ML20079P195
| ML20079P195 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/30/1983 |
| From: | Lacey W DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20079P178 | List: |
| References | |
| PROC-831130-01, NUDOCS 8401310122 | |
| Download: ML20079P195 (164) | |
Text
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T REVIEW AND REVISION'0F THE EMERGENCY PREPAREDNESS PLAN
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l Chapter 57 00NTR0LLED Emergency Implementing Procedures c 0 P Y N 0. - & t Volume II I REY. Approval
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I i 9 RECOGNITION AND CLASSIFICATION OF EMERGENCY CONDITIONS
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O _, OSC Meeting Number: 119 Reviewed: / Novaebgr 22, 1983 Approved: MV, M/ '
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L i< Approved: M I ager, Nuclear Safety & Licensing Dept.
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EPP/Impicmenting Procedure EPP/IP I-1 '
; Recognition and Classification of Emergency Condit ions ,
l i O I . TABLE OF CONTENTS A. Purpose B. References C. Responsibilities D. Action Levels / Precautions
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tj E. Procedure r-F. Final Condition G. Atte.nments i 1 e
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a EPP/ Implementing Procedure s Recognition and Classification i of Emergency Conditions A. Purpose 1.0 This procedure describes the immediate actions to be taken to t recognize and classify an emergency condition. 4 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
.2 Implementing Procedures.
q Tj 2.0 Title 10, Code of Federal Regulations Part 50, Appendix E. 2' 3.'0 NUREG-0654/ FEMA-REP-1, " Criteria for Preparedness and Evaluation of Emergency Response Plans and Preparedness in. Support of Nuclear H Power Plants." 4 4,0 Beaver Valley Power Station Operating Manual. C. Responsibility r.s 1.0 The Emergency Director (Shift Supervisor, until properly relieved g by a designated alternate) has the responsibility and authority for implementation of the actions prescribed in this procedure. D. Action Levels /Precaurions
-1.0 Action Level --
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$ 1.1 An off-normal a. vent, corresponding to one of the initiating ] . events-described herein, has occurred.
P 1.2 An action step in a Plant Operating or Emergency Operating
) Procedure refers to this procedure for classification of the 4 indicated plant conditions.
1 [ 2.0. Precautions T 1 2.1 Cortinued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is c appropriately revised as conditions change, or as more y definitive inforation is obtained. 1 a 2.2 Emergency Action Levels (EAL's) are specified in the TABS to o this instruction, in Attachment I to this procedure and in the BVPS Emergency Plan, Table 4.1. (~')
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EPP/I-plem:nting Proc durs EPP/IP I-1
- R: cognition and Classification gf Emergency Conditions
________________________________ g NOTE The EAL's in the TABS to this procedure have precedence over other EAL's should a conflict. between EAL's be noted. g ________________________________ 3 2.3 The EAL's signify the need for implementation of dose assessment measures onsite and/or offsite and assessment of plant status, as applicable. i 2.4 Table 1 (Attachment 1) demonstrates 1.ow an initiating
; ' condition leads directly to the apprcpriate emergency classification, based on the magnitude of the event.
Hcwever, an initiating event and related EAL's need not apply o to all emergency classifications. i
} 2.S Attached to this instruction are data sheets to be used in J
~ classifying emergency conditions. Each data sheet identifies the initiating condition (ie., RCS Pressure Hi/ Low) and the respective emergency action levels for each classification.
- j 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 assess and classify ths condition.
1 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. 1 E. Procedure _ T 1.0 Verify b 1.1 Verify the initial indication (alarm, surveillance report, h"- etc.) by comparison to redundant instrument channels, comparison to other related plant parameters, physical observations and field measurements.
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- j 2.0 Classification 2.1 Locate the appropriate data sheet in Attachment 3. Data sheets are arranged by initiating event (s) either a single 7 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.
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I f i , . EPP/Impicstnting Procsdure EPP/IP I-l Recognition and Classification of Emergency Conditions 3( ) 2.3 Declare the appropriate emergency condition. additional actions in accordance with the Emergency Operating Perform Procedures and the appropriate EPP/ Instructions: 2.3.1 EPP/I-2 Unusual Event 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 l Title 10, Code 'of Federal Regulations Part 50, Appendix E, states, "A licenses shall have the capability to notify responsible State and local governmental agencies within 15 minutes after declaring an. emergency". 3.0 Abnormal Conditions - 2.1 If the abnormal condition does not constitute an Unusual Event or greater, continue correctivo actions in accordance with the BVPS Operating Manual and resume normal operations.
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a 3.2 If the event is not classified as an Unusual Event, but is reportable to the NRC pursuant to OM Chapter 48, Sectica 9.D.
] DLC PID 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.
n j 3.3 Should station management deem it necessary, a edurtesy call
, call should be made to the' primary offsite agencies (BCEMA, PEMA, CCDSA and HCOES) on a timely basis consistent with j normal working hours.
! a 3.4 Assessment actions shall be continued, and if necessary, the emergency classification escalated (or downgraded) as more definitive information becomes available of if plant 0 conditions change significantly. i l F. Final Conditions ld 9 1.0 The initiating conditions have been de-classified to non-emergency y status and any tensination' requirements per BVPS/IP's have been y satisfied. L. M
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EPP/Impiccinting Proctdurs EPP/IP I-1 l Recognition and Classification of Emergency Conditions G. Attachnents O j
. 1.0 Table 1, Action Level Criteria for Classification of Emergency Conditions.
l 2.0 Table 2, FSAR Postulated Accident Classifications. 3.0 Data Sheets for Classification of Emergency Conditions. t .I j
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Recognition and Classification of Emergency Conditions , Attachment 1 (1 of4) .
; TABLE s AC'110N LEVEL CRTTERIA POR Cl.ASSIFICATION OF FMRROENCY CONDrl10HS IHrt1ATTHO CONDrt10N UN tlBUAL EVENT ALERT SrTE FMEROENCY O ENERAL ist RRO ENCY Off-norma! Events Which Events which Indicate an Events Which involve Actual Events Which Involve Actual Could Indicate a Potential Actual Degradation of the or Likely Major Failures of or Imminent substantial Degradation of the Lev.el of Level of Safety of the Plant Plant Functions Needed for Core Degradation or mett-Safety of the Plant Prctection of the Public ing with Potential for Ims of Containment integrity Radioactive Effivent Rc!ce.sc E=cceds Tech Spec Relepae Exceech inn Times llelease Corresponds to Release Corresponds to Limiti Unplanned or Un- Instantaneous Tech Spec >20 mrem /hr at Site >600 mrem /hr to Whole Lpplicable te Any Release Point (s) monitored Releases suspect- I imiti Unplanned or Un- Boundary Body at Site Boundary t nd Resulting from Any Initiating ed of exceeding Tech Spec monitored Releases Sus- -or- -or-Event Limit pected of Exceeding 100 Off-site Dose Due to Event Off-site Dose Due to Event tinics Tech Spec Limit is Projected to Es med is Projected to Execed 5 170 mrem to Whole Booy cr rerw to Whole Body or Child Thyroid 25 rem Io the Child 'Ihyroid TAB 1 R: lease ce Emma of Control of Fuct flandlir.g Accident Major Damage to Spent Fuel Radoactive Materlat Within Resulthw ' in Release of Due to Fuel llandlicg Acci-the Plant Radioactivity to Occupied dent
- Areas Such 'Itat iho Direct -or-Radiation Levels in the Uncontrolled Decrease in Areas increase by a Factor Fuel Por.1 ital. r to Helow M of >1000 Levelof Fuel
-or-Nl6 Other Verified, Uncontrol-led Events Which Result in y
TAB 2 an unexpected Increase of
;p In-Plant Direct Radiation 1.evels by a Pactor of >1000 -
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EPP/ Implementing Procedure EPP/IP I-l Recognition and Classification ( of Emergency Conditions TADLE 1 ACTION I.EVEl. CRITERIA FOtt CI.Afh CATION OF EMEROENCY CONDmONS Attachment I (2 of 4) AI.ERT SrtBEMEROENCY OENER AI, EM EROENCY I INITIATIMO CONDmON UNUSUAL EVENT Reactor Coolant Syalem OtCS) !!elow Tech Spec 1,lmiting Less of 2 of 3 Fission Pro-Twparature Imw Conditions for Operation duct !!arriers With a Polen-UEO) tial loss of Third Darrier TAD 3 Applicable to Any initiatg
*~ Event that May 1.end to ilus ECS Freeswe Illgh Execeds LCO Limit LWltion.
TAB 4 ,,,, Exceeds LCO Exceeds 50 gpm '. Exceeds Make-up Capacity EC8/Contalement teak Any Initiating Events, from tan & Whatever Source that Makes
>200 gpm >50 gpm w/ MSL Ilreak Itelease of f.arge Amounts RC8/Beoondary IAsk Exceeds LCO of Itadioactivity in a Simrt TAnn
-or- w/indAcation of Fuel Failure
>to gpm w/ MSL Dreak -or- Time Probable, For Example:
-or- >1000 gpm Main Steam IJae Break MSL lireak w/ MSIV Failure 1,0CA With Failure of 1.
TAB 7 ECCS I Degraded Core-Possible Feel Cladding Degradation RCS Activity Exceeda LCO RCS I Activity >300
-or- pCl/gm Imss of Coolable Geometry 2. LOCA With Inlilally Reactor Coolant Monitor Successful ECCS. Sub-Alarm, or anedyses >t pCl/ acquent Failurer of flest TAB 8 Removal Systems With gm, Steady State I.ikely Failure of Con-tainment CCS Safety or Relief Valve Leak Exceeds LCO er Valve Fallure hoperable 3. toss of All Ornite and TAB 9 Offsite Power Concur-rent With Total loss of ECS Tesnperstaure liigh Exceeds ICO Emergency Feedwater TAD 3
- 4. Ioss of Feedwater and l ECS Pressure Imw Delow LCO Condensate Followed
! TAB 4 by failure of Emer-gency Feedwater Idtletion of BCCS Valid Safety Circuit Trip or ystem I! Necessary Manual Initiation N 5. Reactor Protection RCS Pump Failure : Impeller Selzure , r omp e c a Re ir TAB 11 Scram. Followed by t less of Contalmusent Integrity Requiring Shutdown by LCO ' Containment Pressure >5 & a d Ma e-up Sys e s
<45 psig -
e TAB 12 ,, _ Issue 7 Rev. 2 less of ~
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Occurs
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EPP/ Implementing Procedure , EPP/IP I-1 Recognition and Classification of Emergency Ccnditions TABLE w 1 ACTION LEVEL CRITEltIA FOR CLASSn CATION OF EMERGENCY CONDITIONS Attachment 1 (3 of 4) INff1ATTNG CONDf710N UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY lese ei FJgip*ered Safety or Fire Requir!ng Sheldown by LCO Loss of 2 of 3 Fission Pro-Protection Feetsres : duet Harriers With a Polen-tial Loss of Third Barrier TAD 13 JA plicable to Any initiating Falters of Resetoe Protection Reactor Not Suberitical Event that May Lead to this Systene to todtlate ce Complete : af ter Valid Scram Signalis) : ' Conoition. o saaem TAB 14 -or-tems of Flant Control /Befety Loss of Capability to Loss of Capability to Any initiating Events, from Systeses : Achieve Cold Shutdown Achieve flot Shutdown Whateven f amee that Makes TAR 15 Helease of Large Amounts of Radioactivity in a Short Imse of Endlestors, Amiunciators Lom on Process or Effluent Los of All Alarms Loss of All Alarms >15 min Time Probable, For Example ce Alarma Parnmeters, Requiring Shut- (Annunciators) Sustained for with Plant Not in Cold S/D down by LCO 5 mins -or-Plant Transient Occurs 1. LOCA With Failure of TAD 16 While All Alarms are Lost ECCS
- 2. LOCA With Initially Control Room Evacuation Required or As.ticipated. Required. Shutdown System Successful ECCS. Sub-Control of Shutdown Control at Remote Shut- sequent Failure of Heat Systems Established at down Panel Not Established !!cmoval Systems With Remote Shutdown Panel Within 15 min Likely Failure of Cos.-
TAD 17 .tainment Tosie se Flammable Osses Hear-by or On-site IIelease! Enters Faellity. Potential Enters Vital Areas and 3. 14ss of All Ornite and Pctentially llarmful liabitability Problems flestricts Necessary Access Offsite Power Concur-MD 18 rent With Total Loss of Emergency Feedwater Security Compromise in Accortlance with Security Plans Imminent less of Physien! , Control of Plant 4. Loss of Feedwater and TAD 19 Condensate Followed by Failure of Em er-team of Orndte AC Power 14ss of Capability gency Feedwater y TAD 20 Temporary loss of Both less of Doth F2cceds System Upon Occurence 1 minutes 5. Reactor Protection h Imns of All Off-site Power a 'PA R 90 System Falls to initiate or Complete a Required Imse of AD OrHite DC Power . Upon Occurence loss of Vital DC Power For Scram. Followed by More than 15 min Loss of Core Cooling
. TAD 21 and Make-up Systems v ,
Tornado Warning. Probable Effcci on Strikes Vital Plant Wue- Wimh in Excess of Design -or-Sinuon tures i.evels Ion of P Control y O TAB 22 Issue 7 Rev. 4 Occurs
EPP/ Implementing Procedure EPP/IP l-1 Recognition and Classificatior. of Emergency Conditions TATILE .1 ACTION f.EVEI,CRITE!!IA FOlt CI.AR CATION OF EMEROENCY CONDITIONS Attachment I (4 af 4) UNUStIAL EVENT ALEllT SITH EAtEHOENCY OENER AI. EM ERGENCY INff1ATINO CONDff10N Flood or Imr Water Flood (705 feet M S I., Flood >705 feet MSL Flood >735 feet MSI. Ioss of 2 of 3 Fission Pro-Ilequiring S/D. Iow Water -or- duct flarriers With a Poten-
<l.C O Damage to Yllel Equipment flal I.oss of Third !!arrier TAB 23 Applicable to Any Initiating I vont that May I. cad to this Detected on Site Scismic Greater than ODE Occurs Greater than SSE Occurs Condition.
Earthganke Instrumentation
-or-TAB 24 Within Plant, Not Urader Potentially Affecting Safety Affecting Safety Systems Any Initiating Events from Fire Whatever Source that Makes Control in 10 Minutes Af ter Syst ems. Itequired for Shutdown Fire Fighting Commenced !!clease of Large Amounts TAB 25 of Radionetivity in a Stort Time Probable, For Example Explanton Near or O n-elle Explosion Known Damage to Facility, Severe Damage to Safe Potential Significant Dam- Af fecting Operation Shutdown Equipment age 1.' l.OCA With Failure of TAB 26 ECCS Alreraft Unusual Activity Over Aircraft or Missile From Crash Affects Vital Strue- 2. LOCA With Initially Facility Whatever Source Strikes and tures by impact or Fire Successful ECCS. Sub-
-or- Significantly Degrades a sequent Fallare of Ilent Aircraf t Crashes Ornite Station Safety Structure itemoval Systems With I.tkely Failure of Con-TAB 27 tainment TYalJ Derailment in Orelle Aress 3. toss of All Onsite and Offsite Power Concur-TAB 28 .
rent With Total Loss of Catercraft Strikes Intake Structure, Emergency Feedwater TAB 28 flesulting In Flow Reduction
- 4. loss of Fcedwater and Condensa te Followed Transportation of injured by Failure of Emer-Cont:m!aaled lepary and Contaminated Individ- gency Feedwater unt(s) to Offsite Ilospital System TAB 28
- 5. Reactor Protection Accident at SAPS itcquires Protective Actions System Falls to initiate at ilVPS or Complete a flequired gg gg Scram, Followed by t less of Core Cocling Rupture of Pipeline Onsite and Make-up Systems Oil Pipellae Rupture TAB 28 w/ or w/o Fire -or- -
Loss of Plant Control Issue 7 Rev. 2 Occurs 'hrtles Falld h TAB 28 Penetration of Casing
I* EPP/Impismanting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions
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Attachment 2 (1 of 1) Table 2 ; FSAR POSTULATED ACCIDENT CLASSIFICATIONS 4 ACCIDENT EMERGENCY CLASSIFICATION Fuel Handling Accident General Emergency (maximum) Accidental Release of Waste Liquid Unusual Event [ Rupture of VCT Site Emergency i Rupture of GST Alert
- Steam Generator Tube Rupture Alert I (w/offsite power)
Steam Generator Tube Rupture Site Emergency (w/o offsite power) j Main Steam Line Break in Site Emergency a j Containment Main Steam Line Break Outside Alert Containment Main Feedwater Pipe Rupture Alert Rod Cluster Control Assembly Site Emergency Ejection if Single RCS Pump Locked Rotor Alert Complete Loss of Coolant Flow Unusual Event Single RCCA Withdrawal at Full Unusual Event Power r i Loss of Coolant Accident General Emergency 9 Issue 7 Rev.-2 l
EPP/ Implementing Proceduro EPP/IP I-1 Recognition and Classification of Emergency Conditions O INTESTIONALLY BL\NK 9 I i l i t 4 i i i 10 Issue 7 Rev. 2
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( , . EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions ,, f% Q Attachment 3 (1 of 4) TAB 1 RADIOACTIVE EFFLUENT NOTE For monitored effluent paths with automatic discharge isolation (or diversion *), the occurrence of a monitor alarm does not constitute a release in excess of Technical Specification--PROVIDED--the automatic valve properly isolated or diverted the effluent release path. Appropriate samples should be taken to verify the monitor reading. Tf the discharge does not isolate, consider ths release to be " unplanned" and take appropriate action as specified below. t
*eg; main condenser air ejector diverted from atmosphere release point to containment.
