emergency notifications, see EP G-3, "Emergency Notifications of Off-Site Agencies."
1.2.4 For transition to recovery, see EP OR-3, "Emergency Recovery."
- 2. DISCUSSION 2.1 The steps required by this procedure are in addition to the steps required to maintain the plant in, or restore the plant to, a safe condition.
2.2 Events not meeting the minimum classification criteria contained in this procedure should be reviewed for reportability in Xli .0D2, "Regulatory Reporting Requirements and Reporting Process."
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Emergency Classification and Emergency Plan EP G-I R38 Activation Page 2 of 24 UNITS 1&2 2.3 Emergency Action Levels (EAL) are the plant-specific indications, conditions or instrument readings that are utilized to classify emergency conditions defined in the DCPP Emergency Plan. EALs are mode applicable based on operating mode definitions.
2.4 Although the majority of the EALs provide very specific thresholds, the ISEC/SEC/RM must remain alert to events or conditions that lead to the conclusion that exceeding the EAL threshold is imminent. If, in the judgement of the ISEC/SEC/RM, based on factual information received from reliable sources, the threshold will be exceeded, then the classification should be made as if the threshold has actually been exceeded.
2.5 Emergency Action Level Wall Charts are provided as job aids in the following locations:
2.5.1 Joint Information Center (JIC) 2.5.2 Emergency Operations Facility (EOF) 2.5.3 Technical Support Center (TSC) 2.5.4 Control Room 2.5.5 Simulator 2.6 Emergency Classification Levels (ECLs) 2.6.1 UNUSUAL EVENT (UE) - Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.
2.6.2 ALERT - 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 intentional malicious dedicated efforts of a hostile act.
Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline exposure levels.
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Emergency Classification and Emergency Plan EP G-1 R38 Activation Page 3 of 24 UNITS 1&2 2.6.3 SITE AREA EMERGENCY (SAE) - Events are in process or. have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or security events that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents 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 Guidelines exposure levels beyond the site boundary.
2.6.4 GENERAL EMERGENCY (GE) - Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or security events that result in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels off-site for more than the immediate site area.
2.7 Additional definitions can be found in Attachment 1 of this procedure.
- 3. RESPONSIBILITIES 3.1 Interim Site Emergency Coordinator (Interim SEC or ISEC): Control room shift manager is responsible for initial event classification and emergency plan activation. The ISEC may upgrade the event classification until relieved by either the SEC or RM. In addition, the ISEC may downgrade an NUE to no ECL.
3.2 Site Emergency Coordinator (SEC): The SEC may upgrade the classification of an event until relieved by the recovery manager.
3.3 Recovery Manager (RM): The RM, once staffed, is responsible for upgrading or downgrading ECLs, and may direct the SEC to change ECLs.
- 4. PREREQUISITES None
- 5. PRECAUTIONS AND LIMITATIONS 5.1 The expectation is that emergency classifications are to be made as soon as conditions are present and recognizable for the classification, but within 15 minutes or less in all cases of conditions present.
5.2 The plant operating mode that exists at the time that the event occurs (prior to any protective system or operator action is initiated in response to the condition) should be compared to the mode applicability of the EALs. If a lower or higher plant operating mode is reached before the emergency classification is made, the declaration shall be based on the mode that existed at the time the event occurred.
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Emergency Classification and Emergency Plan EP G-1 R38 Activation Page 4 of 24 UNITS 1&2
- 6. INSTRUCTIONS 6.1 Declare an Emergency Classification Level (ECL) by:
NOTE: The expectation is that emergency classifications are to, be made as soon as conditions are present and recognizable for the classification, but within 15 minutes or less in all cases of conditions present.
6.1.1 Referring to the appropriate EAL Matrix, EAL Wall Charts, and/or EAL Technical Basis Manual.
6.1.2 Reviewing EALs:
- a. Review EAL thresholds from left (highest) to right (lowest).
- b. IF an EAL threshold has been exceeded, THEN:
- 1. Verify MODE applicability.
- 2. Note the EAL number.
- 3. Have the classification independently verified.
- 4. Make a verbal declaration to the team members using the '.Update" method. This constitutes the event declaration time.
6.2 The ISEC or SEC may:
6.2.1 Upgrade the event to a higher ECL until the recovery manager arrives at and assumes responsibility in the EOF. However, the ISEC and SEC shall.not.
downgrade an event classified at the ALERT or higher level at.any time. The ISEC may downgrade an NUE to no ECL.
6.2.2 Only the recovery manager may downgrade an ECL at the ALERT or higher level according to the most current controlling EAL.
- 7. RECORDS 7.1 There are no quality or nonquality records generated by this procedure.
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Emergency Classification and Emergency Plan EP G-1 R38 Activation Page 5 of 24 UNITS 1 &2
- 8. REFERENCES 8.1 EP EF-1, "Activation and Operation of the Technical Support Center."
8.2 EP EF-2, "Activation and Operation of the Operational Support Center."
8.3 EP EF-3, "Activation and Operation of the Emergency Operations Facility."
8.4 EP OR-3, "Emergency Recovery."
8.5 EP G-3, "Emergency Notification of Off-Site Agencies."
8.6 Emergency Action Level Technical Basis Manual EP_G-1u3r38.DOC 0226.1447
EP G-1 R38 Page 6 of 24 Definitions U 1&2Attachment 1: Page 1 of 5 Adversary As applied to security EALs, an armed or suspected-to-be-armed intruder whose intent is to commit sabotage, disrupt station operations or otherwise commit a crime on station property.
4.
Affecting Safe Event in progress has adversely affected functions that are necessary to Shutdown bring the plant to and maintain it in the applicable HOT or COLD SHUTDOWN condition. Plant condition applicability is determined by Technical Specification Limiting Conditions for Operation (LCOs) in effect.
Example 1: Event causes damage that results in entry into an LCO that requires the plant to be placed in HOT SHUTDOWN. HOT SHUTDOWN is achievable, but COLD SHUTDOWN is not. This event is not "AFFECTING SAFE SHUTDOWN."
Example 2: Event causes damage that results in entry into an LCO that requires the plant to be placed in COLD SHUTDOWN. HOT SHUTDOWN is achievable, but COLD SHUTDOWN is not. This event is "AFFECTING SAFE SHUTDOWN."
Available The state or condition of being ready and able to be used (placed into operation) to accomplish the stated (or implied) action or function. As applied to a system, this requires the operability of necessary support systems (electrical power supplies, cooling water, lubrication, etc.).
Bomb Refers to an explosive device suspected of having sufficient force to damage plant systems or structures.
Civil Disturbance A group of persons violently protesting station operations or activities at the site.
Close To position a valve or damper so as to prevent flow of the process fluid. To make an electrical connection to supply power.
Confinement The barrier(s) between areas containing radioactive substances and the Boundary environment.
Confirm / To validate, through visual observation or physical inspection, that an Confirmation assumed condition is as expected or required, without taking action to alter the "as found" configuration.
Containment The procedurally defined action taken to secure containment and its Closure associated structures, systems and components as a functional barrier to fission product release under existing plant conditions. Containment
-Closure is defined by AD8.DC54, "Containment Closure."
Contiguous Being in actual contact; touching along a boundary or at a point.
Control Take action, as necessary, to maintain the value of a specified parameter within applicable limits; to fix or adjust the time, amount, or rate of; to regulate or restrict.
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EP G-1 R38 Page 7 of 24 Definitions U 1&2Attachment 1: Page 2 of 5 Environment The EPA PAGs are expressed in terms of dose commitment: 1 Rem TEDE Protection Agency or 5 Rem CDE Thyroid. Actua.l or projected off-site exposures in excess of (EPA) Protective the EPA PAGs require DCPP to recommend protective actions for the Action Guidelines general public to off-site planning agencies.
(PAGs)
Exceeds To go or be beyond a stated or implied limit, measure, or degree.
Explosion A rapid, violent, unconfined combustion, or catastrophic failure of pressurized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.
Extortion An attempt to cause an action at the station by threat of force.
Faulted In a steam generator, the existence of secondary side leakagethat results in an uncontrolled decrease in steam generator pressure or the steam.
generator being completely depressurized.
Failure A state of inability to perform a normal function.
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.
Fission Product Multiple physical barriers any one of which, if maintained intact, precludes Barriers (FPB) the release of significant amounts of radioactive fission products to the environment. The FPBs are the Reactor Fuel Clad (FC), Reactor Coolant System (RCS) and Containment (CNMT).
Hostage Person(s) held as leverage against the station to ensure that demands will be met by the station.
Hostile Action An act toward DCPP or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate DCPP 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 DCPP. Non-terrorism-based EALs should be used to address such activities, (e.g., violent acts between individuals in the owner controlled area).
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.
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EP G-1 R38 Page 8 of 24 Definitions U 1&2Attachment 1: Page 3 of 5 IDLH A condition that either poses an immediate threat to life and health or an immediate threat of severe exposure to contaminants which are likely to have adverse delayed effects on health.
Inoperable Not able to perform its intended function.
Intruder Person(s) present in a specified area without authorization.
Intrusion The act of entering without authorization. Discovery of a bomb in a specified area is indication of intrusion into that area by a hostile force.
Lower Flammability The minimum concentration of a combustible substance that is capable of Limit (LFL) propagating a flame through a homogenous mixture of the combustible and a gaseous oxidizer.
Maintain Take action, as necessary, to keep the value of the specified parameter within the applicable limits.
Normal Plant Activities at the plant site associated with routine, testing, maintenance, or Operations equipment operations, in accordance with normal operating or administrative procedures. Entry into abnormal or emergency operating procedures, or deviation from normal security or radiological controls posture, is a departure from Normal Plant Operations.
Operable Able to perform its intended function.
Owner Controlled The land area(s) adjacent to the site boundary that are owned and Area (OCA) controlled by the licensee, whereby access can be limited by the licensee for any reason. Generally described, the DCPP OCA is the area between the Port San Luis gate and security gate A, bounded by the eastern hills directly adjacent to the site access road and the northern evacuation route, and bounded to the west by the Pacific Ocean.
(Note: for commitments identified in the Diablo Canyon Physical Security Plan, the "Owner Controlled Area" (OCA) is within the "Site Boundary" as described in UFSAR).
Primary System The pipes, valves, and other equipment which connect directly to the Reactor Vessel or reactor coolant system such that a reduction in Reactor Vessel pressure will effect a decrease in the steam or water being discharged through an unisolated break in the system.
Protected Area The Protected Area is within the security isolation zone and is depicted in Dwg. 471124 "Plot Plan."
Reduced Inventory The condition existing whenever RCS water level is lower than 3 feet below Condition (RIC) the Reactor Vessel flange (below 111 foot elevation) with fuel in the core.
Restore Take the appropriate action required to returnthe value of an identified parameter to within applicable limits.
Ruptured In a steam generator, existence of primary-to-secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.
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EP G-1 R38 Page 9 of 24 Definitions U 1&2Attachment 1: Page 4 of 5 Sabotage Sabotage is deliberate damage, misalignment, or mis-operation of plant equipment with the intent to render the equipment inoperable. Equipment found tampered with or damaged due to malicious mischief may not meet the definition of Sabotage until this determination is made by security supervision.
Safe Plant Hot or cold shutdown (reactor subcritical) with control of coolant inventory Shutdown and decay heat removal.
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.
Significant Transient An unplanned event involving any of the following:
" Automatic turbine runback > 25% thermal reactor power
" Electrical load rejection > 25% full electrical load
- Safety injection activation
" Thermal power oscillations > 10%
Site Boundary As depicted in the Final Safety Analysis Report Update (UFSAR),
Figure 2.1-2, Site Plan and Gaseous Effluent Release Points.
Strike Action Work stoppage within the protected area by a body of organized labor workers to enforce compliance with demands made on DCPP. The strike action must threaten to interrupt normal plant operations.
Sustained Prolonged. Not intermittent or of a transitory nature.
Trip To deenergize a pump or fan motor; to position a breaker so as to interrupt or prevent the flow ofcurrent in the associated circuit; to manually activate a semi-automatic feature.
