View source for DCL-09-020, Updated Emergency Plan Implementing Procedures

{{Adams
| number = ML090990433
| issue date = 03/30/2009
| title = Updated Emergency Plan Implementing Procedures
| author name = Persky M
| author affiliation = Pacific Gas &amp; Electric Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000275, 05000323
| license number = DPR-080, DPR-082
| contact person = 
| case reference number = DCL-09-020
| document type = Emergency Preparedness-Emergency Plan Implementing Procedures
| page count = 124
}}

=Text=
{{#Wiki_filter:Pacific Gas and Electric Company' 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*
EP G-2 EP G-3 EP G-4 EP G-5 EP R-2*
EP R-3 EP R-7 EP OR-3 EP RB-1 EP RB-2 EP RB-3 EP RB-4 EP RB-5 EP RB-8 EP RB-9*
EP RB-10 EP RB-11 EP RB-12 EP RB-14 EP RB-14A EP RB-15 EP RB-16*
EP EF-1 EP EF-2 EP EF-3 EP EF-4 EP EF-9 EP EF-10 38 Emergency Classification and Emergency Plan Activation 32 Interim Emergency Response Organization 50 Emergency Notification of Off-Site Agencies 22 Assembly and Accountability 11 Evacuation of Nonessential Site Personnel 27 Release of Airborne Radioactive Materials Initial Assessment 8C Release of Radioactive Liquids 15A Off-Site Transportation Accidents 6B Emergency Recovery 5B Personnel Dosimetry 6
Emergency Exposure Guides 6
Stable Iodine Thyroid Blocking 4A Access to and Establishment of Controlled Areas Under Emergency Conditions 6
Alternate Personnel Decontamination Facilities 21 Instructions for Field Monitoring Teams 13 Calculation of Release Rate 14 Protective Action Recommendations 12 Emergency Offsite Dose Calculations 7
Plant Vent Iodine and Particulate Sampling During Accident Conditions 8A Core Damage Assessment Procedure 1A Initial Detection of Core Damage 11 Post Accident Sampling System 2
Operating Instructions for the EARS Computer Program 36 Activation and Operation of the Technical Support Center 28 Activation and Operation of the Operational Support Center 31 Activation and Operation of the Emergency Operations Facility 16 Activation of the Off-Site Emergency Laboratory 10 Backup Emergency Response Facilities 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 N S.........................................................................................
4
: 7.
R EC O R D S..................................................................................................
4
: 8.
R E FE R E N C E S..............................................................................................
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."
EP_G-1u3r38.DOC 0226.1447

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.
EP G-1u3r38.DOC 0226.1447

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.
EP_G-1u3r38.DOC 0226.1447

Emergency Classification and Emergency Plan Activation EP G-1 R38 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.
EPG-1u3r38.DOC 0226.1447

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 U 1 &2 Attachment 1: Page 1 of 5 Definitions 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 Shutdown Event in progress has adversely affected functions that are necessary to 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.
EP G-1u3r38.DOC 0226.1447

EP G-1 R38 Page 7 of 24 U 1 &2 Attachment 1: Page 2 of 5 Definitions 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.
EPG-1u3r38.IOC 0226.1447

EP G-1 R38 Page 8 of 24 U 1 &2 Attachment 1: Page 3 of 5 Definitions 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.
EP G-1u3r38.DOC 0226.1447

EP G-1 R38 Page 9 of 24 U 1 &2Attachment 1: Page 4 of 5 Definitions 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 Reactor trip 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.
EP_G-1u3r38.DOC 0226.1447

EP G-1 R38 Page 10 of 24 U 1 &2 Attachment 1: Page 5 of 5 Definitions 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.
EPG-1u3r38.DOC 0226.1447

EP G-1 R38 Page 11 of 24 U1 &2 Attachment 2: Page 1 of 14 Emergency Action Level Matrix 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 1 1 2
1 3 1 4 5
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 based on dose assessment instead of radiation monitor readings. While necessary declarations 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.
EPG-1u3r38.DOC 0226.1447

EP G-1 R38 Page 12 of 24 U 1 &2 Attachment 2: Page 2 of 14 Emergency Action Level Matrix GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the Reactor Vessel Unexpected increase in plant radiation Table R-1 Effluent Monitor Classification Thresholds ReleasePoint Monitor GE SAE Alert UE 1(2)-RM-14/14R Offscale hi 8.0E4 cpm 2.OE-3 iC/cc a Plant1VentG(2)-RM-24/24R 1.OE-6 giC/cc 1.OE-8.C/cc S1t(2)-RM-28/28R 1.OE-5 i.C/cc 1.0E-7 tiC/cc e
3.0E-9 amps 3.OE-10 amps o 
~1 (2)-RM-87--
u 2.OE+ipC/cc 2.0E0
_C/cc 1(2)-RM-71/72/73174 Main Steam With Steam Dump or 3.OE+5 cpm 3.OE+4 cpm 3.OE+3 cpm 3.OE+2 cpm one or more SRVs.
open on affected SG Oily Water Separator 0-RM-3 6.OE+4 cpm 6.OE+2 cpm L Effluent Liquid q Radwaste IDischarge O-RM-18 Offscale hi
* 1.0E+5 cpm d Line Effluent SGEBD Tank Liquid Effluent 1(2)-RM-23 Offscale hi 2.OE+4 cpm 11 12 1 3 1 4 1 5 16 IDEFI RA2.1 Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the reactor vessel resulting in a valid high alarm on ANY of the following radiation monitors:
" New Fuel Storage Area Rad Mon RM-59, Hi Rad (6.5 mR/hr)
" Spent Fuel Pool Area Rad Mon RM-58, Hi Rad (20 mR/hr)
" Contmt Area Mon High Rad RM-2, Hi Rad (21 mR/hr)
" Containment Ventilation Exhaust Radiation Monitor RM-44NB high alarm (1.35E-4 pLC/cc)
RA2.2 A water level drop in the reactor refueling cavity, spent fuel pool or fuel transfer canal that will result in irradiated fuel becoming uncovered 1
2 3
4 5
6 DEF RU2.1 Valid low water level alarm indicating uncontrolled water level decrease in the reactor refueling cavity, spent fuel pool, or fuel transfer canal with all irradiated fuel assemblies remaining covered by water AND Unplanned valid direct area radiation monitor reading increases RU2.2 Unplanned valid direct radiation area monitor reading increases by a factor of 1000 over normal*
levels Normal levels may be considered as the highest reading in the past twenty-four (24) hours excluding the current peak value R
Abnormal Red Release Rad Effluent 2
Onffsite Rad Conditions, Spent Fuel Events Release of radioactive material or increases in radiation levels within the facility that impedes operation of systems required to maintain safe operations or to establish or maintain cold shutdown
* With effluent discharge not isolated 1 1 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 U1 &2 Attachment 2: Page 3 of 14 Emergency Action Level Matrix 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 annunciator "SEISMIC INSTR SYSTEM"
;Tornado or high winds > 80 mph (36.36 m/sec)
* U.S. Geological Survey (USGS)
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 visible damaure-getpnetratedmissions of 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 in ANY 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 U 1 &2 Attachment 2: Page 4 of 14 Emergency Action Level Matrix 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.
safe shutdown.
1 2
3 4
5 6
DEF 1
2 3
4 5
6 DEF 2.
Note3: If the fire or explosion is a hostile action, HA2.1 HU2.t None see Subcategory H.4 EALs for possible Fire or explosion resulting in EITHER:
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 U1 &2 Attachment 2: Page 5 of 14 Emergency Action Level Matrix 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 A security 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 A credible site-specific security threat notification Failure of Spent Fuel Cooling systems threat within 30 rain. of the site OR AND A valid 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 Room AND Inaccessibility, for Control Room evacuation EvacuationAN 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 in the 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 U 1 &2 Attachment 2: Page 6 of 14 Emergency Action Level Matrix 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 Power Malf.
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 &2 Attachment 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 IV 5M 6
1 mil~
5 IBM IN-5;-
60 1 r-;
6 M
CG2.1 CS2.1-CA2.M CU2.1 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.
* Containment hydrogen concentration >
s OR leg as indicated by ANY of the following:
CU2.2
* 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<S 105 rft 9 in.
Loss of inventory as indicated by unexplained Core uncovery for > 30 min. as indicated by Table C-1 sump/tank level RVLIS upper range < 60%
increase in ANY Table C-D sump/tank level C
EITHER:
CS2.2 O RVLIS full range <63.3%
AND full range.< 56.6%
OR Reactor Vessel water level cannot be monitored Cold SD/I!RVLOR With Containment closure established:
Reactor Vessel level cannot be monitored for 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 6 in. 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 Top of 103 ft 56.6% full
*- Reactor Cavity Sump With Containment closure not established:
active fuel PRT RVLIS full range < 62.1%
SRCDT OR Reactor Vessel level cannot be monitored with CCW surge tank indication of core uncovery as evidenced by Auxiliary Building sump EITHER:
RWST 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 I
EPG-1u3r38.DOC 0226.1447

EP G-1 R38 Page 18 of 24 Emergency Action Level Matrix U1 &2 Attachment 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 &#xfd;6~
3 CA3.1 CU3.1 None None An unplanned event results in RCS temperature An unplanned event results in RCS temperature RCS 
> 200&deg;F for > Table C-3 duration 
> 200&deg;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
Unable to restore or maintain EITHER of the None None None 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
I 516 Ifl n
None None None CUM Inadvert.CU.
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 U 1 &2Attachment 2: Page 9 of 14 Emergency Action Level Matrix 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 If an 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 U 1 &2 Attachment 2: Page 10 of 14 Emergency Action Level Matrix
- 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 hours 
> 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 s fan l etre s
manual actions taken from the reactor control the manual actions taken from the reactor control cdown the reactor and indication of an extreme console are NOT successful in shutting down the console are successful in shutting down the challenge to the ability to cool the core exists recoratr System resctor.
reactor Ma1f.
1 2
1 2
l l1 2
W 7 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%
OR b eco wr>5 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 U1 &2Attachment 2: Page I1 of 14 Emergency Action Level Matrix 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 
&#xfd; I1 2
3 4
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 AND A significant transient is in progress communications capabilities 4,
Central Alarm Station X
X AN OR (CAS) and Secondary Compensatory non-alarming indications (PPC, Om SU4.2 Int.I Alarm Stations (SAS)
SPDS) are unavailable Compensatory non-alarming indications (PPC, 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 &2 Attachment 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 U 1 &2 Attachment 2: Page 13 of 14 Emergency Action Level Matrix 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 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 U 1 &2 Attachment 2: Page 14 of 14 Emergency Action Level Matrix Fuel Cladding Barrier Reactor Coolant System Barrier Containment Barrier I
I F-I Loss E l1 Potential 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
- Reactor Vessel water level <Table F-2 thresholds
- Restoration procedures not effective within 15 min.
C.Radlation "1 3. Containment radiation
: 1. Containment radiation Ll 4. Containment radiation (RM-30 or RM-31)> 80 Rhr (RM-30 or RM-31)
(RM-30 or RM-31) 20 R/hr 
> 6 RJhr None None None I
: 4. With letdown In service, I
EP-RB-14A Dose Point radiation > 15 RPhr D.Inventory 
-1 5. SGTR in progress t-3. Reactor Vessel water level "1 2. RCS leak rate' available U 2. Unisolable RCS leak exceeding
: 31. Rapid unexplained Containment pressure drop U 5. Containment pssure 47 psig and increasing AND Table F-2 thresholds makeup capacity as the capacity of one charging pump following initial increase P
MSL radiation I
indicated by a loss of RCS in the normal charging mode 
& Containment hydrogen concentration a 4%
(RM-71, 72, 73 or 74) subcooling (150 gpm) 3 2. Following LOCA, Containment pressure or sump 6
>5lEcm 
~i.level response cot consistent with LOCA f5.0E4rcpm (r 5 min.
shton
: 3. SGTe t r
si conditionsL
: 7. Containment pressure > 22 psig with < one full after reactor shutdown) 
"1 3. SGTRthat resultsIn ancI train of depressurization equipment operating ECCS (SI) actuation "13. Ruptured SIG is also faulted outside of Containment I
Note: One Containment Spray pump and two CFCUs comprise one futo tr[n of depresuration equipment i
: 14. Primary-to-secondary leakage > 10 gpm with non-isolable steam release from affected SIG to the environment E.Other
: 6. Coolant activity 3 5. Valve(s) not closed o 300 pCI/gm Dose AND Equivalent 1-131 None None None Direct pathway to the environment exists after Non Containment isolation signal I
F. Judgment
: 7. ANY condition In the U 4. ANY condition in the 
-1 4. ANY condion In the opinion U1
: 3. ANY condition In the opinion 3 6. ANY condition in the opinion of the b 8. ANY condition in the opinion of the opinion of the opinion of the of the ISEC/SEC/RM that of the ISEC/SEC/RM that ISEC/SECIRM that indicates loss of the ISECISEC/RM that indicates potential loss of the ISEC/SEC/RM that I
ISECISEC/RM that indicates loss of the RCS Indicates potential loss of the Containment banter Containment barrier indicates loss of the Fuel 1 indicates potential loss of barrier r
RCS barner Clad barrier 
-the Fuel Clad barder Table F-2 Reactor Vessel Water Level Thresholds No, RVLIS No.
Level RCPs Full Range None 32%
Dynamic Head 4
46%
Ir 3
35%
.',.2*-,
26%
oz&#xfd; *,.Acjmv 1
22%
EP_G-1u3r38.DOC 0226.1447