UNUSUAL EVENT i 1. Monitored Release Exceeds Technical Specification
, A radioactivity release in excess of MPC limits (10 CFR 20 Appendix B) for an isotopic mix in a liquid release; or in excess of the Environmental Technical Specification (ETS 2.4) for a gaseous release as indicated by one of thfe following effluent
) monitors in a valid alarm and the release path is not isolated:
Instrument Description EAL Setpoint (Hi-Hi Alarm) RW-1LV-104 Liquid Waste Effluent Monitor 2.6 E4 CPM RW-ILW-116 Liquid Waste Contaminated Drains 1.2 E5 CPM RM-1GW-108A Gaseous Waste, Particulate 1.0 E6 CPM i j RM-1GW-108B Gaseous Waste, Gas 1.0 E6 CPM l RM-LVS-101A Ventilation Vent, Particulate 1.0 E6 CPM l RM-IVS-101B Ventilation Vent, Gas 3.2 E3 CPM I j RM-IVS-107A RB & SLCRS Release, Particulate 5.0 E5 CPM
- } RM-IVS-107B RB & SLCRS Release, Gas 3.1 E4 CPM l
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EPP/Implem:nting Procedure EPP/IP I-l Recognition and Classification of Emergency Conditions (2 of 4) NOTE The specific t!PC limit for a given batch release (liquid or gasecus) is based on prior scopling results which are documented on the Radioactive Waste Discharge Authorization (RWDA). If a Hi-Hi alarm occurs on ene of the inst.ruments listed above, a sample should be taken of the affected effluent path (tank or monitor sample, as applicable) and the results compared to the pre-discharge sample results. If the sample results differ significantly, a new RWDA shall be calculated. If the sum of the ladividual ?!PC fractions exceed 1.0, the release exceeded technical specifications. Similar assessment can be performed for continuous release pathways using the last periodic sample results.
- 2. Unmonitored Release Exceed Technical Specifications Any liquid or gaseous radioactivity release via an unmonitored path which is estimated or suspected to exceed ?!PC limits (10 CFR 20 Appendix B) following dilution. If an isotopic breakdown is not available, ths MPC limit is 1 E-7 pCi/cc gross beta gamma and/or 1 E-3 pCi/cc tritium following dilution (= river activity).
ALERT
- 1. Monitored Release-Liquid A liquid release estimated or suspected to excced 12 times the EPA Primary Drinking Water Standards-attributable to the Station.
9 (See EPP/IP-2.7 " Liquid Release Determination". (12 times EPA is the limit established by DER /BRP in the " Plan f'or Naclear Generating Station Incidents") .
- 2. Monitored Relense-Gaseous Exceeds 100 times Technical Specifications A gaseous release estimated or suspected to exceed 100 times the gaseous release r.echnical specification (ETS 2.4) as indicated by one of the following effluent monitors exceeding the EAL setpoints listed below a_nd n the release path has not been isolated:
Monitor # ' Estimated Flow EAL Setpoint RM-VS-111 (Lo Range) 1000 CFM 7.4 E3 RM-VS-112 (Lo Range) 42,500 CFM 3.8 E4 RM-GW-110 (Hi Range) 60,000 CFM 8.6 E3 12 Issue 7 Rev. 2
EPP/Implemtn' ting Procedure' I 7
.. EPP/IP I-l Recognitlon and Classification ~'
of Emerg6ncy Conditions
-t Attachment 3 (3 of 4)
If actual flow is different than estimated flow, calculate a new EAL as follows: Actual Flow s X EAL = New EAL Estimated Flow Setpoint
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The setpoints correspond to 100 times the gaseous release limit for a conservative radionuclide mix. These monitors are installed in parallel to the identified monitors and are read out locally on the SPRING-4 Control Room Terminal (Cr-1), and locally, if noces:ary.
- 3. Unolanned or Unmonitored Release
'Any liquid radioactivity release via an unmonitored path estimated i or calculated to' result in. water treatment plant intake activity in excess 12 times 'the EPA Drinking Water Standards.
I Any airbo'rne activity release via an unmonitored path; or an 4 unplanned release via a monitored patt; calculated or estimated to 100 times technical specification (Instantaneous) limits. j . SITE AREA EMERGENCY , 1. (A} m Airborne Release Corresponds to:
- a. 20 mreb/ hour at the site boundary (OR the protected area s
security fence) as determined by field radiation surveys or dose projection as indicated by one of effluent monitors
. exceeding the 3etpoints listed below and the release path has ; not besn iso' lated: ; Monitor _ Estimated Flow EAL Setpoint ; RM-GW' -
109 (H1' Range)~ 1,000 CFM 18,000 CPM T RM-VS-110 (Mid Range) 42,000 CFM ~350 CPM RM-VS-109 (Mid Range) 60,000 CFM 275 CPM
, R{f-RM-219A/B N/A 30 R/Hr i If the actual ' flow is different than the estimated flow, calculate a new EAL as follows: ' i Actual Flow' EAL Setpoint = New EAL
.s Estimated Flow s s
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EPP/ Implementing Procrdur EPP/IP I-l Recognition and Classification of Emergency Conditions Attachment 3 (4 of 4) OR
- b. Offsite dose due to the event is projected to exceed 170 mrem to the whole body or the child thyroid.
NOTE Since dose projections commence whenever a release exceeds the technical specification limit, a prolonged, low level release may result in the declaration of a Site Area Emergency withcut exceeding the 20 mrem / hour criterion. GENERAL EMERGENCY
- 1. Airborne Release Corresponds to:
- a. >600 mrem /hr at the site boundary (NOT the protected area security fence) as determined by field radiation surveys or dose projection as indicated by one of the following effluent monitors in a valid (High-High) alarm and the release path is not isolated.
l Monitor Estimated Flow EAL Setpoint RM-GW-109 (Hi Range) 1,000 CFM 18,030 CPM BKG j RM-VS-110 (Mid Range) 42,500 CFM 350 CPM BKG RM-VS-109 (Mid Range) 60,000 CFM 275 CPM BKG RM-MS-100 N/A 50 C?M BKG MS-101 650C?M BKG EAL Setpoint RM-MS-100 50 CPM BKG l MS-101 650 CFM BKG l If the actual flow is different than the estimated flow, calculate a new EAL as follows:
} Actual Flow EAL Setpoint = New 2AL Estimated Flow i
14 Issue 7 Rev. 2
EPP/Implzmsnting Proceduro EPP/IP I-1 Recognition and Classification of Emergency Conditions m k Attachment 3 (1 of 2) TAB 2 IN-PLANT RADIATION LEVELS UNUSUAL EVENT Not Applicable. ALERT
- 1. Unexpected Increase in In-Plant Radioactivity Levels
- a. Fuel Handling Accident results in release of radioactivity to occupied areas such that direct radiation levels in the area increase by a factor of 1000 or higher.
- b. A verified, uncontrolled even results in an unexpected
] increase in in plant direct radiation levels by a factor
- greater than 1000; as indicated by:
Instrument Description _EAL RM-1RM-201 Area Radiation Monitors 1000 x normal thru RM-1RM-214 Ch
.;'"') Increased readings on the following instruments indicate a release of radioactivity to the plant. They are verified by field measurements:
RM-IVS-101 A/B Ventilation Vent Monitor
- RM-1VS-102 A/B Auxil. Bldg. Ventilation Exch. Monitor
- RM-IVS-103 A/B Fuel Bldg. Ventilation Exh. Monitor
- RM-IVS-104 A/B Containment Purge Exh. Monitor
- I RM-1VS-105 Leak Collect Area Gas Monitor
- j RM-IVS-106 Waste Gas Tank Vault Exh. Monitor
- RM-IVS-107 A/B RB & SLCRS Release Monitor
- f RM-1RM-215 A/B Containment Monitor *
, RM-1RM-117 A/B Multisample Monitor
- NOTE:
- Field measurements with portable survey instruments 1000 x normal.
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EPP/Impitm:nting Procedura EPP/IP I-l Recognition and Classification of Emergency Conditions Attachment 3 (2 of 2) SITE AREA EMERGENCY
- 1. Spent Fuel Damage Major damage to spent fuel due to fuel handling accident; tosults in offsite doses in excess of 170 mrem.
Instrument Description Alarm 1:AL Area and ventilation monitors identified above N/A N/A (Alert) Field measurements with portable survey N/A 20 mrem /hr* instruments
*at site boundary.
- 2. Spent Fuel Pool' Level Decrease Uncontrolled decrease in fuel pool water to below level of fuel.
Instrument Description Alarm EAL A6-3 Spent Fuel Pool Level Low N/A A11-40 Fuel Pool T/T Drains Revr High N/A Tk Level GENERAL EMERGENCY Refer to offsite Release EALs. l 2 16 Issue 7 Rev. 2
B EPP/Implemanting Procedure EPP/IP I-1 i Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 3 RCS TEMPERATURE HI/ LOW f 4 UNUSUAL EVENT { 1. RCS Temperature <LCO Instrument Description Alarm EAL 4 TI-RC-412 Loop 1A Tavg N/A >541*F TI-RC-421 Loop 1B Tavg N/A >541*F 1 TI-RC-432 Loop IC Tavg N/A >541*F i 2. RCS Temperature Greater Than Safety Limit Operation outside of acceptable region on Figure 2.1-1 of BVPS Technical Specification (temperature versus thermal power and PZR pressure).
- 3. RCS Temperature Exceeds DNB LCO (>581*F)
ALERT j O Not Applicable. i l SITE AREA EMERGENCY { Not Applicable. )' GENERAL EMERGENCY j Not Applicable. 1 i
- 1 i !
fI I
' i k
i Ii 17 Issue 7 Rev. 2 i 5
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions - O INTENTIONALLY BLANK O i 1 lf l 18 Issue 7 Rev. 2
EPP/Impicmanting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 4 RCS/PZR PRESSURE HI/ LOW UNUSUAL EVENT
- 1. RCS/PZR Pressure Exceeds Safety Limit (>2735 PSIG)
Instrument Description Alarm EAL PI-RC-402A/403A RCS Pressure N/A >2735
- A4-9 " Pressure Press High" 2385 N/A i A4-19 " Pressure Control Press High" 2310 N/A A4-13 " Pressure Centrol Press Hi Pwr 2335 N/A Relief Act"
- 2. RCS/PZR Pressure Less Than Safety Limit .
Operation outside of acceptable region on Figure 2.1-1 of BVPS Technical Specifications (Pressure versus thermal power and RCS temperature). ALERT ], . . Not Applicable. SITE EMERGENCY Not Applicable. GENERAL EMERGENCY Not Applicable. i 4 9 i J4 i O
\ ,) '
19 Issue 7 Rev. 2 ( l
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions INTENTIONALLY BIANI ( 4 20 Issue 7 Rev. 2
EPP/Implemanting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 2) TAB 5 RCS LEAKAGE NOTE
; There are no instruments which directly measure RCS leakage. RCS Leakage is determined by a leak rate surveillance procedure. The j 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 Low Range Area Monitor RM-1RM-202 Containment High Range Area Monitor TI-RC-463 Pressurizer Power Relief Disch. Temperature TI-RC-465/467/469 Pressurizer Safety Relief Disch. Terperture l l 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 Re1ief Disch. Temp. High" Al-58 " Containment Pressure High" Al-60/66 " Containment Pressure High High" rs A4-3 " Pressurizer Control Level Low" (,) f A3-96 " React Flange Leakoff Temp. High" UNUSUAL EVENT
- 1. Any Non-isolable Pressure Boundary Leakage
- 2. Unidentified Leakage >l gpm
- 3. Identified Leakage >10 gpm
- 4. Controlled Leakage >28 gpm at RCS Pressure 2230 i 20 PSIG i
- 5. (See also RCS/ Secondary Leakage) 1 ALERT
- 1. Leakage Exceeds 50 gpm SITE AREA EMERGENCY
- 1. Leakage Exceeds Make-up Capability l I l l l l
(~' l 21 Issue 7 Rev. 2 i l
EPP/Implem:nting Procedura EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (2 of 2) GENERAL EMERGENCY
- 1. LOCA
- a. Loss of Coolant Accident with failure of ECCS.
- b. Loss of Coolant Accident with subsequent failure of heat removal systems; likely failure of containment.
- c. Loss of Coolant Accident with fuel failure and probable imminent failure of containment.
O i i 22 I.ssue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O (j Attachment 3 (1 of 1) TAB 6 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 LI-RC-460/462 Pressurizer Level A4-3 "Pressuriz6r Control Level Low" UNUSUAL EVENT
- 1. ECS/ Secondary Leakage Exceeds 1 gpm Through all Non-isolated S/Gs
- 2. RCS/Seccadary Leakage Exceeds 500 gpd Through Any One S/G
- 3. Steam Generator Activity Exceeds 0.10 pCi/ gram Dose Equivalent I-131 4.
~
(see also RCS Leakage) ALERT
- 1. RCS/ Secondary Leakage Exceeds 200 gpm SITE AREA EMERGENCY
- 1. RCS/ Secondary Leakage Exceeds 1000 gpm
- 2. 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 l
t i 3 (O) 23 Issue 7 Rev. 2 - I l l
= .
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions
'i INTENTIONALLY BLANK 9
i l i i I 24 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 7 MAIN STEAM LINE BREAK UNUSUAL EVENT Not Applicable ALERT
- 1. MSL Break Concurrent with 10 gpm RCS/ Secondary Leak Annunciator Description
, , AS-13 "Steamline Pressure Low or Pressure Rate High" l A7-9 " Loop 1 Stesmline Pressure Low" i A7-17 " Loop 2 Steamline Pressure Low" ! A7-25 " Loop 3 Steamline Pressure Low" l
- 2. MSL Break With MSIV Failure
{ SITE AREA EMERGENCY l
- 1. MSL Break Concurrent with 50 gpm RCS/ Secondary Leak with Fuel Failure Same annunciators as above GENERAL EMERGENCY I.
! Not Applicable t
i i 1 i 25 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classific ation of Emergency Conditions , O i s i IhTENTIONALLY SLANK O r i e i eV. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions
'e Attachment 3 (1 of 1) TAB 8 FUEL CLADDING DEGRADATION UNUSUAL EVENT
- 1. I-131 Dose Equivalent Exceeds LCO (>1.0 uCi/ gram) (Steady State)
Instrument Description Alarm RM-1CH-101A/B Reactor Coolant Letdown Hi/Hi Monitors t l Radiochemistry analyses l 2. Specific Activity Exceeds LCO (>100/E pCi/ gram) (Steady State) i Instruments / analyses as above. ALERT l
- 1. RCS I-131 Dose Equivalent Activity Exceeds 300 uCi/ gram Instruments and Analyses as above.
SITE AREA EMERGENCY
- 1. Degraded Core-Possible Loss of Coolabie Geometry Evidence is uneven core temperature distribution (thermocouples); RCS flow decrease; in addition to the i activity indications above.
1 GENERAL EMERGENCY
, 1. Loss of 2 of 3 Fission Product Barriers 6
l Fuel cladding failure with LOCA and with potential loss of I containment integrity. I 1 < l 27 Issue 7 Rev. 2 L
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions ' O I INTENTIONALLY BLANK O 4 o 1 I e 2e 1 s.e , ee. 2 0-
EPP/Implemtnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 9 PORV/ SAFETY RELIEF FAILURE UNUSUAL EVENT
- 1. PORV or Safety Relief Valve Leakage PORV or safety relief leakage exceeds primary leakage LCO (>10 gpm). Indicacions of leakage are:
! 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 i . j A4-36 " Pressurizer Relief Tank Level High" i A4-25 " Pressurizer Power Relief Line Disch Temp High" A4-26/27/28 " Pressurizer Safety Relief Line Disch Temp High" A4-37 " Pressurizer Relief Tank Press High" 4
- 2. Safety Relief Valve Fails to Operate I
j Safety valve fails to operate at LCO (> 2485 10 PSIG). I ] 1
, ALERT l
l See LOCA EALs SITE AREA EMERGENCY l
- i 1
See LOCA EALs ! ! GENERAL EMERGENCY i< See LOCA EALs i! 4 i i 1 29 Issue 7 Rev. 2 4 5 l
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions e i 1 i i INTENTIONA!JY BLANK e i I d l i
, l 4
30 Issue 7 Rev. 2 1
. .. . ~. . _
, e
- EPP/Implemanting Procedure EPP/IP I-l Recognition and Classification of' Emergency Conditions P
4 Attachment 3 (1 of'1) TAB 10 SIS INITIATION I UNUSUAL EVENT
- 1. Initiation of SIS Valid safety circuit trip or necessary manual initiation. 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 4
FI-SI-961/962/963 High Head Safety Injection Haader Flow (Cold Legs)
}'
VI-SI-940 High Head Safety Injection to RCS }!' Injection Hdrs 1 FI-SI 945/946 Low Head SI Fump Disch Header
,D) a, FI-SI-943 Boron Injection Tank Flow ALERT Not Applicable SITT AREA EMFRGENCY Not Applicable GENERAL EMERGENCY Not Applicable f
i ~1 f 5 31 Issue 7 Rev. 2 l
EPP/ Implementing Procedure EPP/IP I-l Recognition and Classification of Emergency Conditions O ' INTENTIONALLY BLANK O l l 32 Issue 7 Rev. 2 l l
l EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions
, Attachment 3 (1 of 1) TAB 11 i
RCS PUMP LOCKED ROTOR it UNUSUAL EVENT
- Not Applicable ALERT 4
- 1. RCS Pump Locked Rotor i
RCS pump locked rotor, resulting in reduction in RCS Flow. fl Annunciator Description A3-104 " Reactor Cool Pump 1A Flow Low" 3 A3-112 ' Reactor Cool Pump 1B Flow Low" 1 A3-120 " Reactor Cool Pump IC Flow Low" Reactor Coolant Pump "run" lamps off
- SITE AREA EMERGENCY Not Applicable t GENERAL EMERGENCY Not Applicable i,
i r i i i , i i 4 i 1 i , 33 Issue 7 Rev. 2 i e
. . _ . - _ . - - _ . . - - - . _ . . ~ . _ . . . . - . _ _ . - . . _ _ . . . - . - _ _ . . . - . , .
