ML20070V666
| ML20070V666 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/30/1982 |
| From: | Lucia S ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17297B901 | List: |
| References | |
| EPIP-14B, NUDOCS 8302170503 | |
| Download: ML20070V666 (582) | |
Text
i-Revicicn 3 PALO VERDE NUCLEAR CENERATING STATION STATION MANUAL Title Division INDEX '
j-s EMERGENCY PLAN IMPLEMENTING PROCEDURES f-INDEX f
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-'% . n L PALO VERDE NUCLEAR GENERATING STATION EMERGENCY, PLAN Emergency Plan Implementing Procedures Index Revision 3 Page 1 of 3 Procedura Fdr=er Date' Number- Number Procedure Title Rev. Effective i
EPIP-01 Emergency Organization 0 10/11/82 . -
EPIP-02 Emergency Classification 0 12/10/82 EPIP-03 UNUSUAL EVENT Implementing Actions 0 10/06/82 EPIP-04 ALERT Implementing Actions 0 10/06/82 EPIP-05 SITE EMERGENCY Implementing Actions 0 10/06/82-EPIP-06 ' GENERAL EMERGENCY Implementing Actions 0 10/06/82 EPIP-07 Notification Process - UNUSUAL EVENT 0 12/10/82
(.' EPIP-08 Notification Process - ALERT, SITE O 12/10/82 EMERGENCY or GENERAL' EMERGENCY EPIP-09 I
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EPIP-10 EPIP-ll Technical Support Center / Satellite TSC 0 10/06/82 Activation EPIP-12 Operations Support Center Activation 0 10/06/82 EPlP-13 Emergency Operations Facility Activation 0- 10/11/82 EPIP-14A Release Rate Determination 0 10/06/82 EPIP-14B Dose Assessment 1 12/23/82 EPIP-15 Protectise Action Guidelines 0 10/06/82 EPIP-16 Onsite Survey and Sampling 0 10/06/82 EPIP-17 Offsite Survey and Sampling 0 10/06/82 EPIP-18 Emergency Exposure Guidelines 0 10/16/82 EPIP-19 Onsite Evacuation 0 12/10/82 EPIP-20 lPersonnelAssemblyandAccountability 0 12/10/82 e 'O e
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PALO VERDE NUCLEAR GEMERATING STATION EMERGENCY PLAN Emertency Plan Implementing Procedures Index Revi; ion 3 -Page 2 of 3 Procedurc Former Date Number Number- Procedure Title - Rev. Effective EPIP-21' Search ard Rescue' 0 10/06/82 -
- EPIP-22 Personnel Injury 0 11/12/82 EPIP-23 Fire Fighting 0 10/06/82 EPIP-24 Security 0 11/16/82 EPIP-25 Reentry for Emergency Operations 0 10/06/82 EPIP-26 Potassium Iodine (KI) Administration 0 10/06/82
-, EPIP-27 Sample Analysis at the Station 0 10/06/82 EPIP-28 Personnel Monitoring and Decontamination 0 10/06/82.
EPIP-29 Area / Equipment Monitoring and 0 10/06/82 I:econtamination EPIP-30 l EPIP-31 Recovery 0 12/1'0/82-EPIP-32 EPIP-33 Offsite Assistance 0 12/06/82 EPIP-34 Transportation' Accidents 0 10/06/82 EPIP-35 Review, Update and Revision of the PVNGS 0 11/02/82 Emergency Plan EPIP-36 Emergency Preparedness Training 0 10/06/82 EPIP-37A Emergency Preparedness Drills 0 10/06/82 EPIP-37B Emergency Preparedness Exercises 0 11/02/82 EPIP-38 Emergency Equipment and Supplies Inventory 0 10/11/82
...- EPIP-39 Emergency Operations Director (EOD) 0 12/10/82 EPIP-40 Administrative and Logistics Coordinator 0 12/10/82 (ALC) 9 ' M e g 8
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PALO VERDE NUCLEAR GENERATING STATION 3 DIERGENCY PLAN i
Emergency Plan Implementing Procedures Incex Revision 3 3 Of 3 t' Page i Procedure
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-Former t Number Number Date '-
Procedure Title Rev. Effectivt I-EPIP-41 Radiological Assessment Coordinator (RAC) 0 12/10/82-EPIP-42 Technical Analysis Coordinator (TAC) 0 12/10/82 EPIP-43 Radiological Assessment Communicator 0 12/10/82 (RACom)
\i EPIP-44 TSC Liaison Engineer (TLE) 0 12/10/82 t
EPIP-45 Government Liaison Engineer (GLE) 0 12/10/82 EPIP-46 EOF Contact 0 12/10/82 . .
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EPIP-47
,e Logistics Communicator
- ' 0_ 12/10/82, !
EPIP-48 Security Coordinator 0 12/10/82 FPIP-49 Dosimetry Clerk b 12/10/82 EPIP-50 Status Board Keeper (SBK) 0 12/10/82 EPIP-51 Of fsits Technical Representative (OTR) 0 01/27/83 EPIP-52 ENC Technical Advisor 0 12/10/82 EPIP-53 Covernment Staffing at TSC EPIP-54 EPIP-55 TSC/ EOF Personnel Identification 0 l 12/10/82
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REVISION PVNGS EMERGENCY ORGNTIZATION O Page 2 of 29 TABLE OF CONTENTS ,
SECTION PAGE NGiBER 3
1.0 OBJECTIVE .
3
2.0 REFERENCES
4 3.0 LIMITATIONS AND PRECAUTIONS 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 4 4.3 Instructions 5 g-Ej APPENDICES Appendix A - Onshift Emergency Organization 26 Appendix B - Onsite Emergency Organization 27 Appendix C - Offsite Emergency Organization 28 Appendix D - PVNGS Emergency Organization 29 w
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PVNGS EMERGENCY PLAN QcEwaE EPIP-ol
, IMPLEMENTING PROCEDURE REVISION O Page 3 of 29 PVNGS F'ERGENCY ORGANIZATION 1.0 OBJECTIVE 1.1 To detail the fun'etions and responsibilities of personnel in the PVNGS Emergency Organization both Onshif t and Onsite including interface with the Offsite Emergency Organization.
This procedure sets forth the authority and responsibilities Furthermore, it of the Emergency Organization positions.
describes how various roles will be transferred to different personnel according to the level of emergency staffing required to respond to specific emergency classificaticas from the following emergency centers:
Control Room (CR)
Satellite Technical Support Center (STSC)
Technical Support Center (TSC)
Operational Support Center (OSC)
Emergency Operations Facility (EOF)
Emergency News Center (ENC)
Service Building (Alternate CSC)
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2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-02, "PVNGS E=ergency Classification" 2.1.2 EPIP-11, "TSC/STSC Activation" 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, " Functional Criteria for Emergency Respcase Facilities" 2.2.3 PVNGS Erergency Plan, Rev. 2 2.2.4 pvt;GS Paysical Security Plan
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PVNGS EMERGENCY PLAN [ceouse
- p. IMPLEMENTING PROCEDURE EPIP-01
'- REVISION PVNGS EMERGENCY ORGANIZATION O Page 4 of 29 3.0 LIMITATIONS AND PRECAUTIONS .
3.1 Operations personnel will perform their duties to place the plant in a safe condition as prescribed by Recovery Operations Procedures. If conflicts in personnel assignments or sequence of actions arise, first priority will be given to preserving l the health and safety of the public. &
4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination ;
4.1.1 The PVNGS Emergency Organization operates from five onsite 5 emergency centers (CR, STSC, TSC, OSC, and Service +
Building) and is supported by three offsite centers (EOF, Corporate Emergency Center (CEC), and' ENC). It is the i responsibility of the Shif t Supervisor to initially. assess l and classify the emergency and notify plant staff I personnel. For an UNUSUAL EVENT the emergency is directed from the affected unit Control Room /STSC and command of the situation remains there with the onshift Emergency Coordinator until either deescalation /close-out or reclassification to a more severe emergency level occurs.
In the event of an ALERT or more severe classification the TSC, EOF, ENC and OSC are activated. The onsite emergency corrective actions will be directed by the onsite Emergency Coordinator normally located at the TSC. The Emergency Operations Director who will be located at the EOF will provide overall direction of both the onsite tnd offsite emergency response organizaticas. The Corporate Emergency Center will be activated and fully operational
- for a SITE or GENERAL EMERGENCY classification and will provide the Emergency Operations Director and his staff with the resources (i.e., engineering, legal, financial.,
etc.) available within the APS organization.
4.2 Prerequisites 4.2.1 An incidet.; has occurred and has been classified per the provisions of EPIP-02 which requires activation of one of the following Emergency Organizations:
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- EPIP-01 REVISION PVNGS DIERGENCY ORGANIZATION 0 Page 5 of 29 4.2.1.1 NOTIFICATION OF UNUSUAL EVENT ,
o Onshift Emergency Organization (Appendix A) '
OR ,
4.2.1.2 ' ALERT, SITE EMERGENCY and GENERAL DIERGENCY o Initially Onshift Emergency Organization (Appendix A) o Subsequently, Onsite and Offsite E=ergency Organization (Appendices B and C) 4.3 Instructions 4.3.1 Onshift Emergency Organization The onshift Emergency Organization as depicted in Appendix A will be the first to be activated in response 1 to an emergency situation at PVNGS. If an ALERT or more severe emergency classification is declared the onsite Emergency Organization will be activated. Until such time that the onsite Emergency Organization is fully staffed, the onshif t Emergency Organization shall respond to the emergency as delineated in this section and in accordance with appropriate EPIP's.
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PVNGS EMERGENCY PLAN [RO 7 IMPLEMENTING PROCEDURE Epip_01-
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PVNGS EMERGENCY ORGANIZATION O Page 6 of 29 NOTE '
i In an ALERT or more severe classification, +
z the onshift response organization is q supplemented by the onsite response ~
9' organization. Thus, the Emergency i - d.
Coordinator role will be transferred from - Q the Duty Manager to the Maintenance and j' Operations Manager or his alternate, the . . .)
Technical Support Manager. Once the- -
'}j Emergency Coordinator role transfer has :4 been completed, the Duty Manager shall -
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4.3.1.1 Emergency coordinator "J. <
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The Duty Manager shall be the first individual within 1 the Emergency Organization to assume the onshif t ,~ a Emergency Coordinator role. He will be notified by d
.) the affected unit Shift Supervisor to report to the .j Control Room when an emergency condition exists. If j the Duty Manager is incapacitated, the Shif t Supervisor shall assume the responsibilities of the '
Emergency Coordinator. The Emergency Coordinator -
shall direct the utilization of APS resources during
.'a an emergency. As director of the onshift Emergency Organization he will normally be stationed in the i "d Control Room or the STSC. The responsiblities and functions of the Emergency Coordinator include: >
- a. Notifying: .
u
- 1. Company emergency response personnel;
- 2. Local noncompany emergency support groups;
- 3. Nuclear Regulatory Commission;
- 4. County and state agencies.
- b. Activating the onsite Emergency Organization for an ALERT or more severe classification. .
- The Duty Manager role can be assumed by various PVNGS management personnel. These individuals may be assigned to a " normal" emergency response role (e.g., Radiation Protection Supervisor -
Radiological Protection Coordinator.
- The responsibility for the decision to perform these items cannot be delegated.
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- c. Declaring changes in the emergency classification '
. level.
- d. Providing protective action recommendations to offsite emergency management agencies regarding evacuation, sheltering or similar protectiv'e measures (EPIP-15).
- e. Authorizing emergency workers to exceed 4000 mrem / year whole body exposure limits (EPIP-18).
- f. Determining the necessity for evacuation of nonessential personnel from the site (EPIP-19) and for evacuating personnel from onsite emergency centers.
- g. Coordinating and directing emergency operations performed by company personnel within the site boundary.
- h. Maintaining communication with offsite e=ergetcy
("') support groups.
- i. Authorizing overtime and other expenses associated with establishing and maintaining emergency response.
- j. Initiating the deployment of emergency teams as needed (i.e., Search and Rescue, Emergency Repair, Field Monitoring).
l 4.3.1.2 Shift Sups visor .
The Shif t Sr;.crvisor will be responsible for the '
initial assessment and evaluation of any abnormal or l
emergency conditions and for initial classification
. and declaration of the emergency. Additionally, his responsibilities include the following:
I l ** The responsibility for the decision to perform these items cannot be delegated.
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- a. Promptly notifying the Duty lbnager of any '
abnormal or emergency condition.
- b. Maintaining control of unit operations and mitigating accid.ent conditions from the Control Room.
- c. Assuming the responsibilities of Emergency Coordinator in the event the Duty Manager is incapacitated or otherwise unavailable.
The Shift Supervisor will report significant events and actions to the Emergency Coordinator.
4.3.1.3 Assistant Shift Supervisor During emergency conditions the Essistant Shift i Supervisor will maintain his normal duties of directing the Nuclear Operators and assisting the
.s Shift Superviser. He will continue to report to the
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Shift Supervisor. In the event of a fire he will act as Fira Team Leader.
4.3.1.4 Shift Technical Advisor (STA)
The STA will report to the STSC of the affected unit.
His responsibilities include:
- a. Advising the Shif t Supervisor on activities that are occurring, or are being planned, that may impact the safe and proper operation of the plant.
- b. Monitoring the Safety Parameter Display System
.(SPDS) in the STSC and developing trend data for Control Room personnel use/information.
The STA reports to the Shift Supervisor.
4.3.1.5 Operations Shift Personnel Operations Shift Personnel (Nuclear Operators III and II) are responsible for the safe and proper operation of the unit and will respond to abnormal and emergency conditions as necessary to mitigate such situations.
Operations Shif t Personnel will contact the Control Room and act under the direction of the Shift Supervisor.
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REVISION PVNGS EMERGENCY ORGANIZATION O Page 9 of 29 4.3.1.6 Radiation Protection Monitor ,
This position will be filled by a Radiation Protection Technician from the affected unit's shift complement.
The Radiation Protection Monitor is stationed at the STSC and reports to the E=ergency Coordinator. His responsibilities include: -
- a. Initial onsite and offsite dose projections.
- b. Initial direction of onsite and offsite Field Monitoring Teams.
- c. Provision of technical advice (i.e. , onsite radiation levels, radiation exposure criteria, etc.) to the Emergency Coordinn tor.
In an ALERT or more severe classification, the Radiation Protection Monitor will be relieved of the
.-s
- responsibility for directing Field Monitoring Teams s' ) and projecting doser by the Radiological Protection
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. Coordinator (on arrival at the TSC). He will reasin in the STSC and conitor the radiological assessment activities being performed in the TSC and keep the-Operations Advisor apprised of the situation.
4.3.1.7 Operational Support Center (CSC) Coordinator This position will be initially assumed by the Shif t Maintenance Fore =an whL will report directly tof the Ecergency Coordinator. The OSC Coordinator 'is stationed at the OSC where his responsibilities and ,
functions include:
- a. Coordination of ~=anpower resources available at
! the OSC.
- b. Deployment of 3mergency teams (i.e., Search and Rescue, E=ergency Repair, Field Monitoring) on direction from the Emergency Coordinator.
, In the evant of an ALERT or more severe classification, the Shif t Maintenance Foreman will be relieved by the designated OSC Coordinator of the onsite Energency Organization. He will then remaia in the OSC and act as Repair Coordinator.
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This position will oc initially assumed by the Shift Systems Engineer whose normal work station is in the Maintenance Control Center (located in the TSC). The >
Technical Engineering Coordinator reports directly to ,'
the Emergency Coordinator and is responsible for:
- a. Providing technical input to the Control Room staff. 3 y
- b. Physically activating the TSC in accordance with ,j-EPIP-ll when an ALERT or more severe emergency y classification is declared. d
- A In the event of an ALERT or more severe cle.ssification U level, the Shif t Systems Engineer' will be relieved by it the designated Technical Engineering Coordinator of d the onsite Emergency Organization. Once the Shift :
Systems Engineer has been relieved of the Technical y
-3
\ t Ecgineering Coordinator function, he and the onshift H' Analysts (see Section 4.3.1.9) will fill the position "
of Systems Engineers assisting the Emergency Maintenance Coordinator in the TSC.
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4.3.1.9 Analysts These positions will be filled by Maintenance ?
Planner - Coordinators. The Analysts will report to the TSC and assist the Shif t Systems Engineer in ,
4 l carrying out his function as Technical Engineering J
Coordinator. When the onsite Emergency Organization j is activated, these individuals will assume the roles -
l of Systems Engineers and report to the Emergency l
Maintenance Coordinator at the TSC. 1 4.3.1.10. Security Director This position will be initially assumed by the Security Shift Captain. To ensure that PVNGS security is maintained the Security Shift Captain will assign a
! Security Shift Sergeant to the responsibilities of the Security Shift Captain at the Security Building. The Security Director is stationed at the TSC where his l
responsibilities and functions include:
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. IMPLEMENTING PROCEDURE REVISION PVNGS EMERGENCY ORG NIZATION O Page 11 of 29
- a. Directing the onsite security force in the functions of personnel accountability and s'ite access Control.
- b. Maintaining station security and implementing security contingency measures as appropriate per the PVNGS Physical Security Plan.
- c. Calling out station emergency response personnel at the direction of the Emergency Coordinator in accordance with EPIP-07 and EPIP-08, as appropriate to the emergency classification.
The Security Shif t Captain acting as the Security Director reports directly to the Emergency Coordinator and will be relieved by the designated Security Director of the onsite Emergency Organization. Upon transferring this function, the Security Shift Captain will assu=e his emergency duties in the Security
, . Building.
4.3.1.11 Security Force Security personnel located at the Central Alarm Station, Secondary Alarm Station, and other fixed posts shal" maintain their positions unless otherwise directed by the Security Directcr. Other Security Force members will report to the Security Director for further instructions.
4.3.1.12 Maintenance Technicians Maintenance Technicians (mechanical, electrical and I&C) will report to the OSC and are responsible for performing emergency maintenance repair and/or corrective actions as coordinated by the OSC j
i
. Coordinator. They will be members of emergency teams
! as specified in Section 4.3.1.16.
4.3.1.13 Chemistry Technician The Chemistry Technician will report to the OSC and is responsible for performing post-accident chemistry samples and analyses and other plant chemistry supporting operations as coordinated by the OSC Coordinator.
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PROCEDURE PVNGS EMERGENCY PLAN NO.
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- REVISION PVNGS EMERGENCY ORGANIZATION -
0 Page 12 of 29 4.3.1.14 Radiation Protection Technician .
Radiation Protection Technicians in the onshif t Emergency Organization, with the exception of the Radiation Protection Monitor (see Section 4.3.1.6),
will report to the OSC and are responsible for '
radiological controls support such as access control, personnel monitoring, and radiological monitoring.
Additionally, Radiological Protection Technicians may be assigned as members of emergency teams as specified in Section 4.3.1.16.
4.3.1.15 Satellite TSC Communicator The Emergency Coordinator shall designate a Nuclear Operator to act as STSC Communicator. The responsibilities of the STSC Communicator are:
- a. Upon direction from the Emergency Coordinator,
,, commence initial notifications in.accordance with EPIP-07 and EPIP-08, as appropriate to the
( "} emergency classification.
- b. Maintain records of communications received from or transmitted offsite.
In the event the onsite Emergency Organization is activated (e.g. , ALERT or more severe classification),
the Nuclear Operator filling this role will be relieved by the designated STSC Communicator.
4.3.1.16 Emergency Teams ,
Emergency teams (Search and Rescue, E=ergency Repair, First-Aid, Field Monitoring) will be formed from Emergency Response Shif t Personnel assemblad at the OSC. At a minimum, personnel assembled at the OSC
. include:
1 Radiation Protection Technician 1 Chemistry Technician 2 Mechanical Maintenance Technicians 1 Electrical Maintenance Technician 1 I&C Maintenance Technician E=ergency teams are formed by the OSC Coordinator at Ls,e the direction of the Emergency Coordinator and will perform duties as follows:
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- a. Search and Rescue Team ,
A Search and Rescue Team will consist of at least two members, with at least one member being a Radiation Protection Technician. Members of a Search and Rescue Team will, as a minimum, be first-aid trained and Radiation Exposure Permit .
(REP) qualified and will constitute the First Aid Team when required. Search and Rescue Team members will report to the OSC Coordinator when
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the onshif t Emergency Organization exists. Upon activation of the onsite Emergency Organization, the Search and Rescue Team will report to the Hazards Control Coordinator, who is located in the TSC.
- b. Emergency Repair Team The Emergency Repair Team will consist of at least
/ two Maintenance Technicians. If radiological
" _, 3 conditions necessitate, a Radiation Protection Technician will also be assigned to the team. The Emergency Repair Team will initially report to the OSC Coordinator. When the onsite Emergency Organization is activated, the Emergency Repair Team will report to the Repair Coordinator, who is located in the OSC.
- c. Field Monitoring Team A Field Monitoring Team will be formed by the OSC Coordinator upon request from the Radiation .
Protection Monitor or Radiological Protecton Coordinator. This Team will perform onsite and/or offsite monitoring activities. Thd Team will consist of at least two members, with at least one
. member being a Radiation Protection Technician.
The Field Monitoring Team will report to and take direction from the Radiation Protection Monitor until he is relieved of this responsibility by the Radiological Protection Coordinator in the onsite Emergency Organization.
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IMPL'iMENTING PROCEDURE EeIP-01 REVISION PVNGS E!!ERGENCY ORGANIZATION O Page 14 of 29 4.3.1.17 Fire Team ,
The Fire Team will consist of assigned shif t personnel (the Assistant Shift Sup visor, two Nuclear Operators, one Radiation Protection Technician, and one Chemistry Technician). The Fire Team will report to the Assistant Shift Supervisor who will be the Fire Team Leader. The Fire Team will respond to fire alards and will respond at the location of the fire with assigned equi.) cent to combat the fire and to assess the need fer offsite assistance.
4.3.2 Onsite Emergency Orga>1zation The Z:ergency Coordinator of the onshift Emergency Organization will order the activation of the onsite Emergency Organization (as depicted in Appendix B) when an ALERT or more severe classification level is declared.
The onsite E=ergency Organization positions will be manned as soon as possible (generally within 90 minutes)
(, I following such a declaration. The activation of the onsite Emergency Organization substantially enhances the station's ability to deal with emergencies by focussing greater manpower resources on the situation.
The primary function of the onsite E=ergency Organization will be to manage the emergency by:
- a. Diagnosing plant conditions.
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- b. Ide;.tifying and implementing corrective actions.
- c. Coordinating onsite emergency activities.
I d. Directing protective action for station personnel.
- e. Cot =unicating with offsite agencies until the Emergency Operations Facility (EOF) is activated.
Specific functional assignments within the onsite r
E=ergency Organization are listed in the following i sections.
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EPIP-01 REVISION PVNGS EMERGENCY ORGANIZATION O Page 15 of 29 4.3.2.1 Emergency Coordinator .
Af ter being notified and following arrival onsite, the Operations and Maintenance Manager or his alternate (Technical Support Manager) will be briefed on plant conditions and the status of the emergency by the onshift Emergency Coordinator (Duty Manager).
Following this briefing the Operations Maintenance Manager will relieve the Duty thnager of his duties
- as Emergency Coordinator and will assume management control of the onsite Emergency Organization. The functions and responsibilities of the onsite Emerg.ncy Coordinator in addition to those assumed f rom the onshift E=ergency Coordinator (see Section 4.3.1.1) are:
- a. Manage operations in the TSC. This includes collecting and analyzing the technical information necessary for assessment of plant operational f'~ s aspects, providing technical counsel to support
( / the Control Room, assessing radiological release potential, monitoring onsite exposure and contamination control, repairing plant co=ponents or systems as required by the emergency and/or consequences, and maintaining onsite personnel accountability.
- b. . Provide management direction to the Control Room through the Operations Advisor.
- c. Provide =anagement direction to the Operational Support Center through the Operational Support Center Coordinator.
- d. Assign plant staff personnel to positions in the onsite Emergency Organization as appropriate.
- e. Request assistance as necessary for onsite radiation monitoring from federal agencies, either directly or through the county / state emergency response organization once established.
- When the EOF is activated the Emergency Operations, Director assumes the following nondelegable responsibilities: (1) communicating plant
(' ,
status updates and radiological release data to NRC/ FEMA, county / state, EOC personnel and (2) making protective action recommendations to offsite emergency management authorities.
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This position will be filled by the Radiation Protection Supervisor, his alternate will ta a Radiological Engineer. The Radiological Protection.
Coordinator is stationed at the TSC, where his responsibilities and functions include: ,
- a. Relieving the Radiation Protection Monitor of the responsibility for overall control and direction of onsite and offsite field monitoring, and for plant radiological controls.
- b. Providing direction to the Radiological Protection Support Staff at the OSC in matters pertaining to plant radiological controls.
- c. Providing technical advice to the E=ergency Coordinator on radiological aspects of onsite
-> emergency activities.
- d. Supervising dose rate projection activities at the TSC.
- e. Providing technical advice to the Ecergene.y Coordinator and/or the Radiological Assessment Coordinator concerning recom=endations for offsite
-protective actions based on the results of dose projections.
l f. Evaluating the need for the administration of l Potassium Iodide to PVNGS personnel per'EPIP-26.
- g. Evaluating conditions requiring emergency ,
j radiation exposure.
- h. Directing the decontamination of PVNGS personnel
.and equipment.
l
- 1. Providing radiological update status to the Radiological Assessment Coordinator in the EOF.
I l The Radiological Protection Coordinator reports to the E=ergency Cocrdinator.
- Support provided for the Radiological Protection Coordinator includes:
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- 1. Field Team Communicator .
The Field Team Communicator, located in the TSC, will handle direct radio communications with PVNGS onsite and offsite Field Monitoring Teams. He
, will assist the Radiological Protection Coordinator by performing onsite and offsite radiological dose rate projections. He will
_ r'eport to and take direction from the Radiological Protection Coordinator.
- 2. Field Monitoring Team (s)
(Perform as described in Section 4.3.1.16.c).
4.3.2.3 Technical Engineering Coordinator
. This position will be filled by the Engineering Manager, his alternate will bc the Operations
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Engineering Supervisor. The Technical Engineering
- Coordinator is stationed at the TSC where his functions and responsibilities include:
- a. Relieving the onshift Technical Engineering l Coordinator following a briefing concerning plant status and conditions.
- b. Directing engineering, system analyses, procedures i development, and related licensing efforts I concerning the e' ergency.
- c. Providing updated status of the reactor and the unit to the Technical Analysis Coordinator in the EOF.
- d. Maintaining liaison with offsite technical support, such as NSSS supplier, A-E, NSAC, EPRI, and INPO.
The Technical Engineering Coordinator reports to the Emergency Coordinator. His support staff in the TSC will consist of the following: -
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- 1. Computer Support Coordinator '
F.'i . .
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Provides continuous operations (hardware and !F.i software) for support of analyses related to plant conditions and dose assessy.nt. This position j}.
will be filled by the Computer Supervisor. His alternate will be a Computer Engineer.
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- 2. Chemistry Coordinator y-]i C.
bd Provides evaluation of coolant samples to aid in ;d diagnosing reactor core conditions and release 49>
potentials and interprets results of chemical hj analyses for evaluation of plant systems. Thia ir position will be filled by the Chemistry hl Supervisor. His alternate vill be a Chemist.
- d . .
?-
- 3. Reaetor Analyst Pq
,nt., r .
Performs detailed analyses of ccre physics and j heat transfer parameters to assess reactor core ?J status and to evaluate the integrity of reactor W
- ' coolant pressure boundary and fuel cladding. This Li position will be filled by the Nuclear Supervisor. %
4.3.2.4 Emergency Maintenance Coordinator l'.
This position will be filled by the Maintenance i';'
Superintendent. His alternate will be the Maintenance ."
