ML20214K148

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Issue 7 of Rev 7 to Emergency Preparedness Plan Implementing Procedure EPP/I-1, Recognition & Classification of Emergency Conditions
ML20214K148
Person / Time
Site: Beaver Valley
Issue date: 06/26/1986
From: Lacey W, Sieber J
DUQUESNE LIGHT CO.
To:
Shared Package
ML20214K130 List:
References
EPP-I-1-I07, EPP-I-1-I7, NUDOCS 8608180152
Download: ML20214K148 (75)
v • d • e


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i RECOGNITION AND CLASSIFICATION

! 0F EMERGENCY CONDITIONS 1

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OSC Meeting Number: BV-OSC-30-86 Reviewed: A . June 26, 1986 Approved: h l Plant M(nager -

Approved: . 1 V ,

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i Issue 7, Rev. 7 lO 8608180152 860812 PDR f

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- -- EPP/Isrplementing Procedure EPP/I-1 Recognition and Classification i- of Emergency Conditions

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TABLE OF CONTENTS I A. Purpose t ..

f B. References i

j C. Responsibilities i

l D. Action Levels / Precautions I

i E. Procedure i

F. . Final Condition G. Attachments

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. EPP/Implimenting Proctdura EPP/I-1

' Recognition and Classification of Emergency Conditions D I i

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A. Purpose 1.0 This procedure describes the immediate actions to be taken to recognize and classify an emergency condition.

2.0 Identified are the four emergency classifications, the initiating event (s) and emergency action levels for each classification.

! B. References 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.

2.0 Title 10, Code of Federal Regulations Part 50, Appendix E.

3.0 NUREG-0654/ FEMA-REP-1, " Criteria for Preparedness and Evaluation I

of Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

4.0 Beaver Valley Power Station Operating Manual.

C. Responsibility The Emergency Director (Shift Supervisor, until properly relieved by a designated alternate) has the responsibility and authority for 4

CI implementation of the actions prescribed in this procedure.

D. Action Levels / Precautions l

1.0 Action Level 1.1 An off-normal event, corresponding to one of the initiating events described herein, has occurred.

1.2 An action step in a Plant Operating or Emergency Operating

{ Procedure refers to this procedure for classification of the indicated plant conditions.

2.0 Precautions l

2.1 Continued surveillance and assessment of plant conditions are '

j necessary to ensure that the emergency classification is l

eppropriately revised as conditions change, or as more i i.efinitive information is obtained.

2.2 Emergency Action Levels (EAL's) are specified in the TABS to this instruction, in Attachment 1 to this procedure and in the BVPS Emergency Plan, Table 4.1.

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EPP/ Implementing Procedure EPP/I-1 .

Recognition and Classification cf Emergency Conditions NOTE The EAL's in the TABS to this procedure have precedence over other EAL's should a conflict between EAL's be noted.

2.3 EAL's will be triggered by the results of offsite dose projections and assessment of plant status by the onshift operating staff or the Emergency Organization, if activated.

In many cases, the proper classification will be immediately apparent. In other cases, more extensive assessment is necessary to determine the applicable emergency classification.

2.4 Table 1 (Attachment 1) demonstrates how an initiating condition leads directly to the appropriate emergency classification, based on the magnitude of the event.

2.5 Attached to this instruction are data sheets to be used in classifying emergency conditions. Each data sheet identifies the initiating condition (ie., RCS Pressure Hi/ Low) and the respective emergency action levels for each classification.

Identified with each EAL is a representative listing of the various instruments and other indications which may be symptoms of an emergency, or which could be used to asseas and classify the condition. These symptoms should not be confused with the actual EAL criteria detailed in the Tabs.

2.6 Plant operating personnel should use Table 2 (Attachment 2) as guide only. This list of accidents / events identified in the BVPS FSAR gives the emergency classification corresponding to the postulated accident outcome. It is unlikely that the actual accident conditions will be the same as those analyzed and the higher or lower emergency classifications may be warranted.

2.7 The EAL's in Table 1 and Table 2 have been developed to provide adequate response to postulated emergency conditions that could exist at Beaver Valley. Emergency conditions could arise, however, that are not covered by a specific EAL.

In these cases emergency conditions should be classified by the general definitions of the emergency classes which are:

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. EPP/Irplementing Proc dura EPP/I-1 Recognition and Classification of Emergency Conditions iG t

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a. Unusual Event - Off-normal events which could indicate a potential degradation of the level of safety of the plant,
b. Alert - Events which indicate an actual degradation of the level of safety of the plant.
c. Site Area Emergency - Events which involve actual or likely major failures of plant functions needed for protection of the public.
d. -General Emergency -

Events which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

E. P_rocedure 1.0 Verify 1.1 Upon receipt of an initial indication (alarm, surveillance report, observation, etc.) that an emergency condition may exist, an assessment shall be initiated to verify the validity of the indication and whether the EAL criteria have been met. This may be performed by comparison to redundant instrument channels, comparison to other related plant O, parameters, physical observations and field measurements.

1.2 If this assessment cannot be completed within 15 minutes of the initial indication, it shall be considered that the emergency condition indicated does exist and appropriate emergency actions shall be initiated in accordance with the applicable emergency implementing instructions or procedures.

2.0 Classification

! 2.1 Locate the appropriate Tab in Attachment 3. Tabs are arranged by initiating event (s); either a single plant parameter (ie., RCS Pressure Hi/ Low) or parameters (ie., Fuel Clad Degradation).

i 2.2 Determine the appropriate emergency classification by

comparing the verified plant parameters to the EAL's for each emergency condition.
2.3 Declare the appropriate emergency condition. Perform
additional actions in accordance with the Emergency Operating Procedures and the appropriate EPP/ Instructions

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EPP/Impicmentin; Procedurs EPP/I-1 .

Recognition and Classification cf Emergency Conditions 2.3.1 EPP/I-2 Unusual Event e

2.3.2 EPP/I-3 Alert 2.3.3 EPP/I-4 Site Area Emergency 2.3.4 EPP/I-5 General Emergency NOTE Title 10, Code of Federal Regulations Part 50, Appendix E, states, "A licensee shall have the capability to notify responsible State and local governmental agencies within 15 minutes after declaring an emergency".

3.0 Abnormal Conditions 3.1 If the abnormal condition does not constitute an Unusual Event or greater, continue corrective actions in accordance with the BVPS Operating Manual and resume normal operations.

3.2 If the event is not classified as an Unusual Event, but is reportable to the NRC pursuant to OM Chapter 48, Section 9.D.

DLC Corporate Communications should be notified of the event for a possible press release. The event should be reported using the NRC Event Notification Form found in EPP/IP 1.1, Attachment 4.

3.3 Should station management deem it necessary, a courtesy call should be made to the primary offsite agencies (BCEMA, PEMA, CCDSA and HCOES) on a timely basis consistent with normal working hours.