Unavailable Not able to perform its intended function.
Uncontrolled An evolution lacking control, but is not the result of operator action.
Unplanned A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.
Valid An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
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EP G-1 R38 Page 10 of 24 Definitions U 1&2Attachment 1: Page 5 of 5 Visible Damage Damage to equipment or structure that is readily observable without measurements, testing, or analysis. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety structure, system, or component. Example damage includes: deformation due to heat or impact, denting, penetration, rupture, cracking, paint blistering. Surface blemishes (e.g., paint chipping, scratches) should not be included.
Vital Area Any plant area which contains vital equipment. Any area, normally within the protected area, which contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.
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EP G-1 R38 Page 11 of 24 Emergency Action Level Matrix U1 &2 Attachment 2: Page 1 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Offsite dose resulting from an actual or imminent Offsite dose resulting from an actual or imminent Any unplanned release of gaseous or liquid Any unplanned release of gaseous or liquid release of gaseous radioactivity exceeds release of gaseous radioactivity exceeds radioactivity to the environment that exceeds radioactivity to the environment that exceeds two 1000 mRem TEDE or 5000 mRem thyroid CDE for 100 mRem TEDE or 500 mRem thyroid CDE for 200 times the Radiological Effluent Technical times the radiological effluent Radiological Effluent the actual or projected duration of the release using the actual or projected duration of the release Specifications (RETS) limits for 15 minutes or Technical Specifications (RETS) limits for actual meteorology longer 60 minutes or longer 11 2 13 14 5 6 DOEF. 1 2 3 14 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF RGI.1 RSI.1 RAI.1 RUI.1 Valid reading on ANY monitors that exceeds or is Valid reading on ANY radiation monitors that Valid reading on ANY LIQUID monitors Valid reading on ANY LIQUID monitors expected to exceed Table R-1 column "GE" for exceeds or is expected to exceed Table R-1 > Table R-1 column "Alert" for > 15 min. > Table R-1 column "UE" for 560 min.
>-15 min. (Note 1) column "SAE"for> 15 min. (Note 1) RA1.2 RU1.2 Note 1: If dose assessment results are available at Note 1: If dose assessment results are available at Valid reading on ANY GASEOUS monitors Valid reading on ANY GASEOUS monitors the time of declaration, the classification should be the time of declaration, the classification should be > Table R-1 column "Alert" for > 15 min. > Table R-1 column 'UE" for -60 min.
R based on dose assessment instead of radiation monitor readings. While necessary declarations based on dose assessment instead of radiation monitor readings. While necessary declarations RA1.3 RUl.3 Abnormal should not be delayed awaiting results, the dose should not be delayed awaiting results, the dose Confirmed sample analyses for gaseous or liquid Confirmed sample analyses for gaseous or liquid Red Offsite assessment should be initiated / completed In order assessment should be initiated / completed in order releases indicate concentrations or release rates releases indicate concentrations or release rates Release Rad to determine if the classification is warranted, to determine if the classification should be > 2 x RETS limits for 5 60 mi.
Red Conditions See RG1.2 subsequently escalated. See RS1.2 >200 x RTS limits for- 15 mi.
Effluent RGI.2 RSI.2 Dose assessment using actual meteorology Dose assessment using actual meteorology indicates doses > 1,000 mRem TEDE or indicates doses > 100 mRem TEDE or 500 mRem 5,000 mRem thyroid CDE at or beyond the site thyroid CDE at or beyond the site boundary boundary RS1.3 RG1.3 Field survey indicates closed window dose rate Field survey results indicate closed window dose > 100 mRem/hr that is expected to continue for rates > 1,000 mRem/hr expected to continue for > 1 hr, at or beyond the site boundary
> 1 hr, at or beyond the site boundary OR OR Field survey sample analysis indicates thyroid CDE Analyses of field survey samples indicate thyroid of 5 500 mRem for 1 hr of inhalation at or beyond CDE of 5,000 mRem for 1 hr of inhalation, at or the site boundary beyond the site boundary Category R continued on next page.
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EP G-1 R38 Page 12 of 24 Emergency Action Level Matrix U 1 &2Attachment 2: Page 2 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Damage to irradiated fuel or loss of water level that Unexpected increase in plant radiation has or will result in the uncovering of irradiated fuel Table R-1 Effluent Monitor Classification Thresholds outside the Reactor Vessel ReleasePoint Monitor GE SAE Alert UE 11 12 1 3 1 4 1 5 16 IDEFI 1 2 3 4 5 6 DEF
- - Offscale hi 8.0E4 cpm RA2.1 RU2.1 1(2)-RM-14/14R 2.OE-3 iC/cc Damage to irradiated fuel or loss of water level that Valid low water level alarm indicating uncontrolled a Plant1VentG(2)-RM-24/24R - - 1.OE-6 giC/cc 1.OE-8 .C/cc has or will result in the uncovering of irradiated fuel water level decrease in the reactor refueling cavity, S1t(2)-RM-28/28R - - 1.OE-5 i.C/cc outside the reactor vessel resulting in a valid high spent fuel pool, or fuel transfer canal with all 1.0E-7 tiC/cc alarm on ANY of the following radiation monitors: irradiated fuel assemblies remaining covered by e 3.0E-9 amps 3.OE-10 amps " New Fuel Storage Area Rad Mon RM-59, o ~1 (2)-RM-87--
2.OE+ipC/cc 2.0E0 _C/cc Hi Rad (6.5 mR/hr) water u AND
" Spent Fuel Pool Area Rad Mon RM-58, Hi Rad 1(2)-RM-71/72/73174 (20 mR/hr) Unplanned valid direct area radiation monitor Main Steam With Steam Dump or 3.OE+5 cpm 3.OE+4 cpm 3.OE+3 cpm 3.OE+2 cpm " Contmt Area Mon High Rad RM-2, Hi Rad reading increases one or more SRVs.
open on affected SG (21 mR/hr) RU2.2
" Containment Ventilation Exhaust Radiation Oily Water Unplanned valid direct radiation area monitor Separator 0-RM-3 - - 6.OE+4 cpm 6.OE+2 cpm Monitor RM-44NB high alarm (1.35E-4 pLC/cc) reading increases by a factor of 1000 over normal*
L Effluent RA2.2 levels R 2 Liquid q Radwaste A water level drop in the reactor refueling cavity, Normal levels may be considered as the highest Offscale hi
- 1.0E+5 cpm spent fuel pool or fuel transfer canal that will result reading in the past twenty-four (24) hours Abnormal Onffsite IDischarge O-RM-18 - -
in irradiated fuel becoming uncovered excluding the current peak value Red Rad d Line Effluent Release Conditions, SGEBDTank Release of radioactive material or increases in Spent Fuel Liquid Effluent 1(2)-RM-23 - - Offscale hi 2.OE+4 cpm radiation levels within the facility that impedes Rad Effluent Events operation of systems required to maintain safe
- With effluent discharge not isolated operations or to establish or maintain cold shutdown 11 2 I 3 I 4 I 5 I 6 I DEF I RA2.3 Valid radiation monitor readings > 15 mR/hr in areas requiring continuous occupancy to maintain plant safety functions:
Control Room (0-RM-1)
OR Central Alarm Station (by survey)
RA2.4 Valid radiation monitor readings > 2 R/hr in the following areas requiring infrequent access to maintain plant safety functions:
" Auxiliary Building
" Fuel Handling Building
" Turbine Building
" Intake Structure EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 13 of 24 Emergency Action Level Matrix U1 &2 Attachment 2: Page 3 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Natural and destructive phenomena affecting the Natural and destructive phenomena affecting the plant Vital Area Protected Area Table H-1 Vital Areas 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF
. Containment HA1.1 HU1.1
. Auxiliary Building EFM "Alert" alarm or CP M-4, "Earthquake" Seismic event identified by ANY TWO of the indicates Operating Basis Earthquake (> 0.2 g) following:
. Fuel Handling Building exceeded - Earthquake felt in plant
. Turbine Building HAI.2
- Seismic event confirmed by PK15-24 main
. Intake Structure ;Tornado or high winds > 80 mph (36.36 m/sec)
- annunciator "SEISMIC U.S. Geological Survey INSTR (USGS)SYSTEM"
. RWST within Protected Area boundary and resulting in
. CST visible damage to ANY Table H-1 plant structures I HU1.2 Note2: If vehicle crash is a hostile action, see equipment or Control Room indication of degraded Report by plant personnel of tornado or high winds Subcategory H.4 EALs for possible performance of those systems > 80 mph (36.36 m/sec) striking within Protected Natural & classification HA1.3 Area boundary Hazards Destructive Vehicle crash within Protected Area boundary and HU1.3 Phenomena None resulting in visible damage to ANY Table H-1 plant Report of turbine failure resulting in casing structures or equipment or control room indication penetration or damage to turbine or generator of degraded performance of those systems seals.
(Note 2)
HAI.4 HUI.4 Turbine failure-generated missiles result in ANY Uncontrolled flooding in ANY Table H-1 area that visibledamaure-getpnetratedmissionsof ANY TableHhas the potential to affect safety related equipment visible damage to or penetration of ANY Table H-1 needed for the current operating mode area HAl.5 HUI.5 Hurricane warning or tsunami (actual or warning)
Uncontrolled flooding inANY Table H-i area that affecting the Protected Area results in degraded safety system performance as indicated in the Control Room or that creates industrial safety hazards (e.g., electric shock) that precludes access necessary to operate or monitor safety equipment Category H continued on next page.
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EP G-1 R38 Page 14 of 24 Emergency Action Level Matrix U 1&2 Attachment 2: Page 4 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Fire or explosion affecting the operability of plant Fire or explosion within the protected area safety systems required to establish or maintain boundary.
1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF
- 2. None Note3: Ifthe fire or explosion is a hostile action, see Subcategory H.4 EALs for possible HA2.1 Fire or explosion resulting in EITHER:
HU2.t Fire in buildings or areas contiguous to ANY Table Fire or classification
- Visible damage to any Table H-1 plant H-1 area not extinguished within 15 min. of Control Explosion structures containing safety systems or Room notification or validation of a Control Room components alarm (Note 3)
- Control Room indication of degraded HU2.2 performance of systems required to establish or maintain safe shutdown (Note 3) Report by plant personnel of an unanticipated explosion within Protected Area boundary resulting in visible damage to permanent structure or H equipment (Note 3)
Hazards Release of toxic, corrosive, asphyxiant or Release of toxic, corrosive, asphyxiant or flammable gases within or contiguous to a Vital flammable gases deemed detrimental to normal Area which jeopardizes operation of systems operation of the plant required to establish or maintain safe shutdown 1 2 3 4 5 6 DEF 1 2 3 4 6 6 DEF 3 HA3.1 HU3.1 Toxic and None None Report or detection of toxic, corrosive or asphyxiant Report or detection of toxic, corrosive, asphyxiant Flammable gases within or contiguous to ANY Table H-1 area or flammable gases that have entered or could Gas in concentrations that may result in an atmosphere enter the Owner Controlled Area in amounts that Immediately Dangerous to Life and Health (IDLH)) can adversely affect normal plant operations HA3.2 HU3.2 Report or detection of gases in concentration > the Recommendation by local, county or state officials Lower Flammability Limit within or contiguous to to evacuate or shelter site personnel based on ANY Table H-1 area offsite event Category H continued on next page.
EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 15 of 24 Emergency Action Level Matrix U1 &2Attachment 2: Page 5 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hostile action resulting in loss of physical control Hostile action within the Protected Area Hostile action within the Owner Controlled Area or Confirmed security condition or threat which of the facility airborne attack threat indicates a potential degradation in the level of safety of the plant 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF HG4.1 HS4.1 HA4.1 HU4.1
, A hostile action has occurred such that plant A hostile action is occurring or has occurred within A hostile action is occurring or has occurred within Asecurity condition that does not involve a hostile personnel are unable to operate equipment the Protected Area as reported by the Security the Owner Controlled Area as reported by the action as reported by the Security Watch Security required to maintain safety functions Watch Commander Security Watch Commander Commander OR OR OR A hostile action has caused: A valid notification from NRC of an airliner attack Acredible site-specific security threat notification Failure of Spent Fuel Cooling systems threat within 30 rain. of the site OR AND Avalid notification from NRC providing information Imminent fuel damage is likely for a freshly of an aircraft threat off-loaded reactor core in pool Control Room evacuation has been initiated and Control Room evacuation has been initiated plant control cannot be established 5 1 2 3 14 5 6 DEF 1 2 3 4 5 6 DEF HS5.1 HA5.1 H Control None Control Room evacuation has been initiated Entry into OP AP-8A, Control Room None Hazards EvacuationAN Room AND Inaccessibility, for Control Room evacuation Control of the plant cannot be established per OP AP-8A, Control Room Inaccessibility, within 15 rain.
Other conditions*existing which in the judgment of Other conditions existing which in the judgment of Other conditions existing which in the judgment of Other conditions existing which in the judgment of the ISEC/SEC/RM warrant declaration of General the ISEC/SEC/RM warrant declaration of Site Area the ISEC/SEC/RM warrant declaration of an Alert the ISEC/SECIRM warrant declaration of a UE Emergency Emergency 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF HG6.1 HS6.1 HA6.1 HU6.1 Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which inthe judgment of the Other conditions exist which in the judgment of the 6 ISEC/SEC/RM indicate that events are in process ISEC/SEC/RM indicate that events are in progress ISEC/SEC/RM indicate that are in progress or ISEC/SEC/RM indicate that events are in progress or have occurred which involve actual or imminent or have occurred which involve an actual or likely have occurred which involve an actual or potential or have occurred which indicate a potential Judgment substantial core degradation or melting with major failures of plant functions needed for substantial degradation of the level of safety of the degradation of the level of safety of the plant. No potential for loss of containment integrity or protection of the public. ANY releases are not plant. ANY releases are expected to be limited to releases of radioactive material requiring offsite security events that result in an actual loss of expected to result in exposure levels which small fractions of the EPA Protective Action response or monitoring are expected unless physical control of the facility. Releases can be exceed EPA Protective Action Guideline exposure Guideline exposure levels (1 Rem TEDE and further degradation of safety systems occurs reasonably expected to exceed EPA Protective levels (1 Rem TEDE and 5 Rem thyroid CDE) 5 Rem thyroid CDE)
Action Guideline exposure levels (1 Rem TEDE beyond the site boundary and 5 Rem thyroid CDE) offsate for more than the site boundary EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 16 of 24 Emergency Action Level Matrix U 1&2Attachment 2: Page 6 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Loss of all offsite power and loss of all onsite AC AC power capability to vital buses reduced to a power to vital buses single power source for greater than 15 minutes such that any additional single failure would result in station blackout CAI.1 CUl.1 Loss of ALL offsite and onsite AC power to Unit AC power capability to Unit 1(2) Vital 4kV buses F, 1(2) Vital 4kV buses F, G and H for > 15 min. G and H reduced to a single power source (e.g.,
C one DG, supply line from unaffected unit or one offsite power source) for > 15 min. such that ANY Cold SD/ None None additional single failure would result in loss of ALL Refuel Loss of AC power to vital buses System Malf. Power Unplanned loss of required DC power for greater than 15 minutes CU1.2 Unplanned loss of vital DC power to required DC buses based on < 105 VDC bus voltage indications AND Failure to restore power to at least one required DC bus within 15 min. from the time of loss Category C continued on next page.
EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 17 of 24 Emergency Action Level Matrix U 1 &2Attachment 2: Page 7 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL-EVENT Loss of Reactor Vessel inventory affecting Fuel Loss of Reactor Vessel inventory affecting core Loss of RCS/RPV inventory with Irradiated fuel In Unplanned loss of RCS inventory with irradiated Clad Integrity with Containment challenged and decay heat removal capability the RPV fuel in the Reactor Vessel irradiated fuel in the Reactor Vessel CG2.1 IV 5M 6 1 CS2.1-mil~ 5 IBM CA2.M 5;- 60 IN-CU2.1 1r-; 6 M I Containment challenged as indicated by ANY of With Containment closure not established: Loss of inventory as Indicated by EITHER: Unplanned RCS level decreasing below the the following: RVLIS full range < 62.1% Reactor Vessel level < bottom of the RCS hot Reactor Vessel flange for a 15 min.
- Unplanned rise in containment pressure Reactor Vessel level cannot be monitored for >
- RVRLIS LI-400 , standpipe or ultrasonic AND 30 min. with unexplained increase in ANY sensor
30 min. as indicated by Table C-1 sump/tank level ' RVLIS upper range < 60% increase in ANY Table C-Dsump/tank level C EITHER: CS2.2 O RVLIS full range <63.3% AND Cold SD/I!RVLOR full range.< 56.6% With Containment closure established: OR Reactor Vessel level cannot be monitored for Reactor Vessel water level cannot be monitored Refuel Reactor Vessel level cannot be monitored with RVLIS full range < 56.6% > 15 min. with unexplained increase in ANY System core uncovery indicated by ANY of the OR Table C-1 sump/tank level Malf following: Reactor Vessel level cannot be monitored for .- .. ..-... **.....-..
- Containment radiation (RE-30 or RE-31) >30 min. with EITHER: Reatr e veThresholds
> 20 R/hr
- Unexplained increase in ANY Table C-1 ElIM RVLIS
- Erratic source range monitor indication sump/tank level
- Unexplained Increase in ANY Table C-1
- Erratic source range monitor indication RV flange 114 ft 81.5% upper 2 . sumpitank level 83.3% full 2 Loss of Reactor Vessel inventory affecting core Hot leg 105 ft 9 in. 60% upper RCS Level Table C-1 Sumps/Tanks decay heat removal capability with irradiated fuel . , bottom 63.3% full in the Reactor Vessel 6in. below 105 ft 3 in. 62.1% full
- Containment Structure Sump 1-1 (2-1) _ 6 I I, hot leg
- Containment Structure Sump 1-2 (2-2) CS2.3 Topof 103 ft 56.6% full
- - Reactor Cavity Sump With Containment closure not established: active fuel
OR SRCDT Reactor Vessel level cannot be monitored with
- CCW surge tank indication of core uncovery as evidenced by
- Auxiliary Building sump EITHER:
- Containment radiation (RE-30 or RE-31)
> 20 R/hr
- Erratic source range monitor Indication CS2.4 With Containment closure established:
RVLIS full range < 56.6%
OR Reactor Vessel level cannot be monitored with indication of core uncovery as evidenced by EITHER:
- Containment radiation (RE-30 or RE-31)
>20 R/hr
- Erratic source range monitor indication EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 18 of 24 Emergency Action Level Matrix U1 &2Attachment 2: Page 8 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Inability to maintain plant In cold shutdown with Unplanned loss of decay heat removal capability with irradiated fuel in the Reactor Vessel irradiated fuel in the reactor vessel 5 6 ~ 5 ý6~
3 CA3.1 CU3.1 None None An unplanned event results in RCS temperature An unplanned event results in RCS temperature RCS > 200°F for > Table C-3 duration > 200°F Temp. OR CU3.2 RCS pressure.increase > 10 psig due to a loss of Loss of ALL RCS temperature and Reactor Vessel RCS cooling level indication for
> 15 min.
Unplanned loss of all onsite or offsite communications capabilities.
4 CU4.1 None None None Loss of ALL Table C-2 onsite (internal)
Comm. communications capability affecting the ability to C perform routine operations Cold SDI OR Refuel Loss of ALL Table C-2 offsite (external)
System communications capability Malf.
RCS leakage
~ 5 ROM CU5.1 5 None None None Unable to restore or maintain EITHER of the following due to RCS leakage for > 15 min.:
RCS Pressurizer level > 17%
Leakage OR Above the low end of the target level control band (if pressurizer level was intentionally lowered
< 17%)
Inadvertent criticality 6
n None I 516 Ifl Inadvert.CU. None None CUM CrIL An unplanned sustained positive startup rate observed on nuclear instrumentation Category C continued on next page.
EP_G-1u3r38.DOC 0226.1447
EP G-1 R38 Page 19 of 24 Emergency Action Level Matrix U 1&2Attachment 2: Page 9 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Table C-2 Communications Systems Table C-3 RCS Reheat Duration Thresholds Sysem Onsite Offaite (internal) (external) Containment and RCS Barrier Status Duration Unit 1, Unit 2 and TSC X X RCS intact (Containment closure N/A) 60 min.
Radio Consoles DCPP Telephone System X XContainment closure established (PBX) AND 20 min.*
Portable radio equipment X RCS not intact (handle-talkies) Containment closure not established Operations Radio System X X AND 0 min.
C Security Radio Systems X RCS not intact Central Alarm Station X X Ifan RCS heat removal system is in operation within this Cold SDI (CAS) and Secondary time frame and RCS temperature is being reduced, this EAL Refuel Alarm Stations (SAS) is not applicable.
System Consoles Malf. Fire Radio System X Hot Shutdown Panel X X Radio Consoles Public Address System X NRC FTS X Mobile radios X Satellite phones X X Direct line (ATL) to the X County and State Office of Emergency Services (OES)
EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 20 of 24 Emergency Action Level Matrix U 1 &2Attachment 2: Page 10 of 14
- GENERAL EMERGENCY SITE AREA EMERGENCY ALERT . UNUSUAL EVENT Prolonged loss of all offsite power and prolonged Loss of all offsite power and loss of all onsite AC AC power capability to vital buses reduced to a Loss of all offsite power to vital buses for greater loss of all onsite AC power to vital buses power to vital buses single power source for greater than 15 minutes than 15 minutes such that any additional single failure would result in station blackout-1 2 3 4 11213 4_ 1 2 31l 3 1 2 3 4 I 1 SGI.1 SS1.1 SAI.I SU1.I Loss of ALL offsite and onsite AC power to Unit Loss of ALL offsite and onsite AC power to AC power capability to Unit1 (2),Vital 4kV buses F, Loss of ALL offsite AC power to Unit 1(2) Vital 4kV Loss of 1(2) Vital 4kV buses F, G and H Unit 1(2) Vital 4kV buses F, G and H G and H reduced to a single power source ' buses F, G and H for > 15 min.
Power AND EITHER: - for > 15 min. (i.e., one DG or one offsite power source) for Restoration of ANY Vital 4kV bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> > 15 min.
is not likely Loss of all vital DC power OR CSFST Core Cooling-RED or MAGENTA path SSI .2 Loss of ALL vital Dc power based on < 105VDC bus voltage indications for > 15 min.
Automatic trp and ALL manual actions fail to shut Automatic-trip fails to shut down the reactor and Automatic trip fails to shut down the reactor and dutowathe rctori and iLLand acation fan etre s l s manual actions taken from the reactor control the manual actions taken from the reactor control challenge to the ability cdown the reactor to cool the and indication of core an extreme exists recoratr are NOT successful in shutting down the console are successful in shutting down the console System resctor. reactor Ma1f. 1 2 W 7 1 2 l l1 2 2 8G2.1 6S2.1 SA2.1 RTS Automatic trip and ALL manual actions fail to shut An automatic trip failed to shut down the reactor An automatic trip failed to shut down the reactor None Failure down the reactor AND AND AND EITHER of the following have occurred due Manual actions taken at the reactor control Manual actions taken at the reactor control to continued power generation: console do not shut down the reactor-as indicated console successfully shut down the reactor as CSFST Core Cooling-RED by reator power> 5% indicated by reactor power < 5%
b eco wr>5 OR CSFST Heat Sink-RED Inability to reach required shutdown within 3Technical Specification limits Inability No2e3N4ne None to Reach None None None SU3.1 or Plant is not brought to required operating mode Maintain within Technical Specifications LCO action SD Cond. statement time Category S continued on next page.