Control Center Supervisor. The Emergency Maintenance. -
Coordinator is stationed at the TSC, where his functions and responsibilities include:
- a. Relieving the onshift OSC Coordinator of overall
- l responsibility for emergency plant repair. .
l '
l b. Coordinating repair and damage control for plant ;
l systems including mechanical, electrical, and (-
instrument and control equipment. *3 i J
' c. Advising the Emergency Coordinator on matters 3 which deal with repair, maintenance, and h j deployment of Emergency Repair Teams. N
- d. Directing the OSC Coordinator to assemble and ..'.
dispatch Emergency Repair Teams. -
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PVNGS EMERGENCY PLAN gesouse IMPLEMENTING PROCEDURE EPIP-01 REVISION PVNGS EMERGENCY ORGANIZATION O Page 19 of 29
- e. Assessing mechanical operation of various plant systems and equipment.
- f. Maintaining liaison with the Administrative and Logistics Coordinator in the EOF in matters pertaining.to manpower support.
The Emergency Maintenance Coordinator reports to the Emer'gency Coordinator. His support staff will consist of the following:
- 1. Systems Engineers These positions will be filled by Maintenance Planner-Coordinators. The Systems Engineers will recommend courses of action for emergency repairs and provide possible alternatives for maintenance operations. The Systecs Engineers will be stationed in the TSC to enhance the level of j
direct support available to the Emergency s
Maintenance Coordinator.
- 2. Mechanical Coordinator This position will be filled by the Mechanical Maintenance Supervisor. His alternate will be a Mechanical Systems Engineer. The Mechanical Coordinator will determine and recommend repair / damage control and corrective actions for plant mechanical, HVAC and piping systems. He l
will report directly to the Emergency Maintenance Coordinator and will be stationed with a Mechanical Technician at the Eervice Building to facilitate access to tools and plant system schematics.
- 3. Electrical Coordinator This position will be filled by the Electrical Maintenance Supervisor. His alternate will be an
! Electrical Systems Engineer. The Electrical
- Coordinator will deter =ine and recommend repair / damage control and corrective actions for plant electrical systems. He will report directly to the Emergency }hintenance Coordinator and will s be stationed with an Electrical Technician at the Service Building.
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[RCCEDURE IMPLEMENTING PROCEDURE EPIP-01 REVISION PVNGS EMERGENCY ORGANIZATION O Page 20 of 29
- 4. Instrument and Control Coordinator ,
This position will be filled by the I&C Supervisor. His alternate will be an I&C Systems Engineer. The I&C Coordinator will determine alternative I&C capabilities or configurations, and direct the repair / installation / modification of .
instrument and control equipment. The I&C Kaintenance Supervisor will report to the Emergency Maintenance Coordinator and will be stationed with an I&C Technician at the Service Building.
In the event the Service Building becomes uninhabitable, personnel ordinarily stationed there shall report to the TSC.
4.3.2.5 Hazards Control Coordinator r ', This position will be filled by the Safety Administrator. His alternate will' be a Safety Engineer. The Hazards Control Coordinator is stationed at the TSC, where his functions and responsibilities include:
- a. Advising the Emergency Coordinator on matters concerning the safety of plant personnel during the emergency.
- b. Directing the OSC Coordinator in the assembly and dispatch of Search and Rescue Teams.
l c. Evaluating the hazards of toxic material release l and/or chemical spills, should such an event occur or appear imminent.
l d. Providing technical advice to the Fire Team Leader should a fire be the cause of, or occur, during an i
I emergency.
l l The Hazards Control Coordinator reports to the Emergency Coordinator.
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PVNGS EMERGENCY PLAN Qcecuns IMPLEMENTING PROCEDURE EPIP-01 REVISION PVNGS EMERGENCY ORGANIZATION O Page 21 of 29 1:
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4.3.2.6 Personnel Resources Coordinator ,
This position will be filled by the Administrative ,s Services Manager. His alternate will be the Office 4( -
Supervisor. The Personnel Resources Coordinator will be stationed in the TSC where his functions and II responsibilities include- hl '
3.],
- a. Eclieving the Security Director of the function of J.
calling out additional emervncy response Q peraonnel (at the direction or the Ecergency *
'S-Coordinator). J.
- b. Planning for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> emergency response
..)
yI organization staffing throughout the course of the emergency. i.]
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- c. Assessing the need for, and assisting the OSC >
Coordinator in meeting the manning requirements of the OSC. [ll3
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The Personnel Resources Coordinator reports to the :[:) '
Emergency Coordinator. .Q
]$
4.3.2.7 OSC Coordinator ]
..il This position will be filled by the Day Shift '@
Supervisor. The OSC Joordinator is stationed in the j OSC where his functions and responsibilities include: .s
- a. Relieving the Shift Maintenance Fore =an of his 1 responsibilities as onshift OSC Coordinator.
- b. Functionally supervising the OSC. l
- c. Coordinating manpower resources available at the 3 l OSC. '
i
- d. Assembling and dispatching e=ergency teams :. 3 (i.e. , Search and Rescue, First-Aid, Emergency I' Repair, or Field Monitoring) at the direction of .$,
l the Hazards Control, Ecergency Maintenance, or .
0 '#i
'/ '
Radiological Protection Coordinator respectively. -
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IMPLEMENTING PROCEDURE EPIP-01 REVISION PVNGS EMERGENCY ORGANIZATION O Page 22 of 29 The OSC Coordinator reports to the Personnel Resources Coordinator and is assisted by the:
- 1. Repair Coordinator This position will be filled by a Shift.
Maintenance Foreman. Tha Repair Coordinator will -
be responsible for ensuring that maintenance technicians and Emergency Repair Teams are dispatched at the direction of the Emergency Maintenance Coordinator. The Repair Coordinator will be stationed at the OSC with Maintenance Technicians and will report to the OSC Coordinator.
Additional personnel resources available at the OSC and coordinated by the OSC Coordinator include:
- 1. Chemistry Support Staff The Chemistry Support Staff will be responsible for taking and analyzing post-accident samples according to procedures and providing chemistry support as directed by the Chemistry Coordinator.
- 2. Radiological Protection Support Staff The Radiological Protection Support Staff will be dispatched at the direction of the Radiological Protection Coordinator to conduct onsite/offsite radiation surveys. The Radiological Protection Support Staff will also be available for dispatch with Search and Rescue, Emergency Repair Teams and the Fire Team (as required).
- 3. Emergency Teams Emergency teams will be assembled and act in accordance with Section 4.3.1.16 of this procedure.
4.3.2.8 Security Director This position will be filled by the Manager of Operations Security. His alternate will be the Operations Security Supervisor. The Security Director will be stationed at the TSC, where his responsibilities include:
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- a. Relieving the Security Shift Captain of his ~
responsibilities as onshift Security Director.
- b. Maintaining plant security and implementing security contingency measures as appropriate per the PVNGS Physical Security Plan.
- c. Calling out emergency response personnel, until relieved of this responsibility by the Personnel Resources Coordinator.
- d. Directing the. onsite security force in personnel accountability, evacuation, access control, and '
personnel and equipment security control.
- e. Coordinating the movement, cicarance, and badging of Emergency Response Personnel entering the
. station to provide emergency support.
The Security Director reports to the Emergency l
\'s Coordinator and is assisted by the~ Security Force as !
described in Section 4.3.1.11.
4.3.2.9 Operations Advisor This position will be filled by the affected unit Operations Supervisor. His alternate will be an Operations Supervisor from an unaffected unit. The Operations Advisor will be the management liaison to the Control Room and will be stationed at the
! Satellite TSC where his functions and responsibilities l include:
- a. Providing technical and operational advice to the
, Shift Supervisor.
l l b. Acting as an interface to maintain the flow of
-information between the TSC and Control Room.
- c. Analyzing conditions (via the SPDS and Chemical and Radiological Analysis Computer System (CRACS))
l and develop.ing guidance for the Emergency Coordinator and Operations personnel.
- d. Assisting in the development of emergency operating and other procedures, as necessary for conducting emergency operations.
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PVNGS EMERGENCY PLAN PROCEDURE, no.
IMPLEMENTING PROCEDURE EPIP-01 REVISION PVNGS EMERGENCY ORGANIZATION O Page 24 of 29 The Operations Advisor reports to the Emergency -
Coordinator. His support staff consists of the following:
- 1. Radiation Protection Monitor This position will be filled by a Radiation - -
Protection Technician. The Radiation Protection Monitor will monitor onsite and offsite radiation dose projections in the Satellite TSC. He will maintain coc=unication with the Radiological Protection Coordinator at the TSC and will keep the Operations Advisor apprised of the onsite and offsite radiological conditions. The Radiation Protection Monitor will be stationed in the Satellite TSC and will report directly to the Operations Advisor.
- 2. Satellite TSC Communicator 5
This position will be filled by a Nuclear Operator II. The onsite Satellite TSC Co==unicator will maintain the con =unications link for the Operations Advisor with the Emergency Coordinator in the TSC. He will relieve the Nuclear Operator II in the onshift emergency organization. He will be stationed in the Satellite TSC, reporting directly to the Operations Advisor.
4.3.2.10 Shift Sapervisor
- The' Shif t Supervisor will continue to be responsible for control of unit operations, assessing unit operational aspects, and implementing corrective actions to mitigate the consequences of an emergency, as described in Section 4.3.1.2 . The Shift Supervisor reports to the Emergency Coordinator and will direct the activities of shift operating personnel as listed below:
- 1. Assistant Shif t Supervisor Functions and responsibilities as described in Section 4.3.1.3.
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PVNGS EMERGENCY ORGANIZATION 0
- 2. Shift Technical Advisor , .
Functions and responsibilities as described in Section 4.3.1.4.
- 3. Operations Shift Personnel (Nuclear Operators III and II). . .
~
Functions and responsibilities as described in Section 4.3.1.5.
4'. Fire Tean Functions and responsibilities as described in Section 4.3.1.17.
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REVISION DIERGENCY CLASSIFICATION O Page 2 of 30 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 3
~
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites '
6 4.3 Instructions 6 f:h
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- APPENDICES Appendix A - Emergency Classification Flowchart 10 Appendix b Energency Classification Check List 11 Appendix C - Criteria for Emergency Classification 12 Appendix D - Emergency Action Levels (EAL's) 13
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_ REVISION EMERGENC'Y CLASSIFICATION O Page 3 of 30 1.0 OBJECTIVE 1.1 To provide a means of classifying an event at PVNGS into one of the four emergency classifications as described in PVNGS Emergency Plan.
2.0 3EFERENCES 2.1 implementing References 2.1.1 Recovery Operatione Procedures 2.1.2 PVNGS Emergency Plan, Rev. 2, Section 5 " Emergency Conditions."
2.1.3 EPIP-31, " Recovery" 2.2 Dev'elopmental Refererces T_
' ~
' 2.2.1 NUREG-0654, Rev. 1, Appendix 1, " Criteria for Preparation and Evaluation of Radiological Emergency Respouse Plans and Preparedness in Support of Nuclear Power Plants" 3.0 LIMITATIONS AND PRECAUTIONS 3.1 This procedure will not take pricrity over the measures required to maintain or restore the plant to a safe condition. Prompt notification of offsite authorities should be given.within 15 minutes of declaration of a particular emergency classification. This time is measured from when the Shif t Supervisor declares a particular emergency class and notifies the Duty Manager.
3.2 Continued surveillance and assessment of plant conditions is necessary to ensure that the emergency classification is appropriately revised as conditions change, or as more information is obtained.
3.3 This emergency procedure does not replace any plant operating procedures. During an emergency condition continue to use the appropriate plant procedure in parallel to this and other
... Emergency Plan Implementing Procedures (EPIP's).
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%' REVISION EMERGENCY CLASSIFICATION O Page 4 of 30 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 4.1.1 Introduction to the Modular Concept 4.1.1.1 The Basic Module -
- a. Four emergency classifications have been established. The classes are:
- 1. NOTIFICATION OF AN UNUSUAL EVENT
- 2. ALERT
- 3. SITE EMERGENCY
- 4. GENERAL EMERGENCY
- b. The rationale for these classes is to provide
, early and prompt notification of minor events (the
' " Basic Module Events") which could lead to more.-
g serious consequences, or which might.be indicative ~
._j of more serious conditions which are not yet fully realized. A system of " modules" has been provided to ensure more effective response preparation for more serious indicators.
- c. The Basic Modules are abnormal conditions considered to be the initiating events upon which energencies discussed within the Emergency Action Levels are based.
j d. Prompt recognition of the occurrence of one or more of the initiating events of the Basic Module may prevent the sitaation from progressing to either a NOTIFICATION OF UNUSUAL EVENT category or an energency classification of greater severity.
- e. The 13 Basic Module events as depicted in Appendix A are: -
- 1. Unplanned or unanticipated change in radiation levels, or release of gaseous effluent.
- 2. Fuel handling a.ccident.
. 3. Indications leading to or actual loss of c(._/ -
fission product barrier.
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- 4. Steam lins break or main steam safety or relief valve failures.
~5. Primary reactor coolant leak, primary to
' secondary leakage, or pressurizer safety or relief valve failure.
- 6. Loss of power or alarms.
- 7. Loss of feedwater.
- 8. Other limiting conditions for operations.
- 9. Reactor Protection System failure.
- 10. Control Room evacuation.
- 11. Fire. -
,- w, 12. Nattiral phenomena and other hazards.
( .
- 13. Security threat.
- f. As shown in Appendix A, an emergency (initiating condition) may progress to a particular emergency classification as a result of a combination of one or more of the Basic Module events. In most instances, these elements of the Basic Module will advance to the category of a NOTIFICATION OF UNUSUAL EVENT, and, with continued degradation, could escalate to the more severe classes of j ALERT, SITE DIERGENCY, or GENERAI. DIERGENCY.
- g. As shown in Appendix A, each of the four classes of an emergency is indicative of nine or = ore sets of initiating conditions.
- h. The events within each class are either identical '
to, or are slight modifications of, those that l
exist in Section 5 of the PVNGS Emergency Plan.
What the "modularized" system denotes is a graphic l
t-reproduction of Tables 5.1-1 through 5.1-4. This module format yields three important advantages.
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- 1. It affords prompt recognition of an emergency condition and an indication of its severity as defined by the Emergency Action Levels.
- 2. Prompt recognition leads to prompt action as i well as an accelerated process of initial :
notification and activation of onsite and [
offsite agencies.
- 3. It enables reactor operations personnel to l-effectively move through the recovery procedures and into the EPIP's.
- 1. The utilization of the " modular" approach in assessing a radiological accident, affords greater probability of responding to a potentially hazardous occurrence in a more timely manner.
. 4.1.2 Responsibility .
([')
U-4.1.2.1 The Shift Supervisor has the responsibility to initially classify an event into one of the four emergency classifications and to notify the Duty Manager.
l 4.1.2.2 The Emergency Coordinator (initially the Duty Manager or Shift Supervisor, if Duty Manager is unavailable or incapacitated) has the responsibility to implement the Emergency Plan and for subsequent reclassification of the emergency.
1 4.2 Prerequisites 4.2.1 A Recovery Operations Procedure has been initiated which warrants activation of the Emergency Plan.
4.2.2 An unusual condition exists at or near PVNGS which appears
- to warrant activation of 'the Emergency Plan.
4.3 Instructions 4.3.1 Off Normal Plant Condition 4.3.1.1 At any time the plant condition is off normal', the
,, Shif t Supervisor will perform the following:
~. J.
Pv2?6 000A (9.82)
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PVNGS EMERGENCY PLAN PROCEDURE N O.
- n. IMPLEMENTING PROCEDURE EPIP-02 e .
Gl REVISION EMERGENCY CLASSIFICATION O Page 7 of 30
- a. Notify the Duty Manager to report to the affected unit Control Room.
- b. Evaluate the situation and determine if corrective actions are required to place the plant in a stable and safe condition.
- c. Organize the onshift staff to take actions to maintain or return tc a safe plant condition.
- d. Classify the event in accordance with Section 4.3.2. If an Emergency Plan classification is not immediately evident, notify unaffected units and shif t personnel that an off normal plant condition exists. ,
4.3.2 Classification NOTE If )
' If conditions are established such that it is difficult to determine specific classification, classify the incident at the most conservative (i.e., more severe) level.-
4.3.2.1 Normally the classification guidance contained in the appropriate Recovery Operations Procedure will be used to determine the initial emergency classification. In the event none of the Recovery Operations Procedures are appropriate to the situation, the Shift Supervisor / Emergency Coordinator shall classify the incident in sccordance with the following steps.
4.3.2.2 Shif t Supervisor / Emergency Coordinator select affected module (s) on Emergency Classification Flowchart (Appendix A) and then follow horizontally across to the actual event to recognize the appropriate emergency classification.
l l 4.3.2.3 If Appendix A proves to be inadequate for determining I
a particular emergency classification, the Shift l Supervisor /Ecergency Coordinator shall refer to the Emergency Action Levels (Appendix D) and select the s appropriate emergency classification based on this i
_) review.
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1 PVNGS EMERGENCY PLAN Q cewac m IMPLEMENTING PROCEDURE EPIP-02
) REVISION EMERGENCY CLASSIFICATION O Page 8 of 30 4.3.2.4 Shift Supervisor / Emergency Coordinator record the date/ time of initial classification, as determined from 4.3.2.1, 4.3.2.2, or 4.3.2.3 above, on the Emergency Classification Check List (Appendix B).
NOTE If there is an~ uncontrolled release occurring, the Chemical.and Radiological Analysis Computer System (CRACS) will project an emergency classification based on release data and dose rate projections.
4.3.2.5 Based on the classification of the emergency, the Emergency Coordinator shall initiate the appropriate ~
Emergency Plan Implementing Procedure (EPIP) as follows:
- a. NOTIFICATION 0F UNUSUA'L EVENT Implementing- -
.--)
V Actions,- EPIP-03
- b. ALERT Implementing Actions - EPIP-04
- c. SITE EMERGENCY Implementing Actions - EPIP-05
- d. GENERAL E4ERGENCY Implementing Actions - EPIP-06 4.3.3 Reclassification 4.3.3.1 An emergency may escalate to a higher classification as station conditions worsen or additional abnormal station conditions arise. This could also happen as a result of a combination of two or more of the Basic Module events.
4.3.3.2 An emergency may be initially classified at one level and, upon further investigation or af ter corrective actions, may be reclassified to a less severe class of e=ergency.
4.3.3.3 If the Emergency Coordinator determines that reclassification is necessary he shall perform the following:
- a. Repeat the classification steps of 4.3.2 above, recording information in,the appropriate reclassification column of '
Appendix B.
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- PV2500CA (8 82)
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PVNGS EMERGENCY PLAN Qcewas
.m IMPLEMENTING PROCEDURE EPIP-02 j REVISION
'ESERGENCY CLASSIFICATION O Page 9 of 30
- b. Discuss plant status and reclassification with the following individuals depending upon the emergency class:
- 1. SITE or GENERAL EMERGENCY - Energency Operations Director, Operations Advisor, Radiation Protection Coordihator, and Technical Engineering Coordinator.
- 2. ALERT - Radiation Protection Coordinator, Operations Advisor, and Technical Engineering Coordinator. .
- 3. UNUSUAL EVENT - Shif t Supervisor and Radiation
, Protection Monitor.
- c. If the event is reclassified (either upward or downward) direct a plant' operator to announce the status of the emergencj over the PA. system and
- SD insure the appropriate.EPIP is implemented.per, .
%' Section 4.3.2.5.
- d. If the event is reclassified such that plant status conditions fall within the following guidelines implement EPIP-31.
o Radiation levcis are stable or decreasing with time.
o Releases of radioactive materials to the
' environment have ceased or are controlled within permissible license limits.
o Fire, flooding, or similar emergency conditions no longer constitute a hazard to the plant or station personnel.
o Measures have been successfully instituted to correct or compensate for malfunctioning equipment.
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- Rev 0 Page 1 of 1 IT1 n
- Page !! of 30 gw CIASSIFICATION CHECK LIST E!
o m@ INITIAL CLASSIFICATION UE, ALERT. SITE. CUJERAL 4 2 ITI - CA1TCORY DATE/ TIME RECI.ASSIFICATION RECLAS$1FICATICN RECIASSIFICATION n b DATE/flHE DATE/ TIME g$ N
- 1. Unplanned or unant scipated change DATE/ TIME In radiation levels. or release of raJIetog' cal liquid or gaseous ui g OO eifluent.
/ / /
N H TN
- 2. /uel handling accident.
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- 3. 'InItcations leading to or actual _
_/__ _/ H b loss of fission product barrier. ma _/ /
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- 4. Steam Itne break or main steam
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gp safety or rettei valve fat ture. /_ _/ / S. Primary reactor coolant leak,
/
/_ /
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, valv. istture. / _ _/ /_ / / /_
- 6. Loss of power or alarms.
/ /_
/ /_ / / / /
- 7. t.oa. or feeduater. / /
./ / /
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- 8. Other ItattIng conditions for / /- /- / O 21 r+erations.
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- 9. Reactor Protection System failure.
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- 10. Control sous evacuattou. / /
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- 15. Elte.
/* /.. .,_ / / / /
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- 12. Natural phenomena and other h*Entd**
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- 13. Security threat.
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX C m . IMPLEMENTING PROCEDURE EPIP-02 Page 1 of 1 REVISION EMERGENCY CLASSIFICATION O Page 12 of 30 CRITERIA FOR EMERGENCY CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT Unusual events 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 offsite response or contioring are expected unless further degradation of safety systems occurs. Purpose of offsite notification is to (1) assure that the first step in any response later found to be necessary has been carried out, (2) bring the operating staff to a state of readiness, and (3) provide systematic handling of unusual events information and decisionmaking. ALERT Events are in progress or have occurre'd wb'.cn involve an actual or potential sub-stantial degradation of the level of safet7 of the plant. faly releases expected to be limited to small fractions of the EPA Ptotective Action Guideline exposure levelse Purpose of offsite alert is to (1) assure that emergency personnel are readily available to respond if situation becomes nore serious or to perform confirmato'ry radiation monitoring if required, and (2) provide offsite authorities current status information. SITE EMERGENCY Events are in progress or have occurred which involve actual or likely major failurec of plant functions needed for protection of the public. Any releases not expected to l exceed EPA Protective Action Guidelines exposure levels ,except near site bcundary. Purpose of the site area emergency d claration is to (1) assure that response centers are manned,,(2) assure that mor' *eams are dispatched, (3) assure that personnel required for evacuat A r-site areas are at duty stations if situation becomes more seriou: ide consultation with offsite authorities, and (5) provide updates for the , -- through offsite authorities. GENERAL DIERGENCY Events are in progress or have occurred which involve actual or imminent 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. I Purpose of the general emergency declaration is to (1) initiate predetermined protective actions for the public, (2) provide continuous assessment of information from licensee and offsite organization measurements, (3) initiate additional measure; as indicated by actual or potential releases. (4) provide consultation with offsite authorities and (5) provide updates for the public through offsite authorities. PV2'6 0CCA & 8b . L
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D m IMPLEMENTING PROCEDURE EPIP-02 Page 1 of 18 t REVISION EMERGENCY CLASSIFICATION O Page 13 of 30 EMERGENCY ACTION LEVELS (EAL'S) NOTIFICATION OF UNUSUAL EVENT i PALO VERDE NUCLEAR GENEPATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 1. Safety Injection System 1. HPSI pump running annunciator; actuation. various safety equipment status system panel indications.
- 2. Radiological effluent 2. In accc.-lance with Technical technical specification Specification Section 3/4.3.3, limits exceeded. Radiolo~gical Effluent Process Monitors SQN-RU-141, SQB-RU-145, SQN-RU-143 in valid, alarm mode. ,
~'
- 3. Fuel Damage Indication 3. Process radiation monitor alarms and
- a. High coolant activity - reactor coolant sample indicates sample (e.g., exceeding either:
coolant technical spec- a. I-131 dose equivalent exeeds ification for iodine fig. 3.4-1 of Technical Specifi-spike). cations section 3/4.4, or
- b. Failed fuel monitor b. Coolant specific activity indicates increase greater exceeds 100/E uci/gm.
than 0.1% equivalant fuel failures with 30 minutes.
- 4. Abnormal coolant temperatures 4. a. Reactor power exceeds Technical and/or pressure or abnormal Specification limits-Section 2.1; fuel temperatures outside b. High T avg and pressurizer low technical specification pressure alarms occur; or
, limits. c. Subcooling margin monitor l indicates less than 5'F margin tc saturation when at power; or
- d. RCS pressure greater than 2350 psia;
- e. 10% of the operarable core exit thermocouples exceed 650*F.
PV2?6-000A (E80
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PVNGS EMERGENCY PLAN o [ROCEDURE 3 IMPLEMENTING PROCEDURE EPIP-02 Page 2 of 18 REVISION EMERGENCY CLASSIFICATION O Page 14 of 30 4 EMERGENCY ACTION LEVELS (EAL'S) NOTIFICATION OF UNUSUAL EVENT PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 6. Exceeding either primary / 6. Primary to secondary leak rate secondary leak rate technical greater than 1 gpm total through specification or primary both steam generators as identified system leak rate technical by RCS water inventory balance.
specification.
- 7. Unidentified primary system 7. Unidentified primary' system leakage leak rate exceeding technical greater than 1 gpm as determined by specification. monitoring containment sump inventory and-discharga and by RCS'
,3 ~
water inventory balance. I s
- 8. Failure of a safety or relief 8. Pressurizer safety valve opens and in a related system to close fails to reset as indicated by:
following reduction cf appli- a. Pressurizer TRDL alarm at window cable pressure. 4A01A, and
- b. Increasing reactor drain tank level, temperature and pressure indicated on CHN-LI-2'68, ~
CHN-TI-268 and CHN-PI-268 on panel 303, and
- c. Relief line temperature in-
, dicator(s) reading greater than ' alarm set points on one or more of the following indicators on panel B04:
Relief Line
. Safety Valve Teso, Ind.
RC-PSV-200 RCi-TI-107 RC-PSV-201 RCN-TI-107 RC-PSV-202 RCN-II-106-RC-PSV-203 RCi-TI-106
- 9. Loss of offsite power or 9. AC bus failure annunciators.
loss of onsite AC power
, capability. ,
PV216 (CD418 82)
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D IMPLEMENTING PROCEDURE EPIP-02 Page 3 of 18 (D REVISION EMERGENCY CLASSIFICATION O Page 15 of 30 EMERGENCY ACTION LEVELS (EAL'S) NOTIFICATION OF UNUSUAL EVENT PALO VERDE NUCLEAR GENERATING STATION l Initiating Events EAL (Alarm, Instrument Reading, etc. )
- 10. Loss of containment integrity 10. a. Any containment automatic requiring shutdown by tech- isolation valve found to be in-nical specification. , operable, or
- b. Any penetration found open that is not capable of being closed by an operable containment automatic isolation valve but required to be closed during accident conditions
' ~
and normally closed by a valve, blind flange or deactivated automatic valve, or I. - ')
c. Either air lock inoperable, or
- d. Penetration (s) fail type B and C leak test requirements (as spec-ified by Technical Specificatons Section 3/4.6.1).
- 11. Loss of engineered safety 11. a. LCOs for engineered safety features feature or fire protection exceeded per tech specs, system to the extent b. LCOs for Fire Protection System requiring shutdown by exceeded.
technical specifications.
- 12. Fire at the plant that 12. a. Any of various fire protection cannot be controlled by alarms.
l the PVNGS Fire Team. b. Verbal report.
- 13. Indications or alarms on 13. a. ESF process or effluent process or effluent para- monitor (s) inop.
meters not functional in the control room to the b. Meteorological instrumentation extent requiring unit inop. shutdown; or other signifi-cant loss of assessment or c. Unit Computer inop. communication capability.
'e-M I
Pv216 00CA 48,62) 1 --
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D
, IMPLEMENTING PROCEDURE EPIP-02 Page 4 of 18
_, REVISI'C N Ei4ERGENCYCLASSIFICATION O Page 16 of 30 DIERGENCY ACTION LEVELS (EAL'S) NOTIFICATION OF UNUSUAL EVENT
' PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 14. Security threat' attempted 14. As reported or observed.
entry or attempted sabotage.
- 15. Natural pbenomenon being 15. a. Seismic trigger annunciator; experienced or projected b. as visually observed by or beyond usual levels: reported to, station personnel;
- a. any earthquake; c. as visually observed by or
- b. 50 year flood; reported to, station personnel.