.3
*** ISSUED FOR USE BY:
DATE:
PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EXPIRES:____
NUMBER EP RB-9 REVISION 13 PAGE 1 OF 42 UNITS TITLE:
Calculation of Release Rate 1 AND2 03/13/09 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
: 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.
2.2 This procedure provides a manual methodology for performing release rate calculations as a backup to the Emergency Assessment and Response System (EARS) or the Excel application "Quick Dose."
This procedure in conjunction with EP RB-11, "Emergency Off-Site Dose Calculations" can be used to determine projected off-site TEDE and thyroid CDE doses.
: 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 -
Form 69-9260.
4.2 To manually calculate Noble Gas and Iodine-i131 Equivalent Release Rates for a Main Steam Line Release follow the step-by-step instructions given in Attachment 7.2 -
Form 69-.41105.
4.3 To manually calculate Noble Gas and Iodine-i 31 Equivalent Release Rates for a Containment Leakage Release follow the step-by-step instructions given in.3 - Form 69-10555.
: 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.
EP RB-9u3rl3.DOC 03B' 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DIABLO CANYON POWER PLANT REVISION 13 PAGE 2 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2
: 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,"
08/31/94 7.2 Form 69-11105, "Noble Gas and 1-131 Equivalent Release Rates for a Steam Release,"
02/03/09 7.3 Form 69-10555, "Noble Gas and 1-131 Equivalent Release Rates for Containment Leakage," 08/31/94
: 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

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 3 OF 42 1 AND 2 UNITS 8.10 PG&E, Nuclear Operations Support Calculation RA-93-04, EP R13-9, Calculation of
.Release Rate, Units 1 and 2, Rev. 7 - Validation and Verification 8.11 PG&E Calculation PAM-0-04-517, Rev. 4, 4/6/97 "Steam Generator Narrow Range Level Uncertainty" 8.12 SH&ES Calculation No. EP-94-02, Rev 0, Validation and Verification of EP RB-9, "Calculation of Release Rate," Rev 10, and EP RB-11, "Emergency Offsite Dose Calculations," Rev 11 EPRB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 4 OF 42 1 AND 2 APPENDIX 6.1 Table 1 Source Term for Various Postulated Accidents
: 1.
Major LOCA with Core Melt - RE-30/31 >300R/hr
: 2.
Major LOCA (Gap Release) - RE-30/31 >I R/hr, <300R/hr
: 3.
Small Break LOCA (No fuel damage) - RE-30/31 <1R/hr
: 4.
Blackout
: 5.
Major Steamline Break
: 6.
Major Feedwater Line Break
: 7.
Steam Generator Tube Rupture
: 8.
Locked Reactor Coolant Pump (RCP Rotor)
: 9.
Control Rod Ejection
: 10.
Gas Decay Tank Rupture
: 11.
Liquid Holdup Tank Rupture
: 12.
Volume Control Tank (VCT) Rupture
: 13.
Fuel Handling Accident in Fuel Handling Building (FHB)
Source Term Core Gap RCS RCS RCS RCS GAP GAP GAP - Noble Gas Only RCS.- Noble Gas Only RCS - Noble Gas Only Spent Fuel (Highest Assembly Gap)
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 5 OF 42 1 AND 2 UNITS APPENDIX 6.2 Figure 1 Plant Vent Noble Gas Monitor Response RE-14/14R, Normal Range 1.010"/
1.OOE-08 CPM 1.OOE09 0.1 1.0 10.0 100.0 1000.0 T"rmAter Shut&AM1 fs EPRB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER EP RB-9 REVISION 13 PAGE 6 OF 42 UNITS 1 AND 2 APPENDIX 6.3 Figure 2 Plant Vent Noble Gas Monitor Response RE-87, Extended Range 1.00E+10 pCi/cc 1.OOE+09 per Amp 1.00E+08 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs J
EP RB-9u3rl3.DOC 
`03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER EP RB-9 REVISION 13 PAGE 7 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 APPENDIX 6.4 Figure 3 Plant Vent Gross Gamma Monitor Response RE-29, High Range 1.00E+00 1.OOE-01 pCi/cc per 1.00E-02 mR/Hr I.OOE-03 I.00E-04 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 8 OF 42 1 AND2 UNITS APPENDIX 6.5 Figure 4.1 1-131 TEDE Correction Factor 1-131 TEDE Correction Factor 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 40.0 100.0 200.0 400.0 1000.0 Time After Shutdown (Hrs)
EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER EP RB-9 REVISION 13 PAGE 9 OF 42 UNITS 1 AND 2 APPENDIX 6.5 (continued)
Figure 4.2 1-131 Thyroid CDE Correction Factor 1-131 Thyroid CDE Correction Factor 1.50 1.40 1.30 1.20 1.10 1.00 I- 
-t F 
-~ 
-t F
I I
I __
11 _ 
---- I-____
_I_
I__ 
'Accident Source Term
-o-Coolant
-A--Gap p_____
0 
-i-Core Spent Fuel.
A/i 19 y
y I F
I 40.0 100.0 200.0 400.0 1000.0 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 Time After Shutdown (Hrs)
EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 10 OF 42 1AND2 UNITS APPENDIX 6.6 Figure 5.1 Main Steamline Monitor Response - Empty Generator RE-71, RE-72, RE-73, RE-74 1.00E-01 1.00E-02 1.OOE-03 pCi/cc per CPM 1.OOE-04 1.00E-05 1.00E-06 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 11 OF 42 1 AND 2 APPENDIX 6.6 Figure 5.2 Main Steamline Monitor Response - Normal Generator RE-71, RE-72, RE-73, RE-74 1.00E-01 I.OOE-02 1.OOE-03 pCi/cc 1.OOE-04 per CPM 1.00E-05 1.00E-06 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs EP RB-9u3r 3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER EP RB-9 REVISION 13 PAGE 12 OF 42 UNITS 1 AND 2 APPENDIX 6.6 (continued)
Figure 5.3 Main Steamline Monitor Response - Flooded Generator RE-71, RE-72, RE-73, RE-74 1.00E-02 pCi/cc per CPM 0.1 1.0 10.0 100.0 1000.0 Time After Shutdown, Hrs EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 13 OF 42 IAND 2 UNITS APPENDIX 6.7 Figure 6.1 Iodine TEDE Conversion Factor Iodine TEDE Conversion Factor 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 0.20 0.10 0.00 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 40.0 10.0.0 200.0 400.0 1000.0 Time After Shutdown (Hrs)
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 14 OF 42 1 AND 2 UNITS APPENDIX 6.7 (continued)
Figure 6.2 Iodine Thyroid CDE Conversion Factor Iodine Thyroid CDE Conversion Factor 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 0.20 0.10 7 0.00 0.1 0.2 0.4 1.0 2.0 4.0 10.0 20.0 40.0 100.0 200.0 400.0 1000.0 Time After Shutdown (Hrs)
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 15 OF 42 1 AND 2 APPENDIX 6.8 Figure 7 Design Basis Containment Monitor Exposure Rate RE-30 and RE-31 1.OOE+ 06 1.00E+ 05 R/Hr 1.00E+ 04 1.00E+ 03 5.OOE- 01 6.OOE+ 00 1.20E+ 01 2.40E+ 01 4.80E+ 01 7.20E+ 01 1.68E+ 02 Time After Shutdown (Hrs)
EP RB-9u3rl3.DOC 03B 0203.1409

