ML20212N267
| ML20212N267 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/03/1986 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML20212N265 | List: |
| References | |
| PROC-860703-01, NUDOCS 8608280151 | |
| Download: ML20212N267 (591) | |
Text
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CHANGE LIST DATE 7/16/86 Procedure Procedure Title Rev. Date
"* # Effective EPIP-04 ALERT. SITE AREA AND GENERAL 11 7/16/86 EMERGENCY IMPLEMENTING ACTIONS
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Procedure Procedure Title Rev. Date Number Effective EPIP-02 DERGENCY CLASSIFICATION 5 7/9/86 EPIP-23 FIRE FIGHTING 4 7/9/86 i
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Procedure Procedure Title Rev. Date Number Eggeetive EPIP-03 PCN 02 Notification of Unusual Event 10 6/13/86 Implemencing Actions u EPIP-15 Protective Action Guidelines 04 6/13/86 6*
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REVISION EMERGENCY CLASSIFICATION '5 Page 1 of 29 9e DDC COPY Fil{
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REVISED BY DEN 46 WAfd TEAltN brDThd EXT.3000/T3fe4 i TECH. REVIEWER j/em j w DATE [-F-8,
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, IMPLEMENTING PROCEDURE EPIP-02 REVISION EMERGENCY CLASSIFICATION 5 Page 2 of 29 REVISION HISTORY Rev. No. Date Revised Pages Comments 3 4, 7, 9, 15 To incorporate PCN #01 of 17, 19 Rev. 2 and to correct
_ references and minor editori.-1 changes 4 13, 17, 25 To incorperate PCN #01 of Rev. 3; revise note so wording came as in other 3 precedure; spellinz error correction
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IMPLEMENTING PROCEDURE EPIP-02 REVISION EMERGENCY CLASSIFICATION 5 Page 3 of 29 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 4
2.0 REFERENCES
- 4 3.0 LIMITATIONS AND PRECALTTIONS S 4.0 DETAILED PROCEDURE , 7 4.1 Personnel Indoctrinations / Responsibilities 7 4.2 Prerequisites 9 4.3 Instructions 9
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s APPENDICES Appendix A - Offsite Dose and Barrier Challenge / Failure 11 j Event Classification Appendix B - Non Rx Trip Event Classification 15 Appendix C - Classification Criteria 24 l
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[R IMPLEMENTING PROCEDURE EPIP-02 REVISION EMERGENCY CLASSIFICATION 5 Page 4 of 29 1.0 OBJECTIVE To provide a means of classifying off-normal events into one of the four emergency classifications described in the PVNGS Emergency Plan.
2.0 REFERENCES
2.1 Implementing References .
2.1.1 EPIP-03, " Notification of Unust,a1 Event Implementing Actions" 2.1.2 EPIP-04, " Alert, Site Area and General Emergency Implementing Actions" 2.1.3 EPIP-15, " Protective Action Guidelines".
2.1.4 EPIP-20 " Personnel Assembly and Accountability".
2.1.5 PVNGS Technical Specifications 2.1.6 41EP-12Z01, " Emergency Procedure" ~
2.1.7 " Event Reporting Manual" !
2.1.8 41RO-1ZZ10. " Functional Recovery Procedure" 2.1.9 PVNGS Security Plan 2.2 Developmental References 2.2.1 NUREG-0654 Rev. 1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 PVNGS Emergency Plan, Rev. 6 .
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, 2.2.3 PVNGS Final Safety Analysis Report (FSAR), Amendment 14 February ,1985 .
2.2.4 CEOG E0P Technical Guidelines, CEN-152, Rev. 02, April 1984 2.2.5 EPA-520/1-75-00, " Manual of Protective Actions Guides and Protective Actions for Nuclear Incidents," Revised June 1980.
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j IMPLEMENTING PROCEDURE EPIP-02 REVISION EMERGENCY CLASSIFICATION 5 Page 5 of 29 2.2.6 10 CFR 50, " Domestic Licensing of Production and Utilization Facilities," 1983.
2.2.7 CEOG Task 467, May 1983, " Guideline for Core Damage
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Assessment".
3.0 LIMITATIONS AND PRECAUTIONS 3.1 Surveillance and assessment,of plant and containment conditions ,
are necessary to ensure appropriate classification of an event and appropriate Protective Action Recommendations (PAR) made to offsite officials. These PARS are made to offsite officials even when no release is in progress.
3 .'2 Definitions and Abbreviations 3 3.2.1 Notification of Unusual Event - This classification applies to unusual events which are in progress or have occurred
-' which indicate a potential degradation of the level of safety of the plant. No releases' of radioactive material requiring of fsite response or monitoring are expected unless further -
degradation of cafety systems occur.
3.2.2 Alert - This classification consists of events which are in
, progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency Protective Action Guideline exposure levels.
3.2.3 ' Site Area Emergency - Consists of , events which are la progress or have occurred which involve actual or likely i major failures of plant functions naeded for the protection of the public. Any releases are not expected to exceed Environmental Protection Agency Guideline exposure levels -
beyond the site boundary. ,
3.2.4 General Emergency - Consists of events which are in progress or have tccurred which invol"a actual or inninent substantial-
- core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected .
to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
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IMPLEMENTING PROCEDURE EPIP-02 REVISION EMERGENCY CLASSIFICATION 5 Page 6 of 29
, 3.2.5 ARM - Area Radiation Monitor 3.2.6 PRM - Process Radiation Monitor PAG - Protective Action Guidelines: Guidelines used in 3.2.7 establishing recommendations given te and acted upon by offsite authoriti9 s to ensure the safety of the public.
3.2.8 NSLB - Main Steam Line Break .
3.2.9 MSSS - Main Steam Support Structure 3.2.10 SBCS - Steam Bypass Control System 3.2.11 ADV - Atmospheric Dump Valves 3.2.12 ESFAS - Engineered Safety Features Actuation System
,. I 3.2.13 PAR - Protective Action Recommendation .,
3.2.14 RPS - Reactor Protection System .
3.2.15 RO - Recovery Operating Procedures 3.2.16 CHIC - Corporate Headquarters Information Center 3.2.17 CEC - Corporate Emergency Center 3.2.18 JENC - Joint Emergency News Center
. 3.2.19 SS - Shift Supervisor 3.2.20 EC - Emergency Coordinator 3.2.21 RMS - Radiation Monitoring System 3.2.22 WB - Whole Body 5
3.2.23 NUE - N,otification of Unusual Event -
3.2.24 CRS - Control Room Supervisor 3.2.25 SIAS - Safety Injection Actuation Signal 3.2.26 RCS ' Reactor Coolant System
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REVISION EMERGENCY CLASSIFICATION 5 Page 7 of 29 4.0 DETAILED PROCEDURE 4.1' Personnel Indoctrination / Responsibilities NOTE The rationale and criteria used to derive Appendices A and B is given in Appendix C.
Appendix C describes the criteria used in the ,
development of the emergency classifications. .
It is intended for information only, not for event classification.
EPIP-02 is not implemented for the notification of significant events unless a situation degrades to the point of impacting on a fission product barrier and compromising a safety
._ ' function. Notification of significant events is made per the, " Event Reporting Manual".
4.1.1 If a conflict or uncertainty exists, the more conservative, higher numbered, implementing Action'EPIP ,
should be initiated when classifying the event.
4.1.2 For Emergency Classificatior.s of ALERT or higher, the Shift Supervisor of the designated unaffected unit shall relieve the Shift Supervisor of the affected unit as the Emergency Coordinator. For Notification of Unusual Events it will be the discretion of the Shift Supervisor of the affected unit, if he is to be relieved as Emergency Coordinator by the Shift Supervisor of the designated unaffected unit.
4.1.3 The normal assignments of designated unaffected unit Shift Supervisors are listed.. If conditions exist which make the use of the listed Shift Supervisor undesirabis, another qualified individual may relieve as the Emergency Coordinator at the discretion of the affected unit Shift Supervisor.
4.1.4 If an ind'ication of barrier challenge or failure exists which is inconsistent with the recovery procedure in use, initiate the Emergency Classification indicated and rediagnose plant conditions to identify any additional procedure which may be necessary to address existing conditions.
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-_ IMPLEMENTING PROCEDURE EPIP-02 REVISION EMERGENCY CLASSIFICATION 5 Page 8 of 29 4.1.5 The rationale used to develop the classification of events based on indications of barrier challenge or failure is provided in Appendix C. This information describes the rslationship between safety function and barrier integrity.
4.1,6 Responsibilities of the affected unit shift supervisor are:
4.1.6.1 Initial classification of the event per this procedure.
NOTE ,
Designated Unaffected Unit Shift Supervisor to assume the role to the Emergency Csordinator in the Onshift Emergency Organization are:
Affected Unit SS Unaffected Unit SS Unit 1 Unit 2 Unit 2 Unit 1
, .' Unit 3 Unit 2 Entire Site Unit 1
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4.1.6.2 Notification of the Shift Supervisor of the designated unaffected unit or other individual selected as Emergency Coordinator.
4.1.6.3 Organization of the onshift staff to place the plant in a safe condition.
4.1.6.4 Assumption of the Emergency Coordinator's posit' ion until relieved.
4.1.7 Responsibilities of the Emergency Coordinator are:
4.1.7.1 Overall responsibi.11ty for directing the onshift emergency response organization. ,
4.1.7.2 Implement EPIP's based on initial classification.
4 .1. 7 . 3 Verif,ication/ reclassification of the event after initial l
licensee actions are completed. ;
1 4.1.7.4 Monitoring plant conditions and reclassifying the event 1 ts necessary until the event is terminated. l l
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- REVISION EMERGENCY CLASSIFICATION S Page 9 of 29
! . 4.1.7.5 Downgrade the event based on plant status with all safety functions satisfied and boundary status verified. u 4.1.7.6 Terminate the event taking into account that the event has been downgraded and the anticipated plant response is such that there should be no challenge to any fission product barriers or radiatien releases in excess of Tech Specs; and present plant conditions are such that there
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is no possibility of an adverse impact on the health or safety of the general public or plant personnel. .
4.2 Prerequisites
. 4.2.1 A situation has occurred which recuires the implementation of '
the PVNGS Emsegency Plan to protect the health and safety of the public.
4.3 Instructions
4.3.1 When plant conditions are such that Emergency Plan -
implementation may be required, the Shift Supervisor / Emergency Coordinator shall perform the following: , ,
4.3.2 Classify the event using the appropriate appendix:
Appendix A - If an event oriented Recovery Procedure or the functional Recovery Procedure is in use.
i Appendix B - If a non-Rx trip event has occurred.
4.3.3 If the event oriented Recovery Procedure that is in use is ,
effectively directing the maintenance of Critical Safety Functions and plant recovery, the CRS/EC may elect to NOT l classify an " Uncomplicated Reactor Trip" as an NUE. SIAS
- l actuations caused by low pressurizer pressure require event clsasification as an NUE due to assumed SI flow into the RCS. Reactor Tripa which involve other ESFAS actuations in which the,cause is known, may be determined uncomplicated g plant parameters are trending as expected and ESFAS reset criteria are mg at the time classificatien would normally be required. Anytime an uncomplicated trip has been determined, the Event Reporting Manual should be consulted to I ecsure appropriate notifications are made.
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REVISION EMERGENCY CLASSIFICATION 5 Page 10 of 29
. 4.3.4 Record the date/ time / events of initial classification. Upon u verification / reclassification of the event, record the date and time and supporting information.
4.3.5 Initiate end complete the implementing actions given in the
- appropriate classified-event implementing procedure (i.e.,
EPIP-03 and 04). lf
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- CONTROLLED BY USER PROCEDURE p PVNGS EMERGENCY PLAN No. APPENDIX A IMPLEMENTING PROCEDURE EPIP-02 Page 1 of 4 REVISION EMERGENCY CLASSIFICATION 5 Page 11 of 29 Offsite Dose and Barrier Challenge / Failure Event Classification 1.0 Determine the event classification as follows:
1.1 Evaluate any barrier challenges / failure per Appendix A, Table 1.
1.2 Evaluate any currant offsite radioactive release per Appendix A, Table 2.
6 1.3 The following Pcgraded Electrical conditions require -
classification as NUE.
LOSS OF OFFSITF P0k'ER - Inability to provide power to both PBA-S03 and PBB-SO4 from any offsite 525KV transmission line. ,
LOSS OF ONSITE AC POWER CAPABILITY - Inability to provide power to NAN-S01 and NAN-S02 or PBA-503 and PBB-SO4 from any source.
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Evaluate plant electrical status for ariy required classification.
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NOTE i Protective Action recommendations are based en plant and containment conditions and these l recommendations are made to offsite officials {
even when no release is in progress. !
i 2.0 Select the most restrictive, higher classification, from the Tsble 1, Table 2, and degraded electrical conditions as the event l classification. !
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REVISION EMERGENCY CLASSIFICATION 5 Page 12 of 29 Appendix A Table 1 - Barrier Challenge / Failure Classification Criteria 1.0 Make Checks by any of the following conditions that currently exist.
RCS CLAD CONTAINMfNT ,
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A'1VS Physical breach voiding in upper of containment plenum * @ ,
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> 2750 psia Activity (> 300 CIAS required but ue/gm dose equiva- not completed t'i.e.
lent I-131)
Uncontrolled loss both automatic of RCS inventory valves in a pene-
> 50 gpm CET > 700 F tration fail to ,
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> 3.5% by volume Containment pressure
> 50 psig Vital Auxiliaries / Radiation Release Total loss of offs 3te and onsite AC power (Blackout) l Total loss of offsite and onsite AC power (Blackout) for longer l5 than 60 minutes Loss of all Class IE DC power.
Loss of all Class IE DC power for longer than 15 minutes.
Failure of ESF Safety Systems (both trains) to actuate when required (Diesal Generator start failures excluded) .
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> 10gpm primary / secondary leakage concurrent with loss of condenser vacuum <
> 10 gpm primary / secondary leakage concurrent with loss of
'" secondary coolant outside containment
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IMPLEMENTING PROCEDURE EPIP-02 Page 3 of'4 REVISION EMERGENCY CLASSIFICATION 5 Page 13 of 29 Appendix A Table 1 - Barrier Challenge / Failure Classification Criteria (Cont'd.)
2.0 Determine the emergency classification level for barrier challenge / failure per the following guidelines:
Number of Checks made in 1.0 Barrier Scatus Classification O No barriers lost Unusual Event ,
or challenged (EPIP-03) 1 One barrier lost Alert (EPIP-04) or challenged 2 Two barriers lost Site Area Emergency or challenged' (EPIP-04) lg c 3 or Three barriers lost General Emerge,ncy 6 j ,
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Based upon information provided by the Radiation Protection Grcup and/or RMS, determine the emergency classification level according to the following:
Notification of Unusual Event (EPIP-03)
Plant Vent Monitor RU-143 Chn. I 2 6.62 E-4 u'ci/cc ,
Fuel Bldg. Exh. Monitor RU-145 Chn. 1 2 1.63 E-3 uci/cc Condenser Exh. Monitor RU-141 Chn. 1 2 4.60 E-2 uci/cc Alert (EPIP-04)
Plant Vent Penitor RU-143 Chn. 1 2 6.62 E-3 uci/cc Fuel Bldg Exh. Monitor RU-146 Chn. 1 2 5.91 E-2 uci/cc p Condenser Exh. Monitor RU-142 Chn. 1 2 4.60 E-1 uci/cc Site Area Emergency (EPIP-04) _
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Plant Vent Monitor RU-144 Chn. 1 30 min. @ 2 2.20 E-1 uci/cc. ,
RU-144 Chn. 1 2 min. G 2 2.20 uci/cc l-Fuel Bldg. Exh. Monitor RU-146 Chn. 1 30 min. @ 2 1.96 uci/cc RU-146 Chn. 2 2 min. @ 2 1.96 E+1 uci/cc Conden::er Exh. Monitor RU-14'2 Chn. 1 30 min. @ 2 1.53 E+1 uci/cc-RU-142 Chn. 2 2 min @ 21.53 E+2 uci/cc General Emergency (EPIP-04) S
, Plant Vent Monitor RU-144 Chn. 1 2 4.40 uci/cc lI Fuel Bldg. Exh. Monitor RU-146 Chn. 2 2 3.91 E+1 uci/cc Condenser Exh. Monitor RU-142 Chn. 2 2 3.06 E+2 uci/cc l
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- CONTROLLED BY USER PROCEDURE m PVNGS EMERGENCY PLAN NO. APPENDIX B IMPLEMENTING PROCEDURE EpIp.02 Page 1 of'9 HEVISION EMERGENCY CLASSIFICATION 5 Page 15 of 29 Appendix B Non Rx Trio Event Classification Cri,teria 1.0 Classify non Rx trip events as follows:
1.1 Based on existing plant conditions select the most appropriate event category from below:
Event Category Tab ,
Increase in Radiation Levels or Radioactive Effluent Relpase Rate 1 Technical Specification LCO Nonconformance, 2
Degraded 7acility Control, Indication, or Alarm 3 Fire and/or Security Compromise 4 Natural Disaster / Physical Hazard to Facility 5 ,
Degraded Electrical 6 1.2 Refer to the indicated tab for the event category chosen and select the classification appropriate for existing conditions.
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CONTROLLED BY USER PROCEDURE PVNGS EMERGENCY PLAN N O. APPEND 17. B IMPLEMENTING PROCEDURE EPIP-02 Page 2 of 9 REVISION EMERGENCY CLASSIFICATION 5 Page 16 of 29 TAB 1 Increase in Radiation Levels or Radioactive Effluent Release Rate Notification of Unusual Event (EPIP-03)
- RCS sample activity requires shutdown per Tech Spec 3.4.7
- Rad Protection and/or RMS confirms radioactive effluent. releases exceed: ,
Plant Vent Monitor RU-143 Chn. 1 > 6.62 E-4 uci/cc Fuel Bldg. Exh. Monitor RU-145 Chn. 1 > 1.63 E-3 uci/cc Condenser Exh. Monitor RU-141 Chn 1 > 4.60 E-2 uci/cc ,
- Trr.nsportation of internally or externally contaminated injured person to offsite hospital Alert (EPIP-04)
- RCS samp1,e activity > 300 uC/gm (DE I-131)
NOTE Radiation readings " increase by a factor of 1000" refers to unexpected or casualty situations. This is not metnt to include normal plant evolutions such as resin transfer or source transport.
- Direct radiation readings within facility increase by a factor of 1000 l
- Rad Protection and/or RMS confirms radioactive effluent releases exceed:
Plant Vent Monitor RU-143 Chn. 1 > 6.62 E-3 uci/cc Fuel Bldg. Exh. Monitor RU-146 Chn. 1 > 5.91 E-2 uci/cc Condenser Exh. Monitor RU-142 Chn. 1 > 4.60 E-1 uci/cc
- RCS leak rate > 50 gpm
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Site Area Emergency (EPIP-04)
- Major damage to spent fuel
- Rad Protection and/or RMS confirms effluent radioactive releases exceed:
- l Plant Vent Monitor RU-144 Chn. 1 30 min. @ > 2.20 E-1 uci/cc RU-144 Chn. 2 2 min. @ > 2.20 uci/cc Fuel Bldg. Exh. Monitor RU-146 Chn. 1 30 min. @ > 1.96 uci/cc .
RU-146 Chn. 2 2 min. @ > 1.96 E+1 uci/cc Condenser Exh. Monitor RU-142 Chn.~1 30 min. @ > 1.53 E+1 uci/cc RU-142 Chn. 2 2 min @ > 1.53 E+2 uci/cc <
- Radiation Protection measures > 50 MR/Hr at site boundary with portable instruments ',-
's s' General Emergency (EPIP-04) .-_
- Rad Protection and/or RMS confirms effluent radioactive releases exceed:
Plant Vent Monitor RU-144 Chn. 2 > 4.40 uci/cc Fuel Bldg. Exh. Monitor RU-146 Chn. 2 > 3.91 E+1 uci/cc Condenser Exh. Monitor RU-142 Chn. 2 > 3.06 E+2 uci/cc
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- Radiation Protection measures > 1.0 R/Hr at site boundary with portable l instruments l l
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-~. PVNGS EMERGENCY PLAN N O. APPENDIX B IMPLEMENTING PROCEDURE EPIP-02 Page 4 of'9 REVISION EMERGENCY CLASSIFICATION 5 Page 18 of 29 TAB 2 Technical Specification LCO Non-Conformance
, Notification of Unusual Event (EPIP-03)
- Rad Protection and/or RMS confirms section 3/4.11 Tech Spec Radiological Effluent limits exceeded
- RCS activity sample requires shutdown per Tech Spec 3.4.7 ,
- Noncompliance with a technical specification, such that the
. requirement of the LCO and associated action requirements are not met within the specified time intervals and require reactor shutdown.
Alert (EPIP-04)
- RCS leakrate >50 gpm
- AWS Site Area Emergency (EPIP-04)
None General Emergency (EPIP-03 fi None -
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Degraded Facility. Control, Indication and Alarm Notification of Unusual Event (EPIP-03) 1
- Degraded control room indication or alarms on process parameters l such that plant shutdown is required )
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Alert (EPIP-04) i
- Loss of most or all annunciators Evacuation of control roon required or anticipated )
Complete loss of any function needed for plant cold shutdown, when
-- in cold shutdown
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Site Area Emergency (EPIP-04) ,
- Loss of most or all annunciators and plant transient indicated or in progress Imminent loss of physical control of the plant
- Complete loss of any function needed for plant hot shutdown, when in hot shutdown
- Control room evacuated and local control of shutdown systems not established within 15 minutes General Emergency (EPIP-04) f
- Loss of physical control of the facility
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- PVNGS EMERGENCY PLAN No APPENDIX B IMPLEMENTING PROCEDURE spip-02 Pae. 6 of'9 REVISION E!!ERGENCY CLASSIFICATION 5 Page 20 of 29 TAB 4 Fire and/or Security Compromise Notification of Unusual Event (EPIP-03)
- Fire within the Unit lasting longer than 10 minutes
- Declared Security Emergency -
- Declared Security Alert (with offsite authorities notified and immediate response requested)
Alert (EPIP-04)
- Required evacuation of contrcl room
, - SS/EC determines that the leval of plant safety is substantially
\._- reduced due to fire or ongoing security compromise.
Site Area Emergency (EPIP-04)
Imminent loss of physical control of the plant
- Control room evacuated ag local control of shutdown systems not established within 15 minutes
- Fire compromising the operability of safety systems in both trains General Emergency'(EPIP-04)
- Loss of physical control of the plant
- Any major internal or external events which could cause massive.
damage to plant systems potentially leading to releases of large amounts of radioactivity
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PVNGS EMERGENCY PLAN NO. APPENDIX B IMPLEMENTING PROCEDURE EPIP-02 Page 7 of*9 REVISION EMERGENCY CLASSIFICATION 5 Page 21 of 29 TAB 5 u
Natural Disaster / Physical Hazard to Facility Notification of Unusual Event (EPIP-03)
- Natural phenomenon beyond usual level experienced or projected Earthquake greater than 0.lg ground shaking, flood , tornado onsite .
- Other hazards experienced or projected Aircraft crash onsite or unusual aircraft activity over facility ,
Train derailment onsite
. Explosion near or onsite N_'
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Toxic or flammable gas release near on onsite
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Turbine rotating component failure resulting in rapid shutdown Alert (EPIP-04)
- Severe natural phenomena experienced or projected with unit in -
modes 5-6 Earthquake greater than design levels, 0.2g ground shaking, Tornado striking facility, or Severe flooding ,
- Other hazards experienced or projected Aircraft crash on facility Missile im' pacts on facility Explosion damage to facility affecting plant operation Toxic or flammable gas restricts entry to facility environs
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- g. NO- APPENDII B IMPLEMENTING PROCEDURE EPIP-02 Page 8 of'9 REVISION EMERGENCY CLASSIFICATION 5 Page 22 of 29 5'
Site Area Emereeney (EP:P-04)
- Severe natural phenomena experienced or projected with unit in modes 1-4 Earthquake greater than design levels, 0.2 ground shaking, Flood with failure of protection of vitsi equipment Sustained winds in excess of design levels ,
- Other hazard experienced or projected with unit in modes 1-4 Aircraft crash affecting vital structures by impact Severe damage to safe shutdown equipment by missile or explosion
~'s Lack of entry into vital ar(as due to uncontrolled toxic or
, flammable gas General Emergency (EPIP-04)
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- Any major internal or external events which could cause massive damage to plant systems potentially leading to release of large amounts of radioactivity 6
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.~. PVNGS EMERGENCY PLAN NO. APPENDII B IMPLEMENTING PROCEDURE EPIP-02 Page 9 of'9 REVISION EMERGENCY CLASSIFICATION 5 Page 23 of 29
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TAB 6 DEGRADED ELECTRICAL Notification of Unusual Event (EPIP-03)
- Loss of Offsite Power Inability to provide power to both PBA-S03 and PBB-SO4 from
. any offsite 525KV transmission line. -
- Loss of Onsite AC Power Capability Inability to provide power to NAN-S01 and NAN-SO2 or PBA-503 alld PBB-SO4 from any source.
4 Alert (EPIP-04)
NONE Site Area Emergency (EPIP-04)
NONE ~
General Emergency (EPIP-04)
- NONE l
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'(. IMPLEMENTING PROCEDURE EPIP-02 REVISION APPENDIX C Page 1 of'6 EMERGENCY CLASSIFICATION 5 Page 24 of 29
, CLASSIFICATION CRITERIA 1.0 CLASSIFICATION CRITERIA The classification criteria for Notification of Unusual Event through a General Emergency are based on three main consideraticas:
- 1) The extent of fission product barrier challenge or failure
- 2) The projected / actual offsite dose rate associated with '
radioactivity releases.
- 3) Potential or actual reductions in the level of plant safety i Evaluation of these criteria allows the development of Emergency Action Leveh (EALs) which are independent of event sequences and
' readily corAelate with the symptom / function based Emergency Operating Procedure (EOP) Guidelines.
(' :
Using this system, most emergency classifications may be based on the failure of, or challenge to, the fission product barriers. " Failure" of barriers is defined in terms consistent with NUREG-0654, Appendix '
1, Example Initiating Conditions - eg: primary coolant leaks of 50 gpm constitutes " failure" of the primary coclant boundary (based on charging pump capacity for 2 pumps minus minimum letdown); 300 uCi/cc dose equivalent I-131 constitutes'" failure" of the clad (based on
, release of 1*. equilibrium gas gap equivalent I-131); loss of containment integrity is defined per Technical Specification Section 1.7.
A " challenge" to a barrier is defined as one of the following conditions:
- 1) Loss of a critical safety . function which protects that barrier.
- 2) An existing situation which will cause a barrier failure within a given time period unless successful corrective actions are implemented.
- 3) An initiating' event which in all probability has damaged a fission product barrier but has yet to be verified.
The SS/EC has the authority to increase the classification above that determined by EPIP-02 when, in his judgement, plant conditions warrant increased response and awareness from offsite personnel and agencies.
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_ PVNGS EMERGENCY PLAN PROCEDURE NO- APPENDIX C IMPLEMENTING PROCEDURE EPIP-02 Page 2 of'6 REVISION EMERGENCY CLASSIFICATION 5 Page 25 of 29 Table 3.0 lists indications of barrier challenge / failure for RCS, Clad, Containment, and vital auxiliaries / radiation release.
I The fission product barrier criteria is applied to event classification in increasing order of severity as follows:
NOTIFICATICN OF UNUSUAL LVENT
- 1. No loss of and no challenge to a fission product barrier -
ALERT
- 1. A challenge to one. barrier, or
- 2. A verified failure of one barrier
, SITE AREA EMERGENCY
- 1. Challenges to two barriers, or
- 2. Verified failure of one barrier and a challenge to another, or
- 3. Verified failure of two barriers GENERAL EMERGENCY
- 1. Challenges to all three barriers, or
- 2. Verified failure of one barrier and challenges to the other two, or
- 3. Verified failure of two barriers and challenge to the other, or
- 4. Verified failure of all three barriers Guidance for evaluation and classi.fication of non Rx trip events is taken directly from NUREG 0654. The arrangeuent of example situations by event categories provides an efficient method for the operator to i
make a classification depending upon the severity of the condition.
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APPENDIX C IMPLEMENTING PROCEDURE EPIP-02 Page 3 of'6 REVISION EMERGENCY CLASSIFICATION 5 Pege 26 of 29 2.0 EVENT CLASS!?! ;.T*"'.
Appendices A and B present potential plant conditions for consideration in determining event classification. SRO's and Emergency Coordinators responsible for implementing this procedure are required to be familiar with the specific conditions which constitute barrier challenge / failure and those non trip events requiring emergency classification.
Appendix A lists possible challenges / failures that might exist to the ,
fissian product barriers. A check by any of the indicated conditions constitutes one barrier challenge or failure. (Therefore, if two conditions under "RCS" are checked, that constitutes two barriers challenged or failed.) Event classification will be made after evaluating the number and extent of barrier challenge / failure along with the projected doses resulting from any offsite releases. The activity release levels associated with emergency classification levels are based on the following NUREG-0554 criteria:
( _'
! Unusual Event -
Exceed Tech Spec 3/4.11 Radiological Effluent limits.
Alert - Effluent release rate 10X Tech Spec limits ~
or 1 mR WB @ site boundary for 2 hr release. i Site Area Emergency - > 50 mR/hr WB @ site boundary for 30 min. release or
> 500 mR/hr WB @ site boundary for 2 min release.
General Emergency - > 1 rem /hr WB @ site boundary.
The Site Area Emergency classification is divided into activity concentrations that must be mainta.ined for either two or thirty
. minutes in order for the offsite dose limits to be met or exceeded.
i Appendix B provides guidance for evaluating conditions not resulting in a Rx trip that require emergency classification per NUREG-0654.
Six event categories have been selected, under which, similar non trip events can be listed according to emergency classification. Most classification should be straightforward once the event category has been selected. Event classifications based upon degraded security conditions, however, can be somewhat more involved.
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[ROCEDURE IMPLEMENTING PROCEDURE EPIP-02 Page 4 of'6 REVISION E.'!ERGENCY CLASSIFICATION 5 Page 27 of 29 The PVNGS Security Department classifies security infractions into two types:
- 1. Security Alert
- 2. Security Emergency Any declared Security Emergency will be classified as a Notification of Unusual Event. Should any plant damage, loss of facility control, or loss of accessability result from a degraded security condition, ,
the guidelines for upgrading the emergency classification are in Tab 3, Degraded Facility Control, and Tab 5, Physical Hazards to Facility. Should a security compromise further degrade such that a substantial reduction in the level of plant safety occurs, an alert classification is appropriate. The Shift Supervisor's/ Emergency Coordinator's judgement will be required'to determine the severity of the security intrusion and the likelihood that a fission product
, barrier might be challenged to warrant the upgraded emergency f classification.
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~ Security compromises resulting in a declared Security Alert with immediate response requested from offsite authorities is also -
classified Notification of Unusual Event. This will ensure ~
notification of appropriate company management personnel to off-normal conditions serious enough to warrant immediate response from offsite authorities'. Security Alerts of a less serious nature where offsite authority assistance is requested would not require classification.
It should be understood that the key point to consider for classification of Security Alerts is whether offsite authorities are notified to provide immediate response or assistance.
Table 4.0 lists applicable licensee actions per event classification.
These actions will *oe implemented per the direction of the appropriate EPIP.
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. m' PVNGS EMERGENCY PLAN [ROCEDURE o-APPENDIX C IMPLEMENTING PROCEDURE EpIp.02 page s of 6 REVISION EMERGENCY CLASSIFICATION 5 Page 28 of 29 TABLE 3.0 Indications of Barrier Challenge / Failure RCS CLAD CONTAINMENT RVI2!S indicates ATw'S Physical breach
. voiding in upper of contai= cent plenum OR -
D_ R_
> 2750 psia Activity ( > 300 CIAS required but uCi/gm dose equi- not completed (i.e.
Uncontrolled loss valent I-131) both automatic of RCS inventory valves in a pene-
> 50 gpm CET > 700 F tration fail to close) f H2 concentration
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> 3.57. by volume Containment pressure
> 50 psig VITAL AUXILIARIES / RADIATION RELEASE Loss of offsite and onsite AC power (Loss of one or the other requires NUE) ] l Loss of offsite and onsite AC power for longer than 60 minutes Loss of all Class IE DC power.
j Loss of all Class IE DC power for longer than 15 minutes.
Failure of ESF safety systems (both trains) to actuate when required
> 10 gpm primary / secondary leakage concurrent with LOP 0.R
> 10 gpm primary / secondary leakage concurrent with loss of secondary coolant outside containment -
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(EPir-03) Alert (EPIP-04) Site Area faergency
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- diteens; no release or radioactive material authoristes er Alert stattes cauae; any releases are emp/-
etted to be limited te, smati fractions or frA/ PAC owposure e enro,. 1,,C. . . te, . Cose.,t, authorities or site Area foergency status /caesse; any releases are not e=pected to o .nrer. ,,,C. s t a t n . Ce,s.o., y autloori ties of f;enera s e ++r=
eleney status /casese; seev ocleases cars be reasonaben empceec.s y,
(A on "O M sfa 2
u requiring errstep levels at the seta boundary e=ceed (PA/*AC coposure M response or monitoring levels beyond the site houndary to esteed (PA/PA,. espesguee H unless further degradation er levels offsite O sen sess rus tlw,r degradat ion site for more than the QQ is e=pected unless safety systems occur immediate orna rurther degradation or ' of safety systems nceur k
O f
safety systems occur e $ased on the situation e Recommend to the State that the PieIIc De appraised er the situation and stay touted o Iteconocad to the Stata that con.
sideration or appropriate pro-o Recommend to the State that con-sideration nr appropriate. pro-tective art 6oris beseet see ac t ese l g
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y recommend that no protecteve action de to (BS/slAlt raJie station tectiva acLenns b ued on actual or projected data is warranted er projected deta es weseanted per the appropriate (P6P Cf h e par the appropriate (PIP riecessary for update or to stendby e Augeant resources try 7
activating STSC. ISC. 0$C. yZ eor. JtNC, CallC and Ctc o Augment resources by stivtg. SISC. e Augment resources by ativtg, Sf5C. ISC OSC. f0f, JENC.
e Augment onshirt TSC, 05C. fol. JfMC. CHIC, and C(C CHIC and C(C resources e Olspatch (onsite/orrsitel Monitoring Teams with o Olspatch (ensiteforrsite) Fleid e Dispatch tonsite/orrsitel Field o Activate SISC assoc. communications Monitoring Beaus with atsociated istnitoring with associated eqeelpeent coneenitcations equipment rommunications egesipoent e Partially activate
' ClelC e Provide meteorological e Provide a dedicated individual assessments to ortsite for plant status updates to o Provide a dedicated ind e v e deoa l for plant status sepdates or I
- e Tereenste with verbal authorities and er releases orrsele authorities erraete suenarities D ZT
' summary to errsite are oceserting, dose estimates rn Ou authorstees rollowed ror actual releases o Provide meteorological data 5 - O by written report and doso estimates (for o stake senior technical and (n g,g O
- e. management starr avel8able M* wethin rive 15) days e Terminate by verbal summery actual releasest to orrsite r O g IU
' to errsite authorities authorities 1,or pereodic consultation with RC and $ tate w U k- 04 Z q C
- rollowed by written summary o Provide release and dose D e Escalate to a higher within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> projections based on available o Provide esteorological stata . O s
N classification Oft plant conditloes enfermation and end dose estamates tror actual tre N foreseeable contingencies releasest to offsite authnraties i
h- wie e dedicated indevedual ,,
e Escalate te e higher , .
classification o Teralnate (or reduct8on off a Provide release and dose emergancy class verbasly projections hated upon available
- f. at (Or rollowed by written summary within it hours plant condition 6nresseation and t
i foreseeable contingencees I y 5 lp.
Oft on Da *U t
s' a farminate emergency tor reduction nt) s 00 00 *O e Escalate to C(N[RAL [MfRCfflCY rp (D tTO Z
yy- a,,eteo.lve e,rsit errici .et. ls leg, ,ecomm.nd even wl.ee,et.8 . .,e M 0% C3 p rolesse is. Iin .,nrogress I, lent e d cent.l nt co dI tlone a,,d gl a.. No e r.c-nda t ions .r. -de is g, M l $y ,,
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PRCCEDURE CHANGE NOTICE (PCN1 Page 1 of 1 70AC-0ZZ02 Rev. 9
Title:
1 10 l b1 l lDDC Coatact (axt. 6633) l Notific'aticn of Unu.sual Event Implementing Acticms ,h %d ,,
l Orignator: (Print) l E.v.t . l Unit (s) affected:
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lMryRichardson ! 6180 1 1,2,3 l
l Reason for this PCN: .
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I l Correct phone number for ANPP Ccrrunications l
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I l l Expiration: l 1 .
I I l l Permanent l l Page nu=cer(s) affected lTo:al Numoer of l l by this PCN: !Pages attached: I l 12 49 '
2 l 1
l l- Does PCN require a 30.59 review? x No Yes t.reter to a.1.2) l
/ l l
l- Does PCN affect activities in l l the RCA? x No Yes (Copy to ALARA) l I
I l- Does PCN effect the non-rad.ogical l i environ =ent of any offsite area? x No Yes (Contact Co=pliance) l I ,
I l- Is PCN associated with an AC, l l Program, E= erg. Plan or Secur.
l l Prog., Phase I-IV Test, or a No x Yes (PRB/PRG/TRRG l l ST? review required) l l .
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f - V-lb l TECHNICAL REVIEkT.R (Supervisory Level Date l l ' 1
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. PALO VERDE NUCLEAR GENERATING STATION PROCEDURE CHANGE NOTICE PAGE / of f INTENT CHANGE: NO E
.. YES C
- 1. PROCEDURE T1TLE AloliEcaben o ()nisua/ Evenl Is ole ~.enbm Aebens J
- 2. PROCEDURE NUMBER EP/#.c3 REV. /0 PCN /
2a. Manager concurrence Mly DATE to exceed 5 PCNs
- 3. EEASON POR PCN: % m b 141 srsc 6 .,,,,mler acas,e -/h/ A ,vK mov m sh
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- 5. AFPECTED STEPS:
CHANGE REQUIRED:
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- 6. PREPARED BY:
~ ENTERED IN PROCEDURE BY:
} dada. L,kir 2hcala, SIGNATURE DATE SIGNATURE DATE
- 7. TDIPORARY APPROVAL: ,
I 4W l SIGNATURE DATE
/ \ SS/ Assist. SS DATE
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RB/fRC/TRRC:
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46 - 01$ hff f//j'#'hlk' W//:?f/c/
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IMPLEMENTING PROCEDURE EPIP-03 f REWSION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 1 of 26 I
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APPROVED BY [ ^ - - - -
_ DATE / (- [ f 6 Cl. ib DD EFFECTIVE DATE .
DN-1598A/0787A PV2'6-000A e8 82)
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CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEDURE .
IMPLEMENTING PROCEDURE EPIP-03 REVISION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 2 of 26 REVISION HISTORY v
Rev. No. Date Revised Pages Cc= cents 5 12-18-84 Comolete Revised Accendices and Ca11 outs 6 02-08-85 _Cocolete. , Incoroorated PCN's 401 & 02 of Rev. 5 Revised Accendices and Ca11 outs.
7 05-10-85 9, 10, 16 Incoroorated PCN 401 of Rev.
m.
6 and added sten for
- q. ,
cancellation using groue page.
8 06-17-85 3,7,8,9,12,13 Added termination message 16,17,18,19, form and instructions.
21,23 Changed initial and follev-
)
un message 50 actions )
(circle vs cross-out) are consistent. Changed initial and follow-up message to match changes the state reouested. Capitalized
\
announcements to.make stand out. Uedated all references to the correct accendices.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE N O.
IMPLEMENTING PROCEDURE EPIP-03 REVISION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 3 of 26 REVISION HISTORY Rev. No. Date Revised Pages Cc=ments 9 09-10-85 4, 5. 7, 9 Incorocrated PCNI) 1&2 10, 11, 12, of Rev. 8. Added specific 19, 20, 24, announcement instructions, 25, 26 instructions for notifing cocoliance, new groue caging system rf and added STSC Communication checklist.
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( 10 0 51' II sj,7, 9, 10, 11 Incorocrated PCN/k 1 & 2 of 12, 13, 14, Rev. 9. Deleted Time /
16, 17, 24, Initials Colu:m in 25, 26 Accendices I and J.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN o
[ROCEDURE IMPLEMENTING PROCEDURE EPIP-03 NOTIFICATION OF UNUSUAL EVEST IMPLEMENTING ACTIONS 10 Page 4 of 26 TABLE OF CONTENTS SECTION PAGE SUfBER 1.0 OBJECTIVE 5
2.0 REFERENCES
5 3.0 LIMITATIONS AND PRECAUTIONS 5
, 4.0 DETAILED PROCEDURE 6 4.1 Personnel Indoctrination / Responsibilities 6 4.2 Prerequisites 6 4.3 Instructions 6 t.
APPENTICES Appendix A - Emergency Notification Call List - Emergency Coordinator /STSC Co=municator 11 Appendix B - Emergency Notification Call List - PVNGS Security 12 Appendix C - Initial Emergency Message Form 13 Appendix D - Follow-up Emergency Message Form 14 Appendix E - E=ergency Termination Message Form 17 Appendix F - Instructions for Co=pleting Appendix C, D or E 18 Appendix G - Notification Alert Network (NAN) Radio Backup 21
, Appendix H - Protective Action Recommendations 23 Appendix I - Emergency Coordinator Response 24 30 Appendix J - STSC Co=municator Response 26 M4@A &Q
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CONTROLLED BY USER PVNGS EMERGENCY PLAN Tcease ,
IMPLEMENTING PROCEDURE EPIP-03 NOTIFICATION OF UNUSUAL EVENT I!!PLE!!ENTING ACTIONS 10 Page 5 of 26 s
1.0 OBJECTIVE 1.1 This procedure provides a series of implementing actions to taken upon declaration of a NOTIFICATION OF UNUSUAL EVENT. ,
2.0 FERENCES 2.1 Im lementing References '
2.1.1 E P-02, " Emergency Classification" 2.1.2 EPIP 1, " Technical Support Center /Satel to TSC Activation" 2.1.3 EPIP-22, " Personnel Injury" 2.1.4 EPIP-23, "F e Fighting" (j 2.1.5 9N219.05.00, " cument/ Record rnover Control"
. 2.2 Developmental Referen s 2.2.1 NUREG-0654, Rev. 1, t i* ria for Preparation and Evaluation of Radiological Emerge y Response Plans and Preparedness in Support of Nuclear Po*e Plants."
2.2.2 PVNGS Emergency P1 n, Rev.
l 3.0 LI5!ITATIONS AND PREc.UTIONS 3.1 Continued surv illance and assessment o lant conditions are necessary to nsure that the emergency cla ification is appropriac y revised as conditions change o more definitive informati is obtained.
3.2 Notif ations to State / County agencies per Appen 'x A, " Emergency Noti cation Call List - Emergency Coordinator /STS Communicator" sh 1 be commenced within 15 minutes of declaration f an ergency. .
Av2$6-0004 18,82)
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CONTROLLED RV UEFR PVNGS EMERGENCY PLAN QCEME IMPLEMENTING PROCEDURE EPIP-03 NOTIFICATION OF UNUSUAL 5~4.
EVENT IMPLEMENTISG ACTIONS 10 Page ,8' of 26 1.0 CBJECTIVE 1.1 This procedure provides a series of implementing actions to be taken upon declaration of a NOTIFICATION OF UNUSUAL EVEhT.
)
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-02, "E=ergency Classification" 2.1.2 EPIP-11, " Technical Support Center / Satellite TSC Activation" 2.1.3 EPIP-22, " Personnel Injury" 2.1.4 EPIP-23, " Fire Fighting"
.. 2.1.5 9N219.05.00, "Docu=ent/ Record Turnover Control" (v,
2.2 Developmental References 2.2.1 NUREG-0654, Rev. 1, " Criteria for Preparatien and Evaluation of Radiological E=ergency Response Plans and Preparedness in Support of Nuclear Power Plants."
2.2.2 PVNGS E=ergency Plan, Rev. 6 3.0 LIMITATIONS AND PRICALTIONS 3.1 Continued surveillance and assesscent of plant conditions are necessary to ensure that the emergency classification is appropriately revised as c6r.ditions change or care definitive information is obtained.
3.2 Notifications to State / County agencies per Appendix A, " Emergency Notification Call List - Emergency Coordinator /STSC Co==unicator" shall be coe.senced within 15 cinutes of dae.laration of an emergency.
33 All nohlica$ ions ikoulcl be cas ple& doe -lo con lacbn h NRC As Ne EUS - 1 rnosh he mnnec\ eenlinuousi a$ e NR C 's n ws';
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IMPLEMENTING PROCEDURE EPIP-03 NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 6 of 26 4.0 DETAILED PROCEDURE v 4.1 Personnel Indoctrination / Responsibilities 4.1.1 In a NOTIFICATION OF UNUSUAL EVENT situation, time is available to take precautionary and constructive steps to prevent a more serious event and/or to mitigate any censequences that may occur. This event status places the plant in a readiness position for possible cessation of routine activities and/or augmentation of onshift resources.
No releases of radioactive material requiring offsite response are expected. Appropriate notification of NRC and state / county authorities is made.
4.1. 2 The Shift Supervisor shall be responsible for initiating this procedure. The Emergency Coordinator shall be responsible for ce=pleting the impler.enting actions of this procedure.
4.2 Prerequisites 4.2.1 The emergency has been classified per EPIP-02, "E=ergency Classification."
4.3 Instructions 4.3.1 The affected unit Shift Supervisor shall perform the following:
NOTE Designated Unaffected Unit Shift Supervisor to assume the role of the Emergency Coordinator in the Onshift E=ergency Organization are:
Affected Unit Unaffected Unit Shift Supervisor Unit 1 Unit 2 Unit 2 Unit 1 Unit 3 Unit 2 Entire Site Unit 1 l
Pv216-000A 68.82)
CONTROLLED BY USER PVNGS EMERGENCY PLAN CEDURE
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IMPLEMENTING PROCEDURE EPIP-03 NOTIFICATION OF UNUSUAL EVENT IliPLE!!ENTING ACTIONS 10 Page 7 of 26 4.3.1.1 'Jotify the Shift Supervisor of the designa'ted unaffected unit (or Shift Supervisor of an unaffected unit) to report to the Control Room of the affected unit and assu=e the duties of the onshift Emergency Coordinator.
For NOTIFICATION OF UNUSUAL EVENT, it will be at the discretion of the affected unit Shift Supervisor if he is to be relieved as Emergency Coordinator by the shift supervisor of an unaffected unit.
4.3.1.2 Notify the Control Rooms of the unaffected units.
g 4.3.1.3 Ensure tha following is pn ed over the plant wide telephone page (phone no "ATIINTION ALL PLANT PERSONNEL - A NOTIFICATION OF UNUSUAL EVENT HAS BEEN DECLARED. SATELLITE TECHNICAL SUPPORT CENTER AND OPERATIONS SUPPORT CENTER EliERGENCY PERSON'iEL FOR UNIT .. REPORT TO YOUR E.'IERGENCY e- STATION. OTHER PERSONNEL ASSIGNED TO THE E}!ERGENCY ORGANIZATION - STAND 3Y. ALL OTHER PERSONNEL CONTINUE '
WITH NOR.'!AL ROUTINE L~dTIL FURTHER NOTICE".
(Give a brief description of the event, if appropriate, and repeat the announcement).
4.3.1.4 Ensure the announcement in step 4.3.1.3 is tepeated over the Site Warning Siren /Public Address System.
Pv2Y6@CA t&8a u - . _ _ .
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PVNGS EMERGENCY PLAN @csouns IMPLEMENTING PROCEDURE EpIp-03 REVISION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 8 of 26 NOTE Protective Action recommendations (Appendix H) are based on plant and containment conditions and these recommendations are made to offsite officials even when no release is in progress. '
NOTE If the e=ergency is terminated before initial notifications are finished, complete the notifications per Appendix A, then repeat Appendix A with the notification of termination. If the emergency is terminated before initial (s<' notification can be started, provide both initiating and terminating messages in the sa=e call.
4.3.1.5 Direct the Satellite TSC Com=unicator to fill out Appendix C, " Initial Emergency Message Form," in accordance with instructions provided in Appendix F, and make notifications per Appendix A.
4.3.1.6 Ensure the actions of the appropriate Recovery procedures have been implemented.
4.3.2 The Emergency Coordinator / Shift Supervisor shall perform the following:
4.3.2.1 Ensure actuation of the Satellite TSC in accordance with EPIP-11. " Technical Support Center / Satellite TSC Activation."
4.3.2.2 Implement additional Emergency Plan Implementing Procedures according to the situation that resulted in the emergency being classified as a NOTIFICATION OF UNUSUAL EVENT.
Pv2?6@0A 16/82:
CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE EPIP-03 REVISION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 9 of 26 L
4.3.2.3 Determine the need for any additional personnel. If needed, additional personnel should be requested by the existing on-shift organization.
4.3.2.4 If it is determined that the OSC is not required to t
support the emergency response, notify the OSC to l
deactivate and allow the response personnel to respond to normal work stations.
( -
4.3.2.5 Direct the STSC Communicator to prepare Appendix D,
" Follow-up Emergency Message Form" in accordance with instructions provided in Appendix F.
4.3.2.6 Reevaluate the emergency classification and perform licensee actions as conditions change by implementing EPIP-02.
4.3.2.7' When the situation warrants. downgrading / upgrading a
NOTIFICATION OF UNUSUAL EVENT, proceed to appropriate implemer. ting and notification procedures and direct the Shift Supervisor to announce the reclassification over l
the public address system and inform the other Control Rooms. Keep PVNGS Plant Manager informed as to status of event.
l l 4.3.2.8 Provide over all direction and control of Ehe ONSHIFT l emergehey response as per Appendix I - Emergency Coordinator Response.
l 4.3.3 PVNGS Security, after being notified by the Emergency Coordinator or STSC Communicator that a NOTIFICATION OF UNUSUAL EVENT is in progress or has occurred, or has been terminated, shall complete Appendix B, "Emergencf l Notification Call List - PVNGS Security," and notify these l individuals or departments of the situation.
4.3.4 Emergency Situation Terminated 4.3.4.1 Consult with the PVNGS Plant Manager prior to closing out emergency.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEbRE IMPLEMENTING PROCEDURE EPIP-03 REVIS!CN NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 10 of 26 4.3.4.2 The Shift Supervisor (or Emergency Coordinator) shall ensure the following announce- -- is made over the plant wide telephone page (phone no. ..
" ATTENTION ALL PERSCNNZL, THE EMERGENCY SITUATION DECLARED IN UNIT HAS NOW BEEN TERMINATED."
(Provide special instructions as necessary).
4.3.4.3 Ensure the announcement in step 4.3.4.2 is repeated over the site warning siren /public address system. ~
4.3.4.4 Ensure the announcement in steps 4.3.4.2 and 4.3.4.3 is repeated once.
j 4.3.4.5 Direct the STSC Cc==unicator to fill out Appendix E, "E=ergency Termination Message Form," per instructions provided in Appendix F.
1 4.3.4.6 Direct the STSC co==unicator to transmit the termination j per Appendix A.
l 4.3.4.7 Th .S./E.C. shall noti"*
- PVNGS Cocoliance Dent. at ' ,
ext or beeper N duri .f hours) and request a wr1 - e provided to offsite authorities within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
S.S./E.C. shall provide copies of shif t logs, control room logs, etc. as requested by Co=pliance for preparation of the report.