- c. tornado on site.
_s 16. Unusual hazards experienced- 16. As visually observed by or reported E ; a. aircraft crash onsite;-
to, station personnel.
- b. onsite explosions;
- c. onsite or nearsite related accidents that could result in the release of toxic material or spills of flansable materials.
~
- 17. Turbine, rotating component 17. Turbine trip as evaluated.
l failure causing rapid l plant shutdown. -
- 18. Other plant conditions 18. As situations occur.
l exist that warrant l increased ewareness on the i part of state / local offsite authorities or require plant shutdown due to technical specification requirements - or require other than l nor=al controlled shutdown. l l
%b i i m em::4 is a:,
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D
.m IMPLEMENTING PROCEDURE EPIP.-02 Page 5 of 18 REVISION EMERGENCY CLASSIFICATION O Page 17 of 30 EMERGENCY ACTION LEVELS (EAL'S)
NOTIFICATION OF UNUSUAL EVENT - PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 19. Any serious radiological 19. As situations occur.
exposure of plant personnel or the transportation to offsite facilities of contaminated injured personnel. r...>
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PV2 6@CA i8 #2)
1 l i PVNGS EMERGENCY PLAN. PROCEDURE NO. APPENDIX D
. IMPLEMENTING PROCEDURE EPIP-02 Page 6 of 18 REVISION EMERGENCY CLASSIFICATION O Page 18 of 30 EMERGENCY ACTION LEVELS (EAL'S)
' ALERT PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Readira, etc.)
l'. Severe loss of fuel 1. a. Very high primary coolant activity cladding. (300 uCi/ gram of I-131 dose equivalent.
- b. Letdown monitor indicates an increase of greater than 1% fuel failures within a 30 minute period, or 5% total fuel failures.
- 2. Rapid gross failure of one 2. a. Shift Supervisor's opinion based steam generator tube with loss of offsite power. on observation of one or more of..
the following: . - )i
- 1) Decrease in feedwater flow to the da= aged steam generator indicated at SGN-FR-1112 (S/G-1) or 3GN-FR-1122 (S/G-2)
- on panel B06, or
- 2) Decreasing pressurizer prescure indicated at RCN-PR-100 on panel B04, or
- 3) Decreasing pressurizer level indicated at RCN-LR-110 on panel B04, or
- 4) Volume control tank level decreasing indicated at CHN-LI-226 on panel B03, or
- 5) Charging pump flow increasing indicated at CHB-FI-212 on panel B03, or
- 6) Condenser vacuum punp/ gland seal exhaust monitor high alars from SQN-RU-141 and SQN-RU-142 indicated at cabinet J-SQN-C03, or
.f e Pv216 0C04 i8 821
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D ,i m
-IMPLEMENTING PROCEDURE EPIP-02 Page 7 of 18 REVISION EMERGENCY CLASSIFICATION . O Page 19 of 30 EMERGENCY ACTION LEVELS (EAL'S)
ALERT PALO VERDE NUCLEAR JENERATING STATION _ Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 7. Steam generator blowdown monitor high alarm from SQN-RU-4 (S/G-1) or SQN-RU-5 (S/G-2) indicated at cabinet J-SQN-C03, and
~
- b. Offsite power loss to 13.8 kv intermediate buses NAN-SOS and NAN-506 and momentary loss of 4.16-kv buses NBN-S01 and NBN-S02
~
indicated by: ,] , s
- 1) 13.8 kV Unit 1 SWOR-S05-TR3L alarm at window 1AISA and low voltage indicatica at NAN-EI-SOS on panel B01, and
- 2) 13.8 kv Unit 1 SWGR-S06-TRBL alarm at window 1A15A and low voltage ind'. cation at NAN-EI-S06 on panel B91, and
- 3) Momentary LOP / load shed A alarm at window 1A3C, and
- 4) Momentary IE / load shed B alarm at window 1C18C.
- 3. Rapid failure of steam gener- 3. By the following indicators:
ator tubes (e.g., several hundred gpm primary to second- a. Pressuri::cr pressure decreasing ary leak rate). uncontrollably at RCA-PI-102A, RCB-PI-1023, RCC-PI-102C, RCD-PI-102D on panel B05, or Reactor trip on low pressure indicated by SNSR Lo alarm at window 4C01D and/or PZR PRESS LOW also at window 4C02A, and
..s ua.
PV216-0CDA 48 Q 9
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D IMPLEMENTING PPOCEDURE EPIP-02 Page 8 of 18 m REVISION EMERGENCY CLASSIFICATION O Page 20 of 30 EMERGENCY ACTION LEVELS (EAL'S) ALERT PALO VERDE NUCLEAR GENERATING STATION
- b. Condenser vacuum pump / gland seal exhaust monitor high alarm from
=
SQN-RU-141 and SQN-RU-142 indicated at cabinet J-SQN-C03, or Steam generator blowdown monitor high alarm from SQN-RU-4 (S/G-1) or SQN-RU-5 (S/G-2) indicated at c'abinet J-SQN-C03, and
- c. No significant increase in containment building pressure indicated at:
HCA-PI-351A HCA-PI-352A HCB-PI-351B HCB-PI-352B' s- - " HCC-PI-351C HCC-PI-352C ( ,) HCD-PI-351D HCD-PI-352D, and
- d. No signific.unt increase in containment building recirculation-sump levels indicated at SIN-LI-10 and SIN-LI-11 on panel B02, and
- e. No containment atmosphere non-itor Ch. B high alarm from SQB-RU-1 indicated at cabinet J-SQN-C03 and by HI CNTMT RAD CH TRIP alarm at window 5A01C. ,
- 4. Steam line bres.k with signi- 4. Indicated by:
ficant (e.g., greater than 10 a. Steam generater differential gpm) primary to secondary leak pressure AFAS indication signal rate. indicated on panels B02 and B05 and high containment building pressure indicated by HI CONTMT , PRESS PRE-IRIP alarm at window 5A06D and containment atmosphere monitor Ch. B high alarm from l SQ3-RU-l indicated at cabinet i J-SQN-C03 and by HI CNTMT RAD CH TRIP alarm at window 5A01C, or 9 l 8V2?6@CA 4818D
PVNGS EMERGENC( PLAN PROCEDURE N O. APPENDIX D IMPLEMENTING PROCEDURE EPIP-02 Page 9 of 18 N REVISION EMERGENCY CLASSIFICATICN O Page 21 of 30 EMERGENCY ACTION LEVELS (EAL'S) ALERT PALO VERDE NUCLEAR GENERATING STATION
- b. High steam flow indicated at -
SGN-FR-1112 (S/G-1) or SGN-FR-1122 (S/G-2' on panel B06 and low T avs indica:ed at RCN-TR-100 on panel B04 and T avg-T ref. HI-LO alarm at window 4A08B, or
- c. Low steam generator pressure MSIS indication signal indicated at panels B02 and B05, and
- d. 1) Condenser vacuum pump / gland
, seal exhaust monitor high alarm from SQN-RU-141 and SQN-RU-142 indicated at cabinet J-SQN-C03,
~
- or
- t..j 2) Steam generator blowdown monitor high alam from .
SQN-RU-4 (S/G-1) or SQN-RU-5 (S/G-2) indicated at cabinet J-SQN-C03.
- 5. Unidentified primary coolant 5. Containme";: sump level alarm, area leakage rate greater than monitor ala = and measured or 50 gpm. calculated leakage > 50 gpm.
- 6. High radiation levels or 6. Corresponding alarms and indications high airborne contamination on appropriate Area Monitoring System which indicates a severe monitors.
degradation in the control of radioactive materials (sudden increase by a factor of 1000 over normal radiation readings).
- 7. Loss of offsite power and 7. Loss of lighting, alarms, and loss of vital onsite AC annunciator functions.
power.
- 8. Loss of vital DC power. 8. DC bus failure annunciators.
Q.- r PV2*6 CC34 (8.82) d
PVNGS EMERGENCY PLAN _ PROCEDURE NO. APPENDIX D IMPLEMENTING PROCEDURE EPIp-02 page 10 of la REVISION . EMERGENCY CLASSIFICATION O Page 22 of 30 EMERGENCY ACTION LEVELS (EAL'S) ALERT PALO VERDE NUCLEAR GENERATING STATION Initiating Ev uts EAL (Alar =, Instrument Reading, etc.) '
- 9. Loss'of coolant flow which 9. Indication of no coolant flow has led to fuel failure. accompanied by activity levels as determined in item ALERT 1.
- 10. Loss of any engineered safety 10. ESF.LCOs exceeded, accompanied by feature system function. inability to take compensating action.
.J.. Failure of the reactor protec- 11. Indication of Rx trip without tion system to initiate and corresponding decrease in power level.
complete a scram placing the
, reactor in a suberitical.
j 3 condition.' O'
- 12. Fuel handling accident in 12. Area radiation alarm, or Fuel Building. XJ-SQA-RU-31 or
. (FSAR-15.7.3.1) XJ-SQB-RU-32
- 13. Fuel handling accident in 13. Area radiation alarm, or Containment. XJ-SQA-RU-33 or (FSAR-15.7.3.2) XJ-SQB-RU-34 i 14. Serious fire with potential 14. a. Any of various Fire Protection .
l to cause degradation of System alar =s plant safety systems. b. Verbal reports;
- c. Fire pump automatic start annunciator.
l
- 15. Most or all alarms 15. Control room observation.
{ (annunciators). nonfunctional ' and reactor is not in shutdown.
- 16. Radiological effluents greater 16. Any radiological effluent monitor than 10 times technical speci- (e.g., J-SQN-RU-141, J-SQB-RU-145 or fications instantaneous limits SQN-RU-143) confirmed readira 10 (an instantaneous rate which, times above alarm set point.
?
l PV2*6 0CDA (8 82) e
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D
, IMPLiEMENTING PROCEDURE EPIP-02 Page 11 of 18 REVISION EMERGENCY CLASSIFICATION 0 Page 23 of 30 1
EMERGENCY ACTION LEVELS (EAL'S) A t O _AL.E.". '". , PALO VERDE NUCLEAR GENERATING STATION {H
.t .
Initiating Events EAL (Alarm, Instre;.ent Reading, etc.) h 1 if continued over 2 hours, would ) result in about 1 mr at the site boundary under average meteorol- j% ological conditions). 5 l
- 17. Ongoing security compromise. 17. As observed and reported by security personnel. . I I
- 18. k Severe natural phenomenon 18. a. Seismic Trigger Annunciator, being experienced or pro- .followed by Seismic Switch ]*
~
~,
. jected, such as: Ant.unciator,'with indication of'
' k.
- a. Earthquake exceeding ground motion greater than 0.18g a Operating Basis Earth- ~ {
horizontal, or greater than quake levels; { 0.178 vertical. {
- b. Tornado striking facility; b. As reported; )
or c.' Anemometer reiding approaching
- c. Winds near design level !
90 mph. ! I
- 19. Other bzards being 19. As reporte.d by, or to, station ;
experie. iced or projected personnel. i such as:
- a. aircraft crash on facility;
- b. missle impact.on facility;
- c. explosion damage affecting l plant operation; j
- d. entry into facility environs
, of uncontrolled toxic or i i flammable gas; ' or
- e. turbine failure causing casing i; penetration.
l (Some effect on facility experienced i or anticipated.) ( j ' Pv2 6 0CCA 48.82)
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D IMPLEMENTING PROCEDURE EPIP-02 Page 12 of 18 REVISION DIERGENCY CLASSIFICATION , O Page 24 of 30 EMERGENCY ACTION LEVELS (EAL'S) ALERT PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL ( Alarm. Instrument Reading, etc.)
- 20. Evacuation of control room 20. As deemed necessary bj Shif t required or anticipated with Supervisor.
control of chutdan systems established from local stations.
- 21. Other plant conditions exist 21. As deemed necessary by Emergency warranting precautionary Coordinator.
activation of the TSC and EOF.
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REVISION EMERGENCY CLs.SSIFICATION , O Page 25 of 30 DIERGENCY ACTION LEVELS (EAL'S) SITE EMERGENCY PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.) ~
- 1. Known loss of coolant 1. Decreasing pzr level with 3 charging accident greater than pumps operating.
make-up pump capacity.
- 2. Degraded core with possible 2. Gross fuel clad failures (extremely loss of coolable geometry. high coolant activity).
- 3. Rapid failure of steam 3. AC vital bus failure accompanied by 1 generator tubes (several above, (and Main Steam radiation hundred gpm leakage) monitor al.. ms).
accompanied by loss of
- e
-3 offsite power.
t , .
- 4. Steam line break with 4. (Alert #1, plus Alert #4 but leakage steater than 50 gpm 50 gpm).
primary to seconda n leak-age and e dication of fue* damage. 1
- 5. Loss of offsite power and loss 5.
of oncite AC power for more Alert #7 for 1 15 minutes. than 15 minutes.
- 6. Loss of all vital onsite DC 6. Alert #8 for > 15 minutes.
power for more than 15 minutes.
- 7. Complete loss of any function 7. Shutdown margin cannot be made) 1%.
needed for plant hot shutdown.
- 8. Transient requiring operation 8. LSTS exceeded'w/o reactor trip but no of shutdown systems with failure indication of fuel uamage.
to scram (continued power generation with no core damage immediately evident). Pv M CCOA (8.82)
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m l PVNGS EMERGENCY PLAN. PROCEDURE NO. APPENDIX D IMPLEMENTING PROCEDURE- EPIP-02 Page 14 of 18 ' REVISION EMERGENCY CLASSIFICATION O Page 26 of 30 EMERGENCY ACTION LEVELS (EAL'S)
. SITE EMERGENCY PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Readine, etc.) *
- 9. Major damage to spent fuel 9.
Building. (FSAR-15.7.3.1) Alarm XJ-SQB-RU-32 or XJ-SQA-RU-31 and as reported.
- 10. Major damage to spent fuel 10. Alarm XJ-SQB-RU-34 or XJ-SQA-RU-33 and in containment. (FSAR-15.7.3.2) as reported.
, 11. Fire compromising the function 11. a. Fire pump automatic start of safety systems. annunciator;
- b. Various Fire Protection System alarms; *
- c. Various alarms according to affected safetiy system; j
~
f
- d. Shift Supervisor determines fire to be beyond capability of PVNGS Fire Team.
1
- 12. Most or a11 ' alarms 12. As observed.
(annunciators) lost and plant transient initiated or in progress.
- 13. a. Effluent monitors detect 13. Stack monitor alarm with corresponding levels corresponding to indications per Station Manual greater than 50 mrem / hour procedures on:
whole body for 1/2 hour E greater than 500 mrem / hour , XJ-SQN-RU-13 whole body for two minutes XJ-SQN-RU-11 (or five times these levels or to the thyroid) at tha site XJ-SQN-RU-32 boundary for adverse meteorology.
- b. These dose rates are projected based un other plant parameters or are measured in the environs.
- c. EPA PAGs are projected to be exceeded outside the site boundary.
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a u PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D IMPLEMENTING PROCEDURE EPIP-02 Page 15 of 18
, s REVISION EMERGENCY CLASSIFICATION O Page 27 of 30 EMERGENCY ACTION LEVELS (EAL'S) y[.
SITE EMERGENCY 5 PALO VERD2 NUCLEAR GENERATING STATION , , M Initiatine Events EAL (Alarm, Instrument Reading, etc.) i
- 14. Imminent loss of physical 14. Situation evident.
control of the plant. i i
- 15. Severe natural phenomenon i
- 15. -(t being experienced or pro- ','
jected with plant not in I cold shutdown, such as: ,y
- a. earthquake greater than. a. Seismic Trigger Annunciator followed by Safe Shutdown Earthquake; Seismic Switch Annunciator with indication of ground motion greater than 0.31g horizontal or greater than 0.348
_, . vertical; -
- b. tornado in excess of 3
- b. Rotational Velocity greater than 240 mph, design levels; translational velecity greater than -
60 mph; -
- c. winds in excess of c. Average wind velocity greater than '
design levels, 90 mph or gusts greater than 105 mph. , y
- 16. Other hazards being experi- 16. As observed by, or reported to, enced or projected with -
station personnel. reactor not in cold shut-down, such as;
- a. aircraft crash affectin o vital s~tructures by impact
- or fire;
- b. severe damage to Safe Shut-down equipment from missiles or explosion; l c. entry of uncontrolled flammable gas into vital areas; entry of .
uncontrolled toxic into vital areas where lack of access to the area constitutes a safety .
'n problem.
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S PVNGS EMERGENCY PLAN PROCEDURE NO. APPEIDIX D IMPLEMENTING PROCEDURE EPIP-02 Page 16 of 18 REVISION EMERGENCY CLASSIFICATION O Page 28 of 30 EMERGENCY ACTION LEVELS (EAL'S) SITE EMERGENCY-PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 17. Evacuation of control room 17. Control room evacuation accompanied by accompa:.ied by the inability lack of access to local shutdown to locally control shutdown system controls.
systems within 15 minutes.
- 18. Other plant conditions exist 18. As determined by Emergercy warranting activiation of Coordinator.
emergency centers and radiation protection teams, or issuance of a precautionary , notification to the public .
.' near the site.
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PVNGS EMERGENCY PLAN PROCECURE NO. APPENDIX D IMPLEMENTING PROCEDUf1E EPIP-02 Page.17 of 18 REVISION EM.2GENCY CLASSIFICATION O Page 29 of 30 EMERGENCY ACTION LEVELS (EAL'S) GENERAL EMERGENCY PALO VERDE NUCLEAR GENERATING STATION Initip ing Events EAL (Alarm, Instrument Reading, etc.) -
. 1. a. Effluent monitors detect 1. a. Stack monitor alarms with-levels corresponding to corresponding indications per 1 rem / hour Whole Body (or Station Manual procedures:
5 rem / hour thyroid) at XJ-SQN-RU-13 the site boundary under XJ-SQN-RU-11 actual meteorological XJ-SQN-RU-32 conditions.
- b. These dose rates are pro- b. (See Appendix 10.F).
jected based on other paraceters (e.g., radiation level in containment with ., leak rate appropria.te for _ existing containment pres-sure with some confirmation from effluent monitors) or . 1 are measured in the environs.
- 2. Loss of two of three fission 2. As evaluated-based upon consideration procuct barriers with a potential loss of third of coolant activity, coolant inventory and makeup rate, and containment barrier (e.g., loss of primary pressure.
coolant boundary, cladding i ' failure, and a high potential for breach of containment).
- 3. Loss of physical control of 3.
the facility. Situation evident. i
- 4. Small or large break LOCA, 4. As evaluated-based upon consideration acconpanied by failure of ECCS initiation, leading to of coolant activity, coolant invent: ry and makeup rate, and containment severe core melt in from pressure.
minutes to hours. Breach of containme.nt likely. Pv216-0CCA (8.82) l l l
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPEND 1X D
- , IMPLEMENTING PROCEDURE EPIP-02 Page 18 of 18 REVISION DfERGENCY CLASSIFICATION O Page 30 of 30 DIERGENCY ACTION LEVELS (EAL'S)
GENERAL EMERGENCY PALO VERDE NUCLEAR GENERATING STATION Initiating Events EAL (Alarm, Instrument Reading, etc.)
- 5. Transient initiated by loss of 5. As evaluated.
feedwater and condensate systems, followed by failure of emergency feedwater system for extended period. Core celt possible in several hours. Breach of containment expected ' to follow core melt.
- 6. Transient requiring operation 6. Site Emergency #8 with indication of shutdown systems with' fail- of fuel da= age or loss of ECCS. - -
i ure to scram resulting in core - damage or inability of core cooling and makeup systems to meet load. (Could result in core melt.)
- 7. Failure of offsite and onsite 7. Loss of lighting,' alarms, and AC power accompanied by total annunciator functions, coupled with loss of emergency feedwater loss of steam-driven auxiliary makeup capability for several feedwater pump. '
hours. Would lead to eventual core celt and likely breach of containment.
, 8. Small break LOCA with 8. Site Emergency #1 followed by loss of initially successful ECCS. ECCS and containment spray.
Subsequent failure of ECCS and contain=ent heat removal systems extended over several hours which could lead'to core melt and containment breach. 4 PV2'6-00CA s0 82) g e* * < * *'* C*}9 9
PVNGS EMERGENCY PLAN PROCEDURE N O.
; IMPLEMENTING PROCEDURE EPIP-03 REVISION Page 1 of 6 UNUSUAL EVENT IMPLEMFliTING ACTIONS 0 ASSIGTED COPY PV_NGS SLI # t'64 i .
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PVNGS EMERGENCY PLAN PROCEDURE N O.
,- IMPLEMENTING PROCEDURE EPIP-03 REVISION UNUSUAL EVENT IMPLE}EITING ACTIONS 0 Page 2 of 6 TABLE OF CONTENTS ,
SECTION PAGE NUMBER 1.0 OBJECTIVE 3 -
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 4 4.3 Instructions 4 ( APPFllDICES Appendix A - Unusual Event Implenentira Procedure Check List 6 s 4 I r m_.s-Pv2MOA is.02) e
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. 4 IMPLEMENTING PROCEDURE EPIPH)3 REVISION UNUSUAL EVENT IMPLEMENTING ACTIONS 0 Page 3 of 6 1.0 OBJECTIVE .
1.1 The objective of this precedure is to provide a series of implementing actions to be taken upon declaration of a NOTIFICATION OF UNUSUAL EVENT. This procedure also directs personnel to the use of additional procedures to adequately respond to those conditions classified as an UNUSUAL EVENT. , 1.2 This procedure may be considered as a type of immediate action procedure for the timely implementation of pertinent portions of the overall PVNGS Emergency Plan. ,
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-01, "*7::GS Emergency Organization" 2.1.2 EPIP-02, "PVNGS Emergency Classification" s 2.1.3 EPIP-07, " Notification Process - UNUSUAL EVENT" 2.1.4 EPIP-11, "TSC/STSC Activation" "2 . Developmental Referenc2s 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. 2 . 3.0 LIMITATIONS AND PRFrAUTIONS 3.1 Continued surveillance and assessment of plant conditions is necessary to ensure that the emergency classification is appropriately revised as conditions change, or more definitive inf ormation is obtained. 4 Pv2tS 000A it22}
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PROCEDURE PVNGS EMERGENCY PLAN NO. (~ l IMPLEMENTING PROCEDURE EPIP-03 REVISION UNUSUAL EVENT IMPLEMENTING ACTIONS 0 Page 4 of 6 4.0 DETAILED PROCEDURE , 4.1 Personnel Indoctrination 4.1.1 In an UNUSUAL EVENT situation, time is available to take precautionary and constructive steps to prevent a more serious event and/or to mitigate any consequences that may - occur. This event status places the plant in a readiness position for possible cessation of routine activities and/or augmentation of onshif t resources. No releases of radioactive material requiring offsite response are expected. Appropriate notification of state / county authorities is made. 4.1.2 The Shift Supervisor shall be responsible for initiating this procedure. The Duty Manager, upon assumlag the role of Emergency Coordinator, shall be responsible for completing the implementing actions of this procedure. 4.2 Prerequisites 4.2.1 A NOTIFICATION OF UNUSUAL EVENT has been declared per the. provisions of EPIP-02. 4.3 Instructions 4.3.1 The affected unit Shift Supervisor shall perform the following: 4.3.1.1 Initicily classify the emergency per EPIP-02. 4.3.1.2 Notify the Duty Manager. If the Duty Manager is , incapacitated, the Shift Supervisor shall assume the
. role of Emergency Coordinator.
4.3.1.3 Announce the following over the public address system:
" ATTENTION ALL PERSONNEL - AN UNUSUAL EVENT HAS BEEN DECUaED. PERSOICEL ASSIGNED TO THE ONSHIFT EMERGENCY ORGANIZATION, REPORT TO YOUR EMERGENCY STATIONS. ALL OTHER PERSONNEL CONTINUE WITH NORMAI ROUTINE UNTIL FURTHER NOTICE".
(Give a brief description of the event, if appropriate, and repeat the announcement).
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PVNGS EMERGENCf PLAN PROCEDURE () NO. IMPLEMENTING PROCEDURE EPIP-03 REVISION UNUSUAL EVENT IMPLEMENTING ACTIONS 0 Page 5 of 6 g 4.3.1.4 Ensure the actions of the appropriate recovery or casualty procedures have been implemented. 4.3.2 The Energency Coordinator shall perform the following: 4.3.2.1 Implement EPIP-07 and activate the Satellite TSC in accordance with EPIP-11. 4.3.2.2 Implement additional Emergency Plan Implementing Procedures according to the situation that resulted in the emergency being classified as an UNUSUAL EVEliT. Complete the check list as indicated in Appendix A. 4.3.2.3 Determine the need for any additional personnel. Direct the Security Shift Captain to call in additional personnel as needed by utilising the computer call-out listing. 4.3.2.4 Reevaluate the mergency classification as conditions "3 change by implementing procedure EPIP-02. 4.3.3 Emergency response personnel shall assume their emergency roles in accordance with EPIP-01. l l C_ l l Pv:'saca is at, i
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PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX A
, ~. T IMPLEMENTING PROCEDURE EPIP-03 Page 1 of 1 REVISION UNUSUAL EVENT IMPLEMENTING ACTIONS 0 Page 6 of 6 NOTIFICAT "N OF UNUSUAL EVENT -
IMPLEMENTIhu 'ROCEDURE CHECK LIST IMPLEMENTED (1) INITIALS / TIME (2) TES/NO EPIP-01 APS Emergency Oreanization X/ / - EPIP-02 PVNGS Emergency Classification X/ / EPIP-07 Notification Process - Unusual Event X/ / EPIP-11 TSC/STSC Activation X/ / EPIP-12 Operational Support Center Activiation / / EPIP-32 Public Information/!!edia X/ /
/ /
/ /
/ /
/ /
/ /
(. REMARKS: l l l i l l l EmergencyCoorddnatorSignature Date NOTE: (1) X indicates that this procedure is required to be implemented. l (2) Time indicates when procedure is initiated. l
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PVNGS EMERGENCY PLAN PROCEDUaE N O.
^~ IMPLEMENTING' PROCEDURE EPIP-04 k.1e REVISION ALERT IMPLE EITING ACTIONS 0 Paa,e 2 of 7 TABLE OF CONTENTS ,
SECTION PAGE NUMBER 1.0 OBJECTIVE 3 - - 2.0 REFERFl!CES . 3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PRCCEDURE
- 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 4 4.3 Instructions 4
.c f( ) APPENDICES Appendix A - Alert Implementing Procedure Check List 6 4
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- o. l ktw1 IMPLEMENTING PROCEDURE EPIP-04 REVISION ALERT' IMPLEMENTING ACTIONS -
0 Page 3 of 7-1.0 OBJECTIVE - 1.1 The objective of this procedure is to provide a series of implementing actions to be taken upon declaration of an ALERT. This procedure also directs personnel to the use of additional procedures to adequately respond'to those conditions classified as an ALERT. " This procedure may be considered as a type of immediate action procedure for the timely implementation of pertinent portions of the overall PVNGS Emergency Plan.