EPP/ Implementing Proc ' dure EPP/IP I-1 Recognition and Classification of Emergency Conditions F INIINTIONALLY BLANK O l l l 34 Issue 7 Rev. 2 9
.. _ . - = . .
1 }- EPP/Implemanting Procedure EPP/IP I-1 Recognition and Classification
- ; of Emergency Conditions
. Attachment 3 (1 of 1) TAB 12 CONTAINMENT INTEGRITY UNUSUAL EVENT
- 1. Loss of Containment Integrity Containment leak rate exceeds technicalspecificationLCbs,as discovered during surveillance test; or inability to maintain containment pressure.
Instrument Description l Pl-LM-100 Containment Total Pressure I
-{ PI-CV-101 Total Pressure "l 1.
Al-58 " Containment Pressure High" t ;
,' Al-35/43 " Containment Air Partial Pressure High/ Low" ALERT i
Not Applicable i ~ q SITE AREA EMERGENCY
- 1. High Containment Pressure Containment total pressure greater than 5 PSIG but less than 45 PSIG i
1 Instruments as identified in Unusual Event above. GENERAL EMERGENCY 4
- ,. 1. Failure of containment imminent concurrent with LOCA and fuel
' I cladding damage.
i i i 1 i
, i i '! < , 'l i '
l [J \ l 35 Issue 7 Rev. 2 4 1 _ . _ . -m= . -- . . , , ,-a.-.- ,_e , , , ~ ,, , . . , ~ , - ,-.----,.._w,.e v.-- , , , ,- ,,,
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions . O 3 INTENTIONALLY BLANK O I t l' 36 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions , Attachment 3 (1 of 1) TAB 13 LOSS OF ESF'S UNUSUAL EVENT
- 1. Loss of Engineered Safety Features (ESP) requiring shutdown by LCO. The following is a list of operable ESF subsystems necessary to meet LCO:
SIS Accumulators Operable Operatle SIS Subsystems Surveillance Baron Injection Tank Operable
. Operable Containment Quench Spray Subsystems Surveillance i
Operable Containment Recirculation Spray Subsystems Surveillance j Operable Chemical Addition System Surveillance i 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 Operable Mechanical Vacuum Pumps Surveillance ESF Activation System Operable with Proper setpoints/ Surveillance response times ALERT i Not Applicable SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY
; Not Applicable I
i F i I i e-t O 37 Issue 7 Rev. 2 i e-m - - , . - + = w r +5 Minutes
, SITE AREA EMERGENCY i
1.
! Loss of All Annunciators >15 Minutes with Plant N'ot in Cold S/D I '
Uncontrolled Transient Occurs While Annunciators are Inoperative I
! GENERAL EMERGENCY
- 1. Loss of Plant Control i
i 43 Issue 7 Rev. 2
^
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O INTENTIONALLY BIANK O I 4 l 44 Issue 7 Rav. 2 i
EPP/Implemsnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions i
' ~
~ ^' ' Attachment 3 (1 of 1) TAB 17 CONTROL ROOM EVACUATION i.
UNUSUAL EVENT Not Applicable i ALERT
- 1. Control Room Evacuation Required or Anticipated-Control at Remote j Shutdown Panel Evacuation of the Control Room is required or anticipated and control of shutdown systems has been established at the Remote
- Shutdown Panel.
Inst rument Description i1 I RM-1RM-213 Main Control Rcom Area Monitor )l
'A11-53/54 Control Room Chlorine Detector (3
- Channels) 1 J
Fire in Control Room 5 () Heavy Smoke in Control Room Other Toxic Gases observed. SITE AREA EMERGENCY j 1. Required Control Room Evacuation-Remote Control not Established j Within 15 Minutes i j Evacuation of the Control Room is required.and control of i shutdown systems has not been established at the Remote l 1 Shutdown Panel within 15 minutes 6
' GENERAL EMERGENCY
'I
- 1. Loss of Plant Control i
i i 1 l i. 45 Issue 7 Rev. 2' i
- - , . . , . - e -r .aa, ~ , , , , , -- e
EPP/Impinmenting Procedure EPP/IP I-1 Recognitton and Classification of Emergency Conditions O i INTENTIONALLY BLINK l i e l l l 1 i i l 46 Issue 7 Rev. 2
EPP/ Implementing Procedura EPP/IP I-1 Recognition and Classification of Emergency Conditions 1 Attachment 3 (1 of 1) TAB 18 , T0XIC/ FLAMMABLE GASES ( UNTSUAL EVENT
- 1. Uncontrolled Release Near-by or ONsite-Potentially Harmful i
Inst ument Description A11-53 Control Room Chlorine Detector i
! A11-86 " Chlorinator Control Unit Area Chlorine Gas Leak"
], A11-54 " Chlorine Gas Leak" Observation by irritation, noticeable odor, samples, verbal reports of authenticated accidents resulting in release.
}l ALERT t
- 1. Enters Facility. Causes Habitability Problems
)_ SITE AREA EMERGENCY-
- 1. Gas Enters Vital Areas and Restricts Access Necessary for Safe Shutdown i
GENERAL EMERGENCY
- 1. Loss of Plant Control i
f
- l 1
-1 i
t i 1 4 47 Issue 7.Rev. 2
-, ., ri--,e-c -- m--- -
*2- mm. m w e- - - - .,--*u p- --- ,mm- y+cp- p--.- -r .e-m3 g g- -> emh +-- *'
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O i INTENTIONALLY BLANT O 4 48 Issue 7 Rev. 2
1 EPP/Implemtnting Procedura EPP/IP I-1 Recognition and Classification i of Emergency Conditions ! b) (, Attachment 3 (1 of 1) TAB 19 SECURITY COMPROMISE UNUSUAL EVENT Not Applicable. Action per BVPS Security Plan. ALERT Not Applicable. Action per BVPS Security Plan. SITE AREA EMERGENCY
- 1. Imm'nent Loss of Physical Control of Plant GENERAL EMERGENCY
- 1. Loss of Physical Control of Plant O
i i 4 i y 49 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O INTENTIONALLY BLANK O l 1 i 50 Issue 7 Rev. 2
- - . -. . .. _ . _ . _ _- -.__- .=.
EPP/Implemsnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 20 LOSS OF AC POWER UNUSUAL EVENT
- 1. Loss of On-site AC Power Capability i
4 t Annunciator Description 1 AS-76 "4160 V Bus 1A Undervoltage" or s AS-100 "4160 V Bus ID Undervoltage" I or l A8-109 "4160 V Emergency Bus 1AE Undervoltage" f or l AS-117 "4160 V Emergency Bus IDF Undervoltage"
. I j Diesel Generator Inoperative per LCO <
,t .
}e i 2. Loss of Of fsite Power per LCO ALERT l . 1. Temporary Loss of Both Ons'ite and Offsite AC Power (Diesels
; Unavailable)
SITE AREA EMERGENCY ll; d l, 1. Loss of Both Onsite (Diesels' Unavailable) and Offsite Power for Longer than 15 Minutes i GENERAL EMERGENCY
- 1. Loss of Plan!t Control i
NOTE
?
Any failure to meet an LCO which results in taking the plant from
! operating status to an cperational Mode 3, hot standby, j constitutes the Unusual Event Classification.
i 1 r,
?
51 Issue 7 Rev. 2 J
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O INTENTIONALLY BLANK i l O l f l l l 4 g
._~_....._
l EPP/Implemsnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions j Attachment 3 (1 of 1) TAB 21 LOSS OF DC POWER 4 UNUSUAL EVENT t
- Not Applicable j ALERT
+
- 1. Loss of All Onsite DC Power Annunciator Description "DC Dist Pn1 No 1 Loss of Control DC" .
,, - (one fer each of 7 panels) -
I - ji SITE AREA EMERGENCY j
;. j 1. Loss of DC Pos er Sustained for Longer than 15 Minutes j GENERAL EMERGENCY
'l 4
- 1. Loss of Plant Control I
+ 4 f i 1 ! r
, i I i 4
ii l.! it i t 1
;j a i i! i t
- t Il i
i i. 8 < a .
'}
2 . !O , 53 Issue-7 Rev. 2. 1 i I
------r- - - - ,e-w rr m - ., -w,- - r .w-+.-t - e **' "* *P v71y rer - 1 0-"-"*
- EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classificatica of Emergency Conditions O
INTENTIONALLY BLANK i O 4 i i l 54 Issue 7 Rev. 2
EPP/Implemsnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 22 TORNADO UNUSUAL EVENT i 1. Tornado Warning Received / Tornado Sighted-Probable Effect on Station , 4 Instrument Description Met. System Wind Speed Indicator 35' ! Met. System Wind Speed Indicator 150' 4 Met. System Wind Speed Indicator 500' Weather Bureau advisories Personnel sighting 1 ALERT
- 1. Tornado Strikes Vital Plant Structures SITE AREA EMERGENCY
- 1. Tornado Causes Damage to Safe Shutdown Equipment GENERAL EMERGENCY f
- 1. Loss of Plant' Control l
l [ 55 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O i INTENTIONAIJ.Y BIANT e i 1 56 Issue 7 Rev. 2
enw a .+-m w. e ema ML 1 EPP/Implemsnting Procedura EPP/IP I-1
;" Recognition and Classification of Emergency Conditions -
Attachment 3 (1 of 1) TAB 23 RIVER WATER HI/ LOW UNUSUAL EVENT
- 1. River Water Level Less Than or in Excess of LCO l By Observation / Report by Corps of Engineers.
j ALERT i
- 1. River Water Level Between 705 and 730 MSL (Main Transofrmer grade elevation is 706 MSL)
SITE AREA EMERGENCY
- 1. River Water Level Exceeds 730 MSL i
i 2. Flood Causes Damage to Vital Equipment GENERAL EMERGENCY
- 1. Loss of Plant Control i
i i 1 f t i t i i m, t O 57 Issue 7 Rev. 2 1
. , , . , . . , _ . . _ . . . ~ , , , . . , . _ . , c.,.. _ , . . ,
EPP/ Implementing Procedure EPP/IP I-1 l Recognition and Classification ! of Emergency Conditions O l l i t 6 1 INTENTIONALLY BLAhT O l ll\ 4 i l l l l 58 Issue 7 Rev. 2
l. l EPP/Implemsnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions ( Attachment 3 (1 of 1) TAB 24
- EARTHQUAKE l UNUSUAL EVENT i
! 1. Earthquake Detected by Site Seismic Instrumentation The Accelerograph Recording System initiates upon detection of a '. seismic event resulting in 0.01 g acceleration. "S ie smic Accelerograph Operation" annunciator (A11-59) indicates start of systes. i ALERT i
- 1. Earthquake Greater Than 0.06 g (OBE) Occurs SITE AREA EMERGENCY i 1. Earthquake Greater Than 0.125 g (SSE) Occurs i
GENERAL EMERGENCY
- 1. Loss of Plant Control c -
6 I i l i l l -i
~
59 Issue 7 Rev. 2
-1 1
g 2 _ , , , , , _ - - y-.y. - - _ . -
, ,.y, - , . ,-p.- -,.m, g. , g, -,_-,,- - a .w.-_, ,__.-w_ , _ _ - - -gg._ , _ -.n
o EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O INTEhTIONALLY BLANK O 4 l 60 Issue 7 Rev. 2 i
_ _ .=. = _ - _ . _ . _ _ _ . . . D EPP/Implemanting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAB 25 i FIRE UNUSUAL EVENT . 1. Fire Within Plant Not Under Control Within 10 Minutes Fire within plant which is not brought under control within 10
- minutes from start of firefighting efforts.
- ALERT
- 1. Fire Which Potentially Affects Safety Systems SITE AREA EMERGENCY I
} 1. Fire Affects Safety Systems Necessary for Shutdown l .. , GENERAL EMERGENCY t I
- 1. Loss of Plant Control h
I i i t
,t s
i , i I l II 4 i 4 O 61 Issue-7 Rev. 2 4 v,--- - - --
c, .. . ;
~
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions i O INTENTIONALLY BLANK O J l issue 7 Rev. 2
E b EPP/Implemtnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O (m,/ Attachment 3 (1 of 1) TAB 26 EXPLOSION UNUSUAL EVENT
- 1. Near or Onsite Explosion With Potential Significant Damage ALERT
- 1. Explosion With Knewn Damage to Facility, Affecting Operation SITE AREA EMERGENCY
- 1. Explosion Causes Severe Damage to Safe Shutdown Equipment GENERAL EMERGENCY
- 1. Loss of Plant Control Occurs
() 63 Issue 7 Rev. 2
. . . ~
d EPP/ Implementing Procedure 'EPP/IP I-1 Recognition and Classification of Emergency Conditions O INTEhTIONALLY BLAhT O l I
.i 64 Issue 7 gey, 2
; 4 EPP/Implemsnting Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions Attachment 3 (1 of 1) TAE 27 AIRCRAFT UNUSUAL EVENT
- 1. L'nusual Aircraft Activity Over Facility
- 2. Aircraft Crashes Onsite ALERT
- 1. Aircraft or Missile Strikes a Station Structure SITE AREA EMERGENCY
~
- 1. Aircraft or Missile Crash Affects Vital Structure by Tmpact or Fire GENERAL EMERGENCY
- 1. Loss of Plant Control Occurs i
(N 4 4 l l
.O L.)
> 65 Issue 7 Rev. 2 1
EPP/ Implementing Procedure EPP/IP I-1 Recognition and Classification of Emergency Conditions O 1 INTE!frIONALLY BLANK O l 66 Issue 7 Rev. 2
- ,.-e EPP/Impismsnting Procedure EPP/IP I-1 Recognition and Classificatica of Emergency Conditions
\ Attachment 3 (1 of 1) TAB 28 i
3 MISCELLANEOUS , UNUSUAL EVENT
- 1. Train Dorails Onsite j Observation
- 2. Watercraft Strikes Intake Structure-Results in Flow Reduction i
Observation 4 ' 1i Loss of Reactor Plant River Water Flow Indications. i f ; 3. Contaminated Injury f Personnel injury occurs which results in the transportation of i! contaminated and injured personnel to an offsite hospital.
'li 4. Accident at SAPS :
1 PAX / Bell Telephone
; "Shippingport Evacuation Alert" annunciator (A4-100) l' 5. Oil Pipeline Rupture 1
i j Observation
'i ;,, 6. Turbine Casing Failure 8
Turbine casing penetrated by turbine blading or other missiles. !! ALERT ' Not Applicable
} SITE AREA EMERGENCY t
ij Not Applicable I GENERAL EMERGENCY Not Applicable t
.i
~
-)
67 Issue 7 Rev.-2~ k.._._ - ,, - _ . _ - - - . - , -- - -, , . . - , , . . , , - . , ..
i i .... EPP/ Implementing Procedure EPP/IP I-1 l Recognition and Classification of Emergency Conditions I O INTENTIONALLY BLANK O 4 l 1 68 Issue 7 Ra.v. 2
- - - - + - . __.
- . = . .
s % s s . EPP/I-2 I % 11/29/83 s 9 P
- l
' CONTROLLED COPY NO. - 6 >
3 i s '
; , x I -
UNUSUAL EVENT l 1 - 1
- i .
i i s
\
t s i ;
- , OSC Meet.itig, Number
- 3% 119
, g .
1
! Reviewed: i / Novemhev M;s1983 '
Approved: M' - l S[at' ionjSuperintend ; Approved: -- i nager, Nuclear Safety & Licensing Dept. s j %
! e,
~~
; ., s-i Issue.7 Rev. 2 !
g . s
~
- A 4 ~%
i
.?
4., -
#% l P
o EPP/ Implementing Procedure EPP/I-2 Unusual Event O TABII 0F CONTENTS A. Purpose
,B. References C. Responsibilities D. Action Level / Precautions E. Procedures F. Final Conditions G. Attachments O
8 1 f O
EPP/ Implementing Procedure ty Unusual Event V A. Purpose This instruction describes the actions to be taken for an Unusual Event at the Beaver Valley Pcwer Station. B. References 1.0 Beaver Valley Power Station Emergency Preparedness Plan and l Implementing Procedures. 2.0 Beaver Valley Power Station Operating Manual. 3.0 Beaver Valley Power Station Radiological Control Manual. 4.0 Title 10 Code of Federal Regulations Part 50, Appendix E. I 5.0 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants". C. Responsibility The Emergency Director (Shift Supervisor, until properly relieved by a designated alternate) has the responsibility and authority for (~~) implementation of the actions prescribed in this instruction. L ,J \ D. Action Levels / Precautions 1.0 Action Levels 1.1 An Unusual Event has been declared based on tha occurrence of off-normal events which could indicate a potential
; degradation of the level of safety of the plant per EPP/I-1.