k-1 I
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 16 OF 42 1 AND 2 UNITS APPENDIX 6.9 Figure 8 Design Basis Noble Gas Release Rates Ci per Sec 7.OOE+00 6.OOE+00 5.OOE+OO 4.OOE+OO 3.OOE+OO 2.OOE+OO
: 1. OOE +00 O.OOE+00
-- Based on 100%Core Noble Gas Released to Containment H-0 10 20 30 40 50
: 60.
70 80 90 100 Time After Shutdown, Hrs EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER EP RB-9 REVISION 13 PAGE 17 OF 42 UNITS 1 AND 2 APPENDIX 6.10 Figure 9 Design Basis 1-131 Equivalent Release Rates 1.OOE+00 9.00E-01 8.00E-01 7.OOE-01 6.OOE-01 if i~Vi i i I,
-t r 
.ased on 25 CoIdne Released to Containment Containment Sprays Inoperable t--
I I.1 1-Ci per Sec 5.00E-01 4.OOE-01 I
- - - - -- 1-131 THYROID CDE EQUIVALENT 1-1 I*:
3.00E-01 2.00E-01 1.00E-01 O.00E+00
-I-1-131 TEDE EQUIVALENT U 1 4-1 1
1 1
1 1 1 1
1 0
10 20 30 40 50 60 70 80 90 100 Time After Shutdown, Hrs EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DIABLO CANYON POWER PLANT REVISION 13 PAGE 18 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 APPENDIX 6.11 Accident Summary Sheets This Appendix contains summary sheets for the various postulated accidents which have been analyzed in the FSAR. These sheets contain both the "design basis" and "expected" case variables which were assumed in the FSAR analyses. The sheets can be used to compare actual measurements with assumed numbers from the FSAR, in order to help evaluate how things are going in relation to predictions, or they can be used as a source of data to supply unavailable numbers in calculations which are performed at the time of the accident.
Two sets of data are included. The "design basis" case is expected to be highly conservative, where every variable is at a worst-case condition. The "expected" case is the best estimated prediction of what might actually occur. When FSAR values are used to make calculations or predictions at the time of the accident, the "design basis" values can be used to provide a quick upper limit result, but as soon as data becomes available which tends to confirm one case or the other, the one which best agrees with the data should be used.
The accident classifications identified in this Appendix are based on the analyzed off-site doses of the activity releases.
NOTE: Do not use these Summary Sheets to classify emergencies. Always refer to EP G-1 to consider all possible EALs.
EP G-1 classifications based on plant conditions other than off-site doses are presented also to illustrate the relatively close and usually conservative declarations that would be made even before dose calculations were performed.
The summary sheets provided are:
A. MAJOR LOCA B. MAJOR STEAM LINE BREAK C. MAJOR FEEDWATER LINE BREAK D. BLACKOUT (OR PLANT COOLDOWN WITH ATMOSPHERIC DUMP)
E. SMALL LOCA F. TUBE RUPTURE G. LOCKED ROTOR H. FUEL HANDLING ACCIDENT IN FUEL HANDLING BUILDING I.
FUEL HANDLING ACCIDENT IN CONTAINMENT J.
ROD EJECTION ACCIDENT K. GAS DECAY TANK RUPTURE L. LIQUID HOLDUP TANK RUPTURE M. VCT RUPTURE EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS-AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 19 OF 42 1 AND2 APPENDIX 6.11 (continued)
Summary Sheet A Major LOCA PARAMETER
: 1.
Total Release to Containment Free Volume, Ci
: a.
Xe-133 b..
Other Noble Gases
: c.
1-131 FSAR DBA 2.03x108 5.73x108 2.21x10 7 1.90x10 8 Core 100% of core N.G., 25%
of core iodines 0.022 FSAR EXPECTED 1.36x10 6 4.27x10 5
1.82x10 5 2.73x10 5 Gap 100% of gap N.G., 25%
of gap iodines 0.0075 d.
e.
f.
Other Iodine Source Term Release Assumption
: 2.
Containment Spray Effectiveness
: a.
Removal half-life (hrs)
: b.
Number of operable spray pumps
: 3.
Containment Leak Rate (%/day)
: 4.
Total Release to Environs, First 2 Hours, Ci
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other Iodine
: e.
Release Mechanism 1
0.1 for 1 st day, 0.05 after 1 st day 2
16,840 25,930 191 1,325 Containment Leakage 0.05 for I st day, 0.025 after 1 st day 56 21 0.05 0.08 Containment Leakage EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 20 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet A Major LOCA FSAR PARAMETER DBA
: 5.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary) 5.29x1O4
: b.
10000m (6 mi. LPZ) 2.20x10 5-
: 6.
Whole Body Dose Results
: a.
Total 800m dose for 5.6E+00 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem) 5.7E-01
: 7.
Thyroid Dose Results
: a.
Total 800m dose for 9.6E+01 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem) 1.8E+01
: 8.
Accident Classification (Based on above Dose):
General Emergency (Based on EP G-1):
Site Area Emergency
: 9.
Miscellaneous
: a.
Containment-free volume cc 7.36x10l&deg;
: 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.
FSAR EXPECTED 5.29x10-5 2.20x10-6 3.7E-04 6.4E-05 1.3E-03 9.2E-04 Unusual Event Site Area Emergency EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 21 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet B Major Steam Line Break FSAR DBA FSAR EXPECTED PARAMETER
: 1.
Initial Conditions and Assumptions
: a.
Primary Coolant Activity (pCi/gm)
: 1)
Xe-133
: 2) 1-131
: 3)
Other Iodine
: b.
Secondary Water Activity (gtCi/gm)
: 1) 1-131
: 2)
Other Iodines
: c.
Assumed Fuel Defects (%)
: d.
Primary to Secondary Leakage (gpm)
: e.
Steam Release, 1 st Two Hours (lbs)
: 1)
Failed Generator
: 2)
Other generator (atmospheric dump)
: f.
Total Steam Release During 8-Hour Cooldown (lbs)
: g.
Liquid Release Fraction for Iodine
: 1)
Failed Generator
: 2)
Other generators
: 2.
Activity Release to Environs, First 2 Hours (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other lodines
: e.
Source Term 270 2.6 7.9 67.2 0.65 2.0 4.4E-05 9.OE-05 0.2 0.014 1.5E-02 3.7E-02 1
1 162,784 393,464 1,250,000 0.1 0.01 1.2E-03 1.9E-04 1.6E-05 1.3E-04 RCS 3.5E-07 5.2E-08 4.4E-09 3.6E-08 RCS EPRB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 22 OF 42 I AND2 APPENDIX 6.11 (continued)
Summary Sheet B Major Steam Line Break PARAMETER 3-(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
FSAR DBA 5.29x1O4
: b.
10000m (6 mi. LPZ) 2.20x10-5
: 4.
Whole Body Dose Results
: a.
Total 800m dose for 1.7E-03 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem) 2.6E-04
: 5.
Thyroid Dose Results
: a.
Total 800m dose for 8.8E-02 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem) 5.3E-02
: 6.
Accident Classification (Based on above Dose):
Alert (Based on EP G-1):
Unusual Event
: 7.
Miscellaneous
: a.
Fluid Mass/Stm Gen (lbs)
Water 81,500
: 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:
FSAR EXPECTED 5.29x10-5 2.20x10-6 5.4E-07 7.8E-08 1.6E-05 9.9E-06 No Emergency Unusual Event 3, Table 4.6-19.
EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DIABLO CANYON POWER PLANT REVISION 13 PAGE 23 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 Appendix 6.11 (continued)
Summary Sheet C Maj or Feedwater Line Break The release from this accident comes from release of steam by safety valves and/or atmospheric steam dump of steam generator water during cooldown if the condenser is not available. The steam generator water is contaminated if there is tube leakage. The feedwater itself which is released has very little activity in it and is ignored.
This accident is basically the same as a major steamline break and Summary Sheet B can be used.
Note, however, that the steam release will be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release. This will reduce the thyroid dose somewhat from the steamline break case.
EP RB-9u3rI3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER EP RB-9 REVISION 13 PAGE 24 OF 42 UNITS 1AND 2 APPENDIX 6.11 (continued)
Summary Sheet D Blackout (Plant Cooldown With Atmospheric Dump)
The release from this accident comes from release of steam by safety valves and/or atmospheric steam dump of steam generator water which is contaminated if there is tube leakage.
This accident is basically the same as a steamline break and Summary Sheet B can be used.
Note, however, that the steam release will be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release. This will reduce the thyroid dose somewhat from the steamline break case.
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 25 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet E Small LOCA (Release of Coolant to Containment)
PARAMETER
: 1.
Initial Coolant Activity ([tCi/gm)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other Iodine
: e.
Source Term
: f.
Fuel Defects (%)
: 2.
Initial Release to Containment (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other Iodine
: e.
Assumption
: 3.
Containment Spray Effectiveness
: a.
Removal Coefficient (hr-1)
: b.
Number of operable spray pumps
: 4.
Containment Leak Rate (%/day)
FSAR DBA 270 30 2.62 7.88 RCS 1
65,430 7,950 63 193 100% of Coolant N.G.
activity +10% of coolant iodines FSAR EXPECTED 45.7 5.6 0.45 1.35 RCS 0.2 16,280 1,980 16 48 100% of Coolant N.G.
Activity +10% of coolant iodines 31 92 1
2 0.1 for 1st day, 0.05 after 1st day 0.05 for 1 st day, 0.025 after 1st day
: 5.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
: b.
10000m (6 mi. LPZ) 5.29xl0A4 2.20x10-5 5.29x10-5 2.20x10-6 EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 26 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet E Small LOCA (Release of Coolant to Containment)
FSAR FS PR
:PECTED PARAMETER DBA EX
: 6.
Whole Body Dose Results
: a.
Total 800m dose for 1st two hours (Rem) 1.8E-04 4.4
: b.
Total 10000m dose for 30 days (Rem) 5.OE-05 1.4
: 7.
Thyroid Dose Results
: a.
Total 800m dose for 1st two hours (Rem) 2.OE-04 9.0
: b.
Total 10000m dose for 30 days (Rem) 3.OE-05 i.0
: 8.
Accident Classification (Based on above Dose):
Unusual Event No (Based on EP G-1):
Site Area Emergency Sit
: 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.
E-06 E-06 E-07 E-07 Emergency e Area Emergency EP RB-9u3r]3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:.
Calculation of Release Rate NUMBER EP RB-9 REVISION 13 PAGE 27 OF 42 UNITS 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet F Tube Ruptuire' PARAMETER FSAR DBA FSAR EXPECTED
: 1.
Initial Conditions and Assumptions (Pre-accident Iodine Spike Case)
: a.
Primary Coolant Activity (ptCi/gm) 1)
2) 3)
4)
Xe-133 1-131 (equivalent) 1-131 Other Iodine 270 60 41.4 110.4 67.2 0.65 2.0
: b.
Secondary Water Activity (gCi/gm) 1)
2) 1-131 -
Other lodines 6.9E-02 1.8E-01 I1
: c.
Assumed Fuel Defects (%)
: d.
Primary to Secondary Leakage (gpm) 1)
2)
Pre-existing Tube Rupture 1
160
: e.
Steam Release, 1 st Two Hours (lbs) 4.4E-05 9.OE-05 0.2 0.014 31,000 380,000 1,500,000 0.01 0.01 1) 2)
Failed generator Other generators (atmospheric dump) 146,700 445,000
: f.
Total Steam Release During 8 hour Cooldown (lbs)
: g.
Liquid Release Fraction for Iodine
: 1)
Failed generator
: 2)
Other generators (1) 0.01 when rupture site is covered 1.0 when covered by less than 12" water 1,530,000 0.01 *(1) 0.01 *(1)
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 28 OF 42 1AND 2 APPENDIX 6.11 (continued)
Summary Sheet F Tube Rupture FSAR DBA FSAR EXPECTED PARAMETER
: 2.
Total Release to Environs First 2 hours (Ci)
(Pre-Accident Iodine Spike)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other lodines
: e.
Source Term 3-(x/Q) CL (sec/m 3)
: a.
800 m (site boundary)
: b.
10000m (6 mi. LPZ)
: 4.
Whole Body Dose Results
: a.
Total 800m dose forl st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 5.
Thyroid Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 6.
Accident Classification (Based on above Dose):
(Based on EP G-l):
2.8E+04 2.OE+03 5.5E+02 1.4E+03 RCS 5.29x10-4 2.20x10-5 2.3E-01 1.OE-02 2.4E+03 2.4E+02 1.4E-01 6.2E-0 1 RCS 5.29x10-5 2.20x10-6 7.7E-03 3.OE-04 1.9E+02 8.OE+00 General Emergency Site Area Emergency 4.3E-03 2.OE-04 Alert Site Area Emergency EPRB-9u3r13.DOC 03B
.0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 29 OF 42 UNITS 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet F Tube Rupture FSAR PARAMETER DBA FSAR EXPECTED 7.
Miscellaneous
: a.
Fluid Mass/Steam Gen (lbs)
: 1)
: Water,
: b.
Safety Valve and Steam Dump Valve Capacities (lbs/hr/valve)
: 1)
S/G safety valve
: 2) 10% atmospheric dump
: 3) 35% atmospheric dump 81,500 800,000 380,000 597,000
: 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.
EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 30 OF 42 1AND2 APPENDIX 6.11 (continued)
Summary Sheet G Locked Rotor Accident FSAR DBA FSAR EXPECTED PARAMETER
: 1.
Total Release to Environs, 1 st Two Hours (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other lodines
: e.
Source Term
: f.
Assumptions
: 1)
Coolant Activity
: 2)
Primary to Secondary Leakage (gpm)
: 3)
Secondary Steam Release, 1 st Two Hours (lbs)
: 4)
Total Steam Release During 8 Hour Cooldown (Ibs)
: 2.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
: b.
1000m (6 mi. LPZ)
: 3.
Whole Body Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 4.
Thyroid Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem) 2.7E+02 5.5E+01 8.6E-01 1.3E+00 Gap 6.3E-06 9.6E-06 8.2E-08 2.8E-07 Gap 1% fuel defects
+3% of gap activity I
0.2% fuel defects
+3% of gap activity 0.014 520,000 1,600,000 5.29x10-4 2.20x10-5 1.3E-02 1.1E-03 3.OE-01 7.2E-02 520,000 1,600,000 5.29x10-5' 2.20x10-6 1.6E-05 1.2E-06 2.5E-04 6.2E-05 EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 31 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet G Locked Rotor Accident PARAMETER
: 5.
Accident Classification (Based on above Dose):
(Based on EP G-1)
: 6.
Miscellaneous
: a.
Fluid Mass/Steam Gen (Ibs)
: 1)
Water
: b.
Safety Valve and Steam Dump Valve Capacity (lbs/hr/valve)
: 1)
S/G safety valve
: 2) 10% atmospheric dump
: 3) 35% atmospheric dump
: c.
Liquid Release Fraction for lodines FSAR DBA Alert Alert FSAR EXPECTED No Emergency Alert 81,500 800,000 380,000 597,000 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.
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY' DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate.
NUMBER REVISION PAGE UNITS EP RB-9 13 32 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet H Fuel Handling Accident in Fuel Handling Bldg PARAMETER
: 1.
Initial Conditions
: a.
Radial Peaking Factor of Damaged Assembly
: b.
Elapsed Time Since Reactor Shutdown (hrs)
: c.
Type of Release to Pool
: d.
Bundle Submergence (fi)
: e.
Pool Decontamination Factor for Iodine
: f.
Total Assembly Gap Activity at Time of Accident
: 1)
Xe-133
: 2)
Other Noble Gases
: 3) 1-131
: 4)
Other Iodines
: 5)
Source
: 2.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
: b.
1000m (6 mi. LPZ)
: 3.
Total Release to Environs, 1 st Two Hours (Ci)
: a.
Xe-133
: b.
Other Noble Gases FSAR DBA 1.65 FSAR EXPECTED 1.26 100 100 100% of assembly gap activity 26 100 100,000 4,500 52,670 7,000 Spent Fuel 5.29xl0-4 2.20x10-5 100,400 4,100 80 10 Spent Fuel 100% of assembly gap activity 26 760 8,137 1,500 5,282 220 Spent Fuel 5.29x10-5 2.20x1 0-6 523 101 0.005 0.0002 Spent Fuel C.
d.
e.
1-131 Other Iodines Source Term EPRB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 33 OF 42 1AND 2 APPENDIX 6.11 (continued)
Summary Sheet H Fuel Handling Accident in Fuel Handling Bldg FSAR FSAR PARAMETER DBA EXPEC'
: 4.
Whole Body Dose Results
: a.
Total 800m dose for 1 st 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 1 st 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
: 7.
Miscellaneous
: a.
Fuel Handling Building Volume (ft3) 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.
rED a Emergency EP RB-9u3rl3.DOC 03B
.0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 34 OF 42 I AND 2 APPENDIX 6.11 (continued)
Summary Sheet I Fuel Handling Accident in Containment FSAR DBA FSAR EXPECTED PARAMETER
: 1.
Initial Conditions
: a.
Radial Peaking Factor of Damaged Assembly
: b.
Elapsed Time Since Reactor Shutdown (hrs)
: c.
Type of Release to Pool 1.65 1.26 d.
e.
f.
Bundle Submergence (ft)
Pool Decontamination Factor for Iodine Total Assembly Gap Activity at Time of Accident (Ci)
: 1)
Xe-133
: 2)
Other Noble Gases
: 3) 1-131
: 4)
Other Iodines
: 5)
Source Term 100 100% of assembly gap activity 26
'100 100,000 4,500 52,670 7,000 Spent Fuel 100 100% of assembly gap activity 26 760 8,137 1,500 5,282 220 Spent Fuel
: 2.
(x/Q) CL (sec/m3)
: a.
800m (site boundary)
: b.
1000m (6 mi. LPZ)
: 3.
Total Release to Environs, 1 st TwoHours (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other Iodines
: e.
Source Term 5.29x10-4 2.20x10-5 12,460 557 65 8.7 Spent Fuel 5.29x10-5 2.20x10-6 38 7
0.033 0.0013 Spent Fuel EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 35 OF 42 1 AND 2 APPENDIX 6.11 (continued),
Summary Sheet I Fuel Handling Accident in Containment PARAMETER
: 4.
Whole Body Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 5.
Thyroid Dose Results
: a.
Total 800 m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 6.
Accident Classification (Based on above Dose):
(Based on EP G-1):
: 7.
Miscellaneous Activity Release Mechanism FSAR DBA 3.1E-01 1.3E-02 1.8E+01 7.6E-01 FSAR EXPECTED 1.0E-04 4.0E-06 6.0E-04 3.0E-05 General Emergency Alert Site Area Emergency Alert Activity released from cavity to containment 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.
EP RB-9u3rl3.DOC' 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 36 OF 42 1 AND2 APPENDIX 6.11 (continued)
Summary Sheet J Rod Ejection Accident PARAMETER
: 1.
Total Release to Containment Free Volume (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other Iodine
: e.
Source Term
: f.
Release Assumption FSAR DBA 2.01x10 5 6.82x1 04 7.32x103 1.1 lx10 4 Gap.
Coolant activity (1%
defects) plus 10% of core gap activity times a liquid release fraction of either 0.1 (for I) or 1.0 (for N.G.)
FSAR EXPECTED 1.52x10 5 6.22x104 7.28x10 3 1.09x10 4 Gap Coolant activity (0.2%
defects) plus 10% of core gap activity times a liquid release fraction of either 0.1 (for I )or 1.0 (for N.G.)
: 2.
Containment Spray Effectiveness
: a.
Removal half-life (hrs)
: b.
Number of operable spray pumps
: 3.
Containment Leak Rate (%/day)
: 4.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
: b.
1000m (6 mi. LPZ)
: 5.
Total Release to Environs, 1 st 2 Hours (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other Iodine
: e.
Source Term
: f.
Release Mechanism 0.022 1
0.1 0.0075 2
0.05 5.29x10-4 2.20x10-5 11.2 4.1 0.0098 0.015 Gap Containment Leakage 5.29x10-5 2.20x10-6 5.6 2.0 0.002 0.002 Gap Containment Leakage EPRB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO'CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 37 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet J Rod Ejection Accident PARAMETER
: 6.
Whole Body Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 1000 n dose for 30 days (Rem)
: 7.
Thyroid Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 8.
Accident Classification (Based on above Dose):
(Based on EP G-l):
: 9.
Miscellaneous
: a.
Containment free volume (cc)
: b.
RCS Coolant Mass (gm)
FSAR DBA 7.3E-04 1.3E-04 FSAR EXPECTED 3.6E-05 6.4E-06 3.3E-03 1.4E-04 3.7E-05 1.6E-06 Unusual Event Site Area Emergency No Emergency Site Area Emergency 7.36x1010 2.4x108
: 10.
References
: a.
FSAR, Table 15.5-52.
: b.
DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-13.
EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 38 OF 42 1AND 2 APPENDIX 6.11 (continued)
Summary Sheet K Gas Decay Tank Rupture PARAMETER
: 1.
Total Release to Environs, 1 st Two Hours (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: 2.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
: b.
10000m (6 mi. LPZ)
FSAR DBA 65,400 7,300 5.29x104 2.20x1o-5 2.OE+00 8.4E-02 FSAR EXPECTED 16,300 2,140 5.29X10-5 2.20x10- 6
: 3.
Whole Body Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 1 0000m dose for 30 days (Rem)
NOTE: Thyroid doses are negligible.
: 4.
Accident Classification (Based on above Dose):
(Based on EP G-1):
: 5.
Miscellaneous
: a.
Tank Volume (cc)
: b.
Tank Press (psi) c.-
Volume Released (cc) 4.4E-02 1.8E-03 General Emergency Alert Site Area Emergency Alert 2.18x10 7 100 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.
EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 39 OF 42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet L Liquid Holdup Tank Rupture PARAMETER
: 1.
Activity in Holdup Tank (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other lodines
: e.
Source Term
: 2.
Cleanup Parameters
: a.
Liquid Release Fraction for lodines from Tank to Auxiliary Building Atmosphere
: b.
Charcoal Filter Cleanup Factor
: c.
Release Duration (hrs)
: 3.
Activity Release to Environs, 1 st Two Hours (Ci)
: a.
Xe-133
: b.
Other Noble Gases
: c.
1-131
: d.
Other lodines
: 4.
(x/Q) CL (sec/m 3)
: a.
800m (site boundary)
: b.
10000m (6 mi. LPZ)
: 5.
Whole Body Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
FSAR DBA 51,000 4,710 492 1,086 RCS FSAR EXPECTED 10,200 930 98.3 217 RCS 10-4 10-4 0.01 2
0.1 2
51,000 4,710 0.00492 0.01086 5.29xl0-4 2.20x10-5 1.4E+00 6.OE-02 10,200 930 9.8E-5 2.17E-4 5.29x10-5 2.20x10-6 3.7E-02 1.6E-03 EPRB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE UNITS EP RB-9 13 40 OF-42 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet L Liquid Holdup Tank Rupture FSAR PARAMETER DBA
: 6.
Thyroid Dose Results
: a.
Total 800m dose for 1.9E-03 1st two hours (Rem)
: b.
Total 10000m dose 8.0E-05 for 30 days (Rem)
: 7.
Accident Classification (Based on Dose):
Site Area Emergency (Based on EP G-i):
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.
FSAR EXPECTED 2.6E-06 1.1E-07 Site Area Emergency Alert EP RB-9u3r13.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-9 DIABLO CANYON POWER PLANT REVISION 13 PAGE 41 OF 42 TITLE:
Calculation of Release Rate UNITS 1 AND 2 APPENDIX 6.11 (continued)
Summary Sheet M Volume Control Tank Rupture FSAR FSAR PARAMETER DBA EXPECTED
: 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
: e.
Source Term RCS RCS
: 2.
Cleanup Parameters
: a.
Liquid Release Fraction for Iodines from 1 0-4 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, 1 st 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
: b.
1000m (6 mi. LPZ) 5.20xi0-5 2.20x10-6
: 5.
Whole Body Dose Results
: a.
Total 800m dose for 4.7E-01 9.3E-03 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem) 1.9E-02 3.9E-04 EP RB-9u3rl3.DOC 03B 0203.1409