EP_G-1 u3r38.DOC 0226.1447
EP G-1 R38 Page 21 of 24 Emergency Action Level Matrix U1 &2Attachment 2: Page I1 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Inability to monitor a significant transient in Unplanned loss of most or all safety system Unplanned loss of most or all safety system Table C-2 Communications Systems progress annunciation or indication in control room with annunciation or indication in the control room for either (1) a significant transient in progress, or greater than 15 minutes System Onsite Offaite (2) compensatory non-alarming indicators are System _ (internal) (external) unavailable Unit 1,Unit2andTSC X X 142 I1 2 3 4 'ý Radio Consoles SS4.1 SA4.1 SU4.1 DCPP Telephone System X X (PBX) Loss of greater than approximately 75% of the Unplanned loss of greater than approximately 75% Unplanned loss of greater than approximately 75%
annunciators or indicators associated with safety of the annunciators or indicators associated with of the annunciators or indicators associated with Portable radio equipment X systems on Vertical Boards 1 through 5, and safety systems on Vertical Boards 1 through 5, - safety systems on Vertical Boards 1 through 5, (handle-talkies) Control Consoles 1, 2 and 3 and Control Consoles 1,2 and 3 for and Control Consoles 1,2 and 3for 15 rfiin.
Operations Radio System X X AND > 15 min.
Security Radio Systems X Significant transient is in progress AND EITHER: Unplanned loss of all onsite or offsite 4, Central Alarm Station X X AND AN A significant transient is in progress OR communications capabilities Int.I and Secondary (CAS) Stations Alarm (SAS) Compensatory SPDS) non-alarming indications (PPC, are unavailable Compensatory Om non-alarming indications (PPC, SU4.2 SPDS) are unavailable Loss of ALL Table C-2 onsite (internal)
Comm. Consoles communications capability affecting the ability to Fire Radio System X perform routine operations Hot Shutdown Panel X X OR Radio Consoles Loss of ALL Table C-2 offsite (external) communications capability Public Address System X NRC FTS X Mobile radios X Satellite phones X X Direct line (ATL) to the X County and State Office of Emergency Services (OES)
Category S continued on next page.
EP_G-1u3r38.DOC 0226.1447
EP G-1 R38 Page 22 of 24 Emergency Action Level Matrix- U 1 &2Attachment 2: Page 12 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Fuel Clad degradation 11 2 13 47 -1; SU5.1 With letdown in service, EP-RB-14A Dose Point radiation > 3 RPhr None None None Fuel Clad SU5.2 Degrad. CoCoolant activity > 60 pCilgm Dose Equivalent 1-131 OR Coolant activity > 600.0 pCi/gm Dose Equivalent Xe-1 33 S RCS leakage System 4 .
Malf.
6SUM RCSNone None None Unidentified or pressure boundary leakage Leakage > 10 gpm OR Identified leakage > 25 gpm Inadvertent criticality 7 ~ 3 4 ~
Inadvert. None None None SU7.1 Crit. An unplanned sustained positive startup rate observed on nuclear instrumentation EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 23 of 24 Emergency Action Level Matrix U 1 &2Attachment 2: Page 13 of 14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT FGI.1 FSI.1 FAI.1 FUI.1 1 2 3 4 1 2 1 3 4 1 2 3 4 J. 1 2 3 4 Loss of ANY two barriers Loss or potential loss of ANY two barriers ANY loss or ANY potential loss of either Fuel ANY loss or ANY potential loss of Containment AND (Table F-1) (Note 5) Clad or RCS (Table F-i) (Note 5)
Loss or potential loss of third barrier (Table F-1) (Note 5)
F (Table F-i) (Note 5)
Fission Note 5: The logic used for these initiating conditions reflects the following considerations:
Product Barrier The Fuel Clad barrier and the RCS barrier are weighted more heavily than the Containment barrier. UE EALs associated with RCS and Fuel Clad barriers are addressed under System Malfunction Barriers EALs.
- At the Site Area Emergency level, there must be some ability to dynamically assess how far present conditions are from the threshold for a General Emergency. For example, if Fuel Clad and RCS barrier "loss" EALs existed, that, in addition to offsite dose assessments, would require continual assessments of radioactive Inventory and containment integrity. Alternatively, if both Fuel Clad and RCS barrier 'Potential Loss" EALs existed, the ISEC/SEC/RM would have more assurance that there was no immediate need to escalate to a General Emergency.
- The ability to escalate to higher emergency classes as an event deteriorates must be maintained. For example, RCS leakage steadily increasing would represent an increasing risk to public health and safety.
EPG-1u3r38.DOC 0226.1447
EP G-1 R38 Page 24 of 24 Emergency Action Level Matrix U 1&2Attachment 2: Page 14 of 14 Fuel Cladding Barrier Reactor Coolant System Barrier Containment Barrier I I F-I Loss E l1Potential Loss El Loss : El Potential Loss El Loss Potential Loss A.CSFST 1. CSFST Core Cooling- - 1. CSFSTCore Cooling- bI 1. CSFST RCS Integrity-RED 1. CSFST Containment-RED RED MAGENTA None OR None OR CSFST Heat Sink-RED and heat I i,, CSFST Heat Sink-RED ' sink required and heat sink required _ L-B.Core Exit TCe -I 2. Core exit TCsa 1,200-F D-2. Care exit TCs > 700F t] 2. Core exit TCs > 1,200=F I I I AND Restoration procedures not effective within 15 rein.
None None Ne b 3. ALL of the following:
Core exit TCs > 700F
- 4. With letdown In service, I ,
- 5. Containment pssure 47 psig and increasing AND , Table F-2 thresholds makeup capacity as the capacity of one charging pump MSL radiation I indicated by a loss of RCS in the normal charging mode & Containment hydrogen concentration a 4%
- ISSUED FOR USE BY: DATE: EXPIRES:____
- 1. SCOPE 1.1 This procedure describes the manual method to determine the release rate of airborne radioactive materials from a plant vent release, main steam line release, or containment leakage.
- 2. DISCUSSION 2.1 Initial calculations of radiological release rates are performed in the control room in accordance with EP R-2, "Release of Airborne Radioactive Materials" by the emergency evaluation coordinator.
- 3. RESPONSIBILITIES 3.1 Dose assessment personnel perform this procedure when required.
- 4. INSTRUCTIONS 4.1 To manually calculate Noble Gas and Iodine-131 Equivalent Release Rates for a Plant Vent Release follow the step-by-step instructions given in Attachment 7.1 -
- 5. RECORDS All records generated by the utilization of this procedure for an exercise or emergency shall be forwarded the next working day tothe supervisor, emergency planning, for review and retention.
- 6. APPENDICES 6.1 Table 1, Source Term For Various Postulated Accidents 6.2 Figure 1, Plant Vent Noble Gas Monitor Response RE-I 4/14R, Normal Range 6.3 Figure 2, Plant Vent Noble Gas Monitor Response RE-87, Extended Range 6.4 Figure 3, Plant Vent Gross Gamma Monitor Response RE-29, High Range 6.5 Figures 4.1, 1-131 TEDE Correction Factor, and 4.2,1-131 Thyroid CDE Correction Factor (2 pages) 6.6 Figures 5.1, 5.2, and 5.3, Main Steamline Monitor Response RE-71., RE-72, RE-73, RE-74, for Empty, Normal, and Flooded Conditions (3 pages) 6.7 Figures 6.1, Iodine TEDE Conversion Factor, and 6.2, Iodine Thyroid CDE Conversion Factor (2 pages) 6.8 Figure 7, Design Basis ContainmentMonitor Exposure Rate RE-30 and RE-31 6.9 Figure 8, Design Basis Noble Gas Release Rates 6.10 Figure 9, Design Basis 1-131 Equivalent Release Rates 6.11 Accident Summary Sheets
- 7. ATTACHMENTS 7.1 Form 69-9260, "Noble Gas and 1-1 31 Equivalent Release Rates for a Plant Vent Release,"
- 8. REFERENCES 8.1 EP EF-1, "Activation and Operations of the Technical Support Center" 8.2 EP EF-3, "Activation and Operation of the Emergency Operations Facility" 8.3 EP EF-6, "Operating Procedures for EARS Stations" 8.4 EP G-1, "Accident Classification and Emergency Plan Activation" 8.5 EP R-2, "Release of Airborne Radioactive Materials" 8.6 EP RB-1 1, "Emergency Off-site Dose Calculations" 8.7 EP RB-I 2, "Plant Vent Iodine and Particulate Sampling During Accident Conditions" 8.8 EP RB-14, "Core Damage Assessment Procedure" 8.9 Diablo Canyon Power Plant Unit I and 2 Emergency Plan EPRB-9u3rl3.DOC 03B 0203.1409
- 1. Major LOCA with Core Melt - RE-30/31 >300R/hr Core
- 2. Major LOCA (Gap Release) - RE-30/31 >I R/hr, <300R/hr Gap
- 4. Blackout RCS
- 5. Major Steamline Break
- 7. Steam Generator Tube Rupture RCS
- 8. Locked Reactor Coolant Pump (RCP Rotor) GAP
- 9. Control Rod Ejection GAP
- 10. Gas Decay Tank Rupture GAP - Noble Gas Only
- 11. Liquid Holdup Tank Rupture RCS.- Noble Gas Only
- 13. Fuel Handling Accident in Fuel Handling Building (FHB) Spent Fuel (Highest Assembly Gap)
- 1. OOE +00 O.OOE+00 0 10 20 30 40 50 60. 70 80 90 100 Time After Shutdown, Hrs EP RB-9u3rl3.DOC 03B 0203.1409
- 1. Total Release to Containment Free Volume, Ci 6
- a. Xe-133 2.03x108 1.36x10 5
- c. 1-131 7 5 2.21x10 1.82x10 5
- d. Other Iodine 1.90x10 8 2.73x10
- e. Source Term Core Gap
- f. Release Assumption 100% of core N.G., 25% 100% of gap N.G., 25%
- 2. Containment Spray Effectiveness
- a. Removal half-life (hrs) 0.022 0.0075
- b. Number of operable spray pumps 1 2
- 3. Containment Leak Rate (%/day) 0.1 for 1st day, 0.05 for I st day, 0.05 after 1st day 0.025 after 1st day
- 4. Total Release to Environs, First 2 Hours, Ci
- a. Xe-133 16,840 56
- b. Other Noble Gases 25,930 21
- c. 1-131 191 0.05
- d. Other Iodine 1,325 0.08
- e. Release Mechanism Containment Leakage Containment Leakage EP RB-9u3rl3.DOC 03B 0203.1409
- 5. (x/Q) CL (sec/m 3 )
- a. 800m (site boundary) 5.29x1O4 5.29x10-5
- b. 10000m (6 mi. LPZ) 2.20x10 5- 2.20x10-6
- 6. Whole Body Dose Results
- a. Total 800m dose for 5.6E+00 3.7E-04 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 5.7E-01 6.4E-05
- 7. Thyroid Dose Results
- a. Total 800m dose for 9.6E+01 1.3E-03 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 1.8E+01 9.2E-04
- 8. Accident Classification (Based on above Dose): General Emergency Unusual Event (Based on EP G-1): Site Area Emergency Site Area Emergency
- 9. Miscellaneous
- a. Containment-free volume cc 7.36x10l°
- b. RCS Coolant Mass (gm) 2.4x10 8
- 10. References
- a. FSAR, September 1990, Revision 6, Section 15.5.
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6.