3.4 Assessment actions shall be continued, and if necessary, the emergency classification escalated (or downgraded) as nore definitive information becomes available of if plant conditions change significantly.

F. Final Conditions 1.0 The initiating conditions have been de-classified to non-emergency status and any termination requirements per BVPS/IP's have been satisfied.

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EPP/Impicasnting Procedure EPP/I-1

, Recognition and Classification
of Emergency Conditions
G. Attachments -

} 1.0 Table 1, Action Level Criteria for Classification of Emergency i Conditions.

2.0 Table 2, FSAR Postulated Accident Classifications.
3.0 Data Sheets for Classification of Emergency Conditions.

f' 4.0 BVPS Exclusion Area 1

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EPP/IP Implementing Procsduro EPP/1-1 Cccogiesticn and Classificotlon cf Emergency Conditions i

1A.BLE 4.1 - ACTION L{y[L CRITERIA FOR CLASSIFICATION OF EMERGENCY CONDITIONS INITIATING UNUSUAL ALERT SITE AREA GENERAL CONDITION EVENT EMERGENCY EMERGENCY Orr-normal Events Events Which Indicata Events Which involve Events Which which Could Indicate an Actual Degradation Actual or Likely involve Actual a Potential Deg ra d- of the Level or Safety Major Failures or or Imminent ation of the Level of the Plant. Plant Functions Needed Substantial Core of Safety of the for Protection or the Deg rada t ion o r me l t-Plant. Public. ing with Potential for Loss or Containment integ ri ty.

i R:dioactive Erriuent Unplanned airborne Unplanned airborne Release Corresponds Radiological effluent selease gives orrsite release gives orrsite to )20 arem/hr. at release results in ADPilff ble go_ Aryy dose rate greater dose rate greater Site Boundary orrsite dose projected

!!21ea se_fg}nt[1) than 0.5 enem/hr. than 2.0 mrem /hr. *

-or- to exceed 1 rem and Rg9ulijng_from Orrsite Dose Due to the Whole Body A!!yJn3 tja11ng_1 vent to Event is or 5 rem to the

-or- -o r- Projected to Exceed Child Thyroid.

Unplanned liquid Unplanned liquid 170 arem to Whole release in excess release results in Body or Child Thyroid, or HPC Ilmits. downstream community water radioactivity and/or greater than 12 times EPA standards.

R31 ease or Loss of fuel Handling Acci , Major Damage to Spent Radiological effluent Control of Radinactive dent Resulting in Fuel Due to Fuel corresponds to greater Material Within the Release of Radioactiv- Handling Accident than 125 mrem /hr. whole Plant. ity to occupied -o r- body dose rate or Areas Such That the Uncontrolled Decrease 600 mrem /hr. child Direct Radiation in fuel Pool Water thyroid at the site i levels in the Areas to Below Level boundary.

' increase by a Factor of Fuel.

7 or > 1000 1 -or-1 Other Verirled, Uncon-trolled Events Which Result in an Unexpected '

increase of in-Plant i Direct Radiatico Levels by a f actor of > 1000.

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EPP/IP laptementing Procedure EPP/l-1 R: cognition and Classification of Esergency Conditions TABLE 4.1 - ACTION LEVEL CRITERIA FOR CLASSIFICATION OF EMERCENCY CONDITIONS INITIATING UNUSUAL ALERT SITE AREA GENERAL CONDITION EVENT EMERGENCY EMERGENCY practor Coolant System Below Tech Spec Loss or 2 or 3 Fission Limiting Conditions Product Barriers With a (RCS) Potential Loss of Third lemperature Low for Operation (LCO)

Ba rrie r.

AppR gab _Le to An M nitiatine RCS Pressure liigh Exceeds LCO Limit [veDL_1tJa _May Lead to this Cond tion i TAB 4 -o r-Any Initiating Events, from 1

, RCS/ Containment teak Exceeds LCO Exceeds 50 gpa Exceeds Make-up Capacity Whatever Source that Makes

Release of Large Amounts or Radioactivity in a I l_JAE3 5 Snort Time Probabie, RCS/ Secondary teak Exceeds LCO >200 gpm >50 gpm w/ MSL l

li4El (5 -or-

>10 gpa w/ MSL Break areak w/ indication of fuel failure

i. LOCA Wien raiiure or ECCS.

Main steam Line ,

Break or Rapid 2. LOCA With initially Succ-essful ECCS. Subsequent Depressurization -or- -or-

"' Failure of Heat Removal of Secondaty Side "

MSL Break w/ MSIV > 1000 gpa Systems with Likely Failure of Containment.

l Failure i li4E3 7 - 3. toss or Aii Onsite and Orrsite Power Concurrent i

g3g i fuel Cladding RCS Activity Exceeds RCS 1 Activity Degraded Core-Post.ible With Total Loss of

! Degradation LCO -or- > 300 uCl/gm Loss of Coolabie Emergency Feedwater, i Reactor Coolant Ceomet ry.

4 Mosil tor Ala rm, or 4. Loss of Feedwater and or analyses I uCi/ Condensate followed by go, Steady State Failure of Emergency l)h(3 ($ Feedwater System.

I 1 RCS Sa ro ty o r Leak Exceeds tCO or 5. Reactor Protection System

! Relief Valvo Valve Inoperable Falls to initiate or

! leiliare Complete a Required Scram, Followed by Loss of Core Cooiing and Make-up Systems 10&E3 9 -o r-ItCS temposatute Iligli Exceeds 100 ,

Loss of Plant Control,0ccurs 1;&E3 3  ;

RCS Pr essist s? tow Deinw 100 TAB _4 s

EPP/IP Impicsenting Proegdure EPP/l-1

, COcognition cod Classification

! cr Emergency conditions j TABLE 4.1 - ACTION LLy[L CRITERIA FOR CLASSIFICATION OF EMERCENCY CONOITIONS INITIATIN G UNUSUAL ALERT SITE AREA GENERAL CONDITION EVENT EMERGENCY EMERGENCY Initiation of ECCS Va l id Sa fe ty Ci rcu i t Lost of 2 or 3 Fission Irip or Necessary Product Barriers With a Manual Initiation. Potential Loss or Third if/kE3 1() Ba rrie r.

RCS rump Tallure L Impeller Slezure Anglica bj e to Any j n _ i t i a t i nq r- Event that May Lead to

'r/ LEI 11 _ _ - _ _ _ enis Conastion.

< -o r-I t oss of Conta isiment Requiring Shutdown Containment Pressure Any Initiating Events, from Integrity by LCO >5 & C45 psig Whatever Source that Makes l

Release or Large Amounts i lbkE3 12 or Radioactivity in a Short Time Probable, j

J Loss of Engineered Requiring Shutdown For Example:

i Safety or rise by 100 l Protection features 1. LOCA With Failure of ECCS.