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Calculation of Release Rate NUMBER REVISION PAGE EP RB-9 13 42 OF 42 1 AND 2 UNITS APPENDIX 6.11 (continued)
Summary Sheet M Volume Control Tank Rupture PARAMETER
: 6.
Thyroid Dose Results
: a.
Total 800m dose for 1 st two hours (Rem)
: b.
Total 10000m dose for 30 days (Rem)
: 7.
Accident Classification FSAR DBA 3.3E-05 1.4E-06 FSAR EXPECTED 4.4E-08 1.8E-09 (Based on Dose):
(Based on EP G-1):
: 8.
Miscellaneous
: a.
Tank Volume (cc)
Site Area Emergency Alert Alert Alert 1.1x10 7
: 9.
References
: a.
FSAR, Table 15.5-57.
: b.
DCM T-15, Radiation Protection, Rev. 0, February 1993, Table 4.6-25.
EPRB-9u3rl3.DOC 03B 0203.1409.

69-9260 08/31/94 Page I of 5 DIABLO CANYON POWER PLANT EP RB-9 ATTACHMENT 7.1 1AND2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 1 - GENERAL INFORMATION 1.1 Enter the following information: Unit # __
Date Time of Readings Calculation #
Date Time of Rx S/D Calculation By:
(Rx S/D)
(name) 1.2 Determine the TIME AFTER RX S/D (Hrs)
Use Table 1 (Appendix 6.1) to' determine Probable Source Term (circle one):
CORE GAP RCS SPENT FUEL SECTION 2 - PLANT VENT FLOW RATE Flow Rate Indicator FR-12 Operable 2.1 If FR-12 is operable, record below the flow rate reading indicated. Go to Section 2.3.
Plant Vent Flow Rate =
cfm 2.1 Flow Rate Indicator FR-12 Inoperable 2.2
: a.
If FR-12 is not operable, determine the Plant Vent Flow Rate by summing the operating fan flow rates below.
Number of Operating Fans Fan Exhaust Rate Pathway Flow Rate FHB x
35,750 cfm 
=
cfmn Aux Bldg x
73,500 cfm 
=
cfm Containment Purge x
55,000 cfm 
=
cfm GE/GW x
25,000 cfm cfm Containment H2 x
300 cfm 
=
cfm Plant Vent Flow Rate = Y Fan Flow Rates 
=
cfm 2.2 Plant Vent Flow Rate 2.3 Convert "Plant Vent Flow Rate" units:
Plant Vent Flow Rate Conversion Factor Plant Vent Flow Rate cfm x
472 cc/sec/cfin cc/sec 2.1 or 2.2 2.3 EP RB-9u3rl3.DOC 03B 0203.1409

69-9260 08/31/94 Page 2 of 5 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 3 - NOBLE GAS RELEASE Noble Gas Concentration 3.1
: a.
Record the plant vent radiation "Monitor Reading" from the EARS, ARMS, or RMS panel* in the Control Room (see Note below). Use RE-29 only if the RE-14/14R/87 monitors are unavailable.
: b.
Calculate the "Noble Gas Concentration" using the Monitor Response Factor from Figure 1, 2, or 3.
NOTE: Monitor Readings from the Control Room RMS Panel read in pCi/cc. If this reading is used in lieu of raw data, enter the value directly in 3.2 below.
Monitor Reading Monitor Response Factor Noble Gas Concentration cpm x
Ci/cc/cpm 
= 
"Ci/cc RE-14/14R Figure 1 Amps x
__tCi/cc/Amps 
=
pCi/cc RE-87 Figure 2 mR/hr x
gCi/cc/mR/hr 
=
_Ci/cc RE-29 Figure 3 Noble Gas Release Rate 3.2
: a.
Enter below the "Noble Gas Concentration" from Section 3.1 and the "Plant Vent Flow Rate" from Section 2.3.
: b.
Calculate and record below "Noble Gas Release Rate."
Noble Gas Conversion Plant Vent Noble Gas Concentration Factor Flow Rate Release Rate
_Ci/cc x
1E-6 Ci/gCi x
cc/sec Ci/sec 3.1 2.3 3.2 EP RB-9u3r13.DOC 03B 0203.1409

69-9260 08/31/94 Page 3 of 5 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 4 - IODINE RELEASE Iodine Monitors CAUTION: Do not attempt to access RE-24R or RE-87 without authorization from Radiation Protection.
4.1 Use the RE-24 or RE-24R iodine monitor (if on scale), or the extended range iodine sampler (RF-87), and go to the corresponding section to calculate the Iodine-131 equivalent release rate.
RE-24, RE-24R (Normal range monitoring)
Concentration Mode 
->Section 5 RE-24R (High range monitoring)
Count Rate Mode 
-- Section 6 RF-24R, RF-87 (High range sampling) 
->Section 7 SECTION 5 - RE-24, RE-24R (Normal range monitoring) Concentration Mode 1-131 Release Rate 5-1
: a.
Calculate the "1-131 Release Rate" using the higher of RE-24 and RE-24R.
1-131 Plant Vent Plateout Conversion Concentration Flow Rate Correction Factor Rc 4Ci/cc x cc/sec x
1.3 x 1E-6 Ci/VCi 
=
RE-24 or RE-24R 2.3 1-131 lease Rate 5.1 Ci/sec 1-131 Equivalent Release Rate 5.2
: a.
Calculate the "1-131 TEDE Equivalent Release Rate" and "1-131 Thyroid CDE Equivalent Release Rate" using Figure 4.1 and Figure 4.2 correction factors.
1-131 Release Rate Ci/sec x
5.1 1-131 Release Rate Ci/sec x
5.1 1-131 TEDE Correction Factor Figure 4.1 1-131 Thyroid CDE Correction Factor Figure 4.2 1-131 TEDE Equivalent Release Rate
=
Ci/sec 5.2.A 1-131 Thyroid CDE Equivalent Release Rate
*=
Ci/sec 5.2.B
*EP RB-9u3r13.DOC 03B 0203.1409

69-9260 08/31/94 Page 4 of 5 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 6 - RE-24R (High range monitoring) Count Rate Mode Flow Rate Ratio 6.1
: a.
Calculate "Flow Rate Ratio." Normal flow rate ratio is 1.3E5.
Plant Vent Flow Rate cc/sec 2.3 RE-24R Flow Rate cc/sec Local indication Flow Rate Ratio 6.1 Default Ratio or 1.3E5 1-131 Collection Rate 6.2
: a.
Record the "CPM Change Rate" as reported by personnel operating the RMS panel. (This data is gathered using EP RB-12 Section 6.1.3)
: b.
Calculate and record below the "1-131 Collection Rate."
CPM Change Rate Conversion Factor cpm/min x
1.4E-7 jiCi min/cpm sec 
=
1-131 Release Rate 6F.
3 1-131 Collection Rate
_Ci/sec 6.2 1-131 Concentration
._pCi/sec x 6.2 Flow Rate Ratio 6.1 Plateout Correction Conversion Factor 1-131 Release Rate Ci/sec 6.3 x
1.3 x 1E-6 Ci/tCi 1-131 Equivalent Release Rate 6.4
: a.
Calculate the "1-131 TEDE Equivalent Release Rate" and "1-131 Thyroid CDE Equivalent Release Rate" using Figure 4.1 and Figure 4.2 correction factors.
1-131 Release Rate Ci/sec 
+
6.3 1-131 TEDE Correction Factor Figure 4.1 1-131 TEDE Equivalent Release Rate Ci/sec 6.4.A 1-131 Thyroid CDE Equivalent Release Rate Ci/sec 6.4.B 1-131 Release Rate Ci/sec 6.4 1-131 Thyroid CDE Correction Factor Figure 4.2 x
EP RB-9u3rl3.DOC 03B 0203.1409

69-9260 08/31/94 Page 5 of 5 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.1 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Plant Vent Release SECTION 7 - RF-24R, RF-87 (High range sampling) 1-131 Release Rate 7.1
: a.
Record below the 1-131 Concentration for the RF-24R or RF-87 silver zeolite cartridge determined by EP RB-12, Section 6.2 (RF-24R) or 6.3 (RF-87).
: b.
Calculate and record "1-131 Release Rate.!"
1-131 Concentration Plant Vent Flow Rate Plateout Conversion Correction Factor x
1.9 x 1E-6 Ci/jtCi 1-131 Release Rate Ci/sec pCi/cc X EP RB-12 2.3 cc/sec 7.1 1-131 Equivalent Release Rate 7.2
: a.
Calculate the "I-131 TEDE Equivalent Release Rate" and "I-131 Thyroid CDE Equivalent Release Rate" using Figure 4.1 and Figure 4.2 correction factors.
1-131 Release Rate Ci/sec 1-131 TEDE Correction Factor Figure 4.1 1-131 Thyroid CDE Correction Factor 7.1 1-131 TEDE Equivalent Release Rate Ci/sec 7.2.A 1-131 Thyroid CDE Equivalent Release Rate
= _Ci/sec 1-131 Release Rate Ci/sec x
7.2 Figure 4.2 7.2.B EP RB-9u3rl3.DOC 03B 0203.1409