2.0 Precautions i 2.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is dppropriately revised as conditions change, or more definitive information is obtained. 2.2 Corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions shall be conducted in accordance with the BVPS Operating Manual while
; simultaneously implementing this instruction.
O
\~~J l Issue 7 Rev. 2
EPP/ Implementing Proc:duro EPP/I-2 Unusual Event 2.3 Following the declaration of an Unusual Event, Federal regulations require notifications of offsite authorities must be made within fif teen minutes. E. Procedure 1.0 All Initiating Events 1.1 Sound Station Alarm once and make appropriate announcement. Announcement should state that an Unusual Event has been declared and the Station Standby Alara has been sounded. The specific plant problem should also be included .in the announcement. All available members of the On-Shift Emergency Organization should report to their stations while all other personnel should continue their normal duties but remain alert for additional announcements. 1.2 Implement appropriate assessment action. Complete and sign Attachment 1, EPP/IP 1.1, Initial Notification Form and instruct Communications and Records Coordinator to commence offsite notifications per EPP/IP 1.1. 1.3 Contact the on-call Emergency Director or- designated alternate and relay information on Initial Notification Form. Provide additional information as requested or as available. The designated Emergency Director and alternates are: Title Name Pax Bell Residence a) Station Supt. W.S. Iacey 5101 643-1258 1-262-0798 b) Chief Engineer R.J. Druga 5102 643-1264 1-653-7412 c) Supt. of Tech. M. Coppula. 5208 643-5308 1-378-1103 Services d) Supt. of Licensing K.D. Grada 5210 643-5500 1-922-1920 and Compliance NOTE Activation of the Technical Support Center (TSC), of other emergency response facilities or personnel is not required at an Unusual Event. However, the Emergency Director may activate all or part of the organization if deemed necessary. l.4 Complete Attachment 3, EPP/IP 1.1, Follow-up Notification Form and provide to offsite agencies upon call back. 2 Issue 7 Rev. 2
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l I EPP/ Implementing Procedure EPP/I-2 l Unusual Event 1 O ____.__....................... NOTE ____e If all call backs are not received from designated offsite agencies after a reasonable period of time, remake the initial notification call per EPP/IP 1.1 l.5 As conditions change, periodically check EPP/I-1 to determine phether reclassification is necessary. 1.6 Continue emergency operations until such time as plant conditions have stabilized and other termination criteria of EPP/IP 6.2 " Termination of the Emergency" have been satisfied. 2.0 Specific Initiating Events
, 2.1 Radioactivity Release to the Atmosphere l
2.1.1 Terminate the release. 2.1.2 Initiate offsite dose projections per EPP/IP 2.6.1,
" Dose Projections - General Methods".
2.1.3 Initiate onsite radiation surveys per EPP/IP 2.2,
'p) 3,, 2.1.4 "Onsite Monitoring for Airborne Release".
Depending on onsite survey results, escalate emergency classification as warranted. i 2.2 Radioactivity Release to the Ohio River. ,
! 2.2.1 Terminate the release.
! 2.2.2 Determine activity vja effluent monitor reading i or per EPP/IP 2.7, " Liquid Release Estimate".
2.2.3 Depending upon activity, escalate or de-escalate the classification or confirm estimate per EPP/IP 2.4, "Offsite Monitoring for Liquid Release". 3.0 Miscellaneous Initiating Events 3.1 Fire / Explosion per EPP/IP 8.1, " Fires in Controlled Areas"
} or Chapter 56B-BVPS-0M.
! l 3.2 Contaminared Personnel Injury per EPP/IP 5,2, " Handling of
.j Contaminated / Irradiated Personnel Injuries", or Chapter 56, Section 4, BVPS-RCM.
]
i j 3.3 Tornado / Earthquake / Storms / Flooding per Chapter 53 BVPS-0M. O] \-- 3 Issue 7 Rev. 2 l l t t F
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EPP/ Implementing Proceduro EPP/I-2 Unusual Event F. Final Conditions 1.0 Oncoming Emergency Director contacted. 2.0 Initial offsite notifications commenced. 3.0 The U.nusual Event has been closed out with normal station administration resumed or the emergency reclassified. G. Attachments 1.0 Checklist - Gas 2.0 Checklist - Liquid 3.0 Checklist - Contaminated Personnel Injury O f l 4 Issue 7 Rev. 2
V n2 - . . - I l'* . s EPP/ Implementing Procedure EPP/I-2 Unusual Event
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t~ Attachment 1 (1 of 1) CHECKLIST Note The use of this checklist is optional. It is provided as a convenience for the Emergency Directo., It need not be filled out, nor retained. This checklist 's i n ,t utended to replace the EPP/ Instruction to which it is attached. O. Unusual Event - Gas EPP/IP STEP OUTLINE Initial Time I-2 1.1 Implement corrective actions
- (Stop release) f I-2 2.2 Initiate and continue dose projection j (EPP/IP-2.6)
I-2 2.3 Initiate radiation survey (EPP/IP-2.2) I-2 1.2 Complete Initial Notification Form I-2 1.3 Notify designated Emergency Director I-2 1.4 Notify additional DLC personnel for assistance i I-2 2.4 Escalate to Alert if necessary j (Alert-Gas checklist) i 1 , I-2 1.5 Notify offsite authorities
, (EPP/IP-1.1)
I-2 1.6,7 Complete follow-up notification I-2 1.8 Have Public Information Department complete their notifications i I-2 1.10 Terminate when termination criteria (EPP/IP-6.2) have been met
-1 O 5 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/I-2 Unusual Event O m INTENTIONALLY BLANK i O t 6 Issue 7 Rev. 2
EPP/Implemsnting Procedure EPP/I-2 I Unusual Event Attachment 2 (1 of 1) t O ....-:.. CHECKLIST l Note
- The use of this checklist is optional. It is provided as a convenience ror the Emergency Director. It need not be filled out, nor retained. This dhecklist is not intended to replace the EPP/ Instruction to which it is attached.
t i Unusual Event - Liquid i EPP/IP STEP OUTLINE Initial TLas i f I-2 1.1 Implement corrective actions (Stop release) I-2 3.2 Estimate release (EPP/IP-2.7). 'If i - Release of 10 MPC, declare Alert (Alert-Liquid checklist) _ I-2 1.2 Complete Initial Notification Form I-2 1.3 Notify designated Emergency Director I-2 1.4 Notify additional DLC personnel for i assistance I ' I-2 3.3 Sample river (EPP/IP-2.4). If s i release 10 MPC, declare Alert (Alert- ~ liquid checklist) I-2 1.5 Notify offsite authorities including Coast Guard, US Corps of Engineers, and water treatment plants (EPP/IP-1.1) 1 I-2 1.6,7 Complete follow-up notification I i I-2 1.8 Have Public Information Department }} i i complete their notifications l I-2 1.10 Terminate when termination criteria {' _ , ._ (EPP/IP-6.2) have been met i ) ,i O 7 Issue 7 Rev. 2 I 4 ll
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EPP/ Implementing Procedure EPP/I-2 ' Unusual Event O i INTENTIONALLY BLANK O-8 Issue 7 Rev. 2
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1 EPP/ Implementing Procedura .EPP/I-2 Unusual Event i Attachment 3 (1 of 2) CHECKLIST Note The use of this checklist is optional. It is provided as a convenience for the Emergency Director. It need not be filled out, nor retained. This checklist is not intended to replace the EPP/ Instruction to which it is attached. Unusual Event - Contaminated Personnel Injury EPP/IP STEP OUTLINE Initial Time 5.2 1.1,2 Sound Standby Alarm and dispatch Emergency Squad 5.2 1.5 Call ambulance (if nacessary). 5.2 1.6 Notify hospital 5.2 1.7 If victim cannot be transported summon medical assistance to station ' (Drs. Wald and Spritzer, RERP program). 5.2 1.8 Notify security officers of impending ambualnce arrival 5.2 1.9 Direct Emergency Squad to transport victim to first aid room (if he can be moved). 5.2 1.11 Decontaminate victim (if time is available). 5.2 1.12 Prepare ambulance to minimize contamination f 5.2 1.13 Direct DLC Supervisor and Radcon
- technician to accompany victim to l hospital 4
! I-2 1.2 Complete Initial Notification Form I
1 s.s' 9 Issue 7 Rev. 2 l 4.__ -_ _
e EPP/ Implementing Procedure EPP/I-2 Unusual Event Attachment 3 (2 of 2) I-2 1.3 Notify designated Emergency Director I-2 1.5 Notify offsite authorities (EPP/IP-1.1) I-2 1.6,7 Complete follow-up notifications e I-2 1.8 Have Public Information Department complete their notifications I-2 1.10 Terminate when termination criteria (EPP/IP-6.2) have been met O I 10 Issue 7 Rev. 2
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< . . 1 I 1 EPP/I-3
~ ^ ' ' " '
, 11/29/83
. CONTROLLED
.i COPY NO. - D= . l i 1 3 i t
- ALERT 4
f 4 ll f 1 i e
- o f
OSC Meeting Number: 119 i Reviewed: _ 4 Novemtwr ,22., 1983 ' ' 1
- 4. Approved: ; [me // a _
C . + S tibn' KperMee~n~d'entr f Approved: -X
) M ger, Nuclear Safety & Licensing Dept.
ll I l Issue 7 Rev. 2 O
EPP/ Implementing Procedure EPP/I-3 Alert
~
TABLE OF CONTENTS O A. Purpose B. References C. Responsibilities D. Action Level / Precautions E. Procedures F. Final Conditions G. Attachments l l 9 t I f i ll O
EPP/ Implementing Procedure Alert A. Purpose This instruction describes the actions to be taken in the event that an Alert Emergency condition has been declared at the Beaver Valley Power Station. B. References 1.0 Beaver Valley Power Station Euergency Preparedness Plan and Implementing Procedures. 2.0 Beaver Valley Power Station Operating Manual. 3.0 Beaver Valley Power Station Radiological Control Manual. 4.0 ritle 10 Code of Federal Regulations Part 50, Appendix E. 4 5.0 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of 1 Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants". C. Responsibilities The Emergency Director (Shift Supervisor, until properly relieved by a designated alternate) has the responsibility and authority for the completion of the prescribed actions in this instruction. D. Action Levels / Precautions 1.0 Action Levels 1.1 An Alert Emergency condition has been declared based on the occurrence of events which indicated an actual or potential degradation of the level of safety of the plant per EPP/I-1. 1.2 An Unusual Event had been declared and based on subsequent information or upon a deterioration in plant conditions, the 1 conditions has been reclassified as an Alert. l 2.0 Precautions i l 2.1 Continued surveillance and assessment of plant conditions are l necessary to ensure that the emergency classification is appropriately revised as conditions change, or more definitive information is obtained. 2.2 Corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions shall be j conducted in accordance with the BVPS Operating Manual while i simultaneously implementing this instruction. I a l k/ 1 Issue 7 Rev. 2 L i
EPP/ Implementing Proceduro EPP/I-3 Alert 2.3 Following the declaration of an Alert, Federal regulations = - require notification of offsite authorities within fifteen minutes. ll
'E. Procedure 1.0 All Alert Initiating Events 1.1 Sound Station Standby Alarm once and announce that an Alert has been declared, all Emergency Squad personnel, Technical Support Center and Operations Support Center personnel should report to their stations. All Emergency Operations Facility personnel should be in a stand-by mode. All other station personnel should report to Primary Assembly Area.
1.2 Implement appropriate assessment actions. Complete and sign Attachment 1, EPP/IP 1.1, Initial Notification Form using data derived from initial assessment activities. Instruct Communications and Records coordinator to begin offsite-notifications per EPP/IP 1.1, Attachment 2. 1.3 Notify the designated Emergency Director or alternate of the emergency condition. Provide information available or as requested. The Designated Emergency Director and alternates are: Residence O Title Name Py Bell a) Station Supt. Unit 1 W .S. Lacey 5101 643-1258 1-262-0798 b) Chief Engineer R.J. Druga 5102 643-1264 1-653-7412 c) Supt. of Tech. M. Coppula 5208 643-5308 1-378-1103 Services d) Supt. of Licensing K.D. Grada 5210 643-5500 1-922-1920 and Compliance 1.4 Complete Attachment 3, EPP/IP 1.1, Follow-up Notification Form and provide information to offsite agencies upon call back. 2 Issue 7 Rev. 2
- = - = = . - := =
J
- EPP/Implemsnting Procedura EPP/I-3
' Alert '
4-; 1.5 Notify the designated Emergency / Recovery Manager or alternate g of the emergenc77 "coiidition ~and place him on standby in anticipation of a possible escalation in the emergency classification. Title Name Lax Bell Residence a) Manager, Nuclear T.D. Jones -5202 643-5800 1-741-5890 Operations b) Manager, Nuclear J.D. Sieber 5212 643-5502 1-364-4547 Safety & Licensing c) Manager, Nuclear F.J. Bissert 5200 643-5300 1-563-7851 Support Services d) Technical Assistant R.F. Balcerek 5218 643-8587 1-741-3711 To V.P. l 1.6 Activate the emergency response organizations using the beepers or Emergency Call-List per EPP/IP 1.2.1. This will activate the Technical Support Center while placing the . Emergency Operations Facility in a standby position. l 1.7 Activate the Operations Support Center and the Radcon Operations Center per EPP/IP 1.5, " Emergency Support Centers (OSC, ROC) Activation, Operation and-Deactivation." s ----________________ , NOTE 4 j If all call backs are not received from designated offsite j agencies after a reasonable period of time, remake the intial notification call per EPP/IP 1.1. i j i
; 4 1.8 As conditions change update DLC Public Information ! Papartment.
. ; 1.9 As conditicas change, periodically check EPP/I-1 to determine ) > whether reclassification is necessary. ji
! 1.10 Ccatinue emergency operations until such time as plant j,j conditions have stabilized and other termination criteria per EPP/IP 6.2, " Termination of the Emergency and Recovery", have j been satisfied.
i (
)
< ,O I 3 Issue 7 Rev. 2-I e I
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EPP/Implem:nting Proceduro EPP/I-3 Alert 2.0 Specific Initiating Events 2.1 Radioactivity Release to the Atmosphere or Unexpected Ir creases in In-Plant Radiation Levels. 2.1.1 Perform corrective measures to terminate release or regain control over plant radiation levels. 2.1.2 Initiate offsite dose projections per EPP/IP 2.6.1, "Do.se Projection - General Methods", and EPP/IP 2.6, " Dose Projection, if necessary. 2.1.3 Initiate onsite radiation surveys per EPP/IP 2.2, "Onsite Monitoring for Airborne Release", and offsite radiation surveys per EPP/IP 2.3, "Offsite Monitoring for Airborne Release" 2.1.4 Depending upon radiation survey results and accident conditions refer to the following procedures if appropriate: a) " Evacuation", EPP/IP 3.1 b) " Personnel Accountability", EPP/IP 3.2 c) " Search and Rescue", EPP/IP 5.1 d) "Re-entry to Affected Areas", EPP/IP 6.1 2.1.5 Note the reading on the Control Room Radiation Monitor (RM-1RM-213) to evaluate habitability of the Control Room. 2.1.6 Continue assessment actions and if necessary escalate the classifice. tion per EPP/I-1. 2.2 Radioactive Release to the Ohio River. 2.2.1 Perform appropriate corrective measures to terminate the release. I 2.2.2 Determine the activity of the release by effluent monitor reading or by estimate per EPP/IP 2.7,
" Liquid Release Estimate".
2.2.3 Confirm activity estimate results by sampling and i analysis per EPP/IP 2.4, "Offsite Monitoring for Liquid Release". 4 Issue 7 Rev. 2 l l
EPP/Implemanting Procedure EPP/I-3 Alert NOTE State agencies responsible for water quality will likely initiate water sampling at downstream water treatment plants. These agencies will curtail the use of water, based on projected radioactivity concentrstions. This protective action and the dilution volume of the Ohio River significantly reduce the potential for offsite doses in excess of 170 mrem (any organ) due to liquid release. 3.0 Miscellaneous Initiating Events t 3.1 Fire / Explosion per EPP/IP 8.1, " Fires in Controlled Areas", i and BVPS Operating Manual, Chapter 56B. 3.2 Ternado/ Earthquake / Storms / Flooding per BVPS Operating Manual, Chapter 53. F. Final Conditions l.0 Oncoming Emergency Director contacted. ,, 2.0 EOF Director contacted. 3.0 Initial Offsite notifications initiated 4.0
;() The Alert has been closed out with normal station administration resumed, a recovery organination established or the emergency reclassified.