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2. LOCA Witn initiaisy Succ-l essful ECCS. Subsequent f ailure of Reactor Reactor Not failure of lleat Removal Protection System m. Subcritical after Systems with Likely to initiate or y- Va l id Scram Failure of Containment.

Complete a Scram Signal (s).

3. Loss of All Onsite and iT/kEl 1kt Orrsite Power Concurrent With Total Loss or loss of Planet Loss of Capability Loss of Capability Emergency Feedwater.

Con t s o l /Sa f e ty k- to Aclileve Cold to Achieve Hot Systems r' Shutdown Shutdown 4. Loss of Feedwater and Condensate Followed by 1rAI3 15 raiiure or Emergency Feedwater System, toss of I rid ica ta r s, loss on Process Loss or All Loss of All Annunciators or or Errluent Pa ra- Alarms ( Annuncia- Ala rms 15 min 5. Reactor Protection System Alarms meters, Requiring tors) Sustained for with Plant Not in Falls to initiate or Shistdown by LCO 5 mins. Cold S/D Complete a Required Scram,

-or- Followed by Loss of Core Plant T ra ns i ent Cooling and Make-up Systems Occurs While All -o r-Alarms are Lost. Loss of Plant Control Occurs.

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Control Room Requi red or Ant i- Required. Shutdown

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cipated. Control of System Control at Shutdown Systems Remote Shutdown Panel Established at Not Established Remote Shutdown Within 15 min.

y Panel.

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EPP/l-1

[PP/IP Implementing Procedure Rscognition sted Classificatiosi or imeegency Conditions TABLE 4.1 - ACTION t[ VEL CRITERIA FOR CLASSIFICATION OF EMERGENCY CONDITIONS UNUSUAL ALERT SITE AREA GENERAL INITIATING EMERGENCY EMERGENCY  ;

CONDITION EVENT t

H-a r-by or On-Si te Enters Facility. Enters Vital Areas Loss of 2 of 3 Fission fonic os Flame-Release Potentially Potential Habit- and Restricts Product Barriers With a able cases lia rm f u l , ability Problems. Necessa ry Access. Potential Loss or Third Barrier.

10413 1 13 in Accordance with Security Plans imminent Loss of ARelicable tg_A_ny Initiatino Seceir s ty Compsomise Playsical Control Lygn_i_1lja t May Lead to of Plant. This Condition.

TAB 19 -or-Any initiating Events, from toss of Capability Whatever Source that Makes loss or On-Site Release of Large Amounts of Radioactivity in a AC Power Short Time Probable, Loss or Both ror Exampie:

TAB 20_ _ _ - - _ - _ _ _ _ _ _ _ _ Temporary toss or Botn. Exceeds 15 mins.

1. LOCA With Failure of ECCS, toss of All off- Upose occurence Site Power 2. LOCA With initially Succ-essful ECCS. Subsequent lEkj3 2I) failure of Ileat Removal upon Occurrence Loss or Vital DC Systems With Likely Loss of All Osi- ,,

Power for More Failure of Containment, Site DC Power ,,

than 15 mins.

3. toss or Aii onsite and lEAI3 21 Orrsite Power Concurrent Warning. Probable Strikes Vital Winds in Excess With Total Loss or lorsiado or ottier of Design Levels Emergency Feedwater.

liigh Wisid3 Effect on Station. Plant St ructures.

4. Loss of Feedwater and Flood >735 feet MSL Condensate followed by f lood or t ow Flood <105 feet Flood > 105 rent MSL Failure of Emergency MSL, Requiring -or-gWater Damage to Vital Feedwater System.

S/D. tow Water

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5. Reactor Protection System lbkE3 2$3 fails to Initiate or Creater than OBE Creater than SSE Complete a Requi red Scram, Farthquake Detected on Site Followed by Loss or Core Soismic Inst reamenta- Occurs Occurs Cooling and Make-up Systems tion. -o r-TAB 24 Loss of Plant Control Occurs, Within Plant. Not Potentially Arrecting Arrecting Safety '

Fire Systems Required Untfe r Cont r o l in Safety Systems. '

to mins. Af ter ror Shutdown.

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E l r/ I P leplencest ing Ps ocMu s e EPP/1-1 Cicognition esal classif Icotloss of f ees gessey Cosedi t ions j,AM[_st.1 - ACllON LEVEL ERITERI A FOR CL ASSIFICATION OF EMERCENCY CONDIT IONS INITI ATING UNUSUAL ALERT SITE ARE A GENERAL CONDlilON EVENT EMERGENCY EMERGENCY fwplosion Nea r o r on-s i te Known Damage to Severe Damage to Loss or 2 or 3 Fission

[=p f os t os Po tesit ia l Facility, Affecting Safe Shutdown Product Barriers With a Sigestricant Damage operation. Equipment. Potential Loss of Third TAB 26 sa crie r.

Alsssaft Ossessesa l Activity Aircraf t or Missile Crash Affects Vltal Applicabje_tg_Any_lnillating over f ac4 8 8 ty f rom Whatever Source Structures by [vesig_ g tia g_Ma y Lead to

-or- Strikes and Signirl- Impact or Fire. this Condition.

Alecsart Crashes cantly Degrades a -or-Osisite Station Safety Any Initiating Events, from Structure, Wiiatever Source that Makes Release of Large Amounts or Radioactivity in a TAB 27 Short Time Probable, I e a les Deeaeament in onsIto for Example:

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1. LOCA With Fallure of ECCS.
2. LOCA With initially Succ-Walesesart Stribes intabe essful ECCS. Subsequent Structure, Hesulting failure of Ileat Removal in Flow Reductlon Systems with likely i

l TAB 28 ra nure or Containment.

Cositamina ted Irasisportation of 3. Loss of All Onsite and 8ajusy Injused and Contam- Of fsi te Power Concurrent inated Isid ividua l( s ) With Total Loss or

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  • Emergency Feodwater.

to Ot t si te liaspi ta l .

4. Loss of Teedwater and Ruptuse of Pipe- Condenst,te Followed by Oil Pipeline Faifure or E.sergency cuptuse Ilsie Onsite w/ Feedwater System, or w/o F i re TAB 28 5. Reactor Protection System Falls to initiate or a

lus hine Respture Pesstration or Casing Complete a Required Scram, followed by Loss of Core

' Cooling and Make-up Sy.tems Loss of Plant Control lCecurs.