69-111{)5 02/03/09 Page 1 of 6
* 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 # __
Date Time of Readings Calculation #
Date Time of Rx S/D Calculation By:
(Rx S/D)
(name) 1.2 Determine the TIME AFTER RX S/D (Hrs)
Use Table 1 (Appendix 6.1) to determine appropriate Source Term. (circle otne)-
CORE GAP RCS SPENT FUEL 1.3 Indicate the~faulty steam generator by placing a check mark in a box below. 'Go to Section 2.1 or 2.2.
Faulted MSL MSL Flow Narrow 10%
Safety Steam Radiation Rate Range Steam Relief Generator Monitor Indicator Recorder Dumps Valves
[] SG-1 RE-71 FI-512 LR-517 PCV-19 RV-3,4,5,6,222
[] SG-2 RE-72 FI-522 LR-527 PCV-20 RV-7,8,9,10,223
[] SG-3 RE-73 FI-532 LR-537 PCV-21 RV-11,12,13,14,224
[
SG-4 RE-74 FI-542 LR-547 PCV-22 RV-15,16,17,18,225 SECTION 2 - STEAM FLOW RATE MSL Flow Rate Indicator, Operable 2.1 If the MSL Flow Rate Indicator on the faulty steam generator in Section 1.3 is operable, record below the greater of the reading indicated, or 4E5 lb/hr. Go to Section 2.3, MSL Flow Rate FR-512,522,532,542 lb/hr 2.1
* If less than 4E5 lb/hr, record and use 4E5 lb/hr.
MSL Flow Rate Indicator Inoperable 2.2
: a.
If the MSL flow rate indicator on the faulty steam generator in Section 1.3 is not operable, determine and record the "Number of Valves Open" releasing steam. ONLY INCLUDE VALVES OPEN ON THE MSL WITH THE FAULTY STEAM GENERATOR IN SECTION 1.3.
EP RB-9u3rl3.DOC 03B 0203.1409

69-11105 02/03/09 Page 2 of 6 EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Steam Release SECTION 2 - STEAM FLOW RATE (Continued) 2.2
: b.
Calculate the "MSL Flow Rate" by summing the "Valve Flow Rates." Go to Section 2.3.
Number of Valves Open Flow Rate Valve Flow Rate 10% Steam Dumps x
4.0 E5 lb/hr 
=
lb/hr Safety Reliefs x
8.5 E5 lb/hr 
=
lb/hr MSL Flow Rate = Y Valve Flow Rates 
=
lb/hr 2.2 Steam Flow Rate 2.3 Calculate and record the "Steam Flow Rate" using the "MSL Flow Rate," from Section 2.1 or 2.2. Go to Section 3.1 or 3.2.
MSL Flow Rate Conversion Factor Steam Flow Rate lb/hr x 3.1 cc hr/lb sec =
cc/sec 2.3 2.1 or 2.2 SECTION 3 - ISOTOPIC STEAM ACTIVITY FRACTIONS Isotopic Steam Activity Fractions - RCS Sample Analysis NOTE: If RCS Sample is not available, then skip Section 3.1 at this time and proceed with Section 3.2 (Page 4).
3.1
: a.
Record the date and time the Reactor Coolant System (RCS) sample was collected.
RCS Sample Collection Date and Time: 
/ 
/
: 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:
Steam Generator Water 'Level 3.1.c
[ ] Empty
[ ] Normal
[ ] Flooded S/G Level Narrrow Range: 
<13%
13%-96% 
>96%
EP RB-9u3rl3.DOC 03B 0203.1409

69-11105 02/03/09 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Steam Release Page 3 of 6 SECTION 3 - ISOTOPIC STEAM ACTIVITY FRACTIONS (Continued) 3.1
: d.
Determine the "Steam Partition Factors" for iodines and particulates using the water level indicated in Section 3.1.c. Record the "Steam Partition Factors" in Section 3.1.h below.
Steam Partition Factors lodines Particulates Empty 0.10 0.01 Normal 0.01 0.01 Flooded 1.00 1.00
: e.
Determine the "Density Correction" using the water level indicated in Section 3.1.c. Record the "Density Correction" below.
Density Correction Empty Normal 0.056 0.056 Flooded 1
All
: 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..
RCS Sample Activity Concentration
-Ci/cc Steam Partition Factor x 1.00 (For Section 5.1)
Density Steam Activity Correction Concentration g-ji Ci/cc a
(For Section 4.2)
Steam Activity Fraction Noble Gases lodines
!'jClIcc x
--jiCi/cc x
x ___
p Ci/cc b
a~d b~d c
d Particulates
[tCi/cc c
Total Steam Activity Concentration =
Ci/cc d = a+b+c EP RB-9u3r13.DOC 03B 0203.1409

69-11105 02/03/09 Page 4 of 6 EP RB-9 (UNITS I AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Steam Release SECTION 3 -ISOTOPIC STEAM ACTIVITY FRACTIONS (Continued)
Isotopic Steam Activity Fractions - FSAR Design Basis - Use only if RCS Sample is not available 3.2
: a.
Determine the faulty steam generator water level using the Narrow Range Level indication:
Steam Generator Water Level
] Empty
[ iNormal
[:1 Flooded S/G Level Narrrow Range: 
<13%
13%-96% 
>96%
: 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.
FSAR - Steam Activity Fractions Empy Normal Flooded Noble Gases 9.96E-01 9.99E-01 9.51E-01 lodines 3.36E-03 3.37E-04 3.20E-02 Particulates 1.78E-04 1.79E-04 1.70E-02 SECTION 4 - RELEASE RATES - MSL RADIATION MONITORS, OPERABLE NOTE: If there appears to be no net RE-7x indication, but the Control Room verifies that the monitor showed an initial Nitrogen-16 response or currently responds to check-source actuation, the monitor is OPERABLE. In this case the entire "background" reading may be used for this calculation to establish an "upper-bound" release estimate, but the method of Section 5.2 should be used to determine release rate'if possible.
MSL Activity Concentrations 4.1
: a.
Record the "MSL Monitor Reading" for the faulty steam generator indicated in Section 1.3.
: b.
Calculate and record the "MSL Activity Concentration" using the appropriate "MSL Monitor response from Figure 5.1, 5.2, or 5.3.
MSL Monitor MSL Monitor Conversion MSL Activity Reading 

===Response===
Factor Concentration cpm x gCi/cc/cpm x 1E-6 Ci/gCi =
Ci/cc RE-71,72,73,74 Appendix 6.6 4.1 EP RB-9u3r13.DOC 03B 0203.1409

69-11105 02/03/09 Page 5 of 6 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Steam Release SECTION 4 - RELEASE RATES - MSL RADIATION MONITORS OPERABLE (Continued)
Isotopic Release Rates 4.2
: a.
If a RCS sample is available, enter the "Steam Activity Fraction" from Section 3.1. If a RCS sample is not available, enter below the FSAR "Steam Activity Fraction" from Section 3.2.
: 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.
Steam Activity MSL Activity Steam Isotopic Fraction Concentration Flow Rate Release Rate Noble Gases Ci/sec 3.1 or 3.2 4.2 lodines x
Ci/cc x cc/sec =
Ci/sec 3.1 or 3.2 4.1 23 4.2 Particulates Ci/sec 3.1 or 3.2 4.2 SECTION 5-RELEASE RATES-MSL RADIATION MONITORS INOPERABLE-RCS ANALYSIS RCS Sample Analysis - Known Steam Flow Rates 5.1
: a.
Calculate and record "Isotopic Release Rate" for noble gases, iodines, and particulates using the "Steam Activity Concentrations" from Section 3. 1. Go to Section 6.1.
Steam Activity Steam Conversion Factor Isotopic Concentration Flow Rate Release Rate Noble Gases
_tCi/cc Ci/sec 3.1 5.1 lodines Ci/cc x 
-cc/sec x 1E-6 Ci/&#xfd;tCi =
Ci/sec 3.1 2.3 5.1 Particulates 
._Ci/cc Ci/sec 3.1 5.1 EP RB-9U3r13.DOC 03B 0203.1409

69-11105 02/03/09 Page 6 of 6 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.2 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for a Steam Release SECTION 5 - RELEASE RATES - MSL RADIATION MONITORS INOPERABLE -
RCS ANALYSIS (Continued)
RCS Sample Analysis - Known Primary to Secondary Leak Rate 5.2
: a.
Enter the "RCS Sample Activity Concentrations" and "Steam Partition Factors" for noble gases, iodines, and particulates recorded in Section 3..h (Page 3).
: 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.
RCS Sample Steam Primary to Activity Partition Secondary Conversion Isotopic Concentration Factors Leak Rate Factor Release Rate Noble Gases
[tCi/cc x
3.1 Ci/sec 5.2 Ci/sec 5.2 Iodines j..
Ci/cc x
3.1 x _
gpm x
6.3E-05 (Ci cc min)
([tCi gal sec)
Particulates ICi/cc x 
=
Ci/sec 3.1 5.2 SECTION 6 - NOBLE GAS AND 1-131 EQUIVALENT RELEASE RATES 6.1
: a.
Enter below the "Noble Gases Release Rate" and "Iodine Release Rate" from Section 4.2, 5.1, or 5.2.
: b.
Determine "Iodine TEDE Conversion Factor" using Figure 6.1 and "Iodine Thyroid CDE Conversion Factor" using Figure 6.2 and record below.
: c.
Calculate and record "1-131 TEDE Equivalent Release Rate" and "1-131 Thyroid CDE Release Rate."
Noble Gas Release Rate
=_
Ci/sec 6.1 Enter result of 4.2, 5.1 or 5.2 Iodine Release Rate Ci/sec x 4.2, 5.1, or 5.2 Iodine Release Rate Ci/sec x 4.2, 5.1, or 5.2 Iodine TEDE Conversion Factor Figure 6.1 Iodine Thyroid CDE Conversion Factor Figure 6.2 6.1 EP RB-9u3rl3.DOC 03B 0203.1409

69-10555 08/31/94 Page I of 2 DIABLO CANYON POWER PLANT EP RB-9 ATTACHMENT 7.3 1 AND2 TITLE:
Noble Gas and 1-131. Equivalent Release Rates for Containment Leakage SECTION 1 - GENERAL INFORMATION 1.1 Enter the following information: Unit # __
Date Time of Readings Calculation #
Date Time of Rx S/D Calculation By:
(Rx S/D)
(name) 1.2 Determine the TIME AFTER RX S/D (Hrs)
Use Table 1 (Appendix 6.1) to determine appropriate Source Term. (circle one):
CORE GAP RCS SPENT FUEL SECTION 2 - FSAR DESIGN BASIS NOBLE GAS AND 1-131 EQUIVALENT RELEASE RATES Average RE-30 and RE-31 Monitor Reading 2.1 Calculate the "Average Monitor Reading" for RE-30 and RE-3 1.
NOTE: If RE-30 and RE-31 are INOPERABLE, record the "EQUIVALENT RE-30/31 READING" from EP RB-14, 4.3.3.
RE-30 RE-31 Average Monitor Reading Monitor Reading Monitor Reading R/hr 
' X R/hr)1/2 R/hr 2.1 Average Monitor Reading to FSAR Design Basis Exposure Rate Ratio 2.2 Calculate the "Monitor to Design Basis Ratio" using Figure 7.
FSAR Monitor to Average Design Basis Design Basis Monitor Reading Exposure Rate Ratio R/hr 
+
R/hr=
2.1 Figure 7 2.2 EP RB-9u3rl3.DOC 03B 0203.1409

e 69-10555 08/31/94 Page 2 of 2 EP RB-9 (UNITS 1 AND 2)
ATTACHMENT 7.3 TITLE:
Noble Gas and 1-131 Equivalent Release Rates for Containment Leakage SECTION 2 - FSAR DESIGN BASIS NOBLE GAS AND 1-131 EQUIVALENT RELEASE RATES Noble Gas Release Rate 2.3 Calculate the "Noble Gas Release Rate" using Figure 8.
Monitor to Design Basis Ratio Design Basis Noble Gas Release Rate Noble Gas Release Rate Ci/sec 2.3 x
2.2 Ci/sec Figure 8 1-131 Equivalent Release Rate 2.4
: a.
Determine the "Design Basis 1-131 TEDE and Thyroid CDE Equivalent Release Rate" using Figure 9 and record below.
: b.
Calculate and record "1-131 TEDE Equivalent Release Rate" and the 1-131 Thyroid CDE Equivalent Release Rate.
Monitor to Design Basis Ratio 2.2 Monitor to Design Basis Ratio 2.2 x
x Design Basis 1-131 TEDE Equivalent Release Rate Ci/sec Figure 9 Design Basis 1-131 Thyroid CDE Equivalent Release Rate Ci/sec Figure 9 1-131 TEDE Equivalent ReleaseRate
=
Ci/sec 2.4 1-131 Thyroid CDE Equivalent Release Rate
=
Ci/sec 2.4 EPRB-9u3rl3.DOC, 03B 0203.1409