1
+
G. Attachments ll' 1.0 Checklist - Gas j 2.0 Checklist - Liquid + i i i k i 1 i a . $0 \s-5 Issue 7 Rev. 2 l l l l l
]
EPP/ Implementing Procedure EPP/I-3 Alert O INTENTIONALLY D'JSK l O i 1 1 l 6 Issue 7 Rev. 2
* ^
EPP/ Implementing Procedure EPP/I-3 !. Alert 4 Attachment 1 (1 of 2) CHECKLIST Note The use of this checklist is optional. It is provided as a convenience for the Emergency Director. It need not be filled out, nor retained. This checklist is not intended to replace the EPP/ Instruction to which it i-attached. Alert - Gas EPP/IP STEP OUTLINE Initial Time 4 I-3 1.1 Implement corrective actions (Stop release) I-3 2.2 Initiate and continue dose projection (EPP/IP-2.6)
-(O) I-3 1.2 Complete Initial Notification Form I-3 2.3 Initiate onsite radiation survey (EPP/IP-2.2)
. I-3 2.4 Evacuate personnel if necessary l
(EPP/IP-3.1) I-3 1.3 Notify designated Emergency Director I-3 1.4 Notify offsite authorities including - Coast Guard and Westinghouse j (EPP/IP-1.1)
! I-3 1.5 Place Emergency / Recovery Manager j on Standby i
- I-3 2.6 If dose rate at site boundary 120 mrem /hr or possible accumulative dose of 170 mrem classify as Site Area Emergency
+
\~ 7 Issue 7 Rev. 2
, , . - - , - - . - ., - +- - - ---- - - * ~
EPP/ Implementing Precedure EPP/I-3 Alert Attachment 1 (2 of 2) O I-3 1.6 Activate Technical Support Center (EPP/IP-1.4) (EPP/IP-1.3). Activate Radcon Operations Center, Operations Support Center (EPP/IP-1.5), if necessary I-3 1.8,9 Complete follow-up notification I-3 1.10 Have Public Information Department complete their notifications I-3 1.12 Terminate when termination criteria (EPP/IP-6.3) have been met _ O 4 1 i 8 Issue 7 F.ev. 2 l l l
EPP/ Implementing Procedure EPP/I-3 Alert
-g Attachment 2 (1 of 2)
CHECKLIST Note The use of this checklist is optional. It is provided as a convenience for the Emergency Director. It need not be filled out, nor retained. This checklist is not intended to replace the EPP/ Instruction to which it is attached. Alert - Liquid EPP/IP STEP OL*TLINE Initial Time I-3 1.1 Implement corrective actions (Stop release) I-3 3.2 Estimate release (EPP/IP-2.7). If - 10 MPC, notify offsite authorities immediately 4.1 6 If 10 MPC advise Midland Water Treat-ment Plant to stop taking water from Ohio River () I-3 1.2 1.3 Complete Initial Notification Form I-3 Notify designated Emergency Director I-3 1.4 Notify offsite authorities including Coast Guard, US Corps of Engineers Westinghouse, and Water Treatment Plants (EPP/IP-1.1) I-3 1.5 Place Emergency / Recovery Manger on Standby I-3 3.3 Determine activity by sampling (EPP/IP-2.4) t 9 Issue 7 Rev. 2
EPP/Implem:ncing Procedure EPP/I-3 Alert Attachm. int 2 (2 of 2) O I-3 1.6 Activate Technical Support Center (EPP/IP-1.4) (EPP/IP-1.3). Activate Radcon Operations Center, Operations Support Center (EPP/IP-1.5), if necessary I-3 1.8,9 Complete follow-up notification I3 1.10 Have Public Information Department complete their notifications I -3 1.12 Terminate when termination criteria (EPP/IP-6.3) have been met 9 l l 10 Issue 7 Rev. 2
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l . - l 1 4 EPP/I-4 11/29/83 i
)
I l CONTROLLED COPY NO. G - E V SITE AREA EMERGENCY 1 . Ii
;i
- OSC Meeting Number
- 119 _
Reviewed: p / Novenber (22,1983 l Approved: Ae/ M /f/ M _ I SfatW /uperYnt endent }
; Approved: ) la -
Ma ger, Nuclear Safety & Licensing Dept. _ il i 5 l-I- l Issue 7 Rev. 2 !O I l l l
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EPP/ Implementing Procedure EPP/I-4 Site Area Emergency TABLE OF CONTENTS A. Purpose J B. References C. : Responsibilities D. Action Level /Precartions E. Procedures F. Final Conditions G. Attachments I i O I t 4 e I I t 1, - 1 0 l _--x-
EPP/ Implementing Procedure p Site Area Emergency A. Purpose This instruction describes the actions to be taken in the event that a Site Area Emergency has been declared at the Beaver Valley Power Station. B. References 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures. 2.0 Beaver Valley Power Station Operating Manual. 3.0 Beaver Valley Power Station Radiological Control Manual. 4.0 Title 10 Code of Federal Regulations Part 50, Appendix E.
! 5.0 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of 1
Radiological Emergency Response Plans and Preparedness in Support j of Nuclear Power Plants". C. Responsibilities The Emergency Director (Shift Supervisor, until properly relieved by a i(s (~,, designated alternate) has the responsibility and authority completion of the prescribed actions in this instruction. When the for Emergency Operations Facility is operational, this responsibility is assumed by the Emergency / Recovery Manager. D. Action Levels / Precautions 1.0 Action Levels i i 1.1 A Site Area Emergency has been declared based on the i
' occurrence of events which involve actual or likely failures of plant functions needed for the protection of the public.
Events classified as Site Area emergencies are described in EPP/I-1. l 1.2 An Unusual Event or an Alert emergency condition had been declared and emergency measures are being performed; and on
- the basis of subsequent information or upon deterioration in
!I plant conditions, the condition has been reclassified as a Site Area Emergency. f 1 Issue 7 Rev. 2 i
EPP/Implemrnting Procedure EPP/I-4 Site Area Emergency 2.0 Prec'autions 2.1 Continued surveillance and assesscient of plant conditions are O necessary to ensure that the emergency classification is appropriately revised as conditicas change or more information is obtained. 2.2 The Site Area Emergency is the lowest emergency classification in which offsite protective actions for airborne releases may be warranted. In consideration of the lead time necessary to implement protective actions,
~
notifications of offsite authorities must be made within fifteen minutes after declaration of a Site Area Emergency. E. Procedure 1.0 All Site Area Initiating Events 1.1 Sound Stard-by Station Alarm or ce and announce that a Site j Area Emergency has been declared. Also included in the j announcement should be instructier.s to activate the Emergency Response facilities and instructions for all non-essential personnel. 1.2 Implement appropriate assessment or corrective actions. Complete Attachment 1, EPP/1.1, Initial Notification Form and instruct offsite notifications conmence per EPP/IP-1.1. 1.3 Notify the designated Emergency Director or his alternate. O
, Title Name Pax Bell Residence ] a) Station Supt, W.S. Lacey 5101 643-1258 1-262-0798 ; Unit 1 643-1264 i
b) Chief Engineer R.J. Druga 5102 1-653-7412 4 c) Supt. of Tech. M. Coppula 5208 643-5308 1-378-1103 i Services I d) Supt. of Licensing K.D. Grada 521C 643-5500 1-922-1920 and Compliance e I i i l i 2 Issue 7 Rev. 2
.= = n _ - -
2 -. EPP/Impicmsnting Procedure ' EPP/I-4 Site Area Emergency ,m (x 1.4 Notify the designated Emergency / Recovery Manager er his d alternate. Alternate: Title - Name Pax Bell Residence a) Manager, Nuclear T.D. Jones 5202 643-5800 1-741-5890 Operations b) Manager, Nuclear J.D. Sieber 5212 643-5502 1-364-4547 Safety and Licensing c) Manager, Nuclear F.J. Bissert 5200 643-5300 1-563-7851 Support Services- ' d) Manager, Nuclear R.F. Balcerek 5218 643-8587 1-741-3711 1.5 Activate the following Emergency Response Centers: Technical i Support Center, Emergency Operations Facility, Operations Support Center, Radeon Operations Center and notify
, appropriate personnel to staff these facilities. The following procedures may be referenced:
f 1.5.1 EPP/IP-1.4 "TSC. Activation Operation and Deactivation". 1.5.2 EPP/IP-1.6 " EOF Activation, Operation and Deactivation". () 1.5.3 EPP/IP-1.5 "Emeigency Support Center (OSC, ROC) Activation Operation, and Deactivation". 1.5.4 Monthly BVPS Telephone Call-list. 1.6 Complete Attachment 3, EPP/IP-1.1, Follow-up NotificationForm l and provide information to offsite agencies upon call back j per EPP/IP-1.1. l ................................ j NOTE If all call backs'are not received from designated offsite
~
agencies after a reasonable e period .of time, remake the initial notification call per EPP/IP 1.1. l i g 4 3 Issue 7 Rev. 2 s
-- --.a - ,
-l EPP/Implem:nting Proc:duro EPP/I-4 Site Area Emergency 1
1.7 Continue assessment actions. According to plant conditions l the following may be referenced: 1 1.7.1 EPP/IP-3.1 " Evacuation" 1.7.2 EPP/I' 3.2 " Personnel Accountability" 1.7.3 EPP/IP-3.3 " Search and Rescue" 1.8 Update offsite authorities / agencies as conditions change. If requested by offsite agencies, provide DLC Liaisons to the offsite Emergency Operations Centers. 1.9 If plant conditions deteriorate, escalate the emergency classification. Perform actions in accordance with the appropriate EPP/ Instructions-1.10 Ccntinue emergency operations until such time as plant conditions have stabilized and other termination criteria of EPP/IP-6.2, " Termination of the Emergency and Recovery" have been satisfied. 2.0 Specific Initiating Events 2.1 Radioactivity Release to the Atmosphere of Unexpected Increase In-plant Levels. 2.1.1 Perform corrective measures to terminate the telease or to regain control over plant radiation lh levels. 2.1.2 Initiate offsite dose projection activities per EPP/IP-2.6.1, " Dose Projection - General Me'thods " , continuing with EPP/IP-2.6, " Dose Projection", if
. necessary.
2.1.3 Initiate emergency onsite radiation surveys per EPP/IP-2.2, "Onsite Monitoring of Airborne Release", and offsite radiation surveys per EPP/IP-2.3, "Offsite Monitoring of Airborne Release". 2.1.4 Based on the results of the dose projection activities recommend an appropriate protective action to offsite authorities per EPP/IP-4.1,
" Recommendation of Offsite Protective Actions".
- ,I 4 Issue 7 Rev. 2
i
- LPP/Implemsnting Procedure EPP/I-4
- Site Area Emergency 1
The Emergency / Recovery Manager (Emergency Director until the " EOF is activated) is the only individual authorized to i determine and recommend a protective action to offsite l authorities.
, 2.1.5 Remain aware of the reading on the Control Room i
Area Radiation Monitor (RM-IRM-213) and obtain , appropriate airborne radioactivity samples. I 2.1.6 Based on the survey results, reclassify the ; emergency as appropriate per EPP/I-1. Offsite authorities must be notified of any reclassification. 2.2 Radioactive Release to the Ohio River. 1 2.2.1 Liquid releases to the Ohio River are not j, identified as initiating events for a Site Area
, Emergency since it is unlikely to have offsite i doses in excess of 170 mrom (any organ) due to the ! release. A liquid release could occur concurrent
- with the events which initiate the ~ Site Area emergency. Corrective actions and asssessment
'O measures for liquid releases are provided Section E 2.2 of EPP/I-3.
in 2.3 Miscellaneous Initiating Events 2.3.1 Fire / Explosion per EPP/IP-8.1, " Fires in Controlled Areas", and Chapter 56B of the Beaver Valley Power Station Operating Manual. l 2.3.2 To rnado/ E a rt hquake/ S to rms / F looding per Chapter 53 BVPS Operating Manual. F. Final Conditions t 1.0 Oncoming Emergency Director contacted. I !l 2.0 Emergency / Recovery Manager contacted.
'l 3.0 Offsite notifications initiatsd and updated.
,I d 4.0 The Site Area Emergency has been closed out with normal station administration resumed and a recovery organization established or the emergency is reclassified. { G. Attachments 1.0 Checklist 5- Issue 7 Rev. 2 1 . i
- ---n.-- , , - - - - -, ----- - -r-. e n r -
EPP/Impicm:nting Precedure EPP/I-4 Site Area Emergency Attachannt 1 (1 of 2) CHECKLIST Note Tha use of this checklist is cotional. It is provided as a convenience for the Emergency Director. It need not be filled out, nor retained. This checklist is not intended to replace the EPP/ Instruction to which it is attached. Site Area Emergency EP?/IP STEP 0UTLINE Initial Time - I-4 1.1 Implement corrective actions , I-4 2.2 Initiate and continue dose projection (EPP/IP-2.6) - I-4 1.2 Ccmplete Initial Notification Form I-4 2.3 Initiate onsite radiation survey (EPP/IP-2.3) I-4 2.4 Initiate offsite radiation survey (EPP/IP2.3) fh I-4 2.5 Recommend protective actions (EPP/IP-4.1) (to be included in all
~
subsequent notifications) I-4 1.3 Notify designated Emergency Director I-4 1.4 Notify offsite authorities (EPP/IP-1.1) _
- -4 1.5 Notify Emergency / Recovery Manager I-4 1.6 Activate TSC .
I-4 1.7 Activate EOF, OSC, ROC
- I-4 2.6 Use respirators if necessary i
i i l i 6 Issue 7 Rev. 2 Ol !
.. . . - .- . . - . - _ . = . _ ~ _ .. .-- . .. . - . - . _ . . . - . . = _
EPP/Implemsnting Procedure EPP/I-4 1 Site Area Emergency Attachment 1 (2 of 2) ,_, _ CHECKLIST (continued) i Site Area Emergency EPP/IP STEP OUTLINE , Initial Time j i I-4 '1.8,9 Complete follow-up notification I-4 2.7 Reclassify if necessary i I-4 1.10 Have Public Information Department complete their notifications, activate ENC I-4 1.11 Implement unit evacuation (EPP/IP-3.1)
! (EPP/IP-3.2) (EPP/IP-5.1)
I-4 1.12 Periodically disseminate info to offsite authorities I-4 1.13 If plant conditions deteriorate, escalate classification l i I-4 1.14 Terminate u!nT. termination criteria (EPP/IP-6.2) have been net ] 4 s
\ t
, f l, >t i; l 7 Issue 7 Rev. 2 4
l 1 l EPP/I-5 l 11/29/83 i CONTROLLED C O P_YN O.' 0 = j I i j l GENERAL EMERGENCY i, I t .i
- O '
.l OSC Meeting Number: 119 l ] Reviewed: / Noven6er 32,1983 l Approved: m/ f]>; _ S[ation upefintend Approved: , ' *
, M ger, Nuclear Safety & Licensing Dept.
l t .I I k i Issue 7 Rev. 2 O
EPP/ Imp.1.ementing Procedure EPP/I-5 General Emergency 9-TABLE OF CONTENT.3 A. Purpose B. References C. Responsibilities D. Action Level /Precautians
~
E. Procedures F. Final Conditivns G. Attachments e i 4 1 O
EPP/ Implementing Procedure General Emergency v A. Purpose This instruction describes the actions to be taken in the event that a General Emergency has been daclared at the Beaver Valley Power Station. B. References 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures. 2.0 Beaver Valley Power Station Operating Manual. 3.0 Beaver Valley Power Station Radiological Control Manual. 4.0 Title 10 Code of Federal Regulations Part 50, Appendix E. 5.0 NUREG-0654/ FEMA-REP-1 "Criteriaafor Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." C. Responsibilities The Emergency Director (Shift Supervisor, until properly relieved by a designated alternate) has the responsibility and authority for the y completion of the prescribed actions in this instruction. When the j Emergency Operations Facility is operational, this responsibility is assumed by the Emergency / Recovery Manager. D. Action Levels / Precautions 1.0 Action Levels
, 1.1 A General Emergency has been declared based on the occurrence of. events which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Events classified as General Emergencies are described in EPP/I-1.
1.2 A less severe emergency has been declared and emergency measures are being performed; and on the basis of subsequent information or upon a deterioration in plant conditions, the
, condition has been reclassified as a General Emergency.
i i iO
,V 1 Issue 7 Rev. 2
EPP/Implex;nting Procedure EPP/I-5 G:n ral Er2rg:ncy 2.0 Precautions 2.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change or more definite information is obtained. 2.2 The General Emergency classification includes actual or imminent events for which offsite protective actions will be needed. Notificatic:_2 to offsite authorities must be made within 15 minutes after the declaration of the General Emergency. l
, l 2.3 Corrective actions to contend with the situation and to mitigate possible deterioration in plaat conditions in . accordance with the BVPS Operating Manual shall be conducted sinultaneously with this instruction.
E. Procedure . 1.0 All General Emergency Initiating Events
!~
1.1 Sound Stand-by Station Alarm once and announce that a General Emergency has been declared. Included in the announcement should be instructions for activating the Emergency. Response Facilities and for all non-essential personnel. 1.2 Implement appropriate assessment actions. Complete attachment 1. EPP/IP 1.1 and instruct offsite notification to commence per EPP/IP 1.1. 1.3 Notify the designated Em_rgency Director or his alternate.
} Title Name Pax Bell Residence a) Station Supt. W.S. Lacey 5101 643-1258 1-262-0798 ! Unit #1 b) Chief Engineer R.J. Druga 5102 e43-1264 1-653-7412 c) Supt. of Technical M. Coppula 5208 643-5308 1-378-1103 Services d) Supt of Licensing K.D. Grada 5210 643-5500 1-922-1920 and Compliance 1
2 Issue 7 Rev. 2
EPP/Implemsnting Procedure EPP/I-5 General Emergency 1.4 Notify the designated Emergency / Recovery Manager or his O alternate. Title Name Pax Bell Residence a) Manager, Nuclear T.D. Jones 5202 643-5800 1-741-5890 Operations b) Manager, Nuclear J.D. Sieber 5212 643-5502 1-364-4547 Safety & Licensing c) Manager, Nuclear F.J. Bissert 5200 643-5300 1-563-7851 Support Services j d) Technical Asst. R.F. Salcerek 5218 643-8587 1-741-3711 to V.P. 1 1.5 Activiate the following emergency response centers: Technical Support Center, Emergency Operations Facility, Operations Support Center, Radcon Oparations Center, and notify appropriate personnel to staff these facilities. The following procedures may be referenced: 1.5.1 EPP/IP 1.4 " Technical Support Center, Activation, Operation and Deactivation". 1.5.2 EPP/IP 1.6 -
" Emergency Operations Facility.