4.3.5 Record Retention 4.3.5.1 y44 Appendices A, B, C, D, E, I :n_ ? -shall be turned over to the Emergency Planning Dept., mail station 6010, to ensure they are forwarded to DDC for proper storage in accordance with 9N219.05.00, "Docu=ent/ Record Turnover Control."
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CONTROLLED BY USER PROCEDURE PVNGS EMERGENCY PLAN NO. APPENDIX C, IMPLEMENTING PROCEDURE EPIP-03 Page 1 of 1 REVISION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 13 of 26 INITIAL EMERGENCY MESSAGE FOR!
NOTIFICATION OF UhTSUAL EVENT, ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY
- 1. Verbatim text of Message: THIS IS (IS NOT) A DRILL!! (Circle One) THIS IS PALO VERDE NUCLEAR GENERATING STATION (NOTIFICATION OF UNUSUAL EVENT)
(ALERT)-(SITE AREA EMERGENCY) (GENERAL EMERGENCY)
(circle applicable classification) declared at -
- Wind is from degrees - At mph.
(time) (date) (speed)
PALO VERDE AUTHESTICATOR (authenticator letters)
- 2. This is , at the Palo Va.rde Nuclear Generating (name/ title)
Station Unit .
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- 3. (Circle One)
(a) There is @ , repeat @ , radioactive release taking place and no special protective actions are recommended at this time.
OR (b) There is B , repeat 8 , radioactive release in excess of allowable operating limits and M protective actions are recommended et this time.
OR (c) There is @, repeat 8, radioactive release taking place at this time.
However, the following protective actions are recom= ended.
Sectors Distance (Miles)
OR (d) A radioactive release M , repeat M , taking place. We recommend that people in affected sectors remain indoors with windows and doors closed.
Sectors Distance (Miles)
OR (e) A radioactive rplease M , repeat M , taking place. We recommend that evacuation of affected sectors be considered.
Sectors Distance (Miles)
- 4. THIS IS (IS NOT) A DRILL!! (Circle One)
Approved By (SS/EC/EOD) DATE TIME 94t'6 000A s$s821 9
CONTROLLED BY USER r' PROCEDURE PVNGS EMERGENCY PLAN N O. APPESTIX D IMPLEMENTING PROCEDURE EPIP-os Page i of 3' NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 14 of 26 FOLLOW-UP EMERGENCY MESSAGE FORM v
- 1. Verbatim text of >fessage: THIS IS (IS NOT) A DRILL!! (Circle One)
T'4IS IS A PALO VERDE NCCLEAR GENERATING STATION follow-uo information messace concerning the (NOTIFICATION OF UNUSUAL EVENT) (ALERT) (SITE AREA EMERGENCY 1 (GENERAL EMERGENCY)
(circle applicable classification) declared at -
(time) (date)
- 2. This is , at Palo Verde Nuclear Generating Station.
Unit . (na=e/ title)
- 3. Brief description of event
- 4. Meteorological Data
- a. Wind direction from (degrees) - at miles per hour (direction) (speed) from to (sector) (sector)
- b. Stability Class: ABCDEFG (Circle One)
- c. Precipitation Yes No
. (Circle One)
- 5. Radiological Data
- a. Radioactvity (check one)
( ) Has been released
( ) Has not been released Pv21@0A <&82)
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- 5. b. Release Time
- c. Reactor Trip Time
- d. Location / Source of Release
- 6. Current Release Rates
- a. I-131 Equivalent Ci/second '
- b. Noble Gas Ci/second *
- c. Particulates Ci/second
- 7. Two-hour plume centerline projected dose at:
Distance Sector k* hole Body Child Thyroid Dose (REM) Dose Commit =ent (REM)
Site Boundary 2 miles 5 miles 10 miles
- 8. Plume arrival time offsite:
2 mi 5 mi 10 mi Ruth Fisher School Arlington S'chool
- 9. Estimated duration of release minutes Pv2'6 0004 i8<82)
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- 10. The Fo11cwing E=ergency . Measures Including Protective Actions are Recc== ended: ,
- 11. The Fo11 cuing Emergency Response Actions are Underway:
- 12. We Recuest the Fo11cving Onsite Support and Assistance frc= Offsite
(.
Sources:
i
- 13. Our Prognosis of the E=ergency is that Conditions:
Are Under Control Can Be Expected to Terminate Within hours Are Worsening
- 14. Other Information:
10 a) Power Prior.to Event b) Current Power en mode '
c) 5tede of Operettien Till Correction d) Estimated Ti=e to Restart l
- 15. THIS IS (IS NOT) A DRILL!! (Circle One) l
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IMPLEMENTING PROCEDURE EPIP-03 Page 1 ef,1 REVISION NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTICNS 10 Page 17 of 26 E>ERGENCY TERMINATION MESSAGE FORM
- 1. Verbatim text of message: THIS IS (IS NOT) A DRILLt! (Circle Cne)
THIS IS PALO VEREE NUCLEAR GENERATING STATION. THE (NOTIFICATICS OF CNUSCAL EVENT) (ALERT) (SITE AREA EMERGENCY) (GENERAL E}ERGENCY)
(circle approprite classification) DECLARED AT -
HAS BEEN TERMINATED AT (Time) (Date)
(Time) (Date)
- 2. This is __ , at Palo (Name) (Titic)
Verde Nuclear Generating Station Unit .
- 3. PALO VERDE AUTHESTICATOR (Authenticator Letters)
)
- Approved:
(SS/EC/EOD) Date/ Time
. i PV216 0004 e&42
CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX P IMPLEMENTING PROCEDURE EPIP-03 Page 1 of 3 REVISION NOTIFICATION OF CNUSCAL EVENT IMPLEMENTING ACTIONS 10 Page 18 of 26 INSTRUCTIONS FOR COMPLETING APPENDIX C, D OR E 1.0 INITIAL EMERGENCY MESSAGE FORM (APPENDIX C)
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l.1 Fill in data required by steps 1 and 2 of Appendix C, " Initial Emergency Message Form." Obtain authenticator from the confidential envelope marked on the outside with the appropriate month and drill sequence number (if it is a drill). -
1.2 Obtain from the Radiation Protection Monitor (onshift) data required to complete step 3 of Appendix C.
l.3 Circle appropriate wording of step 4 of Appendix C.
NOTE When the NAN ring button is pushed and it
, appears that all the receiving stations are on line, or, the ring has stopped, the PVNGS originating station shall initiate a roll call in the order listed below. (Consider the time of day)
NOTE ,
If the NAN dedicated telephone fails, refer to Appendix G, " Notification Alert Network (NAN)
Radio Backup" for instruction en using channel 8, KON-Sil, for notifications.
1.4 By means of a single call on the Notification and Alert Ngt dedicated telephone, contact the following State / County agencies listed in Appendir A.
Duty Hours (3:00 a.m. to 5:00 p.m. Monday-Friday)
Maricopa County Sherif fs Office Maricopa County Department of Civil Defense and E=ergency Services Arizona Department of Public Safety Arizona Division of Emergency Services Arizona Radiation Regulatory Agency Off-Duty Hours (3:00 p.m. to 8:00 a.m., Monday-Friday, all day Saturday, Sunday and Holidays)
Maricopa Covncy Sheriff's Office Department of Public Safety PV2'6 000A a$ita
CONTROLLED BY USER PROCECURE PVNGS EivlERGENCY PLAN .-.
NO. APPENDIX IMPLEMENTING PROCEDURE EPIP-03 Page 2 of 3 REVISION NOTIFICATICN OF CNUSUAL EVENT IMPLEMENTING ACTICNS 10 Page 19 of 26 1.5 In the event that an offsite govern =ent agency (or agencies) does not answer the NAN phone or NAN backup radio during a test, drill, or actual emergency, the nuclear operator (or STSC Com=unicator) shall notify the agency via : gular PBX telephone (numbers listed in App. A) 1.6 When con:act is made, the caller shall identify himself and reques: that the individuals obtain a copy of the appropriate Emergency Message Form.
1.7 When each individual has obtained a copy, read the co=pleted Emergency Message Form verbatim and request MCSO to read back verbatim.
1.8 Offer to repeat infor=ation , and reiterate as necessary.
NOTE
. - - - - .- = . . . - . . . . - . . . . . . . . . . . - . . . . . . . . . -
' , To verify the group page activation, monitor the pager installed in the STSC. Be aware that as
(,' ' cuch as t'.o (2) minutes may'. lapse between dial-up and the broadcast announcement.
fcA 1.9 Notify additional personnel as listed in Appendix A a; .;.;;;;rf tc.
and infor= them of the situation. Provide the following message for both Group Paging Systems Notification /Callout:
, "THIS IS PVNGS, UNIT ___, CLASSIFICATION ONE, PLEASE RESPOND APPROPRIATELY" (Repeat message once).
1.10 If an individual requests information not contained in the Emergency Message Form, make reasonable efforts to obtain and give the information only after all initial notifications have '
been made.
1.11 Con:act the NRC via the Emergency Natification System (ENS) .
dedicated telephone within 60 minutes of declaring an emergency.
If the ENS phone fails, use commercial phone or HPN phone as an alternate line. , j 1.12 When con:ac: is made, the caller shall identify himself and read the comple'ced Emergency Message Form verhttim (omit the Palo Verde Auchen:1cator).
1.13 Offer to repeat information and reiterate as necessary.
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NOTE If the emergency is non-radiological in nature, steps 4-9 may be deleted.
2.2 Obtain from the Radiation Protection Monitor data required to complete steps 4-9.
2.3 Obtain from the E=ergency Coordinator data required to complete steps 10-14 2.4 Circle appropriate wording in step 15.
2.5 Dispense information when requested by offsite agencies (NRC or
,, ARRA).
3.0 EMERGENCY TERMINATION MESSAGE FORM (APPENDIN El 3.1 Fill in data required by steps 1-3 to Appendix E, "E=ergency Termination Message Form."
3.2 Obtain approval from SS/EC/EOD.
3.3 Transmit termination per Appendix A.
NOTE To verify the group page activation, monitor the pager installed 'n the STSC. Be aware that as much as two (2) uinutes may lapse between dial-up and the broadcast announcement.
3.4 k' hen using the Group Paging Systems to announce event termination, use the following message:
"THIS IS PVNGS, UNIT , EMERGENCY TERMINATED. PLEASE CANCEL RESPONSE TO EMERGENCY."
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PROCEDURE PVNGS EMERGENCY PLAN N O. i APPENDIX e IMPLEMENTING PROCEDURE EPIP-03 Page 1 of 2 NOTIFICATION OF CNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page il of 26 NOTIFICATION ALERT NETOWRK (NAN) RADIO BACKUP CHA.UEL 8 - KON511 In case of failure of the NAN'ringdown telephone, the NAN backup is Channel 8 on the PVNGS radio. FCC regulations require the Palo Verde designator
'KON-311' be used to precede.and conclude all outgoing ce=munications.
- 1. Take control of the radio channel by saying: "All stations this net," (Repeat) "All stations this net, this is K-0-N 3-1-1 Palo Verde to all 3-1-1 stations, stand by for Warning, Point roll call."
- 2. Wait 30 seconds to allow the offsite agencies to get to their radios, then repeat the previous transmission.
"- NOTE k After 5 P.M. weekdays, all day Saturday, Sunday or holidays, Maricopa County Sheriff's Office (MCS0) and Department of Public Safety (DPS) will be the only agencies responding.
- 3. Initiate roll call of the offsite govern =ent agencies, allowing stations on the net to respond.
3.1 "5-1-1 Palo Verde to 5-1-1 Maricopa County Sheriff's Office. Do you copy?" Allow response: "5-1-1 MCSO copies."
3.2 "5-1-1 Palo Verde to 3-1-1 Maricopa County Department of Civil Defense & Emergency Services. Do you copy?" (MCDCD&ES).
Allow response: "5-1-1 Civil Defense copies."
3.3 "5-1-1 Palo Verde to 5-1-1 Department of Public Safety. Do you copy?"
Allow response: "5-1-1 DPS copies."
3.4 "5-1-1 Palo Verde to 5-1-1 Arizona Division of Emergency Services. D9 you copy?"
Allow response: "5-1-1 ADES (State EOC) copies."
3.5 "5-1-1 Palo Verde to 5-1-1 Arizona Radiation Regulatory Agency.
Do you Copy?"
, Allow response: "5-1-1 ARRA copits."
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-- PVNGS EMERGENCY PLAN NO. APPESTIX G IMPLEMENTING PROCEDURE EPIP-03 Page 2 of.2 NOTIFICATION OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 22 of 26 NOTIFICATION ALERT NET.'ORK (NAN) RADIO BACKUP (CCST'D)
CHANNEL 8 - KCN511
- 4. Upon ccepletion of roll call, transmit the notification message verbatim. Take an acknowledge =ent roll call, allcwing MCSO to read the message back in its entirety, and provide assistance or clarification, as needed. .
- 5. Upon completion of the secend roll call, anncunce: "K-0-N 3-1-1 Palo Verde off." This is the required FCC sign-off.
- 6. Continue notifications per Step 1.8 of Appendix F.
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PROCEDURE Appg3, PVNGS EMERGENCY PLAN NO.
EPIP-03 Page 1 -
IMPLEMENTING PROCEDURE NOTIFICATION OF C'iUSUAL 10 Page 23 of 26 EVE.NT IMPLEMENTISG ACTICSS PROTECTIVE ACTION REC 01DfESDATICSS Classification Protective Actions Category Recommendations Inform state and county Notification of Unusual Event- authorities of SUE status /
events are in progress which indicate a potential cause and based on the degradation of the' level of situation recommend that safety of the plant; however, no protective action is necessary or to standby no releases of radioactive for an update due to material requiring offsite potential degradation response / monitoring are of plant safety.
expected unless further degradation of safety systems occur.
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NOTIFICATICS OF UNUSUAL EVENT IMPLEMENTING ACTIONS 10 Page 21 of 26 EMERGESCY CCCRDINATOR RESPONSE POSITION FILLED BY: Onshift Organi:stion
- 1) Shift Suparvisor of the designated unaffected unit
, 2) Shift Supervisor of the affected unit
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RESPONSIBILITY: The individual onsite with the respensibility and authority to immediately and unilaterally initiate emergency actions, including providing notification and protective action rec.o=mendations to govern = ental authorities responsible for implementing offsite emergency measures. Provide overal.1 direction and control of the ONSHIFT Emergency response.
. INITIAL RESPONSE
-' 1. Ensure plant wide public address announcement is made as per steps 4.3.1.3 and 4.3.1.4 of this procedure.
- 2. Activate the Satellite STSC per EPIP-11, " Technical Support
, Center / Satellite TSC Activation."
- 3. Commence notification process per Appendix F or direct the STSC Communicator to do same.
4 Notify unaf fected unit control rooms of situation.
S. Verify personnel resources are on standby in the OSC.
- 6. Provide plant wide publ,1c address announce=ent when the the STSC fs activated.
- 7. Implement EPIPs according to the situation that resulted in the classification.
j SUBSEQUENT RESPONSE
- 8. As necessary, direct implementation of EPIP-23, " Fire Fighting" and EPIP-22, " Personnel Injury."
(1) For a fire, dispatch the Fire Team and order the Security Director to contact the Bechtel or alternate Fire Departmen. for assistance (if required)
W2'S OCCA 18<821
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PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX I IMPLEMENTING PROCEDURE EPIP-03 Page 2 of 2 NOTIFICATION OF UNUSUAL EVENT IMPLEMEFTING ACTIONS 10 Page 25 of 26 EMERGENCY COORDINATOR RESTONSE H
(2) For personnel injury, contact the First Aid Station and inform them i l
of the situation. Dispatch a First Aid Team, if necessary, and j l coordinate any required offsite assistance.
- 9. Determine the need for additional personnel and directthe Security Director to initiste call out. -
)
l 10. If it is determined that the OSC is not required to support the emergency response, notify the OSC to deactivate and allow the response personnel to return t.o normal work stations. )
- 11. As cppropriate, complete Follow-up Emergency Message Form.
- 12. Reevaluate the emergency classification as conditions change per EPIP-02, l
reclassify as necessary. Keep PVNGS Plant Manager informed as to status of event. l
- 13. Reassess corrective and protective actions. Verify activities under.ay.
Recoverv 14 Consult with the PVNGS Plant Manager prior to closing out emergency.
- 15. Complete notifications per Appendix F when emergency is closed out or direct the STSC Communicator to do the same.
- 16. Provide termination announcement or direct Shif t Supervisor to provide sam'c per steps 4.3.4.2 and 4.3.4.3 of this procedure. -
- 17. Notify PVNGS Compliance at ex event termination. Provide logs as requested.
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ApFENDIX J IMPLEMENTING PROCEDURE EPIP-03 Page 1 of 1 SOTIFICATION OF UNUSUAL EVEST IMPLEMESTISG ACTICSS 10 Page 26 of 26 STSC COMMUNICATCR RESPOSSE POSITION FILLED BY: Nuclear Operator from affected unit RESPONSIBILITY Initiate the notification process as directed by the onshift Emergency Coordinator. Ensure oparability of communications equipment. Maintain c:mmunications logbook.
IMMEDIATE ACTIONS STSC Activation
- 1. Report to the STSC upon notification.
Notification of UNUSUAL EVENT
)
- 2. Complete the Initial Emergency Message Form as directed by the om hift E=ergency Coordinator or Shift Supervisor.
- 3. Initiate notification process t.s directed *by Emergency Coordinator
(,f (or Shift Supervisor, in his absence). (
4.
Inform Emergency Coordinator when initial notifications are complete.
- 3. Contact the Security Director and inform him to call in additional personnel if so directed by Emergency Coordinator.
6.
Complete the Follow-up Message Form as directed by the Emergency Coordinator.
- 7. Provide follou-up information when requested by the State / County agencies.
- 8.
Maintain records of communications received or tra.tsmitted offsite.'
- 9. Complete Emergency Termination Message Form as directed by the onshift Emergency Coordinator or Shift Supervisor upon event termination.
- 10. Transmit termination per Appendix A.
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PVNGS EMERGENCY PLAN QCEDURE IMPLEMENTING PROCEDURE EPIP-04
- ALERT SITE AREA AND GENERAL EMERGENCY IMPI2MENTING ACTIONS 11 Page 2 of 33 REVISION HISTORY Rev. No. Date Revised Pages Comments 5 2-28-85 All Revised Procedure and Appendicies; added steps to clarify procedure and added
. appendix to provide NAN backup instructions 6 10, 11 and 17 Incorporated PCN #01 of Rev. .
! and added step for 4
x cancellation of emergency J. with group page.
7 3.5,7,8, Added termination message ,,
9, 10, 13 form and instructions; 14, 17, 18, Capitalized announcements to 19, 20, 22, make easy to indentify; 24, 25, & 27 Added step for announcement if accountability is performed; Changed and
_ updated all referrals to
-- various appendices. Also added note to provide guidance on notifications.
Added information on 15 minute time requirement.
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PVNGS EMERGENCY PLAN $CEDURE IMPLEMENTING PROCEDURE EPIP-04 REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 3 of 33 REVISION HISTORY Rev. No. Date Revised Pages Comments 8 09-10-85 4,6,9,11,12 Revised to add new plans (l's 13,14,21,22 STSC Communicate checklist, 26,27,29,30 and specific instructions 33,34,36,37, for annnuncements 38 9 01-15-86 4,9,10,11,13, Incorporated PCN (11 and 2 of 14,15,16,18 Rev. 8, deleted time /
N, 19,26,27,28, initials column in 29,30,31,32, Append!ces I and J.
33,34,35,36, _
37,38 l
10 Consolidated EPIP-04, _
EPIP-05.and EPIP-06.
11 Ylb-AG All Complete Rewrite
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[ROCENRE
- IMPLEMENTING PROCEDURE EPIP-04 ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 4 of 33 TABLE OF CONTENTS SECTION ,
PAGE NUMBER 1.0 OBJECTIVE 5
2.0 REFERENCES
5 3.0 LIMITATIONS AND PRECAUTIONS 6 4.0 DETAILED PROCEDURE . 6 4.1 Personnel Indoctrination / Responsibilities 6 ,
4.2 Prereauisites 7 4.3 Instruc.tions 7 APPENDICES '
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Appendix A - Emergency Notification Call List - Emergency 11 Coordinator /STSC Communicator l Appendix B - Emergency Notification Call List - PVNGS Security 12 Appendix C - Initial Emergency Message Form 13 Appendix D - Followup Emergency Message Form 14 Appendix E - Emergency Termination Message Form 17-Appendix F - Instructions for Completing Appendix C, D or E 18 Appendix G - Notification Alert Network (NAN) Radio Backup 21 !
Appendix H - Protective Action Recommendativa. 23 Appendix I - Emergency Coordinator Response -
25 Appendix J - STSC Communicator Response 32 a
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2.0 REFERENCES
2.1 Implementing References -
2.1.1 EPIP-02, " Emergency Classification" 2.1.2 EPIP-11, " Technical Suppory Center / Satellite TSC Activation" 2.1.3 EPIP-12, " Operations Support Center Activation" 2.1.4 EPIP-13, " Emergency Operations Facility Activation" 2.1.5 EPIP-14A, " Release Rate Determination"
.)
2.1.6 EPIP-14B, " Initial Dose Assessment"
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2.1.7 EPIP-15, " Protective Action Guidelines" 2.1.8 EPIP-16, "Inplant Surveys and Sampling" 2.1.9 EPIP-17. "Onsite/Offsite Surveys and Sampling" 2.1.10 EPIP-18, " Emergency Exposure Guidelines" -
2.1.11 EPIP-19, "Onsite Evacuation" 2.1.12 EPIP-20, " Personnel Assembly and Accountability" 2.1.13 EPIP-21, " Search and Rescue" 2.1.14 EPIP-72, " Personnel Injury" 2.1.15 EPIP-23, " Fire Fighting" 2.1.16 EPIP-24, " Security" 2.1.17 EPIP-25 " Reentry for Recovery Operations" 2.1.18 EPIP-26 " Potassium Iodide (KI) Administration"
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IMPLEMENTING PROCEDURE EPIP-04 REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 6 of 33 2.1.19 EPIP-31, " Recovery" 2.1.20 EPIP-33, "Offsite Assistance" 2.1.21 71AC-9ZZ01, " Event Related Reporting" 2.1.22 9N219.05.00, " Document / Record Turnover Control" 2.2 Developmental References 2.2.1 NUREG-0654, Rev.1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 PVNGS Emergency Plan, Rev. 6 3.0 LIMITATIONS AND PRECAUTIONS I 3.1 Continued surveillance and asses'sment of plant conditions are G
necessary to ensure that the emergency classification is appropriately revised as conditions change or more definitive information is obtained. .
3.2 Notifications to State / County Agencies per Appendix A, " Emergency Notification Call List-Emergency Coordinator /STSC Ccmmunicator" shall commence within 15 minutes of declaration of an emergency.
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3.3 The ENS must be manned continuously at the NRC's request.
4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 The Shift Supervisor or Emergency Coordinator shall be responsible for initiating and completing implementing ,
actions of this procedure.
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. IMPLEMENTING PROCEDURE EpIp 04 -
REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 7 of 33
. 4.2 Prerequisites 4.2.1 The emergency has been classified per EPIP-02, " Emergency Classification."
_ 4.3 Instructions 4.3.1 The affected unit Shift Supervisor shall perform the following:
NOTE Designated Unaffected Unit Shift Supervisors are:
Affected Unit Unaffected Unit Shift Supervisor Unit 1 Unit 2 Unit 2 Unit 1
, Unit 3 Unit 2
. Entire Site , Unit 1 4.3.1.1 Notify the Shift Supervisor of the designated unaffected ur.it (or Shift Supervisor of an unaffected unit) to , , .
report to the Control Room of the affected unit and assume the duties of the Emergency Coordinator.
4.3.1.2 The Emergency Coordinator shall provide overall direction and control of the ONSHIFT emergency response as per Appendix I - Emergency Coordinator Response.
NOTE .
The Satellite TSC Communicator shall respond as per Appendix J, "STSC Communicator Response."
4.3.'. 3 Direct the Satellite TSC Communicator (or Government Liaison Engineer) to fill out Appendix C, " Initial Emergency Message Form," in acccrdenca with instructions provided in Appendix F, and make notifications per
- Appen, dix A.
4.3.1.4 Notify the Control Rooms of the unaffected units.
4.3.1.5
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Recommend protective actions in accordance with Appendix H, " Protective Action Recommendations".
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ALERT SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 8 of 33 NOTE Assembly and accountability may be performed at the Emergency Coordinator's discretion during an ALERT. It shall be ,
performed during a SITE AREA or GENERAL . l EMERGENCY classification. Evacuation shall be at the Emergency Coordinator's discretion during any classification.
ACCOUh*rABILITY NOT PERFORMED 4.3.1.6 Ensure the following announ is made over the plant wide telephone page (phone no "ATTE.NTION ALL PLANT PERSONNEL, AN EMERGENCY SIWATIOM CLASSIFIED AS EXISTS IN UNIT . ALL AFIECTED UNIT EMERGENCY RESPONSE PERSONNEL AND ALTERNATES
, REPORT TO YOUR EMERGENCY LOCATION. ALL OTHER PERSONNEL
- STANDBY UNTIL FURTHER NOTICE. (Provide instructions on j route (s) or area (s) to avoid as appropriate and repea
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the announcement).
4.3.1.7 Ensure the announcement in step 4.3.1.6 is repeated over the site sarning siren /public address system.
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i ACCOUNTABILITY PERFORMED 4.3.1.8 Ensure the accountability signal is sounded for approximately one (1) minute to alert personnel. )
4.3.1.9 Ensure the following announcem t made over the plant -
wide telephone page (phone n -
"ATITKrION ALL PLANT PERSONNEL. AN E ifERGENCY SITUATION CLASSIFIED AS EXISTS IN UNIT . ALL AFFECTED UNIT EMERGENCY RESPONSE PERSONNEL AND ALTERNATES REPORT TO YOUR EMERGENCY LOCATION. ALL OTHER PERSONNEL REPORT
, TO YOUR ASSIGNED ASSEMBLY AREA." (Provide instructions on route (s) or area (s) to avoid as appropriate).
4.3.1.10 Ensure the announcement in step 4.3.1.9 is repeated over the Site Warning Siren /Public Adddress System.
4.3.1.11 Ensure the accountability signal is resounded and steps 4.3.1.9 and 4.3.1.10 are repeated once.
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IMPLEMENTING PROCEDURE EpIp.os REVISION t ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 9 of 33 4.3.1.12 Ensure that the actions of the appropriate Recovery procedures have be(n implemented.
4.3.1.13 Direct the STSC Communicator (or Government Liaison Engineer) to prepare Appendix D, " Followup Emergency Message Ferm" in accordance with instructions provided in Appendix 7.
4.3.2 PVNGS Security, after being notified by the Emergency Coordinator or STSC Communicator that an emergencT situation is in progress or he: occurred, or has been terminated, shall complete Apphndix B " Emergency Notification Call List -
PVNGS Security," and notify these individuals or departments of the situation.
4.3.3 Emergency Situation Terminated NOTE
/
/
1 Sound the 'A11~ Clear' signal only if I assembly and accountability has been initiated.
4.3.3.1 The Shift Supervisor (or Emergency Coordinator) shall ensure the All Clear signal is sounded for approximately (1) minute and that the following announce 4 made i over the plant wide telephone page (phone n -
l "AT17.NI' ION ALL PERSONNEL. THE EMERGENCY
! SITUATION DECLARED IN UNIT HAS NOW -
(
3EEN TERMINATED". (Provide special
. instructions as necessary) 4.3.3.2 Ensure the announcement in step 4.3.3.1 is repeated over the Site Warning Siren /Public Address System.
4.3.3.3 Ensure steps 4.3.3.1 and 4.3.3.2 are repeated once, i 4.3.3.4 Direct the STSC Communicator (or Government Liaison Engineer) to fill out Appendix E, " Emergency Termination Message Form," per instructions provided in Appendix F.
4.3.3.5 Direct the STSC Communicator (or Gover unent Liaison Engineer) to transmit the termination per Appendix A.
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IMPLEMENTING PROCEDURE EPIP-04 REWSION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 10 of 33 k 4.3.3.6 At closeout or reduction of the emergency classification. l th if t NG olian .at I eX request a written summary be provi offsite authcrities within eight (8) hours. S.S./E.C. shall I provide copies of shift logs, control room logs, etc., as requested by Compliance for preparation of the report.
Record Retention 4.3.4 1 -
f 4.3.4.1 A copy of Appendices A, B, C, D and E shall be turned over to the Emergency Planning Dept., tail station 6010, for their review. The Operations Dept. will forward the
(~ originals to DDC for proper storage in accordance with 9N219.05.00, " Document / Record Turn Over Control."
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APPENDIX C
.- IMPLEMENTING PROCEDURE EPIP-04 Page 1 of'l REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 13 of 33 INITIAL EMERGENCY MESSAGE FORM NOTIFICATION OF UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY
- 1. Verbatim text of Message: THIS IS (IS NOT) A DRILL (Circle One) THIS IS PALO VERDE NUCLEAR GENERATING STATION (NOTIFICATION OF UNUSUAL EVENT)
(ALERT) (SITE AREA EMERGENCY) (GENERAL EMERGENCY)
(circle applicable classification) declared at -
- Wind is from degrees - At mph.
(time) (date) (speed)
PALO VERDE AUIEENTICATOR (authenticator letters)
- 2. This is , at the Palo Verde Nuclear Generating Station (name/ title)
Unit .
- 3. (Circle One)
(a) There is @, repeat M, radioactive release taking place and no
,1 special protective actions are recommended at this time.
OR (b) There is M , repeat M , radioactive release in excess of allowable --
operating limits and @ protective actions are recommended at this time.
OR (c) There is @, repeat @, radioactive release taking place at this time. However, the following protective actions are re..ommended.
Sectors Distance (Miles)
OR (d) A radioactive release IS, repeat H , taking place. We reco'mmend that people in affected sectors remain indoors with windo'is and doors closed. ;
Sectors Distance (Miles) !
OR (e) A radioactive release H , repeat IS, taking place. We recommend that evacuation of affected sectors be considered.
Sectors Distance (Miles)
- 4. THIS IS (IS NOT) A DRILL (Circle One)
's Approved (EC/EOD) Date Time CONTROLLED BY USER
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[ROCEDURE o APPENDIX D IMPLEMENTING PROCEDURE EPIP-04 Page 1 of'3 ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 14 of 33 FOLLOW-UP EMERGENCY MESSAGE FORM
- 1. Verbatim text of Message: THIS IS (IS NOT) A DRILL (Circle One) THIS IS A PALO VERDE NUCLEAR GENERATING STATION follow-up information message concerning the (NOTIFICATION OF UNUSUAL EVENT) (ALERT) (SITE AREA EMERGENCY) (GENERAL EMERGENCY)
(circle applicable classification) declared at -
(time) (date)
- 2. This is ,'at Palo Verde Nuclear Generating Station (name/ title)
Unit .
- 3. Brief description of event _
i
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- 4. Meteorological Data
- a. . Wind direction from (degrees) - at miles per hour (direction) (speed) from to (sector) (sector)
- b. Stability Class: ABCDEFG (Circle One)
- c. Precipitation Yes No (Circle One)
- 5. Radiological Data
- a. Radioactivity (check one)
( ) Has been released
( ) Has not been released
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[Ra- APPENDIX D IMPLEMENTING PROCEDURE Er r-es ra;c 2 cf 3 REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 15 of 33
- 5. b. Release Time
- c. Reactor Trip Time
- d. Location / Source of Release
- 6. Current Release Rates
- a. I-131 Equivalent Ci/second -
- b. Noble Gas Ci/second
- c. Particulates Ci/second
- 7. Two-hour plume centerline projected dose at:
Distance Sector Whole Body Child Thyroid Dose (REM) Dose Commicment (REM) i j Site Boundary .__
-~
2 miles 5 miles 10 miles -
- 8. Plume arrival time offsite:
2 mi 5 mi 10 mi Ruth Fisher School Arlington School
- 9. Estimated duration of release minutes
- 10. Following Emergen'cy Measures Including Protective Actions are '
Recommended:
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EMERGENCY IMPLEMENTING ACTIONS 11 Page 16 of 33
- 11. The Following Emergency Response Actions are Underway:
- 12. We Request the Following Onsite Support and Assistance from Offsite Sources: -
- 13. Our Prognosis of the Emergency is that Conditions:
'. Are Under Control Can be Expected to Terminate Within hours Are Worsening
, 14. Other Information:
- a) Power Prior to Event (*.)
b) Current Power or Mode -
c) Mode of Operation till Correction d) Estimated Tima to Restart l
l 15. THIS IS (IS NOT) A DRILL (Circle One) 1
[1 t Approved:
(EC/E0D) , Date/ Time i
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, APPENDIX E IMPLEMENTING PROCEDURE EPIP-04 1 Page t or i REVISION ALLRT, SITE AREA Ah"J GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 17 of 33 EMERGENCY TERMINATION MESSAGE FORM
- 1. Verbatim text of messageP THIS IS (IS NOT) A DRILL!! (Circle One)
THIS IS PALO VERDE NCCLEAR GENERATING STATION. THE (NOTIFICATION OF UNUSUAL EVENT) (ALERT) (SITE AREA EMERGENCY) (GENERAL EMERGENCY)
(circle approprite classification) DECLARED AT -
HAS BEEN TERMINATED AT (Time) (Date)
(Time) (Date)
.l 2. This is , at Palo (Name) (Title)
Verde Nuclear Generating Station Unit .
- 3. PALO VERDE AUTHENTICATOR .
(Authenticator Letters)
.7.
Approved:
(EC/EOD) Date/ Time 1
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CONTROLLED BY USER PVNGS EMERGENCY PLAN $ cewne APPENDIX E IMPLEMENTING PROCEDURE EPIP-04 Page 1 of 3 ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 18 of 33 INSTRUCTIONS FOR COMPLETING APPENDIX C, D OR E 1.0 Initial Emetgency Message Form (Appendix C) 1.1 Obtain Authenticator from the confidential envelope marked on the outside with the appropriate month and a drill sequence number (if it
.; is a drill).
, 1.2 Using ERFDADS, call up the current meteorological dats using the fifteen minute average channel and thirty-five foot data.
1.3 Fill in data required by Steps 1 and 2 of Appendix C, " Initial Emergency Message Form."
1.4 Obtain from the Radiation Protection Monitor (onshift) or the Radiological Assessment Coordinator (if EOF is activated) data required to complete Step 3 of Appendix C.
1.5 Circle appropriate wording of Step 4 of Appendix C.
- ^
NOTE When the NAN ring button is pushed and it appears that all the receiving stations are on line or the ring has stopped, the PVNGS originating station shall initiate a roll call
, in order listed below. (Consider the time of day)
NOTE If the NAN dedicated telephone fails, refer to '
Appendix G, " Notification Alert Network (NAN)
Radio Backup," for instructions on using channel 8, KON-511, for notification.
1.6 By means of a single call on the Notification and Alert Net dedicated telephone, contact the following State / County agencies listed in Appendix A.
Duty Hours (8iOO a.m. to 5:00 p.m. Monday-Friday)
Maricopa County 'iheriff's Office Maricopa County Jepartment of Civil Defense and Emergency Services Arizona Depart =er.t of Public Safety
-/
Arizona Division of Emergency Services Arizona Radiation Regulatory Agency.
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PVNGS EMERGENCY PLAN N O. APPENDIX F Page 2 of'3 IMPLEMENTING PROCEDURE EPIP-04 REVISICN ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 19 of 33 Off-Duty Hours (5:00 p.m. to 8:00 a.m., Monday-Friday, all day Saturday, Sunday and Holidays)
Maricopa County Sheriff's Office Department of Public Safety 1
1.7 In the event that an offsite government agency (or agencies) does not answer the NAN phone or NAN backup radio during a test, drill !
or actual emergency, the nuclear operator (or STSC Cocmnnicator) l shall notify the agency via regular PBX telephone (numbers listed
, in Appendix A). -
1.8 When contact is made,'the~ caller shall identify himself and .
request that the individuals obtain a copy of the appropriate l Emergency Message Form.
1.9 When each individial has obtaine'd a copy, read the completed Zmergency Message Form verbatim and request MCSO to read back 3 verbatim. Perform warning point roll call.
a 1.10 Offer to repeat information and reiterate as necessary.
NOTE ,,
, To verify the group page activation monitor the pager installed in the STSC. Be aware that as much as two (2) minutes may lapse between dial-up
, and the broadcast announcement.
1.11 Notify additional personnel as listed in Appendix A and inform -
them of the situation. Provide the following message for both Group Paging Systems Notification /Callout:
"THIS IS PVNGS, UNIT , CLASSIFICATION 'IVO, PLEASE RESPOND APPROPRIATELY." (Repeat message once).
1.12 If an individual requests information not contained in the Emergency Message Form, make reasonable efforts to obtain and give the information only after all initial notifications have been made. ,
1.13 Contact the NRC via the Emergency Notification System (ENS) dedicated telephone within 60 minutes of declaring an emergency.
, If the ENS fails, use the commercial telephone as an alternate line.
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'- EPIP-04 IMPLEMENTING PROCEDURE hge 3 of 3 EWSION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 20 of 33 1.14 When contact is made, the caller shall identify himself and read the completed Emergency Message Form verbatim (omit the Palo Verde Authenticator).
, 1.15 Offer to repeat information and reiterate as necessary.
2.0 Follow-up Ercergency Message Form (Appendix D) 2.1 Fill in data required by Steps 1-3 of Appendix D, " Follow-up Emergency Message Form."
t NOTE If the emergency is non-radiological in nature, steps 4-9 may be deleted.
2.2 Obtain the 'Aadiation Protection Monitor or the Radiological
- w Assessment Coordinator (if EOF is activated) data required to
) complete Steps 4-9.
>2. 3 Obtain the Emergency Coordinator or the Technical Analysis Coordinator (if EOF is activated) data required to complete Steps _.,
10-14.
- 2.4 Circle appropriate wording in Step 15.
2.5 Dispense information when asked by offsite Agencies (NRC or AF3A).
3.0 EMERGENCY TERMINATION MESSAGE FOR!f (APPENDIX E) 3.1 Fill in data required by steps 1-3 of Appendix E. " Emergency Termination Message Form."
3.2 Obtain approval from EC/EOD.
3.3 Transmit termination per Appendix A.
NOTE To verify *the group page activation monitor the pager installed in the STSC. Be aware that as -
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much as two (2) minutes may lapse between dial-up and the broadcast announcement.
3.4 When using the Group Paging Systems to announce event termination, use the following message:
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EMERGENCY Ili?LEMENTING ACTIONS 11 Page 21 of 33 NOTIFICATION ALERT NE'1VORK (NAN) RADIO BACKUP Channel 8 - KON511 In case of failure of the NAN ringdown telephone, the NAN backup is Channel 8 on the PVNGS radio. FCC regulations require the I'alo Verde Designator 'KON511' be used to precede and conclude all outgoing crmmunications.
- 1. Depress Alert Tone button (on Radio Control Panel) for 3 to 4 seconds, wait for a second. Depress again for 3 to 4 seconds.
- 2. Take control of the radio channel by saying: "All stations this net,"
(Repeat) "All stations this net, this is K-0-N 5-1-1 Palo Verde.
5-1-1 Palo Verde to all 5-1-1 stations, stand by for Warning Point roll. call."
- 3. Wait thirty seconds to allow the offsite agencies to get to their radios, then repeat the previous transmission.
NOTE After 5 P.M. weekdays, all day Saturday, Sunday or .
on holidays, Maricopa County Sheriff's Office '
(MCS0) and Department of Public Safety (DPS) will _
be the only agencies responding.
- 4. Initiate roll call of the offsite government agencies, allowing stations on the net to respond.
4.1 "5-1-1 Palo Verde to 5-1-1 Maricopa County Sheriff's Office. Do you copy?" -
Allow Response: "5-1-1 MCSO copies."
4.2 "5-1-1 Palo Verde to 5-1-1 Maricopa County Department of Civil Defense & Emergency Services. Do you copy?" (MCDCD&ES)
Allow response: "5-1-1 Civil Defense copies."
4.3 "5-1-1 Palo Verde to 5-1-1 Department of Public Safety. Do you copy?"
Allow response: "5-1-1 DPS copies."
4.4 "5-1-1 Palo Verde to 5-1-1 Arizona Divisien of Emergency Services. Do'you copy?"
, Allow response: "5-1-1 ADES (State EOC) copies." ,
, 4.5 "5-1-1 Palo Verde to 5-1-1 Arizona Radiation Regulatory Agency.
Do you copy?"
Allow response: "5-1-1 ARRA copies."
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APPENDIX G~
s IMPLEMENTING PROCEDURE EPIP-os page 2 of 2 REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 22 of 33
- 5. Upon completion of roll call, transmit the notification message verbatum. Take acknowledgement roll call, allowing MCSO to read the message back in its entirety, and provide assistance or clarification, as needed.
- 6. Upon completion of the second roll call, announce: "K-0-N 5-1-1 Palo Verde off." This is the required FCC sign-off.
- 7. Continue notifications per Step 1.11 Appendix F.
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S PROTECTIVE ACTION RECOMMENDATIONS Eg P8 T a::
CONDfTION _ RECOMMEND [Q ACT1ON %%
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- 1. Notification of Unusual Event decla red. Inform state and county authorities or OW C status /cause and, based on situation recommend that no protective action is Q[
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necessary or standby for update If M$ 2M yE
. situation worsens.
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, Z 2. An ALERT has been decla red. Inform state and county authorities or Alert status /cause and recommend that 5 P*
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z o 'O TM d the public be apprised of the situation 4g 3I 2 and stay tuned to EDS/KTAR radio station. yg Q ()
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, O 3. A Site Area Emergency has been declared. Inform state and county authorities of
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F Site Area Emergency status /cause and y$ C> F F consider recommending seeking shelter ZM g} g M within a 2-mile radius or the plant as warranted based on plant /containmo,1t U*
m conditions.
- 4. A Genera l Emergency has been decla red. Shelter within 2-mile radius and 5 milet in potentially arrected sector's.* 'D ZT rn oo C -
i m ~g C M 5. EPA Protective Action Guidelines are in accordance with EPA Protective Action O 3 O N projected to be exceeded. Culdelines: y E g a) whole body thyroid I rem to 5 rems to 5 rems 25 rems flecommend shel ter, as a alnimum, for arrected sectors
- and consider evacuation N %
utilass time constraints make it imp ract ica l .
b) whole t'ody 5 rems Recommend evacuation for arrected thyrold 25 rems sectors
- or shelter rne those areas that cannot be evacua ted lief ~ ore ilume a rriva l, y yg i s " NOTE: Arrected sectors include, as a alnlmum, the dowtwind sector (s) and adjacent U OM sectors. For plumes in sectors P, Q, o r N, two sectors on either sido or the affected sector ;, hall be included in the recommenda tion (e.g. , a plume in sector P shall require consideration of sectors M, N, Q and R).
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- 7 m y q 6. Loss of physical control of the plant Evacuation for 2-mile radius and 5 miles y d 2] Z us3 in potentia l ly a rrected sectors.*
N to intruders, a ao N a o -<
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- 7. Substantial core damage has occurred or is projected to the extent that 20%
Evacuation for 2-mile radius and 5 miles in potentially arrected sectors.* ON mT
- M O f"- F y of fuel clad gap activity is released 8$ C> g p from fuel. ge O 8. Large fission product inventory Evacuation for 5-mile radius and 10 miles O
(greater than fuel clad gap activity) has been released to containment.
Ir. potentially affected sectors.* g m o 'D C 9. Imminent containment ra l l u re i s p ro-Jected such that a " puff" release Shelter for areas that cannot be evacu-ated before plume arrival; evacuation of h
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i Q greater than dosi n leak rate will remainder or 5-mile radius and 10-mile O 3 .m O
8 o u r, in conJuct on with 7. or 8. In potentially arrected sectors.*
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- NOTE: Affected sectors include, as a minimum, the dowrwind sector (s) and adjacent sectors. for plumes in sectors P, Q, or N, two sectors on either side of the arrected sector shall be included in the recommendation (e.g., a plume in sector P shall require consideration or sectors M, N, Q and R). y yby 8
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, PVNGS EMERGENCY PLAN QCEDURE APPENDIX I
. IMPLEMENTING PROCEDURE EPIP-04 Page 1 of'7 REVISION ALERT, SITE AREA AND GENERAL g
EMERGENCY IMPLEMENTING ACTIONS 11 Page 25 of 33 EMERGENCY COORDINATOR RESPONSE STSC ACTIVATED POSITION FILLED BY:
(1) PVNGS Plant Manager (2) Manager, Technical Support (3) Shift Supervisor, Unaffected Unit RESPONSIBILITY: To immediately and unilaterally initiate emergency
' actions, including providing notification and protective action recommendations to Governmental authorities responsible for implementing offsite emergency measures.
Provide for the control and coordination of onsite emergency response.
NOTE Refer to the following pages per i ;- appropriate facility activation.
Facility Activated Appendix I Page
~'
STSC 1-4 TSC/ EOF 5-8
, INITIAL RESPONSE ,
- 1. Receive notification from the Shift Supervisor and report to the Control
' Room of the affected unit and assume the position of ONSHIFT Emergency Coordinator.
- 2. Ensure plant wide public address announcement is made as per steps 4.3.1. 6, 4.3.1. 7 or 4.3.1. 9, 4.3.1.10 of this procedure as appropriate.
- 3. Review plant status, initiating event, corrective actions and emergency classification with the Shift Supervisor per EPIP-02, " Emergency Classification." ,
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~
IMPLEMENTING PROCEDURE EPIP-c4 Page 2 of 7 ALERT, SITE ARFA AND GENERAL
- EMERGENCY IMPLEMENTING ACTIONS 11 Page 26 of 33 N EMERGENCY COORDINATOR RESPONSE STSC ACTIVATED
- 4. Activate the Satellite STSC per EPIP-11, " Technical Support Center / Satellite TSC Activation."
- 5. Commence notification process per Appendix F g direct the STSC Communicator to do so.
(1) Direct the Security Director to call in the PVNGS onsite and offsite Emergency Organization personnel.
- 6. Provide plant wide public address announcement when the STSC is activated.
- 7. Verify personnel resources a:e on standby in the OSC.
- 8. Reevaluate the emergency classification as conditions change per EPIP-02 l.
" Emergency Classification," reclassify as necessary.
I 9. As necessary, direct implementation of EPIP-23, " Fire Fighting" and EPIP-22, " Personnel Injury."
(1) For a fire, dispatch the Fire Team and order the Security Director to " '
contact the Bechtel or alternate offsite fire department for assistance (if required).
(2) For personnel injury, contact the First Aid Station and inform them of the situation. Dispatch a First Aid Team, if necessary, and coordinate any required offsite assistance. -
10.. Determine any additional protective action recemmendations to be provided to state and county response agencies per Appendix H, " Protective Action Recommendations."
- 11. As appropriate, complete Follow-up Emergency Message Form.
4
- 12. Determine the need for offsite support and direct the STSC Communicator to call location (s) in EPIP-33, "Offsite Assit ance" and arrange access with the Security Director per EPIP-24, " Security."
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o PVNGS EMERGENCY PLAN @ CEWRE APPENDIX I IMPLEMENTING PROCEDURE EPIP-04 Page 3 of 7 REVISION ALERT, S HE AREA AND GENERAL y EMERGENCY IMPLEMENTING ACTIONS 11 Page 27 of 33 EMERGENCY COORDINATOR RESPONSE STSC ACTIVATED Personnel Assembly and Accountability (If Assembly / Accountability Performed?
- 13. Within 30 minutes of the accountability signal receive a report on accountability in the protected area from the Security Director.
- 14. Be prepared to implement EPIP-21, " Search and Rescue" by providing neces!,ary data to the OSC Coordinator.
- 15. Receive report on site area accountability.
Emergency Exposures and KI
- 16. Per EPIP-18, " Emergency Exposures Guide'11nes," and as necessary, authorize emergency exposures.
- 17. As necessary, authorize administration of KI per EPIP-26, " Potassium l
Iodide (KI) Administration" to emergency workers desiring to use it.
Consult with the Radiation Protection Monitor.
~~
OSC Activation
- 18. If a release is occurring, consult EPIP-12, " Operations Support Centor Activation," to determine habitability of primary OSC.
also uninhabitable, direct an OSC Coordinator to relocate to a protected area (Control Room / STSC, TSC or EOF).
recurity
, 20. As necessary, implement EPIP-24, " Security" and order the Security Director to limit access to the station. contact the Maricopa County Sheriff's Office for assistance in controlling site access, and arrange access for necessary personnel not on the Emergency Personnel Access List and/or not having access to the protected area via card-key system.
, 21. Ensure the Security Director is apprised of offsite assistance requests to
. arrange access.
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PVNGS EMERGENCY PLAN en caouas NO. APPENDIX I IMPLEMENTING PROCEDURE EPIP-04 Page 4 of '7 REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 28 of 33 EMERGENCY COORDINATOR RESPONSE STSC ACTIVATED Corrective Actions
- 22. Determine needs, consult with staff, authorize reentry per EPIP-25,
" Reentry for Emergency Operations."
Assessment Actions
- 23. Ensure that the Radiation Procction Monitor is obtaining needed data using EPIP-14A, " Release Rate Determination," EPIP-14B, " Initial Dose Assessment," EPIP-16, "Inplant Surveys and Sampling" and EPIP-17, "Onsite/Offsite Surveys and Sampling."
Protective Actions
- 24. Continue to evaluate the need for providing any additional protective action recommendations to state and county agencies.
NOTE The following actions are required only if assembly and accountability have been , , ,
initiated.
- 25. Determine the need for early dismissal /cyacuation of non-essentials per EPIP-19, "Onsite Evacuation."
- 26. Establish evacuation order, offsite reassembly area, evacuation route and inform the Security Director. <
- 27. Order evacuation signal when the Security Director reports that preparations are complete.
TSC Activation and Transfer to Authority
- 28. When relieved by the onsite Emergency Coordinator, provide a briefing and transfer responsibilities.
Even; Termination or Reduct' ion
, 29. Contac Compliance at ext I o~ provide written summary wi it. o ours o offsite I
autnorities. Provide documentation as requested.
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IMPLEMENTING PP.OCEDURE EPIP-04 Faga 5 of i ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 29 of 33 EMERGENCY C0CRDINATOR RESPONSE TSC AND EUF ACTIVATED u
IhTIAL RESPONSE
- 2. Receive a briefing from the onshift Emergency Coordinator and assume responsibilities.
i (J :
5 Per EPIP-13, " Emergency Operations Facility Activation," brief the Emergency Operations Director and transfer the responsibilities for notifications and protective action recommendations. . . .
- 6. Verify personnel resources are on standby in the OSC.
SUBSEQUENT RESPONSE
- 7. Reevaluate the emergency classifications conditions change per EPIP-02, reclassify as necessary. - l l
- 8. As necessary, direct implementatien of EPIP-23, " Fire Fighting" and l EPIP-22, " Personnel Injury." l (1) For a fire, dispatch Fire Team and order the Security Director to contact-the Bechtel or alternate offsite fire department for assistance (if required).
(2) For pesonnel injury, contact the First Aid Station and inform them of l
the situation. Dispatch a First Aid Team, if necessary, and coordinate any required offsite assistance.
- 9. . Determine the need for offsite support and direct a Communicator to call locations (s) in EPIP-33, "Offsite Assistance" and arrange access with the Security Director per EPIP-24 " Security," and coordinate with the Administration and Logistics Coordinator at the EOF.