A
*** ISSUED FOR USE BY:
DATE:.
PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EXPIRES:____
NUMBER EP RB-16 REVISION 2
PAGE 1 OF 16 UNITS TITLE:
Operating Instructions for the EARS Computer Program 1 AND2 03/13/09 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE S C O P E...............................................................................................
1 D ISC U S SIO N............................................................................................................................................
1........
I D E F IN IT IO N S...................................................................................................................................................
1 R E SP O N SIB IL IT IE S........................................................................................................................................
1 IN ST R U C T IO N S...............................................................................................................................................
2 RE C O R D S.............................................................................................................................................. 
..... 15 APPENDICES 15 R E F E R E N C E S.......................................
15 A T T A C H M E N T S....................................................................................
16
: 1.
SCOPE 1.1 This procedure provides instructions for the use of the Emergency Assessment Response System (EARS) interface.
1.2 The EARS program incorporates the proprietary dose assessment program, MIDAS, as part of the dose assessment system.
1.3 This procedure is intended to be used as a reference for the Health Physicist and Emergency Supervising Engineer.
: 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.
2.2 MIDAS is the software program that performs atmospheric dispersion and dose assessment calculations. MIDAS runs inside the EARS system.
2.3 This procedure provides general guidelines for using the EARS system. Personnel using the EARS system for emergency response should be fully trained and qualified.
: 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.
EPRB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 2 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2
: 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.
The other is located in the Technical Support Center.
: a.
The Program is started by double-clicking the "Shortcut to EARS" button. You will be prompted to select either:
NOTE: Running the program in Drill mode without the drill feeder operating may result in a run-time error.
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.
This entry is optional, but recommended. If you choose to enter this information, enter your PG&E LAN ID or the facility where you are runnirng EARS (EOF/TSC).
CAUTION: If the next step the EARS program does not load the historic (24 hour) meteorology data, EARS was shut down incorrectly during the previous use (event). Proceed to section 5.2 for instructions on how to shut down EARS and restart a valid EARS event.
: d.
Click "OK". The program will then begin "Initializing the Met data",
loading the historic meteorology data (24 hours of data for determining wind field vectors). This may take a minute or two.
: 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.
EP RB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 3 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.2 Resolving an invalid startup of EARS NOTE: The initial time parameters for EARS should contain current date and time information in the "Reactor Shutdown", "Release Start" and the "Update" Date/Time fields. If EARS was not shut down correctly on the previous use, the Date/Time fields will contain dates and times from the last update performed in that event.
5.2.1 If the date and time does not reflect the current date and time in any of the following fields ("Reactor Shutdown", "Release Start", or "Update"), use the following steps to shutdown and restart EARS:
: 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:
"EARS Quit Posted Do you want to end the event?"
5.2.2 Restart the program by double-clicking the EARS icon and go to 5.1.la.
5.3 Selecting Plant Unit 5.3.1 You must select either Unit 1 or Unit 2 when you begin data entry for the program.
EP RB-16u3I02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 4 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.4 Entering Time/Date information in EARS 5.4.1 The initial time parameters for EARS should Contain current time and date information. If EARS was not exited correctly on the previous use, the time and date fields will contain information from the last update performed. If the date and time information is incorrect:
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:
Reactor Shutdown Time - needed to decay the source term (Gap or Core inventory) to the correct radionuclide fractions. EARS will be automatically round, the time to the nearest quarter hour preceding the time entered. This time may be the same quarter hour as the release start date/time.
0 Release Start Date/Time - needed to accurately project the distance that the plume has traveled and the areas affected by the release. This time will be rounded to the quarter hour preceding the time entered (ex. 09:10 would be 09:00).
0 Release Stop Date/Time - end of the projected release. The default value for this field is three hours (entered automatically by the program) after the release begins. For most scenarios, this value will be adequate. Do not edit this field unless you do not want a three hour release duration.
NOTE: The Date/Time fields for the program can be changed by high-lighting the entire field or the time portion of the field. You cannot change part of the time or date. The Date and Time field uses a pre-formatted configuration. You do not need to enter "/" for dates or ":" for time when entering data.
5.5 Selecting Source Term for EARS 5.5.1 The program will allow you to select from five different source terms:
Fuel rod gap (typically indicated by RE-30 or RE-31 reading of greater than 1R/hr and less than 300R/hr). This is the default setting for source term.
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)
EPRB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 5 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.5.2 For additional information on selecting the appropriate source term, see Appendix 6.1 of EP RB - 9, "Calculation of Release Rate."
5.5.3 Confer with the ESE, TSC engineering, and TSC RP staff, and obtain concurrence on the source term prior to proceeding with the dose calculation.
5.6 Selecting Pathways in EARS 5.6.1 Select the release pathway tab that corresponds to the current accident conditions. When the pathway is selected the screen will access plant information for current radiation monitors and modes of removal that may be applicable to the pathway and allow you to edit or add additional information.
: 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:
s EP EF-3, Attachment 6.21, "Leak Path Flow Chart" or, PEP EN-1, Attachment 8.7, "Emergency Engineering Guideline Computational Aids."
5.6.2 Confer with the ESE, TSC engineering, and TSC RP staff, and obtain concurrence on the release path prior to proceeding with the dose calculation.
5.6.3 If the release pathway is through the Plant Vent to the atmosphere, select the appropriate EARS tab from the eight red tabs on the menu.
5.6.4 For Plant Vent releases, proceed to attachment identified below for further instructions:
0 Containment Purge to Plant Vent (Attachment 9.1)
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)
EPRB-16u3d02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 6 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.7 Calculating Release Information (Starting MIDAS)
CAUTION: Do not begin an EARS calculation until a release has begun.
5.7.1 When you select the "Calculate" button the program will use the release data you have, input and the plant meteorological and radiation data as inputs to the MIDAS system to determine offsite dose projections. Before you initiate the MIDAS run EARS will provide a validation screen with the input data you have entered. When the validation screen appears, review the inputs with the Emergency Supervising Engineer.
5.7.2 If the input values are valid go to step 5.7.4.
5.7.3 If the horizontal stability field indicates "8", and all the other Met data~fields indicate "0", Click "CANCEL". These "0" values indicate that the "quarter hour" met tower data for this update time has not yet been communicated to EARS.
: 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.
5.7.4 Click "OK" after you have validated the data contained on the input screen.
The MIDAS program will launch with the Accident Run Menu selection set to "DOSE PROJECTIONS (MENU A)." The program will automatically print an input report with all the assumptions being used for the calculation.
5.7.5 Click "OK" again to begin calculations. A second input screen (MENU:A) will display the time elements of the calculation. Menu A is the primary method used for performing EARS/MIDAS calculations. The dropdown box allows you to select two other run options:
: a.
LAST 24 HOUR DOSE (MENU F) - Need more information here..12, MIDAS Menu F.
: 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.
CAUTION: Do not change the input parameters that are displayed on this screen.
5.7.6 Click "Start Calc." The program will display the TEDE plot.
EP RB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 7 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.7.7 Click "OK" when the "Print" dialogue box is displayed. A Dose Summary Report will be printed. It contains the information needed to make protective action recommendations based on dose, including current dose rates and projected total doses based on the release duration. This report is also referred to as the "State Report."
5.7.8 Close the report window (click upper right corner X) to return to the MIDAS graphical display. The program will now display the plume with the.4-day TEDE dose on the plot and the legend will contain the highest 4-day TEDE and CDE dose location.
5.7.9 If incorrect assumptions are identified, edit the input data and re-run the calculation using the same update time. Update times are usually entered by default, so you will need to enter the time at the bottom the EARS input screen.
5.7.10 If EARS "crashes" or the system locks-up during calculations, restart the program and enter data for any missing time periods. Data for the earlier updates will still be available. Find the time of the last saved update and re-enter data for each fifteen minute period until you have "Caught-up" to current time.
5.8 MIDAS Options Once the initial calculation has been performed the EARS program is able to display or provide reports for many other dose assessment parameters. The menu for this information is provided at the bottom of the display. The following section describes these options.
NOTE 1: Options that are available for each selection are designated by colors. Selected items are highlighted in light-green background. After a selection is made option buttons are high-lighted in yellow. The "confirm" button is high-lighted in flashing pink when it is ready to perform a new calculation.
NOTE 2: For most EARS/MIDAS runs you will want to print a 4-day TEDE Dose map (Section 5.8.2) and a CDE Thyroid Dose (Section 5.8.3) map.
5.8.1 Point of Interest (POI)
: 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).
: d.
Next, click the "POI" button to enable the function (toggles to "POI Active").
EP RB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 8 OF 16-TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2
: 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.
CAUTION: The data displayed using the POI function does not contain units. Numerical data for the POls will be in the same units as the map legend.
: 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.
5.8.2 TEDE Dose/Dose Rates The, following options may be selected for displaying/printing TEDE dose:
: 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 hours (15 minute puff release) 3 hours - default 8 hours 24 hours
: 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.
5.8.3, Thyroid CDE Dose/Dose Rates The following options may be selected for displaying/printing Thyroid CDE dose:
: 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 hours 3 hours - default 8 hours 0
24 hours EP RB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 9 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2
: 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.
5.8.4 EDE (Effective Dose Equivalent) Dose Rates The following options may be selected for displaying/printing EDE dose rates:
: 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 hours - default 3 hours 8 hours 24 hours
: 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.
CAUTION: If you need to go back to the TEDE or CDE screen you will need to change the exposure time for the display. EDE defaults to 0.25 hour and TEDE/CDE plots should be three, hours (TEDE/CDE default) unless you have been using a longer duration. The application will not automatically change this. exposure time. Toggle the exposure time button until you have the correct duration.
5.8.5 Field Monitors Field Monitoring estimates are available for the following parameters:
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.
5.8.6 Population Dose This function is provided to meet the requirements of NUREG 0654 (Section M.4) for the ability to calculate a population dose (manRem). It is a re-entry/recovery function that is rarely used.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 10 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.8.7 Plume Tracks This display shows the plume segments at each time interval. These are used by MIDAS to calculated ground deposition. This display does not provide useful information to the ERO other than to identify areas that may need to be monitored by field teams.
5.8.8 Special Reports
: a.
4-day TEDE Report - is prepared for each calculation (State Report).
This button simply provides another means of getting to the 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 hours 5.8.9 Ingestion Pathway
: a.
Five isotopes are considered for ingestion pathway factors:
1-131 Cs-134 Cs-137 SR-89 SR-90 EPRB-16u3r02.DOC 03B 0203.1245

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 11 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2
: 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 hours 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.
5.8.10 X/Q (dispersion [X/Q] and deposition [D/Q] coefficients)
.1 X/Qs may be display as a screen graphic or printed as tabular data. The "Bldg wk" (Building Wake) yellow button cannot be toggled. The X/Qs may be calculated in any of the following modes:
0 Undepleted - no deposition is removed from the plume Depleted Iodine - deposited iodine is removed from the plume 0
Depleted Particulate - deposited particulates are removed from the plume Deposited Iodine - deposition rate for iodines 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."
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 12 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.8.12 Print Map button The button with a printer icon can be used to send a screen print to the printer.
Click the button once to perform this function. The next dialogue box provides the following options:
0 Printer - sends map to local printer 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.
0 Email - allows you to send the screen primt to an Email address. You must enter the Email address. (This function is not enabled)
After you have made your choice, click "OK."
You may also print the map using a right-click. However, this will not include the legend and input information.
5.8.13 Map Features Button Information that is displayed on the screen maps can be changed using this option. Not all information on the menu can be displayed and much of the information cannot be displayed in conjunction with other information. In most cases it easiest to remove all options except the ones you wish to view Also some options must be at a small enough resolution to be viewed. This is particularly true for streets and street names.
The Map Features section also allows you to add emergency information to the map. The following options are available:
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
: 2.
To view Pressurized Ion Chamber (PIC) locations on the plume maps, click on the "PICs" box.
: 3.
Click "OK" to return to plume map screen.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 13 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.8.14 Zoom Out Button This button can be used to view larger sections of the emergency planning zone. You may also zoom (out or in) by right-clicking the mouse.
Additionally, you may zoom in by drawing a rectangle with the. mouse of the area you wish to view in greater detail.
5.9 Exiting a MIDAS Run (return to EARS input screen)
Select "End Run" from the menu at the bottom of the screen. Three options are available when you have finished a MIDAS run:
5.9.1 Run next time step - Save the current run and initiate the next run (15 minute intervals). A new run can only be initiated after a fifteen minute data averaging period.
5.9.2 Save Run and Exit - Save the current run and return to the EARS interface.
This is the standard option for returning to EARS and preparing for the next run. Once saved, the information can be shared with another workstation. You may also recap a previous run after exiting.
5.9.3 Exit without saving - Do not save the current run and return to the EARS interface. If you select this option your current run is not saved and cannot be recapped.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 14 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2 5.10 Exiting EARS To exit the EARS system, select "quit" from the Menu options at the top of the Input screen.
CAUTION: EARS should only be exited using the menu selection. Do not use the "X" close screen. If EARS is exited using the "X" method, the next launch of the program will contain inputs from the previous run.
5.11 Other EARS Program Options 5.11.1 MODE The default mode for EARS to run in is "local." When the program is run in the local mode it cannot be overwritten by users at another workstation.
5.11.2 OPTIONS 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.
Also, if busses are removed from service some radiation monitors will not be available.
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.
To close the window, re-click "View" and "Met Data."
: 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."
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 15 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2
: 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."
NOTE: You can view the information on the screen and see the instantaneous release rate calculation, isotopic fractions and current meteorological data with these screens. As selections are made the results are updated instantaneously on these screens. Other EARS/MIDAS functions (Add information for Store
[collects data from other time periods] and Recap (used by non-controlling
[TSC] station functions. Recap can also be used by the controlling station to look at previous runs.
5.11.4 Store This Function gathers the release rate and meteorological data into the MIDAS input files and the database without printing a release rate summary or invoking MIDAS. This is normally used when you need to catch up to a current time for a release that started in the, past or when wrong assumptions were made initially and need to be corrected. It is not necessary to run MIDAS for each 15 minute period; you can save the incremental periods and then run MIDAS one time to be current.
5.11.5 Recap The Recap function allows the user to view earlier EARS/MIDAS runs.
: a.
When the "MIDAS - Accident Dose Calculation" window appears, select the "Recap Previous Run" option.
NOTE: If you invoke the MIDAS calculation then the system will recalculate based on current time. The resulting MIDAS outputs may not match those previously performed due to the time difference (decay and deposition remove isotopes). The use of the RECAP function should be coordinated between the EOF and TSC EARS operators.
: 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