- 1. Initial Conditions and Assumptions
- a. Primary Coolant Activity (pCi/gm)
- 1) Xe-133 270 67.2
- 2) 1-131 2.6 0.65
- 3) Other Iodine 7.9 2.0
- b. Secondary Water Activity (gtCi/gm)
- 1) 1-131 1.5E-02 4.4E-05
- 2) Other Iodines 3.7E-02 9.OE-05
- c. Assumed Fuel Defects (%) 1 0.2
- d. Primary to Secondary Leakage (gpm) 1 0.014
- e. Steam Release, 1st Two Hours (lbs)
- 1) Failed Generator 162,784
- 2) Other generator (atmospheric dump) 393,464
- f. Total Steam Release During 8-Hour 1,250,000 Cooldown (lbs)
- g. Liquid Release Fraction for Iodine
- 1) Failed Generator 0.1
- 2) Other generators 0.01
- 2. Activity Release to Environs, First 2 Hours (Ci)
- a. Xe-133 1.2E-03 3.5E-07
- b. Other Noble Gases 1.9E-04 5.2E-08
- c. 1-131 1.6E-05 4.4E-09
- d. Other lodines 1.3E-04 3.6E-08
- a. 800m (site boundary) 5.29x1O4 5.29x10-5
- b. 10000m (6 mi. LPZ) 2.20x10-5 2.20x10-6
- 4. Whole Body Dose Results
- a. Total 800m dose for 1.7E-03 5.4E-07 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 2.6E-04 7.8E-08
- 5. Thyroid Dose Results
- a. Total 800m dose for 8.8E-02 1.6E-05 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 5.3E-02 9.9E-06
- 6. Accident Classification (Based on above Dose): Alert No Emergency (Based on EP G-1): Unusual Event Unusual Event
- 7. Miscellaneous
- a. Fluid Mass/Stm Gen (lbs)
- b. Safety Valve and Steam Dump Valve Capacities (lb/hr/valve)
- 1) S/G safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000
- 8. References
- a. FSAR, September 1990, Revision 6, Section 15.5
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 199:3, Table 4.6-19.
- 1. Initial Coolant Activity ([tCi/gm)
- a. Xe-133 270 45.7
- b. Other Noble Gases 30 5.6
- c. 1-131 2.62 0.45
- d. Other Iodine 7.88 1.35
- f. Fuel Defects (%) 1 0.2
- 2. Initial Release to Containment (Ci)
- a. Xe-133 65,430 16,280
- b. Other Noble Gases 7,950 1,980
- c. 1-131 63 16
- d. Other Iodine 193 48
- e. Assumption 100% of Coolant N.G. 100% of Coolant N.G.
- 3. Containment Spray Effectiveness
- a. Removal Coefficient (hr-1) 31 92
- b. Number of operable spray pumps 1 2
- 4. Containment Leak Rate (%/day) 0.1 for 1st day, 0.05 for 1st day, 0.05 after 1st day 0.025 after 1st day
- 5. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29xl0A4 5.29x10-5 5
- 6. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (Rem) 1.8E-04 4.4 E-06
- b. Total 10000m dose for 30 days (Rem) 5.OE-05 1.4E-06
- 7. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (Rem) 2.OE-04 9.0 E-07
- b. Total 10000m dose for 30 days (Rem) 3.OE-05 i.0E-07
- 8. Accident Classification (Based on above Dose): Unusual Event No Emergency (Based on EP G-1): Site Area Emergency Sit e Area Emergency
- 9. Miscellaneous
- a. Containment-Free Volume (cc) 7.36x10 10
- b. RCS Coolant Mass (gm) 2.4x10 8
- c. Liquid Release Fraction for Iodine 0.1
- 10. References a.. FSAR, Table 15.5-11.
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-17.
- 1. Initial Conditions and Assumptions (Pre-accident Iodine Spike Case)
- a. Primary Coolant Activity (ptCi/gm)
- 1) Xe-133 270 67.2
- 2) 1-131 (equivalent) 60
- 3) 1-131 41.4 0.65
- 4) Other Iodine 110.4 2.0
- b. Secondary Water Activity (gCi/gm)
- 1) 1-131 - 6.9E-02 4.4E-05
- 2) Other lodines 1.8E-01 9.OE-05
- c. Assumed Fuel Defects (%) I1 0.2
- d. Primary to Secondary Leakage (gpm)
- 1) Pre-existing 1 0.014
- 2) Tube Rupture 160
- e. Steam Release, 1st Two Hours (lbs)
- 1) Failed generator 146,700 31,000
- 2) Other generators (atmospheric 445,000 380,000 dump)
- f. Total Steam Release During 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1,530,000 1,500,000 Cooldown (lbs)
- g. Liquid Release Fraction for Iodine
- 1) Failed generator 0.01 *(1) 0.01
- 2) Other generators 0.01 *(1) 0.01 (1) 0.01 when rupture site is covered 1.0 when covered by less than 12" water EP RB-9u3rl3.DOC 03B 0203.1409
- 2. Total Release to Environs First 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Ci)
- a. Xe-133 2.8E+04 2.4E+03
- b. Other Noble Gases 2.OE+03 2.4E+02
- c. 1-131 5.5E+02 1.4E-01
- d. Other lodines 1.4E+03 6.2E-0 1
- a. 800 m (site boundary) 5.29x10-4 5.29x10-5
- b. 10000m (6 mi. LPZ) 2.20x10-5 2.20x10-6
- 4. Whole Body Dose Results
- a. Total 800m dose forl st two hours (Rem) 2.3E-01 7.7E-03
- b. Total 10000m dose for 30 days (Rem) 1.OE-02 3.OE-04
- 5. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (Rem) 1.9E+02 4.3E-03
- b. Total 10000m dose for 30 days (Rem) 8.OE+00 2.OE-04
- 6. Accident Classification (Based on above Dose): General Emergency Alert (Based on EP G-l): Site Area Emergency Site Area Emergency EPRB-9u3r13.DOC 03B . 0203.1409
- 7. Miscellaneous
- a. Fluid Mass/Steam Gen (lbs)
- 1) Water, 81,500
- b. Safety Valve and Steam Dump Valve Capacities (lbs/hr/valve)
- 1) S/G safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000
- 8. References
- a. FSAR; Revision 7, September 1991, Tables 15.5-64 thru 15.5-74.
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-16.
- 1. Total Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 2.7E+02 6.3E-06
- b. Other Noble Gases 5.5E+01 9.6E-06
- c. 1-131 8.6E-01 8.2E-08
- d. Other lodines 1.3E+00 2.8E-07
- e. Source Term Gap Gap
- f. Assumptions
- 1) Coolant Activity 1% fuel defects 0.2% fuel defects
- 2) Primary to Secondary Leakage I 0.014 (gpm)
- 3) Secondary Steam Release, 520,000 520,000 1st Two Hours (lbs)
- 4) Total Steam Release During 8 Hour 1,600,000 1,600,000 Cooldown (Ibs)
- 2. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29x10-4 5.29x10-5'
- b. 1000m (6 mi. LPZ) 2.20x10-5 2.20x10-6
- 3. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (Rem) 1.3E-02 1.6E-05
- b. Total 10000m dose for 30 days (Rem) 1.1E-03 1.2E-06
- 4. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (Rem) 3.OE-01 2.5E-04
- 5. Accident Classification (Based on above Dose): Alert No Emergency (Based on EP G-1) Alert Alert
- 6. Miscellaneous
- a. Fluid Mass/Steam Gen (Ibs)
- 1) Water 81,500
- b. Safety Valve and Steam Dump Valve Capacity (lbs/hr/valve)
- 1) S/G safety valve 800,000
- 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000
- c. Liquid Release Fraction for lodines 0.01
- 7. References
- a. FSAR, Tables 15.5-41 and 42.
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-14.
- 1. Initial Conditions
- a. Radial Peaking Factor of Damaged 1.65 1.26 Assembly
- b. Elapsed Time Since Reactor Shutdown 100 100 (hrs)
- c. Type of Release to Pool 100% of assembly gap 100% of assembly gap activity activity
- d. Bundle Submergence (fi) 26 26
- e. Pool Decontamination Factor for Iodine 100 760
- f. Total Assembly Gap Activity at Time of Accident
- 1) Xe-133 100,000 8,137
- 2) Other Noble Gases 4,500 1,500
- 3) 1-131 52,670 5,282
- 4) Other Iodines 7,000 220
- 5) Source Spent Fuel Spent Fuel
- 2. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29xl0-4 5.29x10-5
- b. 1000m (6 mi. LPZ) 2.20x10-5 2.20x1 0-6
- 3. Total Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 100,400 523
- b. Other Noble Gases 4,100 101 C. 1-131 80 0.005
- d. Other Iodines 10 0.0002
- e. Source Term Spent Fuel Spent Fuel EPRB-9u3rl3.DOC 03B 0203.1409
- 4. Whole Body Dose Results
- a. Total 800m dose for 1st two hours (Rem) 2.5E+00 1-.5E-03
- b. Total 10000m dose for 30 days (Rem) L.OE-01 6.1E-05
- 5. Thyroid Dose Results
- a. Total 800m dose for 1st two hours (Rem) 2.2E+01' 8.2E-05
- b. Total 10000m dose for 30 days (Rem) 9.2E-01 3.4E-06
- 6. Accident Classification (Based on above dose): General Emergency Alert (Based on EP G-1): Site Area Emergency Site Are a Emergency
- 7. Miscellaneous
- a. Fuel Handling Building Volume (ft 3) 435,000 b.. Fuel Handling Building Exhaust Rate 35,700 35,700 (cfm)
- c. Filter Cleanup Factor 0.10 0.01
- 8. References
- a. FSAR, Tables 15.5-43 through 15.5-47.
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-22.
- 1. Initial Conditions
- a. Radial Peaking Factor of Damaged 1.65 1.26 Assembly
- b. Elapsed Time Since Reactor 100 100 Shutdown (hrs)
- c. Type of Release to Pool 100% of assembly gap 100% of assembly gap activity activity
- d. Bundle Submergence (ft) 26 26
- e. Pool Decontamination Factor for Iodine '100 760
- f. Total Assembly Gap Activity at Time of Accident (Ci)
- 1) Xe-133 100,000 8,137
- 2) Other Noble Gases 4,500 1,500
- 3) 1-131 52,670 5,282
- 4) Other Iodines 7,000 220
- 5) Source Term Spent Fuel Spent Fuel
- 2. (x/Q) CL (sec/m3)
- a. 800m (site boundary) 5.29x10-4 5.29x10-5
- b. 1000m (6 mi. LPZ) 2.20x10-5 2.20x10-6
- 3. Total Release to Environs, 1st TwoHours (Ci)
- a. Xe-133 12,460 38
- b. Other Noble Gases 557 7
- c. 1-131 65 0.033
- d. Other Iodines 8.7 0.0013
- e. Source Term Spent Fuel Spent Fuel EP RB-9u3rl3.DOC 03B 0203.1409
- 4. Whole Body Dose Results
- a. Total 800m dose for 3.1E-01 1.0E-04 1st two hours (Rem)
- b. Total 10000m dose 1.3E-02 4.0E-06 for 30 days (Rem)
- 5. Thyroid Dose Results
- a. Total 800 m dose for 1.8E+01 6.0E-04 1st two hours (Rem)
- b. Total 10000m dose 7.6E-01 3.0E-05 for 30 days (Rem)
- 6. Accident Classification (Based on above Dose): General Emergency Alert (Based on EP G-1): Site Area Emergency Alert
- 7. Miscellaneous Activity Activity released from cavity to containment Release Mechanism atmosphere is confined directly above the cavity water level. It is picked up by the fan coolers and sent out through the containment purge.
- 8. References
- a. FSAR, Tables 15.5-48 through 15.5-50.
- b. DCM No. T-15, Radiation Protection, Rev. 0, February 1993, Section 4.6.7.21.
- 1. Total Release to Containment Free Volume (Ci) 5 5
- a. Xe-133 2.01x10 1.52x10
- b. Other Noble Gases 6.82x1 04 6.22x104 3
- c. 1-131 7.32x103 7.28x10
- d. Other Iodine 1.1 lx10 4 1.09x10 4
- e. Source Term Gap. Gap
- f. Release Assumption Coolant activity (1% Coolant activity (0.2%
- 2. Containment Spray Effectiveness
- a. Removal half-life (hrs) 0.022 0.0075
- b. Number of operable spray pumps 1 2
- 3. Containment Leak Rate (%/day) 0.1 0.05
- 4. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29x10-4 5.29x10-5
- b. 1000m (6 mi. LPZ) 2.20x10-5 2.20x10-6
- 5. Total Release to Environs, 1st 2 Hours (Ci)
- a. Xe-133 11.2 5.6
- b. Other Noble Gases 4.1 2.0
- c. 1-131 0.0098 0.002
- d. Other Iodine 0.015 0.002
- e. Source Term Gap Gap
- f. Release Mechanism Containment Leakage Containment Leakage EPRB-9u3rl3.DOC 03B 0203.1409
- 6. Whole Body Dose Results
- a. Total 800m dose for 7.3E-04 3.6E-05 1st two hours (Rem)
- b. Total 1000 n dose 1.3E-04 6.4E-06 for 30 days (Rem)
- 7. Thyroid Dose Results
- a. Total 800m dose for 3.3E-03 3.7E-05 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 1.4E-04 1.6E-06
- 8. Accident Classification (Based on above Dose): Unusual Event No Emergency (Based on EP G-l): Site Area Emergency Site Area Emergency
- 9. Miscellaneous
- a. Containment free volume (cc) 7.36x1010
- b. RCS Coolant Mass (gm) 2.4x108
- 10. References
- a. FSAR, Table 15.5-52.