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, APPENDIX I IMPLEMENTING PROCEDURE EPIP-04 Page 6 of '7 REVISION ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 30 of 33 EMERGENCY COORDINATOR RLSPONSE TSC AND EOF ACTIVATED Personnel Assembly and Accountability (If Assembly / Accountability Performed) -
- 10. Within 30 minutes of the accountability signal, receive e report on accountability in the protected area from the Security Direct r.
- 11. Be prepared to implement EPIP-21, " Search and Rescue," by providing necessary data to the OS:: Coordinator (via Emergency Maintenance Coordinator).
- 12. Receive report on site area accountability Emergency Exposures and KI ~
- 13. Per EPIP-18, "Emer3ency Exposure Guidelines" and as necessary, authorize emergency exposures.
- 14. As necessary, authorize administration of KI per EPIP-26 to emergency workers desiring to use it. Consult with the Radiological Protection ..
Coordinator.
OSC Activation
- 15. If a release is occurring, consult EPIP-12, " Operations Support Center Activation" to determine habitability of primary OSC.
Security
- 17. As necessary, implement EPIP-24, " Security" and order the Security Director to limit access to the station, contact Maricopa County Sheriff's Office for assistance in controlling site access, and arrange access for necessary personnel not on the Emergency Personnel Access List and/or not having access to te protected area via card-key system.
- 18. Ensure the Security Directer is apprised of offsite assistance requests to arrange access.
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EMERGENCY COORDINATOR RESPONSE TSC AND EOF ACTIVATED 1 l l Corrective Action
- 19. Determine needs, consult with staff, authorize reentry per EPIP-25, l
" Reentry for Emergency Operations."
Assessment Actions l l s -
- 20. Ensure that the Radiologica1' Protection Coordinator is obtaining needed '
f, data using EPIP-14A, " Release Rate Determination," EPIP-14B, " Initial Dose Assessment," EPIP-16, "Inplant Surveys and Sampling" and EPIP-17, "Onsite/Offsite Surveys and Sampling." Protective Actions NOTE I The following actions are required only
, if assembly and accountability have been initiated.
- 21. Determine the need for early dismissal / evacuation of non-essentials per EPIP-19, "Onsite Evacuation."
- 22. Establish evacuation order, offsite reassembly area, evacuation route and inform the Security Director. I
- 23. Order evacuation signal when the Security Director reports that preparations are complete.
Reovery f
- 24. Consult with the Emerr,ency Operations Director concerning implementing EPIP-31, " Recovery."
)
Event Termination or Reduction 25 Contact PVNGS Compliance at ext. K to-provide writt'en summary wi in ours to offsite crit s. Provide documentation as requested. w- CONTROLLED BY USER l
CONTROLLED BY USER PROCEDURE
,- PVNGS EMERGENCY PLAN .
NO. APPENDIX J IMPLEMENTING PROCEDURE EPIP-04 Page 1 of.2 ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11 Page 32 of 33 STSC' COMMUNICATOR RESPONSE POSITION FILLED BY: Nuclear Operator from affected unit RESPONSIBILITY: Initiate the notification process as directed by the
~ onshift Emergency Coordinator. Ensure operability of communications equipment. Maintain communications logbook.
IMMEDIATE ACTIONS STSC Activation
- 1. Report to the STSC upon notification.
Notification of A2RT, SITE AREA EMERGENCY, GENERAL EME3GENCY
~
2'. Complete the Initial Emergency Message Form as directed by the Onshift Emergency Coordinator or Shift Supervisor. , NOTE If the emergency situation is terminated before initial notifications are finished, ccmplete the notifications per Appendix A and then repeat Appendix A with the notification of termination. If the emergency is terminated before initial notifications can be started, provide both initiating and terminating messages in the same call.
- 3. Initiate notification process per Appendix F as directed by the Emergency Coordinator (or Shift Supervisor in his absence).
- 4. Inform the Emergency Coordinator when initial notifications are complete.
- 5. Contact the Security Director and inform him to call in additional personnel if so direc,ted by the Emergency Coordinator.
- 6. Prepare the Follow-up Emergency Message Form as directed by the Emergency Coordinator.
- 7. Provide follcw-up information when requested by the State / County agencies.
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' IMPLEMENTING PROCEDURE EPIP-04 APPENDIX J Page 2 of.2 ALERT, SITE AREA AND GENERAL EMERGENCY IMPLEMENTING ACTIONS 11
- Page 33 of 33 Notificaticn of ALERT, SITE AREA EMERGENCY ,
GENERAL EMERGENCY
- 8. Maintain records of communications ansmitted received offsite. or tr Offsite Assistance-
- 9. Contact .
A) via telephone if directed by the Emergency nator. Coordireq e , Appendix
- 10. Appendix Record B). name and time on " Telephone Communicatio .
n Log Sheet," (EPIP-3'3,
- 11. Transfer call to Emergency Coordinator r for cla ifi s. i cation, if necess.'ry. '
- 12. Inform the Emergency Coordinator of contact /l offsite assistance and estimated time of arrivalack of contact, scope of ACTIVATION OF ONSITE EMERGENCY ORGANIZATIO 13.Operations Transfer continuous communications link with th in the TSC.
e NRC to the NRC Liaison -
- 14. Review State / County agencies and NRC to Government or notifying Liaisos -
n Engineer in the EOF.
- 15. Notify the Emergency Coordinator when responsibili i ;
transferred to the Government Liaison Enginee t es have been i r.
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- Continuing Activity.
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Title:
l lDDC Contact (ext. 6o33) l l Orignator: (Print) l nknl L,po-lGnki- Sale /Ak 7-c Acdadb, l gg gf l (Ext. l Unit (s) affected: l
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, l- Does PCN require a 50.59 review? 1 No Yes (refer to 5.1.2) l C I I
l- Does PCN affect activities in l l the RCA? >( No Yes (Copy to ALARA) l l l l- Does PCN effect the non-radiogical l l environment of any offsite area? X No Yes (Contact Compliance) l l l- Is PCN associated with an AC, l l Program, Emerg. Plan or Secur.
- l l Prog., Phase I-IV Test, or a No l Yes (PRS /PRG/TRRG l l ST? review required) l l
l 1 - I i .' l l rsW l l TECHNICAL REVIEWER (Supervisory Level W DatY'.eN l l
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RB/FRG/TRRG 'C f1AN (if requireal NM
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PALO VERDE NUCLEAR GENERATING STATION PROCEDURE CHANGE NOTICE PAGE [ .of / INTENT CHANGE: NO
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- 1. PROCEDURE TITLE 7/,6/L,,,,/ 64,,[,f-/Ad///, ra:e Af d,odce, e
- 2. PROCEDURE NUMBER ENP-/ .REV. f PCN_. 2 2a. Manager concurrence dk DATE to exceed 5 PCNs
- 3. REASON POR PCN: L ,e ,,,6L.,$, Agavouna fa 34),,_,ej,msf
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- 1. PROCEDURE TITLE 'Sc/,mu/ Staw[ Cedr /544/2/, 73rt' //cAvden
- 2. PROCEDURE NUMBER BP/P-// REV. f PCN /
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ENTERED IN PROCEDURE BY: LdG.LJ, ' alx/a CIGNATURE DATE SIGNATURE DATE
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- 8. EPT. !ANAGER: 9. ED RC/TRRC:
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DEPT. HEAD e M/;e# DATE /L 4' I PRB/PRG/TRRG REVIEW / /M DATE / APPROVED BY - DATE /, EFFECTIVE DATE /
- DN-1664A/0296A PV216 CCOA (8/t2) ,
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. CONTROLLED BY USER PVNGS EMERGENCY PLAN o
[ROCEDURE IMPLEMENTING PROCEDURE EPIP-11 TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION ACTIVATION 5 Page 2 of 48 REVISION HISTORY Rev. No. Date Revised Pages Comments 3 5/10/85 ALL Revised to incorporate PCN #01 of Rev. 2 and to reflect actual oolicies and practices of Emergency Planning. 4 9/18/85 3,4,5,6,9,10 Revised to reflect new rev. 15,16,17,19, of E-Plan and to incorporate b',i 20,22,23,24, previous drill comments. 25,26,28,30, 39,42 5 (l44 4 DWekd Geckbds
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F CONTROLLED BY USER PVNGS EMERGENCY PLAN QcEcune IMPLEMENTING PROCEDURE EPIP-11 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION 5 Page 3 of 48 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 5
2.0 REFERENCES
.5 3.0 LIMITATIONS AND PRECAUTIONS 6 4.0 DETAILED PROCEDURE 7 4.1 Personnel Indoctrination / Responsibilities 7 4.2 Prerequisites 8 4.3 Instructions 9 Y' APPENE1CES Appendix A - Shift Technical Advisor Response 12 Appendix B - Radiation Protection Monitor Response 13 Appendix C - Security Director Response 16 Appendix D - Technical Engineering Coordinator (Onsite) 22
Response
Appendix E - Technical Engineering Assistant (Onsite) 24 Response ' Appendix F - Radiological Protection Coordinator (Onsite) 25
Response
PV216 000A (&82) 9
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. CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEDURE o
IMPLEMENTING PROCEDURE EPIP-11 ' TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION I ACTIVATION 5 Page 4 of 48 APPENDICES (CONT'D) v SECTION PAGE NUMBER Appendix G - h7C Liaison - Health Physics Response 31 Appendix H - Emergency Maintenance Coordinator (Onsite) .32
Response
Appendix I - Hazards Control Coordinator (Onsite) Response 34 Appendix J - Operations Advisor (Ou ite) Response 35 Appendix K - Personnel Resources Coordinator (Onsite) 36
Response
Appendix L - Chemistry Coordinator (Onsite) Response 38 Appendix M - Reactor Analyst (Onsite) Response 39 Appendix N - Computer Support Coordinator (Onsite) Response 40 Appendix 0 - Field Team Communicator (Onsite) Response 41 Appenidx P - Information % nitor Response 42 Appendix Q - Operations Coordinator Response ' 43 Appendix R - NRC Liaison, Operations Response 44 Appendix S - Clerical Aide / Status Board Keeper-TSC Response 45 Appendix T - TSC Floor Plan 47 Appendix U - TSC Equipment Layout 48 i 1 PV216-000A $42) e . " , 9
CONTROLLED BY USER : : PVNGS EMERGENCY PLAN PROCEDURE NO. + IMPLEMENTING PROCEDURE EPIP-11 TECHNICAL SUPPORT CESTER/ SATELLITE TSC REVISION ACTIVATION 5 Page 5 of 48 1.0 03.". :.CTIVE 1.1 To provide instructions for the activation and operation of the Technical Support Center (TSC) and the Satellite TSC (STSC).
2.0 REFERENCES
2.1 I=plementing References .- 2.1.1 IPIP-03, " NOTIFICATION OF UNUSUAL EVENT Implementing Actions" 2.1.2 EPIP-04, "AL ET ::pl: ntink f.: irn:"
*AuRT,SnT ARER and GfUEML EMCR3DKY Zeyl erne Ahm h ,, ,a 2.1.3 EP!"-" "e:~I lHEA 2'f:20:1:CY Irpla- nting Ae.ica."y I,
2.1.4 Er!? Of, " : CP.AL DTP.CIS:07 ,::p!:::nting Ani;;;" 2.1.5 EPIP-14A, " Release Rate Determination" 2.1.6 EPIP-14B, " Initial Dose Assessment" 2.1.7 EPIP-15, " Protective Action Guidelines" . 2.1.8 EPIP-16 "Inplant Surveys and Sampling" 2.1.9 EPIP-17. "Onsite/Offsite Surveys and Sampling" ' 2.1.10 EPIP-18, " Emergency Exposure Guidelines" 2.1.11 EPIP-20 "Personnal Assembly and Accountability" .
'2.1.12 EPIP-21, " Search and Rescue" 2.1.13 EPIP-25. " Reentry for Emergency Operations" 2.1.14 EPIP-26 " Potassium Iodide (KI Administration" 95RP-EP 9 ,,7;t92, "becedammdos)"
P-!* 2.1.15 Perreml " nitcring nd 02:ent::innies" - ,
=
2.1.16 - EPIT -; , ".'. ::/E ui; ment ";n i ; o .--in6 . d D ::M ed:::icf k 2.1.17 9N219.05.00, " Document / Record Turnover Control" e e
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CONTROLLED BY USER PVNGS EMERGENCY PLAN QCEDURE IMPLEMENTING PROCEDURE EPIP-11 REVISION TECHNIJAL SUPPORT CENTER / SATELLITE TSC ACTIVATION 5 Page 6 of 48 2.2 Developmental References 2.2.1 NUREG 0654, Rev. 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 NUREG 0696, Feb. 1981, " Functional Criteria for Emergency Response Facilities" ' 2.2.3 PVNGS Emergency Plan, Rev. 6 2.2.4 75AC-9ZZ01, " Radiation Exposure Authoriztion, Permits and Control," Rev. 2. 2.2.5 ANSI N45.2.9-1974, " Requirements For Collection, Storage, and Maintenance of Quality Assurance Records foz Nuclear Power Plants" 2.2.6 7N409.02.00, " Emergency Preparedness Organization and Staffing," Rev. O. 3.0 LIMITATIONS AND PRECAUTIONS 3.1 Activation of the TSC should be completed within the augmentation time goals set forth in the PVNGS Emergency Plan. 3.2 The Satellite TSC and the TSC may be used by designated personnel for normal daily activities as well as for training and emergency drills. Use of these facilities shall be limited to activities that will not degrade preparedness to react to abnormal conditions or reduce system (s) reliability. This use shogld' be reviewed by the Site Emergency Planning Supervisor. 3.3 Each individual in the TSC/STSC upon event termination = hall submit any written documentation to the Emergency Coordinator who ensures they are forwarded to Emergen' cy Plani.ing Dept. for storage in accordance with 9N219.05.00, " Document / Record Turnover Control." A e
. CONTROLLED BY USER J PVNGS EMERGENCY PLAN [ROCEME IMPLEMENTING PROCEDURE EPIP-11 TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION ACTIVATION 5 Page 7 of 48 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 During a NOTIFICATION OF UNUSUAL EVENT, direction and coordination of onshift emergency operations shall be 1 provided by the Emergency Coordinator at the Satellite TSC.
During an ALERT or more severe classification, emergency . assessment and control shall initially be directed-from the Satellite TSC and transferred to the TSC once it has been activated. 4.1.1.1 Prior to activation of the onsite and offsite Emergency ' Organizations, the following activities take place in the Satellite TSC: (1) Environmental assessment (offsite dose projections). k-(2) Field Monitoring Team direction by the Radiation Protection Monitor. (3) Technical analysis by the Shift Technical Advisor (STA). (4) Emergency management by the Emergency Coordinator (EC). (5) Initial notifications including protective action recommendations by the Satellite TSC Communicator. 4.1.2 When the onsite and offsite Emergency Organization has been activated, the responsibility for the above listed functions shall be transferred to the TSC and/or the Emergency ' Operations Facility (EOF). 4.1.2.1 The Satellite TSC then functions as an extension of the TSC to provide direct technical support to the Control Room personnel in the areas of: (1) Engineering and technical analytical support. (2) Reactor analytical support. (3) Unit operations support. (4) Radiological analytical support. m*coonen
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN Qceouse IMPLEMENTING PROCEDURE EPIP-11 TECHNICAL SUPPORT CESTER/ SATELLITE TSC REVISION ACTIVATION 5 Page 8 of 48 4.1.3 The functions performed in the TSC are: (1) Manage onsite emergency response. ~ (2) Direct onsite radiological protection activities. (3) Direct emergency maintenance. (4) Direct personnel accountability and site security. (5) Direct safety and hazards control. (6) Perform engineering and technical analysis for Control Room support. (7) Perform reactor analysis. (8) Provide eeergency I&C support.
/
(9) Provide computer and chemistry te-hnical support. (10) Direct Inplant/Onsite field monitoring activities. 4.1.4 The TSC radiological emergency kit contains a supply of calibrated radiological monitoring equipment, protective clothing, portable lighting, and additional supplies. 4.1.5 Activation of the Satellite TSC shall take place upon declaration of a NOTIFICATION OF UNUSUAL EVEhT. 4.1.6 Activation of the TSC and aurpentation of the Satellite TSC staff by the onsite Emerge.y Organization shall take . place upon declaration of an ALERT or more severe emergency. ' 4.2 Prerequisites 4.2.1 A NOTIFICATION OF UNUSUAL EVEVT or higher emergency classification has been made. y PY2164CA (8/22)
CONTROLLED BY USER PVNGS EMERGENCY PLAN Qocsouse IMPLEMENTING PROCEDURE , EPIP-11 i ' TECHNICAL SUPPORT CE E R/SATELLITi TSC REVISION ACTIVATION 5 Page 9 of 48 4.3 Instructions 4.3.1 Activation of the Satellite TSC 4.3.1.1 The following enihift n Emergency Organization personnel shall report to the affected unit Satellite TSC: (1) The affected unit Shift Supervisor or Shift
- Supervisor cf the designated unaffected unit (Onshift Emergency Coordinator) - EPIP-03,
" Notification Of Unusual Event Implementing Actions," EPIT-O'.,,"'le-t I- ;12 ::::r; '.:t ic r ,_"
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5 5P5,'*55l,5NkeYAIGlml e Sp5 ,~ Ile$s." (2) Shift Technical Advisor - Appendix A. " Shift 5 Technical Advisor Response." ('
.(3) Designated Radiation Protection Technician, (Radiatica Protection Monitor) - Appendix B,
" Radiation Protection Monitor Response."
(4) Designated Nuclear Operator (STSC Communicator) 4.3.1.2 The following onsite Emergency Crganization personnel shall report to the affected unit Satellite TSC (if required) to relieve their respective onshift counterpart. (1) Radiation Protection Monitor - Appendix B. 4.3.1.3 The affected Unit Superintendent (or affected Unit Day Shift Supervisor) shall report to the STSC and assume the position of Operations Advisor. He provides technical and operational advice to the Shift Supervisor, and
, ensure that information flow is maintained between the '3 TSC and the Control Room as per Appendix J, " Operations Advisor (Onsite) Response."
4.3.2 Preliminary, Activation of the Technical Support Center . w
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~ CONTROLLED BY USER PVNGS EMERGENCY PLAN QCEWRE IMPLEMENTING PROCEDURE EPIP-11 '
TECHNICAL SUPPORT CEhrER/ SATELLITE TSC REVISION b ACTIVATION 5 Page 10 of 48 4.3.2.1 The Security Shift Captain shall report to the TSC, assume the duties of Security Director as per Appendix C, .
" Security Director Response."
4.3.3 Complete Activation of,the Technical Support Center 4.3.3.1 All Emergency Organization personnel reporting to the TSC shall re:rieve their activation materials from the TSC activation cabinet and establish their assigned. work areas as shown in Appendix V. 4.3.3.2 The Technical Engineering Coordinator shall report to the
' TSC as per Appendix D, " Technical Engineering Coordinator (OSSITI) Response."
4.3.3.3 The Security Director of the onsite Emergency ! Organization shall report to the TSC and relieve the . Security Shift Captain as per Appendix,C_,." Security. - U Director Response." - 4.3.3.4 The following onsite Emergency Organization personnel shall report to the TSC and perform their designated function: . and (1) Emergency Coordinator - EPIP-03 EPIP-04 EP'r-05, 4s.d Er:r % " Emergency Coordin)ator Resp,onse." (h (2) Technical Engineering Assistant - Appendix E. . " Technical Engineering Assistant Response."
- (3) Radiological Protection Coordinator - Appendix F,- '
" Radiological Protection Coordinator (Onsite) '
Response." (4) NRC. Liaison - Health Physics - Appendix G. "NRC Liaison - Health Physics Response." - (5) Emergency Maintenance Coordinator - Appendix H.
"Ermrgency Maintenance Coordinator (Onsite)
Response." ' ,
~
CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE N O. IMPLEMENTING PROCEDURE EPIP-11 TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION 5 ACTIVATION 5 Page 11 of 48 (6) Hazards Control Coordinator - Appendix I, " Hazards Control Coordinator (Onsite) Response." (7) Personnel Resources Coordinator - Appendix K,
" Personnel Resources Coordinator (Onsite) Response."
(8) Chemistry Coordinator - Appendix L, " Chemistry Coordinator (Onsite) Response." . (9) Reactor Analyst - Appendix M. " Reactor Ana5yst (Onsite) Response." (10) Computer Support Coordinator - Appendix N, "Corputer Support Coordinator (Onsite) Response." (11) Field Team Communicator - Appendix 0, " Field Team Communicater (Onsite) Response." ( (12) Information Monitor - Appendix P, "Information U Monitor Response." (13) Operations Coordinator - Appendix Q, " Operations Coordinator (Onsite) Response." (14) NRC Liaison - Operations - Appendix R "NRC Liaison
- Operations Response."
(15) Clerical Aide / Status Board Keeper-TSC - Appendix S.
" Clerical Aide / Status Board Keeper-TSC Response."
4.3.4 Declaration of TSC Readiness l 4.3.4.1 The onsite Emergency Coordinator shall assure TSC readiness and notify the onsite emergency response i facilities that the TSC is activated. 4.3.4.2 Upon activation of the TSC, the onsite Emergency Coordinator shall relieve the onshift Emergency Coordinator of the Emergency Coordinator functions. ! l 4
%.w PY216400A (k82)
CONTROLLED BY USER
, PVNGS EMERGENCY PLAN QCEDURE APPENDIX A IMPLEMENTING PROCEDURE EPIP-11 Page 1 of'l TECHNICALSUPPCkTCENTER/SATELLITETSC REVISION ACTIVATION 5 Page 12 of 48 SHIFT TECHNICAL ADVISOR RESPONSE POSITION FILLED BY: (1) Shift Technical Advisor RESPONSIBILITY: Advise and assist the Shift Supervisor on assessing plant conditions. Activato and monitor SPDS, develop trend data and provide these data to Control Room personnel.
ACTIONS
- 1. Report to STSC.
- 2. Activate the SPDS.
*3. Monitor the SPDS.
*4. Develop trend data and provide these data to the Shift Supervisor and other Control Room personnel.
*S. Advise the Shift Supervisor of corrective actions.
4
- Continuing Activity h
PV25000A t&Q ,
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN @caoune APPENDIX B IMPLEMENTING PROCEDURE EPIP-11 Page 1 of $ TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION 5 ACTIVATION 5 Page 13 of 48 RADIATION PROTECTION MONITOR RESPONSE POSITION FILLED BY: (1) Radiation Protection Technician from affected unit RESPONSIBILITY: Provide initial onsite and offsite dose projections. Initially direct field monitorir.g teams. Provide technical advice to Emergency Coordinator concerning radiological conditions and protective action recommendations. Monitor radiological assessment . activities of onsite Emergency Organization upon being relieved of dose assessment and field monitoring responsibilities by Radiological Protection, Coordinator or the Radiological Assessment Coordinator. Provide Control Room with appropriate information. . IMMEDIATE ACTIONS
- 1. Report to the STSC upon notification
- 2. Ensure operational status of dose calculation computer.
(
- 3. Perform initial offsite dose rate projection per EPIP-14A, " Release Rate Determination," and 14B,
" Initial Dose Assessment," if a release has occurred.
- 4. Inform onshift Emergency Coordinator of dose rate projection results and assist in determining what protective actions are necessary per EPIP-15,
" Protective Action Guidelines."
*S. Direct activities of onsite/offsite Field Monitoring Teams per EPIP-16, "Inplant Surveys and Sampling," and and EPIP-17, "Onsite/Offsite Surveys and Sampling."
*6.
Evaluate need to administer Potassium Iodide (KI) per EPIP-26, " Potassium Iodide (KI) Administration."
- 7. If OSC is activated, contact OSC Coordinator, using the Radiological Assessment Line, to ensure that:
(1) Sufficient radiological protection equipment is
, dvailable to OSC personnel.
(2) Continuous habitability surveys (airborne, dose rate, contamination) are being performed in the OSC.
- Continuing Activity PV24000A (Mn ,
CONTROLLED BY USER J PVNGS EMERGENCY PLAN [ROCEDURE APPENDIX B IMPLEMENTING PROCEDURE EPIP-11 Page 2 of 3 TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION 5 ACTIVATION S Page 14 of 48 SUBSEQUENT ACTIONS Complete the following until relieved of these resp 6nsibilities by the Radiological Protection Coordinator at the TSC or the Radiological Assessment
' Coordinator at the EOF.
Onsite and Offsito Surveys and Samoling
- 8. Supervise formation, briefing, and dispatch of monitoring teams per EPIP-16 and,EPIP-17.
- 9. Determine / change offsite sampling locations, if necessary.
*10. Direct that appropriate surveys and samoling be performed.
*11. Receive reports from monitoring tea:ns every one-half hour via portable radio.
Protective Action Guidelines
*12. Update and refine dose assessments for critical receptor ,
site locations upon significant changes in: (1) Release rates-(2) Duration of releases (3) Isotopic mixture of release (4) Meteorological conditions
*13. D.atermine if protective actions are warranted in accordance with EPIP-15 and recommend to Emergency Coordinator. .
l Search and Rescue !
- 14. Assist OSC Coordinator in determining radiation levels and approximate stay ' times for teams in affected areas.
l
- Continuing Activity PV218 000A 18/82)
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CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEDURE o APPENDIX B IMPLEMENTING PROCEDURE EPIP-ll Page 3 of 3 TECHNICAL SUPPORT CESTER/ SATELLITE TSC REVISION 3 ACTIVATION 5 Page 15 of 48 Activation of Onsite Emergency Organization
- 15. Contact Radiological Protection Coordinator at TSC, using the Radiological Assessment Line or Environmental Assessment Line, to provide the following:-
(1) OSC radiation protection status . (2) Status of onsite/in-plant field monitoring teams (3) Transfer of responsibility for above to Radiological Protection Coordinator ,
- 16. Transfer control of offsite field monitoring teams, dose projections, protective action recommendations to the Radiological Assessment Coordinator n'pon activation
; of the EOF.
s.
*17. Monitor radiological assessment activities of onsite Emergency Organization and provide Control Room personnel with appropriate information.
*18. Perform dose rate measurements and air samples in STSC/CR, as required.
- Continuing etivity ,
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN [ROCEWRE APPENDIX C IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 6 TECHNICAL SUPPORT CESTER/ SATELLITE TSC REVISION 6 ACTIVATION 5 Page 16 of 48 , s SECURITY DIRECTOR
RESPONSE
u t POSIT N FILLED BY: Security Shift Captain (Onshift) l Manager, Operations Security (Onsite) Security Shift Captain (Alternate) RESPONSIBILIi "- Provide for site security, access control, rsonnel i i recountability, evacuation and medical tra sportation. Call out the Emergency Organization upon irection from the Emergency Coordinator. IMMEDIATE ACTIONS '
- 1. R ort to TSC. Upon arrival, si in on the TSC Stai ing Board ar.d establish re onsible area.
- 2. If nece sary, assign a Secur .y Shif t Sergeant to act (w as Secur y Shift Captain. ave him report to the Security B Iding.
- 3. Inform Access oint Gu ds to limit protected area access to only ose ossessing ACADs.
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4 Call in additiona ersonnel appropriate to the emergency classi ics on as directed by Emergency l Coordinator (E by ut izing automatic dialing system. NOTE
)
If the Auto Dia r at !VNGS malfunct ns call APS 411 Building S curity ar.d request the vstem be activated at he 411 Building. ' S. If he Auto Dialer List One shows no acknowledgement by ther the primary, alternate or backt. respondent for n Emergency Organization position, inf. m the En.ergency Coordinator of the inability to entact the respondent. SUBSEQUENT ACTIO'a
- 6. C~'t Security Shift Captain by plant phone (ext or d establish security measures for statio acce:.s by arriving offsite assistance parsonnel (ALE or higher).
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CONTROLLED BY-USER PVNGS EMERGENCY PLAN QcEoune APPENDIX C IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 6 TECHNICAL SUPPORT CENTER /SAE LLITE TSC REVISION fh I ACTIVATION 5 Page 4J of 48 l SECURITY DIRECTOR
RESPONSE
l POSITION FILLED BY: Security Shift Captain (Onshift)
, Manager, Operations Security (Onsite) {
Secu-ity Shift Captain (Alternate) I RESP 0NSIBILITY: Provide for site security, access control, personnel accountability, evacuation and medical transportation. p Call out the Emergency Organizatier..up:. di.ce;ien f:re the "- r;-cy coer & 2ter-IMMEDIAE ACTIONS l
- 1. Report to TSC. Upon arrival, sign in on the TSC Staffing Board and establish responsible area.
- 2. . If necessary, assign a Security Shift Sergeant to act as Security Shift Captain. Have him report to the
(. Security Building. .
- 3. Inform Access Point Guards to limit protected area access to only those possessing ACADs.
Notif ene dwy day shdf hews se,
- 4. ^ y' addi ional personnelpa(ppr, priata o to ther:co . a u e ,. u . r),
emergency classification ce dirce::d by C; u ; = :y-C::: din:::: (IC) by utilizing automatic dialing system. ) NOTE If the Auto Dialer at PVNGS malfunctions call APS 411 Building Security and request the system be ' a.:tivated at the 411 Building. . s
- 5. If the Auto Dialer List One shows no ackaculedgeoent by either the primary, alternate or backup respondent for an Emergency Organization position, inform the l Emergency Coordinator of the inability to contact the '
respondent. SUBSEQUENT ACTIONS -
- 6. C Security Shift Captain by plant phone (ex o d establish security measures for station access y arriving offsite assistance personnel (AI~:RT l
or higher). l 0
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TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION 5 Page 17 of 48 SECURITY DIRECTOR RESPOSSE (Continued) TSC Access
- 7. Determine need for additional security personnel and contact as necessary.
- 8. Remain at TSC and complete following, as necessary, until .
relieved by Onsite Security Director.
- 9. Direct a member of the Security Force to be stationed at the TSC Entrance and to limit access to the TSC to only those personnel on the TSC Access List.
- 10. Grant access to emergency personnel whc have been verbally authorized by Emergency Coornicator.
Personnel Assembly and Accountability
. 11. Contact Security Shift Captain at the Security, Head-
, quarters and have him prepare for assembly and account-ability per EPIP-20, " Personnel Assembly and Account-ability."
- 12. Infor Security Access Point guard by normal and the Craft Access Point guard (ext hat assembly and accountability are in progres
, to assist existing personnel.
- 13. Arrange for Construction Security to unlock Visitor's i Center, if necessary. '
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- 14. Direct the Security Shift Captain to contact the Maricopa County Sheriff's Office by dedicated telephone line or radio to inform them of impending onsite evacuation and to request traffic control north or south of plant on Wintersburg Road.
- 15. App'roximately 20 minutes after the accountability signal has sounded, obtain copies of the computer print-out of personnel who are in the protected area.
(If ccmputer or card-key unoperable, see EPIP-20)
- 16. Receive accountability reports from Sacurity Shift Captain for Assembly Areas in protected area.
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- 17. Report protected area accountability to Emergency Coordinator within 30 minutes.
- 18. Receive accountability reports from Security Shi't Captain from site assembly area.
- 19. Direct security to routinely check ANPP controlled buildings to ensure they are not occupied. ,
- 20. Report overall accountability outside protected area to EC as soon as practicable.
- 21. Arrange to pick up Individual Accountability Sheets for each area as soon as practicable.
Search and Rescue
- 22. Inform EC of missing or disabled personnel and last knowr. location so that search and rescue can begin per EPIP 21, " Search and Rescue." ,
Onsite Evacuation ,
- 23. Obtain information from Emergen,y Coordinator on assembly area evacuation order, reassembly area and evacuation route.
- 24. Contact Maricopa County Sheriff's Office by dedicated telephone or radio to request traffic assistance at key evacuation route points and also at the offsite reassembly area.
- 25. Dispatch a Security vehicle with one Security Force Member as Evacuation Team Leader to Bechtel Gate. No. I to prepare to lead the Bechtel manuals to the reassembly area.
- 26. Contact o struction Security by telephone (e x,t . 2nd request a Security Team to control traffic at the various exit gates.
- 27. Cont e Bus Transportation Supervisor by telephone (ext tc~ deploy buses to the ANPP/Bechtel Construc ton ffi ce pickup point, the Nuclear Operations pickup point, and the Water Reclamation Facility pickup point. Have him inform the drivers of the reassembly area and evacuation route.
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- 28. Dispatch Security Force to bus pickup po'ints and ates to assure the following order of evacuation (un ss a different order is specified by the Emergency Coordinator): '
(1) Bechtel parking lots (personal vehi es) via Gate No. 1, 2, and 3 (2) ANPP/Bechtel Construction Offi buses via Gate No. 3 ANPP van pools via Gate N . lA (4) ANPP parking lots (per nal vehicles) via Gate
'o . 3 A (5) ANP Nuclear Oper ions buscs via Gate No. 3A
, (6) ANPP W *er Rec mation Facility via Gate No. 12
- 29. ' Contact the Radt gical Protection Coordinator and V assure that a me .*oring/ decontamination team has ]
been dispatche to e reassembly area.
- 30. Cent c* +a assembly area by telephone Palo V Inn flassay pa Pump Stat .
and in them of the im nding evacuation.
- 31. Conta t Assembly Area Supervi or at the following loc ions to inform them of the impending evacuat' ion si nal and the location of bus p kups.
(1) ANPP Construction Office ex (2) Bechtel Emergency Control Center xt I (Itave Bechtel inform Bechtel Fire Te and Bechtel Medical Staff to remain at the Bechtel Safety office and not to evacua .) (3) Admin. Annex Bldg. Assembly Area e. (4) Water Reclamation Facility e (5) Visitor's Center ext. PV2'6- A 68,82) p 6 y .
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PVNGS EMERGENCY PLAN QOCEDURE p IMPLEMENTING PROCEDURE EPIP-ll Page 4 of 6 ' TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION ACTIVATION - 5- Page y/ of 48 SECURITY DIRECTOR RESPONSE (Continued)
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- 28. Dispatch Security Force to bus pickup points and gates I to assure the following order of evacuation (unless a '
different order is s'pecified by the Emergency Coordinator): - f ' (1) Bechtel parking lots (personal vehicles) via . . Gate No. 1, 2, and 3 . (2) ANPP/Bechtel Construction Office buses via Gate No. 3 (3) ANPP van pools via Gate No.1A
, (4) ANPPap'rking lots (personal vehicles) via. Gate .
No. 3A l . (5) ANPP Nuclear Operations buses via Gate No. 3A (6) ANPP Vater Reclamation Facility via Gate No. 12
- 29. Contact-the Radiological Protection Coordinator and assure that a monitoring /deconta=ination team has been dispatched to the' reassembly arte..
- . 30.
eassembly. area by telephon g u I r Hassaya_pa Pu=p Statief
- and
.. orm t em of the impending evacuatic
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- 31. Contact Assembly Area Supervisor at the following !
I locations to' inform them of the impending evacuation signal and the location of bus pickups. . (1) ANPP Construction Office ext (2) Be, htel Emergency Control Center ex (Have Bechtel inform Bechtel Fire Team and Bechtel Medical Staff to remain at the Bechtel Safety office and not to evacuate.) , (3) Admin. Annex Bldg. Assembly Ares (4) Vater Reclamation Facility ex
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ACTIVATION
- 5 Page 20 of 48 SECURITY DIRECTOR RESPONSE (Continued)
- 32. Notify the Emergency Coordinatcr that preparations ave been made and the evacuation signal may be given.
- 33. Dispatch Security Force to routinely check ANP trailers and buildings in the Administration area outs de the .
protected area to ensure all non-essential (sonnel have left the premises. 34 Recuest ate Site Security by tele one
- o' routinely check the isitor's ruction offices, Bechte Warehouse and a sociated areas.
- 35. Cort et the E g Lea r by radio or telephone
'erde IG H sayampa Pump Station at tne o er ssembly area to determine if any emergency upplies are needed.
Report all eeds to Admin' trative and Logistics ] fI Coordinator. O Of t' site Emergency Vehicle erso.nel Access to PVNGS
- 36. Obtain following i ormation about emergency vehicles that may be used nd nform the Security Shift Captain.
(1) Vehicle ype (2) Licens or other id 7tification number (3) Colo (4) Nu. er of occupants
- 37. Dispat . a Security Force Membe to accompany all vehi es.
- 38. D' ect Security Access Point by tele one (e -
o allow entry to protected area of th e ANPP personnel or contractors called to PVNGS who have oc been previously authorized normal access. Fire Fighting
- 39. Call Bechtel Fire Department, a on .
direction from EC, and inform of typ fire, location and extent of fire, special precautions, and special equipment. PV2'WA 18'82 e
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PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE EPIP-11 Page 5 of 6 TECHNICAL SUPPORT CEhTER/ SATELLITE TSC REVISION ACTIVATION , 5 Page 36 of 48 SECURITY DIRECTOR . RESPOSSE (Continued) l 32. Notify the Emergency Coordinator that preparations have been made and the evacuation signal may be given.
- 33. Dispatch Security Force to routinely check ANPP trailers and buildings in the Administration area outside the protected area to ensure all non-essential personnel have left the premises. -
- 34. -Reques orate Site Security by telephene (ext. o-routinely check the Visitor's Center, construction offices, Jechtel Warehouse and associated areas.
~
- 35. Contact the E Team Leader by radio or telephone de I Hassaya=pa Pu=p Station ( l ti t e o e reassembly area to a l k . e any emergency supplies are needed, h' Report all needs to Administrative and Logistics l Coordinator.
Of fsit Emergency Vehicle / Personnel Access to PVNGS l '
- 36. Obtain followixig information about emergency vehicles that may be used and inform the Secu:ity Shift Captain.
(1) Vehicle type
. (2) License or other identification nu=ber (3) Color -
, (4) Number of occupants
- 37. Dispatch a Security Force Member to accompany all
' vehicles.
- 38. Direct Security Access Point by telephone (ex to allow entry to protected area of those ANPP personnel er contractors called to PVNGS who have not been previously authorized normal access.
Fire Fighting
- 39. Call Bechtel Fire Department, at upon direction from EC, and inform of type o fire, location and extent of fire, special precautions, And special equipment. -
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- 40. Direct Security to assign personnel to escort Bechtel Fire Team to fire.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN [RCEME APPENDIX D IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 2* REVISION g TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION 5 Page 22 of 48 TECHNICAL ENGINEERING COORDINATOR (CNSITE)
RESPONSE
POSITION FILLED BY: (1) Manager, OPS Engineering (2) OPS Engineering Supervisor RESPONSIBILITY Direct engineering and systems analyses, procedures development and related licensing efforts. Maintain , contact with offsite technical support groups.., IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board.
- 2. Obtain list of equipment out of commission prior to emergency.
1 *3. Maintain list of equipment out of commission during
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emergency.
*4. Access records management and obtain needed technical materials throughout emergency.
- 5. Ensure that the followin; personnel are responding as per their appropriate appendix:
(1) Chemistry Coordinator (2) Reactor Analyst (3) Computer Support Coordinator. (4) Technical Engineering Assistant
- Continuing Activity
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*6. Determine need for additional enginee' ring and technical support personnel, and inform Personnel Resources Coordinator.
SUBSEQUENT ACTIONS
- 7. Assist Emergency Coordinator as needed to determine .
corrective actions. .
- 8. Assist Emergency Coordinator as needed during reclassification activ.ities.
- 9. Provide updated status of reactor and unit to Technical Analysis Coordinator in the EOF using the Technical Line.
*10. Periodically brief NRC representative on plar.t status and corrective actions.
*11. Establish and maintain a communications line using the
. Operations Ring Down circuits with the Corporate Emergency Center / Engineering Group. (This may be delegated to a Technical Engineering Assistant.)
. *12. Assist in determination of need for offsite technical support.
*13. Periodically provide Event Status updates to the Status Board Keeper for posting on Status Board.
- Continuing Activity PY24 030A $4n y .Y w-
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CONTROLLED BY USER- _J~ .. PVNGS EMERGENCY PLAN Tcewna APPENDIX E IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 ON TECHNICAL SUPPORT CENTER / SATELLITE TSC $ ACTIVATION 5 Page 24 of 48 TECHNICAL ENGINEERING ASSISTANT
RESPONSE
POSITION FILLED BY: (1) Shif: Technical Advisors, off-duty (2) Other designated personnel with appropriate training RESPONSIBILITY Monitor plant system data via ERFDADS. Maintain . liaision with Architect-Engineer concerning technical status and proposed recommendations. IMMEDIATE ACTIONS ,
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board.
- 2. Relieve initial briefing from Technical Engineering Coordinator and establish responsible area.
\'l - *3. Monitor plant systems data via EF7 DADS.
SUBSEQUENT ACTIONS
*4. If so directed, establish communications link with the Corporate Emergency Center / Engineering Group using the Operations Ringdown circuits.
*5. Maintain communication with Architect-Engineer, NSSS Supplier and required vendor personnel through the CEC / Engineering crew concerning plant status and recommendations for ccrrective action. '
*6. Inform Technical Engineering' Coordinator of proposed recommendations and significant change in plant status.
- 7. Submit logs and status board update sheets to Technical Engineering Coordinator when emergency is can, celled.
- Continuing Activity s
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PVNGS EMERGENCY PLAN o [ROCEWRE APPENDIX F IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 6 REVISION $ TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION $ Page 25 of 48 RADIOLOGICAL PROTECTION COORDINATOR (ONSITE)
RESPONSE
u POSITION FILLED BY: (1) Manager, Radiological Services - (2) Radiological Engineer RESPONSIBILITY: Relieve Radiation Protection Monitor of dose rate projection and onsite/inplant field monitoring , supervision responsibilities. Direct onsita-field monitoring activities and inplant radiological controls. Supervise dose rate projections. IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish respo'nsible area.
,, 2. Ensure that the following are available:
(1) Meteorological overlays and base maps (2) Procedures and forms
- 3. Ensure operational status of dose calculation computer.
4 Contact Radiation Protection Monitor at STSC using the Radiological Assessment Line or Environmental Assessment Line and determine: (1) Extent of radiological releases and plant conditions (2) Location of onsite and offsite monitoring teams (if dispatched) (3) Status of dose assessments and protectivo action recommendations (If EOF is not activated.)
- 5. Determine need for additional personnel to assist in dose assessment.
- 6. Relieve Radiation Protection Monitor of responsibility for' control of:
(1) Onsite field monitoring (2) Inplant radiological controls
- (3) Release rate determination and dose calculations Pv25 coo 4 ts/sa
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- 7. Inform Emergency Coordinator when TSC is ready to
- conduct dose assessments.
SUBSEQUENT ACTIONS Onsite and Inplant Surveys and Sampling
- 8. Form, brief, and dispatch Monitoring Teams through Emergency Maintenance Coordinator per EPI'P-16, Inplant Survey and Sampling," and EPIP-17, "Onsite/Offsite Survey and Sampling.",
- 9. Direct that appropriate surveys and sampling be performed.
*10. Receive reports from Inplant/Onsite monitoring teams.
*11. Receive reports of sample analysis from Radiation k Protection Technicians.
. *12. Receive reports on contaminated areas and/or equipment from Radiation Protection Technicians.
Onsite Evacuation
- 13. Determine the [ppropriate reassembly area and evacuation route in conjunction with Emergency Coordinator.
- 14. Dispatch personnel for monitoring at offsite reassembly -
areas through the Emergency Maintenance Coordinator.
*15. Provide guidance to the Radiaticn Monitoring Team at the reassembly area as requested.
- Continuing Activity PY216400A (4/8a I ,
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[ROCEDURE pp IMPLEMENTING PROCEDURE EPIP-11 Page 3 of 6 TECHNICAL SUPPORT CESTER/ SATELLITE TSC REVISION f ACTIVATION 5 Page 27 of 48 Emergency Exposure Guidelines
*16. Authorize doses up to the limits of 10CFR20.
- 17. Provide the Emergency Coordinator with radiological evaluation of situation and conditions requiring emergency exposures in excess of 10CFR20 limits.
- 18. Completa and sign Radiation Exposure Permit (75RP-9ZZ44, " Radiation Exposure Permits") or designate individual to complete this task.
m _ 19. Obtain initial estimates of radiation dose of exposed personnel as quickly as possible.
- 20. Report exposures in excess of 10CFR20 (refer to EPIP-18, Appendix B) to Emergency Coordinator.
K.- 21. Update and refine dose estimates when time permits. Potassium Iodide (KI) Administration
- 22. _o may Advise Emergency Coordinator as to when and wh_o voluntarily receive KI.
- 23. Obtain bottle (s) of 130mg KI tablets frem a Radiological Emergency Kit.
l
- 24. Dispense one (1) tablet to each individual designated by '
Emergency Coordinator to voluntarily use KI (task may be delegated).
*25. Maintain record of Potassium Iodide Distribution as per EPIP-26, " Potassium Iodide (KI ) Administration," ;
Appendix B (cask may be delegated). Search and Rescue
*26. Assist OSC Coordina' tor in determining radiation levels and' approximate stay times for teams in Radiologically Controlled areas.
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- Continuing Activity l maaoaem -
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, PVNGS EMERGENCY PLAN -
[ROCEDURE App s9xx y IMPLEMENTING PROCEDURE EPIP-11 Page 4'of 6 TECHNICAL SUPPORT CESTER/ SATELLITE TSC REVISION ACTIVATION 5 L Page 28 of 48 f I Personnel Iniurv The following items should be performed by the Radiological
- Protection Coordinator, if possible, or by a member of the Radiological Support Staff.
- 27. Determine, with advice of plant nurse, the order of priorities for: -
(1) Treatment (2) Evacuation (3) Decontamination (4) Necessity or protective clothing / respiratory protection (5) Other priorities dictated by radiological / hazardous e conditions.
- 28. Request use of onsite emergency vehicle (s).
5.' 29. Designate an individual to prepare the stati aebulance to transport injured personnel to hospital.
- 30. Request Security to call offsite ambulance service, if onsite vehicles are unavailable, and to issue dosimetry to ambulance personnel.
- 31. . Designate individual to meet and accompany ambulance to patient's location.
32. Determine emergency route to be used per EPIP-22,
" Personnel Injury," Appendix D.
33. Designate one or more individuals qualified in use of G-M survey instruments and radiation contrcl procedures to accompany patient to hospital. - Personnel and Area /Ecuioment Monitorin:: and Decontamination
- 34. Determine need for personnel men'itoring and decontami- e
** Decontamination." nation per EP!"- ", "7xx...d .n:175gp.92373 t .i :ri .g
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- TECHNICAL SUPPORT CESTER/ SATELLITE TSC ACTIVATION 5 Page 29 of 48
- 35. Determine if crucial areas and/or equipment requires .
conitoring and decontamination in accordance with j[ ET'" ? , "' re /E;uip;; .; M;..it;-in; - ' 75RP-1127F, 3
" Decontamination. " C
- 36. Complete, date, and sign Radiation Exposure Permit.
- 37. Stipulatemethodofdecontaminationasdes.cri$ edin 1; S?':- :: . 75BP- 12 73, ,
f Fire Fichting
- 38. Dispatch, upon notification by Emergency Coordinator, a monitoring team to assist with radiological aspects of fire emergency.
- 39. Instruct monitoring team to survey all outside fire fighting assistance personnel and supervise .
-s-decontamination evaluations prior to release from site.
Reentrv for Emergency Oeerations *
- 40. Contact OSC Coordinator using the OSC Dedicated Phone, and provide, in conjunction with Emergency Coordinator and Emergency Maintenance Coordinator, a :
, description of:
(1) Vork to be performed (2) Number of people work requires (3) Necessary tools, spare parts, and equipment (4) Radiological conditions, if known .
- 41. Provide Emergancy Coordinator, if required, with radiological evaluation of situation (s) , requiring emergency
- exposure (s) and complete Radiation Exposure Permit authorining emergency exposure in accordance with EPIP-18.
- 42. Co=plete or designate individual to complete the l Radiation Exposure Permit detailing specific protective equipment, allowable doses and ALARA procedures outlined in EPIP-25.
,'4 3 . 'Obtain initial estimates of radiation dose of exposed J personnel as soon as possible.
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- 44. Receive reports of exposures in excess of 10CFR20 limits and report to Emergency Coordinator.
- 45. Update and refine dose estimates when time permits.
Habitability Surveys of TSC
*46. Designate Radiation Protection personnel in TSC to perform dose rate measurements and air samples as required.
- Continuing Activity k
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( ACTIVATION 5 Page 31 of 48 NRC LIAISON - HEALTH PHYSICS
RESPONSE
POSITION FILLED BY: ALARA Stcff Engineer RESPONSIBILITY: Establish continuous communications with the NRC to provide radiological information until the NRC Emergency Response Team arrives onsite. IMMEDIATE ACTIONS
- 1. Report to TSC. Upon , arrival, sign in on the TSC Staffing Board and establish responsible area
- 2. Receive briefing from the Radiological Protection Coordinator on radiological status.
*3. Establish continuous communications with the NRC using ! PBX phone.
U
- 4. Provide initial radio'.ogical conditions to the NRC.
SUBSEQUENT ACTIONS
*5. Maintain continuous communications with the NRC until the NRC Emergency 'tesponse Team arrives onsite.
- Continuing Activity ,
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CONTROLLED BY USER : . PVNGS EMERGENCY PLAN [ROCEDURE APPENDIX H IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 2 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC $ ACTIVATION 5 Page 32 of !.8 EMERGENCY MAINTENANCE C00RDINAT0h (ONSITE) RESPONSE i POSITION FILI 2D BY: (1) Manager, Maintenance (2) Superintendent MCC
. RESPONSIBILITY Assume responsibility for plant emergency repair.
Coordinate repair and damage control including directing the OSC Coordinator to assemble / dispatch Emergency Repair Teams. , , IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish responsible area.
- 2. Establish contact with the OSC Coordinator via the
.__ dedicated OSC Line.
3. Receive requests for all emergency teams and direct the OSC Coordinator to form these teams.
- 4. Access records management and obtain needed materials.
- 5. Determine need for additional maintenance support personnel and inform the Personnel Resources Coordinator.
SUBSEQUENT ACTIONS
- Emergency Status
*6 Provide periodic updates to the OSC Coordinator of the status of the emergency.
Emergency Reentry and Repair
*7. Assess operation of plant systems including mechanical, electrical, and I&C equipment.
*8. Advise Emergency Coordinator on matters dealing with repair, maintenance, and deployment of Emergency Repair Teams.
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*9. Determine if emergency repair operations are crucial to needs of Emergency Organization and inform Emergency Coordinator.
*10. Confer with Emergency Coordinator and Radiological Protection Coordinator prior to contacting OSQ
', Coordinator or Repairs Coordinator using Maintenance Control Line with a description of: (1) Work to be performed. (2) Number of personnel required. (3) Tools, spare parts and equipment needed.,
; (4) Radiological conditio'ns, if known.
*11. Direct OSC Coordinator or Repairs Coordinator using Maintenance Control Line, to assemble and dispatch Emergency Repair Teams, as necessary.
Area / Equipment Monitoring and Decontamination
- 12. Determine if contaminated areas and/or equipment are crucial to needs of Emergency Organization and inform Emergency Coordinator to arrange for decontamination.
- Continuing Activity
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CONTROLLED BY USER E PVNGS EMERGENCY PLAN PROCECURE NO. APPENDIX I IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 REVISION j
" TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION 5 Page 34 of 48 HAZARDS CONTROL COORDINATOR (ONSITE) RESPONSE ~
POSITION FILLED BY: (1) Health and Safety Administrator (2) Safety Engineer ~ RESPONSIBILITY: , Advise Emergency Coordinator concerning industrial safety of plant personnel. Evaluate hazards of potential or actual toxic material releases and/or chemical spills.
~.