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-16 DIABLO CANYON POWER PLANT REVISION 2
PAGE 16 OF 16 TITLE:
Operating Instructions for the EARS Computer Program UNITS 1 AND 2
: 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,"
12/09/05 9.4 "Path 4 - Containment Release to the Plant Vent through Containment Sump and the Auxiliary Building," 12/09/05 9.5 "Path 5 - Steam Generator Release to the GE/GW area and then to the Plant Vent,"
02/03/09 9.6 "Path 6 - Plant Vent Release via the CVCS and Auxiliary Building," 12/09/05 9.7 "Path 7 - Plant Vent Release via CCW and the Auxiliary Building," 11/21/05 9.8 "Path 8 - Plant Vent Release via the Spent Fuel Pool and Fuel Handling Building,"
11/21/05 9.9 "Path 9 - Steam Generator Tube Rupture to Atmosphere," 02/03/09 9.10 "Path 10 - Design Basis Leak through Containment to Atmosphere," 11/21/05 9.11 "Manually Specified Release," 12/09/05 9.12 "MIDAS Menu F," 12/09/05 9.13 "MIDAS Menu X," 12/09/05 EPRB-16u3r02.DOC 03B 0203.1245

12/09/05 Page I of I DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.1 1AND2 TITLE:
Path 1 - Containment Purge to the Plant Vent
: 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
" 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.
Set Containment Spray Status (95% reductioin of iodine source term).
Three options are available to describe the use of containment sprays:
" None - containment sprays have not been used to remove activity from the containment atmosphere.
" One - One train has been used to remove for removal.
" Two - Both spray trains have been used.
If you select one or two pumps you must also enter the time that sprays were started. The program will take a 95% reduction for each time period that fans are running
: 5.
When you have finished entering data for the release path click the "Calculate" button.
: 6.
Return to step 5.7 of this procedure.
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12/09/05 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-16 ATT'ACHMENT 9.2 AND TITLE:
Path 2 - Release to the Plant Vent through the GE/GW Area Select data for this pathway:
: 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:
" R-14
" 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.
Set Containment Spray Status (95% reduction of iodine source term)
Three options are available to describe the use of containment sprays:
" None - containment sprays have not been used to remove isotopes from the containment atmosphere
" One - One train has been used to remove for removal
" Two - Both spray trains have been used If you select one or two pumps you must also enter the time that sprays were started. The program will take a 95% reduction for each time period that fans are running.
: 5.
When you have finished entering data for the release path click.the "Calculate" button.
: 6.
Return to step 5.7 of this procedure.
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12/09/05 Page I of 1 DIABLO CANYON POWER PLANT EP RB-16 ATTACFTMENT 9.3 1AND2 TITLE:
Path 3 - Containment Release to the Plant Vent through the Fuel Handling Building Select data for this pathway:
: 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-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.
Set Containment Spray Status (95% reduction of iodine source term)
Three options are available to describe the use of containment sprays:
" None - containment sprays have not been used to remove isotopes from the containment atmosphere.
* One - One train has been used to remove for removal
" Two - Both spray trains have been used If you select one or two pumps you must also enter the time that sprays were started. The program will take a 95% reduction for each time period that fans are running.
: 5.
When you have finished entering data for the release path click the "Calculate" button.
: 6.
Return to step 5.7 of this procedure.
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12/09/05 Page 1 of I DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.4 AND TITLE:
Path 4 - Containment Release to the Plant Vent through Containment Sump and the Auxiliary Building Select data 1for this pathway:
I
: 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.
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02/03/09 Page 1 of I DIABLO CANYON POWER PLANT EP RB-16 A 2 ATTACHMENT 9.5 2
TITLE:
Path 5 - Steam Generator Release to the GE/GW area and then to the Plant Vent Select data '.for this pathway:
I.
Exhaust Fans:
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.
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-14
" 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.
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.
" Empty (<13% level): 10% of the iodines and 1% of the 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.
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12/09/05 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.6 1AD2 TITLE:
Path 6 - Plant Vent Release via the CVCS and Auxiliary Building Select data for this pathway:
: 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.
5.
When you have finished entering data for the release path click the "Calculate" button.
Return to step 5.7 of this procedure.
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11/21/05 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-16.
ATTACHMENT 9.7 I1AN~D2 TITLE:
Path 7 - Plant Vent Release via CCW and theAuxiliary Building Select data for this pathway:
: 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:
" R-14
" R14R
" 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.
5.
When you have finished entering data for the release path, click the "Calculate" button.
Return to step 5.7 of this procedure.
EP RB-16u3r02.DOC 03B 0203.1245

11/21/05 Page 1 of I DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.8 AND TITLE:
Path 8 - Plant Vent Release via the Spent Fuel Pool and Fuel Handling Building Select data for this pathway:
: 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
" R14R
* 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.
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02/03/09 Page I of I DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.9 AND TITLE:
Path 9 - Steam Generator Tube Rupture to Atmosphere Select data for this pathway:
: 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:
e Flow monitor input:
Check "FM Input" checkbox Enter the flow rate in "Release Flow Rate" box in Ibm/hr (minimum flow rate is 4e5 lbm/hr) e Use 10% safety valve Check "10% safety" checkbox Select the Percent demand from the "Pct Demand" dropdown box. You may need to contact the Control Room to get this information.
Select which Safety valves are open (1-5)
: 3.
Water Level Three options are provided for water level in the Steam Generator:
e 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.
o Empty (<13% level): 10% of the iodines and 1% of the particulates are assumed to be released.
The water level is used to set the partitioning factors for iodines and particulates in the 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.
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11/21/05 Page 1 of I DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.10 1AND2 TITLE:
Path 10 - Design Basis Leak through Containment to Atmosphere This pathway is used to estimate dose resulting from small (design basis) leaks in penetrations in containment.
CAUTION: this method should only be used for an unknown release path where PICs or off-site monitoring indicates an unmonitored release is in progress.
Select data for this pathway:
: 1.
Set Containment Spray Status (95% reduction of iodine source term)
Three options are available to describe the use of containment sprays:
" None - containment sprays have not been used to remove isotopes from the containment atmosphere.
" One - One train has been used to remove for removal.
" Two - Both spray trains have been used.
If you select one or two pumps you must also enter the time that sprays were started.
: 2.
Radiation Monitors Either of the containment high range monitors (RM-30 or RM-3 1) may be used for this calculation.
Select the toggle button for the monitor you wish to use. The program will *hse the current reading for the monitor to determine release rates. You may also enter a value in the field.
: 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.
EP RB-16u3r02.DOC 03B 0203.1245

12/09/05 Page 1 of I DIABLO CANYON POWER PLANT EP RB-16 ATTACHMENT 9.11 1
AND2 TITLE:
Manually Specified Release Thissection of EARS allows you to create a release pathway if the accident does not fit one of the ten established pathways.
: 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.
EPR-f 
~0.~
3 2314 EP RB-16ur02.DOC 03B 0203.1245

112/09/05 Page 1 of I DIABLO CANYON POWER PLANT EP RB-16AN ATTACHMENT 9.12 AND TITLE:
MIDAS Menu F
: 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 hour 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."
EPRB-16u3r02.DOC 03B 0203.1245

I 12/09/05 Page I of 1 DIABLO CANYON POWER PLANT EPRB-16 ATTACHMENT 9.13 AND TITLE:
MIDAS Menu X-This methodology may be used to generate dose projections when the RMS is not available.
: 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."
6, Select "New" or "Edit Last" for the spreadsheet to edit. "New" will overwrite the previous version of the spreadsheet. Edit Last will allow you to edit or update the stored spreadsheet.
: 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.
EPRB-16u3r02.DOC 03B 0203.1245

.... 4.
*** ISSUED FOR USE BY:
DATE:
EXPIRES:____
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 NUCLEAR POWER GENERATION REVISION 27 DIABLO CANYON POWER PLANT PAGE I OF 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE:
Release of Airborne Radioactive Materials Initial AND Assessment 1A2 03/13/09 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
: 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.
1.2 It does not describe the operation of the plant equipment necessary to terminate or minimize the release. This latter subject is covered in the appropriate E, ECA, and FR series Emergency Procedures for the particular release mechanism.
: 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.
2.2 This procedure shall only be used by Control Room personnel to perform initial accident dose assessments. This procedure shall not be used to evaluate compliance with Technical Specification limits during planned effluent releases conducted as part of normal plant operations. The methodology contained in this procedure is intended to provide a rapid and conservative calculation of the projected off-site doses due to an accidental release of airborne radioactive materials. More advanced methodologies are contained in procedures EP RB-9 and EP RB-1I or the appropriate chemistry procedures.
: 3.
DEFINITIONS 3.1 Accidental Release: A release of radioactive material unrelated to any planned effluent release evolutions.
3.2 Committed Dose Equivalent (CDE): The dose to the organs or tissues that would be received from an intake of radioactive material by an individual during the 50 years following the intake.
3.3 Committed Effective Dose Equivalent (CEDE): The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the CDE to these organs or tissues.
EP R-2u3r27.DOC 03B 0203.1256

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 27 PAGE 2 OF 5 TITLE:
Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 3.4 Deep Dose Equivalent (DDE): Dose associated with exposure of the whole body (depth of 1 cm).
3.5 Total Effective Dose Equivalent (TEDE): The sum of the DDE (for external exposure) and CEDE (for internal exposure).
3.6 TEDE Rate: The time rate of change of Total Effective Dose Equivalent as a function of immersion and inhalation exposure time.
3.7 Thyroid CDE Rate: The time rate of change of Thyroid Committed Dose Equivalent as a function of immersion and inhalation exposure time.
: 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.
4.2 Interim Site Emergency Coordinator (ISEC) is responsible for determining when an assessment is needed and directing the EEC to implement this procedure based on emergency evaluation priorities.
: 5.
PREREQUISITES 5.1 Unified Dose Assessment Center (UDAC) is not activated and performing the function of radiological assessment.
5.2 Interim Site Emergency Coordinator (ISEC) has determined, based on plant accident conditions or symptoms of an accidental radiological release, that an initial assessment of projected off-site doses has priority over other actions being performed by the EEC.
The following listed symptoms indicate that an airborne release may be occurring from within the RCA as guidance to the ISEC:
There is actual of suspected leakage of water, steam, or noncondensible gases from any vessel or piping system containing primary coolant, liquid radwaste, or gaseous radwaste.
Damage occurs to a submerged, irradiated fuel assembly with the resultant release of significant quantities of noncondensible gases.
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.
A major radioactive material spill occurs.
EPR-2u3r27.DOC 03B 0203.1256

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 27 PAGE 3 OF 5 TITLE:
Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment
: 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.
6.2 If the Main Condenser is available during a SGTR event with a stuck open Safety Relief or 10% Steam Dump to atmosphere, there are two release pathways until the affected SG is isolated. The MSL monitor reading on the affected steam generator encompasses the total release rate of the simultaneous release paths.
6.3 Defaultrelease rates are extremely conservative and may result in higher classifications or PARs than would be warranted if actual release indications were available.
6.4 N-16 will be detected on the MSL Radiation Monitors while at power and may cause a false high off-site dose calculation.
6.5 This procedure shall not be used to evaluate compliance to Technical Specifications during planned effluent releases. Such evaluations shall be performed by the Chemistry Department.
6.6 Fuel Handling Accident (FHA) in Containment with Equipment Hatch open is a special case. Use the analyzed default dose rates and doses listed in Attachment 10.1 and go directly to EP G-l for comparison to the Emergency Action Levels (EALs).
6.7 For plant vent releases, including short duration puff releases such as a ruptured gas decay tank, TRS values for RM-14/14R (cpm) and RM-87 (amps) should be verified and the peak value used for performing the long hand EP R-2 calculation using attachments to this procedure.
: 7.
INSTRUCTIONS This calculation can be performed using the Plant Data Network (PDN) program "EPR2net" or by long hand, as follows:
7.1 Release Rate Calculations 7.1.1 Obtain a working copy of Attachment 10.1.
7.1.2 Determine release source location as Plant Vent, Atmospheric Steam Release, or Unmonitored.
CAUTION: Do NOT use SPDS to obtain radiation monitor readings.
7.1.3 Gather and record the required information in accordance with the appropriate section of the form.
NOTE: Plant Vent Extended Range Rad Monitor RE-87 will automatically activate if the Normal Range Gas Monitors RE-14/14R approach their maximum reading.
7.1.4 Perform the required calculation to determine the release rate of Total Effluent and record the results in both this Attachment and Attachment, 10.2.
EP R-2u3r27.DOC 03B 0203.1256