2.0 REFERENCES
2.1 Im-lementing References 2.1.1 EPIP-01, "PVNGS Emergency Organization" c7% 2.1.2 EPIP-02, "PVNGS Emergency Classification" b" '.! 2.1.3 EPIP-08,"NotiIicationProcess-ALERT,SITEEMERGENCY,or GENERAL EMERGFiCY" 2.1.4 EPIP-11, ""dC/STSC Activation" 2.1.5 EPIP-12, " Operations Support Center Activation" 2.1.6 EPIP-13, " Emergency Operations Pacility Activation" 2.1.7 EPIP-20, " Personnel Assembly and Accountability" 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 Nucicar P e.er Plants" 2.2.2 PVNGS Emergency Plan, Rev. 2 3.0 LIMITATIONS AND PRECAUTIONS 3.1 Continued surveillance and assessment of niant conditions is
. , , necessary to ensure that the emergency classification is
!.M apprcpriately revised as conditions change, or more definitive
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Q IMPLEMENTING PROCEDURE EPIP-04 REVISION ALERT IMPLEMENTING ACTIONS 0 Page 4 of 7 4.0 DETAILED PROCEDURE - 4.1 Personnel Indoctrination 4.1.1 In an ALERT situation, limited releases of radioactive material cay occur and radiological / meteorological information may have to be obtained for assessment of onsite an,d offsite consequences. The emergency response for an ALERT '.ncludes activation of onsite and offsite emergency ce.ters. An ALERT calls for prompt initial and follow-up notification to offsite emergency management organizations. The ALERT status is c:aintained until the event is terminated or reclassified. 4.1.2 The Shif t Supervisor shall be responsible for initiating this procedure. The Duty Manager, upon assuming the role of Emergency Coordinator, shall be responsible for completing the implementing actions of this procedure. _ 4.2 Prerequisites t 4.2.1 An ALERT has been declared per the provisions of EPIP-02. 4.3 Instructions 4.3.1 The affected unit Shift Supervisor shall perform the following: 4.3.1.1 Initially classify the emergency per EPIP-02. 4.3.1.2 Notify the Duty Manager. If the Duty Manager is incapacitated, the Shif t Supervisor shall assume the role of Emergency Coordinator. 4.3.1.3 Announce the following over the public address system:
" ATTENTION ALL PERSONNEL - AN ALERT HAS 3EEN DECLARED. PERSONNEL ASSIGNED SPECIFIC RESPONSIBIITIES IN THE EMERGENCY ORGANIZATION, REPORT TO YOUR DIERGENCY STATIONS. ALL OTHER PERSONNEL REPORT TO YOUR ASSIGNED ASSEl:BLY AREAS".
(Give a brief description of the event, if appropriate, and repeat the announcement). C 4.3.1.4 Ensure that the actions of the appropriate recovery or casualty procedures have been imple=ented. PV256 000A (6 83 e
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IMPLEMENTING PROCEDURE Epip_04 REVISION ALERT' IMPLEMENTING ACTIONS 0 Page 5 of 7 4.3.2 The Emergency Coordinator shall perform the following: 4.3.2.1 Implement EPIP-08 and ensure accountability within the protected area is being performed by implementing EPIP-20. 4.3.2.2 Implement additional Emergency Plan Implementing
- Procedures according to the situation - t resulted in the emergency being classified as an Ar. . Complete the check list as indicated in Appendix *,
4.3.2.3 Direct the Security Shift Captain to call in the Onsite and Offsite Emergency Organization personnel by utilizing the appropriate computer call-out listing. 4.3.2.4 Determine the need for offsite assistance. If , assistance is necessary, direct. a Con =unicator to j contact the required agency per EPIP-33. f 's! f 4.3.2.5 Reevaluate the emergency _ classification as conditions change by implementing procedure EPIP-02. 4.3.2.6 Transfer the Emergency Coordinator function in accordance with EPIP-01. 4.3.3 Emergency response personnel shall assume their emergency roles in accordance with EPIP-01. 4.3.4 Technical Support Center / Satellite Technical Support Center (TSC/STSC) Activation 4.3.4.1 . The Emergency Coordinator shall implement EPIP-ll to activate the TSC and STSC. 4.3.5 Operations Support Center (OSC) Activation 4.3.5.1 The OSC Coordinator shall implement EPIP-12. 4.3.6 Emergency Operations Facility (EOF) Activation 4.3.6.1 The Emergency Operations Director shall implement EPIP-13.
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1 PVNGS EMERGENCY PLAN PROCEDURE NO. (,', IMPLEMENTING PROCEDURE EPIP-04 APPENDIX A Page 1 of 2 Na/ REVISION i ALERT'1MPLEMENTING ACTIONS 0 Page 6 of 7 i 4 ALERT .
, IMPLEMENTING PROCEDURE CHECK LIST
- IMPLEMENTED (1) INITIALS / TIME (2)
YES/NO EPIP-01 PVNGS Emergency Organization X/ / - EPiP-02 PVNGS Emergency Classification X/ / EPIP-06 Notification Process - ALERT, SITE EMERGENCY, or GENERAL EMERGENCY X/ / i EPIP-ll TSC/STSC tetivation X/ / EPIP-12 Operational Support Center Activation X/ / EPIP-13 Emergency Operations Facility Activation X/ / EPIP-14A Release Rate Determination / / EPIP-14B Dose Assessment / / EPIP-15 Protective Action Guidelines / / EPIP-16 Onsite Surveys and Sampling / /
- EDIP-17 Offsite Surveys and Sampling / /
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EPIP-19 Onsite Evacuation / / EPIP-20 Personnel Assembly and Accountability X/ / EPIP-21 Search and Rescue / / EPIP-22 Personnel Injury / /
- EPIP-23 Fire Fighting / /
i EPIP-24 Security / / EPIP-25 Rentry for Emergency Operations / / EPIP-26 Potassium Iodine (KI) Administration / / EPIP-27 Sample Analysis at the Station / / EPIP-28 Personnel M.onitoring and Decontanina tion / / EPIP-29 Arca/ Equipment Monitoring and I Decontamination / / '~ EPIP-31 Recovery / / j EPIP-32 Public Inf ormation/ Media X/ / r EPIP-33 Offsite Assistance / / EPIP-34 Transportation Accidents / / i NOTE: (12Xindicatesthat.thisprocedureisrequiredtobeimplemented. (2) Time indicates when procedure in initiated. $ , c~q D PVU6 CCOA +3 th
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SECTION PAGE NMIBER 1.0 OBJECTIVE 3
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 4 4.0 DETAILZD PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 4 4.3 Instructions 4
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REVISION SITE EMERGENCY IMPLEMENTING ACTIONS O Page 3 of 8 1.0 OBJECTIVE , 1.1 The objective of this procedure is to provide a series of implementing actions to be taken upon declaration of a SITE EMERGENCY. This procedure also directs personnel to the use of additional procedures to adequately respond to those conditions classifisd as a SITE DIERGENCY. - This procedure may be considered as a type of immediate action procedure for the timely implementation of pertinent portions of the overall PVNGS Emergency Plan.
2.0 REFERENCES
2.1 Implementing References
. 2.1.1 EPIP-01, "PVNGS Emergency Organization"
.- 2.1.2 EPIP-02, "PVNGS E=ergency Classification" p]3, 2.1.3 EPIP-08, - r otification Process 1 ALERT, SITE EMERGENCY, or GENERAL DIERGENCY" 2.1.4 EPIP-11. "TSC/STSC Activation" 2.1.5 EPIP-12, " Operation. Support Center Activation" 2.1.6 EPIP-13, " Emergency Operations Facility Activation" 2.1.7 EPIP-15, " Protective Action Guidelines" 2.1.8 EPIP-19, "Onsite Evacuation" 2.1.9 EPIP-20, " Personnel Assembly and Accountability" 2.1.10 EPIP-32, "Public Information/ Media" 2.2 Developmental References 2.2.1 NUREG-0654, Rev.1, "Criterie for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 PVNGS E=ergency Plan, Rev. 2 r..,
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REVISION IMPLEiENTING ACTIONS O Page 4 of 8 3.0 LIMITATIONS AND PRECAUTIONS , ; 3.1 Continued surveillance and assessment of plant conditions 'is necessary to ensure that the emergency classification is appropriately revised as conditions change, or more definitive l' i information is obtained. , 1' 4.0 DETAILED PROCEDURE i
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4.1 Personnel Indoctrination .j. 4.1.1 In a SITE EMERGENCY, substantial releases of radicactive 5
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material may occur. Consideration of appropriate q, protective actions, based on actual or projected data, is V - warranted. All onsite and offsite emergency centers are '3 activated. Onsite evacuation will be initiated if 11 : I appropriate. The station will provide updated 3 radiological / meteorological information to offsite d emergency management organizations. The SITE EMERGENCY j
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suf status will be maintained until the event is terminated or reclassific.ation takes place. , 4.1.2 The Shift Supervisor shall be responsible for initiating this procedure. The Duty Manager, upon assuming the role of Emergency Coordinator, shall be responsible for s completing the implementing actions of this procedure. . 4.2 Prerequisites 4.2.1 A SITE EMERGENCY has been declared per the provisions of EPIP-02. 4.3 Instructions ! 4.3.1 The affected unit Shift Supervisor shall perform the l following: t 4.3.1.1 Initially classify the emergency per EPIP-02. s 4.3.1.2 Notify the Duty Manager. If the Duty Manager is incapacitated, the Shif t Supervisor shall assume the , role of Emergency Coordinator. l PV216 CCOA 49. $h
PVNGS EMERGENCY PLAN pceme IMPLEMENTING PROCEDURE EPIP-05 SITE EMERGENCY IMPLEMENTING ACTIONS 0 Page 5 of 8 4.3.1.3 Sound the Emergency Siren and announce the following over the public address system:
" ATTENTION ALL PERSONNEL - A SITE EMERGENCY HAS BEE'i DECLARED. PERSONNEL ASSIGNED SPECIFIC RESP 0hSIBIITIES IN THE EMERGENCY ORGANIZATION, REPORT TO YOUR DIERGENCY STATIONS. ALL OTHER PERS0' CIEL REPORT TO .
YOUR ASSIGNED ASSD1BLY AREAS". (Give a brief description of the event, if appropriate, and repeat the announcement). 4.3.1.4 Notify each unit's Control Room and instruct the Shift Supervisor to activate the unit't. Emergency Accountability Signal. 4.3.i.5 Ensure that the actions of the appropriate recovery or casualty procedures have been implemented.
, 4.3.2 The Emergency Coordinator shall perfor.m the following:
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4.3.2.1 Implement EPIP-08 and ensure accountability within the protected area is being performed by implementing EPIP-20. 4.3.2.2 If conditions warrant, initiate an onsite evacuation in accordance with EPIP-19. 4.3.2.3 Implement additional Emergency Plan Implementing l Procedures according to the situation that resulted in the emergency being classified as a SITE DIERGENCY. Compluce the check list as indicated in Appendix A. 4.3.2.4 Direct the Security Shift Captain to call in Onsite and Offsite Emergency Organizatien personnel by utilizing the appropriate computer call-out listing. l 4.3.2.5 Determine the need for offite assistance. If - assistance is necessary, direct a Communicator to contact the required agency per EPIP-33. 4.3.2.6 Reevaluate the emergency classification as conditions change by implementing procedure EPIP-02. 4.3.2.7 Transfer the Emergency coordinator function in _accordance with procedure EPIP-01. N2% %Ch ts.tn
a PVNGS EMERGENCY PLAN PROCEDURE NO, IMPLEMENTING PROCEDURE EPIP-05
~ REVISION SITE EMERGENCY IMPLEMENTING ACTIONS 0 Page 6 of 8 4.3.3 Emergency response personnel shall assume their emergency roles in accordance with EPIP-01.
4.3.4 Technical .'upport Center / Satellite Technical Support Center (TSC/STSC) Activation 4.3.4.1 The Emergency Coordinator shall implement procedure EPIP-11. f 4.3.5 Operations Support Center (OSC) Activation i 1 4.3.5.1 The OSC Coordinator shall implement procedure EPIP-12. 1 4.3.6 Emergency Operations Facility (EOF) Activation 4.3.6.1 The Emergency Operations Director shall implement procedure EPIP-13.
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2.0 REFERENCES
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This procedure may be considered as a type of immediate action procedure for the timely implementation of pertinent portions of the overall PVNGS Emergency Plan.
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-01, "PVNGS Emergency Organization"
,- 2.1.2 EPIP-02, "FVNGS Emergency Classification" i
2.1.3 EPIP-08, " Notification Process - ALERT, SITE EMERGENCY, or GENERAL DERGENCY" 2.1.4 EPIP-ll, "TSC/STSC Activation" 2.1.5 EPIP-12, " Operations Support Center Activation" 2.1.6 EPIP-13, " Emergency Operations Facility Activation" 2.1.7 EPIP-15, " Protective Action Guidelines" 2.1.8 EPIP-19, "Onsite Evacuation" 2.1.9 EPIP-20, " Personnel Assembly and Accountability" 2.1.10 EPIP-32, "Public Information/ Media" 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 Plans" 2.2.2 PVNGS Emergency Plan, Rev. 2
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4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination h 4.1.1 In ~a GENERAL DIERGE' ICY, substantial core degradation, witn pc'ential loss of containment integrity may occur. Under 5 these conditions, substaatial radioactive releases may I occur, accordingly prompt consideration of appropriate f, protective actions, based on actual or projected data, is l warranted. Consideration of predetermined protective h action recommendations (in the event of potential loss of a n fission product barriers) may also be warranted. Onsite j and offsite e=ergency centers are activated. Onsite : evacuation will be initiated if appropriate. The station- ! will provide updated radiological / meteorological information to offsite emergency management organizations . {. t as necessary. The GENERAL DIERGENCY status will be j maintained until the event is terminated, or t reclassification takes place. I ( 4.1.2 The Shift Supervisor shall be responsible for initiating ) this procedure. The Duty Manager, upon assuming the role j of Emergency Coordinator, shall be responsible for completing the implementing actions of this procedure. j 4.2 Prerequisites i ! 4.2.1 A GENERAL DfERGENCY has been declared per the provisions ! j of EPIP-02. i s 4.3 Instructions i, 4.3.1 I The affected unit Shif t Supervisor shall perform the i following: l l 4.3.1.1 Initially classify the emergency per EPIP-02. ! i 4.3.1.2 Notify the Duty Manager. If the Duty Manager is ' incapacitated, the Shif t Supervisor shall assume the i role of Emergency Coordinator. l PV2'6 0C04 e9 82) ?
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PVNGS EMERGENCY PLAN PROCEDURE NO. O IMPLEMENTING PROCEDURE EPIP-06 REVISION CENERAL EMERGENCY IMPLDIENTING ACTIONS 0 Page 5 of 8 4.3.1.3 Sound the Emergency Siren and announce the following over the public address system:
" ATTENTION ALL PERSONNEL - A CENERAL EMERGENCY HAS BEEN DECLARED. PERSONNEL ASSIGNED SPECIFIC RESPONSIBIITIES IN THE EMERGENCY ORGANIZATION, REPORT TO YOUR EMERGENCY STATIONS. ALL OTHER PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREAS".
(Give a brief description of the event, if appropriate, and repeat the announcement). 4.3.1.4 Notify each unit's Control Room and instruct the Shift Supervisor to activate the unit's Emergency Accountability Sienal. 4.3.1.5 Ensure that the actions of the appropriate recovery or casualty procedures have been implemented. 4.3.2 The Emergency Coordinator shall perform the following: 4.3.2.1 Promptly determine the need for reco= mending that appropriate government agencies implement the predetermined protective actions. EPIP-15 provides specific guidance for this determination and related protective actions. 4.3.2.2 Implement EPIP-08 and ensure accountability within the protected area is being performed by implementing i EPIP-20. i l 4.3.2.3 If. conditions warrant, implement EPIP-19. 4.3.2.4 Implement additional Emergency Plan Implementing Procedures according to the situation that resulted in the emergency being classified as a GENERAL EMERGENCY. Complete the check list as indicated in Appendix A. l 4.3.2.5 Direct t'2e Security Shift Captain to call in Onsite L and Offstie Emergency Organization personnel by utilizing the appropriate computer call-out listing.
- 4.3.2.6 Determine the need for offsite assistance. If assistance is necessary, direct a Communicator to contact the required agency per EPIP-33.
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PVNGS EMERGENCY PLAN PROCEDURE N O. T~ IMPLEMENTING PROCEDURE EPIP-06 REVISION GENERAL EMERGENCY IMPLEMENTING ACTIONS 0 Page 6 of 8 4.3.2.7 Reevaluate the emergency classification as conditions change by implementing procedure EPIP-02. 4.3.2.8 Transfer the Emergency Coordinatcr function in accordance with procedure EPIP-01. - 4.3.3 Emergency response personnel shall assume their emergency - roles in accordance with EPIP-01. 4.3.4 Technical Support Center / Satellite Technical Support Center (ISC/STSC) Activation 4 4.3.4.1 The E=ergency Coordinator shall implement procedure EPIP-11. 4.3.5 Operations Support Center (OSC) Activation 4.3.5.1 The OSC Coordinator shall implement procedure EPIP-12. 4.3.6 Eccrgency Operaticns Facility (EOF) Activation 4.3.6.1 The Emergency Operations Director shall implement procedure EPIP-13. l j PV2?6 0004 ed 323 l
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APPENDIX A i IMPLEMENTING PROCEDURE EPIP-06 Page 1 of 2'
- REVISiO'J GENERAL EMERGENCY ,
IMPLEMENTING ACTIONS 0 'Page 7 of 8 1 GENERAL EMERGENCY - IMPLEMENTING PROCEDURE CHECK LIST IMPLEMENTED (1) INITIALS / TIME (2) YES/NO EPIP-01 PVNGS E=ergency Or2anization X/ / EPIP-02 PVNGS Emergency Classification X/ / EPIP-08 Notification Process - ALERT, SITE D!ERGENCY, or GENERAL EMERGENCY X/ / EPIP-11 TSC/STSC Activation X/ / EPIP-12 Operational Support Center Activation X/ / EPIP-13 Emergency Operations Facility Activation X/ / EPIP-14A Release Rate Determination / / EPIP-14B Dose Assessment / / EPIP-15 Protective Action Guidelines / / EPIP-16 Onsite Surveys and Samoling / / EPIP-17 Offsite Surveys and Samuling / /-
.s EPIP-16 E=ertency Excosure Guidelines / /
EPIP-19 Onsite Evacuation / / EPIP-20 Personnel Assembly and Accountability X/ / i EPIP-21 Search and Rescue / / EPIP-22 Personnel Injurv / / i EI'IP-23 Fire Fighting / /
} EPIP-24 Security / /
EPIP-25 Rentry for Ecertency Ooerations / / EPIP-26 Potassiun Iodine (KI) Administratien / / EPIP-27 Samole Analysis at the Station / / EPIP-28 Personnel Monitoring and
. Decontamination / /
EPIP-29 Area / Equip:ent Monitoring and Decontamination / / EPIP-31 Recoverv / / l EPIP-32 Public Information/ Media X/ / l EPIP-33 Offsite Assistance / / EPIP-34 Transcortation Accidents / / j NOTE: (1} (2) X indicates that this procedure is required to be implemented. t Time indicates when procedure is initiated. i
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2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrication - m 4 4.2 Prerequisites 4 4.3 Instructions 5 c . APPENDICES Appendix A - Notification and Alert Net (NAN) 8 i l Appendix B - NAN Notification Flow 9 ; Appendix C - APS Emergency Notification Fanout 10 - Appendix D - Initial Message Content Forn 11 Appendix E - Follow-up Emergency Message Forn 12 Appendix F - Emergency Notificaticn Call Check List, Emergency Coordinator 15 Appendix G - Notification Systems User's Guide 17
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REVISION NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 3 of 18 1.0 OBJECTIVE 1.1 The objective of this procedure is to describe the notification process required upon declaration of a NOTIFICATION OF UNUSUAL EVENT. This process includes the following: . Initial and follow-up notification to Federal, State, County, and Corporate offsite emergency organizations. Notification of off-duty personnel to augment the onshift emergency organization. Notification of the'PVNGS Visitors Center, APS Site Construction Office, and Bechtel E=ergency Control Center.
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2.0 REFERENCES
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2.1 Implementing Refere'nces 2.1.1 EPIP-03 " NOTIFICATION OF UNUSUAL EVENT Implementing Actions" 2.1.2 APS Emergency Response Facility Equipment Manual
- 2.2 Developmental References 2.2.h. 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. 2 2.2.3 10 CFR 50, Appendix E, " Domestic Licensing of Production and Utilization Facilities" 3.0 LIMITATIONS AND PRECAUTIONS 3.1 ' The notification of specific offsite agencies, such as
. emergency medical services and fire departments, is detailed in EPIP-33 "Offsite Assistance".
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,q IMPLEMENTING PROCEDURE pp7p_o7 V' REVISION NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 4 of 18 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination Upon declaration of a NOTIFICATION OF UNUSUAL EVENT, offsite notification will consist of three primary telephone contacts: dhe NRC, State / County government, and APS corporate personnel. The NRC will be notified via the Emergency Notification System (ENS) dedicated line; State / County government _via the Notification and Alert Net (NAN); and corporate personnel via dedicated telephone fanout, through the Manager, Nuclear Operations and the Vice President, Electric Operations. The National Warning System (NAWAS) will - provide a back-up means of notification to State / County government and the Health Physics Network (HPN) will provide a back-up means of notification to the NRC. Primary and alternate compunications links for offsite notifications are shown in Appendix F of this procedure. The Notification and Alert Net, NAN Notificatio'n Flow and APS Emergency f~h v Notification Fanout are. illustrated in Appendices A through C. The Notification Systems User's Guide (Appendix G) provides the instructions necessary to ensure adequate operations of the primary and alternate systems available for offsite notification. The. equipment addressed includes: the NAN, ENE, HPN, and PVNGS dedicated telephones;'NAWAS, mobile radiotelephone, micro-wave, and pager systems. Callers shall refer to this guide to ensure that successful contact is made in a minimal time period. Notification of the NRC and State / County government should be completed within 15 minutes after declarction of a NOTIFICATION OF UNUSUAL EVENT. Although there is no time requirement for the notification of corporate personnel, it shall be expedited to allow sufficier.t time for any subsequent activation and staffing of the onsita and offsite emergency centers.- . The Emergency Coordinator is responsible for implementing this procedure upon declaration of a NOTIFICATION OF UNUSUAL EVENT. 4.2 Prerequisites "
., 4.2.1 A NOTIFICATION OF UNUSUAL EVENT has been declared, and
( , procedure EPIP-03 is being implemented. PV2*6 00CA (8,82)
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- NOTIFICATION PROCESS -
NOTIFICATION OF UNUSUAL EVENT 0 Page 5 of 18 4.3 Instructions 4.3.2 Initial Notification Tns Emergency Coordinator, or designee, shall perform the following: 4.3.1.1 Complete the Initial Message Form (Appendix D) and begin to fill in information as required on the Follow-up Emergency Mesage Form (Appendix E). 4.3.1.2 By means of a single call, on the Notification and Alert Net dedicated telephone, contact the following State / County agencies: Duty Hours (8:00 a.m. to 5:00 p.m. Monday-Friday) National Weather Service (NWS) Arizona Department of Public Safety (DPS) * ((') Am ' Arizona Radiation Regulatory Agency (ARRA)' Arizona Department of Emergency Services (ADES) Maricopa County Department of Civil Defsnse and Emergency Services (MCCDES) Maricopa County Sheriff's Office (MCS0) NOTE Subsequent notification of affected agencies during off-duty hours shall be made per internal agency procedure. ,
'Off-Duty Hours (5:00 p.m. to 8:00 a.m. All Day Saturday and Sunday)
NWS l DPS MCSO 4.3.1.3 When contact is made, the caller shall identify himself and request that the individuals obtain a copy of the Initial Message Content Form (Appendix D). 4.3.1.4 When each individual has obtained a copy, read the completed Initial Message Content form, verbatim.
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PVNGS EMERGENCY PLAN Qcewas IMPLEMENTING PROCEDURE EPIP-07 3 h' REVISION NOTIFICATION PROCESS - NOTIFICAIION OF UNUSUAL EVENT 0 LPage 6 of 18 4.3.1.5 Offer to repeat information and reiterate as necessary. 4.3.1.6 Obtain the name of each person contacted and record on the E7ergency Notification Call Check List, Emergency Coordinator (Appendix F). 4.3.1.7 Via the Emergency Notification System (ENS) dedicated telephone, contact the NRC. ' 4.3.1.8 When contact is made, the caller shall identify himself and read the completed Initial Message Content form, verbatim. 4.3.1.9 Offer to repeat information and reiterate as necessary. 4.3.1.10 Obtain the name of the person contacted and record in Appendix F. 4.3.1.11 hatify the NRC Resident Inspector in accordance with o . Appendix F if unable to contact with the ENS phone. (. )
't.>' 4.3.1.12 When contact is made, the caller shall identify himself and read the Initial Message Content Form, verbatim.
4.3.1.13 offer to repeat information and reiterate as necessary. 4.3.1.14 Obtain the name of the person contacted, and record in Appendix F. 4.3.1.15 Via the PVNGS emergency telephone, not',fy the Maintenance and Operations Manager; Manager, Nuclear Operations; and the Vice President, Electric Operations. It is preferred that the Emergency Coordinator personally explain the emergency situation and plant status to these key individuals. For the ' NOTIFICATION OF UNUSUAL EVENT class, these indi/iduals will provide necessary additional notification of corporate / station personnel. 4.3.1.15 Record the name of each' person contacted, in l Appendix F. 4 A l l PV216KCA {$ d2) (D "%
1 PVNGS EMERGENCY PLAN Qoceme 4 IMPLEMENTING PROCEDURE ,,,,,.7 r REVISION f NOTIFICATION PROCESS -
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NOTIFICATION OF UNUSUAL EVENT 0 Page 7 of 18 i 4.3.1.17 If an individual requests information not contained in the Initial Message Content Form, make reasonable efforts to obtcin and give the information only after all initial notifications have been made. 4.3.1.18 Determine the need for additional personnel. Direct the Security Director to call in additional personnel by utilizing the computer call out listing (Appendix G). The Security M rector will use the updated (daily) computer print-out as an emergency telephone directory. 4.3.1.19 Notify additional locations as listed in Appendix F, obtain the name of the person contacted, and inform them or the situation. 4.3.2 Follow-up Notification ~
.The Emergency Coordinator, or designee, shall perform the following: - -
l ;) -
' ~ '
4.3.2.1 Follow-up hotification shall be performed at the discretion of the Emergency Coordinator for the NOTIFICATION OF UNUSUAL EVENT emergency classification utilizing Appendix E. 4.3.2.2 Follow-up notification is required if the event escalates to a more severe emergency classification level or the initial event is terminated. PV21f,W,CA 18,82)
PVNGS EMERGENCY PLAN Qcaouse IMPLEMENTING PROCEDURE ,,,,_,, l.?_: REVISION
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NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 8 of 18 CR CR CR Unit 1 . Unit 2 Unit 3 j' - m ' PVNGS EOF TSC
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NWS MCS0 ORGANIZATIONS I ~ MCCDES OPS (EOCl ADES ARRA [E0Cl ofa
%.uo. ...u, NOTIFICATION AND ALERT NET (NAN)
PALO VERDE NUCLEAR.. GENERATING STATION (PVNGS) l I ' " G , l_ .. _
PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE ,,, m , $PPENDIXB (N REVISION
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NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 9 of 18 (DUTY /0FF-DUTY HOURS) OuTY HOURS (8:00 Aal TO 5.00 PMI PVNGS I l . NWS ADES ARRA MCCCES I i I l I DIRECTOR DIRECTOR . [ DIRECTOR DIRECTOR I DPS MCSO l GOVERNOR l i y3 - COMMANbEH COMMANDER V OFF-DUTY HOURS (SEFORE 8c0 AM AND AFTER 5:c3 PMI _ During off-duty hours (i.e., cutside of normal government work days and hours') the NAN noti above, EXCEPT MCCDES is notified via MCS0 and ARRA is nctified via ADES. - 1 - MCCDES is Maricopa County Department of Civil Defense & Emergency Services MCSO is Maricopa County Sheriff's Office ARRA is Arizona Radiation Regulatcry Agency l ADES is Arizona Division of Emergency Services DPS is Arizona Department of Public Safety NWS is National Weather Service The Primary notification points are: ADES and MCSO.
- The Alternate notification points are
- DPS and MCCDES.
NAN NOTIFICATION FLOW - - I)s-PALD VERDE NUCLEAR GENERATING STATION-PVNGS W21640A (9 82) G
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE APPENDIX C EPIP-07 ('d 3 p,y. y op 1 REVISION NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 10 of 18 i S ' h OK
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1 PVNGS EMERGENCY PLAN PROCEDURE NO. j i IMPLEMENTING PROCEDURE APPENDIX D ' (n~~ ' '
'DTD-07 REVISION Dya 1 of 1 NOTIFICATION PROCESS -
NOTIFICATION OF UNUSUAL EVENT 0 Page 11 of 18 INITIAL MESSAGE CONTENT NOTIFICATION OF. UNUSUAL EVENT PALO VERDE NUCLEAR GENERATING STATION
- 1. This is , at the Palo Verde Nuclear '
(name/ title) Generating Station. This is a NOTIFICATION OF AN UNUSUAL EVENT.