1 IMMEDIATE ACTIONS
- 1. , Report to TSC upon notification. Upon arriv11, sign in on the TSC Staffing Board and establish
-' responsible area.
- 2. Determine areas that pose industrial hazards to personnel and inform Emergency Coordinator and OSC Coordinator through the Emergency Maintenance Coordinator.
- 3. Assist Radiological Protection Coordinator with ALARA considerations.
SUBSEQUENT ACTIONS Search and Rescue
- 4. Request the Emergency Maintenance Coordinator'to direct the OSC Coordinator to assemble and dispatch Search and Rescue Teams.
- 5. Complete Search and Rescue information sheet in , '
EPIP-21, " Search and Rescue," Appendix D.
- 6. Notify Emergency Coordinator of results of search and rescue efforts. 1 Fire Fighting
- 7. Provide technical advice to Fire Team Leader during an emergency.
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PVNGS EMERGENOY PLAN PROCEDURE IMPLEM2NTING PROCEDURE EPIP-11 Page 1 of 1 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC f ACTIVATION 5 Page 35 of 48 OPERATIONS ADVISOR (ONSITE)
RESPONSE
9 POSITION FILLED BY: (1) Operat' ions Superintendent of affected unit (2) Operations Day Shift Supervisor of affected unit RESPONSIBILITY: Act as manah;ement liaison with Control Room. Analyze plant conditions and advise Shift Supervisor and Emergency Coordinator. Ensure information flow between TSC and Control hoom. Assist in development-of procedures for conducting emergency operations. IMMEDIATE ACTIONS
- 1. Report to STSC upon notification.
SUBSEQUENT ACTIONS STSC Activation / Operation
/ *2. Provide ti.chnical and operational advice to Shift Supervisor and Emergency Coordinator, as necessary.
*3. Analyze conditions using SPDS and CRACS and provide guidance to Emergency Coordinator and Operations personnel.
*4. Establish communications with the Operations Coordinator (Onsite) in the TSC.
. *S. Assist in developing emergency procedures as necessary for conducting emergency operations.
Emergency Classificatiori
*6. Advise Emergency Coordinator via the Operations Coordinator (Onsite) as to plant status and re-classification of emergency for ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY.
- Continuing Activity 5
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PV216 000A (t/82) m
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ACTIVATION 5 Page 36 of 48 PERSONNEL RESOURCES COORDINATOR (ONSITI)
RESPONSE
POSITION FILLED BY: (1) Adminstrative Services Manager (2) Manager, Office Services RESPONSIBILITY Relieve Security Director of responsibility for callout cf additional emergency personnel. Plan for 24 hour emergency response organization staffing. Assist OSC Coordinator in meeting the manning requirements cf OSC. Serve as primary Assembly Area Supervisor in TSC. IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish respen.cible area.
i
- 2. Assist Security Director with accountability per EPIP-20, " Personnel Assembly and Accountability."
k/ 3. Develop 24-hour mannlag requirements and augment staffing as required.
- 4. Assess and assist OSC Coordinator in meeting the manning requirements of the OSC.
- 5. Assign one Clerical Aide / Status Board Keeper to report to the Technical Engineering Coordinator and maintain the status boards.
SUBSEQUENT ACTIONS Personnel Assemblysand Accountability ,
- 6. Assume role of primary Assembly Area Supervisor for TSC.
- 7. Record names and badge numbers of personnel who have reported to TSC on Individual Accountability Sheet per EPIP-20.
- 8. Contact Security Shift Captain and inform of ' personnel and badge numbers accounted for.
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*9. Grant verbal authorization to personnel requesting access to TSC and notify Security Director to grant SCCOSS.
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. RESPONSE POSITION FILLED BY: (1) Manager, Chemical Services (2) Chemist RESPONSIBILITY: Provide evaluation of coolant samples and air samplea to aid in diagnosing reactor core conditions and release potentials. Interpret results of chemical analyses for evaluation of plant systems.
IMMEDIATE ACTIONS - i
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish responsible area.
.. 2. Contact onshift Chemistry Technician using regular phone line and obtain pertinent chemistry plant data.
- 3. Determine the need for additional chemistry support personnel, and inform the Technical Engineering Coordinator.
- 4. Confer with Technical Engineering Coordinator to determine needs concerning plant chemistry data.
SUBSEQUENT ACTIONS ' *S. Evaluate coolant samples and air samples a.ad interpret results of chemical analyses and assist Technical Engineering Coordina:or, as necessary. . l i l l
- Continuing Activity l
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' ANALYST (ONSITE)
RESPONSE
POSITION FILLED BY: (1) Supervisor, Reactor Engineering (2) Lead Reactor Engineer RESPONSIBILITY: Perform detailed analyses of core physics and heat transfer parameters. Assess reactor core status and evaluate the integrity of and fuel cladding. IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish responsible area.
- 2. Assess core parameters.
- 3. Access records managements and obtain needed technical k .. materials.
4 Determine need for additional reactor support personnel and inform the Technical Engineering Coordinator. S. Inform Technical Engineering Coordinator of recommendations for operation. SUBSEQUENT ACTION
*6. Continue to conduct analyses and assess and evaluate the integrity of plant systems and assist Technical Engineering Coordinator, as necessary. ,
*7 Contact Corporate Ans rt (Deer Valley) as needed by normal phone <
- Continuing Activity s evacoca wen
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PVNGS EMERGENCY PLAN [ROCEDURE o APPENDIX N IMPLEMENTING PROCEDURE EPIP-11 Page 1 of i REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC j ACTIVATION 5 Page 40 of 43 COMPLTER SUPPORT COORDINATOR (ONSITE) RESPONSE , o POSITION FILLED E : (1) Supervisor, Hardware Maintenance (2) Co=puter Engineer RESPONSIBILITY: Provide continuous support of analyses pertaining to plant conditions and dose assessment. IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish responsible area.
- 2. Access CRACS and SPDS as requested.
- 3. Determine need for additional computer support personnel and inform the Technical Engineering Coordinator.
SUBSEQUENT ACTIONS
*4. Provide computer support to TSC staff, when requested.
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RESPONSE
u POSITION FILLED BY: (1) Radiation Protection Section Staff Member RESPONSIBILIT'f: Maintain direct radio contact with PVNGS Inplant/Onsite Field Monitoring Teams. Assist the Radiological Protection Coordinator with dose rate projections. , IMMEDIATE ACTIONS
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board and establish responsible area.
- 2. Report to Radiological Protection Coordinator and obtain information on deployment of Inplant/Onsite Monitoring Teams.
- 3. Ensure that radio communications equipment is operable.
- 4. Synchronize TSC clocks with affected unit clock.
SUBSEQUENT ACTIONS
*5. Maintain commur.ications with Inplant/Onsite Monitoring Teams via radio or plant telephone.
*6. Assist Radiological Protection Coordinator in performance of dose assessment calculations as ,
necessary.
- Continuing Activity 4, .
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! INFORMATION MONITOR RESPONSE j , 1 POSITION FILLED BY: (1) Compliance Supervisor (2) Compliance Engineer RESPONSIBILITY: Shall monitor communications between the Emergency Coo-dinator, Operations Coordinator, and the Operations Advisor and periodically provide emergency status updates to the Onsite Emergency Organization. IMMEDIA~C ACTIONS *
- 1. Report to TSC. Upon grrival, sign in on TSC Staffing Board and establish responsible area.
- 2. Establish communications link with the Emergency Coordinator, Operations Coordinator and the Operations Advisor.
- 3. If so directed by the Emergency Coordinator, make
-s a Site Widt P.A. . '
c ment that the TSC is activated using th e.
*4. Provide periodic emergency status updates via P.A.
announcements ti the Onsite Emergency Organization (OSC, CR, STSC, e.tc.).
*S. Verify accuracy of information posted on TSC Event .
Status Board.
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- 1. Report to TSC. Upon arrival, sign in on the '1SC Staffing Board and establish responsible area.
- 2. Establish communicstions ,with the Operations Advisor (Onsite) in the STSC.
*3. Receive data from the Operations Advisor (Onsite) and report it to the Emergency Coordinator.
- Continuing Activity
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PVNGS EMERGENCY PLAN o [ROCEDURE APPENDIX R. IMPLEMENTING PROCEDURE EPIP-il Page 1 of 1 REVISION h TECH!:ICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION 5 Page 44 of 48 NRC LIAISION - OPERATIONS RESPONSE POSITION FILLED BY: (1) License Training Instructor RESPONSIBILITY: Assume responsibility of continuous communications with the NRC from STSC Communicator until the NRC Emergency Response Team arrives onsite. IMMEDIATE ACTIONS
- 1. Report to TSC. Upon arrival, sign in on the TSC Staffing Board and establish responsible area. '
- 2. Receive briefing from Operations Coordinater on plant status.
- 3. Contact STSC Communicato; and receive NRC communications status.
, 4. Assume continuous communications with NRC from STSC Communicator using the ENS phone.
SUBSEQUENT ACTION
- 5. Maintain continuous communications with NRC until NRC Response Team arrives onsite.
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' TECHNICAL SUPPORT CEhTER/ SATELLITE TSC ACTIVATION REVISION f
5 Page 45 of 48 CLERICAL AIDE / STATUS BOARD KEEPER-TSC
RESPONSE
POSITION FILLED BY: (1) -Designated person (s) ~ with appropriate training. RESPONSIBILITY: Maintain record of emergency actions
. taken by ANPP Emergency Organization on status board. Record status of -,
emergency. IMMEDIATE ACTIONS:
- 1. Report to TSC upon notification. Upon arrival, sign in on the TSC Staffing Board.
- 2. Receive briefing from Personnel Resources Coordinator and establish responsible area.
- 3. Rep (rt readiness to Personnel Resources Coordinator.
- 4. Receive assignment to maintain status boards. Receive status from Technical Engineering Coordinator SUBSEQUENT ACTIONS:
Status Boards NOTE Ensure time recorded on status boards is event time rather than posting time. ,
*5. Record status of emergency as expressed by Technical j Engineering Coordinator.
1 Recovery
- 6. Submit check list to Personnel Resources Coordinator upon cancellation of emergency.
- Continuing Activity Pv244mA 48:4D
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14 - OSC Line 23 - NAN 6 - REMS Terminal 15 - Map Table 24 - OPS Voice 7 - TSC Emergency Kit 16 A-C -Technical Line Lines 1-4 8 A-B - TSC Activation Cabinet 17 - Control Rooa Line 25 - EOF Line 9 - Auto Dialer Terminal 18 - STSC Line 10 - Environmental Assmt. Line 19 A,B - EC/,EOD Line 20 - ENS Phone PV2164X)DA (4/82)
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lDDC Contact (ext. 6633) l , Of rinbo/5 Sff fo k 0:n leJ ~ N V4 $0 " '3acX<e 6/ ease" l Orignator: (Print) (Ext. IUnit(s) affected: l l Gerald A. *5 sikh. l Reason for this PCN: lMI l Y# l
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lDDC Contact (ext. 6633) l l Operabens Sv/pcdCenler &Sde,n l y,,gg, l l Orignator: (Print) lExt. ICnit(s) affected: l l Cerald A. .% ele l Wo! l * ' 3 l l Reason for this PCN:
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l Program, Emerg. Plan or Secur. l l Prog., Phase I-IV Test, or a No l Yes (PRB/PRG/TRRG l l ST7 review required) l l l l - l l '/ - l l l m$ TECHNICAL REVIEkT.R (Supervisory Level
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OPERATICSS SUPPORT CENTER ACT*VATION
- 5 Page 2 of 16 4
REVISION HISTORY Rev. No. Data Revised Pages Com:sents - 4 11-11-85 2,4,5,7,8,12. To incoroorate PCN 401 of 15,16 Rev. 3 and te add a new _ checklist for the Reoair Coord. 5 Cleibf1/ 3,4,5,7,8,10, Deleted Checklists 11,12,13,15, Anoendices A'and C 76 D r"
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NO. IMPLEMENTING PROCEDURE EPIP-12 OPERATIONS SUPPORT CENTER ACTIVATION 3 Page 3 of 16 TABLE OF CONTENTS SECTION PAGE NLMER s 1.0 OBJECTIVE 4
2.0 REFERENCES
4 3.0 LIMITATIONS AND PRECALTIONS 3 4.0 DETAILED PROCEDURE 5 4.1 Personnel Indoctrination / Responsibilities 5 _, 4.2 Prerequisites 7
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4.3 Instructions k 7 APPENDICES Appendix A - OSC Coordinator Response 10 Appendix B - CSC Habitability Criteria 14 Appendix C - Repairs Coordinator Response 15 i e I e 1 4
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OPERATIONS SUPPORT CESTER ACTIVATION . 5 Page 4 of 16 1.0 OBJECTIVE This procedure provides instructions for the activation of the L Oparations Support Center (OSC) and alternate OSC (Service Building).
2.0 REFERENCES
2.1 Imple=enting References 2.1.1 EPIP-04, "?.1:ET :n:1 =:ntin; '. :icn;" -
'ALER7;.ssTURERand GENER9L EME%E: sty Zmplt~en ACf*05 2.1.2 m...
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2.1.3 EC:: 2 5 , ":::C .1 :::::::C'l : plemen-in;; A -i n;" - 2.1.4 EPIP-18, " Emergency Exposure Guidelines" 2.1.5 EPIP-20, " Personnel Assembly and. Accountability" . g' . 3
- i. 2.1.6 EPIP-21, " Search and Rescue" 2.1.7 EPIP-25, " Reentry for Emergenc3 Operations" 2.1.8 E*' 7-:?, "'.;;;/ ui: n .: ::eni:::ing - > "-- --in --ien" h 2.1.9 75AP-9as7g, "0;u,hi,,,;naQ 95219.05.00, " Document / Record Turnover Control" }
2.2 Developmental References 2.2.1 NUREG 0654, Rev. 1, " Criteria for Preparation and
- Evaluation of Radiological Emergency Response Plans and . Preparedness in Support of Nuclear Power Plants" 2.2.2 NUREG 0696, Feb. 1981, " Functional Criteria for Imergency 3 Response Facilities."
2.2.3 PVNGS Emergency Pl.tn, Rev. 6. 2.2.4 10CFR20. " Standards for Protection Against Radiation," 1983. - r 2.2.5 ANSI N45.2.9 - 1974, " Requirements For Collection,
- Storage, and Maintenance of Quality Assurance Records for s -
Nuclear Power Plants." j Pv240 COA @821
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REVISION OPERATIONS SUPPORT CESTER
~} ACTIVATION 5 Page 5 of 16 3.0 LIMITATIONS AND PRECAUTIONS 7
NOTE
, In the onshift emergency organization, the Radiation Prot.ection Monitor at the STSC determines the need to relocate the OSC staff and so informs the Emergency Coordinator.
.- 3.1 Ap ndix B lists the habitability criteria establi .ad- for the OSC. Habitability checks shall be conducted upo initial mannin and as required thereafter. The result of the survey are to transmi::ed to the Emergency Coordi tor, via the Radiologi 1 Protection Coordinator, who de rmines the need to relocate ersonnel to the alternate OSC Service Building). 3.2 If the Service uilding is also uninhab' table, the Emergency O Coordinator shal direct OSC personne to report to one of the protected facili:1 s (Control Room /S tellite Technical Support ] Center,' Technical S port Center o Emergency Operations g k- Facility). a 3.3 At a NOTIFICATION OF UNU AL NT the OSC is partially activated to provide manpo . resources for Emergency Teams, (e.g., Search and Rescue, rgency Repair). If the E.C./S.S. determines the OSC is no req ' red to support the emergency response during a NOTIF ATION UNUSUAL EVENT classification, he ma deactivate the OSC and allow the response personnel t return to the 'r normal work stations. 3.4 Requests for te to be dispatched sh I be channeled through E.C./S.S in the ashift Emergency Organt ation or the Emergency Ma enan:e Coordinator in the site Emergency , Organization , 3.5 The OSC C ordinator and Repairs Coordinator sh 1 forward his check 11 and other written documentation along th any OSC team ecklist and other written documentation to e Emer ency Planning Croup after event termination fo fo *arding to DDC in accordance with 9N219.05.00,
" acument/ Record Turnover Control."
l 4.0 DETAILED PROCEDURE
.1 Personnel Indoctrination / Responsibilities
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3.0 LIMITATIONS AND PRECAUTIONS NOTE . - l
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In the enshift emergency organization, the . Radiation Protection Monitor at the STSC determines the need to relocate the OSC staff . and so informs the Emergency Coordinator 3.1 AppendixBliststhehabitabilitycriteriaestablisbedforthe OSC. Habitability checks shall be conducted upon initial manning and as required thereafter. The results of the survey are to be trans=itted to the Emergency Coordinator, via the Radiological Protection Coordinator, who determines the need to relocate personnel to the alternate OSC (Service Building). 3.2 ~ If the Se:vice Building is also uninhabitable, the Emergency Coordinater shall direct OSC personnel to report to one of the
\- protected facilities (Control Room / Satellite Technical Support Center, Technical Support Center or Emergency Operations Facility). ,
3.3 At a NOTIFICATION OF UNUSUAL EVEhT the OSC is partially activated to provide manpower resources for Emergency Teams, (e.g., Search and Rescue, Emergency Repair). If the E.C./S.S. determines the OSC is not required to support the emergency response during a NOTIFICATION OF UNUSUAL EVEhT classification, he may deactivate the OSC and allow the retpense personnel to return to their normal work stations. 3.4 Requests for tea =s to be dispatched shall be channeled through E.C./S.S in the Onshift Emergency Organization or the Emergency Maintenance Coordinater in the Onsite Emergency
- Organization.
3.5 The OSC Coordinator and Repairs Coordina' tor shall forward W. ch: ali:: J
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Emergency Planning Group after event termination for 4 forwarding to DDC in accordance with 9N219.05.00,
" Document / Record Tt.rnover Control." i
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4.0 DETAII.ED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities . e e IM
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S - lMPLEMENTING PROCEDURE EPIP-12 OPERATIONS SUPPORT CENTER AC'"!VATION 5 Page 6 of 16 4.1.1 The OSC is the assembly and staging area for unit / station personnel pooled for emergency response assignments. Designated emergency response personnel shall report to the OSC if not specifically assigned to a particular emergency position. _ 4.1.2 The OSC Coordinator is responsible for: (1) Activating the OSC. (2) Organizing emergency personnel'uho report to the OSC. (3) Ensuring emergency personnel are available for dispatch. (4) Maintaining a communications link with the E ergency Maintenance Coordinator. 4.1.3 The function of the OSC remains the same for an ALERT, (', 1 - .
- SITE AREA EMERGENCY or GENERAL EMERGENCY classification.
Personnel / equipment augmentation may vary according tc specific circumstances. 4.1.4 The OSC emergency positions and personnel primarily responsible for them include: - (1) OSC Coordinator -I&C Shift Maintenance Personnel. (2) Field Monitoring Teams and Radiological Surveys (in i plant /ensite/offsite) - Radiation Protection Personnel. (3) Rediation Protection Teams (Personnel Monitoring / Dosimetry / Decontamination / Access Control / Reentry , Control) - Radiation Protection Personnel. (4) Repair Teams (Maintenance / Repair / Damage Control) - Maintenance Staff. l l 4 (5) Chemistry Sampling / Analysis - Chemistry Personnel. (6) Search and Rescue Teams /First Aid Tea =s - Designated personnel with appropriate training. (7) Fire T'eam - Designated personnel with appropriate training. 0 4 mWA (8.'82) *
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4.1.5 Repairs Coordinator - Mechanical Shift Maintenance Fore =an (Onsite E=ergency Organization) is responsible for: (1) Ensuring E=ergency Repair Teams are properly briefed and dispatched.
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(2) Coordinating the needs and require =ents of Energency Repair Tea =s in the field. (3) Maintaining co==unications with both the E=ergency ' Maintenance Coordinator and the E=ergency Repair Teams. (') Assisting the OSC Coordinater with the direction of the OSC as deter =ined by the OSC Coordinator. 4.1.6 The pri=ary OSC is located in the lunchroo= of the affected unit's Auxiliary Building. ' 4.1.7 The OSC is equipped with dedicated telephone lines for co==unication with the TSC, Cotitrol Room, STSC and EOF. C 4.1.8 The alternate OSC is located in the Service Building. OSC personnel shall relocate to this area if the E=ergency Coordinator determines that this action is necessary. 4.1.9 E=ergency radiological monitoring equip =ent, first aid supplies, decontamination supplies, protective cl: thing, protective breathing apparatus, field co==unications equipment, and portable lighting are stored in or adjacent ., to the OSC. 4.2 Prerequisites 4.2.1 An ALERT or = ore severe e=ergency has been declared and . . EPIP-04, "AL 2T !::12 en:ing A-rienc ," ET!T 0;, "C!Z /II? E"EECIMCY !=pi renti g intierr," - EPIT 05, "CE.N PJ.L - M E'IECIMCY hgl m..% A ..; , 'j is being icple=ented. 4.3 "W MMD? adGscMat EMAGEucY .ZMMCmCU7WS AC7?C% " Instructions 4.3.1 Activation.of the Primary OSC 4.3.1.1 The I&C Shift Maintenance Foreman shall report to the affected unit OSC as per Appendix A, "0SC Coordinator (Onshift and Ons'ite) Response" 1 PY$16 @& ($/$2) ,
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( IMPLEMENTING PROCEDURE EPIP-12 OPERATIONS SUPP0hT CENTER ACTIVATION 5 Page 8 of 16 4.3.1.2 The following personnel shall report to the OSC and folleu the directions of the OSC Coordinator: (1) Maintenance Staff (2) Radiation Protection Personnel (3) Chemistry Personnel (4) Computer Personnel . 4.3.1. l The OSC Coordinator shall direct onshift . adiation Protection, Chemistry and Maintenance ~ chnicians to I j contact their i==ediate Supervisor ar discuss the ergency situation including any a ' itional manpower ( chnicians) that is required. 4.3.1.4 The O f Coordinator shall direc Radiation Protection
'- personn 1 to establish a radio ogical control point to
' maintain he cleanliness of e OSC.
4.3.1.5 If any addit'onal manpoue is required, Coordinator s 11 call C curity at ext , in the Onshift "mergen f Organization or en sonnel
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j 1 Resources Coordt ator at the TSC in the Onsite E=crgency Organiz n. Request the required technicians be man- 11y notified to report to the OSC or as otherwise .re ted. i l 4.3.1.6 The Mechanica 5 to the affe Maintena.ce Shift Fore =an shall report ed unit OSC s per Appendix C, " Repairs Coordinatr- Response." 4.3.2 Activation f the Alternate OSC 4.3.2.1 In
.e event the primary OSC be mes uninhabitable
( e Appendix B for habitability riteria), the mergency Coordinator shall direct OSC personnel to evacuate / report to the alternate OS (i.e., Service Building). , 4.3 2.2~ The .0SC Coordinator shall ensure the tra. sport of emergency equipment, including decontamin ion N pplies, necessary to est5blish the altern te OSC. l M- O jhNI
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% 4.3.1.2 The following personnel shall repor: to the OSC and Qg follow the directions of the OSC Coordi.ator:
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,(2) Radiarien Protection Personnel N, 4 E ,
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4 'N - " E ti it o 3 4.3.1.3 l *E 5s The OSC Coordinator shall direc: enshif Radiation Prctection, Chemistry and Maintenance Technicians to l j .! M p contact their i==ediate Supervisor and discuss the g { {j0 g emergency situation including any additional nanpower (Technicians) that is required. Ecc 4.3.1.4 I .- The OSC Coordinator shall direct Radiation Protection ( , personnel to establish a' radiological control point to maintain the cleanliness of the OSC. 4.3.1.5 If any additional =anpower is required - CSC Coordinator shall call Security at ex: m, w_
. in the Onshif: E=ergency Organization or the Personnel l Resources Coordinator a: the TSC in the Onsite .
E=ergency Organization. Request the required technicians be manually notified to report to the OSC or- as otherwise directed. . 4.3.1.6 The Mechanical Maintenance Shift Fore =an shall report to the affected unit OSC as per Appendix C, " Repairs Coordina:or Response." 4.3.2 Activation of the Alternate OSC
- 4.3.2.1 In the event the primarf- OSC beco=es uninhabitable (see Appendix B for habitability criteria), the E=ergency Coordinator shall direct OSC personnel to -
evacua:e/ report to the alternate OSC (i.e.. Service Building). 4.3.2.2 . The OSC Coordinator shall ensure the transport of
~e n rgency equip =ent, including decontanination supplies, necessary to establish tte alternate OSC.
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4.3.2.3 In the event the alternate OSC becemes uninhabitable (see Appendix B for habitability criteria), CSC persennel shall report to one of the protected facilities (i.e., Control Room / Satellite Technical l "- Support Center, Technical Support Center, E=ergency
-Operations Facility) per the Emergency Coordinator's direction.
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S Page 10 of 16 OSC COORDINATOR (ONSHIFT AND ONSITE)
RESPONSE
u POSITION FILLED BY: (1) I & C Shift Maintenance Personnel RES?CNSIBILITY: Activate CSC. Coordinate, assemble and dispatch manpower and equipment resources available at OSC. Serve as OSC Assembly Area Supervisor. IT'EDIATE ACTIONS .
- l. Report to OSC upon notification.
- 2. Ensure that co=munication devices are operable.
NOTE Personnel accountability is at the Shift Supervisor / Emergency Coordinator's discretion at (4 ,; an ALERT. It is mandatory at Site Area Emergency or higher.
- 3. Conduct personnel accountability per EPIP-20, " Personnel Asse=bly and Accountability."
(1) Obtain badge numbers and names of emergency personnel y reporting to OSC and complete Individual Accountability Sheet. (2) Inform Security Director of accountability within 20 minutes of initiation of signal.
- 4. Ensure that OSC emergency equipment and supplies are available and in a state of readiness.
- 5. Ensure that OSC reporting personnel have signed in on the OSC Staffing Board.
, 6. Direct Radiation Protection, Chemistry, and Maintenance Technicians , to contact their i= mediate Supervisors and discuss the emergency situation including any additional manpower requirements.
- 7. Ensure' that a radiological control point clean 112.L W of the OSC. - x-is established to maintain a
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- 8. Report OSC readiness to E=argency Coordinator at STSC/CR (Onshif t) using a dedicated dedicated phone line.phone line or at the TSC (Onsite) using the TSC h!.4 Occa essa e
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OPERATIONS SUPPORT CENTER ACTIVATION 3 Page 11 of 16 SUBSECCENT ACTIONS ALTERNATE CSC u
- 9. If the pri=ary OSC is uninhabitable, relocate OSC staff and necessary equip =en to the alternate OSC, as directed by the Emergency Coordinator.
(1) Service Building is the first alternate. (2) If the Service Building is also uninhabitable,' relocate to one of the protected facilities (i.e., STSO/CR, TSC, EOF). SEARCH AND RESCCE
- 10. Upon direction from E=ergency Maintenance Cc:rdinator, form Search and Rescue Team (s) per EPIP-21, " Search and Rescue."
4 r (1) Each team consists of 2 members. (2) Assign one member as Team Leader.
- 11. Obtain information from the Emergency Coordinator concerning identification and location of missing persens.
- 12. Provide Team (s) with ' search and rescue data:
(1) I.D. of missing person (s) . (2) Last known location (check REP if one was issued). (3) Job the individual was working. i (4) Portinent details of plant status.
- 13. Deter =ine radiation levels and stay times with Radiation Protection Monitor (STSC) using the Radiological line or with Radiological Protection Coordinator (TSC, when activated) also using the
? Radiolegical line. .
- 14. Inform the Team (s) of radiation exposure limits, if necessary, in accordance with EPIP-18, " Emergency Exposure Guidelines."
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- 15. Direct Team (s) to notify Hazards Control Coordinator byradio (at
. TSC when activated) of location and/or removal of missing personnel.
- 16. Recall Team via radio when search and rescue operations are no longer necessary.
- 17. Inform the Hazards Control Coordinator at the TSC using the TSC dedicated phone line when Team has concluded its activities and returned to OSC.
RE-ENTRY FOR E!ERGENCY OPERATIONS ,
.18. Direct the Repairs Coordinator to Deploy Emergency Repair Teams, per E?IP-25, "Re-entry for Emergency Operations," upon direct on from Control Room (Onshift) or the Emergency Maintenance Cordinator in the TSC (Onsite).
_ AREA /EOUIP!ENT MONITORING AND DECON"I A'1INATION
- 19. Deploy Decontamination Teams , per ;;l282 .32h,78
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"cnirm' ;; >-> rrer- -inarien," upon guidance from Control Room 4 7 (Onshift) or the Emergency Maintenance Coordinator in the TSC k (Onsite). q k (1) Team shall consist of one Radiation Protection Technician and necessary Chemical, F,fachanical, Electrical, or I & C Technicians.
PERSONNEL
*20. Coordinate OSC personnel requirements with.the Personnel Resources Coordinator t.. the TSC, using the TSC dedicated phone line.
Continuing Activity
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*21. F.aintain an E=ergency Action Log throughcu: eme ;ency. -
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPE!QIX 3 IMPLEMENTING PROCEDURE EPIP-12 Page 1 of 1 OPERATIONS SUPPORT CESTER ACTIVATION 5 Page 14 of 16 CSC HABITABILITY CRI'2RIA The following limits should be considered upper limit habitability criteria. CONSIDER AIRBORNE EVACUATION VROLE SCDY DCSE RATE ACTIVITY CONCEhTRATICS 'k'ITHIN 2-10 mre=/ hour 1-4 x MPC 10-50 crem/ hour 48 hours
' 4-20 x MPC 10 hours 50-100 mrem / hour 20-40 x MFC 5 hours 100-500 = rem / hour 40-200 x MPC 1 hour
> 500 cre=/ hour > 200 x MPC Immediately 1
Where MPC is the =ax1=um permissible concentration for areas as defined in
~- Column 1, Table I, Appendix 3 to 10CTR20. This calculation will allow 200 k,, ;' MFC hours which censervatively limits int' e rnal expesure. This criteria is based on personnel not wearing respiratory equip =ent.
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-A nPPENDIX.C IMPLEMENTING PROCEDURE EPIP-12 Page 1 of 2 OPERATICSS SUPPORT CESTEE ACTITATION 5 Page 15 of 16 REPAIRS C00RDISATCR RESPOSSE POSIT *0N P'I.EED BY: Mechanical Shift Maintenance Foreman.
RESPONSI3IIITY: Ensures that Maintenance Technicians and Emergency Repair Teams are dispatched at the direction of the Emergency Maintenance Coordinator. IP'!EDIATE ACTIONS:
- 1. Report to the OSC upon notification and sign in.
- 2. Assist OSC Coordinator with OSC activation as required.
- 3. - Establish ces.munications with the Emergency Maintenance Coordinator when TSC is activated.
SCESECCENr ACTIONS 4.
- Deploy Emergency Repair Teams, per EPIP-25, "Re-entry for E=ergency Operations," upon direction from Centrol Room (Onshift) or the E=ergency Maintenance Coordinator in the TSC (Onsite) or OSC Ccordinator.
(1) Team shall cans'ist of at least two '-faintenance Technicians and, if radiological conditions necessitate, assign a Radiation Prctection Technician to the team. (2) Designate one member the Team Leader. w 2 msacs <ssa .
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( PVNGS EMERGENCY PLAN proCecust NO. APPENDI.IC IMPLEMENTING PROCEDURE EPIP-12 Page 2 of 2 OPERATICSS SUPPORT CENTER EM CN AC IVATION 5 Page 16 of 16 REPAIRS C00RDISATCR RESPOSSE 5. Receive infor=ation from E=ergency Coordinator, Emergency 4 Maintenance on: Ccordinator and/or Radiological Protection Coordinator (1) Work to be performed. (2) Nu=ber or people required. - (3) Equipoent needed. (4) Radiation conditions, if kno n.
*6.
Receive 1/2 hour reports from Team Leader via portable radio.
, *7.
s Receive report frem Team Leader upon leaving if task cannot be
*,1 ce=pleted in allotted stay ti=e 'or allotted dese.
*8.
Maintain an E=ergency Action Log throughout the emergency.
- Continuing Activity ;
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Kev. 9 . Page 29 of 33. I Procedure No. Revision: (PCN No. (co': sin from C only)l l ERP-/3 l 5 l ... l l l
Title:
IDDC Contact (ext. :o33) l Eiweye,x,y Cp.s:/cas Sce/id l Orignator: (Print) f dcAvador, lex:. l%44 l Unit (s) affected: l l Gentkf' A '$imip/l* MI ' ' l Reason for this PCN: l 5 nellsi n r /ws b EM-CC " S,4 hu Em.w-vw Ink ~d~. l # / '
/ l r l Atbens "n,el 6P/p Cb . Gen.n /E~n,~<v z.~asnd.,a. /L4e.,s
l ' / l Expir'azion: l prnunesh l Page nu=cer(s) affected ITo:al Succer of by this PCN: lPages a::achec: l g y l I g l- Does PCN require a 30.39 review? )( No I
] I Yes (re:er to 2.1.2) [
' i l- Does PCN affect activities in l the RCA? X' No Yes (Copy :o ALGA) l 1 l l
l- Does PCN effect the non-radiogical l
! environ =ent of any offsite area? X No Yes (Con:ac: Co=pliance) l l
l l- Is PCN associated with an AC, l Program, E= erg. Plan or Secur. l l Prog., Phase I-IV Test, or a No X Yes (PR3/PRG/TRR3 1 l ST? revie:t required)
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f~;., / TECHNICAL REVIEkT,R (Supervisory Level hYhb Date l l b %WW PRS /PRG/TRRG,grIIIR.' TAN (if required; ' Yk Dace ' s h [p f' On ~ U hYNtun f/ /*;G FpALAPPROVAL / Dac'e [
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t i$ s s/u EFFE C ~ 1 ' i Numoer (CDC only)
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EMERGENCY OPERATIONS REVISION FACILITY ACTIVATION 5 Page 1 of 50 1 4 i .s
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PVNGS '# DEPT. HEAD v #St/NIN DATE / 2/v [
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DATE // [' APPROVED BY / , "= DATE / [. 4
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EFFECTIVE DATE Cl 'I6 b' DN-1765A/0295A
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- EMERGENCY OPERATIONS REVISION FACILITY ACTIVATION 5 Page of 50 REVISION HISTORY Rev. No. Date Revised Pages Comments 3 05-01-85 All Total Revision Incorporating EPIP's 39-52 4 09-18-85 5, 6, 13, 14 Incorporation of procedure 15, 17, 22, drill comments. New phone 23, 24, 45 numbers and editorial changes.
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EMERGENCY OPERATIONS REVISION 5 FACILITY ACTIVATION 5 Page 3 of 50 4 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 5
2.0 REFERENCES
S 3.0 LIMITATIONS AND PRiCAITTIOh3 . 6 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination /Resvasibilities 6 4.2 Prerequisites 7 4.1 Instructions 7 APFENDICES Appendix A - Emergency Command Center Equipment Layout 10 Appendix B - Em srgency Command Certer Layout 11 Appendix C - Emergency Operations Director Response 12 Appendix D - Administrative and Logistics Coordinatoc Response 16 - Appendix E - Radiological Assessment Coordinator Response 19 Appendix F - Technical Analysis Ccordinator (Offsite) 22
Response
Appendix G - Radio)n~ical Assessment Communicator Response 25
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Appendix H - Government Liaison Engineer Response 27 Appandix T - EOF Contact Response 29 Appendix J - Logistics Communicator Response 32 v CONTROLLED BY USER .. l
CONTROLLED BY USER g PVNGS EMERGENCY PLAN [ROCENRE o IMPLEMENTING PROCEDURE EPIP-13 EMERGENCY OPERATIONS REVISION I FACILITY ACTIVATION 5 Page 4 of 50 TABLE OF CONTENTS APPENDICES (CONT'D.) Appendix K - Security Cooridnator Response 34 Appendix L - Dosimetry Clerk Response and TLD Log -- 3 6 Appendix M - Clerical Aide / Status Board Keeper - EOF Response and Status Boards , 39 Appendix N - Off-site Technical Representative Response and Log 45 t Appendix 0 - JENC Technical Advisor Response 48
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Appendix P - Security Force Member Responsa 49 i ,' Appendix Q - EOF Floorplan 50 O e 9 e o h s
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2.0 REFERENCES
Implementing References 2.1 2.1.1 EPIP-04, "'"" '-%+ menti g acenn"-
"A s y
krr,S.le8amcadG.,..,alEm<ayncy hp!<.enhyAcbcas' 2.1.2 E?!?-C5, " :T: lCA ;" n=;;; : f ;;: . 1; f.ct i: , "- g 4 2.1.3 I?:? 04, "==at nrmm : -n 1-t <-; --e" R 2.1.4 EPIP-14A, " Release Rate Determination" 2.1.5 EPIP-14B, " Initial Dose Assessment" - 2.1.6 EPIP-14C, " Continuing Dose Assessment" , 2.1.7 EPIP-31, " Recovery" 2.1.8 EPIP-33, "Offsite Assistance" 2.1.9 9N219.05.00, " Document Record Turnover Control" , 2.2 Developmental References e 2.2.1 NUREG-0654, Rev. 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." 2.2.2 hVREG " 96, Feb.1981, " Functional Criteria for Emergency Response Facilities." 2.2.3 PVNGS Emergency Plan, Rev. 6. 2.2.4 ANSI N45.2.9 - 1974, " Requirements for the Collection, Storage,.and Maintenance of Quality Assurance Records for Nuclear Power Plants."
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- EMERGF.NCY OPERATIONC REVISION FACILITY ACTIVATION 5 Page 6 of 30 3.0 LIMITATIONS AND FRECAUTIONS 3.1 " Activation of the EOF should be completed within the time .
augmentation goals as set forth in the PVNGS Emergency Plan. 3.2 Each individual in the EOF upon event termination shall submit any written documentation to the Emergency Operations Director who ensures they are forwarded to Emergency Planning Dept. for storage in accordance with 9N219.05.00, " Document Record /
. Turnover Control."
3.3 The EOF may be used by designated personnel for normal daily activities as well as for training and emergency drills. Use of this facility shall be limited to activities that will not degrade preparedness to react to abnormal conditions or reduce system (s) reliability. This use should be reviewed by the Site Emergsney Planning Supervisor. r ( 4.0 DET/ILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities .. 4.1.1 The EOF is the focal point for coordination of onsite and offsite emergency response activities. Management and technical personnel assigned to the EOF are responsible for protective action' recommendations, liaison with offsite governmental organizations and response facilities, and overall management of the PVNGS emergency organization. 4.1.2 During an ALERT, or more severe accident, overall command and coordination of ANPP emergency operations shall be exercised by the Emergency Operations Director at the EOF. He shall provide direction and support for inplant emergency response actions to the Emergency Coordinator, and coordinate corporate support through the CEC. In addition, he shall communicate plant status updates and . radiological release data to the Joint ENC and the CEC. s
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CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE p N O. IMPLEMENTING PROCEDURE EPIP-13 , EMERGENCY OPERATIONS REVISION FACILITY ACTIVATION 5 Page 7 of 50 4.1.3 Functional assignments at the EOF, in addition to those of the Emergency Operations Director are: 4.1.3.1 Radiological Analysis Receive and evaluate source-term, release and meteorological information from the TSC. Interface with AERA representatives to recommend protective action (s) for the population-at-risk. 4.1.3.2 Technical Liaison ~ Function as a primary interface with NRC/ state / county personnel stationed in the EOF to provide updates on the status of the reactor and unit. 4.1.3.3 Administrative and Logistics Support . . Provide needed technical documents, communications and
/ t.naly:ical equipment, clerical assistance, transportation / housing support and security for EOF.
4.1.3.4 Public Information Support Gatiter necesscry information and transmit for . subsequent release to the media from the Joint ENC. l 4.1.4 The EOF shall be activated and manned for an ALERT or more severe emergency classification. 4.2 Prerequisites - 4.2.1 An ALERT or more severe level emergency has been declared and procedure EPIP-04, " ALERT Ispicsenti ; Actionsh E"!P-05, "SI"'E l'EA EMERCESOY Irpl::::tir; i 44ons," rr
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- EMERGENCY OPERATIONS REVISION b FACILITY ACTIVATION 5 Page 8 of 50 NOTE Each individual listed is responsible for set up of their working area of the EOF.
This includes phone hook-up (if necessary) and breaking out from the storage closet all required material to function properly. 4.3.1.2 The following Offsite Emergency Organization personnel shall report to the EOF: (1) Emergency Operations Director - Appendix C,
" Emergency Operations Director Response."
(2) Administration and Logistics Coordinator - Appendix D, " Administration and Logistics Coordinator Response." (3) Radiological Assessment Coordinator - Appendix E,
.} " Radiological Assessment Coordinacor Response."
(4) Technical Analysis Coordinator - Appendix F,
" Technical Analysis Coordinator Response."
(5) Radiological Assessment Communicator - Appendix G,
" Radiological Assessment Communicator Response."
(6) Government Liaison Engineer - Appendix H, .
" Government Liaison Engineer Response."
(7) EOF Cor. tact - Appendix I,
" EOF Contact Response."
(8) Logistics Communicator - Appendix J,
, " Logistics Communicator Response."
(9) Security Coordinator - Appendix K, -
" Security Coordinator Response." .
(10) Dosi=stry Clark - Appendix L,
" Dosimetry Clerk Response and TLD Log."
(11) Clerical Aide / Status Board Keeper - Appendix M,
" Clerical Aide / Status Board Keeper-EOF Response."
(12) R.P. Support Staff - To Be Filled By Training Fersonnel.
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- 4. 3.1.4 ' The JENC Technical Advisor shall report to the Joint Emergency News Center as per Appendix 0.
4.3.1.5 Appendices A, B and Q are provided to shew EOF layout and floorplan. - 4.3.2 Declaration of EOF Readiness 4.3.2.1 Upon completion of EOF staffing and readiness checks, the Emergency Operatlons Director shall contact the Emergency Coordinator, the Corporate Emergency Center (if activated) and the Joint Emergency News Center and inform them that the EOF is operational.
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- 12. High Speed Telecopier 23. Map Table :
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- 2. Ops. Voice #1 13. Telecopier Circuit #1 5
- 3. Exec. Pvt. Line 24. Ops. Voice #3 l
- 14. Telecopier Circuit #2 25. State Radio
- 4. NOAA Weather Radio 15. SIMS/MMIS Computer '
- 5. Technical Line 26. Ops. Voice #2
- 16. ERFDADS Printer 27. CR Line !
- 6. ERFDADS Terminal 1
- 17. ERFDADS Terminal 28. High Speed Telecopier'
- 7. NAN 18. CRACS
- 8. Ops. Voice #4 29. ANPP Radio .
- 19. Env. Assmt. Line 30. EOF Emergency Kit
- 9. Public Info. #1 20. IBM Computer
- 10. OSC Line *21. TSC Line 31. ERFDADS Terminal
- 32. ERFDADS Terminal
- 11. Copy Machine 22. STSC Line 33. REMS Terminal i
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DOSIMETRY OFFICE C - Emergency Operations Director D - Administrative and Logistics Coordinator E - Radiological Assessment Coordinator F - Technical Analysis Coordinator G - Radiological Assessment Coordinator H - Government Liaison Engineer I - EOF Contact J - Logistics Communicator K - Security Coordinator , L - Dosimetry Clerk M - Clerical Aide / Status Board Keeper N - Radiological Support Staff 0 - State of Arizona P - Federal Emergency Management Agency
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- No 'A' & 'B' designated. Letters C through M correspond to the position appendices of this procedure.
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,r PVNGS EMERGENCY PLAN Qcaouse APPENDIX C IMPLEMENTING PROCEDURE EPIP-13 Page 1 of'4 EMERGENCY OPERATIONS REVISION FACILITY ACTIVATION 5 Page 12 of 50 EMERGENCY OPERATIONS DIRECTOR (OFFSITE)
RESPONSE
POSITION FILLED BY: (1) Assistant Vice-President, Nuclear Production (2) Manager, Operations (3). Director, Technical Services RESPONSIBILITY: Command and coordinate ANPP emergency operations. Maintain overall responsibility for ANPP onsite and offsite cciergency functions. Interface between ANPP and federal / state / county emergency response agencies. Oversee the communication of plant status updates and i ' radiological release data and the notification of state and local agencies concerning recommended protective actions. Provide administrative, technical, and logistical
' f support to station emergency operations and
,f ensure the continuity of emergency organiration
' resources. Make appropriate exceptions to QA/QC '
and. plant administrative procedures. ,
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IMMEDIATE ACTIONS: NOTE All actions listed shall be noted in the' EOD Log by the EOD or EOD Stenographer. 1. Report to the EOF upon notification. Upon arrival, sign in on the EOF Staffing Board.
- 2. Contact Emergency C6ordinator at TSC using Emergency Coordinator / Emergency Operations Director (EC/EOD) line and review:
(1) Basis for classification of event. (2) Status of plant conditions. (3) Corrective actions being implemented. . (4) Status of notifications to other ANPP offsite staff and offsite emergency management agencies. l 1 3. y Ensure that all the following positions are staffed. As necessary, assign temporary personnel to fill staff positions until primary personnel arrive. ; l 1 CO.NTROLLED BY USER
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( 1) Radiological Assessment Coordinator ( 2) Technical Analysis Coordinator ( 3) ECF Contact - ( 4) Administrative and Logistics Coordinator ( 5) Logistics Communicator ( 6) Government Liason Engineer ( 7) Security Coordinator ( 8) Clerical Aide / Status Board Keeper ( 9) Radiological Assessment Communicator - (10) Dosimetry Clerk (11) Alternate EOD (to serve as an assistant if needed)
- 4. Conduct briefing with available EOF personnel. As a mini =um, the following items should be discussed:
(1) Adequacy of activation. (2) Ability of assigned personnel to assume their emergency duty roles.
, (3) Operability of equipment.
' f . {j 5. Notify the Emergen:y Coordinator at the TSC using EC/EOD line, the Corporate Emergency Director at the CEC using the Executive Private Ringdown circuit and ADES (TOC) using OPS voice circuit Number 1 that: - (1) EOF is operational (2) Current plant status
- (3) Reco= mended protective actions 6.
Make Site Wide Public Address Announcement that the EOF is operational or delegate this to the ALC. 7. Ensure EOF contae.t notifies the Joint Emergency News Center (JENC) that: (1) The EOF is operational. . (2) The EOD has assumed centrol and responsibility for offsite
- communications.
*8. As appropriate, make*exceptions to QA/QC and plant administrative procedures.
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e f PVNGS EMERGENCY PLAN [R CEDURE APPENDIX C ( _ IMPLEMENTING PROCEDURE EPIP-13 Page 3 of 4 EMERGENCY OPERATIONS REvt5 ION FACILITY ACTIVATION 5 Page 14 of 50 9. Ensure the following offsite agencies are contacted and notified by the GLE that the EOF is operational and the Emergency Operations Director is in command and has offsite communications responsibilities. (1) Arizona Division of Emergency Services (using dedicated voice circuit). (2) Arizona Radiati..a Regulatory Agency (using dedicated voice circuit). (3) Maricopa County Dept. of Civil Defense and Emergency Services (using dedicated voice circuit). (4) NRC Headquarters (using ENS). 10. Ensure the Followup Emergency Messagri Form is coinpleted by the GII in anticipation of next offsite update and recommendation of protective actions. s
/ 11. Provide initial briafing to federal and state staff at EOF.
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*12. Brief EOF staff periodically using the EOF Public Address System.
- 13. As necessary, place EOF on recirculation.
14. If evacuation is ordered, receive from Emergency Coordinator total number of evacuees. Total SUBSEQUENT ACTIONS: Notification
*15. Review onsite actions and requirements periodically with the Emergency Coordinator.
*16. Communicate with Corporate Emergency Director and provide periodic status updates as necessary. l
*17. Consult with EOF Staff as necessary. . 1 l
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- 13. Repeat steps 8 and 9 periodically as necessary and whenever the emergency ,
class changes. .
- 19. Upon downgrade or termination of Emergency Classification, notify PVNGS Compliance Dept, to provide a written summary to offsite authorities within eight hours.
Recovery '
- 20. Do not inform JENC of downgrading, coordinate release of this information through the State EOC/ TOC so that protegtive action recommer.dations may be considered.
- 21. Consult with Emergency Coordinator, NRC. (in EOF), ADES and ARRA (in EOF);
Declare the emergency over when the unit is in a controlled, stable
, e condition; notify offsite agencies as in Step 8 and the ANPP emergency organization.
- 22. Collect all EOF personnel documentation and logs.
(1) Technical Analysis Coordinator (2) EOF Contact - (3) Radiological Assessment Coordinator - (4) Administrative and Logistics Coordinator
- 23. Establish Recovery Orgsnization and assume duties and responsibilities of Recovery Manager in accordance with EPIP-31 " Recovery."
- 24. Notify affected offsite Emergency Management Organizations using dedicated voice circuit systems that recovery operations are in progress.
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RESPONSE
POSITION FILLED BY: (1) Manager, Operations Ccmputer Systems (2) Other Designated Personnel with
- appropriate training RESPONSIBILITY: Calls in offsite resources and plans and provides logistical support for the onsite emergency organization.
Logistical support includes prevision of needed technical documents, additional communications and analytical equipment, additional security support, manpower support, transportation, housing and f feed needs. Acts as liaison to reporting support personnel and American J Nuclear Insurers. IMMEDIATE (CTIONS: , 1. Report Board. to EOF upon notification. Upon arrival, sign in on the EOF Staffing
- 2. Receive initial briefing from Emergency Operations Directer and establish responsible area.
- 3. Ensure that the following equipment is operational:
(1) SPDS (2) CRACS (3) EOF RE&M Terminals l l (4) EOF SIMS Terminal e CONTROLLED BY USER .* \ {
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. u NOTE The SIMS/MMIS Computer Staff reports to the Administrative and Logistics Coordinator and normally returns to the SIMS/MMIS data center. If the Annex
- Building is uninhabitable, they relocate to the EOF. --
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- 4. Ensure that the following positions are staffed and fully briefed:
(1) Logis;ics Communicator. (2) Security Coordinator. (3) Clerical Aide / Status Boardkeeper (4) DDC Staff (5) SIMS/MMIS Computer Staff
- 5. Check that facilities available to Emergency Response Personnel are j adequate.
NOTE The SIMS/MMIS Computer Staff reports to the Administrative and Logistics Coordinator and normally returns to the SIMS/MMIS data center. If the Annex Building is uninhabitable, they relocate to the EOF.
- 6. 'rdvide risadiness briefing to Emergency Operations Director-
- 7. Maintain .1 log of actions as required.
- 8. If so directed by the EOD, make site wide P. A. Announcement that the EOF is operational.
SUBSE0llENT ACTIONS: Offsite Assistance .
*9. Contact support organizations listed in EPIP-33, "Offsite Assistance,"
to obtain necessary t'echnical and/or additional manpower support (assume this function from Emergency Coordinator) using the commercial telephone line (see EPIP-33 for phone numbers). 4 e--
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*10. Contact American Nuclear Insurers, using the commercial telephone line and keep ANI informed of situation as nec.essary (until relieved of this responsibility by the Corporate Financial Coordinator).
Logistical Support
*11. Obtain, as necessary, required:
(1) Technical documents (2) Communication equipment (3) Analytical equipment (4) Manpower support (S) Transportation support (6) Housing and food for Emergency Response Personnel
*12. Assist Government staff with logistics as necessary.
) Recovery
- 13. Receive any documentation and associated logs from the Logistics Communicator after emergency is terminated.
- 14. Receive any documentation and associated logs from the Security Director after emergency is terminated.
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- 15. Receive any documentation and associated logs from the Clerical Alde/ Status Board Keeper after the emergency is terminated.