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 27 PAGE 4 OF 5 TITLE:
Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 7.1.5 If it is not possible to calculate a release rate, refer to the "Default Release Rates" on Page 3 of Attachment 10.1 and choose the most appropriate value for input to Attachment 10.2. For an FHA in containment with equipment hatch open, use default dose rates and doses from Attachment 10.1 and go directly to EP G-1 for comparison to the EALs.
7.2 Off-Site Dose Calculations Calculations may be performed using the Plant Data Network (PDN) program "EPR2net,"
or by long hand, as follows:
7.2.1 Obtain a working copy of Attachment 10.2.
7.2.2 Gather and record the required information in accordance with the appropriate section of the form.
NOTE: Plant Process Computer (PPC) Meteorological Data turn on codes are "METP" (Primary Data) and "METB" (Back-up Data).
7.2.3 Determine the appropriate activity source term and circle the associated Dose Conversion Factor (DCF) to be used in Section 4A and 4B.
7.2.4 Perform the required calculations to determine the TEDE and Thyroid CDE Rates.
7.2.5 Project the Release Duration in hours as input to determining projected doses.
7.2.6 If a duration cannot be projected, use the Default Duration of 3 hours.
7.2.7 Perform the required calculations to determine the TEDE and Thyroid CDE at the Site Boundary (800 meters).
7.2.8 Obtain an independent verification of your calculation whenever time permits to confirm no errors or incorrect assumptions about plant conditions.
7.3 Reporting the Results 7.3.1 REFER TO EP G-1 and compare the results of the above calculations with the Emergency Action Levels.
1.3.2 REFER TO EP RB-10 and compare the results of the dose calculations with the PAR determination criteria.
7.4 Advise the ISEC of any EAL thresholds that are exceeded based on site boundary dose rates and doses, or the need to revise PARs due to changing conditions.
7.5 Continuous Actions 7.5.1 As directed by the ISEC, continue to perform assessment of airborne releases to support evaluation of EAL status and PARs by repeating the above instructions:
7.5.2 Contact Chemistry to request:
: 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.
EP R-2u3r27.DOC 03B 0203.1256

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP-R-2 DIABLO CANYON POWER PLANT REVISION 27 PAGE 5 OF 5 TITLE:
Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment
: 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.
8.2 All checklists generated during activation of the EOF for a real event are non-quality records and shall be retained in RMS in accordance with ADI 0.1D2.
: 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."
11.2 EP G-2, "Activation and Operation of the Interim Site Emergency Organization (Control Room)."
11.3 EP M-6, "Fire."
11.4 EP RB-9, "Calculation of Release Rate."
11.5 EP RB-I 0, "Protective Action Recommendations."
11.6 EP RB-I 1, "Emergency Off-site Dose Calculations."
11.7 EP RB-12, "Mid and High Range Plant Vent Radiation Monitors."
11.8 AR A0595224, "PPC EPR-2 Not Valid for FHA in Containment with Hatch Open" 11.9 PG&E Calculation PAM-0-04-517, Rev. 4, 4/6/97 "Steam Generator Narrow Range Level Uncertainty."
11.10 PG&E Calculation STA-160, Freq., "Estimate of Expected Exposures Associated with a Fuel Handling Accident with Containment Open."
11.11 NRS-RES Calculation No. RA 93-12, New Dose Conversion Factors for EP R-2 and RB-I 1, Validation and Verification, Rev. 1, 12/15/93.
11.12 NOS-RECE Calculation No. RA 93-04, EP RB-9, Calculation of Release Rate, Rev. 7 and R-2, Release of Airborne Radioactive Materials, Rev. 12, Validation and Verification, Rev. 0, 4/12/93.
11.13 SH&ES Calculation No. EP-94-01, Rev 0, EP R-2, Release of Airborne Radioactive Materials, Rev 17, Validation and Verification.
EPR-2u3r27.DOC 03B 0203.1256

02/03/09 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.1 Page 1 of 3 1 AND2 TITLE:
Release Rate Calculations PLANT VENT RELEASE
: 1.
GENERAL INFORMATION Date:
Time:
Assessment No.
Assessment By:
Unit Releasing
: 2.
PLANT VENT FLOW RATE DETERMINATION A.
DIRECT - Plant Vent Flow Rate FR-12 (0-30x10 4 CFM (CFM) 
=
(CFM)
OR B.
ALTERNATE - Operating Ventilation Equipment (Max No. possible) 
#Fans (CFM/Fan)
FHB Exhaust (1) x 35,750 
=
(CFM)
Aux Bldg Exhaust (2) x 73,500 
=
(CFM)
GE/GW Area (1) x 25,000 
=
(CFM)
Cont. Purge (1) x 55,000 
=
(CFM)
Cont. Hydrogen (1) x 300 
=
(CFM)
Plant Vent Flow Rate 
=
(CFM)
: 3.
RELEASE RATE CALCULATION CAUTION: Do NOT use SPDS to obtain monitor readings.
A.
NOBLE GAS RELEASE RATE Circle Reading (Units)
Monitor Used Conversion Factor Plant Vent Flow Rate (CFM)
Primary Backup RE-14/14R/87 pCi/cc x 4.72E-04 x
RE-29 mR/hr x 4.72E-06 x
B.
TOTAL EFFLUENT RELEASE RATE NOTE: Referto Page 3 for criteria in choosing RCS, GAP, or CORE below.
Noble Gas Release Total Effluent Rate (Ci/sec)
Conversion Factor Noble Gas Release Rate (Ci/sec)
Total Effluent Release Rate (Ci/sec) x 1.00 (RCS) 
=
1.11 (GAP) 1.50 (CORE)
NOTE: If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3 of this attachment.
GO TO ATTACHMENT 10.2 EP R-2u3r27.DOC 03B 0203.1256

02/03/09 Page 2 of 3 EP R-2 (UNITS l AND 2)
ATTACHMENT 10.1 TITLE:
Release Rate Calculations 1
GENERAL INFORMATION ATMOSPHERIC STEAM RELEASE Date:
Time:
Assessment No.
Assessment By:
Unit Releasing CAUTION: When critical, N-16 activity seen by MSL Rad Monitors causes invalid readings for offsite dose.
Post-trip, RE-7X reading is valid if the RE-7X monitor showed an initial N-16 response, or responds to checksou rce.
NOTE: If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3.
: 2.
STEAM RELEASES - Use this form to calculate steam releases to the atmosphere WHEN NOT critical.
A.
Required Information (RUPTURED GENERATOR ONLY)
Check MSL Rad Reading S/G LvI Level S/G Flow Flow Rate Ruptured S/G Monitor (cpm)
Narrow
(%)
Rate (lbs/hr)
Range If <4E5 use 4E5
[
SG 1 RE-71 LI-517 FI-512 SG 2 RE-72 LI-527 FI-522
[
SG 3 RE-73 LI-537 FI-532 SG 4 RE-74 LI-547 FI-542 B.
Alternate Steam Flow Rate (Only if the RUPTURED S/G Flow Rate is otherwise not available)
Valve Type 
# Valves Lifted Capacity (lbs/hr)
Flow Rate (lbs/hr) 10% Steam Dump (1 per S/G) x 4.OE+05 Safety Reliefs (5 per S/G) x 8.5E+05 
=
Total Steam Flow Rate (lbs/hr) 
=
(lbs/hr)
: 3.
RADIATION MONITOR FACTORS (Determined based on S/G NR Level indication) (Enter in Section 4 below.)
S/GLevel EMPTY NORMAL FLOODED Narrow Range 
<13%
13% - 96% 
> 96%
Monitor Factor 6.08E-10 6.75E-10 3.07E-10 (DEFAULT)
: 4.
RELEASE RATE CALCULATIONS A.
TOTAL EFFLUENT RELEASE RATE (RE-7x)
MSL Monitor Reading Flow Rate Monitor Factor Total Effluent Release (cpm)
(lbs/hr)
Rate (Ci/sec) x x
GO TO ATTACHMENT 10.2 EP R-2u3r27.DOC 03B 0203.1256

02/03/09 Page 3 of 3 EP R-2 (UNITS I AND 2)
ATTACHMENT 10.1 TITLE:
Release Rate Calculations
: 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.
A.
Check the accident type which most closely resembles the current event.
Default Release Source Rate (Ci/sec)
Term
[
[
]
]
Accident Source LOCA (w/ core melt)
LOCA (w/o core melt)
Main Steam Line Break Feedwater Line Break Blackout Locked Rotor FHB Accident Rod Ejection GDT Rupture LHUT Rupture VCT Rupture 1.74 E+1 5.74 E+0 8.61 E-3 8.61 E-3 8.62 E-1 1.57 E-2 1.45 E+1 1.08 E-2 4.14 E+1 3.10 E+1 8.29 E-2 Condition RE-30 or 31 >300R/hr RE-30 or RE-31 <300R/hr RE-30 or RE-31 not on scale CORE GAP RCS RCS RCS RCS GAP GAP GAP RCS RCS RCS S/G Tube Rupture 1.65 E+0 NR S/G Level <13%
SG - Empty NR S/G Level 13-96%
SG - Normal NR S/G Level >96%
SG - Flooded
[ Containment FHA S.B. Dose TEDE = 13.4 mrem/hr Go Accident with Equip.
Rates Thy. CDE = 51.4 mrem/hr Directly to Hatch Open S.B. Doses TEDE = 6.7 mrem EP G-1 Thy. CDE = 25.7 mrem B.
Record the Default Release Rate in Attachment 10.2, Section 4 and use the DCF choice that is listed for the specific accident source above.
GO TO ATTACHMENT 10.2 EP R-2u3r27.DOC 03B 0203.1256

08/05/94 Page 1 of 1 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.2 1 2 TITLE:
Off-Site Dose Calculations
: 1.
GENERAL INFORMATION Date:
Time:
Assessment No.
Assessment By:
Unit Releasing
: 2.
METEOROLOGICAL DATA-PPC (Plant Process Computer)
Turn On Codes for Met Data are "METP" (Primary Data) or "METB" (Back-up Data)
Parameter Reading Units DEFAULT Wind Speed (10 Meter Level) meters/sec Wind Direction (10 Meter Level)
Degrees Site Boundary XIQ (0.8 kin)
Secim3 5.29E-04
: 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)
A.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
Total Effluent or Site Boundary Default Release XIQ (0.8 km)
DCF Rate (Sec/m3)
(circle one)
(Cilsec) i.E + 05 (RCS) 3.OE + 06 (Gap) x x
1.1E + 07 (Core) 0.1.
1.1E + 05 (SG-Empty) 4.3E + 04 (SG-Normal) 9.3E + 05 (SG-Flooded)
TEDE Rate (mrem/hr)
Projected Release Duration (hr)
(DEFAULT 3 hrs)
TEDE (mrem)
]X7 _
B.
THYROID COMMITTED DOSE EQUIVALENT (CDE) (DO NOT COMPLETE FOR GDT, LHUT, OR VCT RUPTURE)
Total Effluent or Site Boundary Projected Default Release X/Q (0.8 km)
DCF Thyroid Release Rate (Secim3)
(circle one)
CDE Rate Duration (hr)
(Cilsec)
(mrem/hr)
(DEFAULT 3 hrs) x 0.1 1.5E t 06 (RCS) 6.5E + 07 (Gap) x 7.7E + 07 (Core) 1.5E + 06 (SG-Empty) 1.5E + 05 (SG-Normal) 1.4E + 07 (SG-Flooded)
Thyroid CDE (mrem)
LllX_
: 5.
REPORTING THE RESULTS -(Refer to Section 7.3 of Instructions for details)
A.
Refer to EP G-1 for EAL criteria.
B.
ImplementEP RB-10 for PAR criteria EP R-2u3r27.DOC 03B 0203.1256

10/20/08 Page 1 of I DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.3 AND TITLE:
EPR2NET Application
: 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.
EP R-2u3r27.DOC 03B 0203.1256

10/20/08 Page 1 of 2 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.4 1AND 2 TITLE:
Plant Vent Release PLANT VENT RELEASE DATA ENTRY:
L General Information
: 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",
THEN Click on "ALTERNATE", and Place a check mark in the box next to all the fans that are operating.
: 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)
AND indicates "OK" to the right of the activity value, THEN select RM-87 if it indicates "OK" to the right of the RM-87 activity value.
: 4)
IF RM-87 indicates "UNREL" instead of "OK",
THEN select RM-29.
For a Fuel Handling accident or Tank Rupture Release:
: 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.
CAUTION: Every time you click the "NEXT" button at the bottom of this page, the program creates another 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.
EPR-2u3r27.DOC 03B 0203.1256

10/20/08 Page 2. of 2 EP R-2 (UNITS 1 AND 2).
ATTACHMENT 10.4 TITLE:
Plant Vent Release
-DOSE CALCULATIONS DATA ENTRY:
: 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 0.1.
: 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 hours).
a)
Enter 0.25 hours for a release under 15 minutes.
: 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.
EP R-2u3r27.DOC 03B 0203.1256

10/20/08 Page 1 of 2 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.5 AND TITLE:
Atmospheric Steam Release ATMOSPHERIC STEAM RELEASE DATA ENTRY:
: 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.
CAUTION: Every time you click the "NEXT" button at the bottom of this page, the program creates another 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.
EP R-2u3r27.DOC 03B 0203.1256

1'0/20/08 Page 2 of 2 EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.5 TITLE:
Atmospheric Steam Release DOSE CALCULATIONS, DATA ENTRY:
: 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 0.1.
: 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 hours) a)
Enter 0.25 hours 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.
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