- 2. At we experienced:
(time) (a) An operational incident consisting of'
,, (provide description of incident including
(.- statement of NO release, windspeed and bearing) , 1-SR_ (b) A natural phenomenon consisting of (description of phenomenon)
- OR
~
(c) An unusual hazard consisting of (description of hazard)
- 3. Emergency conditions:
t (a) are under control (b) can be expected to terminate within hours-lc) may require offsite assistance, will advise
- 4. There is no need for offsite protective action.
- 5. . This is Palo Verde Authenticator .
7- Out. * (see authenticator code) 1 (v
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J PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE APPENDIX E O. EPIP-07 Paee 1 of 3 b -I, REVISION NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 12 of 18 FOLLOW-UP EMERGENCY MESSAGE FORM
, b.
- 1. Reactor Operations: s R
Reactor System Status Power Level l} Pressure %
. Temp. Flow (Pumps On) %
Cooling Mode ECCS Operating / Operable 9 Containment Status il M Containment Isolated? Containment Temp. !j Containment Press Containment Radiation R/hr. -M Reactivity Controls ., D Control Rods Inserted Status of Emer. Boration System e 2. Steam Plant Status: Y
, ~,
S/G Levels Equip.-Failures Feedwater Source / Flow [ S/G Isolated? ;!.,
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- 3. Electrical Dist. Status: j-E Normal Offsite Power Available? (
Major Busses / Loads Lost * ' , Safeguards Busses Power Source - i D/G Running? Loaded? :. L t
- 4. Radioactivity Released (or Increased Release)?
- 5 Liquid / Gas? ' Location / Source of Release Elevation Release Rate Duration , Stopped? ?
Release Monitored Amount of Release F
% Tech. Specs. I E
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- a. Increased Radiation Levels in Plant: Location (s) ;
[ Radiation Level (s) Areas Eva'cuated .i Maximum Offsite Dose Rates Integrated Dose Location
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE rore_o7 APPENDIX E p,,. 9 nc 1 [ REVISlON b' NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 13 of 18 FOLLO1-UP EMERGENCY MESSAGE FORM (CONT'D)
- b. Meteorology Wind Direction From Wind Speed (Meter /Sec or Miles /Hr)
T (*C or *F) Sigma Theta Temperature ('C or *F) Stability Class A B C D E F Raining (Yes/No)
- 5. Projected Doses: Dose Rates Integrated Dose Site Boundary 2 miles 5 miles 10 miles Sectors Contamination (Surface): Inplant Onsite Offsite
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- 6. Security / Safeguards:
- a. Bomb Threat: Search Conducted?
Search Results Site Evacuated?
- b. Extortion: Source (Phone, Letter, etc.)?
Location of Letter
- c. Intrusion: Insider? Outsider?
Furthest Point of Intrusion Fire Arms Related? Stolen / Missing Material?
- d. Rx Ooer./ Demonstration: Size of Group Demands Violence? Fire Arms Related?
e.' Sabotage / Vandalism: Radiological? Arson Involved? Stolen / Missing Material? (I) W, [ PY216-OC04 i8.82) g .. , m
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. . 1 PVNGS EMERGENCY PLAN [ROCEDURE
_ IMPLEMENTING PROCEDURE - m ,, , ., fP8'DIf,E ., l ~ .'i REVISION
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NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT - 0 Page 14 ef 18 FOLLOW-UP EIERGENCY MESSAGE FORM (CONT'Ts)
- 7. Transportation:
! Mode (Road / Rail / Air /etc.) Carrier Exact Location , Type of Material (HEU/ Spent Fuel / Cat III/Other) Description of Shipment Labels: (On Material Package) Spillage (On Vehicle) Surveys Physical Damage to Container l Fire / Smoke Missing Material?
- 8. The Following Emergency Response Actions are Underway:
- 9. The Following Protective Actions are Reccmmended:
1
- 10. We Request the Following Onsite Support and Assistance from Offsite Sources:
- 11. Our Prognosis of the Emergency is that Conditions:
Are Under Control - Can be Expected to Terminate Within Hours Are Worsening STSC Communicator / Govt. Liaison Eng. Date/ Time
/
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[M PRIlfARY ALTERNATE ALTERNATE 00 g[ 5 (n g ACENCY or INDIVIDUAL PERSON CONTACTED LINK LINK LINK CALLER' DATE/ TIME @p qg National Weather od mo {M*Il Service NAN NAWAS 273-7511 / OO
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/ gg Arizona Radiation &s M *G P! Or Regulatory Agency NAN NAWAS 255-4845 / 4 C 3>
33 2 Arizona Dept. of Emergency Services NAN NAWAS 273-9880 / Maricopa County Dept. of Civil Defense y gg and Emergency Secvices NAN NAWAS 273-1411 / s o 91 m O y fl.f O N Maricopa County z Sheriff's Office 256-1011 NAN NAWAS' / o 6s N PVNCS , Mobile Maintenanee and .Emerg. Rad 10-Operations Manager Tele. Pager Telephone / PVNCS Mobile 5 5% Manager, Nuclear Eme rg .
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1 PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX G IMPLEMENTING PROCEDURE EPIP-07 Page 1 of 2 ON (' ~' NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 17 of 18 NOTIFICATION SYSTEMS USER'S GUIDE
- 1. Emergency Notification System Operation at plant end of circuit.
A. IDLE State - All lamps on all ENS phones are extinguished. . B. Outgoing call to NRC Operations Center.-
- 1. Control Roon or Shift Supervisor or Technical Support Center initiates call.
- a. All phones in CR, SSO, and TSC have steady lamps. .
- b. ,
Ringing tone is heard in handset of initiating phone.
- c. EOF ENS phone lamp blinks.
, d. Resident Inspector's office phone (s).' rings and times out, l' amp \. , ) on phone (s) continues to blink until Resident Inspector answers, or call ends.
- 2. EOF location initiates call.
- a. All phones in CR, SSO, TSC and EOF have a steady lamp.
- b. Initiating phone hears ringing tone in handset,
- c. Resident Inspector's office phone (s) rings and times out, lamp on phone (s) continues to blink until Resident Inspector -
answers, or call ends.
- 3. Resident Inspector's office initiates call.
[
- a. Resident Inspector's office phone (s) - steady lamp appears and l ringing tone is heard in handset,
- b. No indication at any plant location.
NOTE: The ENS circuit does not have privacy feature. a t- . IP 26-CCOA (8,62) _,, , , - - - , -r,
PVNGS EMERGENCY PLAN Qceouse IMPLEMENTING PROCEDURE M ENDIX G
,, 7, _,
O - REVISION NOTIFICATION PROCESS - NOTIFICATION OF UNUSUAL EVENT 0 Page 18 of 18 NOTIFICATION SYSTEMS USER'S GUIDE (CONT'D) C. Incocing call to plant.
- 1. All ENS phones ring and lamps blink, until call is answered (except Resident Inspector's office).
- 2. Resident Inspector's office - not answered.
Ring times out after 30 (to 90) seconds but lamp continues t3 blink until Resident Inspector answers. A re-ring occurs if plant does not answer before time out.
- 3. ENS line - ered at any plant location (except Resident Inspector).
- a. All phones stop rining and a steady lamp appears on all ENS phones in CR, SSO, and TSC. Also EOF if answering location.
- b. EOF ENS phone lamp will continue to blink if not answeri,ng
, location. .
- c. Resident Inspector office phone (s) - lamp will continue to blink until answered, or call ends.
- 4. Line answered by Resident Inspector,
- a. Phone (s) in Resident Inspector's office stop ringing and steady lamp appears on phone (s).
- b. All plant ENS phones continue to rip; and blink until answered then see item C-3 above. .
D. Troubles: A circuit trouble lite has been installed and labeled in the Control Room area. Suggested label: " ENS Line Failure When Lit." I
- 1. Normal condition: Lamp is extinguished.
I
- 2. Trouble condition: Lamp is illuminated. Notify NRC0C immediately by co=sercial line.
- 2. Site Package Configuration
> bin Package - Control Room (CR)
- Shift Supervisor's Office (SS0)
- Technical Support Center CTSC)
EOF Package - Emergency Operation Facilfty (EOF) Resident Package - Resident Inspector's Office (RI) ! m swo* casa
PVNGS EMERGENCY PLAN [7csome j i IMPLEMENTING PROCEDURE Epip_Os RsVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 page 1 of 20 ASme,nn m ut.a.-COT)Y ' r ., !
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PVIiGS SEI # ~' ' s
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APPROVED BY: [- [ W DATE /2 J- 67. DATE EFFECTIVE /j -/g-8j' DN-1985A/0196A PV2164CA 4.82)
PVN,GS EMERGENCY PLAN 2cewas [ i/' IMPLEMENTING PROCEDURE EPIP-08 REVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL DIERGENCY 0 Page 2 of 20 TARLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 3 .
2.0 REFERENCES
3 3.0 LIMITATIONS ANb PRECAUTIONS 4 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 4 4.3 Instructions 5-s .
.()
APPENDICES Appendix A - Notification and Alert Net (NAN) 9 Appendix B - NAN Notification Flow 10 Appendix C - APS Emergency Notification Fanout 11 Appendix D - Initial Emergency Message Form 12 Appendix E - Follow-up Emergency Message Form 13 Appendix F - E=ergency Notification Call Check List, Emergency Coordinator 16 i i Appendix G - Emergency Notification Call Check List, APS Dispatcher 18 Appendix H - Notification Systems User's Guide . 19 PV2?6 OCO A 48'32) .
, , .- - , - www-,
- - - - - 4
PVNGS EMERGENCY PLAN TceouRe , %. IMPLEMENTING PROCEDURE EPIP-08 REVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 3 of 20 a 1.0 OJBECTIVE 1.1 The objective of this procedure is to describe the notification process required upon declaration of an ALERT, SITE EMERGENCY, or GENERAL EMERGENCY. This process includes the following: Initial and follow-up notificatica to Federal, State, County, and Corporate offsite emergency organizations. Notification of off-duty personnel to augment the onshift emergency organization. Notification of the PVNGS Visitor's Center, APS Site Construction Office and Bechtel Emergency Control Center.
2.0 REFERENCES
... 2.1 Imp.lementing Referenecs'
\-)
- 2.1.1 EIIP-04, " ALERT Implementing Actions" 2.1.2 EPIP-05, " SITE EMERGENCY Implementing Actions" 2.1.3 EPIP-06, " GENERAL EMERGENCY Implementing Actions" 2.1.4 EPIP-07, " Notification Process - NOTIFICATION OF UNUSUAI.
EVENT" 2.1.5 EPIP-33, "Offsite Assistance" - 2.1.6 APS Emergency Response Facility Equipme.'t Manual 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. 2 2.2.3 10 CFR 50, Appendix E, " Domestic Licensing of Production and Utilization Facilities" a. (. PV216 0CDA t8 82)
1 PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE tyyp_og
/ ) REVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 4 of 20 3.0 LIMITATIONS AND PRECAUTIONS 3.1 The notification'of specific offsite agencies, such as emergency medical services and fire departments, is detailed in EPIP-33, "Offsite Assistance".
4.0 DETAILED PROCEDURE - 4.1 Personnel Indoctrination 4.1.1 Upon declaration of an ALERT, SITE EMERGENCY, or GENERAL EMERGENCY offsite notification will consist of three-primary telephone contacts: the NRC, S tate / County government, and APS corporate personnel. The NRC will be notified via the Emergency Notification System (ENS) dedicated line; State / County government via the Notification and Alert Net (NAN); and corporate personnel via dedicated telephone fanout, through the- Manager, , Nuclear Operations and the'Vice President, Electric
- - 5 Operations. The. National Warning System (NAWAS) will provide a back-up means of notification of State / County government and the Health Physics Network (HPN) will provide a back-up means of notification to the NRC.
Primary and alternate communications links for offsite notification are shown in Appendices F and G of this procedure. The Notification and Alert Net, NAN Notification Flow and APS Emergency Notification Fanout are illustrated in Appendices A through C. 4.1.2 The Notification Systems User's Guide (Appendix'H) provides the instructions necessary to ensure adequate operations of the primary and alternate systems available for offsite notification. The equipment addressed
- includes the ENS. Callers shall refer to this' guide to i ensure that successful contact is made in a minimal time period.
4.1.3 Notification of the NRC and State / County government should . be conpleted within 15 minutes, after declaration of the em2rgency class. Although there is no time requirecent for the notification of corporate personnel, it shall be i expedited to allow sufficient time for any subsequent ( , activation and staffing o the onsite and offsite emergency centers. l Mh hhd
PVNGS EMERGENCY PLAN. Qccsouas IMPLEMENTING PROCEDURE pp1p_og REVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 5 of 20 4.2 Prerequisites 4.2.1 An ALERT, SITE EMERGENCY, or GENERAL EMERGENCY has been declared, and procedure EPIP-04, 05, or 06 is being implemented. 4.3 Instructions - 4.3.1 Initial Notification The E=ergency Coordinator, or designee (STSC Communicator), shall perform the following: 4.3.1.1 Complete the Initial Emergency Message Content Form (Appendix D), and begin to fill in.as much information as is available, on the Follow-up Emergency Message Form (Appendix E). 4.3.1.2 By means of a single call,'lon .the Notification and f'~,. . Alert Net dedicated telephone, contact clie following ( ,' State / County agencies: Duty Hours (8:00 a.m. to 5:00 p.m. Monday-Friday) National Weather Service (NWS) Arizona Department of Public Safety (DPS) Arizona Radiation Regulatory Agency (4RRA) Arizona Department of Emergency Services (ADES). Maricopa County Department of Civil Defense and Emergency Services (MCCDES) [ Maricopa County Sheriff's Office (MCS0) ' NOTE Subsequent notification of affected agencies during off-duty hours shall be made per internal agency procedures. Off-Duty Hours (5:00 p.m. to 8:00 a.m. all day Saturday and Sunday) 1 l NWS s i DPS - f t MCSO i s 4.3.1.3 When contact is cade, the caller shall identify himself and request that the individuals obtain a copy of the Initial Emergency Message Form (Appendix D). PV216 0CDA (8.321
PVNGS EMERGENCY PLAN QCEDURE IMPLEMENTING PROCEDURE m ,_, . REVISION , NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENEPAL EiERGENCY 0 Page 6 of 20 4.3.1.4 When each individual has obtained a copy, read the completed Initial Escrgency Message Content Form, verbatim. 4.3.1.5 Offer to repeat information and reiterate as necessary. 4.3.1.6 Obtain the name of each person contacted and record on the Emergency Notification Call Check List, Emergency Coordinator (Appendix F). 4.3.1.7 Contact the NRC via the Emergency Notification System (ENS) dedicated telephone. 4.3.1.8 The caller shall identify himself and read the completed Initial Emergency Message Content Form, verbatim.
, 4,,.3.1.9 Offer to repeat infor=ation and reiterate as necessary..
r^, 4.3.1.10 Obtain the name of the persons contacted and record in
- x. j Appendix F.
4.3.1.11 Notify the NRC Resident Inspector in accordance with Appendix F if unable to contact with the ENS phone. 4.3.1.12 When contact is made, the caller shall identify himself and read the Initial Emergency Message Content Form, verbatic. 4.3.1>13 Offer to repeat informatio~n and reiterate as necessary.. 4.3.1.14 Obtain the name of the person contacted and record in Appendix F. 4.3.1.15 Via the PVNGS emergency telephone, notify the Maintenance and Operations Manager; Manager, Nuclear Operations; and the Vice President, Electric Operations. It is preferred that the Emergency Coordinator personally explain the emergency situation and plant status, to these key individuals. 4.3.1.16 Record the name of each person contacted, in ' Appendix F.
~
. 4.3.1.17 Notify additional personnel as listed in Appendix F,
..' obtain the name of the person contacted, and infor=
them of the situation. i PV2'64tA 45 82)
. PVNGS EMERGENCY PLAN PROCEDURE NO.
IMPLEMENTING PROCEDURE mg ( N. REVISION
e NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 7 of 20 4.3.1.18 Determine the need for additional personnel. . Direct the Security Director to call in additional personnel by utilizing the computer callout listing. The Secupity Director will use the updated (daily) computer print-out as an emergency telephone directory.
4.3.1.19 If an individual requests information not contained in the Initial Emergency Message Content Form, make -
. reasonable efforts to obtain and give the information only af ter all initial notifications have been made.
4.3.1.20 Contact the APS Dispatcher via'the micro-wave system. 4.3.1.21 When contact is made, the caller shall identify himself and request that the individual obtain a copy of the Initial Emergency Message Form. 4,.3.1.22 When the individual has obtained a copy, read the completed Initial Emergency Message Form, verbatim. fr' 4.3.1.23 offer to repeat information and' reiterate as necessary.
'. l 4.3.1.24 Obtain the name of the person contacted and record in
- Appendix F.
i 4.3.2 The APS Dispatcher shall perform the following:
. 4.3.2.1 Via commercial telephone, contact the following
. corporate personnel:
- a. Vice President, Nuclear Project Management (Alte rnate : VP, Engineering and Construction) i l
- b. Vice President, Corporate Finance Planning and Control (Alternate: VP, Economic Planning and Control)
- c. Manager, Legal Services (Alte rnate: Mancger, Contract Services) 4.3.2.2 When contact is made, the caller shall identify himself
, and read the following message:
"THERE IS AN ( ALERT, SITE EMERGENCY. or GENERAL EMERGENCY) IN PROGRESS AT THE PALO VERDE NUCLEAR I GENERATING STATION. YOUR ASSISTANCE IN THE EMERGENCY ORGANIZATION IS REQUESTED. PLEASE RESPOND ACCORDINGLY".
Pv216 EDA (8.821 1
PVNGS EMERGENCY PLAN o [ROCEDURE IMPLEMENTING PROCEDURE ,,91948 Cs ' REVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 8 of 20 4.3.2.3 Obtain the name of each person contacted and record on the Emergency Notification Call Check List, APS Dispatcher (Appendix G). 4.3.3 Follow-up Notificatien
~ The Emergency Coordinator, or designee, shall perform the following: -
4.3.3.1 Complete filling out the Follow-up Emergency Message Form (Appendix E). 4.3.3.2 Disseminate the information recorded on t'.te Follow-up Emergency Message Form as. requested by the offsite e=ergency management organization (i.e., NRC, ARRA, ADES, MCCDES) or as significant changes occur. 4.3.4 Additional Notification 4.'3.4.1 If notification of additional offsite agencies (i.e., * [" INF0, NSSS supplies, Bechtel, ambulance, hospital) is - v.' required, such notification shall be perfor=ed in accordance with EPIP-33, 4.3.5 When an emergency is reclassified, the appropriate notification processes (EPIP-07 or EPIP-08) will be initiated. l r i I PV2?6@CA i8,82) l l
PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROGEDURE APPENDIX A EFTP--0A Para 1c8 1
,_, REVISION NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 9 of 20 CR CR CR Unit i Unit 2 Unit 3
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f NWS GOVERNMENT ORGANIZATIONS MCSO OPS ' - f [E C ARRA A0ES ((9c m saa a-sa ! NOTIFICATION AND ALERT NET (NAN) - PALD VERDE NUCLEAR. GENERATING STATION (PVNGS)
PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE EPTP-08 APPENDIX B Pnoe 1 of 1 7 REVISION s NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 10 of 20 [0UTY/0FFDUTY HOURS)
-[ _
DUTY HOURS [8f0 AM TO 540 PM] PVNGS . I I I I I NWS ADES ARRA MCCDES I I I I ( DIRECTOR OIRECTOR OlHECTOR OlRECTOR DPS MCSO , l GOVERNOR l
; CDMMANDER COMMAN0liR <
OFF DUTY HOURS (Bif0RE 2.00 AM AND AFTER 5I0 PM] During off duty hours (i.e., outside of normal government work days and hours) the NAN notification flow appears above, EXCEPT MCCDES is notified via MCSO and ARRA is notified via ADES. MCCDES is Maricopa County Department of Civi( Defense & Emergency Services MCSO is Maricopa County Sheriff's Office . ARRA is Arizona Radiation Regulatory Agency ADES is Arizona Division of Emergency Services DPS is Arizona Department of Public Safety NWS is National Weather Service The Primary notification points are: ADES and MCSO. l The Alternate notification peints are: DPS and MCCDES. i NAN NOTIFICATION FLOW l
. PALO VERDE NUCLEAR GENERATING STATION-PVNGS PV2'$ 000A 18 82)
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O PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE APPENDIX C t'D T D-08 u n, 1 ,, p 1 f s REVISION
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PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE pp7p_og [ENDI D 1 REVISION (',T NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL DERGENCY 0 Page 12 of 20 INITIAL EMERGENCY MESSAGE ALERT, SITE EMERGENCY, GENERAL EMERGENCY PALO VERDE NUCLEAR GENERATING STATION
- 1. This is , at the Palo Verde Nuclear (name/ title)
Generating Station.
- 2. At we experienced an (time /date)
(ALERT, SITE DERGENCY, GENERAL EMERGENCY) Class incident. (circle one) (describe incident)
- 3. Eased on plant conditions, provide one of the following:
(a) There is NO, repeat _NO, radioactive release taking place and no special protective actions are recommended at this time.
.c' OR (b) A radioactive release _IS, repeat 3 , taking place. Wind is from at oph. We recommend that people in sectors remain indoors with windows and doors closed.
OR (c) A radioactive release ,IS, repeat _I_S, S taking place and we recommend that j evacuation of sectors , be considered. O,,R (d) Plant conditions are degrading with potential for fuel damage and ~ breach of containment integrity. Evacuation is recommended for in a two mile radius and sectors five miles downwind from the plant site. 4 Further infor=ation on incident conditions will be provided in followup ressages.
- 5. This is Palo Verde Authenticator .
Out. (See authenticator code) PV2?6-0 COA (4421
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PVNGS EMERGENCY PLAN Q caoms APPE E IMPLEMENTING PROCEDURE yp7p m , I. 9
.C'T NOTIFICATION PROCESS ALERT, SITE '
V EMERGENCY, OR GENERAL EMERGENCY 0 Page 13 of 20 FOLLO'4-UP EMERGENCY MESSAGE FORM
- 1. Reactor Operations:
Reactor System Status Power Level Pressure Temp. Flow (Pumps On) Cooling Mode ECCS Operating / Operable Containment Status Containment Isolated? Containment Temp. Containment Press Containment Radiation R/hr. Reactivity Controls Control Rods Inserted Status of Emer. Boration System-
, 2. Steam Plant Statss: , ,
<.a S/G Levels Equip. Failures Feedwater Source / Flow S/G Isolated?
- 3. Electrical Dist. Status:
Normal Offsite Power Available? Major Busses / Loads Lost Safeguards Eusses Power Source D/G Running? Loaded?
- 4. Radioactivity Released (or Increased Release)?
Liquid / Gas? Location / Source of Release Elevation Release Rate Duration . Stopped? Release Monitored Amount of Release
% Tech. Specs, a.
Increased Radiation Levels in Plant: Location (s) Radiation Level (s) Areas Evacuated Maximum Offsite Dose Rates Integrated Dose Location
/
PV216-0CCA ta 82)
PVNGS EMERGENCY PLAN IQCEwRE IMPLEMENTING PROCEDURE APPENDI E
,,y_y ,,
. REVISIOPJ 1.
) NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY i 0 Page 14 of 20 FOLLOW-UP EMERGENCY MESSAGE FORM (CONT'D)
- b. Meteorology Wind Direction From Wind Speed l T ("C or *F) Sigma Theta (Meter /Sec or Miles /Hr)
Temperature (*C or 'F) ' Stability Class A B C D E F Raining (Yes/No) i'
- 5. Projected Doses:
Dose Rates Integrated Dose Site Boundary 2 miles 5 miles 10 miles Sectors Contamination (Surface): Inplant Onsite Offiste if%
\ .!
- 6. Security / Safeguards:
- a. Bomb Threat: Search conducted?
Search Results Site Evacuated? _ I
- b. Extortion: Source (Phone, Letter, etc.)?
Location of Letter
- c. Intrusion: Insider? Outsider?
Furthest Point of Intrusion Fire Arms Related? Stolen / Missing Material?
- d. Rx Oper./ Demonstration: Size of Group Demands j Violence? Fire Arms Related?
- e. Sabotage / Vandalism: Radiological? Arson Involved?
Stolen / Missing Material?
~.
W276-0CCA (8.32)
PVNGS EMERGENCY PLAN Qcsoune IMPLEMENTING PROCEDURE APPE I E y ,_ng , ,,
, - ~
REVISION ( ^ NOTIFICATION PROCESS ALERT, SITE DERGENCY, OR CENERAL DERGENCY 0 Page 15 of 20 FOLLOW-UP EMERGENCY MESSAGE FORM (CONT'D)
, 7. Transportation:
Mode (Road / Rail / Air /etc.) Carrier Exact Location Type of Material (HEU/ Spent Fuel / Cat III/Other) ~ Description of Shipment , Labels: (On Material Package) (On Vehicic) Spillage Surveys Physical Damage to Container Fire /Scoke Missing Material?
- 8. The Following Emergency Response Actions are Underway:
',7.
li ,' 9. The Following Protective Actions are Recommended:
- 10. We Request the Following Onsite Support and Assistance from Offsite Sources:
l 11. Our Prognosis of the Etergency is that Condition.:: Are Under Control Can be Expected to Terminate Within Hours l Are Worsening Pv216 000A g8.82)
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- CHECK LIST $0 g- Em
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- E:ncrgency Services NAN NAWAS 273-9880 /
Maricopa County Dept. of Civil Defense and Emergency Services E 273-1411 NAN NAWAS / $ m ~$ @ Naricopa County 6 Z y a c-Sheriff's Off~ Ice NAN NAWAS' 256-1011 -
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDEK E IMPLEMENTING PROCEDURE EPIP-08 page 1 of 2 REVISION e NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 - Page 19 of 20 NOTIFICATION SYSTEMS USER'S GUIDE
- 1. Emergency Notification System Operation at plant end of circuit.
A. IDLE State - All lamps on all ENS phones are extinguished. B. Outgoing call to NRC Operations Center. ,
- 1. Control Room or Shift Supervisor or Technical Support Center initiates call.
- a. All phones in CR, SSO, and TSC have steady lamps,
- b. Ringing tone is heard in handset of initiating phone.
- c. EOF ENS phone lamp blinks.
- d. Resident Inspector's office phone (s) rings and. times ou.t, lamp on phone /s) continues to blink until Resident Inspector
}
- x. /
answers, or call ends.
- 2. EOF Iccation initiates call. '
- a. All phones in CR, SSO, TSC and EOF have a steady lamp.
- b. Initiating phone hears ringing tone in handset. .
- c. Resident Inspector's office phone (s) rings and times out, lamp on phone (s) continues to blink until Resident Inspector answers, or call ends.
- 3. Resident Inspector's office initiates call,
- a. Resident Inspector's office phone (s) - steady lamp appears and ringing tone is heard in handset.
- b. No indication at any plant Ibcation.
- 1 l NOTE: The ENS circuit does not have privacy feature.
l . Pv216 0 COA (S.82) I
PVNGS EMERGENCY PLAN Q*csouas
- IMPLEMENTING PROCEDURE ' APPENDIX H EPIP-08 Paee 2 of 2 NOTIFICATION PROCESS ALERT, SITE EMERGENCY, OR GENERAL EMERGENCY 0 Page 20 of 20 i
NOTIFICATION SYSTEMS USER'S CUIDE (CONT'D) C. Incoming call to plant.
- 1. All ENS phones ring and lamps blink, until call is answered (except Resident Inspector's office).
- 2. Resident Inspector's office - not answered. -
- Ring ti=es out after 30 (to 90) seconds but lamp continues to blink until Resident Inspector answers. A re-ring occurs if plant does not answer before time out.