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- Recognition and Classification of Emergency Conditions -

,O Attachment 2 (1 of 1)

Table 2 l

FSAR POSTULATED ACCIDENT CLASSIFICATIONS (Accidents considered worst case)

ACCIDENT EMERGENCY CLASSIFICATION Fuel Handling Accident General Emergency (maximum)

Accidental Release of Waste Liquid Unusual Evelt Rupture of VCT Site Area Erargency Rupture of GST Alert Steam Generator Tube Rupture Alert (w/offsite power)

Steam Generator Tube Rupture Site Area Emergency (w/o offsite power)

Main Steam Line Break in Site Area Emergency Containment Main Steam Line Break Outside Alert Containment Main Feedwater Pipe Rupture Alert Rod cluster Control Assembly Site Area Emergency Ejection Single RCS Pump Locked Rotor Alert Complete Loss of Coolant Flow Unusual Event l Single RCCA Withdrawal at Full Unusual Event i Power Loss of Coolant Accident General Emergency i

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p i Attachment 3 (1 of 5) TAB 1 RADIOACTIVE EFFLUENT General Notes Applicable to all Classifications All emergency conditions based on radiation monitor indications must meet the following basic criteria:

1. The individual radiation monitor readings and alarm setpoints are to be treated as symptoms, rather than definite evidence, that a significant release may have occurred. On receipt of a radiation monitor alarm identified below, or identification that a monitor reading exceeds one of the action levels, an assessment shall be initiated to verify the validity of the reading, and a dose assessment shall be performed. Further actions, such as classification of the emergency condition or the recommendation of protective actions, shall be based on this assessment and not on the existence of an alarm condition.
2. If the assessment identified above cannot be completed within 15 minutes of the alarm, or within 15 minutes from identification of a reading that exceeds one of the action levels below, it shall be considered that the emergency condition indicated does exist and g-") appropriate emergency actions shall be initiated in accordance

( j with the applicable emergency implementing procedures.

In this procedure, the term " site boundary" denotes the demarcation between Duquesne Light BVPS site property and the property of others, and includes all of the land (and water) area defined as the Exclusion Area in the FSAR, as shown in Attachment 4. The " site boundary" is not the fence surrounding the plant protected area. The " unrestricted area" is for EAL purposes, that area beyond the site boundary.

UNUSUAL EVENT

1. CRITERION: Exclusion Area Boundary Dose Rates Resulting From any Unplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceeds 0.5 mrem /hr Beta-Gamma as Measured with Portable Survey Instruments, or as Estimated via Dose Projections.

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EPP/ Implementing Procedure EPP/I-1 -

Recognition and Classification of Emergency Conditions INDICATORS: The following radiation monitor readings correspond to this criterion under adverso meteorological conditions, maximum release flow and " worst-case" release isotope mix.

RM-VS-101B Victoreen 100 cpm above background RM-VS-109 SPING CH 5 50 cpm above background RM-VS-107B Victoreen 200 cpm above background RM-VS-110 SPING CH 5 100 cpm above background RM-GW-109 SPING CH 7 250 cpm above background RM-GW-110LR SA10 35000 cpm above background

2. CRITERION: A Planned Release of Gaseous Radioactivity to the Environment That Exceeds the ODCM-Estab1'shed Alarm Setpoint or Other Conditions Stipulated in the Radioactive Waste Discharge Authorization for That Release.

INDICATORS: The alarm setpoint identified in the discharge permit is exceeded during the release; valve misalignment; greater than calculated ralease volume; etc.

NOTE: A planned release of radioactivity may result in short term exclusion area boundary dose rates that exceed one or more of the emergency action levels specified for Unusual Events or Alert Emergencies. An Ur. usual Event emergency exists only if the planned release exceeds the discharge permit. Dose assessments in this situation are performed via RCM or ODCM procedures rather than EPP/IP's.

3. CRITERTON: Any Unplanned Liquid Radioactivity Release from BVPS-1 in Excess of 10CFR20 MPC Limits for an Isotopic Mix in a Liquid Release to Unrestricted Areas. If an Isotopic _Identi,fication is Not Readily Available, the MPC Limit is 1 E-7 pCi/cc Gross Beta-Gamma and/or 1 E-3 pCi/CC Tritium Following Dilution.

NOTE: In this usage, unplanned releases include unintentional releases via monitored pathways, unmonitored releases, or planned releases that exceed the basis of the applicable discharge permit.

INDICATORS: The alarm setpoint identified in the discharge permit is exceeded during the release with failure of discharge isolation or identification of unmonitored liquid release in excess of 10CFR20 MPC limits.

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. EPP/ Implementing Pr:c duro EPP/I-1 Recognition and Classification of Emergency' Conditions ALERT EMERGENCY

1. CRITERION: Exclusion Area Boundary Dose Rates Resulting From any Unplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceed 2.0 mrem /hr Beta-Gamma as Measured with Portable Survey Instruments, or as Estimated via Dose Projections.

EXCEPTION: Planned routine releases that exceed the ODCM-specified alarm setpoint or otherwise exceed the stipulated conditions of the applicable Radioactive Waste Discharge Authorization are addressed by Criterion 2 of the Unusual Event section of this tab.

INDICATORS: The following radiation monitor readings correspond to this criterion under adverse meteorological conditions, maximum

.elease flow, and " worst-case" release isotope mix.

RM-VS-101B Victoreen 350 cpm above background RM-VS-109 SPING CH 5 250 cpm above background RM-VS-107B Victoreen 700 cpm above background RM-VS-110 SPING CH 5 350 cpm above background RM-GW-109 SPING CH 7 1000 cpm above background RM-GW-109 SPING CH 9 25 cpm above background RM-GW-110LR SA10 1.5ES cpm above background RM-GW-110RR SA9 20 cpm above background

2. CRITERION: Any Unplanned Liquid Radioactivity Release to Unrestricted Areas such that the Drinking Water Radioactivity in Communities Downstream of BVPS Could Exceed 12 Times the EPA Primary Drinking Water Standards.

NOTE: Drinking water activity, as defined here, is measured in the drinking water processing plant intake, with credit taken for near and far field dilution in the river, but with no credit for processing plant filtration.

INDICATORS: Observation of an unplanned or uncontrolled release of liquid radioactivity that is determined to exceed the above criterion by the methods of EPP/IP 2.7.

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EPP/ Implementing Procedure EPP/I-1 ,

Recugnition and Classification of Emergency Conditions G~

SITE AREA EMERGENCY

1. CRITERION: Exclusion Area Boundary Dose Rates Resulting From any Unplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceeds 20.0 mrem /hr Beta-Gamma as Measured with Portable Survey Instruments, or as Estimated via Dose Projections.
2. CRITERION: Exclusion Area Boundary Dose Resulting From any Unplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceeds 170 mrem to any Body Organ (eg: Whole Body, Child Thyroid) for the Actual or Projected Duration of the Release as Estimated via Dose Projections.

INDICATORS: the following radiation monitor readings correspond to these critoria under adverse meteorological conditions, maximum release flow, and " worst-case" release isotope mix.