Activation, Operation and Deactivation". 1.5.3 EPP/IP 1.5 " Emergency Support Center (OSC + ROC)' Activation, Operation and Deactivation". 1.5.4 Monthly BVPS Telephone Call-list. 1.6 If the incident occurs during off-hours and TSC and EOF i personnel are unable to approach the site, the Shift 1 Supervisor retains the position of Emergency Director in the Control Room until the alternate EOF bcs been activated, i communcations established, and the designated Emergency Director or alternate has relieved the Shift Supervisor from j the alternate EOF. j 1.7 Complete Attachment 3, follow-up Not'fication Form, EPP/IP 1.1 using the most current data and provide offsite agencies upon verification callback. i O 3 Issue 7 Rev. 2 l i L
EPP/Impicm:nting Procedure EPP/I-5 G:noral Emsrg:ncy NOTE If all call backs are not received from the designated offsite agencies after a reasonable period of time, remake the initial notification call per EPP/IP 1.1 1.8 Continue assessment acticn. According to plant conditions the following procedures may be referenced: 1.8.1 EPP/IP 3.1 " Evacuation" 1.8.2 EPP/IP 3.2 " Personnel Accountability" 1.d.3 EPP/IP 5.1 " Search and Rescue" 1.9 Direct Radeon personnel to perform radiation and airborne radioactivity surveys at the designated assembly areas. Relocation or a Site evacuation may be necessary. NOTE The implementation of a Site evacuation must be based on the protective action which result in the lowest personnel exposure. Evacuations should be initiated wither before, or after passage of the release and evacuation routes chosen to lead personnel away from the plume. The Emergency Director should consider the dose rate at personnel assembly areas, { dose rate onsite, and dose rates along the routes in making an evacuation decision. $ 1.10 Ensure offsite dose projection activities are initiated in accordance with EPP/IP 2.6.1, " Dose Projections - General Methods", and continue as necessary per EPP/IP 2.6, " Dose I Projectica". I i 1.11 Initiate onsite radiation surveys per EPP/IP 2.2, "Onsite i ' Monitoring for Airborne Release", and offsite surveys per EPP/IP 2.3, "Offsite Monitoring for Airborne Release". l 1.12 Based on the results of the dose projection activities,
- ecommend appropriate offsite protective actions. The Emergency Director is the only individual authorized to determine and recommend a protective action to offsite i
authorities. This authority shifts to the Emergency / Recovery Manager when the EOF is activated. 4 Issue 7 Rev. 2
EPP/Impicmenting Procedura EPP/I-5 General Emergency fs 1.13 Update offsite authorities / agencies as conditions warrant. i If requested by offsite Emergency Operation Centers provide DLC liaisons. 1.14 Continue e.mergency operations until such time as plant conditions have stabilized and other termination criteria of
- EPP/IP 6.2, " Termination of the Emergency and Recovery", have
, been satisfied.
l F. Final Conditions 1.0 Oncoming Emergency Director contacted.
, 2.0 Emergency / Recovery Manager contacted 3.0 Offsite notifications initiated.
4.0 The General Emergency has been closed out with normal station
, administration resumed and a recovery organization established or the emergency has been reclassified.
G. Attachments 1.0 Checklist
/~') I V
i i 4 l
'i 4
l l bs- 5 Issue 7 Rev. 2 i r u - a , . ~ . .
I l EPP/ Implementing Proceduro EPP/I-5 ) General Emergency t t I l 9 l INTENTIONALLY BLANK O i 6 Issue 7 Rev. 2
EPP/Implemnnting Procedure EPP/I-5 General Emergency Attachment 1 (1 of 2) EPP/IP STEP OUTLINE Initial Time I-5 1.1 Implement Corrective Actions I-5 1.2 Complete Initial Notification Form I-5 1.3 Notify designated Emergency Director I-5 1.4 Notify offsite authorities (EPP/IP-1.1) l I-5 1.6 Notify the designated Emergency / Recovery Manager
. I-5 1.6 Activate TSC I-5 1.7 Activate EOF, OSC, ROC I-5 1.9,10 Complete follow-up notification I-5 1.12 Implement unit evacuation if a release is or is about to occur O (EPP/IP-3.1, 3.2, 5.1). Consider other evacuations (EPP/IP-3.1)
I-5 1.13 Have Public Information Department complete their notifications I-5 1.14 Initiate and continue dose project. 1 (EPP/IP-2.6) l I-5 1.15 Initiate onsite radiation survey
; (EPP/IP-2.2)
I-5 1.16 Initiate offsite radiation survey (EPP/IP-2.3) l i i i C1 7 Issue 7 Rev. 2 y <_ ,- - . _ . , y, ,,- , - - - - -
EPP/Impicm:nting Procedure EPP/I-5 General Emergency Attachment 1 (2 of 2) General Emergency O EPP/IP STEP OUTLINE Initial Time I-5 1.17 Recommend protective act:fons (EPP/IP-4.1) I-5 1.18 Use respirators if neces sary I-5 1.19 Periodically disseminato ir4fo to offsite authorities I-5 1.20 Terminate when terminat:.on critoria (EPP/IP-6.2) have been tiet O I f 6 l t t 4 8 Issue 7 Rev. 2 l l l 1
.__ ._ - . = . - _ . - _ . . _ _ . - . .. _ ._,
i - 4 l i EPP/IP 1.1 I 11/30/83 i i
- l. CONTR0LLED ,
l ! c o P 'f N O - . l , l 't NOTIFICATIONS I l' 1 I. ! i :o
- OSC Meeting Number
- 119 Reviewed: m i November 22, 1983 i j l Approved: / 8,/.46 i
Sptior[/Sup4(ihtende Approved: > $_ e
.j ager, Nuclear Safety & Licensing Dept.
i I l i
't i
Issue 7 Rev. 2
. I 1
O 1 l l
l EPP/ Implementing Procedure EPP/IP 1.1 'l Notifications 9 TABLE OF C0krENTS
, , A. Purpose B. References C. Responsibilities D. Action Levels / Precautions E. Procedure F. Final Conditions G. Attachments l
9 l l l l . 9
EPP/ Implementing Procedure Notifications A. PURPOSE This procedure provides guidance for making initial and follow-up notifications during an emergency. B. REFERENCES
- 1.0 Beaver Valley Power Station Emergency Preparedness Plan 2.0 Commonwealth of Pennsylvania Disaster Operations Plan / Annex E.
3.0 State of Ohio Nuclear Power Plant Emergency Respons6 Plan. 4.0 West Virginia Radiological Emergency Plan for A Fixed Nuclear f, Facility. i i 5.0 Title 10 Code of Federal Regulations Part 50, Appendix E. 6.0 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of
)' Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
C. RESPONSIBILITIES 4 i The Communications and Records Coordinator is responsible to ensure that all required offsite notifications are completed within the proper time frame following the declaration of an emergency.
, D. ACTION LEVELS / PRECAUTIONS 1.0 This procedure is to be initiated upon any of the following conditions:
I l 1.1 An emergency condition has been declared at the Beaver Valley l Power Station as defined in the BVPS Emergency Preparedness l Plan. 1.2 An existing emergency condition has been reclassified to a
- higher emergency category, and/or, a significant I
deterioration in conditions has occurred.
! 1.3 The emergency situation has been corrected and the emergency j terminated, and recovery operations have begun.
2.0 To minimize the spread of rumors and undue public anxiety, the following precautions should be followed: 1 2.1 All initial and follow-up notifications shall be made with
' telephone as the primary means, with predesignated back-ups available in the event the telephone systems are inoperable.
O 1 Issue 7 Rev. 2'
EPP/Impicc;nting Proceduro EPP/IP 1.1 Notifications 2.2 No information shall be provided to any individual whose identity is unknown, or co any organization not listed on the Emergency Notification Call-List. Any calls of this nature should be relayed to DLC-PID. 2.3 No press releases on the incidenc shall be made prior to completion of all notifications, and will be made only by Duquesne Light Company Public Information Department. E. PROCEDURE 1.0 Upon declaration of an emergency, the Emergency Director shall: 1.1 Complete or approve the appropriate Initial Notification Form, Attachment 1, and the NRC Event Notification Form, Attachment 4. 1.2 Complete or authorize- completion of the Follcw-up Notification Form, Attachment 3. 1.3 For a General Emergency, approval of the Initial and Follow-up Notification Forms must be obtained from the Emergency / Recovery Manager. NOTE Ensure that the "EPP Switches" associated with the telephones O in the Control Room are positioned in the EPP position during emergency operations. 2.0 Notifications 2.1 Contact each organization or individual using the Emergency Notification Call-List, Attachment 2. 2.2 When party answers, read the introduction paragraph on the initial notification form and pause ta allow the individual to obtian his copy of the form. 2.3 Read the text of the notification, emphasizing the variable information. The initial notification must be kept simple and non-technical. Emphasize the coda word. ! 2.4 The Follow-up Notification Form should be updated as nscessary information changes. 2.5 If a party cannot be contacted in a reasonable period of time, bypass that party and proceed down the list. After other required notifications are complete, re-attempt to 2 Issue 7 Rev. 2
EPP/Implemsnting Procedure EPP/IP 1.1 Notifications g-'s contact any by-passed parties. Every effort must be made to (_,) contact the organizations listed in Attachment 2 and all attempts must be documented. 3.0 Follow-Up Notifications 3.1 The follow-up notification provides technical information to those qualified to ase the data and serves as a means to verify the authenticity of an emergency notification. The i code word also provides verification. 3.2 Relay the information on the Follow-up Notification Form, Attachment 3 and record caller's name in space provided on Emergency Notification Call-List. 2 3.3 Ensure all agencies initially contacted perform the verifications call. If not, contact agency again and request information be relayed to the appropriate individual who will - in turn perform the call-back. 4.0 Subsequent Notifications 4.1 If it becomes necessary to reclassify the emergency to a higher (or lower) classification, the Initial Notification Form is used and notifications are made in the same manner specified in Section E-2 of this procedure.
'( ) 4.2 The Follow-up Notification Form should be updated as the necessary information changes.
4.3 'Jhen the emergency situation at BVPS has been terminated, complete Attachment 5, Emergency Termination Form. l 5.0 Transfer of Responsibility 5.1 When TSC personnel are activated and have arrived on site,
; perform turnover per communicators optional checklist.
1 5.2 When informed by TSC Communications and Records Coordinator, transfer communication responsibilities from the Control Room to the Technical Support Center. I i j 1
! l O 3 Issue 7 Rev. 2 1
EPP/ Implementing Procedure EPP/IP 1.1
~
Notifications F. FINAL CONDITIONS 1.0 Use of this procedure shall be terminated when the emergency situation is corrected or when directed by the Emergency Director. G. ATTACHMENTS 1.0 Initial Notification Form 2.0 Emergency Notification Call-List 3.0 Follow-up Notification Form 4.0 NRC Event Notification Form 5.0 Emergency Termination Form O i i i t I 4 Issue 7 Rev. 2
EPP/Implemsnting Procedure EPP/IP 1.1 Notifications i i
. BEAVER VALLEY POWER STATION Attachment 1 (1 of 1)
Initial Notification Form
! INSTRUCTIONS
, 1. Read the following:
"This is the Beaver Valley Power Station. The following is a notification of an emergency. Record the information to follow on the l
Emergency Initial Notification Form: '
- 2. This is Title l (Name) (Emergency Organization Title) of Duquesne Light Company.
l 3. Emergency Class: UNUSUAL EVENT SITE EMERGENCY
; ALERT GENERAL EMERGENCY i
- 4. Radioactivity: Has Not Been Released Is Being Released
} Release Has Been Stopped Within Plant From Plant
- 5. Type of Release: Airborne Waterborne Surface Spill
- 6. Protective Actions: None Recommended Recommended as follows:
t
- 7. This notification was made at on .
(Time) (Date) f Return phone number is (412) 643-8000.
! 8. Please repeat back the information you have recorded to ensure accuracy. '
l l 9. Notify the appropriate individual (s) of your organization or agency.
- 10. CODE .
, FOR BCEMA/PEMA/HCES/CCDSA/USNRC ONLY: .I ji
- 11. Request the appropriate individual in your organization contact the f
station for additional information if deemed necessary. Approved: i Emergency Director / Emergency / Recovery Manager E il - 5 Issue 7 Rev. 2 i l
EPP/ Implementing Procedure EPP/IP 1.1 Notifications O INTENTIONALLY BIANK O O 6 Issue 7 Rev. 2 l 1
, j 4
EPP/ Implementing Procedure EPP/IP 1.1 Notifications EMERGENCY NOTIrlCATION CALL-LIST NOTE: Calls to the orrsite agencies listed on the sheet must be made in tho' sequence shown, as rapidly as possible following declaration or an emergency, and prior to any. notifications on remaining sheets, er one of the o rg a n iza t ions cannot' be reached, continue with the next, and then re-attempt to notify the bypassed party before moving to subsequcnt sheets. Organ iza t ion / lcsiividua l Eme roency Number A l te rna te Initial Contact / Veri ritat ion Contact lim.2
- 1. BEAVEN COUNTY EMERGENCY MANAGEMENT 775-0880 DLC Radio AGENCY (BCEMA) RELAY TO R. CHIODO
- 2. a. PEidNSYLVANIA EMERGENCY 717-783-8150 Relay through MANAGEMENT AGENCY ( PEMA) Duty BCEMA e Orricer (UNUSUAL EVENT AND GENERAL ONLY) i
- b. DER / BUREAU OF RADIATION 717-787-3479 White hotline PENNSYLVANIA (ALERT AND SITE AREA)
- 3. COLUNHlANA COUNTY DISASTER SERVICES 216-424-9725 216-424-7255 AGENCY (CCDSA) Dispatcher - RELAY TO M. LIPPIATT 1
Attachment 2 (1 OF 8) 7 Issue 7 Rev. 2
i EPP/ Implementing Procedure EPP/IP 1.1 Notifications EMERGENCY NOTIFICATION CALL-llg , O rg a ni za t i on/ I nd i vidua l Emeroency Number initial Contact / A l te rna te yerirication Contact Time
- 4. IIANCOCK COUNTY OFFICE OF EMERCENCY 304-564-4100 304-564-4068 SERVICES (HCCES) Dispatcher - RELAY TO A. KONDIK
- 5. OH10 DISASTER SERVICES ACENCY (ODSA) 614-889-7157 614-8A9-7150 (ALERT AND HIGHER)
- 6. US NUCLEAR REGULATORY COMMISSION OPX Red Hotline 1-202-951-0550 Duty Orricer 1-301-427-4056
- 7. Gene ra l Emeraency OnIV WEST VIRGINIA OFFICE OF 304-348-5380 1-301-348-6370 EMERGENCY SERVICES (WV0ES) tiqTE: Ti t above notifications must be comoleted within fifteen f151 minutes.
b Attachment 2 (2 OF 8) 0 Issue 7 Rev. 2 , O 9 9 't
EPP/ Implementing Procedure EPP/IP 1.1 Notifications EMERGENCY NOTiflCATION cat.l_-LIST O roan i za t lon/ I nd i v idua i {_me reency Number Ai te rna te Initial Contact / yerirication Contact Time
- 8. BVPS-1 SUPERINTENDENT PAX 5101 1-262-0798
- W. S. Lacey Bell 643-1258 __
a) The Station Superintendent notifies the Manager, Nuclear Operations PAX 5202 T. D. JONES Bell 643-5255 1-741-5890
- I b) The Manager, Nuc tecr Operations r.otifies the V.P. Nuclea r Division PAX 5255 J. J. CAREY Bell 643-5255 1-266-7631
- 9. BVPS-1 OPERATIONS SUPERVISOR PAX 5104 774-1734
- L. C. Schad ,
Bell 643-8748
- 10. SHIPPINGPORT ATOMIC POWER STATION PAX 2102 6-2110 Bell 643-4601 11.'BVPS UNIT 2 CONSTRUCTION Bell 643-8800 643-8801 R. Swiderski (Backshirts k weckends DLC-CDN or SB I-Cua rd ) DLC Radio Attachment 2 (3 Of 8) 9 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP 1.1 Notifications EMERGENCY NOTiflCATION CALL-LIST O rga n i za tipn/ i nd iv idua l Eme roency Number 611grnate Initial Contact / Veri ficatjon Contact lime _ .
- 12. OLC PUBLIC INFORMATIOM DEPARTMENT (Notify one)
J. D. F rank PAX 6059 1-366-7392
- D. O. Messner PAX 6060 1-486-8708
- F. Sk l eda r PAX 6058 1-321-8436 J. M. Sasala PAX 6063 1-864-0433 . . _ .
J. F. Grogan PAX 6066 1-362-9704 __
- 13. BRUCE MANSFIELD POWER STATION 643-1642 643-5000 (Normal Working Hours) Ext. 2300 (Ops. Shirt Clerk 643-5851 off-shirt, weekends, holidays)
- 14. BEEPER ACTIVATION - (Calls should be made several times during Alert notifications),
a) Deaver County 843-9220 843-5600 Request operator to tone out / ? b) Pittsburgh Area 1-464- ? (Numbers 7 ava ilable f rom Shi f t Supervisor)
- Indicates personnel with beepers Attachment 2 (4 OF 8) 10 1.ssue 7 Rev. 2 S 9 . O
( [a-~') .. EPP/ Implementing Procedure E?P/IP 1.1 Notifications EMERCENCY NOTIFICATION CALL-LIST t organization / Individual Eme rgency NumbeE Initial Contact / i A l t e rna tg Verification contact Time NOTE: The rolf owing organizations are notified oD1Y for the accidents noted in parenthesis l next to their name.