- 16. Submit documentation, logs, and other data to Emergency Operations Director when emergency is cancelled.
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PVNGS EMERGENCY PLAN [R CEDURE IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 3 EMERGENCY OPERATIONS REVISION 'I FACILITY ACTIVATION 5 Page 19 of 50 RADIOLOGICAL ASSE3SMENT COORDINATOR RESPCN3E POSITION FILLED BY: (1) Manager, Radiation Protection & Chemistry (2) Other Designated Personnel RES01NSIBILITY: Principal liaison of the PVNGS emergency response organization with the Radiological Technical Directorate. Receive and evaluate dose rate-projection information from the Radiological Protection - Coordinator. Advise the Emergency Operations Director of protective tction recommendations to be provided to
- offsite authorities. Qoordinate offsite monitoring efforts. Direct the Radiological Assessment Communicator.
IMMEDIATE ACTIONS: *
- 1. Report to EOF upor. notification. Upon arrival, sign in on the EOF Staffing Board.
4
- 2. Peceive initial briefing frcm Emergency Operations Director and establish responsible area.
3. Ensure that the Radiological Assessment Communicator's position is staffed and fully briefed and that communication systems are
, operational.
- 4. Ensurt R.P. Support Staff is briefed and ready to perform dose projections.
*5. Access CRACS to receive current dose projection data. (If CRACS is ava!!able)
- 6. Ensure operational status of dose calculation computer Continuing Activity e
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IMPLEMENTING PROCEDURE EPIP-13 Page 2 of 3 EMERGENCY OPERATIONS REVISION I i j FACILITY ACTIVATION 5 Page 20 of 50 RADIOLOGICAL ASSESSMENT C00kDINATOR
RESPONSE
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- 7. Ensure that the following materials needed to parform manual dose assessments are available:
(1) EPIP-14A, " Release Rate Determination" i ElIP-14B, " Initial Dose Assessment" I EPIP-14C, " Continuing Dose Assessment" - (2) Isopleths (3) Base Map
- 8. Contact the Radiological Protection C tor at TSC using the Envirer.rsntal Assessment line at ex d-determine
*(1) Extent and consequence of radio 1'ogical releases and plant conditions, (g (2) Protective action recomnendations esde to date.
(3) Potential for future radiological releases. (/ *(4) Location of of fsite field monitoring teams, when dispatched. (May also contact Radiation Protection Monitor for this information)
- 9. Maintain a log of actions as required.
SUBSEQUENT ACTIO'S: Jose Rate Projections 1C. Analyz, source term, meteorological and field monitoring data to determine reasonableness and consistency of data with dose projections used as basis for protective actions.
*11. Evaluate plant conditions to determine probability and magnitude of possible emission increases.
*12. Ensuri Radiological Statua Boards are updated as infermation becomes <
available.
- Continuing Activity I
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IMPLEMENTING PROCEDURE EPIP-13 Page 3 of'3 E.MERGENCY OPERATIONS REVISION I TACILITY ACTIVATION 5 Page 21 of 50 RADIOLOGICAL ASSE3SMENT COORDINATOR RES10NSE Protective Actions
*13. Advise the Emergency Operations Director as te the need for protettive actions.
*14. Provide updates to State of Arizona Representative concerning Pmtective Actions.
Field Mon toring
*15. Provide updttes to the ARRA State Representative as necessary.
*16 Direct Radiological Assessment Communicator to position offsite field
, monitoring teams, as necessary
,/ Recovery ,
l 17. Retelve. any documentation ano associated logs from the R tdiological i Assessment Communicator after emergency is terminated.
- 18. Receive any documentation and associated logs from the Dosimetry Clerk after emergency is terminated.
- 19. Submit documentation, logs and other data to Emergency Operations Director when emergency is cancelled.
- Continuing Activity
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PVNGS EMERGENCY PLAN Q cewas APPENDIX F. IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 3 EMERGENCY OPERATIONS FACILITY ACTIVATION REVISION f 5 Par,e 22 of 50 TECHNICAL ANALYSIS C0ORDINATOR (OFFSITE) RESIONSE POSITION FILLED BY: (1) Designated person from Shift Technical Advisor (STA) Group (2) Other Designated Personnel RESPONSIBILITY: Function as the primary interface with NRC/ state / county personnel stationed in the EOF. Provide updates on the status of the reactor and unit. Supervise the GLE and OTR. I!DfEDIATE ACTIONS: - f '
- 1. Report to EOF upon nctification. Upon arrival, sign in on the EOF Staffing Board. ,
2. (,, . , Receive initial briefir.g from Emergency Operations Director and establish responsible area. l
- 3. Ensure that the following positions are staffed and fullt briefed: -
(1) Government Liaison Er.gineer. (2) Offsite Technical Rep:esentative.
*4 Obt reation on plant status from TSC using the Technical line (ex r normal phone line.
*S. Brief Emergency Operations Director on operational status.
*6. Maintain a log of actions required.
- Continuing Activity
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*7. Provide Emergency Operations Director uith technical guidance on how plant status may impact offsite emergency response actions. ~
*8. Receive reports on technical changes and recommendations from the Technical Engineering Coordinator in ti;e TSC.
Government Staffing at EOF
+9 Provide updates to NRC, state, and county personnel as necessary on the status of the reactor and uni:; assisted by Government Liaison Engineer.
Public Information
*10. If so directed by the EOD, verify the technical accuracy and adequacy of all public information releases prior to dissemination to the news -
media.
- Continuing Activity I
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- 11. Receive any documentation and associated logs after emergency is terminated from (1) Government Liaison Engineer (2) Offsite Technical Representative
- 12. Submit documentation, logs and other data to Emergency Operations Director when emergency is cancelled.
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PVNGS EMERGENCY PLAN [ROCEME o APPENDIX G IMPLEMENTING PROCEDURE EPIP-13 Page 1 of '2 EMERGENCY OPIRATIONS REVISION h FACILITY ATIVATION 5 Page 25 of 30 RAIICLOGICAL ASSESSMENT COMMUNICATOR
RESPONSE
POSITION FILLED BY: (1) Designated person from Radiation Protection Section with appropriate training. (2) Other Designated Personnel RESPONSIBILIH: Maintain a record of matters pertaining to radiological assessment. Maintain communications with radiological assessment personnel at the TSC and STSC. D! MEDIATE ACTIONS:
- 1. Report to EOF upon notification. Upon arrival, sign in on the EOF Staffing Board.
- 2. Obt. tin initial brieflag from Radiological Assessment Coordinator and establish responsible ares.
- 3. Determine operability of folicwing communications circuits:
(1) Normal phone (2) Dedicated voice circuits (3) Environmental Assessment Line (4) Base station radio
- 4. Report inoperable circuits to Radiological Assessment Coordinator and Administrative and Logistics Coordinator.
*5. Establish and maintain communications with T3C and STSC Radiological Assessment personnel using the normal PBX phone line.
- Continuing Activity ,
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*6 Direct offsite radiological field assessment teams to various sampling 1ccations as requested by the Radiological Assessment Coordinator.
Coordinate team movement with stata and other agency teams as required.
*7. Plot reported dose rates and various team locations as an aid in plume tracking. ,
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Inform the Radiological Assessment Coordinator of changes in radiolog,1 cal status. r
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Maintain records of communications concerning radiological assessment.
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*10. Maintain a log of actions as required Recovery 11.
Submit any documents and logs to Radiological Assessment Coordinator when emergency is cancelled.
- Continuing Activity ,
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[R IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 2 EMERGENCY OPERATIONS REVISION h I FACILITY ACTIVATION 5 Page 27 of 50 GOVERNMENT LIAISON ENGINEER
RESPONSE
POSITION FILLED BY: (1) Designated person from Nuclear Engineering or Licensing Department with appropr.iate training. (2) Other Designated Personnel RESPONSIBILITY: Relieve STSC Communicator of responsibility of making initial and subsequent notifications of changes in
- emergency classification to Federal, State and County Agencies. Assist Technical Analysis Coordinator with briefings of Govern =ent stsff at EOF. 'l l
IMMEDIATE ACTIONS: 1 1
- 1. Report to EOF upon notification. Upon arrival sign in on taa EOF Staffing Board.
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- 2. Establi.h responsible area.
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- 3. 7 Receive initial briefing from Technical Analysis Coordinator.
4 ' fo the STSC Com=u icator, using the normal phone line (Unit I - ext. Unit II - ex ' hat you are on station and assume the responsibility for of fsite notifications of changes in emergency classification.
*S. Establish and maintain communications with offsite agencies, per EPIP-04, EPIP-05, or EPIP-06 and using Voice Circuit #4.
*6. Maintain log of communications per EPIP-04. I"I" 05, - EMP-04,- k i
- Continuing Activity
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IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 2 EMERGENCY OPERATIONS REVISION h FACILITY ACTIVATION 5 Page 28 of 50 IMMEDIATE ACTIONS: (Cont'd)
- 7. Notify the FAA using commercial phone lines as necessary.
- 8. Notify the National Transportation Board using co=mercial phone lines as necessary. ,
*9. Maintain a log of actions as required.
SUBSEQUENT ACTIONS: . Government Staffing at EOF
*10. Assist Technical Analysis Coordinator with briefings of Govern =ent staff at EOF, as necessary.
Recovery
- 11. Provide termination of emergency announcement per EPIP-04, E2!P-05 er
(, . EPIP h N ( ;- * . 12. Submit any docume6tation, legs, and other data to Technical Analysis Coordinator when emergency is cancelled. -
- Continuing Activity.
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- 1. Report to EOF upon notification. Upon arrival, sign in on the EOF Staffing Board.
- 2. Receive initial briefing from Emergency Operations Director.
*3.
Establish and maintain communications with the CHIC Director until the
-, Joint ENC is activated. . *4.
Establish and maintain communications with the JENC Facility Manager at the Joint Emergency News Center using the Public Infor9ation Ringdown Phone Circuit #1. S. Report readiness to Emergency Operations Director.
*6. Maintain a log at actions as required.
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' PROTECTIVE ACTIONS RECOMMENDED TO STATE AUTHORITIES BY ANPP SHALL NOT BE TRANSMITTED TO THE JENC.
*7.
e Assure that press releases are reviewed expeditiously at the EOF by the Emergency Operations Director (EOD).
/ 8. Submit lo83 and other data to EOD when emergency is cancelled.
- Continuing Activity .
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- 1. EVENT CLASSIFICATION:
- a. UNUSUAL EVENT ALERT SITE AREA EMERGENCY
- b. GENEbL EfERGENCY. .
Basis (E A L) c. Relet.se (YES / NO) Vind: / / Speed From Stability
- c. Iaitiating Event:
- 1) Basis for event classification:
' 2. EMERGENCY FACILITY ACTIVATION:
- a. STSC/TSC (YES / NO) b. EOF (YES / NO) c. OSC (YES / NO)
- d. Accountability; Plant Evacuation: .
Ordered: (YE3 / NO) Complete: Missing People: (YES / NO) (YES / NO)
- e. Injuries (YES / NO) Search Ordered: (YE5 / NO) ,
Contamination: (YES / NO)
- 3. PLAST STATUS:
, Criticality: Rod Position: Boron:
Power: Hot Leg Temp: T ave: . RCS Pressure: Vessel Level: CTMT Pressure: CTMT Humidity: Temp: CTMT Dose Rate: CTMT Water Level: Sub Cool Margin: SI Flow;
, Pressurizer Level: RhT Level:
- 4. EQUIPMENT STATUS:
RCS Pumps: Turbine: Diesels: ,
, Charging Pumps:
Safety Injection - HPSI: A ,B LPSI: A B CTNT Spray: A - B CTMT Isolation: 5 RADIOLOGICAL STATUS: Value: Instrument Type: Meaning: ,
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IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 2 EMERGENCY OPERATIONS REVISION y FACILITY ACTIVATION 5 Page 32 of 50 LOGISTICS COMMUNICATOR
RESPONSE
POSITION FILLED BY: (1) Designated person from Materials Control Section with appropriate training (2) Other Designated Personnel RESPONSIBILITY: Maintain record of logistics support needed and obtained. Contact offsite support organizations to
, obtain needed support at direction of Administrative and Logistics Coordinator.
IMMEDIATE ACTIONS:
- 1. Report to the EOF upon notification. Upon arrival, sign in on the EOF Staffing Board.
' 2. Receive initial briefing from the Administrative and Logistics Coordinator. Establish responsible area, s
- 3. Ensure all EOF communications equipment is operational with assistance of Radiological Assessment Communicator.
- 4. Synchronize EOF clocks with affected unit control room clock.
S. Establish and maintain a record of logistic support obtained and required.
- 6. Report readiness to Administrative and Logistics Coordinator.
*7. Maintain an action log as required.
SUBSEQUENT ACTIONS: Offsite Assistance
*8.
Contact offsite support orgai.izations per EPIP-33. "Offsite Assistance " at direction of Administrative and Logistler Coordinator. , l
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- 9. Submit any documentation and records to Administrative and Logistics Coordinator upon cancellation of emergency.
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- 1. Report to EOF upon notification. Upon arrival, sign in on the EOF Staffing Board.
- 2. Receive initial briefing from Administrative and Logistics Coordinator and
, establish responsible area.
.. 3. Contact Security Director at TSC using the normal phose at ext. 7019 or .
alternate (the security radio frequency) to determine present sita access conditions. ,
- 4. Inferm the Administrative and Logistics Coordinator of site security conditions and report readiness.
*S. Maintain action log as required.
SUBSEQUENT ACTIONS: Securitv/ Site Access
- 6. Inform the Security Director at TSC using the normal phone or alternate (the security radio frequency), of offsite personnel required onsite to expedite badging process.
*7. Maintain communications with the Security Director at TSC using the normal l phone line regarding personnel granted access to site. .-
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*8. Process personnel necessary for site support prior to site entry i per appropriate security p'rocedures.
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. SECURITY COORDINATOR RESPONSE
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9. Submit any documentation and logs to the Administrative and Logistics Coordinator upon cancellation of emergency. l 7
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IMPLEMENTING PROCEDURE ' EPIP-13 Page 1 of 3 EMERGENCY OPERATIONS REVISION $ FACILITY ACTIVATION 5 Page 36 of 30 ) DOSIMETRY CLERK RESPONSE AND TLD LOG POSITION FILLED BY: (1) Designated person from Radiation Protection Section with appropriate training (2) Other Designated Personnel REPONSIBILITY: I Provide proper dosimetry and TLDs, as necessary, to ! EOF personnel, support personnel reporting to site ! assignment, and site personnel. Maintain dosimetry i issuance records. Perform habitability surveys of I the EOF. IMMEDIATE ACTIONS:
~ f 1. Report to EOF upon notification. Upon arrival, sign in on the EOF Staffing Board. '
2. Receive initial briefing from the Radiological Assessment Coordinator and establish responsible area. - 3. Obtain emergency dosimetry from EOF emergency locker in preparation for distribution.
- 4. Report readiness to the Radiological Assessment Coordinator.
*S. Maintain action log as required.
SUBSEQUENT ACTIONS: 6. Provide sosimetry and TLDs, as necessary, to the following: (1) EOF personnel. (2) Support personnel reporting for site assignment. (3) Site personnel.
*7. Maintain dosimetry issuance records. *
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Report need for additional dosimetry to the Radiological Assessment Coordinator.
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' SUBSEQUENT ACTIONS:
*9. As required perform habitability surveys of the EOF.
10. Submit any documentation and dosimetry issuance records to the Radiological Assessment Coordinator upon cancellation of emergency. (< s Y i
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EMERGENCY OPERATIONS REVISION 5 FACILITY ACTIVATION 5 Page 39 of 30 6 CLERICAL AIDE /STAWS BOARD KEEPER-EOF RESPONSE & STATUS BOARDS POSITION FILLED BY: (1) Designated person with appropriate training. RESPONSIBILITY: Maintain record of emergency actions taken by ANPP Emergency Organization on Status Boards. Record status of ' emergency. IMMEDIATE ACTIONS: ~
- 1. Report to EOF upon notification. Upon arrival, sign in on the EDF Staffing Board. .
- 2. Receive briefing from Administrative and Logistic Coordinator and
- - establish responsible area.
- 3. Rtport readiness to Administrative and Logistics Coordinator.
SUBSEQUENT ACTIONS: - Status Board
*4.
Record status of emergency as expressed by Technical Analysis Coorclinator or Radiological Assessment Coordinator. NOTE Ensure time recorded on status boards is ! event time rather than posting time. l Recovery 5. Submit any documentation to Administrative and Logistics Coordinator upon cancellation of emergency.
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[ROCEDURE IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 3 l EMERGENCY OPERATIONS REVISION h FACILITY ACTIVATION 5 Page 45 of 50 0FFSITE TECHNICAL REPRESENTATIVE RESPONSE & LOG POSITION FILLED BY: (1) Designated person from Nuclear Operations Licensing with appropriate training. , (2) Other Designated Personnel RESPONSIBILITY: Coordinate ANPP emergency response activities with federal / state / county agencies at the State EOC/ TOC. ) Provide up-to-date site information. Interpret substantiated data regarding PVNGS emergency status and conditions for emergency response agencies assigned to the State EOC/ TOC. IMMEDIATE ACTIONS: ' 1.
', Repert to Technical Operations Center (TOC) at State Emergency Operations Center (EOC), ADES Headquarte:s, 5636 East McDowell Road in Phoenix, upon notification.
2. Report presence to ARRA Director of Radiological Technical Operations.
- 3. Contact Technical Analysis Coordinator at EOF using dedicated voice circuit and receive initial briefing.
SUBSEQUENT ACTIONS: ANPP and State EOC/ TOC Coordination
*4 Maintain communications and coordinate actions betteeen ARRA Director of Radiological Technical Operations and ANPP Technical Analysis Coordir.ator at EOF using dedicated voice cirduit.
*S. Provide site information and interpret data at State TOC.
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*6. Maintain log as necessary.
Recoverv
- 7. Submit any documentation and log to Technical Analysis Coordinator at EOF upon cancellation of emergency.
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l OFFSITE TECHNICAL REPRESENTATIVE RESPONSE AND LOG u Time Person Cot.cacted Information Related 4 1. 2. 3. 4. s
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FACILITY ACTIVATION 5 Page 48 of 50 JENC 'ITCHNICAL ADVISOR RESPONSE POSITION FILLED BY: (1) Designated person from Nuclear Engineering I Department with appropriate training. (2) Other Designated Personnel - RESPONSIBILITY: Provide any necessary technical explanations and background to JENC Facility Manager. Review technical content of all media releases. IM'fEDIATE ACTIONS:
- 1. Upon notification report to Joint Emergency News Center (JENC) at 5636 E.
McDawell Rd., Phoenix. j
- 2. Report presence to JENC Facility Manager.
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- 3. Contact Technical Analysis Coordinator at EOF using dedicated voice
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circuit (or alternate) and receive initial briefing. SUBSEQUENT ACTIONS: - Public Information
*4. Maintain frequent communication with ECF contact and receive plant status updates.
*S. Provide technical explanations and background information to JENC Facility Manager, as recessary (and to media if required).
*6.
Review technical content of all media releases. Recovery
- 7. Submit check list to Technical Analysis Coordinator at EOF upon .
cancellation of emergency.
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' o IMPLEMENTING PROCEDURE EPIP-13 Page 1 of'1 REVISION /
EtiERGENCY OPERATIONS 3 FACILITY ACTIVATION ! Page 49 of 50 4 SECT'RITV FORCn MEMBER
~2SPONSE POSITION FILLED BY: Security Personnel RESPONSIBILITY: Restrict access to EOF. '
IM'IEDIATE ACTIONS: 1. Upon being relieved by the reporting Security Officer proceed to EOF and perform the following: (1) Lock EOF. door by stairway #2 (see Appendix Q) to restrict entrance to the (2) tian post inside the Annex Building basement air lock to restrict entrance into the EOF.
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. FACILITY ACTIVATION 5 Page 50 Of 50 EMERGENCY OPERATIONS FACILITY LAY 0tJI' J 5 5 E00 CFFICE E 4" EOF COMMAND CENTER NRC EOF OFFICE LisRARY mf CORADOR'
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, ,s PRCCEDGE CFANGE NOTICE (PCN1 70AC-0ZZO2 Rev. 9 .
?sge 29 of 35
, l Procecure No, hevisten: PCN No. lobtain from ODC only)l
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Title:
iODO Centact (ext. eo33) !
' l Release. Rde b4rnaalwn i 5y w_ l l Orignator: (Pr:n-: .1x:.
.ni:(s) affected: l l E mld S Simikke;> NkNI
l Reascn for this PCN: l l /r t-ldt1 i h ' M'GDens o$h5 MN credA&s r> 1
/ I dinne- elcw acwm#n m L A. b m s:
l V lExp; ration: l y matnefi t l Page nu=cer(s) affected iTo:al Nuncer of [ l by this PCN: i 6 !?sges at ached: f ? 1 I r l- Does PCN require a 30.59 review? X No ns (refer :o 3.1.2) l (/ I I ( l- Does PCN affect activities in l l the RCA? ><' No Yes (Copy :: ALA.U ) I l l l- Does PON effect the non-radiogical l
, I environment of any offsite area? )C No Yes (C ntsc: Compliance) l l
I l- Is PCN associated with an AC, l l Progrs=, E= erg. Plan or Secur. l l Prog., Phase I-IV Test, or a No KYes (PRS / PEG /TREG l l ST7 review required) l l 1 l ^ - l . I
/ / '
l l l inf _ TECHNICAL REVIEkER (Supervisory Level Nv4 33:e l r ~ i l 24 -ev 94 noe . CO* UY-"Flil ~ l PRS //RU/TERG Chg,.AN (if requtreet /' la te 8 i t / % Y$O $ l l FI APPROVAL /
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- EFFECTIVE DATE (DDC only) Assigned Copy .Nummer (DDC only) v
CONTROLLED BY USER i m
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PALO VERDE NUCLEAR GENERATING STATION PROCEDURE CHANGE NOTICE PAGE l of / INTENT CHANGE: NO E hx -
-. TES [
- 1. PROCEDUKE TITLE kg/wsp 8aI* O Mfmin t>?
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- 2. PROCEDURE NUMBER EP/# /V4 REV. T6 PCN V 2a. Manager concurrence to exceed 5 PCNs IV DATE
- 3. REASON POR PCN:
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'5. APPECTED STEPS:
, CHANGE REQUIRED: - ;
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ENTERfD'IN FROCEDURE BY: AJ/Q.Lk SICliATURE Abr/m : DATE SIGNATURE DATII
- 7. TDiPORARY APPROVAL: .
. SIGNATURE DATE SS/ Assist. SS ~ DATI B. DEP . HANAGEjt:
' 9. P RC:
SIGNATURE m 14. N o< y 2 bm DhTO m SIGNATURE / DAT[
- 10. APPROVED BY:
' 9 f /,
DtPaninb(T :tANActR,'S S!quATUnt / / ., Dr.Tr i
t t . CONTROLLED BY USER . PALO VERDE MUCLEAR GENERATING STATION PROCEDURE CHANGE NOTICE PACE / of / INTENT CHANCE: NO O O
'fES
- 1. PRCCEDURE TITI.E /P e / e,4 5 v. 67A
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- 2. PROCEOURE NUMBER Aj/p a / 4/g REV. $ PC:! d1 2a. Manager concurrence M/A DATE ~
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- 3. REASC:8 TCR PCN: i~n pi?srtissi e A ,,,s rs.ss ,-_.i. nei, se r=
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s.- ro.- w -ri.,s _ ,i:, r ., < r ._ s ,, i,n e ,.,,,s,,..., . as- i,,, o s , s . .
- 4. EXP 3ATIC:I: Af e x y- A. e t/j < , ,, ,/
l 5. AFFICTED STEPS: - CHANCE REQUIRED:
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ENTERED IN PROCEDURE BY:. Of J4 ,
/2 -j 3. q q-MNATURE [ DATE SICNATURE DATE
- 7. TDIPORARY APPROVAL: -
J/. SkC::ATURE DATE 'SS/ Assist. SS DATE
, 8. DE 6. MANAGER:
- 9. P B/ :)C/TRRC:
_A u sm$e01.$% N$ /S W '
///yf/ /,// /klg 10..\ P V. BY;
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DEPART:4dMY !!ANACCR',5 SOC;;ATURC # - 11.DATE EFFECTIyg: ODWeb DATE - z . .!
. _.m. * * * * ' -
. CONTROLLED BY USER PALO VERDE NUCLEAR GENERATING STATION ' PROCEDURE CHANGE NOTICE PACE / of /
INTENT CHANGE: NO @ YES O
- 1. PROCEDURE TITLE //f sr / err ,
PF/40r/h##n'
- 2. PROCEDURE NUMBER M / * / 9 ,
REV. [o PC:* / 2a. Manager concurrence
' /V/d2 DATE to exceed 5 PCNs '
- 3. REASON FOR PCN: ),3 dA;t'L W r ansd /d kr { so /?'F6 -
1 Er.-v rr cmmas,ed "
- 4. EXPIRATION: /v/77 (pf/eJ-M>v l
- 5. AFFECTED STEPS: l
, CHANGE REQUIRED fr7e e d sE 7 h/. h E f77 /w dY 0 *
/7 / A,,s l~ w
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- 6. P ARED BY:
nA'N SIGNATURE' x4e/r ENTERED IN PROCEDURE BY: [DATE SICNATURE DATE
- 7. TDIPO Y APPROVAL:
SI ATURE DATE SS/ Assist. SS DATE
- 8. DE ,
MNAGER:
- 9. RB PRC/TRRC:
b 4AO$. v'2.- !YI $ r l r'///]h/[f /$ l r 10 '. BY: 6 /[M[ 6 DC '. sTiltdkT BAN /bR'S SIGNATURE ' # DATE II.DATE ErrCCTIV - Olt /d/f'8 I-
CONTROLLED BY USER f PVNGS EMERGENCY PLAN [ROCEDURE , IMPLEMENTING PROCEDURE EPIP-14A REVISION RELEASE RATE DETER.4INATION 6 Page 1 of 23 4 Q' L'3 SIGNED COPY
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' NO.
IMPLEMENT!NG PROCEDURE EPIP-14A REVISION REIIASE RATE DETERMINATION 6 Page 2 of 23 RSVISION HISTORY Rev. No. DateN h ' Revised Pages Comments Ok.to *%S 5 2 ; - 6 4 - 4, 8, 15 Revised SLM Correction Factor Calculational Method. 6 3,9,10,19 23 Incornorated new Bechtel calculations for isolated containment and external 7 monitors.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN o [ROCEDURE . IMPLEMENTING PROCEDURE EPIP-14A' REVISION RELEASE RATE DETERMINATION 6 Page 3 of 23 TABLE OF CONTENTS SECTION PAGE NL53ER l 1 0,. OBJECTIVE 4
~
2.0 REFERENCES
. 4 3.0 LIMITATIONS AND PRECALTIONS 4 4.0 DETAILED PROCEDURE S
4.1 Personnel Indoctrination / Responsibilities S 4.2 Prerequisites S
, 4.3 Instructions
/ .
6 APPESTICES Appendix A - Release Rate Detemination From an Effluent 10
, Release Point Appendix B - Effective Age Correction Factors For the 12 Effluent Monitors '
t Appendix C - Noble Gas and Iodine Radiological Data 13
'Ap'pendix D - Release Rate Datermination from Main Stet: System
-17 i
^ Appendix E - Release Rate Determination from an Isolated Containment Using Design Basis Leak Rates - ) and Area Monitors or External Containment ) Radiation Monitors 17 l i
~
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PVNGS EMERGENCY PLAN Q camas , IMPLEMENTING PROCEDURE EPIP-14A REVISION RELEASE RATE DETERMINATEN 6 Page 4 of 23 1.0 OBJECTIVE s. This procedure permits determination of radioactive release rates (Sections design basis 4.3.1 and 4.3.2) or the projection of release rates using containment leak rates (Sections 4.3.3 and 4.3.4).
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-14B, " Initial Dose Assessment" 2.1.2 78AC-0ZZ06, " Document and Record Turnover Control" 2.1.3 74CH-9ZZ47, " Core Damtge Assessment"
- r. 2.2 Developmental References 2.2.1 PVNGS Emergency Plan, Rev. 5 2.2.2 FSAR, Chapter 11 " Process and Effluent Radiological Monitoring and Sa=pling Systems", Section 11.5, August 1981.
2.2.3 NUREG-0737, " Clarification of TMI Action Plan Requirements",
, October 1980.
2.2.4
, EPA-520/1-75-001, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," Rev. 6/80.
2.2.5 CE System 80 CESSAR, Standard PWR NSSS t
, g 2.2.6 Staam Tables; Table 1, ASME, 1967 2.2.7 ANPP:
Radiation Design Guide, SYS 80-PE-RG, Rev. 2 2.2.8
" Reactor Shielding Design Manual," T. Rockwell, III, editor.
D. Van Nostand, Princeton NJ . 2.2.9
" Radiological Health Handbook," US DNEV,1970, National Technical Information Service ,
_ 3.0 LIMITATIONS AND PRECAUTIONS 3.1 The accuracy of plant vent monitors is 125". and the accuracy of containment area monitors is t20*.. Therefore, release rate calculations may be limited to two significant figures. ma <sian
, _ , _ .,%,...e =
. CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEWRE IMPLEMENTING PROCEDURE EPIP-14A REVISION l RELEASE RATE DETERMINATION 6 Page 5 of 23 i
4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 Monitor readings and =enitor channel number should be
' obtained from the ce=munication console in the Control Room or the console in the Radiation Protection office.
4.1.2 " Effective age" refers to the time between core s'hutdown and ti=e of the release. Release rates will vary as a function of " effective age". 4.1.3 When selecting values from the appendices, data corre sponding to 1*. failed fuel shall be used unless plant conditiens indicate severe fuel cladding failure. When the effective age falls between two listed values, an effective age that yields the higher value shall be used:
\l; 4.1.4 The Radiation Protection Technician (affected unit) sh'all be responsible for the initial release rate deter =inations and off-site dose calculations (EPIPs-14A, 14B). g As, esse,eerh 4.1.5 The Radiological P::::ctia Cooydinator shall be responsible E for dose assess =ent when the %-is activated (EPIPs-14A, 4 14B,.14C).
4.1.6 If the CD.C'5 7:ter er IBM PC Dose Projection programp a $ to ( be used, proceed directly to the C-T.C Sy:::: C;:r 2* * -r } P W "-= m-
- h PVNGS Emergency Off-site Dose Calculation
- Computer Progres, App. [ of EPIP 14Kf-4.1.7 All release rate determination / projection docu=ents shall be '
processed in accordance with 78AC-0Z206, " Document and Record Turnover Control". These documents may be in the form of the t Data Tables in the appendices or co=puter printouts from 02.C5 cr- the IBM PC program. {
)
4.2 Prerequisites None
, l l
Pvt's 000A (Sist) - ' l - . - - , ..n... . n,.. ~. . ~ . . - -
CONTROLLED BY USER 7 PVNGS EMERGENCY PLAN CENRE [Ro , IMPLEMENTING FROCEDURE EPIP-14A
, REvislON REIIASE RATE DE*ERMINATICN 6 Page 6 of 23
\
4.3 Instructions g,
,p SOTE Use Settion.4.3.1 for actual releases through the Plant Vent, Fuel Building Vent Exhaust and/or Condenser Air Re= oval System. If the release is through the =ain steam lines only, proc.:ed to Section 4.3.2. If.it is desired to redict release rates from conte.inment, proceed . t Section 3.3. /
i ,/ 4.3.1 Deter Mation of Activity Release Rate From an Effluent
- Release \"oint (Accendix A) /
4.3.1.1 \ ./ Co=clety Sectica A of Appendix K, " Release Rate
- f. Determinkien From an Efflusnt/ Release Point" and obtain RMS data ay. monitor channel / number from RP office or
~ Control Room to determine .e monitor correction factor from Appendix .
4.3.1.2 From the Control . com determine which fans are operating and complete Secti ' B. If fan operating information is not available, assui:: that all fans are running. Total plant release raye is e sum of the individual pathway release rates. / 4.3.1.3 Co=plete Se ion C using th Total Noble Gas Release Rate from Sect' n B and the values listed in Appendix C. 4.3.1.4 / If a release is in progress via e main steam lines, g contin,ue with Section 4.3.2; if no perform offsite dose " projections in accordance with EPIP '43, " Initial Dose
~ A 'essment".
f .. e 7 .
- I g 3
_ , , , , , . _ , . , .. . - - - - - - *--" ~~ ir
CONTROLLED BY USER PVNGS EMERGENCY PLAN [a cewas , IMPLETAENTING PROCEDURE EPIP-14A REVISION 6*.
; REI. EASE RATE DETERMINATION 6 Page gaf 24 4.3 Instructions NOTE Use Section 4.3.1 for actual releases through the Plant Vent, Tual Building Vent Exhaust
, and/or Condenser Air Removal System. If the
' release is through the main steam lines only, - proceed to Section 4.3.2. If it is desired to predict release rates from containment, proceed to Section 4.3.3. 4.3.1 Deter =ination of Activite Release Rate Frem an Effluent
, Release Point (Accendix A) 4.3.1.1 Complete Section A of Appendix A, " Release Rate i
f Determination From an Effluent Release Point" and obtain su RMS data and monitor channel number from RP office or Control Room to determine the monitor correction factor frem Appendix 3. i T NOTE Since PASP monitors view the vent
,~a ,directly, the readings reflect Total 4,... Activity. Because credit is taken for
' Iodine volatility and vent filtration
.f!hr;. Noble Gas Activity is at least 96*. of the y
- .3 Total. For this reason it can be assumed
[w[,,~. 4 that PASP monitor indications can be y!
' , ,, converted to noble gas release rates ,
fr u
._j .
directly. q, ! i 4.3fl.2 ' Vent monitor flow rate indications should be used.
; f',%"'d.qh,: these are not available, determine which fans are If
,D:*';,: operating and complete Section B. If' fan operating
^b.h' 4 information is not available, assume that all fans are N. *
'
- running. Total plant release rate is the sum of the individual pathway release rates.
l 4.3.1.3 Complete Section C using the Total Noble G1s Release Rate l l 1 from Section 3 and the values listed in Appendix C. - l "4.3.1.4 If a release is ini progress via the main steam lines. continue with Section 4.3.2; if not, perform offsite dose
}.
projections in accordance with EPIP-14B, "Inirial Dose Assessment".
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IMPLEMENTING PROCEDURE EPIP-14A ! ~ REVISION I
- i RELEASE RATE DETERMINAT!ON 5 Page 7 of 23 Uff0h 4.3.2 Determination of Activity Release Rate Frem tha Main Steam l Lines (Accendix D)
NOTE
)
Due to the low effective energy, Main Steam Line Monitors will not detect a noble gas
, release under maximum design operating ,
parameters (1% Failed Fuel; FSAR Chapter 11). If Main Steam Line Monitor readings areabovenormaloperatingbackgroundfevels then severe core degradation should be
, ,sumed and the higher source termdalues of t gal core inventory should be used for release s rate and dose projection'
' calcu ations. Notify the Shift Supervisor
^ or Radi tion Proteccion Coordinator (if l present) 'mmediately.
(.i 4.3.2.1 Complete Secti A of A' ppendix D, " Release Rate Determination fr Main Steam System".
/
4.3.2.2 Enter the value of a higher reading monitor for the affected steam ge'nera or in Section B of Appendix D, a pg. 1. (Ex. /f only a steam generator is exhibiting pri=ary to secondary lea .ge, enter the higher value between the/A & B channel or this steam generator. If both stead generators exhib primary to secondary leaks l then the higher channel for b th RU-139 and RU-140 shall l be entered and the releases ad d together.) g j 4.3.2.3 MulEiply the higher monitor readin from RU-139 A or B
- l and/or RU-140 A or B by the Correct 1 n Factor shown below
/to obtain Steam Line Concentration.
cord in Section B l
/ both Correction Factor used and Steam L ne Concentration.
,/ .
/
/ '
[ O j . . 4
, MiGm itars ,
t= e e -e-me - - ~ + one eswe, m w a posg. ~ ww ww oeoo -
- m
CONTROLLED BY USER 1 PVNGS EMERGENCY PLAN QCEDURE eIi IMPLEMENTING PROCEDURE EPIP-14A - REVISION RELEASE RATE DETERMINATION 6 Page 7a of 23 1
^
4.3.2 Deter =inatien of Activity Release Rate From the 'tain Steam Lines (Accencix D) FOTE . ! If 3:th channels of either RU-139 or RU-110 are . inopereole, default values should be used for Main Steam Line Release Rates. The following values are based on the Steam Generator Tube Rupture Accident Analysis from CESSAR 15.6: .
, f
NOBLE GAS IODINES - Main Steae Safete Valve Release 2.39 C1/sec .31S Ci/sec i Atmoseheric Duro Valve Ooeration
, 1 0-2 Hours after shut-down 3.87E-2 Ci/sec 5.15E-3 Ci/sec 2-8 Hours after shut-down 2.77E-2 Ci/sec 3.692-3 Ci/see r '; 4.3.2.1. Complete Section A of Appendix D,
{} -
. Main Steam System'. " Release Rate Determination from
+
4.3.2.2 Enter the value of the higher reading monitor for the affected steam generator in Section 3 of Appendix D, pg. 1 (Ex. If only cue steam generator is exhibiting pri=ary to s,econdary leakage, enter the higher value between the A & 3 channel for this steam generator. If both steam generators exhibit primary to secondary leaks then the higher channel for both RU-139 and RU-140 shall be entered and the releases added together). 4.3.2.3 ~ Multiply the higher monitor reading from RU-139 A or 3 and/or RU-140
- A or B by the Correction Factor shown below to obtain Steam Line Con-centration. ,:
Line Ccncentration. Record in Section B both Correction Factor used and Steam 8
g I
Pflie occa ,a 33, ,,
--_. .,_.... - -- ~~ .
CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE EPIP-14A REVISION RELEASE RATE DETERMINATION Page 8 of 23
.1 6
.f . Monitor Correction Factors (4.3.2.3) Effective Monitor (br-pC1) Age (HR) Correction Factor ( mr-cc)
' 0 .078
.5 .089
" 1.0 .11 1.5 , .13 2.0 .17 2.5 .24 3.0 .28 3.5 .32 I i 4 .44' S 1.3 6 1.8 7 5.2 8 15.6 4.3.2.4 Record Noble Gas Concentration in mic:ocuries per cubic centimeter for each monitor used in Section B. NOTE Reactor Coolant System Temperature is used as steam temperature for steam density compensation. 4.3.2.5 Obtain from the Control Room the Reactor Coolant System 1 (RCS) temperature in degrees Fahrenheit and steam line flow rates in pounds per hour. Record flow. rates in Section B. 4.3.2.6 Using RCS temperature and page 3 of Appendix D, select the appropriate Conversion Factor and record in Section B. 4.3.2.7 Complete Section B by multiplying Noble Gas Concentration by Conversion Factor and Steam Flow Rate. 4.3.2.8 ComplebeSectionCusingTotalNobleGasReleaseRate from Section B and values listed in Appendix C (Total Core Inventory) for Total I/NG ratio and I-131/ Total I ratio for given effective age. 4.3.2.9 Add noble gas and I-131 release rates to those determined in Section 4.3.1, if applicable, and perform offsite dose projections in accordance with EPIP-14B. PY7H00A (8,82)
- e#
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CONTROLLED BY USER 1 A PVNGS EMERGENCY PLAN PROCEDURE l no. . l IMPLEMENTING PROCEDURE EPIP-14A REVISION RELEASE RATE DETERMINATION 6 Page 9 of 23 4 4.3.3 Release Rate Projections From an Isolated Contain=ent Using .; D,esign Basis Leak Rates and Area Monitors or External Containment Radiation Monitors (Accendix E) NOTE This section is to be performed using
- information from area monitors (RU-148 .
or RU-149) or external contain=ent -) monitors. Projections based on the use of these numbers should be verified as soon as possible utilizing field measurements and/or lab analysis. If the area monitors, RU-148 or RU-149, are inoperative proceed to Appendix E, section 2.0, use of external containment f radiation monitors. ( ~ 4.3.3.1 Complete Appendix E, page 1 using the instructions and tables in Appendix E. 3 4.3.3.2 Enter the Core Damage Estimate found in Section 1.2.13 of Appendix E in Section E of page 1 Appendix E.
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IMPLEMENTING PROCEDURE EPIP-14A Page 1 of 2 REVISION RELEASE RATE DETERMINATION 6 Page 10 of 23 O RELEASE RATE DETERMINATION FROM AN EFFLUEST RELEASE POINT h Section A: Release Data RX SHUTDCVN: Date Time EFFECTIVE AGE
~
REL START: te Time Section-B: Noble s Release Rate Determination l Part 1. Plant Vent (Aux & Racwaste Bldg,. Catst Refueling & Cntst Power Access Purge) HAN-J0la (30,000 cf=) A s HAN-J01B (30,000 cfm) \ ( HRN-J01A (25,500 cfm) ' Noble Gas HRN-J01B (25,500 cfm) Cone Conversion CPN-J01A (16,500 cfs) Noble Gas E ective ge (RU-143 or Constant Release CPN-J01B (16,500 cfs) Cor eti CPN-J02 ( 2,200 cfs) RU-144) (cc-Ci/cfm Rate
!. Facto App B) (pCi/cc) sec-pCi: (C1/sec)
TOTAL FLCW RATE (cfs) X X X 4.72E-04 = Part 2. Condenser Air Removal stem Vacuum Pump A (60 cfm) .' ble Gas Vacuum Pump B (60 cfm) / C c Vacuum Pump C (60 cfm) Conversion Noble Gas
/ Effective Age (RU 41 or Constant Vacuum Pump D (60 cfm) / Correction RU-14 Release j Steam Packing Exhaust (cc-Ci/cfm Rate Factor (App B) (pC1/c sec-yci) (C1/sec)
TOTAL FLOW RATE (cf X X X 4.72E-04 = Part 3. Fuel 11 ding Vent ' HFN-J01A (21 50 cfm) Noble Cas HFN-J01B (2 ,750 cfs) . Conc HFA-J01 6,000 cfs) Conver on Noble Gar Effective Age (RU-145 or Constant Release HFB-J01 (6,000 cfs) Correction RU-146) (cc-Ci/cf Rate
,. Factor (App B) (pC1/ce) sec-pC1) (Ci/sec).
TOT L FLOW RATE (cfs) X X X 4.72E-04 = , PV24000A stan , n*
. . -.n- , .. . ,.n., . - . --
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. l CONTROLLED BY USER
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App 2NDII g IMPLEMENTING PROCEDURE EPIP-laA Page 1 of 3 REVISION 10a. RELEASE RATE DETERMINATICN 6 Page J4 of 24 ~ l
- ,, RELEASE RATE DETERMINATION FROM AN EFFLUENT RELIASE POINT
-. Section A: Release Data idh RX SRUITCVN: Date Time EFFECTIVE AGE -5 .. REL START: Date Time Section B: Noble Gas Release Rate Determination Part 1. Plant Vent (Aux & Radwaste Bldg, Catst Refueling & Cntat Power Access i
-4
_, Purge) HAN-J0la (30,000 cis) _ HAN-J01B (30,000 cfs) (6)
" HRN-J01A (25,500 cfm) Noble Gas HRN-J01B (25,500 cfs) Cone Conversion Noble Gas CPN-JOIA (16,500 cfs) Effective Age (RU-143 or Constant CPN-J01B (16,500 cis) Release Cozkection RU-144) (cc-Ci/cfm Rate CPN-J02 ( 2,200 cfs) Factor (App B)(uCi/cc) sec-uC1) (CL/sec) .
TOTAL FLOW RATE (cfs) X X X 4.72E-04 =
, % ~. L
.. Monitor or Fan Total
", *. ; 6C '1 s+
' 9 ;C. **
; For PASP Monitors y Monitor- .
PASP Conversion Noble Gas % 3,-%gi,,. 7 Conversion Monitor constant Release ,, Q
.{' , Factor at Reading T/-;, Effective Rate g g R/hr -
C1/sec
. !' . .g. Age (app B) uCi/cc/R/hr r.
l i 'IVTAL FLOW RATE (cfs) X .X X 4.72E-4 =
% ,! 1 Part 2. Condenser Air Removal System i Vacuum Pu=p A (60 cim) .
Noble Gas l Vacuum Pump B (60 cim) Cone Conversion Noble Gas
'lacuum Pu=p C (60 cfd) Effective Age (RU-141 or Constant Vacuum Pu=p D (60 cim) Release ,
Correction RU-142) (cc-C1/cfm Rate Steam Packing Exhaust Factor (App B)(uC1/cc) sec-uci)
+
(C1/sec) TOTAL FLCV RATE (cfs) X X X 4.70E-04
). =
{ emaaoa is,en -
~*
3 . '
CONTROLLED BY USER Q PVNGS EMERGENCY PLAN PROCEDURE (. - NO. APPENDIX A IMPLEMENTING PROCEDURE EPIP-14A Page 2 of 3 REVISION RELEASE RATE DETERMINATION 6 Page of 24 RELEASE RATE DETERMINATION FROM AN EFFLUEST RELEASE POINT For ? ASP Monitors Monitor PASP Conversion Noble Gas Conversion Monitor constant Release
- c. .
Factor at Reading i %: r' Effective R/hr Rate Age (App B) Ci/sec ! uCi/cc/R/hr g g TOTAL FLOW RATE (cfm) X X X 4.72E-4 = Part 3. Fuel Building Vent HFN-J01A (21,750 cfm) Soble Gas KFN-J01B (21,750 efm) Cone RFA-J01 (6,000 cfm) Conversion Noble Gas Effective Age (RU-145 or Constant Release HFB-J01 (6,000 cfm) Correction
- RU-146) (cc-Ci/cfm Rate Factor (App B)(uC1/cc) sec-uci) (C1/sec)
TOTAL FLOW RATE (cfm) X X X 4.72E-04 = For PASP ;!onitors Monitor PASP Conversion Noble Gas Conversion Monitor constant Release
, -: :s 4, Factor at Reading Rate
- e. '4 Effective E.- R/hr .C1/sec 4 Age (App B) %
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APPENhII A IMPLEMENTING PROCEDURE EPIP-II.A Page 2 of 2 7, REVISION REI. EASE RATE DETERMINATION 6 Page 11 of 23 [ Q TOTAL EFFLUEhT NOBLE GAS RELEASE RATE (Ci/sec) = b Section C: I-131 Release Rate Determination Table Used: l[l 1*. iled Fuel l[l 1 Core Inver. tory Noble Gas tal Iodine Release- to Rate Nob Gas Total Iodine (Section B) Rat Volatile Release Raty (Ci/sec) (Appen C) Factor (Ci/sec)/ X X .25 = /
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o page yf of 2t* TOTAL EFFLUENT NOBI.E GAS RELEASE RATE (Ci/sec) = I Section C: I-131 Release Rata Deter:sination Table Csed: l_1 1*; Failed Fuel l[l Total Core Inventory Noble Gas Total *cdine Release to Rate Noble Gas Total Iodine 4 (Section 3) Rati: Release Rate (C1/sec) (Appendix C) h
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, 1 REVISION RELEASE RATE DETERMINATION 6 Page. 12 of 23 i
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- - APPENDIX C IMPLEMENTING PROCEDURE EPIP-1..A Page i of 1 REVISION 3 - RELEASE RATE.DETERMINAT!CN 6 Page 13 of 23 th.fl s
NOBLE GAS AND IODINE RADIOLCGICAL DATA
~ %Y 1",7 AILED FUEL , " TOTAL CORE IETNTORY
.-. Relative.._ Relative . . . . . Relative Re1 ive Release Rate Release Rata. ... . . . .. Release Rata.. . .R cr.se Rate Effective Ratios of -
Ratios of ' Ratios .of . .~ at ios o f
'ge (hr)- otal I/NG I-131/ Total I .
Total I/NG .I-131/ Tot I 0-l' *09 .23 1.5
.14
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1-10 .25 .35 1.5
.25 10-100 .. 16 .75 ~~~8 .75
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i REVISION 13 %
; RELEASE RATE DETER".INATION 6 Page Aso f 2/.
E NOBLE GAS AND IODINE RADIOLCGICAL DATA N0rt. The following ratios have taken credit for vent iodine filtration efficiency of 95* and i. the volatility coeffecient of 0.25. If iodine filtration efficiency has been impairec, c:ultiply the values celow oy a g factor of 20 before using chem in Section C )y for the effected vent only. This will A entail calculatinti Section C for~eacn vent independently and summing tne results to obtain the total iodine release races. (- l'; FAILED FUEL TOTAL CORE INVENTCRY N.i Relative Relative Relative Relative Release Rate Release Rate Release Rate Effactive Release Rate Ratios of Ratios $~of Ratios of Ratios of Age (hr) Total I/NG
- I-131/ Total I Total I/NG I-131/ Tot I -
0-1. 0.0150 .28 0.020 0.15
'g,' 1-10 0.0125 .35 0.020 0.30 >
y
,. 10-100 0.008 f" .75 0.017 0.89
< T *.
l.... >100 0.015 1.0 0.008 '. 0.99
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b) IMPLEMENTING PROCEDURE EPIP-14A APPENDIX D. Page 1 of 3
. REVISION RELEASE RATE DETERMINATION 6 Page 14 of 23 1
t RELEASE RATE EETERMINATION FROM MAIN STEAM SYST<.M
}-
Section A: Release Data h REACTOR SHUTDOWN: Date Time RELEASE START: Date Time ' n EFFECTIVE AGE: Section B: Noble Gas Release Rate Determination ,' 4
' NOTE: Enter N/A for non-affected steam generator.
Monitor Monitor Monitor Sream Line Number Reading Correction Factor Concentration (mr/hr) (VCi/cc) RU-139 X =
, (higher reading chetnnel, if applicable)
RU-140 X = (higher reading channel, if applicable) Noble Gas Steam Density Steam Noble Gas Concentration ' Conversion Factor Flow Release Rate (pCI/cc) (cc-Ci-hr/lb pCi-sec) (Ib/hr) (Ci/sec) RU-139 X X = b RU-140 X X __ = RU-139 Noble Gas RU-140 Noble Gas Total Noble ReleaseJtate
, Release Rate Gas Release Rate
+ =
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APPENDIX D IMPLEMENTING PROCEDURE EPIP-14A Page 2 of 3 REVISION g REI. EASE RATE DETERMINATICN 6 Page 15 of 23 t REI. EASE RATE DETERMINATION FROM MAIN STEAM SYSE M (CONT'D) Section C: I-131 Release Rate Determination (Use Total Core Inventory Ratios h in App, C) Noble Gas Total Iodine Release Rate to Noble Gas Volatility Total Iodine - (Section B) Ration Factor Release Rate (C1/sec) (Appendix C) (C1/sec) X X .01 = Total Iodine I-131/ total Iodine I-131 Release Rate Ratio Release Rate (C1/sec) (Appendix C) (C1/sec)
'% ., X = -
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j .' IMPLEMENTING PROCEDURE APPENDII D EPIP-14A Page 3 of 3 REVISION RELEASE RATE DETERMINATION 6 Page 16 of 23 3 Reactor Coolant Steam Density System / Steam Converstion Factor Temeerature(*F) fee-Ci-hr/lb- p Ci-sec) 200 2.65E-04 220 1.82E-04 240 1.28E-04 4 260 9.25E-05 . 280 6.81E-05 300 6.08E-05 320 3.86E-05 340 2.97E-05 360 2.33E-05 380 1.84E-05 400 1.47E-05 420 1.18E-05 440 9.58E-06
/r 460 7.81E606
480 6.42E-06
- 500 5.31E-06
, 520 4.39E-06
' 540 3.67E-06 560 3.06E-06 580 2.53E-06 600 2.10E-06
, 620 1.74E-06 640 1.42E-06 660 1.14E-06 680 8.75E-07 NOTE 4
- The Steam Density Conversion Factor compensates for
. steam density changes, converts 9C1 to CL, and
; converts flow rate to release rate.