RM-VS-101B Victoreen 3500 cpm above background RM-VS-109 SPING CH 5 2500 cpm above background RM-VS-111LR SA10 25 cpm above background RM-VS-107B Victoreen 7000 cpm above background RM-VS-110 SPING CH 5 3500 cpm above background RM-VS-112LR SA10 40 cpm above background RM-GW-109 SPING CH 7 10000 cpm above background RM-GW-109 SPING CH 9 250 cpm above background RM-GW-110HR SA9 200 cpm above background RM-RM-219A/B 5.0 R/Hr above background RM-RM-201 45.5 mR/hr above background PROVIDED dose rate is due to radiation streaming through personnel air lock.

GENERAL EMERGENCY

1. CRITERION: Exclusion Area Boundary Whole Body Dose Rates Resulting From any Unplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceed 125 mrem /hr Beta-Gamma as 16 Issue 7, Rev. 7 O

. EPP/ Implementing Proc:dara EPP/I-1 Recognition and Classification of Emergency Conditions .

Measured with Portable Survey Instruments, or as Estimated via Dose Projections.

2. CRITERION: Exclusion Area Boundary Thyroid Dose Commitment Resulting From any Unplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceeds 600 mrem per hour of Inhalation as Determined From Analysis of Air Samples, or as Estimated via Dose Projections.

INDICATORS: The following radiation monitor readings ccrrespond to these criteria under adverse meteorological conditions and

" worst-case" release isotope mix.

RM-VS-101B Victoreen 1.0E5 cpm above background RM-VS-109 SPING CH 5 7.0E4 cpm above background RM-VS-111LR SA10 720 cpm above background  !

RM-VS-107B Victoreen 2.0E5 cpm above background RM-VS-110 SPING CH 5 1.1E5 cpm above background RM-VS-112LR SA10 1100 cpm above background RM-GW-109 SPING CH 7 1.5ES cpm above background RM-GW-109 SPING CH 9 3800 cpm above background RM-GW-110HR SA9 3300 cpm above background i RM-RM-219A/B 200 R/hr above background PROVIDED containment remains intact.

RM-RM-201 1500 mR/hr above background PROVIDED containment remains intact.

3. CRITERION: Exclusion Area Boundary Dose Resulting From any Onplanned or Unmonitored Releases of Gaseous Radioactivity to the Environment Exceeds 1000 mrem Whole Body and/or 5000 mrem Thyroid i for the Actual or Projection Duration of the Release as Estimated via Dose Projections.

17 Issue 7, Rev. 7

EPP/ Implementing Pr:cedura EPP/I-1 .

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  • INDICATORS: The following radiation monitor readings correspond O

to these criteria under adverse meteorological conditions and

" worst-case" release isotope mix.

RM-VS-109 SPING CH 5 5.8E5 cpm above background RM-VS-109 SPING CH 7 55 cpm above background RM-VS-111LR SA10 6000 cpm above background RM-VS-110 SPING CH 5 8.9ES cpm above background i RM-VS-110 SPING CH 7 66 cpm above brckground RM-VS-112LR SA10 9500 cpm above background RM-GW-109 SPING CH 9 3.1E4 cpm above background RM-GW-110HR SA9 2.6E4 cpm above background RM-MS-100A,B,C Any valid reading above background PROVIDED that there -

is other evidence of a significant steam generator tube rupture AND greater than 1.0% FF.

RM-MS-101 Any valid reading above background PROVIDED that there is other evidence of a significant steam generator tube rupture AND greater than 1.0* FF.

RM-RM-219A/B 1600 R/hr above background PROVIDED containment remains intact. -

t RM-RM-201 1.5E4 mR/hr above background j PROVIDED containment remains '

intact.

18 Issue 7, Rev. 7 O

. EPP/ Implementing Procedure EPP/I-1 Recognition and Classification of Emergency Conditions O Attachment 3 (1 of 2) TAB 2 IN-PLANT RADIATION LEVELS UNUSUAL EVENT Not Applicable.

ALERT CRITERION: A verified. uncontrolled event results in an unexpected increase in in-plant direct radiation levels by a factor greater than 1000.

INDICATORS: An increase in an area radiation monitor or monitors to levels 1000 times normal, verified by field surveys to preclude a false declaration because of instrument failure.

Instrument Description RM-1RM-201 Area Radiation Monitors 1000 x normal thru RM-1RM-214 Increased readings on the following instruments may indicate a releano of radioactivity to the plant. They are verified by field measurements:

Ventilation Vent Monitor

  • RM-1VS-101 A/B RM-IVS-102 A/B Auxil. Bldg. Ventilation Exh. Monitor
  • Fuel Bldg. Ventilation Exh. Monftor
  • RM-IVS-103 A/B RM-1VS-104 A/B Containment Purgo Exh. Monitor
  • RM-IVS-105 Leak Collect /.tua Gas Monitor
  • RM-IVS-106 Waste Gas Tank Vault Exh. Monitor
  • RM-1VS-107 A/B RB & SLCRS Release Monitor
  • RM-1RM-215 A/B Containment Monitor
  • RM-1RM-117 A/B Multisample Monitor
  • NOTE:
  • Field measurements with portable survey instruments 1000 x normal.

O 19 Issue 7 Rev. 7

EPP/ Implementing Prrc dura EPP/I-1 ,

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O SITE AREA EMERGENCY CRITERION: Spen Fuel Pool Level Decrease to Below Level of Fuel INDICATORS: The following instruments may indicate that this criterion has been met.

Instrument Descr#ption Alarm FM.

A6-3 Spent Fuel Pool Level Low N/A A11-40 Fuel Pool T/T Drains Rcve liigh N/A Tk Level GENERAL EMERGENCY Refer to of fsite Release EALs.

O 20 Issue 7. Rev. 7 O

EPP/ Implementing Proc:d:ro EPP/I-1 Recognition and Classification

  • p of Emergency Conditions

)

Attachment 3 (1 of 1) TAB 3 RCS TEMPERATURE HI/ LOW UNUSUAL EVENT

1. CRITERION: RCS Temperature < LCO Requirina Station to ao into Mode 3. Hot Standby.

INDICATORS:

Instrument Description Alare EAL TI-RC-412 Loop 1A Tavs N/A <541*F TI-RC 421 Loop 1B Tavs N/A <$41'F TI-RC-432 Loop 1C Tavs N/A <541*F

2. CRITERION: RCS Temperature Greater than Safety Limit as Indicated by BVPS Technical Specifications Flaure 2.1-1 (temperature versus thermal power and PZR pressure).

CRITERION: RCS Temperature Exceeds DNB LCO (> 581*F) with Failure

{,

s, 3.

to Meet Applicable Action Requirement.

ALERT Not Applicable.

SITE AREA EMERGENCY Not Applicable.

GENERAL EMERCENCY Not Applicable.