- 15. U.S. COAST CUARD MARINE SAFETY 1-644-5808 800-424 8802 (ALL OFFSITE RELEASES, ACTUAL GR IMMINENT). 1-281-3311
- 16. U.S. CORPS OF ENGINEERS (LIQUID RELEASE)
NEW CUMBERLAND DAM (downriver) 614-537-2571 nelay Through MONTGONERY DAM (upriver) 643-8400 BCEMA g
- 17. NIDLAND WATER PLANT (LIQUID RELEASE) 643-4920 643-4735 -
Mr. John Uccellini (8:00 - 4:00 daily)
- 18. EAST LIVERPOOL WATER Pl. ANT (LIQUID)
^
Mr. Huddleston 216-385-5050 216-385-8812
- 19. CHESTER, W. VA. WATER PLANT (LIQUID)
(Notify via HCOES) 304-564-3311 DLC Radio
- 20. WESTINGHOUSE ATDMIC POWER DIVISION ( Alert and Higher)
- a. Mr. Joe Jenkins PAX 5219 1-831-4758 BELL 643-5018 Attachment 2 (5 OF 8) 11 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP 1.1 Notifications EMERGENCY NOTIFICATION CALL-LIST O rga n i za t ion / i nd i vi dua l Emetgency Number loitial Contact / ALL2rnate Verification Contact limq_
- b. Pr. Gil Kubanscer. (Mg r. ) 1-256-3140 1-751-79G3
- 21. INPO (ALERT AND HIGHER) 404-953-0904 N/A 22., NATIONAL WEATHER SERVICE 1-644-26B2 N/A ___,
( SITE AND GENERAL EMERGENCIES)
- 23. AMERICAN NUCLEAR INSURERS (ALERT AND HIGHER)
Fire /All risk emergencies 800-243-3177 800-243-3173 Radiological nuclea r emergencies 203-677-7305 k
- 24. PENNSYLVANIA POWER COMPANY 643-5000 (24 hours) .)
Shif t Supervisor Of f ice Ext. 2577
- 25. WEST VIRGINIA DEPT. Dr.plEALTH/ 304-348-0691 304-348-3526 _ _ _
RADIATION PROTECTION (NOT NECESSARY TO CALL BUT TifEY ARE ALL AUTHORIZED 10 RECElVE INF0PMATION) Attachment 2 (6 Of 8) 12 Issue 7 Rev. 2 4 O O O
EPP/Impicmenting Procedure EPP/IP 1.1 Notifications EMERGENCY NOTIFICATION CALL-LIST (cont'd) Attachment 2 (7 of 8) ,. The following organizations are not normally notified directly in the event I of an emergency at BVPS, but may be contacted if particular emergency conditions warrant. NOTE: The phone numbers listed below are updated on the annual review. More up-to-date numbers are available in the monthly and quarterly emergency telephone number checklists, and are available in the Control Room. Pennsylvania State Police (Lt. J. Render) 775-5991 I Pennsylvania State Police (Chippewa Barracks) 843-5100 DLC Radio Mobile Pipeline Co. 201-754-3546 Ashland Pipeline Co. 800-354-8850 Freedom Station 1-774-2020 1-216-866-3588 Buckeye Pipeline Co. 1-215-967-3131 i DOE RAP /IRAP Bookhaven Area Office 516-282-2200 516-282-3424 Medic-Rescue Ambulance Service 728-3620 775-0880 Community Ambulance 1-728-6612 775-0880 Sh'ippingport Fire Department 775-0880 Relay through BCEMA Aliquippa Hospital Emergency Room ' 1-857-1274 Relay through BCEMA Beaver County Medical Center 728-7110 Relay through BCEMA Presbyterian University Hospital Emergency Room 1-647-3333 Radiation Emergency Response Program Dr. Neil Wald-Dept. of Radiation Medicine 1-647-3495 1-683-0779 Dr. Albert Spritzer 1-372-3590 1-372-6511 McIntosh Hemphill (E. W. Bliss) Mr. Peterson 643-8602 Conrail Division Supervisor 1-928-7206 i j O 13 Issue 7 Rev. 2
EPP/Impleinenting Procedore EPP/IP 1.1 Notifications Attachment 2 (8 of 8) O Pittsburgh and Lake Erie Chief Dispatcher 261-0650 375-5507 US Weather Bureau-Pittsburgh Air Polution Meteorologist Forecast Office (24-hr) 1-644-2882 1-644-2888 Coraopolis Office 1-644-2891 O l i l l ) 14 Issue 7 Rev. 2
EPP/Implemsnting Procedure EPP/IP 1.1 Notifications BEAVER VALLEY POWER STATION D Follow-Up Notification Form Attachment 3 (1 of 6) The following data represent the most current and most accurate information, projections, and/or prognosis available at the time this
, notification was made.
TIME: Date: By: . Return phone number: 412/643-8000
- 1. Affected Facility: Beaver Valley Power Station Unusual Event / Alert
- 2. Site Area / General Emergency Declared at: on:
Time Date
- 3. Cause of Emergency
- 4. Current Plant Status:
Conditions: Stable / Unstable Reactor: Shutdown /At Power Equipment Damage: Minor / Major Cooling: Normal Cooldown/ Safety Injection Cooldown/NA O 5. Radioactivity Release (If Applicable) Type of Release: Liquid / Gaseous Release to: Ohio River / Atmosphere Time Start: ___ Release Stopped: Yes/No/NA at: Wind Speed (mph) Wind Direction From N/NE/NW/S/SE/SW/E/W Stability Class ABC/D/E/FG
- 6. Projected Dose or Actual Dose Rate:
l, Projected Dose (REM) Actual Dose Rate (REM /KR) Site Boundary 1 j 5-mile radins 10-mile radius I 15 Issue 7 Rev. 2 ' l _ . _ . . . ._ _. - _ . .__ _ _ . . - -
EPP/Implem:nting Procedure EPP/IP 1.1 Notifications Follow-Up Notification Form (Cont'd) At tach.nent 3 (2 of 6)
- 7. Recommended Protective Action: No proter *ive action necessary/_ _ '
Shelter within mile radius / Evacuate within mile radius Approved: Emergency Director / Emergency / Recovery Manager t 9 l l 4 16 Issue 7 Rev. 2
EPP/IP Implementing Procsdura EPP/IP 1.1 A Q C*A vlv Q Notifications N6vl 3 i BEAVER VALLEY PO?ER STATICE Attachment 3 (3 of 6) , Follow-Up Notification ! l DATE TIME TYPE & ACCIDENT VCT GT S/G MSL MIA IKDr I4CA N IOCAAC ESAR BASIS LIQUID RELEASE Radioactive Effluent Release: Yes No Type of Release Liquid M=-=
! Release to Ohio River /ALMd-e -
Time Start aslease Stopped Potential for Release Yes So _ .- _. Additialal Release Yes No Meteorological Data: 35' WS MPH 500' 50
- 35' WD NNE/NW/5/SE/SW/EN . . . - .
,.! Stability Class ABC/D/E/M
! Precipitation . , , ,
DOSE PNUECfICN ME"I!OD: PROCEDORE t
; PAGE ;
O e l
*17 Issue 7 Rev. 2 l 1
EPP/IP Implemanting Procedure EPP/IP 1.1
%tificaeions ABOSHIERIC RELEASE Attachment 3 (4 of 6)
CATI: TIME Monitcr CPM CD1 Release Rate Ci/sec RELEASE IXJRATICN: ACIUAL HRS PRCUECTID HRS PROJDCTED DOSE OR ACICAL IDSE RATE: Affected Area Projected Dose Sectors / Radius WB (RE4)/ 'Ihyroid (RD1) EAB , ACI9AL DOSE RTCE Monitcring Pt. Sector Miles trR/HR CPM mRcm/HR @ 'id EAB . , , _ _ _ _ . . REDMMENDED PROTECTIVE ACTICN: APPROVAL NO EQu;gnVE /CfION NECESSARY/varm;nVE ACTION -_
, ._. SHELTER (Sector / Distance) _. ___. _,
y- - - - - - _ .. .-. EVACUATE (Sector / Distance) O'IHER O 18 Issue 7 Rev. 2
EPP/IP Implementing Procsdure EPP/IP 1.L' Noeifications
< LIQUID >
BEAVER VALLEY PG.T.R S'".ATIOT Follow-Up Notification Attachment 3 (5 of 6: DATE TIME TYPE OF ACCIDENT , Vt.T CST S/G MSL EHA III7f IOCAAl IDCAAO ESAR BASIS LIQUID FILEASE
- FMirw tive Effluent Release: Yes /No L
Type of Release Liquid /mmis Release to Ohio River /Atmoschere Time Start Release Stopped Potential for Release Yes /No Additional Release , Yes /No Meteorological Data: ,
, ._ _ 35' liS M1H 500' im
- 35' WD N/NE/NW/S /SE/SW/ EAT .
~
Stability class ABC/D/E/EU . . . - -
, pitah _ , _ __ _ _ ,, . DOSE PinTECTICE EDOD: .i .
PIOCEDURE j ATTPCD1ENT _! PAGE
- O J I
l l l 19 Issue 7 Rev. 2 i -
( l EPP/IP Implementing Procsdure EPP/IP 1.1 Notifications LIQUID RELEASE Attachment 3 (6 of 6) mm - O tcIUAL PH17DCTED TIME OF RELEASE START RELEASE DURATION hrs hrs RELEASE FIIH gpu gpm IUIAL ACTIVITY LCi/cc I DILUTICN E7CIOR PADIONUCLIDES IN PILEASE - Attad.nent NRC MPC FRACIICN _ _ _ _ _ . . __ _ EPA MFC FRACTICN RIIDNENDED PRDIDCITJE ACTION: APPFCVAL 20 Piem fiVE ICfION NWMARY/PROTE. TIVE ACTICN . - . - . . .- - . . . I IF RELEASE INDICATES AN ALERT IEERGENCY, NOIIEY M MIDIAND WATER l TREA3NENT PIANT AND RDDEE20 TIE PIANT STOP INTAKE FROM HIE OHIO
; R1vER wrII. eDTnm sY mR/aRe. -
i 1 l i O
' 20 Issue 7 Rev. 2
.. 4 EPP/ Implementing Procedura . EPP/IP 1.1 > Nacifications AttachmTnt 4 (1 of 1)
M OF NonTIOTICN ETDT TDS: MTT : N1C RZCICNs ! OATE: / / CAI.I. BACE NUMBER (412) 643-8002 m CE CRCANUATION DUQUESNE 1.ICEI-EEAVE1 YA11ET UNIT #1 g e5 NAME AND TITIZ: Evtvr c AssIrtcAT109/ncutRID NOTIFICAftoNs 1 sonIICAIIod or WUsuA1. EVI:rr thusnt:Ano:: Ivr.:rr ,
. . 151 NO. .
M ..
* * * ~
'.- .FETSICE SEC::1IIT/SATEGUA323 SITE AAZA DmNT .
. . * ~
- IT '
CDrZ2A1. C2RCINCT . . ,,_,j. _ .. ,,. (IVF5 security supervisor) ,
- CNFIJJnrc RZI.ZAsg 50.72 (NO3-CG1CZ3CT)
***'"~,,*_*',, .g ,CAS *
. 4" D ,.
Pont RIACToR EvtNTa 1
.J N PRICE TO E7ZNIT PCWER AT TDS OF RZFCETt RZ3C5NTINICEMED II?? I3ITIATING SIGNALT
-.ATETT DUICTION C1 ECCST IN CIATI3C 5%CNAT.?
.3F AC=ATICN7
.CD ACTICN STATEMENrf
~
.vNT DiscRIPTION/cAnstr ] (3e brief, but concise) % ,
^
e a :a #~ RAD 1DACTITE . "2I. EASE 37 ($ource, actual asesured dosage ia M er mE/br) i r l
~
l '.%
- _-
2TIZE MAJOR F1081.2Mst - '
'txt#ED ACTIONS / priss m f ME.s? 1 1
1 Ioc actsct on nnmc. mirtta av t.tctxstz, I sTAIZ(S) IDCE h i l wicEst mAMz or Dt.IT orrICra c tzQtts? DUTT orrICut :o xEFIAT BAcr. Ixrcana:IcN To Assuat ACCuaACT 21 1ssue 7 Rev. 2 FtEAst cA11 sAct vtTu Asv enANCEs et AnetTrenAI. reren:unew
EPP/ Implementing Procedure EPP/IP 1.1 Notifications I I INTENTIONAL!.Y BLEK G' i O 22 Issue 7 Rev. 2
EPP/Implem:nting Procedura EPP/IP 1.1 Notifications s BEAVER VALLEY POWER STATION 7b
\
Emergency Termination Form Attachment 5 (1 of 1)
"This is Beaver Valley Power Station. This notification is to inform you that the emergency situation at Beaver Valley Power Station has been terminated at hrs. Please complete all applicable procedures before terminating".
- 1) Beaver County Emergency Management Agency 775-0880 Person Contacted Time
- 2) Pennsylvania Emergency Management Agency 717-783-8150 Person Contacted Time
- 3) Columbiana County Disaster Services Agency 216-424-9725 Person Contacted Time
- 4) Hancock County Office of Emergency Services 304-564-3311 Person Contacted Time
- 5) Ohio Disaster Services Agency 614-8B9-7157 Person Contacted Time
- 6) West Virginia Office of Emergency Services 304-348-5380 (General Emergency Level)
,7-~g) %J Person Contacted Time
- 7) U.S. Nuclear Regulatory Commission NRC/ ENS Person Contacted Time i
- (,,
23 Issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP 1.1 , Notifications O INTENTIONALLY BLANK O 24 Issue 7 Rev. 2
i i i
- EPP/IP 1.3
- 11/30/83 i
I CONTROLLED COPY NO. 0 = l i TURNOVER STATUS CHECKLIST l I l $ t I Lo a 4 OSC Meeting Number: 119
, Reviewed: 41 I Novegrber 22, 1983
//
j Approved: hr il ftatilon/Superintende Approved: Idla . M ger, Nuclear Safety & Licensing Dept. l i
- j
. :j
.i i-4 Issue 7 Rev. 2 i! iO f f f
- v. .m---, - , . - ,y,.c, .---.w., , . , --> - . . - . - , . , . . -m ,mm... --
,--,r. . . . , , ...,_--,..--..--...--.--_-.~,----.....e
EPP/ Implementing Procedure EPP/IP 1.3 Turnover Status Checklist O_7-TABLE OF CONTENTS A. ; Purpose B. References C. Responsibilities D. Action Level / Precautions E. Procedures F. Final Conditions G. Attachments 1 0 i l ll 1 l l 0
i EPP/ Implementing Procedure Turnover Status Checklist A. Purpose ' This procedure is a turnover status checklist to be used by the Emergency Director / Emergency Recovery Manager prior to assuming the j responsibility of the Emergency. B. References None i C. Responsibilities The Emergency Director and/or the Emergency Recovery Manager is 1 responsible for completing this checklist.
- i D. Action Levels / Precautions 1.0 Action Levels
! 1.1 An Alert or greater emergency condition, requiring TSC and/or EOF activation has been declared at the Beaver Valley Power Stations.
2.0 Precautions f\
\~# 2.1 The turnover status checklist provides only general type emergency information. The Shift Supervisor / Emergency Director should provide any other important specific information necessary to ensure a comple'te turnover.
2.2 Upon notification of an Unusual Event or Alert Emergency, the Emergency Director shall proceed to the Control Room when appropriate and complete the turnover status checklist with the on-duty NSS. 2.3 Upon notification of a Site Area or General Emergency, the Emergency / Recovery Manager shall proceed to the TSC when appropriate and complete the turnover status checklist with the Emergency Director. E t i l i-
\'
1 Issue 7 Rev. 2 1
, - - .- , . _ - , - - , , - . - ~ - - , -
EPP/Impicm:nting Procedurs EPP/IP 1.3 Turnover Status Checklist E. Procedure
- 1. EPP Status - (Classification) Unusual Event Alert 9
Site Area Emergency General Emergency Time Check Watch Reset
- 2. Have notifications been given? when?
DLC Personnel NRC Offsite Areas
- 3. General Chronology of events TLTZ EVENT O
TSC ACTIVATED EOF ACTIVATED i 2 Issue 7 Rev. 2
i EPP/ Implementing Procedure EPP/IP 1.3 4 Turnover Status Checklist
- 4. Protective Actions 1
I
- Unit Assembly yes no When Site evacuation yes no When Offsite evacuation yes no When Sheltering yes no When i Accountability yes no When Site closed to e
Visitors yes no When
- 5. Plant radiation status (Chronology)
!- TIME EVENT l
d i i P
- 6. Latest unit survey results: Time Status e
'l i
- 7. Latest site survey results: Time Status i ;
l l 1 l l
'l N
3 Issue 7 Rev. 2 ') < l i i ?
,,, _ - . - . . . , - . . . . . . . . . _ - - . _ . , , - , - , . , - , , . , . . nn,. -. - ,, , , , - - . , ,
EPP/Implem:nting Procedure EPP/IP 1.3 Turnover Status Checklist
- 8. Latest off-site radiacion survey,resu_1ts:
TIME LOCATION RESULTS
- 9. Dose Projection Information:
Time Results O f . 10. Statuc of Off-Site Notification (Copy) t Agency Time Individual Contacted Comments l BCEMA ? PEMA CCDSA 1 l HCOES I 1 4 Issue 7 Rev. 2
__7... EPP/Implemanting Procedure EPP/IP 1.3 Turnover Status Checklist ,t .i l' 11. Plant Status: _ ._ ., J _l j
- Accident / Emergency Damaged System
! ESF System Availability i i 1
, Ventilation System 4
j I, System / Rad Monitor Unavailability i
- t
- i
<t l
- 12. Injured or contaminated person Ambulance
} .