- b. DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-13.
- 1. Total Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 65,400 16,300
- b. Other Noble Gases 7,300 2,140
- 2. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29x104 5.29X10-5 6
- b. 10000m (6 mi. LPZ) 2.20x1o-5 2.20x10-
- 3. Whole Body Dose Results
- a. Total 800m dose for 2.OE+00 4.4E-02 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 8.4E-02 1.8E-03 NOTE: Thyroid doses are negligible.
- 4. Accident Classification (Based on above Dose): General Emergency Site Area Emergency (Based on EP G-1): Alert Alert
- 5. Miscellaneous
- a. Tank Volume (cc) 2.18x10 7
- b. Tank Press (psi) 100 c.- Volume Released (cc) 1.48x10 8
- 6. References
- a. FSAR, Table 15.5-53.
- b. DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-23.
- 1. Activity in Holdup Tank (Ci)
- a. Xe-133 51,000 10,200
- b. Other Noble Gases 4,710 930
- c. 1-131 492 98.3
- d. Other lodines 1,086 217
- 2. Cleanup Parameters
- a. Liquid Release Fraction for lodines from 10-4 10-4 Tank to Auxiliary Building Atmosphere
- b. Charcoal Filter Cleanup Factor 0.1 0.01
- c. Release Duration (hrs) 2 2
- 3. Activity Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 51,000 10,200
- b. Other Noble Gases 4,710 930
- c. 1-131 0.00492 9.8E-5
- d. Other lodines 0.01086 2.17E-4
- 4. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29xl0-4 5.29x10-5
- b. 10000m (6 mi. LPZ) 2.20x10-5 2.20x10-6
- 5. Whole Body Dose Results
- a. Total 800m dose for 1.4E+00 3.7E-02 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 6.OE-02 1.6E-03 EPRB-9u3rl3.DOC 03B 0203.1409
- 6. Thyroid Dose Results
- a. Total 800m dose for 1.9E-03 2.6E-06 1st two hours (Rem)
- b. Total 10000m dose 8.0E-05 1.1E-07 for 30 days (Rem)
- 7. Accident Classification (Based on Dose): Site Area Emergency Site Area Emergency (Based on EP G-i): Alert Alert
- 8. Miscellaneous
- a. Tank Volume (cc) 3.03x108
- 9. References
- a. FSAR, Table 15.5-56.
- b. DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-24.
- 1. Activity in VCT (Ci)
- a. Xe-133 3,330 828
- b. Other Noble Gases 198 42
- c. 1-131 12.1 3.0
- d. Other lodines 35 8.7
- 2. Cleanup Parameters
- a. Liquid Release Fraction for Iodines from 10- 4 10-4 Tank to Auxiliary Building Atmosphere
- b. Charcoal Filter Cleanup Factor 0.1 0.01
- c. Release Duration (hrs) 2 2
- 3. Activity Release to Environs, 1st Two Hours (Ci)
- a. Xe-133 3,330 828
- b. Other Noble Gases 198 42
- c. 1-131 0.00012 3E-6
- d. Other lodines 0.00035 9E-6
- 4. (x/Q) CL (sec/m 3)
- a. 800m (site boundary) 5.29x104 5.29x10-5 5 2.20x10-6
- b. 1000m (6 mi. LPZ) 5.20xi0-
- 5. Whole Body Dose Results
- a. Total 800m dose for 4.7E-01 9.3E-03 1st two hours (Rem)
- 6. Thyroid Dose Results
- a. Total 800m dose for 3.3E-05 4.4E-08 1st two hours (Rem)
- b. Total 10000m dose for 30 days (Rem) 1.4E-06 1.8E-09
- 7. Accident Classification (Based on Dose): Site Area Emergency Alert (Based on EP G-1): Alert Alert
- 8. Miscellaneous
- a. Tank Volume (cc) 7 1.1x10
- 9. References
- a. FSAR, Table 15.5-57.
- b. DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-25.
- b. Calculate the "Noble Gas Concentration" using the Monitor Response Factor from Figure 1, 2, or 3.
- b. Calculate and record below "Noble Gas Release Rate."
- EP RB-9u3r13.DOC 03B 0203.1409
- b. Calculate and record below the "1-131 Collection Rate."
- b. Calculate and record "1-131 Release Rate.!"
- DIABLO CANYON POWER PLANT EP RB-9 ATTACHMENT 7.2 1 ND TITLE: Noble Gas and 1-131 Equivalent Release Rates for a Steam Release SECTION 1 - GENERAL INFORMATION 1.1 Enter the following information: Unit # __
- If less than 4E5 lb/hr, record and use 4E5 lb/hr.
- b. Record in Section 3.1 .h below the "RCS Sample Activity Concentrations" for noble gases, iodines, and particulates.
- c. Determine the faulty steam generator water level using the Narrow Range Level indication:
- e. Determine the "Density Correction" using the water level indicated in Section 3.1 .c. Record the "Density Correction" below.
- f. Calculate and record below the "Steam Activity Concentrations" for noble gases, iodines, and particulates by multiplying each "RCS Sample Activity Concentration," times each "Steam Partition Factor" times "Density Correction."
- g. Calculate and record below the "Total Steam Activity Concentration" by summing the "Steam Activity Concentrations" for noble gases, iodines, and particulates.
- h. Calculate and record below the "Steam Activity Fractions" for noble gases, iodines, and particulates by dividing each "Steam Activity Concentration" by the "Total Steam Activity Concentration." Go to Section 4 or 5..
- b. Determine the FSAR "Steam Activity Fractions". for noble gases, iodines, and particulates using the water level indicated in Section 3.2.a. Record the "Steam Activity Fractions" in Section 4.2.c.
- b. Calculate and record the "MSL Activity Concentration" using the appropriate "MSL Monitor response from Figure 5.1, 5.2, or 5.3.
- b. Enter the "MSL Activity Concentration" from Section 4.1 and the "Steam Flow Rate" from Section 2.3.
- c. Calculate and record "Isotopic Release Rate" for noble gases, iodines, and particulates. Go to Section 6.1.
- b. Enter the "Primary to Secondary Leak Rate."
- c. Calculate and record "Isotopic Release Rate" for noble gases, iodines, and particulates. Go to Section 6.1.
- b. Determine "Iodine TEDE Conversion Factor" using Figure 6.1 and "Iodine Thyroid CDE Conversion Factor" using Figure 6.2 and record below.
- b. Calculate and record "1-131 TEDE Equivalent Release Rate" and the 1-131 Thyroid CDE Equivalent Release Rate.
- ISSUED FOR USE BY: DATE:. EXPIRES:____
- 1. SCOPE 1.1 This procedure provides instructions for the use of the Emergency Assessment Response System (EARS) interface.
- 2. DISCUSSION 2.1 EARS is the computer system that obtains and processes plant meteorological and radiological data to determine release rates for use in dose assessment calculations.
- 3. DEFINITIONS None
- 4. RESPONSIBILITIES 4.1 The Emergency Supervising Engineer or Health Physicist is responsible for performing this procedure in support of dose assessment for the UDAC. In the event of failure of the EARS computer in the EOF/UDAC, the Radiological Data Processor or Radiological advisor in the TSC may perform dose assessment calculations.
- 5. INSTRUCTIONS 5.1 Starting EARS 5.1.1 Two EARS workstations are available to the ERO. One EARS computer is located in the Unified Dose Assessment Center (UDAC) section of the EOF.
- a. The Program is started by double-clicking the "Shortcut to EARS" button. You will be prompted to select either:
- Drill (program uses emergency preparedness drill files), or
- Emergency (program uses actual monitored.data)
- b. After you make your selection, click "OK" to continue.
- c. After you click OK, the program will take a few seconds to load source term and radiation monitor data and then prompt you for your USER ID.
- d. Click "OK". The program will then begin "Initializing the Met data",
- e. When complete, the program will load the main input screen, which will require several user inputs based on the release path selected.
- f. Verify the current date and time information is in the "Reactor Shutdown!', "Release Start" and the "Update" Date/Time fields.
- g. If the dates and times are correct, proceed with step 5.3 (skip 5.2).
- h. If the dates and times are incorrect, proceed with step 5.2.
- a. Enter a "quarter hour" time of at least 30 minutes previous to now in both the "Reactor Shutdown" and "Release Start" Date/Time fields.
- b. Enter a "quarter hour" time in the "Update" Date/Time field - 15 minutes later than the release start time entered in step 5.2.1 a.
- c. Click the "Calculate" button
- d. Click "OK" in the "Validate Inputs" screen. There will be up to a one minute delay while EARS performs that release rate calculation (the program will automatically print an input report with all the assumptions being used for the calculation)
- e. Click "OK" (Green button) when the "MIDAS Accident Dose Calculation" screen is displayed
- f. Click "Start Calc" (Green button) when the "MIDAS Accident Dose Calculation Diablo Canyon Menu A" screen is displayed. The program will then display the TEDE plot.
- g. Click "OK" when the "Print" dialogue box is displayed
- h. Click upper right comer X to Close the report (Word document) window and return to the MIDAS graphical display (the program will automatically print a projected dose report with all the assumptions being used for the calculation).
- i. Click "End Run" to exit MIDAS
- j. Select "Exit without saving" and click OK
- k. Select "Quit" from the Menu Bar
- 1. Select "Yes" to quit EARS when the following dialog box appears:
- Select "Quit" from the Menu Bar 0 Select "Yes" to Quit e Restart the program by double-clicking the EARS icon 5.4.2 Three pieces of time information are needed prior to initiating an EARS run:
- Core (typically indicated by RE-30 or RE-3 1 reading greater than 300R/hr)
- FSAR reactor coolant (RE-30 or RE-31 read less than lR/hr and known fuel defects have occurred)
- U1 or U2 Reactor Coolant (which is updated every six months)
- Manual (This pathway is only to be used if the defined pathways do not match the release)
- a. Parameters (and options) needed for each pathway are provided in the attachments to this procedure. For assistance in determining the appropriate pathway, refer to:
- PEP EN-1, Attachment 8.7, "Emergency Engineering Guideline Computational Aids."
- Containment to GE/GW to Plant Vent (Attachment 9.2)
- Containment to Fuel Handling Building to Plant Vent (Attachment 9.3) 0 Containment Sump to Auxiliary Building to Plant Vent (Attachment 9.4)
- Steam Generator to GE/GW to Plant Vent (Attachment 9.5)
- CVCS to Auxiliary Building to Plant Vent (Attachment 9.6)
- CCW to Auxiliary Building to Plant Vent (Attachment 9.6)
- Spent Fuel Pool to Fuel Handling Building to Plant Vent (Attachment 9.7) 5.6.5 Steam Releases
- Steam Generator Tube Rupture to Atmosphere (Attachment 9.8) 5.6.6 Containment to Atmosphere (not via Plant Vent)
- Design Basis leakage to the atmosphere (Attachment 9.9) 5.6.7 Other - Manually specified release information
- Manual entry of meteorological and release rate information (Attachment 9.11)
- a. Observe the RMDDT or PDN met data screen to observe when the "quarter hour" update occurs. Once the PDN met data populates with the update time corresponding to the EARS update time, go back to step 5.7.1.
- a. LAST 24 HOUR DOSE (MENU F) - Need more information here.