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  • EPP/Implementirs Precedura EPP/I-1 .,
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N) Attachment 3 (1 of 1) TAB 4 RCS/PZR PRESSURE HI/IDI UNUSUAL EVEfff

1. CRITERION: RCS/PZR Pressure Exceeds Safety Limit (>2735 PSIG)

INDICATORS:

Instrument Description Alarm EAL PI-RC-402A/403A RCS Pressure N/A >2735 A4-9 " Pressure Press High" 2385 N/A A4-19 " Pressure Control Press High" 2310 N/A A4-13 " Pressure Control Press Hi Pwr 2335 N/A Relief Act"

2. CRITERION: RCS/PZR Pressure Less Than Safety Limit as Indicated by BVPS Technical Specifications Figure 2.1-1 (pressure versus thermal power and RCS Temperature).

ALERT Not Applicable.

SlTE EMERGENCY Not Applicable.

GENERAL EMERGENCY Not Applicable.

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LJ Attachment 3 (1 of 2) TAB 5 RCS LEAKAGE ,

NOTE Thers are no instruments which.directly measure RCS leakage. RCS leakage is determined by a leak rati-surveillance procedure. The instruments listed below may be indicators that a significant leak exists.

RM-LRM-215A Containment Particulate Monitor RM-1RM-215B Containment Gas Monitor RM-1RM-201

Containment High Range Area Monitor RM-1RM-202 Containment Low Range Area Monitor TI-RC-463 Pre:ssurizer Power Relief Disch. Temperature TI-RC-465/467/469 Pressurizer Safety Relief Disch. Temperature LI-RC-470 Pressurizer Relief Tank Level LI-RC-460/462 Pressurizer Level -

PI-LM-100. Containment Total Pressure TI-LM-100 Containment Temperature A4-25 " Pressurizer Power Relief Disch. Temp. High" A4-26/27/28 " Pressurizer Safety Relief Disch. Temp. High" Al-58 "Centainment Pressure High"

" Containment Pressure High High"

' ()

O Al-60/66 A4-3 A3-96

" Pressurizer Control Level Low"

" React Flange Leakoff Temp. High" UNUSUAL EVENT

i. CRITERION: Any Non-isolable Pressure Boundary Leakage
2. CRITERION: Any other RCS Leakage (As Indicated Below) Requiring Station Tc Go Into Moda 3 Hot Standby.
a. Unidentified Leakage >1 gpm _
b. Identified Leakage >10 gpm
c. Controlled Leakage >28 gpm at RCS Pressure 2230 i 20 PSIG

' d. Qee also RCS/ Secondary Leakage)

ALERT

1. CRITERION: Leakege Exceeds 50 gpm I

O 25 Issue 7, Rev. 7

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O SITE AREA EMERGENCY

1. CRITERION: Leakage Exceeds Make-up Capability GENERAL EMERGENCY
1. CRITERION: Loss. of Coolant Accident with Failure of ECCS.
2. CRITERION: Loss of Coolant Accident with Subsequent Failure of Heat Removal Systems; Likely Failure of Containment.
3. CRITERION: Loss of Coolant Accident with Fuel Failure and Probable Ir.oinent Failure of Containment.

O 26 Issue 7, Rev. 7 O

EPP/Inplcmenting Procrdura EPP/I-1 Recognition and Classification of Emergency Conditions rx

?v] TAB 6 Attachment 3 (1 of 1)

RCS/ SECONDARY LEAKAGE NOTE There are no instruments which directly measure RCS/ Secondary Leakage. RCS/ Secondary Leakage is determined by a leak rate surveillance procedure. The instruments listed below are indicators that a significant leak exists.

RM-1SV-100 Condenser Air Ejector Vent Monitor RM-1SS-100 Steam Generator Blowdown Sample Monitor RM-1BD-100 Steam Generator Blowdown Tank Discharge Monitor RM-1BD-101 Steam Generator Blowdown Liquid Monitor LI-RC-460/462 Pressurizer Level l A4-3 " Pressurizer Control Level Low" UNUSUAL EVENT

1. CRITERION: RCS/ Secondary Leakage Exceeds 1 gpm Through All Non-isolated S/Gs
2. CRITERION: RCS/ Secondary Leakage Exceeds 500 gpd Through Any One

( S/G D] 3. CRITERION: Steam Generator Activity Exceeds 0.10 pCi/ gram Dose Equivalent I-131 NOTE: See Also TAB 5 (RCS Leakage)

ALERT

1. CRITERION: RCS/ Secondary Leakage Exceeds 200 gpm SITE AREA EMERGENCY
1. CRITERION: RCS/ Secondary Leakage Exceeds 1000 gpm
2. CRITERION: RCS/ Secondary Leakage Exceeds 50 gpm Concurrent With Main Steam Line Break and Indication of Fuel Failure GENERAL EMERGENCY Refer to RCS Leakage /LOCA EALs

/

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U TAB 7 Attachment 3 () of 1)

MA'N STEAM LINE BREAK OR RAPID DEPRESSURIZATION OF SECONDARY SIDE UNUSUAL EVENT Not Applicable ALERT

1. CRITERION: MSL Break Concurrent with 10 gpm RCS/ Secondary Leak INDICATORS:

Annunciator Description A5-13 " Steam 11ne Pressure Low or Pressure Rate High" A7-9 " Loop 1 Steamline Pressure Low" A7-17 " Loop 2 Steamline Pressure Low" A7-25 " Loop 3 Steamline Pressure Low"

2. CRITERION: MSL Break With MSIV Failure SITE AREA EMERGENCY
1. CRITERION: MSL Break Concurrent with 50 gpm RCS/ Secondary Leak with Fuel Failure INDICATORS:

Same annunciators as above

GENERAL EMERGENCY l

Not Applicable 29 Issue 7, Rev. 7 L

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\~>) Attachment 3 (1 of 1) TAB 8 FUEL CLADDING DEGRADATION UNUSUAL EVENT CRITERION: Coolant Specific Activity Exceeds LCO Requiring Station To Go Into Mode 3 Hot Standby.

a. Iodine dose equivalent exceeds LCO (>1.0pCi/ gram steady state).
b. Specific activity exceeds LCO (>100/E pCi/ gram steady state).

INDICATORS:

Instrument Description Alarm RM-1CH-101A/B Reactor Coolant Hi/Hi Letdown Monitors Radiochemistry analyses

/3 ss ALERT CRITERION: RCS I-131 Dose Equivalent Activity Exceeds 300 pCi/ gram INDICATORS: Instruments and analyses as above SITE AREA EMERGENCY CRITERION: Degraded Core-Possible Loss of Coolable Geometry INDICATORS: Evidence of uneven core temperature distribution l

(thermocouples); RCS flow decrease; in addition to i the activity indications above.

GENERAL EMERGENCY CRITERION: Loss of 2 of 3 Fission Product Barriers

! INDICATURS: Fuel cladding failure with LOCA and with potential loss of containment integrity.

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- EPP/Irplementing Proctdura EPP/I-1 Recognition and Classification of Emergency Conditions 7

Attachment 3 (1 of 1) TAB 9-PORV/ SAFETY RELIEF FAILURE UNUSUAL EVENT

1. CRITERION: PORV or Safety Relief Leakage Exceeds Primary Leakage LCO (>10 gpm) Requiring Station To Go Into Mode 3, Hot Standby.