- 3. ENS line answered at any plant location (except Resident Inspector),
- a. All phones stop rining and a steady lamp appears on all ENS phones in CR, SSO, and TSC. Also EOF if answering location.
+
- b. EOF ENS phone lamp will cont.1nue to blink if not answering
. location. ,
- c. Resident Inspector office phone (s) - lamp will continue to blink until answered, or call ends.
a 4 Line answered by Resident Inspector, a. Phone (s) in Resident Inspector's office stop ringing and steady lamp appears on phone (s).
- b. All plant ENS phones continue to ring and blink until answered then see item C-3 above.
D. Troubles: A circuit trcuble lite has been installed and labeled in the Control Room arca. Suggested label: " ENS Line Failure When Lit." j 1. Normal condition: Lamp is extinguished. l
- 2. Trouble condition: Lamp is illuminated. Notify NRCOC it=ediately by commercial line.
Site Package Configuration Main Package - Control Room (CR)
- Shift Supervisor's Office (SS0) '
- Technical Support Center (TSC) ~
EOF Package - E=ergency Operation Facility (EOF) Resident Package - Resident Inspector's Office (RI) Pv2?$.000A (8 621 i
PROCEDURE PVNGS EMERGENCY PLAN N O. IMPLEMENTING PROCEDURE EPIP-ll REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 1 of 28 ASSICMD COPY - P V N G S Si,I # 4'd d _, i .. APPROVED BY: _ . ,dd-. [ -- fju. ,, , s
-- -.... DATE , 8s DATE EFFECTIVE ///-/-[8 f
( DN-1664A/0196A Pv2?6 CCCA t8,83
PROCEDURE PVNGS EMERGENCY PLAN N O. -
^
IMPLEMENTING PROCEDURE EPIP-11 ( TECHNICAL SUPPORT CENTEPJSATELLITE TSC ACTIVATION O Page 2 of 28 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 4
2.0 REFERENCES
4 3.0 LIMITATIONS AND PRECAUTIONS 4 4.0 DETAILED PROCEDURE 5 4.1 Personnel Indoctrination 5 4.2 Prerequisites 6 4.3 Instructions 6 APPENDICES Appendix A - Energency Coordinator (Duty Manager) Check List 9 (Satellite TSC) ( Appendix B - Shift Technical Advisor Check List 11 l (Satellite TSC) Appendix C - Radiation Protection Monitor Check List 12 (Satellite TSC) l Appendix D - Satellite TSC Connunicator Check List 13 i Appendix E - Shif t Systens Engineer Check List (Prelininary 14 ' TSC Activation) Appendix F - Energency Coordinator (Manager, Nuclear 15 Operations) Check List Appendix G - Technical Engineering Cootdinator Check List 17 Appendix H - Radiological Protection Coordinator Check List 18 PV216 00CA 48.82)
FVNGS EMERGENCY PLAN PROCEDURE N O. IMPLEMENTING PROCEDURE EPIP-ll EWSION TECHNICAL SUPPORT CENTER / SATELLITE TSC . ACTIVATION O Page 3 of 28 APPENDICES (CONT'D) . SECTION PAGE NUMBER Appendix I - Security Director Check List 19 - Appendix J - Energency Maintenance Coordinator Check List 20 Appendix K - Hazards Control Ccordinator Check List 21 Appendix L - Personnel Resources Coordinator Check List 22 Appendir: ?1 - Chemistry Coordinator Check List 23 Appendix N - Reactor Analyst Check List 24 i t Appendix 0 - Computer Support Coordinator Check List 25 , Appendix P - Field Team Consunicator Check List 26 Appendix Q - TSC Readiness Check List 27
\
Appendix R - TSC Ploor Plan 28 I l l I 1 l i _ Pv2'6 000 A 69/82) i
- s. s c
PVNGS EMERGENCY PLAN PROCEDURE NO.
~ EPIP-ll IMPLEMENTING PROCEDURE TECHNICAL SUPPORT CENTER / SATELLITE TSC REVISION ACTIVATION . O Page 4 of 28
~
1.0 OBJECTIVE 1.1 The objective of this procedure is to provide instructions for the activation of the Technical Support Center (TSC) and the Satellite TSC (STSC). This procedure addresses the following: o Activation of the affected unit Satellite TSC. o Preliminary activation of the Technical Support Center by available onshift personnel. o Complete activation of the Technical Support Center by those onsite emergency response personnel assigned to this emergency response facility.
2.0 REFERENCES
)
2.1 Implementing References ' ( 2.1.1 EPIP-01, "PVNGS Emergency Organization" l 4 2.1.2 EPIP-04, " ALERT Implementing Actions" 2.1.3 EPIP-05, " SITE EMERGENCY Implementing Actions" 2.1.4 EPIP-06, " GENERAL EMERGENCY Implementing Actions" 2.1.5 APS Emergency Response Facility Equipment Manual 2.2 Developmental References 2.2.1 NUREG 0654, Rev. 1, "Criterig 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. 2 3.0 LIMITATIONS AND PRECAUTIONS 3.1 The Satellite TSC and the TSC may be used by designated personnel for nor=al daily activities as well as for training l and emergency drills. Use of these facilities shall be I limited to activities that will not degrade preparedness to > react to abnormal conditions or reduce system (s) reliability. m u caissa [ l l ,
PVNGS EMERGENCY PLAN PROCEDURE NO.
.3 IMPLEMENTING PROCEDURE EPIP-ll TECHNICAL SUPPORT CENTER / SATELLITE ISC ACTIVATION O Page 6 of 28 4.1.3 The functions which will be performed in the TSC are as follous:
o Manage onsite emergency response. o Direct onsite radiological protection activities. o Direct emergeacy maintenance. o Direct personnel accountability and site security. A o Direct safety and hazards control. o Perform engineering and technical analysis for Control Room support. o Perform reactor analysis. t i o Provide emergency I&C support. ( o Provide computer and chemistry tedhnical support. o Provide dose rate projections. o Direct field monitoring activities. 4.1.4 The TSC emergency supply storage area contains a supply of calibrated radiological monitoring equipment, protective clothing, communications equipment, portable lighting, and additional supplies as listed in EPIP-38. 4.2 Prerequisites 4.2.1 Activation of the Satellite TSC shall take place upon declaration of a NOTIFICATION OF UNUSUAL EVENT. 4.2.2 Activation of the TSC and augmentation of the Satellite TSC staff by the onsite Emergency Organization shall take place upon declaration of an ALERT or more severe emergency. l 4.3 Ins tructions 4.3.1 Activation of the Satellite TSC 4.3.1.1 The following onshif t Emergency Organization personnel
'a shall report to the affected unit Satellite TSC and complete their designated check lists:
PV2*6 C A 18 83
PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE EPIP-il TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION - 0 Page 7 of 28
- 1. Emergency Coordinator (Duty Manager) - Appendix A.
- 2. Shift Technical Advisor - Appendix B.
- 3. Designated Radiation Protection Tecnnician (Radiation Protection Monitor) - Appendix C.
- 4. Designated Nuclear Operator (STSC Communicator) -
Appendix D. 4.3.1.2 The following onsite Emergency Organization personnel shall report to the affected unit Satellite TSC (if required), relieve their respective onshift counterpart, and complete their check lists as necessary.
- 1. Satellite TSC Communicator - Appendix D. '
- 2. Radiation Protection Monitor - Appendix C.
I 4 . 3.1. 3' The Operations. Advisor shall report to the STSC and provide technical and operational advice to the Shif t Supervisor. He will ensure that information flow is maintained between the TSC and the Control Room. 4.3.2 Preliminary Activation of the Technical Support Center 4.3.2.1 The Emergency Coordinator shall contact the Shift Systems Engineer and direct him to perform the preliminary activation of the TSC per Appendix E. 4.3.2.2 The Shift Analysts shall report to the TSC and assist the Shif t Systems Engineer in carrying out his function as Technical Engineering Coordinator. 4.2.3.3 The Security Shift Captain shall report to the TSC, i assume the duties of Security Director, and complete the check list in Appendix I. 4.3.3 Complete Activation of the Technical Support Center 4.3.3.1 The Technical Engineering Coordinator of the onsite Emergency Organization shall report to the TSC, relieve the Shif t Systems Engineer, and complete the c, check list in Appendix E (as necessary) and Appendix G. h P \ PV2?6 000A tS t?)
, , , - - - . a. -
PVNGS EMERGENCY PLAN PROCEDURE N O. IMPLEMENTING PROCEDURE
} Epip-li TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 8 of 28 1 4.3.3.2 The Security Director of the onsite Emergency .
Organization shall report to,the TSC, relieve the Security Shif t Captain, and complete the check list in Appendix I (as necessary). 4.3.3.3 The following onsite Emergency Organization personnel shall report to the TSC and complete their designated - check lists:
- 1. Emergency Coordinator (Manager, Nuclear Operations) - Appendix F.
- 2. Radiological Protectio 2 Coordinator - Appendix H.
- 3. Emergency Maintenance Coordinator - Appendix J.
- 4. Hazards Control Coordinator - Appendix K.
- 5. Personnel Resources Coordinator - Appendix L.
( "'% . ( ,j 6. Chemistry Coordinator - Appendix M.
- 7. Reactor Analyst - Appendix N.
- 8. Computer Support Coordinator - Appendix 0.
- 9. Field Team Communicator - Appendix P.
4.3.4 Declaration of TSC Readiness 4.3.4.1 Upon completion of TSC personnel check lists, the Manager, Nuclear Operations shall complete the TSC l Readiness Check List of Appendix 0 and notify affected onsite emergency response facilities. l l ., \
\ ,:
PV216 CODA (8 *J) L
l
= \
_ PVNGS EMERGENCY PLAN PROCEDURE N O. d IMPLEMENTING PROCEDURE EPIP-ll APPENDIX A Page 1 of 2 TECHNICAL SUPPORT CENTER / SATELLITE TSC XCTIVATION O Page 9 of 28
- JUTY MANAGER CHECK LIST (Satellite TSC)
ACTION ITEMS TIME / INITIALS
- 1. Contact Shift Supervisor and review:
- a. The logic used to, establish the classification of the /
event.
- b. Status of plant conditions. /
- c. Corrective actions that are being taken. /
- 2. Appoint Nuclear Operator to act as Satellite TSC /
Communicator and commence notification per EPIP-07 and EPIP-08 (as appropriate).
- 3. If an ALERT or more severe emergency is declared, instruct /
/] the Security Director to commence notification of the
(/ Onsite and Offsite Emergency Organization.
- 4. Ensure that the following check lists-are completed by the appropriate personnel: ;
Check List B - Shift Technical Advisor / CheckListC-RadiationProtect{on) Monitor / Check List D - STSC Communicator 1 /
- 5. As necessary:(2)
- a. Determine necessity to evacuate onsite personnel /
(EPIP-19). l b. Authorize emergency workers to exceed PVNGS / administrative exposure limits (EPIP-18). 1
- c. Provide protective action recommendations to /
offsite' emergency management agencies (EPIP-15). l i I
's PV216 OCCA 9-62)
,. . ^*
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX A
~ 'y IMPLEMENT!NG PROCEDURE EPIP-11 Page 2 of 2 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC '
ACTIVATION O Page 10 of 28 DUTY MANAGER CHECK LIST (CONT'D) . (Satellite TSC) NOTES: (1) When this individual arrives at the STSC he will relieve the Nuclear . Operator of notification duties. (2) These action items would normally be necessary during a high level emergency situation (i.e., SITE and/or GENERAL EMERGENCY) and would normally be the responsibility of the onsite Emergency Coordinator. If this position has not been assumed you must take the appropriate actions. These responsibilities cannot be delegated. Signature Date
,r.
% . .l l
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# 3 l
/
PV2?6 0CC A t8.8')
PROCEDURE PVNGS EMERGENCY PLAN N O.
} IMPLEMENTING PROCEDURE EPIP-11 TECHNICAL SUPPORT CENTER / SATELLITE TSC <
ACTIVATION O Page 5 of 28 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination - 4.1.1 During a NOTIFICATION OF UNUSUAL EVE::T, direction and coordination of onshift emergency operations will be provided by the Emergency Coordinator at the Satellite TSC. During an ALERT, or more severe classification, emergency assessment and control will 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 Emergency Organization, the following activities will take place in the Satellite TSC: o Environmental assessment (offsite dose projections). , Field Monitoring Tean direction by the Radiation
~
., s. o
) Protection Monitor.
o Technical analysis by the Shif t Technical Advisor (STA). o Emergency management by the Emergency Coordinator (EC). o Initial notifications including infor=ation regarding protective actions (if required) by the Satellite TSC Co municator. 4.1.2 When the onsite Emergency Organization has been activated, the responsibility for the above listed functions will be transferred to the TSC and/or the Emergency Operations-Facility (EOF). 4.1.2.1 The Satellite TSC will then function as an extension of the TSC to provide direct technical support to the Control Roon personnel in the areas of: o Engineering and technical analytical support. o Reactor analytical support. o {2 . Unit operations support. o Radiological analyticc1 support. PV2'6 OCCA (8 Sh
~ . , . . - 4
.i
v . PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX B ( , IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC l ACTIVATION O Page 11 of 28 SHIFT TECHNICAL ADVISOR (STA) CHECK LIST (Satellite TSC) ACTION ITEMS TIME /INITLiLS
- 1. Activate the SPDS. /
- 2. Monitor SPDS infor:::ation and develop trend data. /
'3. Provide the Shif t Supervisor with trend data and assist in /
determining which corrective actions should be taken to mitigate the event. Signature Date
. 1 ~ ..
r^*" t _" PV2?6-000A (& 22)
e PVNGS EMERGENCY PLAN PROCEDURE NO.
^; APPENDIX C
. IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 12 of 28 RADIATION PROTECTION MONITOR CHECK LIST -
(Satellite TSC) ACTION ITEMS TIME / INITIALS
- 1. As necessary:
- a. Perform initial offsite dose rate projection /
(EPIP-14A and 143).
- b. Inform Duty Manager of dose rate projection results and /
assist in determining what type of protective action recommendations are necessary (EPIP-15).
- c. Direct activities of onsite and offsite Field Monitoring /
Teams (EPIP-16 and 17).
- d. Evaluate the need to administer Potassium Iodide (KI) /
(EPIP-26).
,) 2. Contact OSC Coordinator and ensure that:
- a. Sufficient radiological protection equipment is available /
to OSC personnel.
- b. That the OSC continuous air monitors and area alarm /
monitors are functioning and determine initial radiation levels at OSC.
- 3. When the onsite Emergency Organi=ation is activated /
provide the following informat' ion:
- a. Contact the ' Radiological Protection Coordinator and /
provide him with (1) OSC radiation protection status (i.e., equipment, " background" levels, etc.); (2) as appropriate, the status of dose projections, protective action recommendations, onsite and offsite Field Monitoring Teams.
- b. Monitor radiological assessment activities of the onsite /
Emergency Organization and provide Control Room personnel with appropriate information. ( Signature
=
I Date i ,,j ' I PV2'6 0CCA 48 80)
,,%4 w = ~
4 PVNGS EMERGENCY PLAN PROCEDURE l NO. APPENDIX D (} IMPLEMENTING PROCEDURE TECHNICAL SUPPORT CLRTER/SATEIIITE TSC EPIP-11 ION Page 1 of 1 ACTIVATION O Page 13 of 28 SATELLITE TSC CO'CIUNICATOR Cl!ECK LIST , ACTION ITDIS TIME / INITIALS
- 1. As directed by the Emergency Coordinator initiate notification /
process per EPIP-07 and EPIP-08 (as appropriate).
- 2. When relieved by designated onsite STSC Communicator provide /
him with status of no'ification t process. _
- 3. When notification process is completed inform the Emergency /
Coordinator.
- 4. Ensure STSC communications equipment is operable. /
- 5. Maintain Communication Logbook. /
Signature p ~.
')
,j .
Date 5 6 l l t 1 M G.J l PV2?e OCOA (8.83
* ' ~ ' ~ ~ ~ ' ' '
4 PVNGS EMERGENCY PLAN PROCEDURE NO. () e s APPENDIX E IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 REWSION TECHNICAL SUPPORT CENTER / SATELLITE TSC
' ACTIVATION O Page 14 of 28 SHIFT SYSTEMS ENGINEER CHECK LIST -
(Preliminary TSC Activation) ACTION ITEMS TIME / INITIALS
- 1. Ensure communication devices are operable in the TSC in /
accordance with the APS Emergency Response Facility - Equipment Manual. , EC/EOD Hotline Radiological Line Plant & Security Radio CR Lines Environmental Assessment Line EOF Dedicated Line Technical Line OSC Dedicated Line Maintenance Control Line STSC Dedicated Line
- 2. Ensure SPDS is operational. /
- 3. Ensure CRACS is operational. /
- 4. Ensure TSC computer terminals are operable.
{ /
- 5. Break out manual dose projection maps and overlays from /
emergency lockers.
- 6. Break out onsite/offsite environmental sampling location maps. /
- 7. Report TSC readiness to Emergency Coordinator. /
Signature Date
*?
LY - PV216-00C4 (S 62)
d PVNGS EMERGENCY PLAN PROCEDURE N O. O, IMPLEMENTING PROCEDURE EPIP-11 APPENDIX F Page 1 of 2 TECHNICAL SUPPORT CENTER / SATELLITE TSC
' ACTIVATION O Page 15 of 28 EMERGENCY COORDINATOR (MANAGER, NUCLEAR OPERATIONS) CHECK LIST ACTION ITEMS TIME / INITIALS
- 1. Contact the Duty Manager and review:
- a. The logic used to establish the classification of the /
~
event. ,
- b. Status of plant conditions.
/
l c. Status of notification of Federal, State, and County / emergency manage =ent agencies.
- d. Status of onsite/offsite PVNGS Emergency Organization /
notification process. e. Protective action recoccendations made to date and his / knowledge of state's action (s) (if necessary). 1
~ (;g,/ 2. Review Personnel Accountability Report (EPIP-20). /
- 3. Determine need to evacuate nonessential personnel (required for SITE and/or GE'?ERAL EMERGENCY, EPIP-19).
/
4.* Make protective action recot=endations, as appropriate, con- / ' sidering existing plant conditions and potential degradation (EPIP-15). l 5.* As the situation warrants reclassify the event per EPIP-02. /
- 6. Review the results.of dose projections. / .
l 7. Authorize emergency exposure limits as necessary (EPIP-18). l / ! 8. Authorize dispatch of onsite and offsite Survey Teams as / necessary (EPIP-16 and 17).
- 9. Authorize dispatch of Search and Rescue Teams as necessary. /
(EPIP-21). ! 10. Complete the TSC Readiness Check List, Appendix P of this ! / procedure. l 1 r ,, PV216 0CCA 18 Sh l 1 i
c. PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX F () ~ IMPLEMENTING PROCEDURE EPIP-11 Page 2 of 2 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 16 of 28 EMERGENCY COORDINATOR O!ANAGER, NUCLEAR OPERATIONS) CHECK LIST- (CONT'D) NOTE:
- These items cannot be delegated; however when the EOF is activated and the l Emergency Operations Director assu=es control, the responsibility for -
these itecs will be , transferred to him. Signature Date i s% l l l l
.? , ". I u*
PV2'6 EDA (84) l ( . , . . . . --
PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX G
*y IMPLEMENTING PROCEDURE EPIP-ll Page 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 17 of 28 TECHNICAL ENGINEERING COORDINATOR CHECK LIST ~,
ACTION ITEMS TIME / INITIALS I e
- 1. Access records management and obtain needed technical / :
documents, procedures, blueprints. j i" i
- 2. Ensure that the following check lists are cecpleted by the '
appropriate personnel- {; I Check List J - Emergency Maintenance Coordinator Check List K - Hazards Control Coordinator
/ ] 8 Check List M - Chemistry Coordinator
/
/ tl Check List N - Reactor Analyst /
Check List 0 - Computer Support Coordinator -
/ .
- 3. Determine the need for additional engineering and technical /
support personnel. Contact such personnel as necessary. ,,
't j ?%
j , Signature ;'
- t. .
Date e 9 y r 4 l\ ,/ W2'6 OCCA e6 8h
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- ~
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PROCEDURE PVNGS EMERGENCY PLAN NO. APPENDIX H
', s i IMPLEMENTING PROCEDURE EPIP-11 Page 1 of i TECHNICAL SUPPORT CENTER /SATELLlTE TSC ACTIVATION 0 Page 18 of 28 RADIOLOGICAL PROTECTION COORDINATOR CHECK LIST .
ACTION ITEMS TIME / INITIALS
- 1. Check that all materials needed to perform assessments are available.
- a. Meteorological overisys and base maps.
/
~
- b. Procedures and forms. /
- 2. Access the Rad / Met computer per the provisions of the APS /
Emergency Response Facility Equipment Manual.
- 3. Contact the affected unit's STSC and determine:
- a. Extent of radiological releases and plant conditions. /
- b. Location of onsite and offsite monitoring teams (if. /
gT]^ dispatched). Q.>
/
- 4. Determine the need for additional personnel to assist in performing dose assessment.
- 5. When sufficient personnel and materials are available, inform /
the Emergency Coordinator that the TSC is ready to assume the responsibility for dose assessments. l Signature l Date l l
~
l i l PV216 000A 18 623
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX I r ') IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 TECHNICAL SUPPORT CENTER /5ATELLITE TSC
~
ACTIVATION 0 Page 19 of 28 SECURITY DIRECTOR CHECK LIST ACTION ITEMS TIME / INITIALS
- 1. Check statioa security by contacting the Central Alarm /
Station Operator.
- 2. Confer with the Security Shift Captain concerning protected /
drea p*'*sonnel accountability and security measures for station access by offsite assistance personnel.
- 3. Contact personnel at the Firing Range, inform them of the /
situation and provide instructions as appropriate.
- 4. Determine the need for additional security force personnel. /
Contact such personnel as necessary. Signature g"N j ,
.Date
..)
PV?'6 OCOA ($<8Q
PROCEDURE PVNGS EMERGENCY PLAN N O. APPENDIX J _s
'. IMPLEMENTING PROCEDURE EPIP-11 Fage 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC
- ACTIVATION 0 Page 20 of 28 EMERGENCY MAINTENANCE COORDINATOR CHECK LIST -
i ?i ACTION ITEMS TIME / INITIALS j
<1
- 1. Access records management and obtain needed technical / :l documents, procedures, blueprints. 3;l
.i1
- 2. Determine the need for additional mechanical support / l personnel. Contact such personnel as necessary. ,' i '
N: t$; Signature Mi Date Il)
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PVNGS EMERGENCY PLAN Q'CEDURE APPENDIX K
, IMPLEMENTING PROCEDURE rpIp_11 page 1 of 1 REVISION TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 21 of 28 HAZARDS CONTROL COORDINATOR CHECK LIST -
ACTION ITD!S TIME / INITIALS
- 1. Determine areas that may pose a hazard to personnel and inform /
l the Emergency Coordinator, OSC Coordinator of the areas. l ~
- 2. Assist the Radiological Protection Coordinator with ALARA /
efforts.
- 3. Direct the formation of Search and Rescue Teams as required. /
Signature i Date l l f~x
}< a \ l .
l l l I , .i/ l PV2t6 OCCA t8 823 \ i t
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PVNGS EMERGENCY PLAN PROCEDURE NO. AppggpIx L IMPLEMENTING PROCEDURE EPIP-11 P,sge 1.of 1 TECIINICAL SUPPORT CENTEPdSATELLITE TSC
~
ACTIVATION 0 Page 22 of 28 PERSONNEL RESOURCES COORDINATOR CHECK LIST , ACTION ITE!S TIME / INITIALS_
- 1. Assist the Security. Director with accountability per EPIP-20. /
- 2. Develop 24-hour manning requirements and augment staffing as / .
required. Signature Date s l e PV215.CCCA (8 82) i l
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX M
/ -
IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC ~ ACTIVATION 0 Page 23 of 28 CHD!ISTRY COORDINATOR CHECK LIST ACTION ITEMS TD!E/INITIAIS
- 1. Assist the Radiological Protection Coordinator, as necessary, /
in the set-up of dose assessment materials.
- 2. Contact the onshif t Chemistry Technician (via station /
telephone) and obtain pertinent plant chemistry data.
- 3. Determine the need for additional chemistry support personnel. /
- 4. Confer with the Technical Engineering Coordinator to /
deter =ine needs concerning plant chemistry data for assessment of core conditions and release potentials. Signature Date 5 I l o PV24 OCCA ($ 62)
l . PROCEDURE PVNGS EMERGENCY PLAN N O. APPENDIX N IMPLEMENTING PROCEDURE EPIP-11 Page 1 of'l TECHNICAL SUPPORT CENTER / SATELLITE TSC ~ ACTIVATION 0 Page 24 of 28 1-REACTOR ANALYST CHECK LIST .
' ACTION ITEMS TIME / INITIALS
- 1. Assess core parameters in order to determine current /
core conditions.
- 2. Inform the Technical Engineering Coordinator of /
- recom=endations for operation that would result in i safer ccre conditions.
I 3. Access records canagecient and obtain needed technical /
- documents, procedures, systems, diagrams.
l 4. Determine the need for additional reactor support personnel. / t [ Signature Date i . - - e a
)
I W216 TO4 46 62)
~- . PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX 0 O IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 4 TECHNICAL SUPPORT CE' ITER / SATELLITE TSC
' ACTIVATION O Page 25 of 28 COMPUTER SUPPORT COORDINATOR CHECK LIST -
ACTION ITEMS TIME / INITIALS
- 1. Access computers (CRACS, SPDS) in accordance with the APS /
Emergency Response Facility Equipment Manual and determine plant parameters. ~
- 2. Provide requested data to the Emergency Coordintor, as the /
situation warrants.
- 3. Detemine the need for additional computer support personnel. /
Signature Date r
\ m.
W PV716 0004 18 82)
e PVNGS EMERGENCY PLAN PROCEDURE
-, N O. APPENDIX P IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC ACTIVATION O Page 26 of 28 FIELD TEAM C0mIUNICATOR CHECK LIST -
ACTION ITD!S TIM 5/ INITIALS
- 1. Report to the Radiological Protection Coordinator and obtain /
information on the deployment of Field Monitoring Teams.
- 2. Ensure Field Team co=cunications equipment is operable. /
- 3. Assist the Radiological Protection Coordinator in the /
performance of dose assessment calculations as necessary. Signature Date ,- N
~s' PV216 0CDA t&8.7
.~ .
PVNGS EMERGENCY PLAN PROCEDUPE NO.
'l APPE'IDIX Q IMPLEMENTING' PROCEDURE EPIP-11 Page 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC .
' ACTIVATION O Page 27 of 28 TSC READINESS CHECK LIST ACTION ITD4S TIME / INITIALS
- 1. Conduct briefing with available TSC personnel. As a minimum, the following items shall be discussed:
- a. Adequacy of activation. /
- b. Ability of assigned personnel tc assume their emergency /
duty roles.
- c. Operability of equipment (installed as well as portable /
emergency).
- 2. The Maintenance and Operations Manager or alternate shall:
- a. Assume the role of Emergency Coordinator. /
' b. Declare the TSC fully operational and inform the
(_)g following onsite emergency response facilities: (1) STSC (affected unit) / _ (2) Each unit's Control Room / (3) EOF / (4) APS Site Construction Office / (5) Bechtel E=crgency Control Center / Emergency Coordinator Signature Date
%/
P/216 000A to 82)
N. s
- PROCEDURE PVNGS EMERGENCY PLAN APPENDIX R
, ,? IMPLEMENTING PROCEDURE EPIP-11 Page 1 of 1 TECHNICAL SUPPORT CENTER / SATELLITE TSC A'CTIVATION O Page 28 of 28
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PALO VERDE NUCLEAR GENERATING STATION (PVNGS) ! Source: Bechtel Power Corporation ,,,g g., g Nors: o. .a. o.s.aa.ai r
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, PVNGS EMERGENCY PLAN PROCEDURE NO.
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IMPLEMENTING PROCEDURE EPIP-12
-OPERATIONS SUPPORT CENTER ,
' ACTIVATION O Page 1 of 8 ASSIGr3D COPY c' ' . R ('?