- b. MANUAL SPREADSHEETS (MENU X) - This method allows you to manually enter meteorological and radiological release data in spreadsheet form. This process can be used for release rates that were calculated manually, not from direct access to the RMS. To perform these calculations, use Attachment 9.13, MIDAS Menu X.
- a. Points of interest are any place on the map (within the plume or plume pathway) that individual data is needed. Estimated dose rates, concentrations or other information can be obtained by loading the appropriate map.
- b. To obtain dose information for any POI, first load the map with the type of information you need (TEDE, Thyroid CDE, EDE, etc.)
- c. Size the map to an appropriate distance by zooming in or out. This can be done by right-clicking the mouse. This can also be done by drawing a rectangle around the area. Additionally, you may change the scale of the map (See Section 5.8.11).
- e. Point and click the mouse to the area of interest on the map. The requested information will appear on the screen. You may click multiple areas of the map.
- f. To remove the point of interest data, click the "POI Active" button. This will toggle the button back to "POT" and clear the numerical data from the map.
- a. First select the TEDE button. Button will be high-lighted in light green.
- b. Select "integrated dose" or "dose rate" by toggling the yellow "Dose" button.
- c. Select the exposure time by toggling the yellow time button. Options for duration are:
- 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> (15 minute puff release)
- 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> - default
- 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- d. Select graphic or table output by toggling the yellow graphic/table button.
- e. Click the flashing pink "Confirm" Button to access the data.
- f. Print the screen graphic or tabular data report.
- a. First select the Thyroid CDE button. Button will be high-lighted in light green.
- b. Select "integrated dose" or "dose rate" by toggling the yellow "Dose"
- button.
- c. Select the exposure time toggling the yellow time button. Options for duration are:
- 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />
- 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> - default
- 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> EP RB-16u3r02.DOC 03B 0203.1245
- d. Select graphic or table output by toggling the yellow graphic/table button (default is graphic).
- e. Click the pink "Confirm" Button to access the data.
- f. Print the screen graphic (preferred) or tabular data report.
- a. First select the EDE button. Button will be high-lighted in light green.
- b. Select the exposure time toggling the yellow time button
- 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> - default
- 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- c. Select graphic or table output by toggling the yellow graphic/table button.
- d. Click the pink "Confirm" Button to access the data.
- e. Print the screen graphic or tabular data report.
- Gamma
- Gamma + Beta
- Thyroid They can be printed as tabular data or displayed as a graphic. This information can be used to determine the correlation between estimate field monitoring data and actual field monitoring data.
- a. 4-day TEDE Report - is prepared for each calculation (State Report).
- b. Ingestion Summary Report - This report includes information for the following pathways:
- Air concentration 0 Skin dose
- Ground contamination
- Cow milk
- Meat concentration
- Vegetation concentration
- Ground shine;
- c. Met/Rad Summary - Includes isotopic release listing and summary of the meteorological parameters
- d. RMP - This function is not currently available
- e. Projection Summary - Dose summary versus PAGs for release durations of 0.25, 3, 8, and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5.8.9 Ingestion Pathway
- a. Five isotopes are considered for ingestion pathway factors:
- 1-131
- Cs-134
- SR-89
- SR-90 EPRB-16u3r02.DOC 03B 0203.1245
- b. Seven exposure pathways may be considered for Ingestion Pathway calculations:
- Air concentration (any of the five isotopes listed above)
- Ground deposition (any of the five isotopes listed above)
- Cow Milk (any of the five isotopes listed above)
- Vegetation (any of the five isotopes listed above)
- Meat (any of the five isotopes listed above)
- Skin dose (Integrated skin dose equivalent -'1 year dose) can be calculated for exposure times of 0.25, 3, 8, or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> based on user input)
- Ground Committed Dose
- Initial
- I day
- 4 days
- !year
- 2nd year
- 50 years Each isotope can be selected in conjunction with the type of data requested to produce either a table of expected dose or a graphical representation of the expected dose.
- Depleted Iodine - deposited iodine is removed from the plume 0 Depleted Particulate - deposited particulates are removed from the plume
- Deposited particulate - deposition rate for particulates 5.8.11 Changing Map Scale The map radius is typically set to 20 miles. You can re-set this value by clicking the button marked Miles". Type in the new radius in the dialogue box and click "ENT."
- File - stores JPEG to file. You must enter a file name. The plot will be stored on the server and be able to be viewed by other workstations.
- Field Monitoring teams a Emergency Response Units 0 Monitor Locations
- Law Enforcement teams Text may be attached to the graphics (ex. FMT-1). Once the item is added to the map, you may click and drag the icon to a new location.
- a. Click on the Map Features button to add the following features typically used for each MIDAS run:
- 1. To view FMT radiation monitoring points on the plume maps, referred to in MIDAS as RMPs (radiation monitoring points), click on the "RMPs" box and select either onsite or offsite points
- 3. Click "OK" to return to plume map screen.
- Auto Increment - provides automatic time data for the calculation sequence (every 15 minutes)
- AutoPollMonitors - Toggles on and off for automatically polling information from the plant radiation monitoring system and the meteorological tower. If it is turned off the user can manually enter data into yellow shaded fields.
- Electrical Bus - the program allows you to select the busses that are in service. This information is used to allow you to determine the exhaust flow rate through the plant vent if the flow monitor is not working. The program will only allow you to select fans for busses that are in service.
- Bus F (E-1 Fan, GE/GW Fan)
- Bus G (E-5 Fan)
- Bus H (E-2 Fan, E-6 Fan)
- Bus I (E-3 Fan, E-4 Fan) 5.11.3 VIEW Three data sources may be viewed under this section:
- a. Met Data - Click "View" and "Met Data" to provide a window with the current readings from the primary and back-up meteorological towers.
- b. Release Source - Click "View" and "Release Source" to open a'window with the current source term (isotopic listing in total curies). To close the window, re-click "View" and "Release Source."
- c. Release Rate - Click "View" and "Release Rate" to open a window with the calculated isotopic release rates for the parameters selected (source term and pathway information). To close the window, re-click "View" and "Release Rate."
- a. When the "MIDAS - Accident Dose Calculation" window appears, select the "Recap Previous Run" option.
- b. Next, select the previous run from the list of saved files.
- c. Then click "OK" to load the historical data file.
- 6. RECORDS None
- 7. APPENDICES None
- 8. REFERENCES 8.1 EP RB-9, "Calculation of Release Rate" 8.2 EP EF-3, "Emergency Operations Facility" 8.3 PEP EN-1, "Emergency Engineering Guideline Computational Aids" 8.4 NUREG 0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness' in Support of Nuclear Power Plants" EP RB-16u30I2.DOC 03B 0203:1245
- 9. ATTACHMENTS 9.1 "Path I - Containment Purge to the Plant Vent," 12/09/05 9.2 "Path 2 - Release to the Plant Vent through the GE/GW Area," 12/09/05 9.3 "Path 3 - Containment Release to the Plant Vent through the Fuel Handling Building,"
- 1. Select Exhaust Fans Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, which will then be summed to create a total flow rate to the Plant Vent. Fans that can be selected are limited based on the busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms No editable filtration mechanisms are provided for this pathway. Containment Purge Exhaust bypasses the plant vent filter trains (charcoal and HEPA) and vents directly to the atmosphere.
- 3. Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- R-14
- 4. Set Containment Spray Status (95% reductioin of iodine source term).
- 5. When you have finished entering data for the release path click the "Calculate" button.
- 6. Return to step 5.7 of this procedure.
- 1. Select Exhaust Fans Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, which will then be summed to create a total flow rate to the Plant Vent. Fans that can be selected are limited based on the Busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms No editable filtration mechanisms are provided for this pathway. The exhaust stream cannot be routed through HEPA or charcoal filters.
- 3. Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- 4. Set Containment Spray Status (95% reduction of iodine source term)
- 5. When you have finished entering data for the release path click.the "Calculate" button.
- 6. Return to step 5.7 of this procedure.
- 1. Select Exhaust Fan Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, which will then be summed to create a total flow rate to the Plant Vent. Fans that can be selected are limited based on the Busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms No editable filtration mechanisms are provided for this pathway.
- 3. Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- R-14
- R-14R
- R-87 You may also select a checkbox to use RE-24 when RE-24/24R is running. RE-24 provides better scaling information for a gap release. Before selecting RE-24/24R, ensure that the monitor is operating and on-scale.
- 4. Set Containment Spray Status (95% reduction of iodine source term)
- One - One train has been used to remove for removal
- 5. When you have finished entering data for the release path click the "Calculate" button.
- 6. Return to step 5.7 of this procedure.
- 1. Select Exhaust Fan Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, which will then be summed to create a total flow rate to the Plant Vent. Fans that can be,selected are limited based on the Busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms Releases through the Auxiliary Building can be filtered using particulate filters (HEPA) or iodine filters (Charcoal) or both.
- 3. Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- R-14 e R-14R
- R-29
- R-87 You may also select a checkbox to use RE-24 when RE-24/24R is running. RE-24 provides better scaling information for a gap release. Before selecting RE-24/24R, ensure that the monitor is operating and on-scale.
- 4. When you have finished entering data for the release path click the "Calculate" button.
- 5. Return to step 5.7 of this procedure.
- 2. Filtration' No editable filtration mechanisms are provided for this pathway.
- 3. Radiation Monitors The following radiation monitors are available for use in calculating release rates from this pathway:
- R-29
- R-87 You may also select a checkbox to use RE-24 when RE-24/24R is running. RE-24 provides better scaling information for a gap release. Before selecting RE-24/24R, ensure that the monitor is operating and on-scale.
- 4. Water Level in the Affected Steam Generator Three options are provided for water level in the Steam Generator:
- Flooded (>96% level): all iodines and particulates are assumed to be released.
- Normal (13% to 96% level): 1% of iodines and 1% of particulates are assumed to be released.
- 5. When you have finished entering data for the release path click the "Calculate" button.
- 6. Return to step 5.7 of this procedure.
- 1. Select Exhaust Fan Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, Which will then be summed to create a total flow rate to the Plant Vent. Fans that can be selected are limited based on the Busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms Releases through the Auxiliary Building can be filtered using particulate filters (HEPA) or iodine filters (Charcoal) or both.
- 3. Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- R-14 e R14R
- R-29 o R-87 You may also select a checkbox to use RE-24 when RE-24/24R is running. RE-24 provides better scaling information for a gap release. Before selecting RE-24/24R, ensure that the monitor is operating and on-scale.
- 4. When you have finished entering data for the release path click the "Calculate" button.
- 5. Return to step 5.7 of this procedure.
- 1. Select Exhaust Fans Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, which will then be summed to create a total flow rate to the Plant Vent. Fans that can be selected are limited based on the Busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms Releases through the Auxiliary Building can be filtered using particulate filters (HEPA) or iodine filters (Charcoal) or both.
- 3. Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- 4. When you have finished entering data for the release path, click the "Calculate" button.
- 5. Return to step 5.7 of this procedure.
- 1. Select Exhaust Fan Status The default setting for flow for a release through the Plant Vent is "Use FM 12." FM 12 has a maximum flow rate of approximately 250,000 cfm. If you de-select "Use FM 12" you will be able to select individual fans, which will then be summed to create a total flow rate to the Plant Vent. Fans that can be selected are limited based on the Busses in service. Status of busses should be monitored throughout the event.
- 2. Select Filtration Mechanisms Releases through the.Auxiliary Building can be filtered using particulate filters (HEPA) or iodine filters (Charcoal) or both.
- 3. 'Select Radiation Monitors to use for the Calculation The following radiation monitors are available for use in calculating release rates from this pathway:
- R-14
- R-29'
- R-87 You may also select a checkbox to use RE-24 when RE-24/24R is running. RE-24 provides better scaling information for a gap release. Before selecting RE-24/24R, ensure that the monitor is operating and on-scale.
- 4. When you have finished entering data for the release path click the "Calculate" button.
- 5. Return to step 5.7 of this procedure.
- 1. Select Affected Steam Generator Select the number of the affected Steam Generator (1-4). The radiation monitor (RM-7I-74) for the affected steam generator will be used for performing calculations.