This table was developed from hable 1 of the ASME Steam Tables using the specific volume (ft'/lb) of . saturated vapor at a givea temperature (*F). e
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APPENDIX E l IMPLEMENTING PROCEDURE EPIP-14A Page 1 of 7 REVISION REEEASE RATE DE'ERMINATICN 6 Page 17 of 23 RELIASE RATE PROJECTION FROM AN ISOLATED CONTAINMENT U3ING DESIGN BASIS f '.EAK RATES AND AREA MONITORS OR EXTERNAL COYTAINMENT RADIATION MONITORS Section A: Plant Data
, REACTOR SHLTDC'n'N: Date Time '
RELEASE START: Date Time EFFECTIVE AGE: RU-148 reading or: r/hr RU-149 reading or: r/hr Table 2 Correlation Table 2 Correlation Sectica B: Highest of RU-148 and RU-149 Readings (or Table 2 correlations) Highest of 7 Monitor
- Readings .
(Section A) (r/hr)
, Section C: Noble Gas Release Rate Projection based on area conitors Projected Noble Gas . Projected Projected Concentration Leak Rate Conversion Noble Gas (Table 1) (Tech Specs) Constant Release Rate (pci/cc) (cc/sec)
X (uci to C1) (C1/sec) g 8_. 5 2E+0 2 X 1E-06 = t Section D: 1-131 Release Race Projection based on area monitors Projected-Iodine Projected .
, Total Concentration Leak Rate Conversion Iodine (Table 1) (Tech Speca) Constant Release (uci/ce) (c:/sec) (uct to C1) Ratn X 8."2E+02 X 1E-06 =
Section Et Core Damage Estimate based en Table 1 (Section 1.2.13) 4 of fuel rods are damaged. l M44104 is an '
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- APPENDIX E IMPLEMENTING PROCEDURE EPIP-14A Page 2 of 7 REVISION REI. EASE RATE DETERMINATION 6 Page 18 of 23 Estimating Ccatainment Airborne Concentrations from Internal and External Containment Monitors 1.0 Containment Airborne Concentration Estimation Using RE-148. RE-149
1.1 Summary
The Nemograph in table 1 of this appendix relates the indicated dose rate at either high range in con:ainment area monitor to the airborne, concent rations of either noble gases or radioiodines in the containment. As the airborne concentration is related to the extent of core damage (given releases ,,, from the reactor coolant system) the nomograph also identifies core damage after taking decay into t consideration. 1.2 Instructions 1.2.1 Enter time, date, and name in' legend space on table 1., 1.2.2 This nomograph reqaires data from either high range
' in-containment monicor (RE-148 or RE-149). Obtain a reading from the higher reading monitor. If monitor data are not available or of questionablo validity, refer to Sect. 2.0, Correlation of External Containment Monitors to RE-148 or
, KE-149.
1.2.3 Entar monitor number and reading (R/hr) on table 1. 1.2.4 I,ocate the right hand vertical axis labeled Rem /hr. N 1.2.5 ' Make a mark on the axis at a point responding to the value of g the radiatien monitor reading. 9 d i 4
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,.s N O. APPENDIX E IMPLEMENTING PROCEDURE EPIP-14A Page 3 of 7' REVISION RELEASE RATE DETERMINATION 6 Page 19 of 23 4
1.2.6 Locate the portion of the horizontal axis labeled " Time After
. Shutdown." a 1.2.7 Mark the axis at the time corresponding to effective age of the mixture in containment.
1.2.8 Draw a vertical line through the time marked on the " Time After Shutdown" axis.
- 1.2.9 Draw a horizontal line from the mark on the Rem /hr atis to the left until it intersects the vertical line drawn in step 1.2.8.
1.2.10 Draw a curved line up and to the left parallel 1 Lng the curve for the monitor being used (RE-148 or RE-149) to where the line intersects the axis marked " Reference Rem /hr." Hark the point of intersection. (_ "; 1.2.11 Draw a horizontal line to the left from the mark on the
" Reference Rem /hr" axis through the " Core Damage" axes.
1.2.12 Identify the " Core Damage" axis that is the labeled for the monitor being used (RE-148 or RE-149). Mark that exis at the point that it is intersected by the line drawn in step 1.2.11. 1.2.13 Read the core damage estimate at the point marked in step 1.2.12. 1.2.14 Extend the vertical line drawn in step 1.2.8 until it intersects the curve corresponding to 100% core daaage for the detector used (RE-148 or RE-149). The 100% core damage curve is the uppermost curve. Mark the point of intersection. 1.2.15 Draw s horizontal line to the right from the point made in step 1.2.14 to the intersection of the " Rem /hr" axis and mark this point. 1.2.16 Locate the " Rem /hr" scale on the horizontal axis to the left of the core damage axes. Mark the point on the " Rem /hr" axis
, corresponding to the value from 1.2.15.
1.2.17 Draw a vertical line through this point intersecting all four curves above it. l m1 4 0m A tassa '
1 CONTROLLED BY USER 4 . i
- l. ,4 PVNGS EMERGENCY PLAN PROCEDURE NO-
'. APPENDIX E.
IMPLEMENTING PROCEDURE EPIP-14A Page 4 of 7 REVISION RELEASE RATE DETERMINATION 6 Page 20 of 23 1.2.18 Mark the intersection of the vertical line with the noble gas and iodine curves for the monitor being used (RE-148 or RE-149).
' 1.2.19 On the left side of the horizontal axis, locate the .
" Normalization Factor" portion. Mark the axis at the point corresponding to the core damage estimate read in step 1.2.13.
1.2.20 Draw a vertical line through the " Normalization Factor" axis at the value marked above. 1.2.21 Draw a horizontal line to the left from the point on the iodine curve marked in 1.2.18 until it intersects the vertical drawn in 1.2.20. Mark this intersection. 1.2.22 Draw a line down and to the left at a 45 degree angle from the intersection marked in 1.2.21 (this line will parallel the heavy diagonal lines already drwn on the nomograph) (, until it intersects the left vertical axis marked "pci/cc." Mark this point. 1.2.23 Read the value markea in 1.2.22 and record the value in Appendix E, as the iodine concentration. 1.2.24 Repest steps 1.2.21 through 1.2.23 for the noble gas curve. 2.0 Containment Airborne Concentration Estimation Using Area Monitors External to Containment. 2.1 This section is to be used when the containment high range monitors are not operable or the readings are suspect. , 2.1.1 The following external detectors may be used when the - In-containment high range monitors are inoperative or their readings are suspect. 2.1.1.1 RE-158 B&C Accident range external containment area monitors, they are ion chambers with a range of 0.1 to 10,000 Rfar. 2.1.1.2 RE-3f&RE-38 Power Access Purge Area (PAPA) monitors, they are GM tubes with a range of 0.1 to
; 10,000 mR/hr.
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PVNGS EMERGENCY PLAN PROCEDURE NO. Appgg Ig g IMPLEMENTING PROCEDURE EPIP-14A Page 5 of 7 <; REVISION REI.IASE RATE DETERMINATION 6 Page 21 of 23 2.1.1.3 Hand-held A portable instrument, held against the outside of containment on the 104' elevation
- by the tendon gallery. This instrument should have a range of 0.1 10,000 =R/hr.
Two instruments may be required to meet this range (e.g., an RO-2 and an R0-2A). 2.2 Instructions --
, 2.2.1 Obtain a reading from one of the above instruments (the t ; instrument selected should be taken in the order listed in 2.1.1).
2.2.2 On table 2, mark the instrument ruading on the horizontal axis labeled Dose Rate (Rem /hr). 2.2.3 Draw a vertical line up through this point until the line [N (,' intersects the curve of the detector used. Mark this intersection. 2.2.4 Draw a horizontal line from this point to the right until it intersects the curves for RE-148 & 149. Mark the points of intersection.
, 2.2.5 Draw a vertical line from these points down to the horizontal axis. Mark the intersections on the axis.
2.2.6 Transfer the higher reading from above to the data sheet and
' go to section 1.0 to determine the containment airborne concentration.
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~ [, PVNGS EMERGENCY PLAN Qcaouns , IMPLEMENTING PROCEDURE EPIP-14B ' REVISION $ INITIAL DOSE ASSESSMENT 4 Page 1 of 17 i 9 i O coc COPY. D. AUTHOR G. A. Simiele REVISED BY G. A. Simieleg ,
' EXT. 6661 TECH. REVItWER DATE b PRB/PRG/TRRG REVIEW W MnWU DATE b FINAL. APPROVAL 4/ Y M M H DATE I f .
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(/ EFFECTIVE DATE 6 (DCC f C!R 6nly) 6:_ ASSIGNED COPY NUMBER (DDC only)
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. EPIP-14B REVISION INITIAL DOSE ASSESSMENT 4 Page 2 of 17 REVISION HISTORY
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Rev. No. Date Revised Pages Comments u 3 04/09/85 3-10, Aep E 4 5,[T/R'/c All Deleted Computerized Dose Assessment Method t a F s e 4 e l e e ob
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; TABLE OF CONTENTS
- /
SECTION PAGE NUMBER
, 1.0 OBJECTIVE 4
}
2.0 REFERENCES
4 3.0 LIMITATIONS AND PRECALTIONS S 4.0 DETAILED PROCEDURE 5 .j 4.1 Personnel Indoctrination / Responsibilities 5
; 4.2 Prerequisites 5 4.3 Instructions 6 j $
APPENDICES i Appendix A - Calculation of Projected Whole Body and Thyroid 10 Doses Appendix B - Pluce Centerline Xu/Q Values (sec-mi/m3 -hr) 11 Appendix C - Radiological Data 13 Appendix D - Alternate Methods for Obtaining Meteorological 15 Data t e I i
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1.0 OBJECTIVE This procedure provides instruction to assess projected offsite J whole body and thyroid inhalation doses based upea ceteorological
^ data and noble gas /I-131 release rates. Dose calculations provide a basis for decision making concerning recommendation of appropriate protective action to s*. ate or county authorities.
2.0 REFERENCES
2.1 Implementing References [ 2.1.1 EPIP-14A, " Release Rate Determination" 2.1.2 9N219.05.00 " Document / Record Turnover Control" 2.1.3 70AC-0ZZ01, " Procedure Format, Content and Numbering"
.j 2.2 Developmental References 2.2.1 PVNGS Emergency Plan, Rev. 6
, 2.2.2 NRC Reg Guide 1.145, August 1979; " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants"
.i 2.2.3 NRC Reg Guide 1.111. July 1, 1977, Rev 1; " Methods for a
Istimating Atmospheric Transport and Dispersion of Gaseous Effluent in Routine Releases from Light-Water-Cooled Reactors" Introduction to Nuclear Engineering, John R. LaMarsh, Addison 2.2.4 5 Wesley Publishing Company, December 1977 2.2.5 Health Physics Journal, November 1981, Volume 41 No. 5, page 759 2.2.6 NRC Reg Guide 1.109 " Calculation o*f Anrual Doses to Man from Routine Releases of Reactor Effluents ;or the Purpose of . Evaluating Compliance with 10CFR50, Appendix I", October 1977 2.2.7 EPA " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" Appendix D, Revised June 1980
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PVNGS EMERGENCY PLAN Qcaoune IMPLEMENTING PROCEDURE EPIP-14B ' REVISION INITIAL DOSE ASSESSMENT 4 Page 5 of 17 I 2.2.8 Desert dispersion parameters as referenced in SUREG/CR-2858,
" PAVAN: An At=ospheric Dispersion Program for Evaluating Design Basis Accidental Releases cf Radioactive Materials from Nuclear Power Stations", November 1982 2.2.9 Meteorology and Atomic Energy, David A. Slade, Edicor, 1968 2.2.10 Journal of Apr. lied Meteorology, Volume 3, Pages 83-91, "A Diffusion Model for an Urban Area", D. B. Turner, 1964
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3 .0 LIMITATIONS AND PRECAt;TIONS 3.1 None 4 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities
- ) i 4.1.1 The Radiation Protection Monitor shall be responsible for j initial offsite dose projections.
4.1.2 The Radiological Assessment Coordinator (at the EOF) shall be responsible for dose projections when available. 4.1.3 One Calculation of Projected Doses, Appendix A, shall be completed for centerline site boundary, two, five and ten miles. 4.1.4 Upon event termination transmit Apperidix A to DDC for reter. tion in accordance with 9N219.05.00, " Document / Record Turnover Control". 4.2 Prerequisites 4.2.1 A release of airborne radioactive paterial has occurred or is imminent and its ate of release has been determined in accordance witt EPIP-14A, Release Rate Determination.
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INITIAL DOSE ASSESSMENT 4 Page 6 of 17 4.3 Manual Dose Calculations NOTE If actual airborne activity levels are known, either from field samples or RMS/ PASS sample analysis, these levels, vice moniter readings, aay be used to formulate prctective action
; recommendstions. !
4.3.1 Initiate Appendix A for each receptor site by recording J location, date/ time of reactor shutdown and date/ time of release. NOTE i If the ERFDADS is unavailable, dispatch a technician to the met tower er a to obtain
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weather data locally. Use default values (Appendix D) until ERFDADS data is available. 4.3.2 Complete Section A, Meteorology, using the fif teen mintite i average channel data on ERFDADS. Use the 35ft. elevation for - wind speed and direction and the 200ft.-35ft. temperatures for AT. 4.3.2.1 Using the delta T (*F) from above and the table below - enter the stability class in Section A, or use the default value from Appendix D. If default values are used, write DEFAULT in the section A header after Meteorology. STABILITY
& T ('F)
STABILITY (200 Foot Temo. - CLASSIFICATION CATEGORIES 35 Foot Temo.)
' Extremely unstable A , < - 1.7 Moderately unstable B -1.7 to -1.5 i
Slightly unstable C -1.5 to -1.4
- Neutral D -1.4 to -0.5 Slight,1y stable E -0.5 to 1.4 Moderately stable F 1.4 to 3.6
, Extremely stable G >3.6 t
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, 4.3.2.2 Using wind direction, find the affected sectors. The
- affected sectors are the sector with the plume center line passing through it and the sector to either side, a
except for sectors N, P, and Q. If the plume i centerline is through one of these sectors, (N, P or Q), then two sectorr tc. either side are affected.
' This is to account for additional dispersion by the i Palo VetJe Hills.
4.3.3 Selection of Key Receptar Sites. - NOTE The site boundary and points 2, 5 and 10 miles distant shall be key receptor sites. See Appendix B for a list of populatio/t centers by sector.
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, 4.3.3.1 Select the appropriate overlay that corresponds to the determined stability category and match the overlay with
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the release point on the map. 4.3.3.2 Rotate the overlay until the direct downwind plume - centerline is oriented in the direction of the compass heading of the wind. 4.3.4 Determine Effective Age and Plume Arrival Time at Rcceptor Site by completing Section B. NOTE For a WGDT rupture, assume 1*. ' failed fuel and that only a noble gas release is occurring with an effective age > 48 hrs. 4.3.4.1 Enter downwind distance at receptor site and divide by wind speed from Section A. Th,is gives the plume transit time to the receptor site.
.' ,i 4.3.4.2 Add the effective age of the reactor at time of release l to th9 transit time to get th-s effective age at the receptor site. {
4.3.4.3 Add the transit time to the time of release to find the plume arrival time. 4.3.5' Complete Section C, X/Q Determination, using appendix B, Plume Centerline Xu/Q Values.
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- REVISION
*q INITIAL DOSE ASSESSMENT 4 Page 8 cf 17 4.3.6 Complete Section D, Radioactivity Concentration at Receptor, using X/Q from Section C, noble gas release rate and iodine release rate.
4.3.7 Whole Body Dose Projection, Section E. 2 4.3.7.1 Enter noble gas concentration from section D and noble
- gas mean gamma decay energy (E,ff) from Appendix C (Use effective age at receptor site). .
4.3.7.2 Multiply noble gas concentration, effective energy and the dose rate conversion factor together to find the projected dose rate at the receptor site.
., NOTE " Protective Action Guides are based on , (:. . .h projected dose for two hours, therefore a two hour dose projection should be
.j (/ . determined. 4.3.7.3 Determine the expected duration of the release by requestin~g this information from the control room. If expected duration is less than two hours, use two hours as a minimum value.
.' 4.3.7.4 Multiply projected dose rate times the expected duration l
to find the projected dose for the plume passage. 4.3.8 Thyroid Dose Commitment, Section F 4.3.8.1 Enter the iodine concentration from section D and the release duration from Section E. 4.3.8.2 Using the column corresponding to the assumed core
' damage, find the summation of iodine dose conversion factor, Z yDCF, in Appendix C dhd enter this value in Section F.
- 4.3.8.3 Multiply iodine concentration by I DCF and record the 7
result as thyroid dose commitment per exposure hour. 4.3.8.4 Multiply dose commitment per hour of exposure times the release duration to obtain the adult thyroid 50 year dose _ commitment.
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4.3.9 Refer to EPIP-15 to for=ulate protective action reco==endations. 4.4 Updating Dose Projections 4.4.1 Update and refine dose calculations every hour and upon significant changes (as indicated below): - 4.4.1.1 Release rate change of 20 per cent; 4.4.1.2 Wind direction change of 25 degrees; 4 4.4.1.3 Wind speed change of 20 per cent; I 4.4.1.4 Change of stability class. e r i
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D Calculation of Wholo Body Doso Rate, Doso Commitment and Thyroid Dose Commitmont hg u 'U < z I"* 2 Receptor Site: s H mO Reactor Sliutdown Date: Time: Roloaso Dato: Timo; y g-, ITI (/) e j : Hugegroigav !!: (([ggg ivo Age anal Plasmo Arriva l limo I a 2N
- i. Wind Disection (deg.) o m
-i E ; Downwind Windspeed T rans i t Erf Agu & Erf Age O M "m 2 3
- 2. Wind Speed (mph) Distanco limo Roloase Receptor i
(mi.) (mph)
=
(Ber)
+
(hr) = (hr) 3- Qg
- 3. delta T (*F) / g Plumo Arrival Timo (hr) = ( t ra ns i t+ ro los so t imo )
M 22 oo l fa 73 . Stability class g<
- 5. Arlected sector l
l h
*U C. X/9 DutormTsihign b. Radiogglivi ty concentration at Receptor U i ["
" Xu/Q Windspeed X/Q Hulcaso lla to X/Q flecep to r Concen t ra t ion L
C I" pm(App. B) 3 3 3 3 22 P"'
, N(mi-suc/hr-a ) ( mpti) (sec/m ) (Ci/suc) (sec/m ) (Cl/m ) m g
/ = ,
I. iiG x = ll Os i2- i x - L m Wuolg flody Dojio_ffo_iect ion $
) E.
llecep to r E egg Doso Rate Projected Exposure Projected i 5 $ O"l '1 -i Noblo 043 , Conversion Doso Time Doso l 9 m Q Ita to l O m a j oncen t ra t ion factor 3
# 3 (HeV/ dis) -( Hem-d_{s-m ) ( flem/hr) (hr) (Rem) l Z y C 2 Q (Ci/m ) ( h r-HoV-C i ) M
+ (App. C) e- '"
2 1 i x x 8.90 x to = x = P
$ g l_ k _]hyroid 0050 Commitment ~
i l lleyroTd Doso sto lou se Adult Child l J J todino I DCf' Commitment Duration Thyroid thyroid l l Concentration 3 3 per Exposuro flour Doso Commitment Dosu Commitment I m m 3,, l (Ci/m ) (fice-m /hr-Cl) (Item /h r ) (he) (Rem) ( Httm ) g gy
*g i x = x = , xt = i l l 1 5 -
o k* Performud by 4> ' i C 4 i O
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'm IMPLEMENTING PROCEDURE EPIP-14B Page 1 of 2 REVISION INITIAL DOSE ASSESS >ENT 4 Page 11 of 17 PLUME CENTERLINE Xu/Q VALUES (mi-seeihr-= 1 Wind From: Dist A B C D E F G S (169-191) 0.82 8.9E-06 2.2E-05 4.3E-05 1.5E-04 2.9E-04 4.5E-04 6.9E-04 SSW (191-214) 0.83 8.7E-06 2.2E-05 4.0E-05 1.5E-04 2.8E-04 4.5E-04 6.9E-04 SV (2'4-236) 1.58 1.8E-06 4.9E-06 1.0E-05 5.6E-05 1.1E-04 2.0E-04 3.4E-05 WSW (236-259) 1.37 2.7E-06 6.9E-06 1.4E-05 6.9E-05 1.4E-04 2 -5 E-04 4.0E-04 V (259-281) 1.34 2.7E-06 7.4E-06 1.5E-05 7.2E-05 1.4E-04 2.5E-04 4.0E-04 WNW (281-304) 1.28 3.1E-06 8.1E-06 1.6E-05 7.6E-05 1.5E-04 2.7E-04 4.3E-04
' NW (304-326) 1.31 2.9E-06 7.6E-06 1.5E-05 7.4E-05 1.5E-04 2.5E-04 4.3E-04 NNW (326-349) 1.88 1.2E-06 3.4E-06 6.9E-06 4.3E-05 8.9E-05 1.6E-04 2.9E-04 N (349-C11) 1.68 1.6E-06 4.3E-06 8.9E-06 4.9E-05 1.0E-04 1.9E-04 3.1E-04 NNE (011-034) 1.14 4.0E-06 1.1E-05 2.1E-05 9.2E-05 1.8E-04 2.9E-04 4.9E-04 NE (034-056) 0.75 1.1E-05 2.9E-05 4.5E-05 1.8E-04 3.1E-04 4.9E-04 7.8E-04 ENE (056-079) 0.63 1.7E-05 4.3E-05 7.4E-05 2.2E-04 4.0E-04 6.3E-04 9.4E-04 E (079-101) 0.62 1.7E-05 4.5E-05 7.6E-05 2.5E-04 4.0E-04 6.3E-04 9.4E-04 ? ; ESE (101-124) 0.63 1.7E-05 4.3E-05 7.4E-05 2 2E-04 4.0E-04 6.3E-04 9.4E-04
/
SE (124-146) 0.74 1.2E-05 2.9E-05 5.1E-05 1.8E-04 3.1E-04 5.1E-04 7.8E-04 SSE (146-169) 0.83 8.7E-06 2.2E-05 4.0E-05 1.5E-04 2.8E-04 4.5E-04 6.9E-04 1.00 5.6E-06 1.5E-05 2.7E-05 1.1E-04 2.1E-04 3.6E-04 5.6E-04 2.00 1.0E-06 2.9E-06 6.3E-06 3.8E-05 8.3E-05 1.5E-04 2.7E-04 3.00 5.6E-07 1.1E-06 2.5E-06 2.0E-05 4.7E-05 9.2E-05 1.7E-04 4.00 4.3E-07 7.6E-07 1.2E-06 1.3E-05 3.1E-05 6.5E-05 1.3E-04 5.00 3.6E-07 6.3E-07 7.8E-07 9.2E-06 2.2E-05 4.9E-05 9.8E-05 6.00 2.9E-07 5.4E-07 6.7E-07 6.9E-06 1.8E-05 3.8E-05 8.1E-05 7.00 2.5E-07 4.7E-07 5.8E-07 5.4E-06 1.5E-05 3.1E-05 6.7E-05 8.00 2.2E-07 4.0E-07 5.1E-07 4.5E-06 1.2E-05 2.7E-05 6.0E-05 9.00 2.0E-07 3.6E-07 4.7E-07 3.6E-06 1.0E-05 2.5E-05 5.1E-05 j 10.00 1.8E-07 3.4E-07 4.3E-07 3.1E-06 8.9E-06 2.1E-05 4.7E-05 9 I 9 e.me
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REVIS;ON INITIAL DOSE.' ASSESSMENT 4 Page 12 of 17 Additional Centerline Xu/Q Values t'or Population Cen:ers by Sector: Dist A B C D E F G I I I I I I I Sector A: l l l l l l l l 1 1 I I I I The Red Quail l l l l l l l Store 2 Miles l1.0 E-6l2.9 E-6l6.3 E-6l3.8 E-5l8.3 E-5l115 E-4l2.7 E-4 I I I i 1 1 I Ruth Fisher l l .I [ [ [ l School 7 Miles 12.5 E-7l4.7 E-7l5.8 E-7l5.4 E-6l1.5 E-5l3.1 E-5l6.7 E-5 I I I I I I I Sector F: l l l l l l l 1 l l I I I I 8 Miles Hassayampa l 2.2 E-7 l4.0 E-7 l5.1 E-7 l4.5 E-6 l1.2 E-512.7 E-5 l 6.0 E-5 I I I I I I I Palo Verde l l l l l l l School 11 Miles
- # [1.7 E-7l3.1 E-7l4.0 E-7l2.7 E-6l7.8 E-6l1.9 E-5l4.3 E-5 1 I I I I i i Sector G
- l l l l l
' ' l l i i 1 I I I I Arlington 7 Miles l2.5 E-7l4.7 E-7l5.8 E-7l5.4 E-6l1.5 E-5l3.1 E-516.7 E-5 I I l l l l l Arlington l l l l l l l School 8 Miles l2.2 E-7l 4 E-7 l5.1 E-7l4.5 E-6l1.2 E-5l2.7 E-516.0 E-5 I I I I I I I Sector R: l l l l l l [
l i I l 1 I I Tonopah 8 Miles , l2.2 E-7l 4 E-7 l5.1 E-7l4.5'E-6l1.2 E-6l2.7 E-6l6.0 E-5 e e e e e
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- i. '- APPENDIX C t_ . - ' IMPLEMENTING PROCEDURE EPIP-14B Page 1 of 2 REVISION INITIAL DOSE ASSESSMENT 4 Page 13 of 17 4
NOBLE GAS MEAN GAM:1A DECAY ENERGY (E,gg) Effective 1*. Failed Total Core Age Fuel Inventerv (hours) (MeV) (MeV) 0.0 0.253 0.590 0.5 0.233 0.549 1.0 0.210 0.503 1.5 0.195 0.471 2.0 0.181 0.420 2.5 0.167 0.390 3.0 0.152 0.360 3.5 0.145 , 0.334 4.0 0.136 0.310 5.0 0.117 0.238
- . , 6.0 V., 0.104 0.223
-lj) 7.0 0.090 0.184 8.0 0.075 0.160 9.0 0.069 0.142 10.0 0.064 0.123 11.0 0.059 0.104 12.0 0.051 0.089 16.0 0.042 0.059 20.0 0.040 0.049 24.0 0.037 0.040 48.0 0.031 0.031
>48.0 0.030 0 0.030
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CONTROLLED BY USER. m PVNGS EMERGENCY PLAN PROCECURE NO. APPENDIX C i
. IMPLEMENTING PROCEDURE EPIP-14B Page 2 of'2 REVISION INITIAL DOSE ASSESSMENT 4 Page 14 of 17 Su=mation of Iodine Dose Conversion Factors vs. Effective Age for Adults u Effective 1% Failed Total Core Age Fuel Inventerv i (hours) 1 DCF 7
I yDCF (Rem-m'/hr-CJ) (Rem-m'/hr-C1) 0.0 6.85 x 10' 3.07 x 10' O.5 7.06 x 10' 3.53 x 10' 1.0 7.27 x 105 3.81 x 10' 1.5 7.59 x 10' 4.16 x 10' 2.0 7.75 x 10' 4.46 x 10' 2.5 7.96 x 10' - 4.67 x 10 5 3.0 8.17 x 10' 5.10 x 10' 3.5 8.29 x 105 5.33 x 105
~. 4.0 8.50 x 10' 5.37 x 10' , ' Qj 5.0 8.60 x 105 5.88 x 10' 6.0 9.04 x 10' 5.99 x 10' 7.0 9.16 x 10' 6.45 x 10' 8.0 9.39 x 10' 6.65 x 10' 9.0 9.66 x 10' 6.81 x 10 5 10.0 9.80 x 105 7.19 x 10' 11.0 1.00 x 10 8 7.47 x 10' 12.0 1.02 x~10 8 7.60 x 10' 16.0 1.09 x 10' 8.32 x 10' 20.0 1.17 x 10' 9.37 x 10' 24.0 1.21 x 108 -
9.60 x 10' 48.0 1.46 x 10' 1.26 x 10' 72.0 1.60 x 108 1.50 x 10' 96.0 1.68 x 108 1.62 x 10' ' 120.0 1.73 x 10' 1.69 x 10' - 144.0 1.77 x 10' 1.77 x 10' 9 e _1
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. 4, NO. APPENDIX D 1
( IMPLEMENTING PROCEDURE EPIP-14B Page 1 of 3 REV:QON INITIAL DOSE ASSESSMENT 4 Page 15 of 17 I I. Introduction
'This appendix is used as .an alternate method for determining meteorological conditions in the site environs when the ERFDADS/ Meteorological Tower is inoperative.
Immediately on determination that co=munications with ERFDADS has been lost or that the met tower is inoperative a technician should be dispatched to the met tower area to obtain weather data locally. The dose projection process .should not be held up while waiting for the technician to report. However, the technician should report tho wind direction before the affected sectors are determined. The default salue for affected sectors should not be used unless there is no indication of wind direction available. The following is a listing of the backup methods and a brief description of when to use each one. .( ,
- 1. Default Values - used for initial does projection when the
'; V ERFDADS/ Meteorological Tower is unavailable. These values are extremely conservative an1 should be replaced with real data as soon as possible.
. 2. Local Readings from the main meteorological tower - en a loss of communications via ERFDADS during a release or with a release imminent, a technician should be dispatched to the meteorological tower and readings relayed from the local instruments. Dose projections should no_t be held up while waiting for this data.
Default conditions should be used until the local station is manned. The following sectionr are divided into two parts. Part A is a description of the method and Part B is the operating instructions,for that method. II. Default Assumptions and Values A. Assumptions The use of default values requires that estimates be made conservative enough to ensure proper protective action recocmendations are made to protect the general public. The assumed meteorological conditions must be such that they will yield the most restrictive plume dipersal factors for the ten mile EPZ.
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( APPENDIX D
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IMPLEMENTING PROCEDURE EPIP-14B Page 2 of ~3 REVISION INITIAL DOSE ASSESSMENT 4 Page 16 of 17 3ecause accurate determination of wind direction cannot be made, then a conservative assumption must be used regarding site boandary distance and affected sectors. The most restrictive site boundary from an emergency classification standpoint is the west boundary along Wintersburg Road. This boundary is affected when the wind is from the east. Therefore, when choosing the Xu/Q value for site boundary, use the value listed for wind from ninety degrees. For affected sectors, have the technician at the met tower-visually check the wind vane on the met tower at th.a thirty-five foot . elevation. If the technician is unable to make an estimation of wind direction based on observation of the wind vanes at the met tower, then all sectors should be considered affected. Vind speed presents a problem in that a Icw wind speed will give a conservative estimate of X/Q, but results in less conservative values for transit time / effective age at the receptor. High assumed wind
, speeds result in errors in the X/Q, while being conservative in
- i transit time and effective age. To compensate for this it is
- ~ /
necessary to assume two wind speeds, a low wind speed for X/Q determination and a high wind speed for plume transport. t For atmospheric dispersion factor (X/Q) selection, the class selected must allow for the least dispersion during transport. The stability category that allows for the least dispersion is a condition of extreme stability, Class G. B. Instructions
- 1. The following parameters should be used for default values for projecting off-site doses:
1.1 Wind direction - 90 degrees
, 1.2 Wind speed - for X/Q determination, use 1 mph
- for transit time,,use 10 mph 1.3 Stability class - G =
1.4 For affected sectors and protective action recombendations, use indicated wind direction, if available, or default to all sectors if no direction obtainable. N/ l ~~ CONTROLLED BY USER .- ' ,.. . _., .... ... _ .- %..-e.- . aw,p..=w.ar-- --~===r=== = - ' - - ' * - - " * * * ' " * - * ' ' - ' "
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III. Local Readout at the Metecrological Tower r A. Discussion , This section is to be used when communications from the met tower to the ERFDADS are not available. Initial dose projections should not be held up while waiting to use this section, default values are to be used until a technician gets to the met tower. When the technican arrives at the met tcwer, he must deter =ine that the met tower is operable. If the met tower is not operable report this to the EOF /STSC. B. Instructions 1.0 Send a technician to the met tower. 1.1 The key for the met tower may be obtained from shift 7 f-. security personnel or the RP Office. 2.0 At the met tower. 2.1 Establish communcations with the EOF (if manned) or the , STSC. 2.2 Verify operability of the met tower. 2.2.1 If the tower is inoperative, report this to the EOF or STSC. 2.2.2 If the tower is operable,' proceed to step 2.3. 2.3 Obtain the following data and transmit it to the EOF,or STSC.
. NOTE Use fifteen minute averages for data points. =
2.3.1 , Wind direction in degrees at the thirty-five foot ' elevation. 2.3.2 . Wind speed in mi?es per hour at the chirty-five foot elevation.
.; 2.3.3 Delta T in degrees Fahrenheit (200 ft. - 35 ft.).
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PVNGS EMERGENCY PLAN [ROCEDURE x., . IMPLEMENTING PROCEDURE EPIP-14C
- REVISION CONTINUING DOSE ASSESSMENT 2 Page 1 of 30 AUTHOR Tom Barsuk '
REVISED BY Jerry Simiele- EXT. 66(c/ TECH. REVIEWER DATE 'M Y'I ' PRB/PRG/TRRG REVIEW AWWW N
- FINAL APPROVAL /t 884fDATE d y -
f T T! T /t.
.. , EFFECTIVE DATE (DDC orily) ASSIGNED COPY NUMBER (DDC nly)
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(. IMPLEMENTING PROCEDURE EPIP-14C , REVISION CONTINUING DOSE ASSESSMENT 2 Page 2 of 30 2 REVISION HISTORY
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Rev. No. Date Revised Pages Coments 1 Total Rewrite 2 f[f/Ff All Deleted Manual Method e 4 4 e G . l l 9 l v . D
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REVISION CONTINUING DOSE ASSESSMEST 2 Page 3 of 30 TABLE OF CONTENTS SECTION PAGE NUfBER 1.0 OBJECTIVE 4
2.0 REFERENCES
4 3.0 LIMITATIONS AND PRECALTIONS 5 4.0 DETAILED PROCEDURE 6 4.1 Personnel Indoctrination / Responsibilities 6 4.2 Prerequisites 6 4.3 Instructions 6 APPENDICES , Appendix A - Data Sheets for Dose Assessment Comparisens 12 A-1 Whole Body Dose Rate Comparisen 12 A-2 Thyroid Dose Commitment Comparison 13 A-3 Particulate Ground Deposition Comparison 14 Appendix B - Radiological Data Table B-1 Summation of Iodine Dose Conversion Factors vs Effective Age and Total Iodine to I-131 Dose Ratios for Adult Thyroid 15 Appendix C - PVNGS Emergency Off-Site Dose Projection Computer. Program Instructions 16 AphendixD-AlternateMethodsforObtainingMeteorological Data ' 29 e
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CONTROLLED BY USER 3 PVNGS EMERGENCY PLAN pcswas IMPLEMENTING PROCEDURE EPIP-14C ' t REVISION CONTINUING DOSE ASSESSMENT 2 Page 4 of 30 1.0 OBJECTIVE This procedure provides instructions and calculations necessary to determine actual or projected offsite whole body gn=ma and thyroid inhalation dose co=mitments based upon actual meteorological data and noble gas and I-131 release rates (Ci/sec). Actual or projected dose calculations provide a basis for decision maki:g, ; conce.ning recommendations of appropriate protective actions to i state or county authorities.
2.0 REFERENCES
s 2.1 Implementing References , 2.1.1 EPIP-14A, " Release Rate Determination" 2.1.2 EPIP-14B, " Initial Dose Assessment" ( 2.1.3 EPIP-15. " Protective Action Guidelines" 2.1.4 EPIP-16, "Inplant Surveys and Sampling" 2.1.5 EPIP-17, "Onsite/Offsite Surveys and Sampling" 2.1.6 The CRAC System User's Manual 2.1.7 EPIP-33, "Offsite Assistance" 2.2 Developmental References 2.2.1 PVNGS Emergency Plan, Rev. 6. 2.2.2 NRC Reg Guide 1.145, Augast 1979; " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants". 2.2.3 NRC Reg Guide 1.111, July 1,1977, Rev 1; " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous
- Effluent in Routine Releases from Light-Water-Cooled Reactors" 2.2.4 Introduction to Nuclear Engineering, John R. LaMarsh, Addison.
Wesley Publishing Company, December 1977. ! CONTROLLED BY USER .
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IMPLEMENTING PROCEDURE EFIP-14C REVISION T CONTINUING DOSE ASSESSMENT 2 Page 5 of 30
- 2. 2 . .i Health 759, Physics Jovenal, November 1981, Volume 41 N'o. 5, page 2.2.6 NRC Reg Guide 1.109 " Calculation of Annual Doses to Man from Routine Releases of Reactor Efflu2nts for the Purpose of Evaluating Compliance with 10CFR50, Appendix ,I", October 1977.
2.2.7 EPA " Manual of Protective Action Guides and Protective Acticas for Nuclear Incidents" Appendix D Revised June 1980. 2.2.8 Desert dispezr(on parameters as referenced in S M G/CR-2858,
" PAVAN: An Atmospheric Dispersion Program for Evaluating Design Easis Accidental Releases of Radioactive Materials
, from Nuclear Power Stations", Nov. 82.
2.2.9 Meteorology and Atomic Energy, David A. Slade, Editor, 1968. 2.2.10 Journal of Applied Meteorology, Volume 3, p 83-91, "A Diffusion Model for an Urban Area", D. B. Turner,1964. 2.2.11 ANSI N45.2.9 " Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants, 1974. - 2.2.12 Safety Guide 23 "Onsite Meteorological Programs", USAEC, 2/17/72. 2.2.13 Handbook of Environmental Radiation, Alfred k'. Klement, ed., CRC Press Inc., 1978. 3.0 LIMITATIONS AND PRECAtTTIONS 3.1 Release rate determinations shall be conducted in accordance with EPIP-14A, " Release Rate Determination: - 3.2 Actual dose rates and integrated doses vary as a function of:
- 1) The duration of the release; *
- 2) The release rates (dependent upon effective age);
- 3) The isotopic mixture of the release (dependent upon effective age);
- 4) Existing meteorological conditions.
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CONTROLLED BY USER m PVNGS EMERGENCY PLAN [fcecune IMPLEMENTING PROCEDURE EPIP-14C REVISION CONTINUING DOSE ASSESSMENT 2 Page 6 of 30 t 4.0 DETAILED PROCEDURE [ 4.1 Personnel Indoctrination / Responsibilities 4.1.1 The Radiation Protection Monitor shall be responsible for initial offsite dose calculations and/or projections at per EPIP-14B, " Initial Dose Assessment". 4.1.2 The Radiological Assessment Coordinator (at the EOF) shall be responsible for dose calculaticas and/or projections when the 4 EOF beco=es operational. 4.2 Prerequisites 4.2.1 An AIIRT or more severe class emergency has been declared.
. 4.2.2 A release of airborne radioactive =aterial has :-eurred or is ic:=inent.
. 'S' 4.3 Instructions for Computer Assisted Dose Assessment
.s 4.3.1 Calculate doses and dose rates using the PVNGS Emergency Offsite Dose Projection cooputer program and the IBM PC
, computer, following the instructions included in Appendix C. If the progras or the computer is not available, carry out the manual procedure described in EPIP-14B, " Initial Dose Assessment". Upon completion of dose calculations (whether manual or co=puter-assisted), proceed with section 4.4. 4.3.2 If the ERFDADS is unavailable, dispatch a technician to the met tower area to obtain weather data locally. Use default values (Appendix D) until ERFDADS data is available. Additional meteorological information may be obtained from the National Weather Service per EPIP-33, "Offsite Assistance." . 4.4 Estimation of Off-site Doses and Ground Contamination Based on Field Measurements. e e e me CONTROLLED BY USER e
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IMPLEMENTING PROCEDURE l _ EPIP-14C REVISION CONTINUING DOSE ASSESSMENT 2 Page 7 of 30 ; I NOTE i Off-site samples may be analyzed in the Radiological Emergency Response Vehicle and/or the on-site chemistry lab and the data
- transmitted to the STSC/ EOF for incorporation into off-site dose calculations. This data should then be compared with projected doses and concentration.
4.4.1 Calculation and comparison of whole body dose based on field surveys. 4.4.1.1 Sample teams shall report gross mR/hr at 3' and 3", the ; sample location and sample time. Enter the data in columns 1, 2 and 3 of Appendix A, table A-1. 4.4.1.2 Determine an equivalent dose rate for the time and location. Enter this value in colu=n 4 of table A-1.
.,,, 4.4.1.3 Divide column 4 by column 3 and record the result in column 5 as the ratio of calculated whole body dose rate to measured whole body dose rate.
4.4.2 Calculation and comparison of thyroid dose co=mitments based on field measurements. , NOTE Protective Action Recommendations for thyroid doses are based on the child thyroid dose commitment. Multiply the adult thyroid dose ce=mitment by 2.0 to obtain the child thyroid dose co=mitment. 4.4.2.1 Sample teams shall report iodine sample data in terms of sample location, time, net count rate, duration, flow rate, instrument efficiency and type of instrument used. o
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IMPLEMENTING PROCEDURE EPIP-14C REVISION CONTINUING DOSE ASSESSMENT 2 Page 8 of 30 3 NOTE ', Type of instrument is required only to determine whether the results are gross iodine concentration or I-131 concentration (the SAM-2 counts only I-131, while a frisker counts gross iodine.) 4.4.2.2 Enterthedataintheappropriatecolu=r$ofAppendixA,
., table A-2.
4.4.2.3 Calculate the airborne concentration of iodine using the following formula: ,
,' activity = Net CPM x 1.59 E-11 uCi-f t!/ dom-ce V, x T, x E x 0.9
- j. Where:
v activity = either gross iodine or I-131 activity. ' Net CPM = net iodine count rate. V, = sample flow rate in efm. T, = sample count time in minutes. E = instrument counting efficiency in cpm /dpm. 4.4.2.4 Enter the iodine concentration in column 7 of table A-2. 4.4.2.5 1 Calculate the iodine dose commitment using the following l formulae: . : i for gross iodine activity: D = activity x I DCF 7 for I-131 activity: D = activity x I-131 DCF x total
- I/I-131 a
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IMPLEMENTING PROCEDURE EPIP-14C REVISION C0hTINUING DOSE ASSESSMENT 2 Pcge 9 of 30 Where: D = Adult thyroid dose commitment in rem per hour of exposure to the iodine concentration. activity = iodine concentration in uCi/ce, either total fodine or I-131. 1 DCT = Summation of iodine dose correction factors, 7 found in Appendix B, table B-1. I-131 DCF = I-131 dose factor x breathing rate = 1.77E + 06 Total I/I-131
=
ratio to convert I-131 dose co=mitment to total
' iodine dose commitment. Found in Appendix B, table B-1. Used caly when iodine filter is counted on a SAM-2.
4.4.2.5 Enter the Adult thyroid commitment calculated above in column 8 of Appendix A, table A-2. 4.4.2.6 Calculate an equivalent Adult thyroid dose for the same time and location using the procedure in Appendix C and enter this value in column 9 of table A-2. 4.4.2.7 Divide colu=n 9 by column 8 and enter the ratio in column 10. 4.4.3 Sample teams will report particulate concentrations in terms of location, time net count rate, sample duration, flow rate of sampler, and counting efficiency of counter. Enter this data in the appropriate columns of Appendix A, table A-3. e I sv
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,..w 4.4.3.1 Calculate particulate activity using the following '
forcula: Activity = Net com x 1.59 E-11 uCi-ft !dem-ce
/
V, x t, x E c kcare: Activity = particulate activity in uCi/cc. Net cpm = Net particulate count rate. V, = sample flow rate in efm. l t, = sample count time in minutes. E c
=
instrument c unting efficiency in cpm /dpm. 4.4.3.2 Enter the particulate activity in column 7 of table A-3. u 4.4.4 Calculate the projected ground deposition (surface contamination) using the following formula: C(Ci/m') = Activity Conc. (uCi/cc) x Vd (m/sec) x td (****) k'here : 1 C = 8 Surface contamination (Ci/m ). Activity Conc. = Particulate or iodine ccacentration. V e d Deposition velocity = .01 m/see for iodine and .03 m/sec for particulates, ed = duratien of the release in seconds Enter the projected particulate or iodine contamination level in table A-3. e I
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CONTROLLED BY USER A PVNGS EMERGENCY PLAN PROCEDURE NO. _ IMPLEMENTING PROCEDURE EPIP-14C REVISION C0hTINUING DOSE ASSESSMENT 2 Page 11 of 30 4.5 Comparison of projected values to field measurements. CALTION s AST ADJUSTMENT TO TE SOURCE TERM BASED ON THE FOLLOWING COMPARISONS SHOULD BE DONE ONLY AFTER CAREFUL SCRUTIST OF APPENDIN A, TABLE A-1 AND A-2. CHECK TE LOCATION OF TE MEASURED FIELD - DATA IN RELATION TO THE PLOITED PLUME. 4.5.1 Check the ratios in column 3 of table A-1 and column 10 of table A-2. 4 . 5 .1.1. If the values are consistently less than 1.0, this indicates that field measure ents are greater than hp projected. Check that proper source term assumptions were made and that an unmonitored release is not occurring. If, at the discretion of the Radiological Assessment Coordinator (RAC), it is decided to adjust the source term; divide the calculated value by the average value of the ratio in column 5 of table A-1 for noble gas whole body dose or colu=n 10 of table A-2 for thyroid dose commitment. 4.5.1.2 If values in column 5 of table A-1 or column 10 of table A-2 are consistently greater than 1.0, then field measurements are less than calculated values. If, at the discretion of the Radiological Assest. ment Coordinator (RAC), it is decided to adjust the source term after calculation, then divide the calculated value by the average value of the ratio in column 5 of table A-1 for r.oble gas or column 10 of table A-2 for thyroid dose commitment. 4.5.1.3 Similar co=parisons should be made between grab samples and release data.
- 4.6 Compare commitments calculated here with the Protective Action Guidelines listed in EPIP 15, " Protective Action Guidelines" to make offsite protective action reco=mendations to the State.
4.7 Continue dose projections and field measurements as directed by the Radiological Assessment Coordinator.
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CONTROLLED BY USER m PVNGS EMERGENCY PLAN Qcaouas gppgg g IMPLEMENTING PROCEDURE EPIP-14C Page 1 of '3 REVISION CONTINt*ING DOSE ASSESSMEST 2 Page 12 of 30 1 1 Table A-1 WOLE BODY DorE RATE COMPARISON Column 1 2 3 4 5 I i i l i I Measured (*) l Calculated l RATIO (Calculated / Location I Time I (mR/hr) l (mR/hr) ! Measured) I I I I - I l l I I I 1 l 1 1 I I I I I I I I I I - 1 I I .
. . I I I I l I I I c_
l i l l l I l I I i I 'l I I I I I I I I I I I I I I I I I I I I I I I l . I I I I I I I I I I I I I I I I I I I I I I I I I I i i i I I i 1 I I I I I I I l l l l
- Measured data will be transmitted from the onsite chemistry lab and field teams to the STSC/ EOF.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE 7 NO. APPENDIX B IMPLEMENTING PROCEDURE EPIP-14C Page 1 of'l REVISION CONTINUING DOSE ASSESS.'IENT 2 Page 15 of 30 I l Tabl. :-1 Summation of Iodine Dese Conversion Factors vs. ! Effective Age and Total Iodine to I-131 Dose Ratios for Adult Thyroid
- 1*. Failed Total Core 1*. F.F. TCI Effective Fuel Inventory Tot.I/I-131 Tot.I/I-131 Age I7 DCF E7 DCF Dose Dose Chrs) (Rem m'/hrCi) (Rem m /hrCi)8 Ratio ' Ratio l 0.0 6.85 x 10 5 3.07 x 10' 1.23 1.45 0.5 7.06 x 10' 3.53 x 10 5 1.22 1.42 1.0 7.27 x 10' 3.81 x 10 5 1.22 1.42 1.5 7.59 x 10' 4.61 x 105 1.21 1.41 2.0 7.75 x 10' 4.46 x 105 1.21 1.41 2.5 7.96 x 10' 4.67 x 105 1.20 1.41 3.0 8.17 x 10' 5.10 x 10' 1.20 1.37 3.5 8.29 x 10' 5.33 x 105 1.19 1.37 I 4.0 V 8.50 x 10' 5.37 x 105 1.19 1.37 5.0 8.60 x 105 5.88 x 10' 1.19 1.35 6.0 9.04 x 10' 5.99 x 105 1.18 1.34 7.0 9.16 x 10' 6.45 x 10' 1.17 1.32 8.0 9.39 x 10' 6.65 x 10' 1.17 1.31 9.0 9.66 x 10 5 6.81 x 10' 1.16 1.31 10.0 9.80 x 10' 7.19 x 10' 1.16 1.29 ;
11.0 1.00 x 10' 7..+7 x 10' 1.15 1.29 ! 12.C 1.02 x 10' 7.60 x 10' 1.15 1.26 16.0 1.09 x 10' 8.32 x 10' 1.13 1.24 20.0 1.17 x 10' 9.37 x 10' 1.11 1.21 24.0 1.21 x 10' 9.60 x 10' 1.10 1.18 48.0 1.46 x 10' 1.26 x 10' 1.05 1.09 72.0 1.60 x 10' 1.50 x 10' 1.02 1.04 96.0 1.68 x 10' 1.62 x 108 1.01 120.0 1.03 1.73 x 10 8 1.69 x 108 1.01 1.01 144.0 1.75 x 10 8 1.75 x 10' 1.00 168.0 1.01 1.77 x 108 1.77 x 10' 1.00 1.00 e l l
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APPENDIX C
._ IMPLEMENTING PROCEDURE EPIP-14C Page 1 of 1'2 REVISION CONTINUING DOSE ASSESSMENT 2 Page 16 of 30 4
PALO VERDE NUCLEAR GENERATING STATION (PVNGS) EMERGENCY OFFSITE DOSE CALCULATION COMPUTER PROGRAM INSTRUCTIONS 1.0 SOFWARE DESCRIPTION The PVNGS Emergency Dose Projection Ccmputer Program has been designed for rapid assessment of emergency radioactive effluent releases based upon core inventory. The program is designed for - the IBM personal computer with 512 K RAM (64K advanced basic
- interpreter) with one double sided / double density disk drive and an AST card, an Okidata 93 printer (preferably with a graphics chip to imitate an Epson printer). However, the program can operate without a printer. ,
The computer program calculates both noble gas dose and iodine 30 s year dose commitment and dose rates at site boundary, 2 miles, 5 ' $. miles, and 10 miles based on a straight line Gaussian meterological O model. Plume arrival and effect!.ve age at the above downwind distances are determined also. Based upon the site boundary dose rates, one of the four energency classifications (or none) will be , selected. Dose calculations are based en EPIP 14b and release rate calculations are based on EPIP 14a. To aid in the tracking of plumes, the program is capable of variable trajectory plume plotting. The plume generated has only ' one constant plume width (or dispersion). It should be noted that the plume plot is only an aid and actual plume configuration and dose rates will be different to some extent. 2.0 OPERATION 2.1 Computer and Optional Printer Preparation CAUTION
- DO NOT TOUCH THE INNER PORTION OF THE DISKETTE.