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APPROVED BY: gag-e,,f, DATE d AIE EFFECTIVE //)-d-PS DN-1666A/0196A PV21% 000A (8 82)
PROCEDURE PVNGS EMERGENCY PLAN NO.
' r.
IMPLEMENTING PROCEDURE EPIP-12 EVISION OPERATIONS SUPPORT CENTER dCTIVATION O Page 2 of 8 TABLE OF CONTENTS . SECTION PAGE NUMBER 1.0 OBJECTIVE 3- -
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 _. 4.2 Prerequisites 5 ( ') 4.3 Instructions 5 ( APPENDICES Appendix A - OSC Coordinator Check List 7 Appendix B - OSC Hab'.tability Criteria 8 l s
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PVNGS EMERGENCY PLAN PROCEDURE N O. m IMPLEMENTING PROCEDURE EPIP-12 SiON OPERATIONS SUPPORT CENTER ACTIVATION O Page 3 of 8 1.0 OBJECTIVE , 1.1 The objective of this procedure is to provide instructions for the activation of the Operations Support Centers (OSC's). This procedure addresses the following: o Activation of the unit OSC o Activation of the alternate OSC (Service Building)
2.0 REFERENCES
2.1 Implementing References 4 2.1.1 EPIP-01, "PVNGS Emergency Organization" 2.1.2 EPIP-04, " ALERT Implementing Actions" 2.1.3 EPIP-05, " SITE EMERGENCY Implementing Actions" ( ) 2.1.4 EPIP-06, " GENERAL EMERGENCY Imple=enting 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" 2.2.2 NUREG 0696, Feb. 1981, " Functional Criteria for Emergency Response Facilities" 2.2.3 PVNGS Emergency Plan, Rev. 2 3.0 LIMITATIONS AND PRECAUTIONS l 3.1 Since no habitability criteria are established for the OSC's, i evacuation of OSC personnel may be required as dictated by radiological / environmental emergency conditions. If the area alarm monitor and/or the continuous air monitor alarms, an area habitability survey should be conducted. The results of the survey should be transmitted to the Radiological Protection Coordinator wl o will determine the need to relocate + personnel to the Service 3uilding (alternate OSC). s PV216 (CDA 18 th
PVNGS EMERGENCY PLAN PROCEDURE
- NO.
IMPLEMENTING PROCEDURE _ EPIP-12 EVISION OPERATIONS SUPPORT CENTER ACTIVATION O Page 4 of 8 4.0 DETAILED PROCEDURE - 4.1 Personnel Indoctrination 4.1.1 The OSC is the assembly and staging area for unit / station personnel pooled for emergency response assignments. Designated emergency response personnel will report to the - OSC if not specifically assigned to a particular emergency position. The OSC Coordinator is responsible for:
- 1. Activating the OSC.
- 2. Organizing emergency personnel who report to the OSC.
- 3. Ensuring emergency personnel are available for dispatch.
,'s 4.1.2 The function of the OSC remains the same for an ALERT, \ _. ' SITE EMERGENCY and GENERAL EMERGENCY classifications.
Personnel / equipment augmentation may vary according to specific circumstances. The functions and personnel responsible for them include:
- 1. OSC Coordinator - Shift Maintenance Foreman
- 2. Operating Staff Support - Off-duty Operations Personnel i
l 3. Radiological Surveys (in plant /onsite/offsite) - Radiation Protection Personnel
- 4. Radiation Protection Teams (Personnel Monitoring /
i Dosimetry / Decontamination / Access Control / Reentry Control) - Radiation Protection Personnel
- 5. Repair Teams (thintenance/ Repair /Da= age Control) -
Maintenance Staff
- 6. Chemistry Sampling / Analysis - Chemistry Personnel
- 7. Search and Rescue Teams /First-Aid Teams - Designated personnel from the above list.
- 8. Fire Team - Designated personnel from the above list.
i PV2t6 0004 e6 82)
PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE EPIP-12 REVISION OPERATIONS SUPPORT CENTER
~
ACTIVATION 0 Page 5 of 8 4.1.3 The primary OSC is located in the lunchroom of the. affected units' Auxiliary Building. It is located near the units' Radiation Protection Area to provide for a decontamination facility, a fixed radiological counting facility, and access to the station's RE&M system to evaluate, control, and minimize personnel exposure. 4.1.4 The OSC is connected with the inplant and commercial telephons lines for communication with the TSC and Control Room. 4.1.5 The alternate onsite OSC is located in the Service Building. OSC personnel will relocate to this area if the Emergency Coordinator, on the advice of the Radiological Protection Coordinator, determines that this action is necessary. 4.1.6 Emergency radiological monitoring equipment, first aid supplies, decontamination supplies, protective clothing, C') protective breathing apparatus, field. communications s.,/ equipment, and portable lighting are stored in emergency kits located adjacent to the OSC. 4.2 Prerequisites 4.2.1 An ALERT or more severe emergency has been declared and procedure EPIP-04, 05, or 06 is being imple=ented. 4.3 Instructions 4.3.1 Activation of the Primary OSC 4.3.1.1 The Shif t Maintenance Foreman shall report to the affected unit OSC and complete the check list in Appendix A. 4.3.1.2 The following personnel shall report to the OSC and follow the directions of the OSC Coordinator:
- 1. Designated Off-duty Operations Personnel
- 2. Maintenance Staff l
- 3. Radiation Protection Personnel
; . 4. Chemistry Personnel %(.
PQ'6 000A eS 8D v
p PVNGS EMERGENCY PLAN Qoceouna IMPLEMENTING PROCEDURE EPIP-12 OPERATIONS SUpp0RT CENTER
' ACTIVATION 0 page 6 of 8 4.3.2 Activation of the Alternate OSC 4.3.2.1 In the event the primary OSC becomes uninhabitable (see Appendix B for habitability criteria), the Emergency Coordinator will direct OSC personnel to evacuate / report to the alternate onsite OSC (i.e.,
Service Building). - 4.3.2.2 The ' primary OSC personnel will report / relocate to the alternate OSC and perform steps 4.3.1.1 and 4.3.1.2. 4.3.2.3 The OSC Coordinator.shall ensure the transport of emergency equipment, including decontamination supplies, necessary to establish the offsite OSC. 4.3.2.4 In the event the alternate OSC becomes uninhabitable (see Appendix B for habitability criteria), OSC personnel will report to the TSC. l i i PV216 CCCA (4,82)
PROC 20URE PVNGS EMERGENCY PLAN N O. APPENDIX A
.lMPLEMENTING PROCEDURE EPIP-12 Page 1 of 1 ION OPERATIONS SUPPORT CENTER ACTIVATION O Page 7 of 8 OSC COORDINATOR CHECK LIST -
ACTION ITEMS TIME / INITIALS
- 1. Activate the continuous air monitor. /
- 2. Ensure all communication devices operate. /
.3. If any visitors, contractors, or nonessential personnel /
report to OSC, dispatch them to the Administration Annex Building First Floor for accountability.
- 4. Conduct personnel accountability per EPIP-20, and report /
results to Personnel Resources Coordinator.
- 5. Ensure that all emergency equipment and personnel are in a /
state of readiness.
- 6. Ensure radiation protection support is available to perform /
('v ') surveys, and other assessment functions as required.
- 7. Report OSC readiness to Personnel Resources Coordinator. /
l
- 8. Maintain an Emergency Action Log. / _
OSC Coordinator Signature Date i I l { l , - .
.s PV216 000A 18,82)
.,.7.,
PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX B IMPLEMENTING PROCEDURE EPIP-12 Page 1 of 1 OPERATIONS SUPPORT CENTER ACTIVATION O Page 8 of 8 OSC HABITABILITY CRITERL1 The following limits should be considered upper limit habitability criteria. i CONSIDER AIRBORNE EVACUATION - WHOLE BODY DOSE RATE , ACTIVITY CONCENTRATION 1 WITHIN 2-10 mrea/ hour 1-4 x MFC 48 hours . 10-50 mrem / hour 4-20 x MPC 10 hourc 50-100 arem/ hour 20-40 x MPC 5 hours 100-500 mrem / hour 40-200 x MPC 1 hour 500 mres/ hour 200 x MFC Ia:::diately 1 Where MPC is the maximum permissible concentration ror areas as defined in Column 1, Table I, Appendix B to 10 CFR 20. This calculation will allow 2001:PC hours which conservatively limits internal exposure. This
; s criteria is based on personnel not wearing respiratory equipment.
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6 , I t PVNGS EMERGENCY PLAN PROCEDURE NO.
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IMPLEMENTING PROCEDURE - Epip_13 EMERGENCY OPERATIONS
~
FACILITY ACTIVATION 0 Page 1 of 21 i ASSIGNED COPY G' -> 1 l '0 " PVNGS SM i . i , l I i l l ADPROVED BY: e rm w, DATE / I EFFECTIVE /8- //"[O
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4 PROCEDURE PVNGS EMERGENCY PLAN NO. IMPLEMENTING PROCEDURE Epip-13 REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 2 of 21 4 TABLE OF CONTENTS , , SECTION PAGE NUMBER 1.0 OBJECTIVE 3
2.0 REFERENCES
3 . . 3.0 LIMITATIONS AND PRECAUTIONS 4 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prequisites 5 4.3 Instructions 6 APPENDICES
,s 7
(
,# Appendix A - Emergency Operations Director Check List 8 Appendix B - Radiological Assessment Coordinator Check List 9 Appendix C - Technical Analysis Coordinator Check List 10 Appendix D - EOF Contact Check List
- 11 Appendix E - Administrative and Logistics Coordinator Check List 12 I
Appendix F - Radiological Assesscent Communicator Check List 13 . Appendix G - Government Liaison Engineer Check List 14 l Appendix H - TSC Liaison Engineer Check List 15 l Appendix I - Logistics Coc=unicator Check List 16 Appendix J - Dosimetry Clerk Check List 17 Appendix K - Security Coordinator Check List 18 Appendix L - EOF Readiness Check List 19 Appendix M - ECC Equipment Layout 20 Appendix N - EOF Floorplan 21 PV216 000A ($ $2)
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PVNGS EMERGENCY PLAN PROCEDURE ! NO.
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IMPLEMENTING PROCEDURE EPIP-13 i REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 3 of 21 i 1.0 OBJECTIVE . , 1.1 The objective of this procedure is to provide instructions for the activation of the Emergency Operations Facility (EOF). This procedure addresses the following: Complete activation of the Emergency Operations Facility g by assigned personnel as they arrive at the EOF. ~ j - Functions of the EOF as an emergency center. i - Coordination between the EOF and other divisions of the emergency organization. ( EOF ataffing requirements.
2.0 REFERENCES
.~ , 2.1 Imple=enting References 2.1.1 EPIP-01, "APS Emergency Organization" 2.1.2 EPIP-04, " ALERT Implementing Action" 2.1.3 EPIP-05, " SITE EEERGENCY Implementing Actions" 2.1.4 EPIP-06, "GENERAI, EMERGENCY Implementing Actions" 2.1.5 APS Emergency Response Facility Equipment Manual l 2.2 Developmental References ,
l 2.2.1 UUREG-0654, Rev. 1, " Criteria for Preparation and ! Evaluation of Radiological. Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" l 2.2.2 NUREG 0696, Feb. 1981, " Functional Criteria for Emergency Response Facilities" 2.2.3 PVNGS Emergency Plan, Rev. 2 Pv216 0004 (8 82)
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( PVNGS EMERGENCY PLAN PROCEDURE NO. s' IMPLEMENTING PROCEDURE EPIP-13 REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 4 of 21 3.0 LIMITATIONS AND PRECAUTIONS . . 3.1 Upon activation of the EOF, designated personnel'shall report directly to the EOF and achieve full functional operation as - soon as possible (generally within 90 minutes). l 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 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 reco=mendations, liaison with offsite governmental organ.izations and response facilities, and overall management of the PVNGS emergency organization. The EOF is the central location for the receipt and analysis of field conitoring data and the coordination of further offsite monitoring / sampling by APS Field Survey Teams. 4.1.2 During an ALERT, or more severe accident, overall command of APS emergency operations will be exercised by the Emergency Operations Director (Vice President, Electric Operations) at the EOF. He will provide direction and support for inplant emergency response actions to the Emergency Coordinator (Manager, Nuclear Operations), and coordinate APS headquarters support through the CEC. In addition, he will con =unicate plant status updates and information for media release to the ENC and the CEC. 4.1.3 Functional assignments at the EOF, an addition to the Emergency Operations Director are: 4.1.3.1 Radiological Analysis Analyze source term, release, and meteorological infor=ation to determine anticipated, or actual, impact on areas of concern. Interface with ARRA representatives in recommending protective action (s) for the population-at-risk. meamimi
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t PVNGS EMERGENCY PLAN PROCEDURE NO. O IMPLEMENTING PROCEDURE EPIP-13 E!ERGENCY OPERATIONS FACILITY ACTIVATION 0 . Page 5 of 21 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. Assist APS Corporate Relations personnel at the Emergency News
~
Center by participating in media briefings and _ . interpretirg technical aspects of the emergency. 4.1.3.3 Administrative and Logistics Support Provide needed technical documents, communications and analytical equipment, clerical assistance, transportation / housing support and security for EOF. 4.1.3.4 Public Affairs Support Cather necessary information for subsequent release to the media from the ENC.
) 4.1.4 The ECF will be activated and manned for an ALERT or more severe incident classification.
4.1.5 The EOF emergency supply storage area contains a supply of calibrated radiological monitoring equipment, dosimetry, protective clothing, protective breathing apparatus, first aid supplies, communications equipment, cameras, and portable lighting. In addition to the foregoing, the EOF is equipped with a sleeping area, lounge, food preparation facilities, and energency food and drinking water supplies. A backup Emergency News Center, which may be used to communicate information to the cedia, is located . above the EOF. 4.2 Prerequisites 4.2.1 An ALERT or more severe level emergency has been declared and procedure EPIP-04, 05, or 06 is being implemented. 1 l
%216 0 COA (8 82
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PVNGS EMERGENCY PLAN m esoune IMPLEMENTING PROCEDURE EPIP-13
. EMERGENCY OPERATIONS FACILITY ACTIVATION ~
0 Page 6 of 21 4.3 Instructions 4.3.1 Activation of the EOF 4.3.1.1 The Administration Annex Building Security Officer will request assignment of an additional Security Officer to the Administration Annex Building from the - Security Shif t Captain. When the additional Security Officer arrives, he shall relieve the Administration Annex Building Security Officer of his security related duties. The relieved Security Officer shall then proceed to the EOF and perform the following:
- a. Break out tables stored in the Emergency Com=and Center and install them in accordance with Appendix M.
- b. Connect telephones stored in the Emergency Command '
Center in accordance with the com=anications layout of Appendix M. u.
- c. Break out additional office supplies (nameplates, in-out boxes). -
- d. Report completion of above to Security Shift Captain.
- e. Lock door to restrict entrance to EOF by stairs #2.
(see Appendix N). l 4.3.1.2 The following Offsite Emergency Organization personnel shall report to the EOF and complete their designated - check lists: o Vice President, Electric Operations - Appendix A
.o Radiological Assessment Coordinator - Appendix B o Technical Analysis Coordinator - Appendix C o EOF Contact - Appendix D o Administration and Logistics Coordinator -
Appendix E o Radiological Assessment Communicator - Appendix F PV2'6 OCOA (8.8h
, . . + . - . .,
s PROCEDURE PVNGS EMERGENCY PLAN N O. IMPLEMENTING PROCEDURE Epip-13 REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 7 of 21 o Government Liaison Engineer - Appendix G , , o TSC Liaison Engineer - A'ppendix H o Logistics Comunicator - Appendix I o Dosimetry Clerk - Appendix J . . o Security Coordinator - Appendix K 4.3.2 Declaration of EOF Readiness 4.3.2.1 Upon completion of E0F personnel check lists, the Emergency Operations Directer shall complete the EOF Readiness Check List of Appendix L. 4.3.2.2 The Emergency Operations Director will then contact the Energency Coordinator, the Corporate Energency Center (if activated) and the Emerger.cy News Center and inform thec that the EOF is operational. 1 I t PV24 0004 (8821 6 W-.
- 9 * ,te w* m e
_ PVNGS EMERGENCY PLAN o [ROCEDURE EPIP-13 Page 1 of 1 I ' IMPLEMENTING PROCEDURE REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 8 of 21 EMERGENCY OPERATIONS DIRECTOR CHECK LIST . . ACTION ITEMS TIME / INITIALS
- 1. Contact Emergency Coordinator and review:
- a. The logic used to establish the event classification. / . .
- b. Status of plant conditions. /
- c. Corrective actions that are being taken. / _
- 2. Ensure that the following positions are staffed:
- a. Radiological Assessment Coordinator /
- b. Technical Analysis Coordinator /
- c. EOF Contact /
- d. Administrative and Logistics Coordinator
- 3. Notify the TSC and CEC when the EOF is operational and /
complete the EOF Readiness Check List, Appendix L.
- 4. Based on presentations from the Radiological Assessment /
- Coordinator, recommend protective actions to state and county agencies.
- 5. As necessary, communicate plant status updates and /
radiological release data to NRC/FE'4A, state / county, ECC, CEC, and ENC personnel. . EOD Signature Date i PY2'6 OCOA 48 82)
*- =
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX B
; p, IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 EWSION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 9 of 21 RADIOLOGICAL ASSESSMENT COCRDINATOR CHECK LIST ACTION ITEMS TIME / INITIALS
- 1. Ensure Radiological Assess =ent Communicator's position is /
canned. i -
- 2. Access CRACS to receive current dose projectics data. /
'3. Contact the Radiological Protection Coordinator and deternine:
- a. Extent and consequences of radiological releases and /
plant conditions.
- b. Protectiv.s action recoceendations made to date. /
- c. Location of onsite and offsite field monitoring tents, /
if dispatched.
,, 4. Ensure that materials needed to perfons manual dose assessments are available.
- a. EPIP-14A and 14B /
q b. Isopleths /
- c. Base Map /
- 5. Make recoceendations to the Emergaucy Operations Director as /
- to the need for protective actions.
l
- 6. Ensure Radiological Status Boards are updated as information /
becomes available. f . 7. Make recommendations to ARRA officials as to where PL\T's / should be deployed and what to nonitor. l Radiological Assessment
- Coordinator Signature
- Date 1
\ I' PV2'6 OCOA 48 821 O
'I
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PVNGS EMERGENCY PLAN PROCEDURE
, . , NO. APPENDIX C
.-) lMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 REWSION EMERGENCY OPERATIONS '
FACILITY ACTIVATION O Page 10 of 21 TECHNICAL ANALYSIS COORDINATOR CHECK LIST - ACTION ITEMS TIME / INITIALS
- 1. Obtain plant status from the TSC. / _
- 2. Provide updates on the status of the reactor and unit to / _
h1C, state, and county personnel as necessary.
- 3. Provide the Eaergency Operations Director with technical /
guidance as to how plant status may impact offsite emergency response actions.
- 4. Verify the technical accurscy and adequacf cf all public /
inforuation releases prior to di.:seninat.icn to the sedia.
- 5. Ensure the following positions are staffed:
- a. Govern =ent Liaissa En31neer /
) b. TSC Liaison Engineer /
Technical Analysis Coordinator Signature Date l S l [ { W2 eaca is e23 6
, - ~ _ , , , -
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX D (g) IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 SiON EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 11 of 21 EOF CONTACT CHECK LIST , ACTION ITEMS TIME / INITIALS
- 1. Establish and c:aintain coccunications with the ENC Director /
at the DiC.
~
- 2. Inform the ENC Director of significant changes in plant /
status for subsequent release to the news media.
- 3. Prepare preliminary press releases in accordance with /
EPIP-32. 1 EOF Contact Signature Date , ,T ! i ics, ,.. - [ 5 s W2t6 0C04 #8,82)
PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX E
;O IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 REVISION EMERGENCY OPERATIONS
~
FACILITY ACTIVATION 0 Page 12 of 21 , ADMINISTRATIVE AND LOGISTICS COORDINATOR CHECK LIST - ACTION ITEMS TIME / INITIALS
- 1. Ensure the following equipment is operational:
- a. SPDS /
- b. CRACS /
- c. EOF Computer Terminals (RE&M, SIMS, RMS, CRACS) /
- 2. Ensure support organizations such as 13echtel, CE, INPO are /
contacted to obtain necessary technical cupport per EPIP-33.
- 3. Check that facilities availatie to emergency response /
persont.el are adequate.
- 4. As necessary provide for additional maapower support by /
contacting organizations per EPIP-33. (g 5. As necessary obtain required:
%./
- a. Technical documents /
Coccunication equipment
- b. /
- c. Analytical equipment / .
- d. Transportation supporr /
t ! e. Housing and food for emergency response personnel / )
- 6. Contact American Nuclear Insurers and inform them of '/
situation.
- 7. Ensure the following positions are staffed:
- a. Logistics Communicator /
- b. Dosimetry Clerk /
- c. Security Coordinator /
Administrative and Logistics Coordinator Signature Date t PV216 0 COA to 82) S
- - - - ,- ~
,. - . ,n , , - - - - .
~ _
PVNGS EMERGENCY PLAN o [ROCEDURE (q IMPLEMENTING PROCEDURE gprp_13 C fg1F
d REVISION E!ERGDICY OPERATIONS FACILITY ACTIVATION O Page 13 of 21
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RADIOLOGICAL ASSESSMENT COMMUNICATOR CHECK LIST . ACTION ITDIS TIME / INITIALS 1. Establish and maintain communications with TSC Radiological- / Assessment personnel. t .
- 2. Keep the Radiological Assessment Coordinator informed of /
changes in radiological status. ~
- 3. Maintain records of communications concerning radiological
/
assessment. __
- 4. Maintain the Radiological Status Board in the EOF at the
/
direction of the Radiological Assessment Coordinator. Radiclogical Assessment Communicator Signattre < [. ;
} Date l
*V2'S-CCC A 18 42) f ~ e o e ye %
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PVNGS EMERGENCY PLAN PROCEDURE
, NO. ADPENDIX G IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 REVISION DIERGENCY OPERATIONS FACILITY ACTIVATION O Page 14 of 21 GOVERN!ENT LIAISON E'IGINEER CHECK LIST .
ACTION ITEMS TIME / INITIALS
- 1. Inform the Satellite TSC Communicator that you are on /
station and assume the responsibility for offsite l notifications.
- 2. Establish and maintain communications with the NRC until /
relieved by a designated NRC representative.
- 3. Report the completion of offsite notifications to the /
Technical Analysis Coordinator. Government Liaison - Engineer Signature Date sp' ) 1 l 4 Q./ PV24 rJtC A 48 42) t,* ,,
- PROCEDURE PVNGS EMERGENCY PLAN N O. APPENDIX H r3.: IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1
(-# REVISION DIERGENCY OPERATIONS FACILITY ACTIVATION - 0 Page 15 of 21 TSC LIAISON ENGINEER CHECK LIST . 4 ACTION ITEMS TIME / INITIALS
- 1. Monitor the SPDS terminal in the EOF. /
i
; 2. Contact the CR and TSC to obtain operational status of / ' ^
the unit.
'3. Maintain communication with Bechtel and CE personnel at the /
EOF concerning plant status and reccccendations for corrective action. l
- 4. Inform the Technical Analysis Coordinator of proposed /
j recommendations and of significant changes in plant status. F l S. Ensure the Sts.tus Bo:r:.d Keeper position is sanned 'and / provide scatus board updat.es as necessary.
', TSC Liaison i Er.ginaa.r Signature _
i Date t i l l l d i i 4 - , I t A i PV2'6 0004 e6 62) l e- . _ _ -_ ______m _- _ _
PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX I
^O
IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 16 of 21 LOGISTICS COMMUNICATOR CHECK LIST ACTION ITEMS TIME /irlIT ALS-
- 1. With the assistance of the Radiological Assessment /
Communicator, ensure all EOF communications equipment is operable. .
- 2. Contact support organizations at the direction of the /
Administrative and Logistics Coordinator per EPIP-33. Logistics Communicat.cr Signa *.t.r e Date,_ _ 7
~
l PY2'6 0CCA is 82)
PROCEDURE PVNGS EMERGENCY PLAN NO. APPENDIX J O ms IMPLEMENTING PROCEDURE Epip-13 REVISION Page 1 of 1 EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 17 of 21 DOSIMETRY CLERK CHECK LIST ACTION ITEMS TDIE/ INITIALS
- 1. Obtain emergency dosimetry from the EOF emergency locker /
in preparation for its distribution.
/
~
- 2. As necessary, provide dosimetry and TLD's to EOF personnel, support personnel reporting to site assignment, and site personnel.
- 3. Report the need for additional dosimetry to the Administrative /
and Logistics Coordinator. Dosimetry Clerk Signature l Date e l 1 I p PV2 6 0 COA S t:1
*r9.-+- .
o l PROCEDURE PVNGS EMERGENCY PLAN N O.
~.m APPENDIX K
,o
.) IMPLEMENTING PROCEDURE EPIP-13 page 1 o1.1 REVISION DIERGENCY OPERATIONS FACILITY ACTIVATION O Page 18 of 21 SECURITY COORDINATOR CHECK LIST -
ACTION ITEMS TIME / INITIALS
- 1. Contact the Security Director at the TSC to determine /
present site access conditions.
- 2. Inform the Security Director of offsite personnel that are /
required onsite to expedite the badging process.
- 3. Keep the Administrative and Logistics Cootdinator inforted /
of site security conditions. Security Coordinator Signature - Late
. .,.s 4
e 6 l M,.[ l l nm =:. . ui
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PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX L
^
6.s > IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 19 of 21 EOF READINESS CHECK LIST , . ACTION ITEMS TIME / INITIALS
- 1. Conduct briefing with available EOF personnel. As a minimum, /
the following items shall be discussed:
- a. Adequacy of activation. /
- b. Ability of assigned personnel to assume their /
cmergency duty roles. t
- c. Operability of equipment (installed as well as /
portable emergency).
- 2. The Vice President, Electric Operations shall assume the /
role of Emergency Operations Director, declare the EOF fully cperational and inform the Emergency Coordinator and the Chief Executive Officer at the Corporate Emergency
,- s Center.
i: \
\ .. '
Emergency Operations Director Signature Date PV215 000A 48 823
- . ~ - .-
PVNGS EMERGENCY PLAN PROCEDURE N O. APPENDIX M m,' ' IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 REVISION EMERGENCY OPERATIONS FACILITY ACTIVATION O Page 20 of 21 EMERGENCY CONTROL CENTER EQUIPMENT LAYOUT 8 f *ee (2 lines) c ll a f7* 4 -Q d U U 26 o %
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U _7 P eli. ',-s j, hI d" dA @ Communications Y 1. NAM w ns' -
- 2. EC/EOD l t. p 3. REM Terminal
- 4. ENC Facsimile
- 5. ENC Line
- 6. Voice Circuit (411, ARRA, ADES)
Table Personnel Locations
- 7. Facsimile & Backup A. Emergency Operations Director (411, ARRA, ADES)
B. Administrative and Logistics 8. Technical Line Coordinator 9. TSC Line C. Logistics Co=municator 10. Environmental Line D. Government Liason Engineer
- 11. C.R.A.C.S. Terminal E. IDF Contact 12. Base Station Radio F. Security Coordinator 13. CR Line G. Technical Analysis Coordinator 14. S.P.D.S. Terminal H. Status Board Keeper STSC Line 15.
! , I. Radiological Assissment Coordinator
- Normal Phone Line J. ISC Liason Engineer g ,
K. 6 L. Radiological Assessment Communicator
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M. State of Arizona
PVNGS EMERGENCY PLAN [acEwa PPerm x u
, O, IMPLEMENTING PROCEDURE EPIP-13 Page 1 of 1 REVISION EMERGDICY OPERATIONS ~
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l . l l l PROCEDURE r PVNGS EMERGENCY PLAN N O. t n l i
's) IMPLEMENTING PROCEDURE Epip_143 REVISION , ,
RELEASE RATE DETER!!INATION O Page 1 of 19 l .