- 2. Select Release Flow Parameters The release flow for this pathway may be determined using either of the following methods:
- Select the Percent demand from the "Pct Demand" dropdown box. You may need to contact the Control Room to get this information.
- 3. Water Level Three options are provided for water level in the Steam Generator:
- Normal (13% to 96% level): 1% of iodines and 1% of particulates are assumed to be released.
- 4. When you have finished entering data for the release path, click the "Calculate" button.
- 5. Return to step 5.7 of this procedure.
- 1. Set Containment Spray Status (95% reduction of iodine source term)
- 2. Radiation Monitors Either of the containment high range monitors (RM-30 or RM-3 1) may be used for this calculation.
- 3. Core Damage Assessment This field is not editable. An estimate of core damage (% of source term) is provided based on the readings on the containment high-range monitors.
- 4. Return to step 5.7 of this procedure.
- 1. Select the "Manually Specify" data entry tab
- 2. Select a source term appropriate for the event
- 3. Select a volume that the source term will be diluted by prior to release
- a. Specify a volume
- b. Reactor Coolant System volume
- c. Containment
- 4. Select a percentage of the source term that is going to be released to the dilution volume
- 5. Determine the partitioning factors for each radionuclide group (fraction of the group that will be retained in the dilution volume)
- 6. Determine the clean-up factors for the radionuclide groups (fraction of the group that will be retained by any cleanup process that may be applied to the release (filters)
- 7. Specify the flow rate for the release to the environment
- 8. Specify the flow rate units (the system will convert the units to standard units)
- 9. When you have finished entering data, initiate the calculation by clicking "Calculate."
- 10. Return to step 5.7 of this procedure.
- 1. If you are starting from the EARS Main Menu, click "Calculate." If you are starting from the "MIDAS - Accident Dose Calculation."
- 2. Click "OK" to accept the meteorological data as presented or editas necessary.
- 3. Click "Start CaIc." The program will display a dialog box for the printer.
- 4. Click "OK" to print the Dose Summary Report.
- 5. Click the upper-right-hand "X" to close the report. This will return you to the plot of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report.
- 6. To print a copy of the plot use the printer icon.
- 7. To return to the EARS Main Input screen, click "End Run."
- 1. After starting the MIDAS program, select "MANUAL SPREADSHEETS (MENU X).
- 2. Review the first data panel (Data Source), make any necessary changes and select the "Next" arrow.
- 3. Review the second data panel, make any necessary changes and select the "Next" arrow.
- 4. Select "isotopic spreadsheet" or "isotopic preset spreadsheet." If you chose the preset option you will need to also make a selection from the available spreadsheets.
- 5. Click "Confirm."
- 7. Click "OK" to open the spreadsheet for meteorological data.
- 8. Enter data for the release period for all meteorological parameters.
- 9. Click "OK" when finished.
- 10. Enter isotopic release rates for all isotopes that have a calculated release rate. Enter data for each time period that information is available.
- 11. Click "OK" when finished.
- 12. Review Menu X input, and then click "Next."
- 13. Click "Start Cale."
- 14. Click "OK" to print results.
- ISSUED FOR USE BY: DATE: EXPIRES:____
- 1. SCOPE 1.1 This procedure describes the steps to be taken by on-shift personnel to initially evaluate the off-site consequences of an accidental airborne release that may result in Emergency Plan Activation.
- 2. DISCUSSION 2.1 An accidental airborne release of radioactive materials that may result in site boundary dose rates in excess of the limits specified in the EP G-1 shall require a prompt initial assessment by the operating staff. This initial release rate and dose assessment is performed using either the Plant Data Network (PDN) program "EPR2net", or manually using Section 7 of this procedure.
- 3. DEFINITIONS 3.1 Accidental Release: A release of radioactive material unrelated to any planned effluent release evolutions.
- 4. RESPONSIBILITIES 4.1 Emergency Evaluation Coordinator (EEC) is responsible for performing an initial assessment of an airborne radiological release when directed by the'ISEC.
- 5. PREREQUISITES 5.1 Unified Dose Assessment Center (UDAC) is not activated and performing the function of radiological assessment.
- Alarms occur on in-plant continuous air monitors (CAM)s.
- A fire occurs involving radioactive matenials.Ref118
- Verified alarm on radiation monitors RE-14/14R, RE-28/28R, RE-29, RE-15/15R, or RE-24/24R.
- 6. PRECAUTIONS 6.1 Do not use SPDS to obtain RMS readings. Radiological Monitor readings off SPDS may be based on different units of measurement than required as input to the calculations.
- 7. INSTRUCTIONS This calculation can be performed using the Plant Data Network (PDN) program "EPR2net" or by long hand, as follows:
- a. A sample of the radioactive effluent (if possible) and in-plant airborne activity.
- b. A confirmatory assessment of the site boundary dose rate from the release.
- 8. RECORDS 8.1 All checklists generated during activation of the EOF for drills and exercises are non-quality Good Business Records and shall be retained by Emergency Planning Group for three years.
- 9. APPENDICES None
- 10. ATTACHMENTS 10.1 "Release Rate Calculations," 02/03/09 10.2 "Off-Site Dose Calculations," 08/05/94 10.3 "EPR2NET Application," 10/20/08 10.4 "Plant Vent Release," 10/20/08 10.5 "Atmospheric Steam Release," 10/20/08
- 11. REFERENCES 11.1 EP G-1, "Accident Classification and Emergency Plan Activation."
- 1. GENERAL INFORMATION Date: Time: Assessment No.
- 2. PLANT VENT FLOW RATE DETERMINATION A. DIRECT - Plant Vent Flow Rate FR-12 (0-30x10 4 CFM (CFM) = (CFM)
- 3. RELEASE RATE CALCULATION CAUTION: Do NOT use SPDS to obtain monitor readings.
- 2. STEAM RELEASES - Use this form to calculate steam releases to the atmosphere WHEN NOT critical.
- 3. RADIATION MONITOR FACTORS (Determined based on S/G NR Level indication) (Enter in Section 4 below.)
- 4. RELEASE RATE CALCULATIONS A. TOTAL EFFLUENT RELEASE RATE (RE-7x)
- 1. SOURCE TERM SELECTION AND DEFAULT RELEASE RATES NOTE: Use default release rate only if actual data is not available or if the release is not being monitored.
- 1. GENERAL INFORMATION Date: Time: Assessment No.
- 2. METEOROLOGICAL DATA- PPC (Plant Process Computer)
- 3. DCF Determination - Select the most appropriate source term for the DCF using the criteria in Attachment 10.1. Circle the corresponding DCF in Section 4 below.
- 4. DOSE CALCULATIONS - (From data calculated using Attachment 10.1)
- 5. REPORTING THE RESULTS - (Refer to Section 7.3 of Instructions for details)
- 1. Start EPR2NET
- a. OPEN the epr2net application:
- 1) Click on.the "epr2net" icon on.the PDN Console
- 2) IF icon is unavailable, THEN type <http://172.16.20.2/epr2net> in the Internet Explorer "address" field and press FENTER].
- b. Select the Unit Specific release path button lant Ven or ISteam Releas
- c. For Plant Vent Release data entry, GO TO Attachment 10.4.
- d. For Atmospheric SteamRelease data entry, GO TO Attachment 10.5.
- a. Enter the "Assessment" number
- 2. Plant Vent Flow Rate Determination:
- a. Validate "DIRECT" plant vent flow rate indicates "OK" in the box to the right of the flow rate.
- b. IF the box says: "UNREL" instead of "OK",
- 3. Release Rate Calculation:
- a. Noble Gas Release Rate For Ongoing Release:
- 1) IFon scale, AND indicates "OK" to the right of the activity value, THEN select RM-14 or RM-14R, which ever is-higher
- 2) IF.both RM-14 and RM-14R indicate "UNREL" AND RM-87 equals IE-12 amps THEN select RM-29.
- 3) IF RM-14 or RM-14R is off scale (5E6 cpm is top of scale)
- 4) IF RM-87 indicates "UNREL" instead of "OK",
- 1) Attempt to perform the calculation at the peak monitor reading (RM-14, RM-87 or RM-29 as appropriate) for the duration of the release.
- b. Release Rate Calculation, Total Effluent Release Rate
- 1) Select the appropriate source term (click on "HELP" for guidance).
- 2) Single Click the "NEXT" button at the bottom of the page. This\will open a Dose Calculations window.
- 3) IF more than one Dose Calculations window is open, THEN close all open Dose Calculations windows and click the "NEXT" button at the bottom of the Plant Vent Release page. This will open a Dose Calculations window.
- 1. General Information
- a. Validate current date and time, assessment number, and unit releasing number are the same as the Plant Vent Release page.
- 2. Meteorological Data - PPC
- a. Select Desired Met Data (Primary or Backup)
- 1) Primary is preferred to backup.
- 2) Do not select if any of the 3 parameters indicates "UNREL"
- 3) If both met towers have "UNREL" data, perform a long hand calculation using Attachment 10.1.
- 3. DCF Determination
- a. This carries over from the Plant Vent Release page (do not edit).
- 4. Dose Calculations, Total Effective Dose Equivalent(TEDE)
- a. Total Effective Dose Equivalent (TEDE)
- 1) Verify the projected release duration (default 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />).
- 2) Enter the calculated TEDE rate in block 10 of the ENF if off-site dose rates are not available form FMTs or PICs.
- 3) Compare the release duration "Total TEDE" against dose values in EALs RG1.2 and RS. 1.2 for classification.
- b. Thyroid Committed Dose Equivalent (CDE)
- 1) Compare the release duration "Total CDE" against dose values in EALs RG1.2 and RS. 1.2 for classification.
- 5. Print the Plant Vent Release page and the Dose Calculations page.
- 6. Enter the Assessors name at the top of each page.
- 7. Submit the calculation to the ISEC for approval. Signature on each page.
- 1. General Information
- a. Enter the "Assessment" number.
- 2. Steam Release Rate
- a. Select the faulted ruptured SG.
- b. Type in the number of relief "valves lifted"
- 3. Radiation Monitor Factors
- a. This section is Information only - no editable fields.
- 4. Release Rate Calculations
- a. No entry required in this section. The monitor factor is changed based on SG level (%) indication in Section 2, Steam Release Rate above. This carries over to the DCF section on the Dose Calculations page.
- 5. Single click the "NEXT" button at the bottom of the page. This will open a Dose Calculations window.
- 6. IF more than one Dose Calculations window is open, THEN close all open Dose Calculations windows and click the "NEXT" button at the bottom of the Atmosphere Steam Release page. This will open a new Dose Calculations window.
- 1. General Information
- a. Validate current date and time, assessment number, and unit releasing number are the same as the Atmospheric Steam Release page.
- 2. Meteorological Data - PPC
- a. Select Desired Met Data (Primary or Backup)
- 1) Primary is preferred to backup.
- 2) Do NOT select if any of the 3 parameters indicates "UNREL"
- 3) If both met towers have "UNREL" data, perform a long hand calculation using Attachment 10.1.
- 3. DCF Determination
- a. This carries over from the Atmospheric Steam Release page (do not edit). It is based on the PDN input for SG Narrow Range (NR) water level
- 4. Dose Calculations, Total Effective Dose Equivalent(TEDE)
- a. Total Effective Dose Equivalent (TEDE)
- 1) Verify the projected release duration (default 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) a) Enter 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> for a "puff' release under 15 minutes.
- 2) Enter this calculated TEDE rate in block 10 of the ENF if off-site dose rates are not available from FMTs or PICs
- 3) Compare the release duration "Total TEDE" against dose values in EALs RG1.2 and RS. 1.2 for classification.
- b. Thyroid Committed Dose Equivalent (CDE)
- 1) Compare the release duration "Total CDE" against dose values in EALs RG1.2 and RS.1.2 for classification.
- 5. Print the Atmosphere Steam Release page and the Dose Calculations page.
- 6. Enter the Assessors name at the top of each page.
- 7. Submit the calculation to the ISEC for approval. Signature on each page.