1 2.2.1 Insert the " Emergency Offsite Dose Projection" diskette into disk drive "A" (left side) with the diskette label on the l top. Close the disk driva "A" door.
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CONTROLLED BY USER q a PVNGS EMERGENCY PLAN 7fesouns APPENDIX C _. IMPLEMENTING PROCEDURE EPIP-14C Page 2 of '12 REVISION CONTINUING DOSE ASSESSENT 2 Page 17 of 30 s CALTION NEVER REMOVE THE DISKE'ITE OR REBOOT WHILE TE RED DISK DRIVE LIGHT IS ON. 2.1.2 Turn the computer on. The switch is located on the right side near the rear. If the power is aircady on, press
" Ctrl", " Alt" and " Del" all at lihe same time to reboot the j disk. The program will autocarically be loaded and run.
NOTE Sections 2.1.3 through 2.1.5 are to set-up the Okidata printer.
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} 2.1.3 Ensure the *cable is connected between the printer and the computer.
2.1.4 Check the small dial on the front left side of the printer to make sure that is is set to "7". 2.1.5 Ensure that the perforation line of the paper is above print head then turn on the power. The switch is located on the back right side of the printer. 2.2 Program Operation 2.2.1 The program starts by allowing the operator to update the current date and time and the date and time of the reactor shutdown. The current time is displayed as a running clock. Press the number associated with the item to be updated. Remember to include the " " or ":" where shown. 2.2.1.1 The program will not allow a reactor shutdown date and time to surpass the present date and time or an error
- beep will occur when continuing. If this error beep occurs, change the re cter shutdcwn date and/or time.
2.2.1.2 If the reactor is still operating under power, leave tho shutdown date and time unchanged (00-00-00 and 00:00)'. 2.2.1.3 Press "5" to continue with the program. m 1
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<O. PVNGS EMERGENCY PLAN PROCEDURE
( IMPLEMENTING PROCEDURE NO. EPIP-14C APPENDIX C Page 3 of '12 REVISION CONTINUING DOSE ASSESS'!Ehi 2 Page 18 of 30 2.2.2 The main menu wf11 now be displayed on the screen. "Ihis is the menu which allows different calculations or operations to be perfor=cc. 2.2.3 Selecticn nu=ber 1, " Current Release Dose Determination". This selection should be chosen to reflect actual radioactive releases which are occurring and will perform the following: a) Plot current' plume position on the screen and will 'pdate u each minute
,b) Calculate two hour dose (in rem) and dose rates (in rem /hr.) for both noble gasses and total iodines. The total iodine deses are 50 year dose commitments. The l
screen will display the child iodine dose rate which is twice that of the adult. c) Determine emergency classification based on the site
.)/ boundary noble gas and total iodine dose rates.
Emergency Classification based on noble gas dose rate (rem /hr).
< 5.0 E-3 NONE 5.0 E-5 chru 4.9 E-4 UNUSUAL EVENT 5.0 E-4 thru 4.9 E-2 ALERT 5.0 E-2 thru 9.9 E-1 SITE AREA E!TRGENCY
> 1.0 GENERAL EMERGENCY Emergency Classification based on total iodine dose rate (rem /hr) is five times the above noble gas dose rates.
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APPENDIX C 1MPLEMENTING PROCEDURE EPIP-14C Page 4 of '12 REVISION CONTINUING DOSE ASSESS"EST 2 Page 19 of 30 2.2.3.1 The following is a description of those ite=s displayed on the screen: a) At the top right of the screen is the viewing screen
, which displayed the plume. This screen is updated each minute.
b) At the top left of the screen is the carrent date and running clock which was entered in 2.2.1. - c) Bele.w this is the screeri description. This screen is
" CURRENT RELEASE PROJECTIONS".
d) Below this is the emergency classification. e) Below this is the indicator for whether the plume
^
date is ready to be updated. If the words " PRESS SPACE BAR TO UPDATE" does not appear, than the plume l *) v is already being updated and the cursor is positioned at one of the seven input parameters. f) Seven input parameters pertaining to each plume. - These parameters will be discussed in more detail later. g) Date and time of reactor trip which sas entered in 2.2.1.
, h) Plume number; two numbers are associated with this number. The number on the left indicates the number of plumes on the screen and the other indicates the teral number of plumes g2nerated and on file. .
- 1) The bottom right of the screen displays dose rate information and operator messages.
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CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX C IMPLEMENTING PROCEDURE EPIP-14C Page 5 of'12 REVISION CONTINUING DOSE ASSESSMENT 2 Page 20 of 30 NOTE Obtain temperatures, wind speed and wind direction from meterological tewer using ERFDADS. NOTE With the exception of input <!5, -
"Rel. Time," if the input para =eter is to remain unchanged, just press
" Return".
2.2.3.2 To create or update a plu=e, press the space bar. This will stop the clock and the space bar update prompt will erase. 7:e cursor will move to input #1, " stability classificatzon". Enter the proper classification of A-G s and press "ceturn". If the classification is unknown then enter a "C". The screen will prompt the operator for the =eterological tower temperature difference of 200 feet - 35 feet. A stability classification will be determined. - 2.2.3.3 Move the cursor to input d2, " Wind Speed". Enter the wind speed in mi/hr. Do not leave the speed at zero. Press ' Return' and the cursor will advance to input #3. 2.2.3.4 For input d3, " Wind From", enter the degrees from which the wind is blowing. This is a value from 0 to 360. Press " Return" and the degrees to which the wind is going will be displayed along with the effected downwind sector on the plu=e centerline. The cursor will advance.to input 1/4. 2.2.3.5 For input n4, "Rel. Date", enter the date (mm-dd-yy) on the plu=e release or its update. This date can not surpass today's date. If the date is surpassed, an error beep will sound when the plume atte= pts to update and the ' date will need to be changed. The cursor will advance to input d5. I l CONTROLLED BY USER
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l CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX C IMPLEMENTING PROCEDURE EPIP-14C Page 6 of'12 REVISION , CONTINUING DOSE ASSESSMENT 2 Page 21 of 30 NOTE The Releasa Time must be advanced with each update.
- 2.2.3.6 For input #5 "Rel. Time", enter the time (24 hour clock FM:MM) which the plume was released or the time which one of the input parameters changed. The release time can not surpass today's date and current time. If-the time is surpassed, an error beep will sound when the plume atte= pts to update and the t'ime will need to be changed.
The cursor will advance to input #6. NOTE If "C" is selected but either the noble gas or iodine release rate is zero, curse through the program selections following release rate determination and
\s_l' force the release rate in question to zero.
2.2.3.7 For input #6, " Noble Gas", enter the noble gas release ratu in curies per second. The number may be entered as decimal or scientific notation. If the value it unknown, prest "U" and answer the questions relating to the release rate portion of the program. Release rate ^ calculations are discussed in section 2.4 and are performed using the method of EPIP-14A. The cursor will advance to input #7. 2.2.3.8 For input #7, "I-131", enter the iodine-131 release rate in curies per second. The number may be entered as _ decimal or scientific notation. If the value is unknown, press "U" and answer the questions relating to the release rate portion of the program. Release rate calculations are discussed in section 2.4 and are performed using the method cf EPIP-14A. ' 2.2.3.9 Upon answering #7 the prompt " PRESS SPACE BAR TO UPDATE" will reappear and the " CURRENT TISE" clock will restart. { CONTROLLED BY USER .-
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APPENDIX C
-- . IMPLEMENTING PROCEDURE EPIP-14C Page 7 of 12 REVISION CONTINUING DOSE ASSESSMENT 2 Page 22 of 30 2.2.3.10 At this point the operator has several options to choose fro =. The following cre the choices:
CALTION
' IF THE TRAILING EDGE OF A PLUME EXTENDS PAST TE TEN MILE RADIUS, TE PLUME WILI; BE DELETED FROM THE SCREEN. THIS MUST BE TAKEN INTO CONSIDERATION IF THE PLUME OVERLAPS (REVERSES DIRECTION).
a) Wait until the clock reaches the minute mark and the current plume information will be used to construct a plume and perform dose calculations. Dese calculations will be performed only if a new plume is y detected (change in parameter). The operator will be y prompted to whether a printout is needed. Next the dose rates will be displayed, 'the plume will be drawn and the emergency classification will be updated along with the plume numbers. Plume information and doses will be stored on disk for later retrieval. b) Press the F1 key. This forces the plotting of the plume (and dose calculations if new plume). This performs the same items as 2.2.3.10.a above. Function keys will be discussed in more detail later. c) Press F3 to delete the latest plume. Function keys will be discussed in more detail later. . d) Press other function keys (discussed later) to manipulate the viewing screen. e) Press the space bar to correct or update plume information/ parameters per sections 2.2.3.2 through
- 2.2.3.9.
f) P'ress "R" to return to the main menu in section 2.2.2. r CONTROLLED BY USER
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..' IMPLEMENTING PROCEDURE EPIP-14C Page 8 of '12 REVISION CONTINUING DOSE ASSESSMENT 2 Page 23 of 30 2.2.4 Menu Selection number 2, " Projected Dose Determination".
This selection should be chosen to project doses of radioactive releases which might occur (a "what if" situation). This selection is essentially the same'as menu selection "1" with the following exceptions: a) Plume plotting is not performed with this selection. b) All function keys except F1 (dose calculations) are inoperable. c) This selection will allow the operator to input a release date and time that surpasses the current date and time.
; NOTI i'
Prior to starting dose projections, past p entries should be reviewed and deleted f if not needed. Io delete all past entries, enter the word " KILL" for the plume number and press " Return". I 2.2.5 Menu Selection number 3, " Review Past Entries". This selection is used to review plume and dose information stored on the diskette. 2.2.5.1 Plume data files are identified by two numbers (exp. 1-1230). The first being the plume number, which is a consecutive numbering system. It is possible to have two of these numbers the same if a plume has been deleted and another plume with a different time was entered. 2.2.3.2 The second number is the release time of the plume. All files will having the trailing ".dat" which indicates a data file. I 2.2.5.3 All files will be listed (if any) and the operator will ! be prompted for the file to review. Files may be deleted
- l at this time by entering the word " KILL" for plume number.
2.2.5.4 Once the file numbers have been entered, the relevant information for the plume will be displayed on the screen. A printout may be obtained by pressing both the
* " shift" and "PrtSc" keys (remember to form feed the paper
, and place back on-line).
2.2.5.5 Pressing the space bar will produce the past entry review i screen; the operator may review another file or return to l
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CONTROLLED BY USER m PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIN C _ IMPLEMENTING PROCEDURE EPIP-14C Page 9 of'12 REVISION CONTINUING DOSE ASSESSMENT 2 Page 24 of 30 2.2.6 Menu Selection number 4, " FIELD DATA". This selection is used to calculate total iodine doses using iodine air sa=ples taken by field monitoring teams. 2.2.6.1 The screen will list all the questions to be answered. 2.2.6.2 The " location" is any name which will identify where the sample was taken. An "R" may be entered for location to return to the main menu. - 2.2.6.3 Sa=ples will be decay corrected from the time of reactor ~ shutdown. If the reactor shutdown date shows that it is still operating, an effective age of zero (0) is used (plume travel is not considered). 2.2.7 Menu Selection number 5, " CHANGE REACTOR SHUTDC'.'N/ TIME". This selection allows the operator to return and change or s update the current date and time and also the reactor
;j shutdown date and time in section 2.2.1.
2.3 Function Keys 2.3.1 There are ten (10) function keys (F1-F10) located on the left side of the keyboard. Seven of these keys are used by.the program. CAUTION
^ WHEN PRESSING FUNCTION KEYS, A'ITESTION SHOULD BE PAID TO THE RUNNING CLOCK. IF THE .
CLOCK MAS NOT APPEARED ON THE SCREEN OR THE CLOCK IS NOT RUNNING, THEN THE PROGRAM IS PERFORMING CALCULATIONS AND NO OTHER , FUNCTION KEYS SHOULD BE PRESSED UhTIL IT STARTS TO RUN AGAIN. 2.3.1.1 Function key "Fl" is used in both " Current Release Dose Deter 6ination" and " Projected Dose Determination". Pressing this key forces the program to draw and update the plume instead of waiting until the minute update. If
' the program detects a change in one or more of 3 input parameters, a dose projection will be calculated and the emergency classification based on site boundary dose rates will be displayed. No plume will be drawn in the
" Projected Dose Determination" selection.
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REVISION COSTISUING DOSE ASSESSMENT 2 Page 25 of 30 e 2.3.1.2 Functi:n key "F2" is used in " Current Release Dose Determination" only. Pressing this key switches to a large screen for plotting of plumes. Pressing both the
" shift" and "PrtSc" will print the plume. This will take approxi=ately 2.5 minutes to complete. This screen will not update each minute. Press the space bar to return to the plume parameter screen.
2.3.1.3 Function key "F3" is used in " Current Release Dose Determination" only. Pressing this key will delete the last plume plotted and will return all seven input parameters including plume riumber and emergency l classification bacs to their previous values; Prior to deleting the plume the operator will be asked if the plume is to be deleted in case the key was pressed inadvertently. 2.3.1.4 Function key "F7" is used in " Current Release Dose
, Determination" only. Pressing this key will make the y
) plume screen zoom in (or increase in size). If the screen is increased too much, an error beep will occur.
2.3.1.5 Function key "F8" is used in " Current Release Dose Determination" only. Pressing this key will make the plume screen zoo.s out (or decrease in size). If the screen is decreased too much, an ertor beep will occur. - 2.3.1.6 Function key "F9" is used in " Current Release Dose Determination" only. Pressing this key will draw in 2, 5, and 10 mile radii including the 16 sector marks. 2.3.1.7 Function key "F10" is used in " Current Release Dose Determination" only. Pressing this key will drtw Jn major reads and highways.
- 2.3.2 A region of interest may be focused in on by using the four arrow keys on the number pad on the right side of the keyboard. These keys are "S" for looking up (moves map down), "2" for looking down, "4" for looking left (moves map '
right) and "6" for looking right. Moving too far in one direction,will cause an error beep. 2.4 Release Rate Calculations 2.4.1 When a "C" is selected for either the noble gas or iodine
.l release rate, release rate calculations will be performed and
's the screen will display five types of calculations that may be perfor=ed. Press the number for the calculation to be performed.
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.m PVNGS EMERGENCY PLAN FROCEDURE No. APPENDIX C IMPLEMENTING PROCEDURE EPIP-14C Page 11 of' 12 REVISION CONTISUING DOSE ASSESSMENT 2 Page 26 of 30 g
2.4.1.1 Seletting Plsnt Vent, Fuel Building Vent or Condenser Air Removal will display, for the most part, the same type of screen. The only difference will be the " fans running" , if the total flow is unknown. The following questions will be prompted: e.) Total Flow, the previous flow will be displayed in CFM. If the flow is to remain the same, then just press the return key. If the new flow is lifferent, ~ then enter the new number. If the flow is-unknown then enter a "C". The screen will prompt the cperator for which fans / pumps are running and the flow from each will be summed. NOTE For plant vent, if a no is the answer to if an effluent monitor is
- in use then the program defaults to i
prompting for containment area ks _/ monitor readings or hand held instrument readings. b) Enter the gross beta channel reading from the effluent monitor in uC1/cc. c) The program will then calculate the noble gas, I-131 and totsl iodine release rates and will display them on the screen. .If a mistake was made when inputting data, then press the "R" to redo calculations. Pressing the space bar will return to plume plotting and dose projections. 2.4.1.2 Main Steam Line: a) Enter the monitor reading or averaca readings on the effected steam line(s) in mR/hr. b) Enter the number of steam line monitors that are ' releasing steam. Enter the steam flow in thousands of pounds per hour and the monitor correction factor for each steam line. c) The program will then calculate the noble gas, I-131 and total iodine release rates and will display them on the screen. If a mistake was made when inputting _- data, then press the "R" to redo calculations. Pressing the space bar will return to plume plotting and dose projections. CO.NTROLLED BY USER ..
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2 CONTROLLED BY USER ! l m PVNGS EMERGENCY PLAN PROCEDURE I N O-APPENDIX C L. IMPLEMENTING PROCEDURE EPIP-14C Page 12 of'12 REVISION CONTINUING DOSE ASSESSMENT 2 Page 27 of 30 2.4.1.3 Containment Curie Calculation v a) Enter the number of isotopes from the grab sample analysis. b) Enter the isotope name, activity (uC1/cc), and half-life (hrs.). Each of these will be eatered prior to pressing the return key but are separated by a comma, c) ' Enter the containment temperature (deg. F) and pressure (psig). d) The program will then calculate the total curies in the containment. This value could be taken and used in containment leak rate dose projections. Answer the prompt if another calculation is needed. i a e s 9 {
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_. IMPLEMENTING PROCEDURE EPIP-1:C Page 1 of 3 j REVISION CONTINUING DOSE ASSESSSENT 0 Page 28 of 30
- s ALTERNATE !ZTHODS FOR OBTAINING 51ETEOROLOGICAL DATA I. Introduction This appendix is used as an alternate method for determining meteorological conditions in the site environs when the ERFDADS/ Meteorological Tower is inoperativa.
Immediately on determination that communications with ERFDADS has been
- lost or that the met tower is inoperative a' technician should be dispatched to the met tower area to obtain weather data locally. The dose projection precess should not be held up while waiting for the technician to report. However, the technician should report the wind direction before the affected sectors are deter =ined. The default value for affected sectors should not be used unless there is no indication of wind direction available.
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a/ The following is a listing of the backup methods and a brief description of when to use each one.
- 1. Default Values - used for initial dose projection when the ERFDADS/ Meteorological Tower is unavailable. These values are extremely conservative and should be replaced with real data as soon as possible.
- 2. Local Readings from the main meteorological tower - on a loss of com=unications via ERFDADS during a release or with a release '
imminent, a technician should be dispatched to the meteorological tower and readings relayed from the local instruments. Dese projections should g be held up while waiting for this data. Default conditions should be used until the local station is canned. The following sections are divided into two parts. Part A is a description of the method and Part B is the operating instructions for that method. II. Default Assumptions and Values
- A. Assumptions ,
The use of default values requires that estimates be made conservative enough to ensure proper protective action recommendations are made to protect the general public. The assumed meteorological conditions must be such that they will yield the most restrictive plume dispersal factors for the ten mile EPZ. l -- CONTROLLED BY USER -
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX 3 IMPLEMENTING PROCEDURE EPIP-14C Page 2 of'3 REVISION CONTISUING DOSE ASSESSMENT 2 Page 29 of 30 Because accurate determination of wind direction cannot be made, then a conservative assu=ption must be used regarding site boundary distance and affected sectors. The most restrictive site boundary from an emergency classificatien standpoint is the west boundary along Wintersburg Road. This boundary is affected when the wind is from the east. Therefore, when choosing the Xu/Q value for site boundary, use the value listed for wind from ninety degrees. For af fected sectors, have the technician at the met tower visually check the. wind vane on the met tower at the thirty-five foot e levatier.. If the technician is unable'to make an estimation of wind direction based on obse.rvation of'the wind vanes at the met tower, then all sectors should be considered affected. ,
, I Wind speed presents a problem in that a low wind speed will give a conservative estimate of X/Q, but results in less conservative values
' for transit time / effective age at the receptor. High assumed wind speeds result in errors in the X/Q, while being conservative in
/
, transit time and effective age. To compensate for this it is necessary to assume two wind speeds, a low wind speed for X/Q determination and a high wind speed for plume transport.
For atmospheric dispersion factor (X/Q) selection, the class selected must allow for the least dispersion during transport. The stability category that allows for the least dispersion is a condition of extreme stability, Class G. B. Instructions
- 1. The following parameters shoul'1 be used for default values for projecting off-site doses:
1.1 Wind direction - 90 degrees 1.2 Wind speed - for X/Q determination, use 1 mph
- for transit time, use 10 mph 1.3 Stability class - G '
1.4 For affected sectors and protective action recommendations, use indicated wind direction, if available, or default to all sectors if no direction obtainable. CONTROLLED BY USER .
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. IMPLEMENTING PROCEDURE EPIP-l!.C Page 3 of 3' REVISION CONTINUING DOSE ASSESSMENT 2 Page 30 of 3C III. I.ocal Readout at the Meteorological Tower A. Discussion This section is to be used when com=unications from the met tower to the ERFDADS are not available. Initial dose projections should not be held up while waiting to use this section, def ault values are to be used until a technician gets to the met tower. When the technician arrives at the met tower, he must determine that the =et tower is operable. If the met tower is not operable report this to the EOF /STSC.
B. Instructions 1.0 Send a technician to the met tower. 1.1 The key for the met tower may be obtained from shift , g\ security personnel or the RP Office.
-' 2.0 At the met tower.
2.1 Establish communications with the EOF (if canned) or the STSC. 2.2 Verify operability of the met tower. 2.2.1 If the tower is inoperative, report this to the EOF or STSC. - 2.2.2 If the tower is operable, proceed to step 2.3. 2.3 Obtain the following data and transmit it to the ECF or STSC. NOTE Use fifteen minute averages for data points.
- 2.3.1 , Wind direction in degrees at the thirty-five foot elevation.
2.3.2 Wind speed in miles per hour at the thirty-five foot elevation. l
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2.3.3 Delta T in degrees Fahrenheit (200 ft. - 35 ft.).
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AUTHOR , T. S. Barsuk REVISED BY G. A. Simiele w , EXT. 6661 _ TECH. REVIEVE DATE [/d"Id . PRB/PRG/TRRG REVIEW s, a
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FINAL APPROVAL DATE d [ V' N I EFFECTIVE DATE (UDC only) ASSIGNED COPY NUMBER (DDC only) DN-1669A/0196A
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN [pceoune IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 2 of 13 REVISION HISTORY Rev. No. Date Revised Pages Coc:ments 3 4, s . 6, 7, Corrected references, 10, 11, 12, , revised procedure to match 13 writers guide, corrected referrals to personnel responsibilities; corrected PAG's in Apo. A. 4 Incorporated previous PCNs e eb O e w e
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN QCsoune , IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 3 of 13 TABLE OF CONTENTS SECTION PAGE NWiBER 1.0 OBJECTIVE
- 4
2.0 REFERENCES
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3.0 LIMITATIONS AND PRECALTIONS 4 4.0 DETAILED PROCEDURE 6 1 4.1 Personnel Indoctrination / Responsibilities 6 4.2 Prerequisites 6 1 4.3 Instructions 7
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_. APPENDICES Appendix A - Guidelines for Recommended Protective Actions 10 For Gaseous Plume Exposure Appendix B - Reduction in External Gamma Dose From Passing 12 Cloud Appendix C - Inhalation Shielding Factors for a Wood House 13 Snug Lacrs, Closed Windows ? - t
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PVNGS EMERGENCY PLAN Qcaouse IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 4 of 13 1.0 OBJECTIVE 1.1 To provide a basis for relating actual or projected plume exposure doses to the Environmental Protection Agency (EPA) Protective Action Guides (PAGs).
2.0 REFERENCES
2.1 Implementing Returences 2.1.1 EPIP-14B, " Initial Dose Assessment" 2.1.2 EPIP-17, "Onsite/Offsite Surveys and Sampling" 2.1.3 EPIP-03, " NOTIFICATION OF UNUSUAL EVENT Implementing Actions" . i 2.1.4 EPIP-04, " ALERT, SITE AREA and GENERAL EMERGENCY s Implementing Actions" 2.2 Developmental References - 2.2.1 NUREG 0654, Rev. 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants'.', Nov.
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1980. 2.2.2 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents; as revised June, 1980; ; N EPA-520/1-75-001. 2.2.3 PVNGS Emergency Plan, Rev. 6. 3.0 LIMITATIONS AND PRECAUTIONS 3.1 The protective actions determined by this procedure are to be
- presented to appropriate state / county agencies as RECOMMENDATIONS. Only these agencies are authorized to implement the' protective actions.
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CONTROLLED BY USER . m PVNGS EMERGENCY PLAN Qceouas ' IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 5 of 13 3.2 Protective action recommendations are based on plant and containment conditions and these recommendations are made even
,when no release is in progress. These recommendations are transmitted to government officials using EPIP-03, and
" NOTIFICATION OF UNUSUAL EVEhT Implementing Actions" EPIP-04,
" ALERT, SITE AREA and GENERAL EMERGENCY Implementing Actions."
3.3 Protective action guides represent trigger levels and are not intended to re'present acceptable dose levels. -
.i 3.4 PAGs for the general public are given in ranges. The lowest dose values should be used if there are no major local constraints in providing protection at this level. Local constraints may, however, make the lower values impractical to use,.but in no case should the higher value be exceeded in determining a need for protective action.
" 3.5 The projected dose and affected offsite areas depend upon the j curies released, release rate, duration of the release,
. isotopic mixture of the release (varies with effective age) and meteorological conditions.
3.6 At times, selection of protective actions should be considered subjectively as conditions beyond the scope of this procedure may exist.
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3.7 Vhp the wind is blowing into the Palo Verde Hills (sectors N, P cr Q) and protective actions are being considered, the two sectors on either side of the affected sector shall be included in the recommendation (e.g., a plume in sector P ' sha9 require consideration of sectors M, N, Q and R in the rectamendation.) . 3.8 Protective actions recommended to state authorities by ANPP SHALL NOT be transmitted to the JENC. - 3.9 Government officials should inform EC/EOD prior to implementing protective actions.
- 3.10 If actual airborne radioactivity, noble gas or lodine sample results are available (either from RMS filter analysis or field measurements) this information may be used instead of dose projections for making protective action recommendations.
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- PROCEDURE PVNGS EMERGENCY PLAN N O.
IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 6 of 13 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 Dose estimates which population groups may potentially receive, are calculated in accordance with EPIP-14B,
" Initial Dose Assessment." This dose estimate is referred to as the projected dose. A protective action is an action taken to avoid or reduce this projected dose when the benefits derived from such action are sufficient to 4 offset any undesirable features of the protective action.
4.1.2 The Protective Action Guide (PAG) is based on the projected dose to individuals in the population which warrant taking protective actions. It is used in an effort to minimize the risk from an event which is occurring or has already occurred. N 4.1.3 The responsibility for the decision to notify and
.) recommend protective actions to the appropriate authorities' belongs to the Eaergency Coordinator until he is relieved of this responsibility by the Emergency -
Operations Director. 4.1.4 The Radiation Protection Technician of the affected unit shall be responsible for initial offsite dose calculations and/or projections. 4.1.5 The Radiation Assessment Coordinator (Radiation Protection Monitor, on shift) shall be responsible for updating and ~ refining dose assessments for critical r'eceptor site locations and evaluating appropriate protective actions. 4.1.6 The Radiological Protection Coordinator (Radiological Assessment Coordinator) shall be responsible for relaying - dose assessment and protective action evaluations to the Emergency Coordinator (Emergency Operations Director). 4.2 Prerequisites 4.2.1 Projected *whole body and thyroid dose rates and integrated dose for critical receptor site locations have been calculated in accordance with EPIP-14B anf such doses warrant evaluating, and if necessary, recommending protective actions.
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN [RCEDURE IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 7 of 13 4.3 Instructicas 4.3.1 Radiological Assessment Coordinator (Radiation Protection Monitor, onshift) shall: 4.3.1.1 Evaluate current plant status with respect to potential for releases or increased releases. 4.3.1.2 Update and refine dose estimates for critical receptor site locations upon significant changes in one or more of the following parameters: (1) Release rates. (2) Duration of the releases. (3) Isotopic mixture of the release (varies, as a function of effective age). (4) Meteorological conditions. 4.3.2 Should the plant status or projected doses indicate that [! (. sheltering or evacuation be considered per Appendix A, determine the effectiveness of these protective actions as described below. Time estimates should be obtained from - the State Emergency Operations Center. 4.3.3 Evacuation Effectiveness - The effectiveness of evacuation in limiting radiation dose is a function of the time of
~ exposure if a plume is present. This is dependent upon the time required to evacuate. The evacuation time T(EV) ~
is expressed as: T(EV) = TD+ N+ M+ T - Where: i T = Time delay measured from the point of the - D protective action recommendation from the facility . to government to evacuate to the actual decision by , the competent authority to order the evacuation. T =
. Time required by offi:ials to notify people N
to evacuate. Tg = Time required for people to mobilize and l get under way. T T
= Travel time required to leave the affected
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 8 of 13 4.3.3.1 If evacuation is completed before the plume arrives, then evacuation is 100 percent effective. To determine the time of expcsure to the plume, it is necessary to calculate the plume arrival time T(PA). The plume arrival time, T(PA) is expressed as: T(PA) = TB+ TR Where: - T 3
= Time projected before release begins.
T TR
= Time projected for p1'2me travel for given windspeed and downwind distances from the start of release. To calculate TTR **f'#
to procedure EPIP-14B. 4.3.3.2 Evaluate constraints against evacuation. Compare the estimated evacuation time T(EV) with the estimated plume arrival time, T(PA). 4.3.3.3 Under the following conditions evaluate the benefits of sheltering vs. .the benefits of evacuation. (1) In cases w' tere there is no time to evacuate prior to the arrival of the plume. (2) The projected evacuation time and timo before plume arrival are nearly equal. ' 4.3.3.4 If evacuation appears to offer a significant redue; ion in dose (greater than sheltering) recommend evacuation to the appropriate county and/or state officials. 4.3.4 Sheltering Effectiveness 4.3.4.1 If evacuation does not offer significant dose ' avoidance or if local constraints prevent evacuation recommend that officials warn the affected population to: (1) Seek shelter. (2) Close windows. (3) Turn off ventilation systems.
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN [ROCEDURE o IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 9 of 13 4.3.4.2 Control access to the affected area. 4.3.5 Evaluate the possibility of evacuation after the plume has passed. 4.3.5.1 After the plume has passed, evaluate the significance of ground deposition in accordance with EPIP-17 "Onsite/Offsite Surveys and Sampling". 4 . 3 . 5 . :. Determine if dose rates are sufficient to warrant subsequent evacuation. 4.3.5.3 Multiply the projected dose by the external shielding factor (Appendix B). 4.3.5.4 Compare the projected dose to the PAG for whole body gamma dose (Appendix A).
, 4.3.6 Evaluate the significance of inhalation dose. (Shielding ./
factors for inhalation doses are presented in Appendix C). Shielding factors are for a sealed, wood-frame house. 4.3.6.1 Maltiply the projected dos a by the inhalation shielding factor to determine the reduction in inhalation dose from the plume. Compare the projected dose to the PAG for thyroid dose in Appendix A. 4.3.7 Determine the critical organ of concern, the whole body or the thyroid. Compare the projected dosa for the critical orgsn to the PAG for that organ in Appendix A. - t
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PROTECTIVE ACTION RECOMMENDATIONS
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CONDIT104 RECOHH_ULDIO ACil0N m
- 1. Notification of Unusual Event Decla red. Inform state and county authorities of O status /cause and. based on situation recommend M M (/)
that no protective action is necessary or % 2M h standby for update if situation worsens,
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- 2. An ALERT has been declared. Inform state and county authorf tf os of Alert status /cause and recommend that the public fee TM y apprised of the situation and stay tuned to O 32 a EDS/KI AR radio sta tion. b Q (")
O y 3. A Site Area Emergency has been declared, inform state and county authorities or Site % E 20 UF 0 y Area Emor ency status /cause and consider m CM l F recommend og seeking shelter within a 2-milo 2Z M radius of the plant as warranted based on plant / containment conditions. m M to . A Gene ra l Emergency has bee'n declared. Shelter within 2-mile radius and 5 miles in l potentially arrected sectors.* m om C 5 y
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- 5. EPA Protective Action culdelines are in accordance with EPA Protective Action 6 M projected to be exceeded. Culdelines: Z M E N al whole body 1 rem to 5 rems Recommended shelter, as a minimum for , m E
% thyroid 5 rems to 25 rems arrected sectorsa and consider evacuation unless time constraints make it i mp ra c t i ca l ,
e u b) whole body 5 rems Rocommend evacuation for arrected sectors' thyroid 25 rems or shelter for those areas that cannot be evacuated before plume arrival. y yy 5e 5N em g
- NOTE: Arrected sectors include, as a alnimum, the dow swind sector (s) and adjacent sectors. l'o r M 5 p lume s i n sac to r l', Q, o r N, ewo sectors on either side or the arrected sector shall ha O op included in the recommendation (e.g., a plume in sector P shall requi re consideration ur o %
sector M N, Q and R). % g> U 9 A r
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O O Zm O O PROTECTIVE ACTION RECOMMrNDATIONS 3 5 g sj Og O RJQOMHfRDED ACT10N N 6. CON 0allON Loss of' physical control or the plant 1. EvAnation for 2-mile radius and 5 miles in Q oa O 4ll N O F to intraiders, potentially arrected sectors.* M g I F r m C> p-
- 7. Substantial core damage has occurred or Evacuation for 2-mile radius and 5 miles in 2Z E is projected to tiie extent that 20% of potenially arrected sectors.* m t clad gap activity is released from
- 8. Large fission product Inventory Evacuation for 5-mile radius and to miles in .
t (greater than ruel gap clad activity) potentially arrected sector (s). M C i ,$3
'B C
- 9. Imminent containment f a i lu re i s p ro- Shelter (nr areas that cannot be evacuated h23 M Jected such that a " puff" release greater than design lea 4 rate will before plume arrival; ovacuation or remainder of 5-mile radius and 10-miles in potentially 7
.-. I'1 m occur, in conjunction wi th 7. or 8. affected sectors.* P
- above.
- NOTE: Arrected sectors Include, as a minimum, the dowrrwind sector (s) and adjacent sectors. for y ,,
plumes in sector P, Q, or N, two sectors nn either side of the arrected sector shall be a am included in the recommenda tion (e.g., a plume in sector P shall require consideration or 09 M N sector M, N, Q and R). a am
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CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX B IMPLEMENTING PROCEDURE EPIP-15 Page 1 of'l REVISION PROTECTIVE ACTION GUIDELINES 4 Page 12 of 13 REDUCTION IN EXTERNAL GAMMA DOSE FROM PASSING CLOUD SHIELDING FACTOR (a) STRCCTURE OP. LOCATION AVERAGE RANGE (1) Outside 1.0 -- (2) Veh'icles 1.0 -- (3) Vood frame house (no basement)(b) 0.9 -- (4) Basement of wood house 0.6 0.1 to 0.7(C) (5) Masonry house (no basement) 0.6 0.4 to 0.7(c) (6) Basement of masonry house 0.4 0.1 to 0.5f *)
., (7) Large office or industrial building '
O.2 0.1 to 0.3(c d)
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NOTES: (a) The ratio of the interior dose to the exterior dose (b) A wood frame house with brick or stone veneer is approximately equivalent to a masonry house for shielding purposes. (c) This range is unainly due to different wall materials and different geometries.
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(d) The reduction factor depends on where the personnel are located within ' the building (e.g., the basement or an inside room). .
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CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEDURE o PP NDIX C IMPLEMENTING PROCEDURE EPIP-15 Page 1 of 1 REVISION PROTECTIVE ACTION GUIDELINES 4 Page 13 of 13 INHALATION SHIELDING FACTORS FOR A WOOD HOUSE, SNUG DOORS, CLOSED WINDOWS C 0 1.0 i a i *
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- 8 mph (3.6 M/5) ia h .8 -
2 4 mph. S - (1.8 M/S) . 4 Y .6 - E C . s - C
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E ' Wind Speed = 1 mph (.447 M/S) N 8 .2 " o l
- p Note: 1 mph = 0.447 M/S ,
3 g , O 2 4 6 8 10 EXPOSURE TIME (HRS) 1
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CONTROLLED BYN O PEEN 3Ix o CuY FIL6,0AC 0ZZO2 Ee 1 oc 1 1 PROCEDURE CHANGE NOTICE (PCN) Rev. 9
? age 29 of 35 l Procedure No. .
i Revisica: lPCN No. (obtain i;cm CCC only)l 1 i l l EP/P-/fo , 4 g l I l l
Title:
IDDC Contact (ext. 6633) I a.
. DflM b Survey 4 d SQ~ f y Tackoe Ghsou l l Orignator: (Print) l Ext. l Unit (s) affected: l l Gesafd R Simiele l Reason for this PCN:
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I l /1 d'e4le r A n mfes b E A/A*~CP <snd &$/A 29 r A tt k <t 4 l 1 l l - l l %'Jn a ffeh . l l g/ l Expiration: l l . ! ! l Page nu=ber(s) affected (Total Numoer of l . by this PCN: lPages attached: 47j 73 , 3
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l l l l- Does PCN require a 30.59 review? & No Yes (rerer to 2.1.2) l C') 1 l- Does PCN affect activities in l I i l the RCA? No X"Yes (Copy to ALGA)' l l 1 l- Does PCN ef fect the non-radiogical l l envircnment of any offsite area? .y No Yes (Contact Compliance) l 1 l l- Is PCN associated with an AC, I l Program, Emerg. Plan or Secur. ' l l Prog., Phase I-IV Test, or a No X Yes (PRS /PRG/TRRG l l ST7 review required) l l 1 1 - - l M / b['d$ l TECHNICAL REVIEWER (Supervisory Level Date l l l b! PRB 04494///'
}ldac6/f8 $ .
l l l GyRGCHAIRjtAN(ifrequired) l _/ _
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CONTROLLED BY USER PVNGS EMERGENCY PLAN QCEWRE IMPLEMENTING PROCEDURE EPIP-16 - AEVISICN INPLAST SURVEYS AND SAMPLING 4 Page 1 of 13
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PVNGS C 7 DEPT. HEAD I/8f 8 DATE _[ 'I [b PR3/PRG/TRRG REVIEW _'AI//fYM(( . DATE (( /(( APPROVED BY / [77/ ' DATE 7 6
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EFFECTIVE DATE 64' C 6 fir 1 l ! DN-1629A/0190A j CONTROLLED BY USER ..
CONTROLLED BY USER PVNGS EMERGENCY PLAN CEDURE [R IMPLEMENTING PROCEDURE EPIP-16 - REVISION INPLANT SURVEYS AND SAMPLING 4 Page 2 of 13 REVISION HISTORY Rev. No. Late Revised Pages Cc= cents 3 05-10-85 4.5,6,7 Revised to uedate references 8, 9, 10, 11, and to correctiv reflect 14, 15, 16 current eethed for surveys and sa=uling 4 5'4. # tv All Deleted TIME / INITIALS column in Aeoendix D. Deleted Aeoendices A, B and C. n [
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CONTROLLED BY USER PVNGS EMERGENCY PLAN [ROCEDURE o IMPLEMENTING PROCEDURE EPIP-16 . REVISIOt1 4 INPLANT SURVEYS AND SAMPLING A Page 3 of 13 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 4
2.0 REFERENCES
,4 3.0 LIMITATIONS AND PRECAUTIONS 5
4.0 DETAILED PROCEDURE 6 4.1 Personnel Indoctrination / Responsibilities 6 4.2 Prerequisites 7 4.3 Instructions 7 4.3.1 General Instructions 7
.T 4.3.2 Radiation and Contamination Surveys 8 C_/ 4.3.3 Particulate and Radiciodine Air Samples 9 4.3.4 Noble Gas Air Sa=ples 4.3.5 Exiting Controlled Area 10 APPENDICES Appendix A - Inplant Monitoring Team Response 11 I
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CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE N O. , IMPLEMENTING PROCEDURE EPIP-16 REVISION 1 INPLANI SURVEYS AND SA".? LING 4 Page 4 of 13 , 1.0 OBJECTIVE 1.1 To provide for e=ergency inplant radiological menitoring and surveys in the event of a release of radionuclides.
2.0 REFERENCES
2.1 Icple:enting References 2.1.1 EPIP-17, "Onsite/Offsite Surveys and Sa:pling" i 2.1.2 EPIP-18, " Emergency Exposure Guidelines" g 2.1.3 . . . __, '_ _ D- .. b _' , . m' _ .- ' et e v4 4 2 . '. . ' C: :?, "Are2/E-"ipeane "~-' ^r# ; rrd Decc tr-' 2:ix"- [ 2.1.f 9N219.05.00, " Document / Record Turnover Control" 2.2 Developmental References 2.2.1 NUREG-0654, Rev. 1 " Criteria for Preparation and - Evaluation of Radiolegical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 NUREG-0737, " Clarification of TMI Action Plan Require =ents," Oct. 1980 2.2.3 75RP-9ZZ46, " Radiological Surveys," Rev. 3.
. 2.2.4 75RP-9ZZ48, " Airborne Radioactivity Sampling and Measurement," Rev. 3 -
2.2.5 75AC-9ZZ01, " Radiation Exposure Authorisation, Permits and Control," Rev. 2. 2.2.6 F & J Specialty Preducts, Inc. "Radiciodine Absorption Cartridge Documentation and Technical Perfor=ance Specifications for NRC Audits of Radiciodine Sa=pling Proceduresg" 1984. 2.2.7 ANSI N45.2.9, " Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power
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l Plants," 1974. !
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2.2.8 PVNGS Emergency Plan, Rev. 6 l
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CONTROLLED BY USER PVNGS EMERGENCY PLAN pCEDURE IMPLEMENTING PROCEDURE EPIP-16 REVISION INPLANT SURVEYS AND SAMPLING A Page 5 of 13 3.0 LIMITATIONS AND PRECAUTIONS 3.1 The Radiological Protection Coordinator (RPC) may authorize exposures in excess of PVNGS Administrative Radiation Exposure Limits up to the limits of 10 CFR 20. Exposures in excess of 10 CFR 20 limits up to Emergency Exposure Limits of EPIP-18,
" Emergency Exposure Guidelines," shall be authorized by the Emergency Coordinator. Exposures in excess of Emergency Exposure Limits shall not be authorized.
3.2 The Radiation' Protection Monitor (RPM) or RPC should check applicable dose rates via RMS or the ERFDADS monitor prior to RP access into an area. 3.3 Perform instru=entation peroperational checks and prestage required sampling equipment prior to performing surveys.
, 3.4 Access the controlled area using the Emergency Radiation Exposure Permit, nu=ber 9999, if required.
NOTE When entering areas of unknown radiological conditions, be sure survey meter is switched to the highest scale. 3.3 While in route to the survey location, keep the survey meter turned on and continuously monitor dose rates. 3.6 Under the follcwing conditions inplant monitoring personnel should withdraw from the area icmediately and relay this { information to the RPM /RPC. , 3.6.1 If the unanticipated area dose rate is equal to or greater than 10 R/hr, or levels are significantly greater than expected. e CONTROLLED BY USER . ,
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REVISION N INFLANT SURVEYS AND SAMPLING 4 Page 6 of 13 NOTE The following conditions may indicate airborne radioactivity: a continuous air conitor in a valid alarm condition or observation of steam. 3.6.2 If airborne activity is suspected at the survey location and the field monitoring team is not wearing respirators, control access and leave the area. 3.6.3 If any me=ber of the field monitoring team exceeds their assigned dose limit. 4.0 DETAILED PRCCEDL"tE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 The Radiation Protection Monitor, until relieved by the Radiological Protection Coordinator, is responsible for the i:plementation of this procedure. 4.1.2 Technicians involved in surveying and sampling should be familiar with operation of the air samplers, cartridges, filters, and survey instruments. Monitoring Team members should be familiar with 75RP-9ZZ48, " Airborne Radioactivity Sampling and Measurement," and 75RP-9ZZ46,
" Radiological Surveys." ,
4.1.3 Me=bers of Monitoring Teams should proceed to the Operations Support Center for instructions. , 4.1.4 The Operations Support Center Coordinator shall supervise the formation of Inplant Monitoring Teams. 4.1.5 The E=ergency Maintenance Coordinator, in conjunction with the RPM /RPC, shall direct the briefing and dispatching cf Inplant Monitoring Teams. 4.1.6 The Unit Radiation Protection Supervisor shall provide technical support for the inplant survey teams in coordination with the RPC. 4.1.7 The Inplant Monitoring Team Leader should communicate with m o .
.the RPC at least every 30 minutes via phone and/or portable radio (channel #4).
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.~ PVNGS EMERGENCY PLAN [RCEDURE IMPLEMENTING PROCEDURE EPIP-16 REVISION N INPLAST SURVEYS AND SAMPLING 4 Page 7 of 13 4.2 Prerequisites 4.2.1 An ALER"i or more severe emergency has been classified per EPIP-02, "E=ergency Classification."
4.2.2 Don protective clothing and respiratory apparatus if necessary. 4.2.3 Obtain emergency equipment from the OSC emergency kit. 4.2.4 Perform instrumentation preoperational checks and prestage required sa=pling equipment prior to performir.g surveys. 4.3 Instructions 4.3.1 General Instructions . 4.3.1.1 The inplant teams shall be briefed on area (s) to be
,O- monitored, specific surveys to be performed and any
( special instructions needed by the RPM /RPC. 4.3.1.2 Airborne radioactivity (radioiodine, particulates, and noble gases) should be sampled or measured as directed by the Radiation Protection Monitor or Radiclogical Protection Coordinator. l 4.3.1.3 The Inplant Monitoring Team Leader shall respond as i per Appendix A "Inplant Monitoring Team Response." l 4.3.1.4 Survey meters should be left on while in transit. All unposted or unexpected inplant readings and all readings above 1 R/hr shall be reported to the ' Radiation Protection Monitor or the Radiological Protection Coordinator. m l
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IMPLEMENTING PROCEDURE EPIP-16 - REVISION N INPLANT SURVEYS AND SAMPLING 4 Page 8 of 13 4.3.1.5 Areas to be surveyed shall be determined by the Radiation Protection Monitor or the Radiological Protection Coordinator. Determination of areas to be surveyed should depend on the type of accident, area radiation monitor readings and previous survey data. The major accident categories are listed below with suggested survey areas. Suggested . Accident Tvoe Survey Area LOCA All areas around containment Areas around operating ESF equipment during recirculation phase SGTR Main Steam Lines, Turbine,
,. ~ and Condenser V WGDTR Area around WGDT including entire radwaste building FHlc Fuel handling area 4.3.2 Radiation and Contamination Surveys.
NOTE Ensure you are adequately briefed on e;.pected conditions at survey location prior to departing. 4.3.2.1 While in route to the survey location, keep the stErvey meter on and continuously monitor dose rates. 4.3.2.2 Upon arrival at the survey location perform required radiation and contamination surveys. Record survey results as per 75RP-9ZZ46, " Radiological Surveys" and report findings to the RPM /RPC. s _ . , .
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CONTROLLED BY USER PROCEDURE PVNGS EMERGENCY PLAN N O. IMPLEMENTING PROCEDURE EPIP-16 - REVISION INPIET SGVEYS AND SAMPLING 4 Page 9 of 13 4.3.2.3 Maintain communications with the RPM /RPC and report radiation readings when they change significantly. 4.3.2.4 If the dose rate exceeds expec:ed levels or if exposure of any member of the tec , exceeds their assigned limit, the entire team shall retreat to a low level radiation background area, notify the RPM /RPC and await further instructions. 4.3.3 Particulate and Radioiodine Air Samples NOTE Particulate and radiciodine air samples should be collected and documented in accordance with 75RP-9ZZ48, " Airborne Radioactivity Sampling and Measurement," s except as noted below.
- _ 4.3.3.1 Air sample volumes should be 10 ft' or as directed
. by the RPM /RPC. 4.3.3.2 The maximum flow rate should not exceed 2 CFM to ensure adequate collection efficiency for tilter zeolite cartidges. 4.3.3.3 Determine the sampling time necessary to collect a sample volu=e of 10ft2 and collect sample. NOTE If the air sampling cartridge binds in , the air sampler head, allow several minutes for the a/s head to cool, rather than forcing the cartridge. 4.3.3.4 Disassemble the sample head. Place the particulate filter in a plastic bag and label the bag with the date, time, location, sample volume and name of person taking sample. 4.3.3.5 Place the silver zeolite cartridge in a plastic bag and label as above. 4.3.3.6 Deliver the air sample to the count room for analysis
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N O. IMPLEMENTING PROCEDURE EPIP-16 REVISION INPLANT SL"RVEYS AND SAMPLING 4 Page 10 of 13 - 4.3.4 Noble Gas Air Sa=ples 4.3.4.1 Insert AgX cartridge into AgX holder. AgX cartridges for noble gas sa=ples may be used repeatedly during a one day period. 4.3.4.2 Place filter paper upstream of the AgX cartridge in the holder. 4.3.4.3 Attach holder to one side of the gas collection chamber (=arinelli beaker). 4.3.4.4 Attach tygen tubing to the other percock of gas collection cha=ber and to the air sa=ple pu=p. NOTE It =ay be possible to collect the noble
'. gas air sa=ple at the same ti=e as the
/ particulate / iodine sample. Be sure that the sa=ple flow rate does not exceed 2 CFM.
4.3.4.5 With both percocks open, draw a minimum of 5 volu=e changes or if NG/P/I sa=ples are collected at the same time select an appropriate sampling period. 4.3.4.6 Close both percocks on the gas collection cha=ber. 4.3.4.7 Deliver tha sa=ple to the Radiation Protection Count Room or to an alternate location for analysis as directed by ; the RPM /RPC. 4.3.5 Exiting Controlled Area 4.3.5.1 Notify the RPM /RPC that the survey is co=plete and of your intention to return to the OSC. 4.3.5.2 Proceed to the nearest low background area and perform a s whole body frisk. i 4.3.5.3 If contaminated, notify the RPM /RPC and proceed with S{ decontamination procedures as per EP:P 2*, "? m ; .:1 'N Q, u--<.-.: . . .a n.......:...:-- *L gSgp.yg g g,Q Q. " '
- - 4.3.5.4 Ensure that all survey equip =ent is surveyed and released if possible.
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INPLANT MONITORING TEAM
RESPONSE
POSITION FILIID EY: Radiation Protection Technician RESPONSIBILITY: Perform inplant radiation monitoring. , IMMEDIATE ACTIONS
- 1. Report to OSC upon notification.
- 2. Obtain briefing from supervisory individual:
(a) Radiation Protection Monitor (Onshift) o_r_ (b) Radiological Prote,ction Coordinator (Onsite).
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/ 3. Obtain the following equipment as required:
(1) Legal TLD, job TLD (alarming dosimeter optional) (2) Emergency equipdent as required from the OSC emergency kit.
- 4. Check batteries and perform sontce check tests on survey instruments.
- 5. Check batteries in portable radio.
- 6. Obtain appropriate survey maps and forms from the OSC Emergency Kit or the RP Office, s
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RESPONSE
- 7. Conduct surveys and sa=pling for:
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- a. Dose rate measurements
- b. Particulate, radiciodine and noble gas air sa=ples
- c. Contamination levels -
- 8. Save all sa=ples for reccunt or dispose of sampling =edia as radioactive waste as directed by the RPM /RPC.
SUBSECCENT ACTIONS Reoorting
- 9. Co==unicate with the Radiation Protection Monitor (onshift) or the e' Radiological Protection Coordinator at least every one half hour via i phone or portable radio.
Documentation 10 .' Co=plete all utilized survey maps and retain for DOC. Decentamination
\t 11. Be checked for contamination.
k 11. 75RP-9 Decontaminate self as required, per EFIP-28,p,1), "%c..hwaben."
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Title:
lDDC Contact (ext. 6633) l l l On.vle/0%le Surveys a,,d SaqAif l &kie steasaa l l Orignator: (P tat) I I::t . l Unit (s) affected: l l %td 9: sa.,;de l MSf l 6*' l l Reason for this PCN: . I J] eklek he sees k EP/P.29
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IMPLEMENTING PROCEDURE s EPIP-17 REVISION ONSITE/0FFSITE SURVEYS AND SAMPLING 3 Page 1 of 15 O - ASSIGNED COPY , s PVNGS # f DEPT. HEAD!/ 7,2 fli $,(_.- .' DATE $ I [ PRB/PRG/TRRGREVIEW!d/* '/ig//// - DATE /2[dT> APPROVED BY
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EFFECTIVE DATE M44 j DN-1631A/0190A s.