INDICATORS:

Instrument Description TI-RC-463 Pressurizer Relief Line PORV Temperature TI-RC-465/467/469 Pressurizer Safety Relief Line Temperature LT-RC-470 Pressurizer Relief Tank Level A4-36 " Pressurizer Relief Tank Level High" A4-25 " Pressurizer Power Relief Line Disch Temp High" b\ " Pressurizer Safety Relief Line Disch Temp 4

V A4-26/27/28 High" A4-37 " Pressurizer Relief Tank Press High"

2. CRITERION: Safety Valve Fails to Operate at LCO (> 2485 i 10 PSIG).

4 ALERT See LOCA EALs SITE AREA EMERGENCY See LOCA EALs GENERAL EMERGENCY See LOCA EALs rh

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EPP/Irplcmenting Procsdura EPP/I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 10 SIS INITIATION UNUSUAL EVENT CRITERION: Initiation of SIS by Valid Safety Circuit Trip or Necessary Manual Initiation.

INDICATDRS: The following instruments are indications that SIS has initiated:

Instrument Description Al-80 " Safety Injection Pump Auto Start /Stop" ANN-SIA Safety Injection Activation Annunciator System FI-SI-961/962/963 High Head Safety Injection Header Flow (Cold Legs)

FI-SI-940 High Head Safety Injection to RCS Injection Hdrs

. FI-SI-945/946 Low Head SI Pump Disch Header FI-SI-943 Boron Injection Tank Flow ALERT Not Applicable SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY Not Applicable l

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Attachment 3 (1 of 1) TAB 11 RCS PUMP LOCKED ROTOR UNUSUAL EVENT-Not Applicable ALERT CRITERION: RCS Pump Locked Rotor, Resulting in Reduction in RCS Flow.

INDICATORS:

Annunciator Description A3-104 " Reactor Cool Pump 1A Flow Low" A3-112 " Reactor Cool Pump 1B Flow Low" 4 A3-120 " Reactor Cool Pump 1C Flow Low" Reactor Coolant Pump "run" lamps off SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY l Not Applicable

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EPP/ Implementing Precadure EPP/I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 12 CONTAINMENT INTEGRITY UNUSUAL EVEfff CRITERION: Loss of Containment Integrity Requiring Station To Go Into Mode 3, Hot' Standby.

INDICATORS: Containment leak rate exceeds technical specification LCOs, as discovered during surveillance test; or inability to maintain containment pressure.

Instrument Description P1-LM-100 Containment Total Pressure PI-CV-101 Total Pressure Al-58 " Containment Pressure High" Al-35/43 " Containment Air Partial Pressure High/ Low"

/]

%.J ALERT Not Applicable SITE AREA EMERGENCY CRITERION: Containment Total Pressure Greater Than 5 PSIG But Less Than 45 PSIG INDICATORS: Instruments as identified in Unusual Event above.

GENERAL EMERGENCY CRITERION: Failure of Containment Imminent Concurrent with LOCA and Fuel Cladding Damage.

O Q 39 Issue 7, Rev. 7 a 4

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Attachment 3 (1 of 1) TAB 13 LOSS OF ESF'S UNUSUAL EVENT CRITERION: Loss of Engineered Safety Features (ESP) Requiring Shutdown By LCO. (ie, Requiring Station To Go Into Mode 3, Hot Standby.)

The following is a list of operable ESF subsystems necessary to meet LCO:

SIS Accumulators Operable Operable SIS Subsystems Surveillance Boron Injection Tank Operable Operable Containment Quench Spray Subsystems Surveillance Operable Containment Recirculation Spray Subsystems Surveillance Operable Chemical Addition System Surveillance Operable Containment Isolation Valves Surveillance Containment Integrity (See Containment Integrity EALs)

Operable Containment H2 Monitors Surveillance Operable H2 Recombiners Surveillance

- Operable Containment H2 Purge Surveillance ESF Activation System Operable with Proper setpoints/ Surveillance

( response times

)

ALERT Not Applicable SITE AREA EMERGENCY Not Applicable

, GENERAL EMERGENCY t Not Applicable 1

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[U Attachment 3 (1 of 1) TAB 14 PROTECTION SYSTEM FAILURE UNUSUAL EVENT Not Applicable ALERT CRITERION: Reactor Not Subcritical After Valid Trip Signal (s)

SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY CRITERION: Reactor Protection System Fails to Initiate or Complete a Trip, Followed by a Loss of Core Cooling and Make-up Systems, Which Results in Fuel Degradation.

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4 i-EPP/Inplesanting Procedura EPP/I-1 ,

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iI CRITERION: Loss of Plant Control

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LOSS OF INSTRUMENTATION UNUSUAL EVENT CRITERION: Loss of Indicators, Annunciators, or Alarms in Excess of LCO Requiring Station To Go Into Mode 3. Hot Standby.

a. Loss of indicators, annunciators on effluent parameters during release
b. Inoperable ESF Activation System Instrumentation per table 3.3-3 of BVPS Technical Specifications.
c. Inoperable remote indications on Shutdown Panel in excess of

{ minimum channels per table 3.3-9 of BVPS Technical Specifications.

- d. Inoperable RCS Leakage Detection System (2 of 3 channels failed). Includes:

Containment Particulate Radioactivity RM-1RM-215A Containment Gaseous Radioactivity RM-1RM-215B i - Containment Sump Discharge Flow Measurement Local readout System ALERT j CRITERION: Loss of All Annunciators Sustained for >5 Minutes l SITE AREA EMERGENCY i

1. CRITERION: Loss of All Annunciators >15 Minutes with Plant Not l in Cold S/D
2. CRITERION: Uncontrolled Transient Occurs While Annunciators are Inoperative l

GENERAL EMERGENCY I CRITERION: Loss of Plant Control I

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-x Attachment 3 (1 of 1) TAB 17 CONTROL ROOM EVACUATION UNUSUAL EVENT Not Applicable ALERT i

CRITERION: Evacuation of the Control Room is Required or Anticipated and Control of Shutdown Systems has been Established at the Remote Shutdown Panel.