Name Employer Status: Hospital ~-
- a. -
t :
.I ll t
t i 1 4 . Ii ii !l !l i, V.1 ii a i lfM J.
- 5. Issue 7 Rev. 2 l l
l
, _ _ _ , . . . , . . . , - _. , __ . , - . _ _ , - . . . . . - _ _ - . . _ . _ . - - . . _ . . . . _ ~ . ~ -
EPP/Implem:nting Proc: dura CPF/IP 1.3 Turnover Status Checklist
- 13. Accountability:
Accountability taken (Time) Results: BV1 BV2 CAPS Assembly Areas Occupied Status
- 14. Call out status:
Operations e Radeon Maintenance Mech. Elect. I L C. Test Crew Chemistry Emergency Organization TSC _ EOF y 6 Issue 7 Rev. 2
~
, e .
EPP/Implemanting Procedure EPP/IP 1.3 Turnover Status Checklist
- 15. Emergency News Center, activated: :n Charge:
- 16. Potential for plant degradation:
4
- 17. Potential for Off-Site release of radioactivity:
i Airborne Water i i i i i i D 7 Issue 7 Rev. 2-
EPP/Implcm:nting Procedure EPP/IP 1.3 Turnover Status Checklist -
- 1. 8 . Planed Activities (Next 6 trs.):
O k l Six to Twelve Hrs.: O i f e T i t 0 issue 7 Rev. 2
EPP/ Implementing Procedure EPP/IP 1.3 r Turnover Status Checklist F. Final Conditions 1.0 This procedure will be terminated at the direction of the Emergency Director of Emergency / Recovery Manager or upon de-escalation of the emergency. G. Attachments None I I l 1 i i~ 1 l l lo l i 4 1 I i i i f 9 Issue 7 Rev. 2
EPP/Implementind Procedure EPP/IP 1.3 Turnover Status Checklist
~
G 1 ) e INTENTIONALLY BLANK O 10 Issue 7 Rev. 2 \.
e' O . _ _ _ . , . . - . . EPP/IP 1.5 11/30/83 00gTROM ' b COPY NO EMERGENCY SUPPORT CENTERS (OSC & ROCl ACTIVATION, OPERATION AND DEACTIVATION l 4 i i
'O OSC Meeting Number: 119 Reviewed: m / Novemyel- 22, 1983 '
'i Approved: b '/ afiof' Superintend Approved: Ia - _ ager,' Nuclear Safety & Licensing Dept. l \ Issue 7 Rev. 2 O
e -d EPP/ Implementing Proceduge EPP/IP 1.5 Emergency Support Centers (OSC & ROC) Activation, Operation and Deactivation O TABII 0F CONTENTS J A. Purpose B. References C. Responsibilities D. Action Level / Precautions E. Procedures
; F. Final Conditions G. Attachments O ~
l; 1 0
- - * ^ - - ~
EPP/ Implementing Procedure i Emergency Support Centers (OSC & ROC) O Activation, Operation and Deactivation A. Purpose This procedure provides instructions for the Activation, Operation and Deactivation of the Operations Support Center and the Radcon Operations Center. B. References 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures. 2.0 Beaver Valley Power Station Operating Manual. 3.0 Title 10 Code of Federal Regulations Part 50, Appandix E
,f 4.0 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."
C. Responsibilities 1.0 Tha Operations Support Center Coordinator is responsible for the activation, operation and deactivation process for the Operations s Support Center as outlined in this procedure.
~
2.0 The Radiological Controls Coordinator is responsible for the activation, operation and deactivation of the Radiation Operations Center. i
, D. Action Levels / Precautions
,i 1.0 Action Levels i
i 1.1 An emergency condition corresponding to an Alert or higher emergency classification, has been declared at Beaver Valley Power Station as provided in the BVPS Emergency Preparedness c Plan. l 2.0 Precautions 2.1 Operations Support Center (OSC) i 2.1.1 Location - The Operations Support Center (OSC) is located in -the Process Instrumentation and Rod Position Instrumentation Area located below the Control Room. 2.1.2 Purpose - The OSC provides a location for emergency and operation personnel to assemble in an
\" #
1 Issue 7 Rev. 2
)
l
. , _ _m
e EPP/Impicm:nting Proc: dura EPP/IP 1.5 Emergency Support Centers (OSC & ROC) Activation Operation end Deactivation emergency. This minimizes the congregation of excess personnel in the Control Poem. lh 2.1.3 The Operetians fuppor't Center is equipped with a variety of communication s's; f ems including: Bell and PAX 'linas,<'Pcge Party and Station Alarm Systems, both DIC Radio frequencies and the Operations and Radeon Ecadset Circuits. 1.1.4 An Ope.aticas Support 'Jonter Coordinator has been assigned to direct this center. This individual will report to the Emergency Director ,via the Maintenance Coordinator. Included in the OSC Coordinators functions are: Direction of activities of the in plant supplemental emargency team. assignment of personnel from the onsite pool of available pcreons in response to requests "from tha' Emergency Director and the maintaining of accountability of personnel assigned to the OSC. 2.2 E4dcon Operations Center 'sRO' C) 2.2.1 Location - The Radiation ContrJ1 Foreman's Office is designated as the ECC. The physical location is on the, Turbine Deck (735'). Monitoring equipment, survey rccords and other material to support Radcon activities are available in the ROC. 2.2.2 Purpose - The ROC is designated as the central location for coordinating the activities of Radeon technicians within the station. 2.2.3 The ROC has the following communication capabilities: Bell and PAX lines, Page Party and Station Alarm systems, the NRC/HPN hotline and the ! Radeon headset circtjit. 2.2.4 The- Radiological Controls Coordinator will , coordinate the activities of Radeon personnel and , the ROC from che Technical Support Center. I k 2 1ssue 7 Rev. 2 f' t !-
i e EPP/Implemanting Procsdurs EPP/IP 1.5 Emergency Support Centers (OSC & ROC) Activation, Operation and Deactivation
-( E. Procedure 1.0 Activation 1.1 Upon occurrence of an off-normal or an emergency condition at the facility which has been classified as an Alert, Site Area Emergency or General Emergency the Emergency Director shall direct activation of the OSC and ROC.
1.1.1 The OSC shall be activated according to the normal i i emergency response call-out procedure. l 1.1.2 The ROC shall be activated upon notification by the
,3 Control Room to the Radcon Foreman that an l emergency condition exists.
2.0 Operation 2.1 Operations Support Center 2.1.1 The OSC Coordinator, as requested by the Emergency Director, shall direct the activities of emergency teams that have been formed to augment the Shift Emergency Squad. l 2.1.2 Accountability of personnel in the OSC and those deployed in emergency teams will be. the responsibility of the OSC Coordinator. 2.1.3 All communications and any records generated during activation will follow the guidance outlined in the BVPS Implementing Procedures, i 2.2 Radeon Operations Center (R')C) I 2.2.1 Under the direction of the Radiological Controls Coordinator the ROC provides onsite radiation control personnel for monitoring teams. This function will be consistent with maintaining
, appropriate radiation controls in-plant.
2.2.2 Accountability for personnel assigned to the ROC and monitoring teams will be the responsibility of the Radiological Controls Coordinator.
! 2.2.3 All records and communications shall be conducted consistent with the BVPS Implementing Procedures.
4 3 Issue 7 Rev. 2
C EPP/Implcc:nting Proccduro EPP/IP 1.5 Emergency Support Centers (OSC & ROC) Activation, Operation and Deactivation 3.0 Deactivation 3.1 Operations Support Center 3.1.1 The Emergency Director via the Maintenance Coordinatcr, will inform the OSC when deactivation shall occur. This decision will be based on plant conditions, monitor readings or accident terminaticn. 3.1.2 All records generated during operation shall be forwarded to the Communications and Records Coordinator upon deactivation. 3.1.3 Any remaining responsibilities will be transferred to the TEC. Upon deactivation de-energize and restore emergency equipment and supplies to preactivation conditions. j 3.2 Radeon Operations CE.nter 'POC) - 1 3.2.1 The Radiological Controls Coordinator under the direction of the Emergency Dire . tor will order the ROC deactivated. 3.2.2 All record generated during operation shall be forwarded to the Communications Coordinator upon deactivation. and Records lh 3.2.3 Any remaining responsibilities will be transferred to'the TSC. Upon deactivation de-energize and restore emergency equipment and supplies to proactivation conditions. I The Emergency News Center (ENC) is discussed in EPP/IP 9.1. f F. Final Conditions 1.0 This procedure shall be terminated upon direction of the Emergency Director. Plant conditions, monitor readings or termination of the accident will help determine when close-out occurs. ) l G. Attachments' l i NONE 4 _ Issue 7 Rev. 2 g
1 e-l EPP/IP 3.3 ~ ~ ' ' " ~ ~ ' i 11/30/83' 00MTR0 M " C0P.g. 0. 3 EMERGENCY CONTA?!INATION CONTROL k l
.O OSC ?!eeting Number: 119 ! Reviewed: _ l Novembeg 22, 1983 f Approved: ff// MM
{ pat' ion /SIfperintend { Approved: w F Man [e'r, Nuclear Safety & Licenaing Dept.
}
i Issue 7 Rev. 2 1 O . u 1
E??/ Implementing P-ocedure EPP/IP 3.3 ~ Emergency Contamination Control O TABLE OF CONTENTS A. Purpose B. References C. Responsiblilt les D. Action Levels / Precautions E. Procedure F. Final Conditions 1 G. Attachments 1 i O 1 I i l, 9
l ! EPP/ Implementing Procedure l Emergency Contamination Control j A. Purcose This procedure provides general guidance to the TCS staff to supplement the guidance contained in the Radiation Control Manual (RCM) and/or the Radiation Protection Procedures. B. References 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures. 2.0 Buaver Valley Power Station Radiation Control Manual. 3.0 Title 10 Ccde of Federal Regulations, Part 20 and Part 50. 4.0 NCRP Report No. 65, " Management of Persons Accidentally Contained with Radiocu;11 des". 5.0 ICRP Publication 28, "The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers". 6.0 NUREG - 0654/ FEMA-REP - 1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants". C. Responsibiliti.g The Radiological Controls Coordinator is responsible to implcment this procedure when necessary. D. Action Levels / Precautions 1.0 Action Levels 1.1 An emergency condition has been declared at the Beaver Valley j Power Station as procided in the BVPS Emergency Preparedness Plan. 1.2 As a result of the emergency condition, significantly I abnormal contamination levels are noted. i 2.0 Precautions 2.1 The Beaver, Valley Power Station Radiation Control Manual
+
(RCM) contains provisions governing the control of l contamination. Chapter 3 of the RCM contains procedures that
, implement the RCM provisions. The requirements and guidelines of these documents shall apply to contamination control during emergency conditions except as specifically provided in this EPP/IP, the BVPS Emergency Preparedness l Plan, and/or by direction of the Radiological Controls
[~'\ Coordinator / Emergency Director. 1 Issue 7 Rev. 2 L _ _ ______________________________ -
EPP/Impl:m2nting Procedura EPf/IP 3.3 Emergency Contamination Control 2.2 Skin contamination less than one (1) rad per hour is unlikely to be immediately life-threatening, and therefore skin decontamination efforts should never take precedence over necessary first aid. 2.3 If alpha activity is suspectad, a random select $on of swipes (and air semples) should be counted for alpha activity. The sine of the random selection should be decreas3d or increased on the basis of the initial alpha count results and/or the results of the reactor coolant activity analysis. E. Procedure 1.0 Contamination Control
. 1.1 It may become necessary to extend the boundaries of the I
controlled area. Appropriate access control and associated contamination control measures shall be established for any area in which contamination exists at levels higher thms that specified for a clean area in the ECM. 1.2 Personnel and equipment monitoring and release procedures and criteria shall remain in force to the extent possible. There may be exceptions aoplicable to emergency conditions, as follows: 1.2.1 If background dose rates at normal monitoring locations preclude detection of levels of contamination equivalent to the clean limit, monitoring shall be moved back to a location where this can be done. However, if significsnt levels of contamination exist, it may be appropriate to perform a gross screening at the exit of grossly contaminated area, to be followed by a more completa monitoring at a more suitable location. 1.2.2 If dose rates within the contaminated area (or controlled area) warrant an immediato evacuation, personnel monitoring shh11 not be required prior to evacuation. If possible, personnel exiting such areas should remove any clothing thought to be contaminated, or don clean coveralls to minimize the spread of potential contamination, pending subsequent monitoring. In this case, appropriate i monitoring should be performed at the designated assembly area. 1.2.3 Contamination limits for release of personnel, equipment, and areas specified in the RCM shall remain in effect to the maximum extent possible. The Radiological Controls Coordinator will determine when a change in contamination limits is applicable and will establish appropriate revised limits. However, under site evacuation conditions, lh 2 Issue 7 Rev. 2
9 EPP/Implemtnting Procedure EPP/IP 3.3 i 1 Emergency Contamination Control l t'" decontaminati,on _is ,normally mandatory if the (,,g) contamination exceeds 1800 pC1/100 ca8 . 1.3 The conditions under which a Site evacuation would be initiated might involve significant releases with resultanc
)
contamination of environmental surfaces offsite. Under these i co'nditions , delaying site evacuation to monitor and/or I decontaminate personnel or vehicles would be inconsistent ! with maintaining exposurar as low as reasonably achievable, ) and may be superfluous in light of the potential for re-contacination offsite. The following procedures should be used: 1.3.1 Personnel should be directed to the remove assembly ! area for monitoring via the upwind route. Radcon
- shall monitor personnel on the basis of a screening process to identify contaminants in excess of 1800 pCi/100 cm2 , Personnel monitoring should batically consist of checking hands, feet, and the face with an E140/HP210 or equivalent survey instrument.
- 1. Personnel identified as contaminated should be segregated to an area for eventual decontamination.
! 2. Documentation of the extent and magnitude of
'gs the individual's contamination will be performed after the initial segregation phase of the group monitoring. 1.3.2 If the assembly area is within sectors from which
! the population is being evacuated, the Emergency Director, in cooperation with DLC management and State and county agencies shall designate an assembly area at which personnel monitoring will be
, performed. In this event, personnel and vehicles j will be monitored the same as members of the j general public as provided in the emergency plans
, of the affected jurisdictions.
! 1.4 For rescue efforts in which there is a potential for the l imminent death of the victim, and for which the magnitude of l radiological conditions in the affected area are generally l known, an emergency squad member (s) should proceed to the scene without protective clothing to access the situation and - render first aid. Other members of the Emergency Squad should don appropriate protective clothing and proceed to the area to assist. The initial emergency squal member (s) should ' leave the area and be monitored and/or decontaminated as soon as possible, i 1.5 For fire-fighting efforts, normal fire-fighting gear (holments, coats, boots, gloves, etc) may take the place of 1 J 3 Issue 7 Rev. 2
r- , ( . EPP/Implem:n:ing Proc: dure EPP/IP 3.3 Emergency Cottamination Control protective clothing. This apparel is as likely to provide protection from contaminated water spray. 2.0 Decontamination 2.1 Personnel decontamination shall be performed as provided in the RCM and in Radiation Protection Procedures. - 2.2 Contaminated / injured personnel should be decontaminated prior j to transfer to the hospital, if possible, and if compatible with the extent of the injuries. Even a superficial initial decontamination to remove the loose centamination will help minimize the contamination of ambul.3nces and hospital facilitics and personnel. Refer to EPP/IP-5.2, " Handling of Contaminated / Irradiated Personnel Injuries". , I 2.3 Most cases of skin decontamination with radioactive materials can be decontaminated by Radc9n personnel using methods established in the Radiation Protection Procedures. Refer to RCM Chp No. 5 KE0P-3.1 " Personnel Decontamination - Serious or persistent Contamination". If the contamination has
. enterad wounds or body openings, medical as sistance should be sought. The urgency of auch treatment will depend on the doso rate attributable to the contamination. Except in cases of high-levei contamination, over about one rad per hour including beta radiation, as measured with an ion-chamber instrument (4-7 mg/cm' window), there is no urgency to complete skin decontamination. If the skin contamination is the primary health hazard or if persistent contamination lh + remains after decontamination efforts, Dr. Wald and Dr.
Spritzer should be consulted, and the individual transferred j to the Presbyterian-University Hospital for evaluation and treatment, at the direction of Drs. Wald and Spritzer. Refer t to EPP/IP-5.4. 2.4 Decontamination of persons with significant internal f contamination shall be referred to medical personnel at the l Presbyterian-Univert ity Hospital or the RERP program for
! evaluation and treatment. In the event of a significant uptake of radiciodine, potassitm idode may be administered in accordance with EPP/JP-3.4, " Emergency Respiratory Protection".
F. Final Conditions
; The use of this procedure shall be terminated when monitoring results , indicate contamination control is not r.ecessary' and all applicable ; documentation has been completed.
G. Attachments 1.0 None 4 Issue 7 Rev. 2 w J}}