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,- PVNGS EMERGENCY PLAN Qcsouse IMPLEMENTING PROCEDURE EPIP-17 RsVISION ONSITE/0FFSITE SL'RVEYS AN'J S.U!PLING 3 , Page 2 of 15 REVISION HISTORY Rev. No. Date Revised Pages Co==ents 3 vA.g.'rk All _ Deleted Checklist: Deleted
. gross radioactivity sa= ole sheet and air sa=cle sheet.
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2.0 REFERENCES
4 3.0 LIMITATIONS AND PRECAUTIONS 6 4.0 DETAILED PRCCEDURE 7 4.1 Personnel Indoctrination / Responsibilities 7 4.2 Prerequisites 7 4.3 Instructions 8 APPENDICES Appendix A - Emergency Field Monitoring Data Sheet: Beta / Gamma Dose Rate Measurements 13 Appendix B - Onsite Survey Map 14 Appendix C - Field Monitoring Team Response 15 e
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2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-02, "E=ergency Classification" 2.1.2 EPIP-143, " Initial Dose Assessment" 2.1.3 73Ri'-9ZZ30 " Operation Calibration and Performance Testing of Laboratory Scaler Counting Systens" In.1,4
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, Plants, 1974" 2.2 Developmental References 2.2.1 NUREG-0634, Rev. 1 " Criteria for Preparation and Evaluation of Radiological E=argency Response Plans and Preparedness in Support of Nuclear Power Plants."
2.2.2 75 RP-9ZZ46, " Radiological Surveys," Rev. 3. 2.2.3 75 RP-9ZZ48, " Airborne Radioactivity Sampling and Measurement," Rev. 3. 2.2.4 E=ergency Plan, Rev. 6.
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. IMPLEMENTING PROCEDURE EPIP-17 REVISION ONSITE/CFFSITE SURVEYS AND SAMPLING 3 Page 7 of 15 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 The Radiation Protection Monitor (RPM), until relieved by the Radiological Assessment Coordinator (RAC), is responsible for implemention of this procedure.
4.1.2 Technicians involved in surveying and sampling shotrid be familiar with operation of the air samplers, cartridges and filters, noble gas chambers, and survey instruments. Field Monitoring team members should be familiar with 73RP-9ZZ48, " Airborne Radioactivity Sampling and Measurement," and 73RP-9ZZ46, " Radiological Surveys." 4.1.3 Members of field monitoring teams should proceed to the Operations Support Center for instructions.
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4.1.4 The OSC Coordinator shall supervito the formation of Field C Monitoring Teams. 4.1.3 The Radiological Assessment Coordinator, through the RPM and the Emergency Maintenance Coordinator, shall direct the briefing and dispatching of Field Monitoring Teams. 4.1.5.1 The Field Monitoring Team Leader should communicate with the Radiological Assessment Co=municator at least every one half hour via portable radio using channel
#4; for the RERV, use radio channel #1.
4.2 Prerequisites 4.2.1 An ALERT or more severe emergency has been classified per the provisions of EPIP-02, " Emergency Classification." 4.2.2 Don protectice clothing and respiratory apparatus if necessary. 4.2.3 Obtain appropriate sampling equipment. 4.2.3.1 The of'fsite monitoring teams should obtain the Offsite Survey Team Kits from the RERV. 4.2.3.2 Onsite monitoring teams should obtain necessary equipment from the OSC Emergency Kit Locker. _e - CONTROLLED BY USER
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CONTROLLED BY USER - PVNGS EMERGENCY PLAN PROCECURE N O. s IMPLEMENTING PROCEDURE EpIp.17 - REVISION ONSITE/0FFSIC SURVEYS AND SAMPLING 3 Pag, 8 of 15 l 4.2.4 Offsite RFAT members should assemble at the RERV to perform instrument and radio checks prior to being dispatched. 4.3 Instructions 4.3.1 General Information 4.3.1.1 The offsite sampling locations shall be determined by
, the RPM /RAC based on wind direction and a plume width of 3 sigma Y. The Field Monitoring Team Leader shall respond as per Appendix D, " Field Monitoring Team Response."
4.3.1.2 For plant perimeter surveys, the RPM /RAC shall determine which quadrant should be sampled. Labeled TLDs attached at various points aloag the prctected ares fence repts. eat the center of each survey sector
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and may be used as location reference points (Appendix B.) 4.3.1.3 Air (radiciodine, particulates, and noble gases) samples and radiation measurements should be taken at each sampling location as determined by the RPM /RAC. 4 3<l.4 Surzey neters should be Icft en whils in transit. All offsite readings above 0.2 mR/hr should be reported along with plume centerline and boundary locations if determinable.
- 4. 3.1. 5 All samples should be courted at locations determfu l by the RPM /RAC. ,
4.3.2 Gross Radioactivity Measurement (Appendix A). 4.3.2.1 Determine the dose rate at 3 feet with the beta thield open and closed. Record these values in Appendix A. f om CO.NTROLLED BY USER .-
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4.3.3 Particulate and Radiciodine Air Samples NOTE Particulate and radiciodine air samples - should be collected and documented in accordance with 75RP-9ZZ48, " Airborne Radioactivity Sampling and Measurement," except as noted below. 4.3.3.1 Air sample volumes should be 10 ft' or as directed. 4.3.3.2 Connect the air sampler to an appropriate power source. NOTE If the air sampler being used has a timer, be sure to select an appropriate time prior to starting the sampler. 4.3.3.3 Start the sample'r in the variable position if a variable rate air sampler is available. 4.3.3.4 The maximum flew rate should not exceed 2 CFM to ensure adequate collection efficiency for silver zeolite cartridges. 4.3.3.5 Determine the sampling time necessary to collect a. sample volume of 10ft3 and collect sample. s .se
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REVISION OSSI~E/0FFSITE S*M EYS AND SA'1PLING 3 Page 10 of 15 NOTE If the air sampling cartridge binds in the air sampler, allow several minutes for the A/S head to cool, rather than forcing the cartridge. 4.3.3.6 Disassemble the sample head. Place the particulate filter in a plastic bag and label the bag with the , date, time, location, sample volume and name of person taking sample. 4.3.3.7 Place the silver zeolite cart; ridge in a plastic bag and label as above. 4.3.3.8 Transport the sample to the designated counting location for analysis. 4.3.3.9 At the direction of the RAC, samples may be recounted in the unit chemistry lab or disposed of as radioactive material. 4.3.4 Noble Gas Air Samples 4.3.4.1 Insert AgX cartridge into AgX holder. AgX cartridges for noble gas samples may be used repeatedly during a one day period. - 4.3.4.2 Place filter paper upstream of the AgX cartridge in the holder. 4.3.4.3 Attach holder to one side of the gas collection , chamber (marinelli beaker). 4.3.4.4 Attach tygon tubing to the other petcock of gas , collection chamber and to the air sample pump. ' i Jp CO.NTROLLED BY USER
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CONTROLLED BY USER 7~ PVNGS EMERGENCY PLAN lROCEDURE o IMPLEMENTING PROCEDURE Erre-17 REVISION ONSITE/0FFSITE SURVEYS ANI SAMPLING 3 Page 11 of 15 NOTE It may be possible to collect the noble gas air sample at the same time as the particulate / iodine sample: Be sure the sample flow rate does not exceed 2 CFM. 4.3.4.3 With both petcocks open, draw a minimum of 5 volume changes or if NG/P/I samples are collected at the same time select an appropriate sampling period. 4.3.4.6 Close both petcocks on the gas collection chamber. 4.3.4.7 Place the gas collection chamber in a plastic bag. Label the bag with the sample ic:ation, date, time and name of person taking sample, 4.3.4.S Save the noble gas sample for' analysis in the unit count
/ rooms or as directed by the RAC.
4.3.5 Additional sa=pling media (soil, water, vegetation, etc.) may be collected under the direction of the Environmental Menitoring Group as part of the recovery effort following an accident. 4.3.6 Report to the RAC for idebriefing upon completion of assigned surveys. e
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~ APPENDIX C IMPLEMENTING PROCEDURE EPIP-17 Page 1 of d REVISION I ONSITE/0FFSITE SURVEYS AND SA'!PLING 3 Page 19 of 15 FIELD MONITORING TEAM
RESPONSE
POSITION FILLED BY: Radiation Protection Technicians Maintenance Technicians (as drivers) RESPONSIBILITY: Perform onsite/offsite radiation monitoring. , IMMEDIA7 ACTIONS
- 1. Obtain briefing from S:pervisory Individual: ,
(a) Radiation Protection Monitor (Onshift) go (b) Radiological Assessment Coordinator (Onsite). 4
- 2. Obtain keys for the Radiological Emergency Response Vehicle and f~ other RP Response vehicles from the key cabinet in the RP office or
/ the Security Office and check that the vehicle has an adequate fuel
.. supply. ,
- 3. Ootain keys to Meterological Tower and Gate (as required) from the .
key cabinet in the RP Office or the Security Office. 4 Obtain the following equipment from the RERV as required: (1) Map of onsite TLD locations (2) Map of offsite TLD locations (3) Offsite Survey Team Kit
- 5. Perform instrumentation preoperational checks and prestage required I sampling equipment prior to departing from the RERV assembly goint.
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- 6. Conduct surveys and sampling, as required, per EPIP-17 for: I l
(1) Dose Rate Measurements. 1 i t l & 1
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- 3 Page 15 of 15 FIELD MON 7TORING TEAM
RESPONSE
(2) Particulate and radiciodine air samples (3) Noble gas air samples
- 9. Save all samples for recount er dispose of sampling media -as radioactive waste as directed my the RAC.
SUBSEQUENT ACTIO'.<S flecorting I
- 10. Cocmunicate with the Radiation Protection Monitor bs (enshift) or the Radiological Assessment Communicator (onsite) at least every one half hour via portable
- c. radio.
Documentation
- 11. Co=plete Appendix A and all utilized survey maps and retain for DDC.
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, 4
2.0 REFERENCES
-4 3.0 LIMITATIONS AND PRECAITTIONS 5 1
4.0 DETAILED PROCEDURE 6 i 4.1 Personnel Indoctrination / Responsibilities 6 4.2 Prerequisites 6 4.3 Instructions 6
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, . , _ . . APPENDICES Appendix A - PVNGS Adminsitrative Radiation Exposure Limits 8 Appendix B - Maximum Permissible Dose Limits for 9 Occupational Workers Appendix C - Emergency Exposure Limits 10 E s 0 CO.NTROLLED BY USER . '
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CONTROLLED BY USER PVNGS EMERGENCY PLAN @caouse . IMPLEMENTING PROCEDURE EPIP-18 REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 4 of 10 1.0 OBJECTIVE 1.1 This procedure addresses required authorization, guidance, and maximum exposure criteria in the event of a radiological emergency where it becomes necessary for emergency workers to exceed PVNGS Administrative Radiation Exposure Limits or 10CFR20 exposure limits.
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-26, " Potassium Iodide (KI) Administration" 2.1.2 75RP-9ZZ44, " Radiation Exposure Permits" 3 2.2 Developmental References 2.2.1 NCRP Report #39, 1971 Basic Radiation Protection Criteria 2.2.2 EPA-520/1-75-001, Manual of Protective Action Guides and - Protective Actions for Nuclear Incidents, Revised June 1980 2.2.3 10CFR20, Standards for Protection Against Radiation, 1983 2.2.4 PVNGS Emergency Plan, Rev. 5 2.2.5 NUREG 0654, Rev. 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants". 2.2.6 NUREG 0737, " Clarification of TMI Action Plan Requirements", October, 1980 2.2.7 75AC-9ZZ01, " Radiation Exposure Authorization, Permits and Control",Rev./3 g N
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PVNGS EMERGENCY PLAN [ROCENRE IMPLEMENTING PROCEDURE EPIP-18 REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 5 of 10 3.0 LIMITATIONS AND PRECAt>TIONS 2 3.1 The Radiological Protection Coordinator may authorize exposures in excess of normal PVNGS Administrative Radiation Exposure Limits (Appendix A) up to the Limits of 10CFR20 (shown in Appendix 3). Exposures in excess of 10CFR20 Limits up to Emergency Exposure Limits (Appendix C) shall be authorized by the Emergency Coordinator. Exposures in excess of those listed in Appendix C shall ny be authorized. - 3.2 Personnel authorized to receive exposures in excess of 10CFR20 limits should meet the following criteria: 3.2.1 Personnel shall be voluntears. 3.2.2 Women of child-bearing age and capability should not be permitted to receive emergency exposures (except for lifesaving actions).
\_ 3.2.3 Personnel shall be familiar with the hazards of exposure received under emergency conditions.
e , 3.2.4 Radiation exposure history of volunteers should be known. 3.2.5 Use of volunteers above age 45 should receive first consideration. 3.2.6 Emergency exposures for life saving actions shall be limited to one occurrence. 3.3 Administrative methods to minimize personnel exposure should remain in force to the extent consistent with timely rescus, corrective and protective actions. 3.4 Personnel shall wear dosimeters appropriate for the measurement of anticipated exposure levels. These should include: 3.4.1 Thermoluminescent Dosimeter (Legal). 3.4.2 Thermolumiitescent Dosimeter (Job). 3.4.3 Extremity Desimeters, if appropriate (Appendix B, Note 2). 3.4.4 Alarming Dosimeters.
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i CONTROLLED BY USER s PVNGS EMERGENCY PLAN [ROCEDURE o IMPLEMENTING PROCEDURE EPIP-la - REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 6 of 10 3.5 If necessary, potassium iodide (KI) tablets should be administered in accordance with EPIP-26, " Potassium Iodide (KI) Administration". 3.6 Protective clothing and/or respirators should be used as appropriate. 4.0 DETAILED PROCEDURE - 4.1 Personnel Indoctrination / Responsibilities 4.1.1 The Radiological Protection Coordinator may authorize exposures in excess of PVNGS Administrative Radiation Exposure Limits (See Appendix A) up to the Limits of 10CTR20 (See Appendix B). Exposures in excess of 10CTR20 Limits up to Emergency Exposure Limits (See Appendix C) g. shall be authorized by the Emergency Coordinator. Exposures in excess of those listed in Appendix C shall n{Lt be authorized. 4.1.2 During an emergency, radiation exposures in excess of - occupational limits may be necessary. 4.1.3 Emergency dose limits (Appendix C) are defined for three
- 1) lifesaving actions, 2) corrective and/or categories:
protective actions and 3) sampling under emergency conditions. 4.1.4 Emergency exposures are justifiable only if the doses are commensurate with the significance of the objective and every reasonable effort is made to maintain emergency , worker doses as low as is reasonably achievable. 4.2 Prercquisites 4.2.1 An emergency condition has resulted in the need to conduct lifesaving actions, corrective or protective actions and/or sampling activities which might result in doses exceeding PVNGS Administrative Radiation Exposure Limits. 4.3 Instructions 4.3.1 Authorization CO.NTROLLED BY USER .. .
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.- PVNGS EMERGENCY PLAN QOCEDURE IMPLEMENTING PROCEDURE EPIP-18 REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 7 of 10 NOTE The following actions shall be performed to document emergency radiation exposures.
Although it is preferable to perform these steps before the exposure is received, the Emergency Coordinator may verbally authorize the emergency exposure with documentation to be completed at a later - time. 4.3.1.1 The Radiological Protection Coordinator shall provide the Emergency Coordinator with,a radiological evaluation of the situations and conditions requiring emergency exposures. , 4.3.1.2 During emergency conditions, personnel shall be instructed to use the standing Emergency Radiation i Exposure Permit (REP 9999). Verbal instruction shall be provided on protective equipment, procedures and allowable emergency doses. 4.3.1.3 Documentation shall be completed when time allows in the form of a signed Radiation Exposure Permit (REP 9999) per 75RP-9ZZ44, " Radiation Exposure Permits". 4.3.2 Personnel Exposure Control , 4.3.2.1 Individuals shall abide by all conditions specified in the REP. 4.3.2.2 Individuals shall not enter any area where dose rages are unmeasureable with instruments immediately available. 4.3.2.3 Personnel unable to complete the task within the allotted stay time or allotted dose shall exit the radiation area. , 4.3.3 Subsequent, Actions 4.3.3.1 The Radiological Protection Coordinator shall obtain ! initial estimates of the radiation dose of exposed personnel as quickly as possible, update and refine dose estimates at a later time and immediately report exposures in excess of 10CFR20 Limits to the PVNGS Plant Manager who shall then report to the NRC per 10CFR20.403 and 10CFR20.405. CONTROLLED BY USER .-
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PVNGS EMERGENCY PLAN [ROCEDURE o APPENDIX A IMPLEMENTING PROCEDURE EPIP-18 Page 1 of 1 REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 8 of 10 PVNGS ADMINISTRATIVE RADIATION EXPOSURE LIMITS .. Veekly Quarterly Yearly Whole Body 300 mrem 1.0 REM 4.0 REM 9 O O . '\ I l b CO.NTROLLED BY USER .. .
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4 CONTROLLED BY USER s, PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX B IMPLEMENTING PROCEDURE EPIP-18 Page 1 of I REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 9 of 10 MAXIMUM PERMISSIBLE DOSE LIMITS FOR OCCUPATIONAL WORKERS DOSE LIMITS Critical Organ mrem / quarter Whole Body, Head and Trunk, Active 1,250 1 Blood-Forming Organs, Lens of the Eye or Gonads Hands, Forearms, Ankles, Feet 18,.750 8
,- Skin of Whole Body 7,500 2 Other Organs (Thyroid), 5,000' Tissues and Organ Systems -
Pregnant Women (With Respect to 3 500 mrem the Fe*us) 9 months
- 1. 3,000 millirem is permitted in a calendar quarter or 12,000 millirem in a year as long as the accumulative occupational dose to the whole body does not exceed 5,000 millirem x (age - 18) and the individual's lifeti::;o exposure history is recorded on the NRC's Form 4 or equivalent. Doses
- exceeding 1,250 mrem / quarter must be reported to the NRC per 10CFR20.403 and 10CFR20.405.
- 2. The licensee is required to supply appropriate personnel monitoring equipment and shall require the use of such equipment by each individual who enters a high radiation area or that receives or is likely to receive a dose in any calendar, quarter in excess of 25*. of the applicable 10CFR20 value.
- 3. NCRP, ICRP Guidance.
- 4. NUREG 0737.
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' APPENDIX C ,
IMPLEMENTING PROCEDURE EPIP.-18 Page 1 of 1 - REVISION EMERGENCY EXPOSURE GUIDELINES 3 Page 10 of 10 4 EMERGENCY EXPOSURE LIMITS Sampling Under Corrective or Lifesaving Accident Conditions Protective Actions Actions Whole Body (rem) 5* 25 **** 75 **** ~ Thyroid (rem) 25 **** 125 **** NO LIMIT *** Extremities (rem) 75
- 100** 200**
- NUREG 0737, Nov. 1980
** NCRP Report #39, 1971 No specific upper limit is given for thyroid exposure since in the extreme case complete thyroid loss might be a1 acceptable penalty for a
{, life saved. However, this should not be necessary if respirators and/or s
' thyroid protection for rescue personnel are available as a result of adeqaate planning.
**** Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, Revised Juna 1980.
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l the RCA7 Y No Yes (Copy to AI.AR.A) l l ' l- Does PCN effect the non-radiogical i 1 environment of any offsite area? X No Yes (Contact Coop 11ance) l I - I l- Is PCN associated with an AC, l Program, Emerg. Plan or Secur. 1 l Prog., Phase I-IV Test, or a l-l ST7 No X Yes (PRB/PRG/TRRG l review required) l 1 1 I I I l l A ma - l l TECifNICAL REVIEkIR (Supervisory Level Date { l 1 l46 l
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- 2. PROCEDURE NUMBER EP//v-/9 REV. 4 PCN /
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~~lMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 1 of 19 t
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IMPLEMENTING PROCEDURE EPIP-19 AEVISiON ONSITE EVACUATION 4 Page 2 of 19 REVISION HISTORY Rev. No. Date Revised Pages Cc=ents 3 05-10-85 4,5,6,7,10 Revised to update 18 references and clarifv - portions of text of procedure. 4 flAbfb Deleted Checklists _ e
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IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 3 of 19 TABLE OF CCNTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 4 -
2.0 REFERENCES
4 , 3.0 , LIMITATIONS AND PRECAUTIONS 4.. 4.0 DETAILED PROCEDURE S 4.1 Personnel Indoctrination / Responsibilities S 4.2 Prerequisites S
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4.3 Instructions - 6
. APPESTICES Appendix A - Onsite Evacuation Routes and Bus Pickup Points 12 Appendix B - Offsite Reassembly Areas and Evacuation Routes 13 Appendix C - Radiation Monitoring Team Response 16 Appendix D - Evacuation Team Leader Response 18
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PVNGS EMERGENCY PLAN [ROCECURE o , IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 4 of 19 1.0 OBJECTIVE 1.1 To provide guideline infor:stien pertinent to evacuation of onsite personnel ..ncluding co=pany, construction, contractors and visitors who are not engaged in e=ergency response activities. 2.0 - REFERENCES 2.1 I=plementing References C., 2.1.1 ~ EPIP-04, "C'2T : ,1::=ic; '.n i... " y Q "ALER7,$m?ARChdGEDERM EMAGEtMZ 4 n Acbes,, n g 2.1.2 :::: 05, "::Z 152.'. En :::CY ::p1:22:i ; 9 e*" -' - 8;' 2.1.3 IT:r 00, " :ZrJ:. ::'E ::::. " :pi:::2 9 ; 'r e n " { s 2.1.4 EPIP-11. "Tec!mical Support Center / Satellite TSC Activation"
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5 2.1.5 EPIP-20, " Personnel Asse=bly and Accountability" -
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2.1.7 9N219.05.00 " Document / Record Turnover Control" . , 2.2 Develop = ental References - 2.2.1- NUREG-0654 Rev. 1, " Criteria for Preparation and Evaluation .. of Radiological Emergency Response Plans and Preparedness in Support of Nuc1, ear Power Plants" 2.2.2 PVNGS Emergency Plan, Rev. 6 2.2.3 ANSI N45.2.9 - 1974, "Requirecents for Collection Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants." - 3.0 LIMITATIONS AND*PRECAtTIONS -
, 3.1 This procedure should be conducted in an orderly fashion to avoid personnel injury. '
3.2 ' ANPP Medical staff members shall be considered essential
. personnel and shall not be evacuated.
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CONTROLLED BY USER . PVNGS EMERGENCY PLAN Qceus , IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 5 of 19 3.3 Bechtel Fire Team and Medical staff members shall be considered t essential personnel and shall not be evacuated.
- - . _ . . . . . u : :- i . : :: r e - ..
3.4 Construction Security shall be considered essential personnel and shall not be evacuated. - ' 3.5 Any documentation generated as a result of implementing this . 'i-
.t procedure shall be submitted to the Radiological Protection
, Coordinator upon event termination and forwarded to the E=ergency Planning and Preparedness Dept. for retention in accordance with 9N219.05.00 " Document / Record Turnover Control."
4.0 DETAILED PROCEDiRE 4.1 Personnel Indoctrination / Responsibilities
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4.1.1 In the event of an emergency at PVNGS, it may be desirable ( . to send persons home before thare is an uncontrolled
" release of radioactive material. Such cases may be treated as early dismissal from work and subject only to Section 4.3.1 of this procedure. Notification of such dismissal shall come from the Emergency Coordinator and should be I passed down the supervisory chain to accomplish an orderly sequence of dismissal. Security shall provide traffic .
control.
. 4.1.2 The remainder cf this procedure applies in the event of evacuations where persons may be contaminated and is
;. g .fj addressed in Section 4.3.2 c.f this procedure. -
- 4.1.3 Assembly and accountability per EPIP-20 " Personnel ' ~
Assembly and Accountability," shall be acce=plished prior to any evacuation. 4.1.4 The E=ergency Coordinator is responsible for determining ,1 the need for onsite evacuation, the offsite reassembly area 1 evacuation routes, and the order of evacuation from various parking lots.
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4.1.5 The Security Director is responsible for conducting the . . evacuation. . .i t/l
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PVNGS EMERGENCY PLAN , [ROCEWRE o , IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 6 of 19 4.2 Prerequisites 4.2.1 A SITE AREA EMERGENCY or GENERAL EMERGENCY his been declared or the Emergency Coordinator has det. ermined t at the condition warrants evacuation of non-essential
- personnel.
4.2.2 Assembly and accountability have been completed er EPIP-20 and all groups of non-essential personnel are e their sembly areas awaiting evacuation instrucci s. 4.3 Instruct ons { NOTE
- Accountab icy shall be completed er EPIP-20
.. prior to e.t -y dismissal,
- w. 4.3.1 Early Dismissal l 4.3.1.1 The Emergency C rdinator may determine that it is desirable to send ge,rsons home before there is a danger
' of radiation exposu e.
4.3.1.2 TheEmergencyCoo/ rdina qr shall direct the Security :. Director to inform all Ahsembly Area Supervisors who shall in turn' inform theih roups. 4.3.1.3 The preferred order of notif . tion and early dismissal 4 shall be as follows: ' p;. jd l l (1), Visitor's Center * ' 1 (27 Bechtel and subcontractor manuals '
- (3) Bechtel and subcontractor non-manh is *
(4) ANPP/Bechtel Start-up (S) ANPP Construction ; i j (6) PVNGS Nuclear Operations
- 4. .1.4 The ANPP Medical Staff and Bechtel Fire Team and Medical Staff shall not be dismissed early. The\ Tire )
d Team shall report to its equipment building and adait ;l
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further instruction. The Medical Staffs shall report .,gfj l to their First Aid Stations and await further ..le qf instruction.
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') REVISION ONSITE EVACUATION 4 Page / of 19 i
4.2 Prerequisites 4.2.1 A SITE AREA EMERGENCY or GENERuI, EMERGENCY has been i declared or the Emergency Coordinator has determined that _ the condition warrants' evacuation of non-essential personnel. , 4.2.2 Assembly and accountability have been completed per. EPIP-20 and all groups of non-essential personnel are at their assembly areas awaiting evacuation instructions. ' 4.3 Instructions NOTE Accountability shall be completed per EPIP-20 prior to early dismissal. 4.3.1 Early Dismissal
'i)..
/ 4.3.1.1 The Emergency Coordinator may dete mine that it is desirable to send persons home before there is a danger of radiation e:cposure.
4.3.1.2 The Emergency Coorriinator shall direct the Security Director to inform all Assembly Area Supervisors who shall in turn inform their groups. 4.3.1.3 The preferred order of notification and early dismissal shall be as follows: (1) Visitor's Center . (2) Bechtel and subcontractor manuals
. (3) Bechtel and subcontractor non-manuals (4) ANPP/Bechtel Start-up (S) ANPP Construction (6) PVNGS Nuclear Operations Fire seigade and 4.3.1.4 The ANPP^ Medical Staff and Bechtel Fire Team andgu/,/e/
Medical Staff shall not be dismissed early. ThedFire egufpment building and await Team furthershall report toThe instruction. its.Mdical Staffy shall report s to their First Aid Stationg and await further 4 instruction. 7he ANPP medisd SlbP skllmwrf h Of IE(bM* k S ffcef (mler*. Th AN/P Bre Angack shllnyctf k YAe ECf. k i -
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CONTROLLED BY USER .1 m PVNGS EMERGENCY PLAN [ROCEWRE IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVAC"ATION 4 Page 7 of 19 4.3.1.5 Construction Security shall not be dismissed early. They shall report to their duty stations and await instructions. 4.3.1.6 PVNGS Nuclear Operations technical and training personnel shall be directed to report to the offsite reassembly area rather than go he=e so that they may be recalled if their support is needed. ' o 4.3.2 The E=ergency Coordinator shall: NOTE The instructions provided below have been incorporated into the E=ergency Coordinator's responsibilities found in
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4.3.2.1 Deter =ine if an evdcuation is# required per the level of i e=argency classification or if onsite evacuation is { otherwise desirable. 4.a.2.2 Consult with the Radiological Protection Coordinator (or Radiation Protection Monitor) and deter =ine the 4 appropriate offsite asse=bly area and evacuation route (See Section 4.3.9 of this procedure). 4.3.2.3 Determine the necessity to reassemble emergency personnel in the Operations Support Center and Service Building into orie of the protected facilities, i.e. , the CR/STSC, Technical Support Center or E=ergency Operations Facility. 4.3.2.4 Consult with the Security Director to assure that traffic control and other activities are sufficiently , advanced to allet.' proper evacuation. 4.3.2.5 Orde'r the Shift Supervisor to sound t!ie e:ergency siren to signal evacuation and make a PA announcement with specific instructions. 4.3.3 The Security Director shall:
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CONTROLLED BY USER . 4 m PVNGS EMERGENCY PLAN PROCEDURE No. IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 8 of 19 NOTE The information pr:vided below has been incorporated into the Security Director's responsibilities found in EPIP-11
" Technical Support Center / Satellite TSC . Activation." .
4.3.3.1 Contact the Maricopa County Sheriff's Office by-
- dedicated telephone or radio to request assistance as required.
4.3.3.2 Inform the Sheriff's Office of the designated offsite reassembly area (Palo Verde Inn or Hassayampa Pump Station) once that is determined by the Emergency
.. Coordinator.
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4.3.3.3 Request Sheriff's Office assistance with traffic [ (, control at the offsite reassembly area. 4.3.3.4 Arrange for an orderly sequence of evacuation.
. 4.3.3.5 Direct the Security Force to routinely check ANPP trailers and buildings in the Administration area outside the protected area to ensure all non-essential .
personnel have left the premises. 4.3.3.6 Direct Corporate Site Security to check the Visitor's Center and associated areas. . - 4.3.3.7 Contact the Evacuation Team Leader at the offsite , reassembly area to decercine if any eoergency supplies are needed. The Administrative and Logistics
- Ccordinator shall arrange for any needed supplies.
4.3.3.8 Provide periodic reports on evacuation status to the Emergency Coordinator, l i 4.3.4 Radiological Protection Coordinator e
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.., .. PVNGS EMERGENCY PLAN 7a.caouas IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 9 of 19 NOTE The instructions provided below have been N incorporated into the Radiological Protection Coordinator's responsibilities found in EPIP-il.
4.3.4.1 The Radiological Protection Coordinator shall assist the Emergency Coordinator in deter =ining the appropriate offsite reassembly area and evacuation route. 4.3.4.2 Palo Verde Inn should be selectsd as the offsite reassembly area unless the conditions warrant use of an alternative. In that case, Hassaya:pa Pu=p Station should be used. Appendix B contains the evacuation routes to the two off. site reassembly areas. 4.3.4.3 Provide guidance to the Radiation Monitoring team at the reassembly area as requested. 4.3.5 Radiation Monitoring Team shall: ' 4.3.5.1 Perform monitoring and decontamination as per Appendix C. , 4.3.5.2 Take direction from the Radiological Protection O l 4 Coordinator and proceed to the offsite reassembly area. D 4.3.5.3
%i Establish a conitoring point and, if necessary, a
%I decontamination area in accordance with ~?!?-20, nn . . . ., s v.>>.. . .s ...-- i... -- n h i75RP Rikigl6n.4tmonwnca. .
2 4.3.5.4 d. Monitor release. and clear all individuals and vehicles before Names and addresses of evacuses suspected of having received a dose in excess of 250 crem ce those requiring any decontamination shall be obtained before the evacuees are allowed to leave the reassembly area. 4.3.5.5 Periodically inform th'a Radiological Protection *
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Coor:linator of the progress of monitoring and. , decontamination efforts. 4.3.6 Evacuat' ion Team Leader shall: 4.3.6.1 Be a member of the Security Force appointed by the Security Director. . s P41se04 ta,tr) , t
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["EC2*"" . IMPLEMENTING PROCEDURE EPIP-19 REVISION OSSITE EVACUATION 4 Fage 10 of 19 ( 4.3.6.2 Report to the Bechtel Gate No. 1 and avait the evacuation signal. When the signal is given, he shall lead the evacuating group to the offsite reassembly 1-
, area. .....
4.3.6.3 Direct arriving groups to assembly areas at the offsite reassembly area, per Section 4.3.9.1. or 4.3.9.2'. He . - , should use arriving Assembly Area Supervisors .for assistance. . 4.3.6.4 Assist the Radiation Monitoring Team, as necessary, in - the logistics of monitoring and decontamination. he shall assure that no individual or vehicle leaves the reasse=oly area until cleared by that team. 4.3.6.5 Provide periodic progress reports and direct requests for resources, if necessary, to the Security Director. 4.3.7 Asse=bly Area Supervisors shall: 4.3.1.1 Receive instructions on impending evacuation from the Emergency Coordinator via P.A. announcements and pass
. along to the assembly area group.
4.3.7.2 Release his group to enter personal vehicles or buses once the evacuation signal is given. - 4.3.7.3 Report to the Evacuation Team I,eader at the offsite reassembly, area and assist him as necessary.
,f 4.3.8 Evacuating Personnel shall: '
4.3.8.1 Wait at their assembly areas until the evacuation
- signal is given as shown in Appendix A.
4.3.8.2 Take direction from Assembly Area Supervisors and Security Force members during evacuation. i 4.3.8.3 Proceed as follows when the evacuation eignal is given: (1) Personnel using their personal vehicles shall proceed at an orderly pace to the site exit gates _ , . . and follow the Evacuation Team I,eader. *N (2) Personnel using buses shall line up at the pick-up ; $h
, point and fill each bus as it pulls up to the ..;
iggd pick-up point. .
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PROCEDURE _ PVNGS EMERGENCY PLAN NO. IMPLEMENTING PROCEDURE EPIP-19 REVISION ONSITE EVACUATION 4 Page 11 of 19 4.3.8.4 Proceed to the offsite reassembly area ar.d take direction frem the Evacuation Team Leader. 4.3.8.5 Remain at the offsite reassembly area until cleared to leave by the Radiation Monitoring Team. 4.3.9 Offsite Reassembly Areas and Evacuation Routes -
, NOTE At no time shall buses or personal vehicles block the fire station next to the Palo Verde Inn. A clear path shall be kept open for the emergency vehicles located ac the station.
NOTE g ,, No personnel may be allowed inside the Palo Verde Inn without approval of the Evacuation Team Leader.
, 4.3.9.1 The primary offsite reassembly area shall be Palo Verde Inn. Personal vehicles shall be directed into parking lots around the Palo Verde Inn. Buses shall be
- unloaded outside the parking lot. Personnel shall remain at their vehicles or where they are unloaded.
4.3.9.2 The alternate offsite assembly area shall be the Hassayampa Pu=p Station. This should be uted only if meteorological conditions require an alternate to the , Palo Verde Inn. The Evacuation Team Leader shall' assign assembly locations upon arrival. 4.3.9.3 Appendix B contains the evacuation routes to the two areas, ,
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APPENDIX B
, IMPLEMENTING PROCEDURE EPIP-19 Page 1 of 3 REVISION ONSITE EVACUATION 4 Page 13 of 19 0FFSITE REASSEMBLY AREAS AND EVACUATION ROUTES Directions to Primary Offsite Reasse=bly Area (Palo Verde Inn)
Primary Route (1) Exit Plant Site and proceed North on Wintersburg Road to - intarsection of Wintersburg Road and Buckeye - Salome Highway. (2) At the intersection turn left. (3) Follow Buckeye - Sale =e Highway (West) to turn-off to Tonopah (411th Ave.). (4) At turn-off, turn right (North) and proceed to the Palo Verde Inn, i
. Alternate Route
( .' (1) Exit Plant Site and proceed north on Wintersburg Road to Interstate 10 (I-10). (2) Turn left onto I-10 (West). (3) Follow I-10 to the Tonopah Exit. (4) Turn left off of I-10 onto 411th Ave. (5) Follow 411th Ave to the Palo Verde Inn. i _h.
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APPENDIX B' l.MPLEMENTING PROCEDURE , EPIP-19 Pane 2 of 3._ REVISION ONSITE EVA'UATNN 4 g Page 14 of 19 CFisITE REASSEMBLY AREAS AND EVACUATION ROLTES biraction to the Alternate Offsite Reassembly 3 Area (Hassayampa Pump Station) Primary Rout;a (1) Exit Plant Site and Proceed south on Wintersburg Road to the' intersection of Wintersburg Road and Elliot Road. - (2) At the intersection turn left (East) onto Elliot Road and proceed
, to 355th Avenue.
(3) At 355th Avenue, turn left (North) onto 355th and proceed to Dobbins Road. l (4) At Dobbins Road turn right (East) onto Dobbins and proceed to 351st-Avenue. - (5) At 351st Avenue turn left (North) and proceed to the Buckeye - Salome Highway. (6) At the Buckeye - Salome Highway turn right (East) and proceed to the intersection of 3uckeye - Salome Highway and Baseline Road. (7) At Baseline Read, turn left (angle turn) and follow Baseline to Johnson Road. (8) At Johnson Road turn right (South) onto Johnson and proceed to Lower River Road. . (9) At Lower River Road turn right (West) and proceed to the pu=p station. l Alternate Route ' (1) Exit Plant Site and proceed South en Wintersburg Road to Elliot Road. i i (2) At Elliot Road turn left (East) and proceed to 355th Avenue.
- 5 (3) At 355th Avenue turn left (North) and go to Dobbins. Road. .1 c- !]
(4) At Dobbins Road turn right (East) and proceed to the Buckeye Salome 1
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, (6) At Old Highway 80 Turn left (East) and proceed to Palo Verde Road.
I (7) At the Palo Verde Road turn left (North) and go to I.ower Rivbr Road. ' (8) At the Lcwer River Road turn left (West) and proceed to the pump station.
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' N O. APPENDIX C, IMPLEMENTING PROCEDURE EPIP-19 Page 1 of 2 REVISION 9 OSSITE EVACUATION 4 Page 16 of 19 0FFSITE EEASSEMBLY AREA RADIATION MONITORING TEAM RESPOSSE POSITION FILLED BY: Radiation Protection Technicians , RESPCSSIBILITIES: Perfor= monitoring and decontamination of evacuated personnel as necessary at the offsite reasse=bly area.
IM.EDI ATE AC*:0NS
- 1. Receive initial briefing from Radiological Protection Coordinator.
- 2. Obtain the " Emergency Evacuation Decontamination Kit" from F the Security Desk of Annex Building, or obtain the necessary monitoring and decontamination supplies from '- " "'- '--
'? ft s P n c.nie Of fic ,rer EPD-22, "?:rs~ml M-ite-ing r&
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M un5Fec$ed unk. p-3. t Arrange area. for a vehicle for transport to the offsite reassembly --
- 4. Proceed directly to offsite reesse=bly area (see ap;iendix B) 1 and establish a =enitoring control point. l SUESEOCENT ACTIONS M 5. Monitor and clear all evacuated personnel and vehicles.
El 2 6. Establish decontamination area and decent inate per EP!?-20,- $
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- 8. Periodically infor= by telephone (or Evacuation Team Leader l
l radio) the Radiolegical Protection Coordinator of the l progress of monitoring and decontamination.
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX C IMPLEMENTING PROCEDURE EPIP-19 Page 2 of 2 REVISION ONSIE EVACUATION 4 Page 17 of 19 PERSONNEL MONITORING LIST Person Social Security Monitor Monitored Number Reading Discosition O e b l ee
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_ . - - APPEND H ,D IMPLEMENTING PROCEDURE , EPIP-19 Page 1 of 2 REVISION ONSITE EVACUATION 4 Page 18 of 19 EVACUATION TEAM LEADER
RESPONSE
POSITION FILTJ.n BY: Security Force Member EESPONSIBILITIES: Lead the evacuating group to the offsite reassembly area, exercise control at the area, report status to Security Director. . IMMEDIATE ACTIONS
- 1. Receive initial briefing frou the Security Director.
- 2. Obtain Security vehicle and portable radio and transport Security Team to Bechtel Gate No. 1.
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- 3. Upon sounding of the evacuation signal, lead the evacuating
', vehicles to the offsite reassembly area (see Appendix B).
SUBSEQUENT ACTIONS
. 4 Direct arriving grcups to appropriate assembly points at the offsite reassembly area.
NOTE At the Palo Verde Inn, personal vehicles shall be directed into parking lots around - the Inn. Buses shall unload outside the parking lot. Personnel shall remain at ' their vehicle or where they unload. At the Hassaya=pa Pu=p Station, the Evacuation Team Leader shall assign assembly locations on arrival. ~
- 5. Brief arriving Asse=bly Area Supervisors to provida you with assistance.
- 6. Assist the Radiation Monit6 ring Team tiith logistics, as appropriate.
- 7. Assure that no individual or vehicle leaves the reassembly
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APPEND H .D IMPLEMENTING PROCEDURE EPIP-19 Page 2 of 2 REVISION ONSITE EVACUATION 4 Page 19 of 19 EVACUATION TFAM LEADER i
RESPONSE
u SUESEOUENT ACTIONS (Cont'd) 4
- 8. Periodically infor:n the Security Director as to progress using telephone or portable. radio. .
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~,,,.,3 y PROCEDURE CHANGE NOTICE (PCN)
Page 1 of 1 70AC-0ZZO2
- e. p. ) '4
., C Rev. 9 .
Page 29 of 35 l Procedure No. i hevision: IPCN No. (obtain fro DDC only)l EP/P-A0 l 4 l 1 l
Title:
l lDDC Contact (ext. 6633) l l Pesennel hwWy ad Aax.blully l -3 ,g,, gg, w l Orignator: (Print) l l Ext. IUnit(s) affected: l 1 I l Ur n,lr{ k. $rwr e 1 (o%/ s, 2., 3 I
! l l Reason for this PCN: l D del , , ness L apip-es Srb Am Enr-aserv nsLwAcc l / / ,
/ l
'i 4 Ams" anel EPS-c6 &mi Guenni Ashsunben A Ams " l Expiration:
] #
/ l j1tfPTu22n l Page number (s) affected ITotal Nu=cer of gg4 l l by this PCN:
i 47, g jg, g lPages attached: yy l 4 i I (%, l- Does PCN require a 30.39 review? Y No Yes (refer to 3.1.2) l 4 Q l l l- Does PCN affect activities in - 1 l the RCA? X No Yes (Copy to ALARA) l l 1
!- Does PCS effect the nen-radiogical l
) environ =ent of any offsite area? x No Yes (Contact Compliance) l 1
I l- Is PCN associated with an AC, l l Program, E= erg. Plan or Secur.
, l Prog., Phase I-IV Test, or a No x Yes (PRB/PRG/TRRG - l
-l ST?
review required) l l l l _ l I-TECENICAL REVIEVER (Supervisory Level W'&S l Date l l l . N'WU h l "PR3/PRG/TREET CHAIR.'1AN (if requirea.: // Date j tI- H .. \ . V Y l SAL'iPPROVAL ' C6te j
._ v EFFECTIVE DATE (DDC only) Assigned Copy Number (DDC only)
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s CONTROLLED BY USER . PALO VERDE NUCLEAR GENERATING STATION PROCEDURE CHANGE NOTICE PAGE / of [ INTENT CHANGE:
. NO Q TES h
- 1. PROCEDUKE TITLE hrsonna As5Na [><re/ 8msun /
- 2. PROCEDURE NUMBER EA/P.2O RE Y PCN l 2a. Manager concurrence dh to exceed 5 PCNs DATE !
- 3. REASON EOR PCN: 'IE tbn stw,$lu
' MA W Dec /2.000 in.6f 549 ed Ed Arijsh/ An Anbn
- 4. EXPIRATION:_ A>rma y
- 5. AFTECTED STEPS:
, CHANGE REQUIRED:
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- 6. PREPARED BY:
ENTERED IN PROCEDURE BY: Y u /0 0 . L 'e b .2lrffYo SICNATURE DATE SIGNATURE DATE
- 7. TDIPORARY APPROVAL:
4/k SIGNATURE DATE SS/ Assist. SS DATE
- 8. DE .
l MANAGER:
- 9. PRB/PR /TRRC:
0J N'Ith i SIGNATURE
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'DATE W ? b SIGNATUR'E 'DATE 10.APPROVCD BY: F~ .
74 DthAfd!!ENT !!ANAGER'S SICNATURE 21.DATE ErrECTivE: ' DATE
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PVNGS EMERGENCY PLAN o [ROCEDURE , IMPLEMENTING PROCEDURE EFIP-20 PERSONNEL ASSEMBLY AND ACCOUNTABILITY 4 Page 1 of 28 1
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ODC . COpyFRE ASSIGNED COPY , N . . . .. PJNGS # DEPT. HEAD _ 2 - '_ Ond h%y DATEjz/c[AI PRB/PRG/TRRG REVIE ' M' ////M/// DATE / /((h l APPROVED BY y / J V'
-- _. DATE 6 [6
() { EFFECTIVE DA~'E CI'Ib II# / DN-1588A/0180A 1 Pa*occa issaa
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IMPLEMENTING PROCEDURE EPIP-20 ' PERSCNNEL ASSEMBLY AND ACCCCSTABILITY 4 Page 2 of 28 REVISION HISTORY Rev. No. Date Revised Pages Comments 3 2/13/85 ALL Total Revision: Deleted protected area only accountabilitv.' Gave Shift Suoervisor ootion of accountability at alert. Revised Anoendices. 4 Cl'ibf(- 3,8,11,12,13 Deleted Checklist Recuire-
/ 14,18,19 ments.ANPP Startuo Assembly Area changed to SU'!S
_ building. (
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PVNGS EMERGENCY PLAN [ROCEDURE , IMPLEMENTING PROCEDURE EPIP-20 PERSONNEL ASSEMBLY AND ACCOUNTABILITY 4 Page 3 of 28 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 4
2.0 REFERENCES
'4
. 3.0 LIMITATIONS AND PRECAI.TIONS S 4.0 DETAILED PROCEDURE ,
6
)
4.1 Personnel Indoctrination / Responsibilities 6
' 4.2 Prerequisites 7 4.3 Site Area Assembly and Accountability Instructions 7
~ -
4.4 Emergency Situation Terminated 15 t APPENDICES Appendix A - Assembly Area / Groups 16 4 Appendix B - Security Shift Captain Response 18 Appendix C - Individual Accountability Sheet 20 Appendix D - Administration Annex Building Cafeteria 21 Assembly Area Appendix E - Site Area Assembly Points 22 Appendix F - Bechtel's PVNGS Pre-Evacuation Assembly Plan
- 23 1
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" CEWRE PVNGS EMERGENCY PLAN ["g .
IMPLEMENTING PROCEDURE EPIP-20 REVISION PERSCSNEL ASSEMBLY AND ACCOG~rABILITY 4 Page 4 of 25 1.0 03R.CT!VE 1.1 To assemble all personnel in the event of an emergency at PVNCS in crder to facilitate notification, accountability and subsequent evacuation, if necessary. , , 1.2 To account for the whereabouts of all personnel within the protected area within 30 minutes from the time the accountability signal is activated. 1.3 To ac::un for the whereabouts of all other personnel onsite as soon as practicable (generally within one hour) after the
. accoun: ability signal is activated.
1.4 To maintain personnel accountability for the duration of the emergency conditica. l A
)
2.0 REFERENCES
2.1 I=ple:enting References 2.1.1 EPIP-02, " Emergency Classificatien" 2.1.2 ET:? C:, "0!Z A.C.'. DEECD:CY !rphsenting Arti0n; k
& PIP - 04, "Alerf, 5ab= Atec. sd %e.ul Sm.y, .Dyfem, - lIcbcn
2.1.3 EP:T-04, "cE'Tr.E D:EECI':CY : phaent4..g A--irn 2.i.4 EPIP-ll, " Technical Support Center / Satellite TSC Activation" 2.1.5 EPIP-19, "Onsite Evacuation" 2.1.6 EPIP.-21, " Search and Rescue" 2.1.7 9N219.03.00, " Document / Record Turnover Control" 2.2 Developmental References
.1 2.2.1 hTREG-0654. Rev.1, " Criteria for Preparation and Evaluation of Radiological E=ergency Response Plans and Preparedness in 1 Support of Nuclear Power Plants." !
9
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. CONTROLLED BY USER PVNGS EMERGENCY PLAN PROCEDURE N O.
IMPLEMENTING PROCEDURE s EPIP-20 REVISION PERSONNEL ASSEMBLY AND ACCOUNTABILITY 4 Page 5 of 28 2.2.2 PVNGS Emergency Plan, Rev. 6 2.2.3 ANSI N45.2.9-1974, " Requirements for Collection, Storage and Maintenar.ce of Quality Assurance Records for Nuclear Power Plants." 2.2.4 Bechtel's PVNGS Pre-evacuation Assembly Plan, Rev. 4 3.0 LIMITATIONS AND PRECAITTIONS 3.1 If a breach of security exists, Security Force personnel shall also impleoent appropriate PVNGS Security Plan Implementing Procedures. 3.2 Personnel performing critical operations such as fire fighting, assisting injured personnel, or work which if left unattended could endanger the lives or safety of personnel, do not need to j immediately report to their assembly area. However, they should do one of the following: 1 (1) Secure the operation to a safe condition as rapidly as possible and then proceed to their assembly area. (2) If the operation will take more than flye min es t ur notify the Security Shift Captain at ext. ' 3.3 All Public dddress announcements shall be made via the plant wide telephone page (phone no. 800) and the Site Warning Siren /Public Address System. . 3.4 The Security Shift Captain shall collect Appendix C from Assembly N Araa Supervisors and submit these sheets- d- "#^
'7-& L to the Emergency Planning Department for forwarding to DDC in accordance with 9N219.05.00, " Document / Record Turnover Control."
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1 CONTROLLED BY USER l PVNGS EMERGENCY PLAN o [ROCEDURE -: IMPLEMENTING PROCEDURE EPIP-20 PERSONNEL ASSEMBLY AND ACCOUNTABILITY 4 Page 6 of 28 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination / Responsibilities 4.1.1 Assembly and accountability of all onsite personnel is mandatory for an emergency classified as SITE AREA or GENERAL EMERGENCY. The Emergency Coordinator at his discretion may order assembly and accountability f,or emergencies of a lower classification. 4.1.2 The purpose of assembly is to gather together all site personnel to notify them of the emergency situation and is
' the first step in the accountability and evacuation procedures. Accountability is required to identify any missing individuals for safety and security purposes.
Evacuation is covered in EPIP-19, "Onsite Evacuation." s 4.1.3 The pri=ary method of accounting for personnel located in the
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protected area is by means of the Access Control System. This system requires use of a card-key to enter and exit the protected area and to move through various sections of the protected area. If this system is operabla, accountability may be accomplished for the protected area by means of computer printouts. If inoperable, a backup system is provided in section 4.3.13. 4.1.4 The method of accountability for all Bechtel, Bechtel Subcontractors and visitors is described in Appendix F, "Bechtel's PVNGS Pre-Evacuation Assembly Plan" and shall be implemented by'the Bechtel Field Constuction Manager. 4.1.S The method of accountability for all other personnel onsite but outside the protected area is by a sweep search to ensure that all personnel have left their normal work areas and have reported to their assembly areas. ~ 4.1.6 The Shift Supervisor (or Emergency Coordinator) is responsible for determining the need for assembly and accountability, activating the appropriate signal and providing.i= mediate instructions for assembly. 4.1.7 EACH PERSON ONSITE IS RESPONSIBLE FOR KNOWING HIS OR HER ASSEMBLY AREA AND REPORTING TO THAT AREA AS QUICKLY AS POSSIBLE. Appendix A presents a listing of the various groups at the site and their predetermined assembly creas. Appendix E presents a map of all assembly areas onsite. Pvt'04X)A ($!8D
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