INDICATORS: Control Room evacuation may be required because of high radiation or heavy smoke or fire as indicated by:

Condition - Indicator High Radiation Control Room Area Monitor RM-1RM-213 Heavy Smoke or Fire Observation O

SITE AREA EMERGENCY CRITERION: Evacuation of the Control Room is Required and Control of Shutdown Systems Has Not Been Established at the Remote Shutdown Panel Within 15 Minutes GENERAL EMERGENCY l

CRITERION: Loss of Plant Control i

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.- EPP/ Implementing Proczduro. EPP/I-1

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\j Attachment 3 (1 of 1) TAB 18-T0XIC/ FLAMMABLE GASES UNUSUAL EVENT e CRITERION: Uncontrolled or Potentially Harmful Release of Toxic or Flamnable Gases Onsite or Nearby

~

INDICATORS: Observation by noticeable odor, irritation, samples,-

verbal reports of authenticated accidents resulting in release, or the following annunciators:

Annunciator Description A11-53 Control Room Chlorine Detector A11-86 " Chlorinator Control Unit Area Chlorine Gas Leak" A11-54 " Chlorine Gas Leak" ALERT CRITERION: Toxic or Flammable Gas Enters Facility and Causes ,

Habitability Problems INDICATORS: Same as Unusual Event SITE AREA EMERGENCY CRITERION: Gas Enters Vital Areas and Restricts Access Necessary for Safe Shutdown GENERAL EMERGENCY CRITERION: Loss of Plant Control 51 Issue 7, Rev. 7

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TAB 19

. SECURITY COMPROMISE UNUSUAL EVENT Not Applicable. Action'per BVPS Security Plan.

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ALERT Not Applicable. Action per BVPS Security Plan.

. SITE AREA EMERGENCY CRITERION: Immineat Loss of Physical control of Plant GENERAL EMERGENCY CRITERION: Loss of Physical Control of Plant c.

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LOSS OF AC POWER UNUSUAL EVENT

1. CRITERION: Loss Of On-site AC Power Capability Requiring Station To Go Into Mode 3, Hot Standby.

INDICATORS:

Annunciator Description A8-76 "4160 V Bus 1A Undervoltage" or A8-100 "4160 V Bus ID Undervoltage" or A8-109 "4160 V Emergency Bus 1AE Undervoltage" or A8-117 "4160 V Emergency Bus 1DF Undervoltage" Diesel Generator Inoperative per LCO O

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s 2. CRITERION: Loss of Offsite Power per LCO Requiring Station To Go Into Mode 3, Hot Standby.

i ALERT CRITERION: Temporary Loss of Both Onsite and Offsite AC Power (Diesels Unavailable)

SITE AREA EMERGENCY CRITERION: Loss of Both Onsite (Diesels Unavailable) and Offsite Power for Longer than 15 Minutes GENERAL EMERGENCY CRITERION: Loss of Plant Control a 55 Issue 7, Rev. 7

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  • EPP/Impicssnting Procedura EPP/I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 21 LOSS OF DC POWER UNUSUAL EVENT Not Applicable ALERT CRITERION: Loss of All Onsite DC Power Annunciator Description "DC Dist Pn1 No. 1 Loss of Control DC" (one for each of 7 panels)

SITE AREA EMERGENCY

> CRITERION: Loss of DC Power Sustained for Longer than 15 Minutes O GENERAL EMERGENCY CRITERION: Loss of Plant Control l

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%s TAB 22

Attachment:

3 (1 of 1)

TORNADO Or OTHER HIGH WINDS UNUSUAL EVENT CRITERION: Tornado Warning Received or Tornado Sighted with Probable Effect on Station INDICATORS:

Instrument Description Met. System Wind Speed Indicator 35' Met. Systeer Wind Speed Indicator 150' Met. System Wind Speed Indicator 500' Weather Bureau advisories Personnel sighting i ALERT CRITERION: Tornado Strikes Vital Plant Structures SITE AREA EMERGENCY i

CRITERION: Tornado causes Damage to Safe Shutdown Equipment GENERAL EMERGENCY CRITERION: Loss of Plant Control I

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  • Recognition and Classification l of Emergency Conditions

,ry Attachment 3 (1 of 1) TAB 23 RIVER WATER HI/ LOW UNUSUAL EVENT CRITERION: River Water Level Less Than or in Excess of LCO Requiring Station To Go Into Mode 3, Hot Standby.

INDICATORS: By Observation / Report by Corps of Engineers.

ALERT

, CRITERION: River Water Level Between 705 and 735 MSL (Main Transformer grade elevation is 706 MSL)

SITE AREA EMERGENCY

1. CRITERION: River Water Level Exceeds 735 MSL
2. CRITERION: Flood Causes Damage to Vital Equipment

() GENERAL EMERGENCY CRITERION: Loss of Plant Control l

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Attachment 3 (1 of 1) TAB 24 EARTHQUAKE UNUSUAL EVENT CRITERION: Earthquake Detected by Site Seismic Instrumentation INDICATORS: The Accelerograph Recording System initiates upon detection of a seismic event resulting in 0.01. g acceleration.

" Seismic Accelerograph Operation" annunciator (A11-59) indicates start of system.

ALERT CRITERION: Earthquake Greater Than 0.06 g (OBE) Occurs SITE AREA EMERGENCY CRITERION: Earthquake Greater Than 0.125 g (SSE) Occurs GENERAL EMERGENCY

( j CRITERION: Loss of Plant Control 63 Issue 7 Rev. 7 f

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Attachment 3 (1 of 1) TAB 25 FIRE UNUSUAL EVENT CRITERION: Fire Within Plant Which Is Not Brought Under Control Within 10 Minutes From Start of Firefighting Efforts.

ALERT CRITERION: Fire Which Potentially Affects Safety Systems SITE AREA EMERGENCY CRITERION: Fire Affects Safety Systems Necessary for Shutdown GENERAL EMERGENCY CRITERION: Loss of Plant Control O

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\J' Attachment 3 (1 of 1) TAB 26 EXPLOSION UNUSUAL EVENT CRITERION: Near or Onsite Explosion With Potential Significant Damage To Plant Equipment ALERT CRITERION: Explosion With Known Damage to Facility, Affecting Operation SITE AREA EMERGENCY CRITERION: Explosion Causes Severe Damage to Safe Shutdown Equipment GENERAL EMERGENCY CRITERION: Loss of Plant Control Occurs O

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-U Attachment 3 (1 of 1) TAB 27 AIRCRAFT UNUSUAL EVENT CRITERION: Unusual Aircraft Activity Over Facility or Aircraft Crashes Onsite ALERT CRITERION: Aircraft or Missile Strikes a Station Structure SITE AREA EMERGENCY CRITERION: Aircraft or Missile Crash Affects Vital Structure by Impact or Fire GENERAL EMERGENCY CRITERION: Loss of Plant Control Occurs O

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Attachment 3 (1 of 1) TAB 28 MISCELLANEOUS UNUSUAL EVENT

1. CRITERION: Train Derails Onsite
2. CRITERION: Watercraft Strikes Intake Structure-Results in Flow Reduction INDICATORS: Observation or loss of reactor river water flow indications
3. CRITERION: Personnel Injury Occurs Which Results in the Transportation of Contaminated and Irlured Personnel to an Offsite Hospital.
4. CRITERION: 011 Pip."ine Rupture Observed
5. CRITERION: Turbine Casing Penetrated by Turbine Blading or Other Missiles.

ALERT t

Not Applicable SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY Not Applicable l

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