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,~ PVNGS EMERGENCY PLAN N O.
':- IMPLEMENTING PROCEDURE EPIP-14A REVISION s RELEASE' RATE DETERMINATION O Page 2 of 19 TABLE OF CONTENTS ,
s SECTION PAGE NUMBER 1.0 OBJECTP/E 3
2.0 REFERENCES
3 3.0 LIMITATIONS A'iD PRECAUTICNS 3 4.0 DETAILED PROCEDURE 5
- 4.1 Personnel Indoctrination 5 4.2 Prerequisites 5 4.3 Instructions 5
(]
- APPENDICES Appendix A - Release Rate Determination From the Turbine 11 Building PLANT VFliT Appendix B - Release Rate Determination from the Condenser 12 Air Removal System Appendix C - Release Rate Determination from the Fuel Building 13 Ventilation Exhaust i
i Appendix D - Releasa Rate Determination from Main Steam System 14 Appendix E - Release Rate Determination from Containment 15 Utilizing Containment Area Monitors or Hand-Held Instruments Appendix F - Ratio of Total Iodine / Noble Gas Release Rates 16 Appendix G - Ratio of I-131/ Total Iodine Release Rates 17
' Appendix H - Containment Exposure Rate 18 l ( 19 l
Appendix I - Containment Noble Gas Release Rate PV24000A (8.82) j- r
PVNGS EMERGENCY PLAN PROCEDURE
.- N O.
>g i IMPLEMENTING PROCEDURE EPIP-14A REVISION -
RELEASE RATE DETERMINATION O Page 3 of 19 1.0 OBJECTIVE . 1.1 This procedure describes methodology for the manual determination of airborne radioactive release rates from the turbine building (plant vent and condenser air removal), the fuel building and the main steam lines utilizing effluent monitor readings. If this is not possible, release rates will - be inferred indirectly from area radiation monitors or haid-held mohitors. Upon determination of release rates, actual or projected plume exposure dose rates, and integrated doses may be calculated in accordance with FPlP-14B, " Dose , Assessment".'
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-C8, " Notification Process - ALERT, SITE DIERGENCY, cr GENERAL EMERGFliCY ({3 2.1.2 EPIP-11, " Technical Support Center Activation" 2.1.3 EPIP-12, " Operations Support Center Activation" n 2.1.4 EPIP-13, " Emergency Operations Facility Activation" 2.2 Developmental References l 2.2.1 PVNGS Emergency Plan, Rev. 2 l 2.2.2 FSAR, Chapter 11, " Process and Effluent Radiological Monitoring and Sampling Systems" 2.2.3 NUREG-0737, " Clarification of TMI Action Plan Requirements" 3.0 LIMITATIONS AND PRECAUTIONS 3.1 If an airborne radioactive material release occurs under emergency conditions, the majority of material will be released through the plant vent with the possibility of minor amounts being released through the condenser air removal system, the fuel building exhaust or the main steam lines.
~
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,. PVNGS EMERGENCY PLAN [ROCEWRE '- ' IMPLEMENTING PROCEDURE Epip-14t REVISION %
RETIASE RATE DETERMINATION O Page 4 of 19 3.1.1 Activity release rate calculations for the condenser air recoval system, fuel building exhaust system, main steam system and the turbine building plant vent should be conducted only if the appropriate monitors indicate elevated activities, and actual releases have occurred or are expected to occur. 3.2 Depending upon release sites, one or more of the following monitors must be properly functioning; 3.2.1 AN-143; Low Range Plant Vent Monitor Ru-143; intermediate Range Plant Vent Monitor Ru-144; High Range Plant Vent Monitor
3.2.2 AN-145
Low Pange Fuel Building Exhaust Monitor Ru-145; Intermediate Range Fuel Building Exhaust Monitor Ru-146; High Range Fuel Building Exhaust Monitor 3.2.3 AN-141; Low Range Turbine Building Condenser Air Removal ([)' Monitor ' Ru-141; Intermediate Range Turbine Bail ~ ding Condenser Air Removal Monitor Ru-142; High Range Turbine Building Condenser Air Removal _ - Monitor 3.2.4 Ru-139A,B; 140A,B; ibin Steam Line Monitors 3.2.5 Ru-148 or Ru-149; Containment Area Monitors 3.3 Monitor readings cust be obtained from the communication console in the Control Room or the console in the radiation protection. office. 3.4 Determination of containment release rates utilizing containment area monitors Ru-148 or Ru-149 or hand-held instruments should be used only if effluent monitors are nonfunctional. 3.4.1 Plant vent releases may be calculated by correlating actual containment exposure rates to projected containment exposure rates and release rates. Projected exposure and release rates were calculated assuming a design basis loss of coolant accident (LOCA) based upon NUREG-0737. The entire release is assumed to be through the plant vent. () 3.5 " Effective age" refers to the time af ter core shutdown. Release rates will vary as a function of " effective age". W24 MOA tS4h w - p
PROCEDURE PVNGS EMERGENCY PLAN e) NO. EPIP-14A IMPLEMENTING PROCEDURE REVISION ~ RELEASE' RATE DETERMINATION O Page 5 of 19 4.0 DETAILED PROCEDURE I. 1 Personnel Indoctrination 4.1.1 As delineated in EPIP-O1', the Radiation Protection Technician (affected unit) will be responsible for initial offsite dose calculations and/or projections. 4.1.2 At an ALEkT or more severe level, the Radiological Prctection Coordinator (at the TSC) will be responsible for dose calculations and/or projections. 4.2 Prerequisites , 4.2.1 An Alert or higher level emergency has been classified per the provisions of EPIP-02. 4.2.2 An actual or projected release of airborne radioactive
=aterial has occurred or will occur.
7 h) . Additionally, release rates shall be determined upon 4.2.2.1 significant changes in monitor readings and at a minimum of every two hours for effective ages 0-10 hours and every 10 hours for effective ages 10-100 hours. 4.3 Instructions 4.3.1 Determine release point (s) from effluent monitor reading (s). Proceed to the appropriate section. o Plant Vent Section tilizing Effluent Monitor, 4.3.2. o Condenser Air Removal System, 4.3.3. o Fuel Building Ventilation Exhaust, 4.3.4. ! o Main Stsam Lines, 4.3.5. o Plant Vent or Containment Utilizing Containment Area Monitors or Hand-Held Instruments, 4.3.6. j I 4.3.2 Determination of activity release rate from the plant vent (Appendix A). h. l l l evm ecca ca sa l
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- PVNGS EMERGENCY PLAN PROCEDURE ,
N O. , IMPLEMENTING PROCEDURE EPIP-14A
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REVISION . RELEASE RATE DETERMINATION O Page 6 of 19 4.3.2.1 Obtain the noble gas air concentration in units of uCi/cc from the gross beta channel (Channel B) of monitor AN-143 (low range), Ru-143 (inter =ediate range) or Ru-144 (high range). Record this value on Appendix A, Column 2, Section A. 4.3.2.2 Obtain the I-131 air concentration, in units of tCi/cc ' fro =,the I-131 channel of monitor AN-143, Ru-143 or Ru-144. Record this value on Appendix A, Column 2, Section B. 1 4.3.2.3 Multipif the monitor reading (uci/cc) by the vent flow rate (6.64 E+07 cc/sec, default value) to obtain the i noble gis and/or I-131 release rate in uC /sec. o Convert to Ci/sec utilizing the conversion 1.0E-06Ci/uci.
..s 4.3.2.4 If the I-131 channel is nor. functional multiply the ! J noble gas release rate by the appropriate conversion factor (Appe:. dices F and G) to obtain the release rates of total radioiedince and 1-131 (Section C).
Calculation RRgg = Ang x Flow Rate cc/sec x 1.0E-06 Ci/uci RRTI = RRgg x C1 RRI -131 = RRTI x C2 Where: RRgg = noble gas release rate (Ci/sec)
- RRTI = total radiciodine releas rate (Ci/sec) l RRI -131 = iodine 131 release rate (Ci/sec)
I' Agg = noble gas air concentration (uC1/cc) from monitor Ru-143 or Ru-144 Flow Rate = flow rate cc/sec; plant vent flow rate = 6.64E+07 cc/sec (default valve) or (operating vents x flow rates) l l Ang = noble gas activity (uCi/ce) , PV24 0tOA 68-826 l
PVNGS EMERGENCY PLAN pcess IMPLEMENTING PROCEDURE EPIP-14A REVISION , RELEASE RATE DETERMINATION O Page 7 of 19 o 1.0E-06 . Ci/uCi = conversion from uCi to Ci-C1
= ratio of total iodine / noble gas release rates (Appendix F)
C-2 = ratio of I-131/ total iodine release rates (Appendix G) 4.3.3 Determination of activity release rate from the condenser air removal system (Appendix B). 4.3.3.1 Obtain the noble gas air concentration A(NG), in units of uC1/cc from-the gross B channel (Channel B) of monitor AN-141 (low range), Ru-141 (intermediate range) or Ru-142 (high range). Record this value on Appendix B, Column 2, Section A.
.s 4.3.3.2 Obtain the I-131 air concentration in units of uCi/cc from the I-131 channel of monitor AN-141, Ru-141 or Ru-142. Record this value on Appendix B, Column 2, Section B.
4.3.3.3 Multiply the monitor reading (uci/ce) by the condenser flow rate (1.39E + 06 cc/sec, default value) to obtain. the noble gas and/or I-131 release rate (uci/sec).
~
i o Convert to Ci/sec utilizing the conversion 1.0E-06 1 Ci/uci. l 4.3.3.4 If the I-131 channel is nonfunctional multiply the I noble gas release rate by the appropriate conversion factor (Appendices F and G) to obtain the release l rates of total radiolodines and I-131 (Section C). l Calculation RRNG =ANG x 1.39E+06 cc/sec x 1.0E-06 C1/uci RRTI = RRNG x C1 RRI -131 =RTI x C2 i (Refer to Section 4.3.2.4 for parameter descriptions).
.- 4.3.4 Determination of activity release rate from the fuel building ventilation exhaust (Appendix C).
PV216@DA (8:826
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PVNGS EMERGENCY PLAN PROCEDURE N O. IMPLEMENTING PROCEDURE EPIP-14A REVISION ' RELEAS$ RATE DETERMINATION O Page 8 of 19 4.3.4.1 Obtain the noble gas air concentration, (Channel?f, in units of uCi/cc from the gross B channel of monitor AN-145, Ru-145 or Ru-146. Record this value on Appendix C, Column 2, Section A.
. 4.3.4.2 Obtain the I-131 air concentratien in units of uCi/cc from the I-131 channel of conitor AN-145, Ru-145 or -
Ru-146. Record this value on Appendix C, Column 2, Section B. 4.3.4.3 Multiply the monitor reading (uCi/cc) by the ventilation exhaust rate (2.17E + 07 cc/sec for monitor Ru-145 or 2.83E + 06 cc/sec for monitor Ru-146) to obtain the noble gas and/or I-131 release rate (uCi/sec). o Convert to C1/see utilizing the conversion 1.0E-06 Ci/uci. 4.3.4.4 If the I-131 channel is nonfunctional multiply the noble gas release rate by the appropriate conversion factor (Appendices F and G) to obtain the release rates of total radioiodines and I-131 (Section C). Calculation RRyg = A(NG) x 1.39E+06 cc/sec x 1.0E-06 Ci/uci RRTI = RRNG x C1 RRI -131 = RRTI x C2 l (Refer to section 4.3.2.4 for parameter descriptions) ! 4.3.5 Determination of Activity Release Rate from the Main Steam l Lines (Appendix D). 4.3.5.1 Obtain the exposure rate (R/hr) from the main steam line monitor (s) Ru-139A,B or Ru-140A,B. , 4.3.5.2 Multiple this number (R/hr) by the appropriate l correction factor below. Record on Appendix D, Column 2. PV2?6 0C04 4 2 r-u- m,
PROCEDURE
- PVNGS EMERGENCY PLAN NO.
IMPLEMENTING PROCEDURE EPIP-14A REVISION RELEA 4 RATE DETERMINATION O Page 9 of 19 Effective Ace (hr) Correction Factor 0 - 0.08 6.2 0.08 - 0.5
- 6.6 0.5 - 1.0 6.7 1.0 - 8.0 6.9 8.0 - 24.0 8.4 -
24.0 - 96.0 8.4 96.0 - 192.0 22.0 192 - 720 21.0 720 - 00 14 4.3.5.3 Complete calculations in Appendix D. 4.3.6 Determination of activity release rate from the plant vent utilizing containment area monitors Ru-148 or Ru-149 or hand-held instruments (Appendix E). 4.3.6.1 This method should be utilized only if effluent s monitors are nonfunctional. 4.3.6.2 Obtain the actual exposure rate, E(act) from the high range area monitor Ru-148 and/or Ru-149 in R/hr or the sum of both divided by two for an average over the containment. Record this value on Appendix E, Column 2. If these monitors are nonfunctional and radiological conditions allow, as determined by dose rate measurement at outer containment door, obtnin a contact dose rate measurement (R/hr) with a hand-held l beta / gamma (shield closed) instrument at the inner ! containment door pyrex viewing window. Multiply by l the appropriate correction factor below. Record on Appendix E, Column 2. l Effective Age (hr) Correction Factor 0 - 0.08 1.40 0.08 - 0.5 1.42 1 0.5 - 1.0 1.43 1.0 - 8.0 1.53 8.0 - 24.0 1.57 24.0 - 96.0 1.79 i 96.0 - 192.0 3.4 l 192 - 720 16 l ' Determine the projected containment exposure rate l 4.3.6.3 , (LOCA), E(pro) as a function of " effective age" from l Appendix II. Record this value on Appendix E, Column 3. l evm oco* is.sa l l e
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,., PVNGS EMERGENCY PLAN lR CEWRE IMPLEMENTING PROCEDURE EPIP-14A REVIS!ON RELEASE' RATE DETERMINATION O Page 10 of 19 4.3.6.4 Deter =ine the projected noble gas release rate (LOC ),
R NGpro from Appendix I. Record this value on Appendix E, Column 4. 4.3.6.5 Calculate, release rates as follows: RRNG ACT = E(act) - E(pro) x RNGpro RRTI = RRNG ACT x C1 RRI _131 = RRTI x C2 Where: RRNG ACT = noble gas release. rate (C1/sec) RRTI = total radioiodine release rate (C1/sec) l RRI _131 = I-131 release rate (Ci/sec)
' = actual high range monitor EACT reading from Ru-148 and/or Ru-149 in R/hr or corrected hand-held instru=ent reading E(pro) = projected containment exposure rate (LOCA) at " effective age" from Appendix H R NG pro " projected Noble Gas release rate (LOCA) at " effective age" j from Appendix I l
C1
= ratio of total iodines / noble gas release rates (Appendix F)
C2 = ratio of I-131/ total iodine i release rates (Appendix G) { Pv2'6 0CC A to Sh y- ., . , . .
- - - - ---__----_-__----___-------_-__2----- - - - - - - - - - _ - _ . - ,
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2 RELIASE RATE DETERMINATION Ilott THE TIMBINC Bull, DING. PIANT VENT Q Monitors AN-143. Ru-143 or Ru-144 cn to ITI (f) Effective Noble Cas Plant Vent Conversion Noble cas Release Rate pts ' ZM y$ Air Conc Flow Rate Factor y Age O.r ) (uct/cc) (cc/sec)* (uct to Ct) (C1/see) to ym NOTE: If I-131 monitor is inoperable, g -3 Section A x x 1.0E-6 -
=
complete Section C only, otherwise go Og x x 1.0E-6
=
complete only Sections A and B. *I gg x x 1.0E-6 ' x x 1.0E-6 - g OO x x 1.0E-6 = g O4 x x 1.0E-6 - H Ng 2 O r-Cp 1-131 Plant Vent Conversion I-131 y7 Effective Release Rate Age Air Conc Flow Rate Factor (br) (uct/ce) (ce/see)* (uct to Cl) (C1/sec) 5cction 3 x 1.0E-6 = x x x 1.0E-6 - x x 1.0E-6 x x x 1.0E-6 x 1.0E-6
=
=
5 h$O x 1.0E-6 = M tn O x .o m o H O Z m C 1-131 Elfective Noble cas Plant Vent Conversion Noble Cas Tot I/NG Tot Iodine Release Rate I-131/ Tot I Release Rate d y Air Cone Flow Ratw Factor Belease Rate App C (Ct/sec) o e 'i Ar,e (uct to C1) (Cf/sec) App F (Cf/see) >
'l (br) (uct/ce) (cc/sec)*
=
5ection C x = x x x 1.0E-6 -
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s 1 1 2 - 2 b> L - b ET
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M I"* mg2 RELEASE RATE DETERitINATION FROM THE C0!iDENSER AIR RDIOVAL SYSTEM Honitors AN-141 Ru-141 or Ru-142 ] Noble Cas Condense r Vacuum Vent Conversion Noble Cas M 3 g N Effcctive g Ace Air Conc Flow Rate Factor Release Rate gm (1.r ) (uct/cc) (cc/sec)e (,,Ct to C1) (Ct/sec) [iM k qg Section A g x x 1.0E-6 = NOTEt If 1-131 monitor is inoperable. Z complete Section C only. otherwise 1.0E-6 Qb x x = ts x x 1.0E-6 = complete only Sections A and B. y T I)] x x 1.0E-6 - - 32 x x 1.0E-6 = QQ x x 1.0E-6 = p g4 Condenser Y Effective I-331 Vacuum Vent Conversion I-131 O OI Age Air Conc Flow Rate Factor Release Rate CM (br) (uct/ce) (cc/sec)* (uct to Cl) (Ct/sec) 32 Section a 171 x - x 1.0E-6 x x 1.0E-6 = x - x 1.CE-6 x x 1.0E-6 = x x 1.0E-6 = 2 27 r x x 1.0E-6 =
}
us O]a m m 'i e condenser 5 m
. Effecttve Noble Gas Vacuum Vent Converston tioble Cas' Factor Tot Ih3G Tot I Release Rate I-131/ Tot I I-131 Release Rate z y @
Age Air Conc Flow Rate Release Rate : a * (br) (uCl/cc) (cc/sec)* (uct to C1) (Ct/sec) App F (C1/sec) App C (Cl/sce) H m Section C , , ,, x x 1.0E-6 - x = x =
, x x 1.0E-6 = x = x =
x x 1.0E-6 - x = x = x x x 1.0E-6 x 1.0E-6
=
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REll:ASE R/.TE DETER!!! NATION FROM Tl!E ftEL BUILDING VENTIIATION EXHAUST I"* Honitors AN-145. Ru-145 or Ru-146 2
- Plant Vent %
D-Q Effective Noble Cas Flow Este Conversion Noble Cas h g Age Air Conc
- Factor Release Rate "trl M (hr) (uct/cc) (cc/sec) (uCl to Cl) (Ct/sec) 2 M Sectton A h y3 x x 1.DE-6 =
NOTE: If I-131 mor.itor is inoperable,
>3 M =m x x 1.0E-6 =
complete Section C only, otherwise 2 3 x x 1.0E-6 = complete only Sections A and B. c Qg Q x x 1.0i;-6 = x x 1.0E-6 = . 22 x x 1.0E-6 = y QO p QM Flant Vent d Effective I-131 Flow Rate Conversion I-131 y Til gp T Age Air Conc
- Factor Release Rate 4 p ihr) (uCf /cc) (cc/sec) (uC1 to C1) (Ct/sec)
Section B 22 x x 1.0E-6 = N x x 1.0E-6 = x x 1.0E-6 = x x 1.0E-6 = x x 1.0E-6 = x x 1.0E-6 = 3 Z7 G 9ho F1. int Vent r, Effective Noble Cas Flow* Rate Converston Noble Cas Tot I I-131 6 N @ Age (hr) Air Conc (uct/cc) (cc/sec) Factor Release Rate Tot I/NC Release Rate I-131/ Tot I Release Rate 2 $ C 3 (uC1 t o Ct ) (Cf/sec) App F (Ct/sec) App C (Ct/ rec) H 1 A Section C p x x 1.0E-6 = x ;> x = u x 1.0E-6 = x = x = x x 1.0E-6 = x = x = x x 1.0"-6 = x = x x x x 1.0E-6 x 1.0E-6
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J: ( L APPENDIX CONTAINMENT Nost.t: UAs, t u i AL iuusived, nivu 1-i.s a ncu:sse nai es (Ci/sec) AS A FUNCTION OF EFFECTIVE A'GE (hr), PVNGS
- 101 . , ,
13
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PVNGS EMERGENCY PLAN PROCEDURE N O.
,3
, IMPLEMENTING PROCEDURE EPIP-14B l
REVISION DOSE ASSESSMENT 1 Page 1 of 15 1 ASSIGNED COPY . .. PVNGS SLI #- " "14 5 g . ,.,
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l l l APPROVED BY: / , WM DATE /2//f[1f 2. L/ ~ V - DATE EFFECTIVE /,%.Q~f,K9
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l l PV2t6 0004 (8 82)
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PVNGS EMERGENCY PLAN PROCEDURE NO.
. (O q.; IMPLEMENTING PROCEDURE EPIP-14B REVISION DOSE ASSESSMENT 1 Page 2 of 15 1 TABLE OF CONTENTS '
SECTION PAGE NUMBER 1.0 OBJECTIVE 3
2.0 REFERENCES
3 3.0 LDIITATIONS AND PRECAUTIONS 4 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 5 4.3 Instructions 5 qj APPENDICES Appendix A - Determination of X/Q Values for each 9 Receptor Site Appendix B - Calculation of Whole Body and Thyroid Dose 10 Commitments Appendix C - Average Garna Decay Energy (MeV/ dis) for 11 Noble Gas Mixtures l Appendix D - Ratio of Integrated Thyroid Dose Rate from All 12 Iodines to Integrated Thyroid Dose From I-131 as a Function of Effective Age. f ( Appendix E - Plume Transit Time Calculation 13 Appendix F - Atmospheric Stability Class Determination, 14
, Alternate Methods Appendix G - Site Boundary X/Q Values 15 m
l l n. s \ l PV2'8 OCOA t&82) , b&o * * % % M
PVNGS EMERGENCY PLAN lROCEWRE O, IMPLEMENTING PROCEDURE EPIP-14B
\I REVISION DOSE ASSESSMENT 1 Page 3 of 15 1 1.0 OBJECTIVR -
This procedure provides instructions and calculations necessary to determine actual or projected offsite whole body gamma and thyroid inhalation dose commitments based upon actu.tl meterological data, and noble gas and I-131 release rates (Ci/sec). Actual or projected dose calculations provide a basis - - for decision making concerning recommendations of appropriate protective actions to county or state authorities. .
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-08, " Notification Process, ALERT, SITE EMERGENCY, GENERAL EMERGENCY" 2.1.2 EPIP-ll, " Technical Support Center Activation" J 2.1.3 EPIP-12, " Operational Support Center Activation" 2 1.4 EPIP-13, " Emergency Operations Facility Activation" 2.1.5 EPIP-14A, " Release Rate Determination" 2.1.6 EPIP-15, " Protective Action Guldes" 2.2 Developmental Referencas I 2.2.1 PVNGS Emergency Plan, Rev. 2 2.2.2 NRC Reg Guide 1.145, August 1979; " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants" i l 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, Johd R. LaMarsh, Addison Wesley Publishing Company, racember 1977
._ 2.2.5 Health Physics Journal, November l981, Volume 41 No. 5,
+
, page 759 t,s ~
i PV2iG CCCA (SeS2) O
= = , v g
- p. p- .
PVNGS EMERGENCY PLAN ' Qceoune f] IMPLEMENTING PROCEDURE EPIP-14B s, REVISION DOSE ASSESSMENT 1 Page 4 of 15 1 2.2.6 NRC Reg Guide 1.109 " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I" 2.2.7 EPA " Manual of Protective Action Guides and Protective Actions for Nuclear Accidents" Appendix D, May 1980 2.2.8 PVNGS VSAR Section 2.0 Meteorology " Terrain Adjustment Factors Site Boundary X/Q Values" 3.0 LIMITATIONS AND PRECAUTIONS 3.1 Release rate determinations must be conducted in accordance with EPIP-14A, Release Rate Determination. s 3.2 Actual dose rates and integrated doses will vary as a function of: o the duration of the release; o the release rates (dependent upon effective age); o the isotopic mixture of the release (dependent upon effective age); . o existing meterological conditions. l 3.3 The accuracy of atmospheric dispersion calculations will be l between a f actor of 2 and a factor of 10. Therefore, the accuracy of dose calculations will be between a factor of 2 and 10. l l 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 4 1.1 As delineated in EPIP-01, the Radiation Protection i Technician (affected unit) will be responsible for initial of fsite dose calculations and/or projections. 4.1.2 At an ALERT or more severe level, the Radiological Protection Coordinator (at the TSC) will be responsible l
' for dose calculations and/or projections.
.,)
l PV216 000A ($182) l e ,,pg- _g --
PVNGS EMERGENCY PLAN PROCEDURE NO. s (
; IMPLEMENTING PROCEDURE EPIP-148 REVISION DOSE ASSESSMENT 1 Page 5 of 15 -
4.2 Prerequisites 4.2.1 An ALERT or more severe level emergency has been classified per the provisions of EPIP-02, 4.2.2 An actual or projected release of airborne radioactive material has occurred or will occur. , 4.3 Instructions 4.3.1 Calculation of " plume arrival time" and " effective age" of noble gases at the receptor site (Appendix E). 4.3.1.1 Calculate " transit time" from the release point to the receptor location as follows: a. Determine downwind distance (in miles) to the receptor site and record in column 2 of Appendix E worksheet. (3 j b. Obtain the 35 ft. level windspeed (mph) from the meteorological tower computer printout and record the value in column 3 of the Appendix E worksheet, c. Divide the downwind distance by the windspeed (as indicated on the Appendix E worksheet) and record the resulting " transit time" in column 4 of the Appendix F worksheet. 4.3.1.2 Caluelate the " effective age at the receptor site as fo119ws:
- a. Record the "ef fective age at release" (hr) in ~
column 5 of the Appendix E worksheet. The j " effective age at release" is the number of hours l after core shutdown that the release began. b.
- Add the " transit time" (hr) in coiumn 4 and the
" effective age at release" (hr) in column 5 and record the resulting " effective age at receptor site" (hr) in column 6 I
4.3.1.3 Add " transit time" (hr) to time at which the release began to get "pl ne arrival time" and record in
' column 1 of Appendix B.
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PVNGS EMERGENCY PLAN PROCECURE-o IMPLEMENTING PROCEDURE Epte_14E (U) REVISION DOSE ASSESSMENT 1 1 Page 6 of 15 4.3.1.4 Record " effective aZe at receptor site" in column 2 of Appendix B. s 4.3.2 Obtain release rates (C1/sec) of noble gases and I-131 from EPIP-14A and record in column 3 of Appendix B. 4.3.3 Determine the atomspheric stability category. 4.3.3.1 Obtain the delta F' (200f t-35f t) f rom the meteorological tower computer printout supplied by ERFDADS. Stability categories are defined as follows: Delta F* Stability Category (200ft-35ft) A -1.72 B
-1.72 to -1.54 C -1.54 to -1.36 h~'
D -1.36 to -0.45 E -0.45 to 1.34 F l.34 to 3.62 G 3.62 NOTE For alternate stability class determinations, use Appendix F. '
, 4.3.4 Determine the X/Q values for key receptor sites (Appendix A).
4.3.4.1 From the_ appropriate stability category in Appendix G, obtain Xu/Q values for site boundary; 2, 5 and 10 mile plume centerline locations and record in Appendix A, column 2. Only one sheet (Appendix A) should be used for a given date and time. 4.3.4.2 Obtain the wind speed (mph) at 35ft from the meteorological computer printout and record in
.3 Appendix A.
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE Epip-14B REVISION DOSE ASSESSMENT ~ l Page 7 of 15 A 4.3.4.3 Complete calculations on Appendix A and record the resultant X/Q value on Appendix B, Sections A and B. 4.3.4.4 If necessary, Xu/Q values for specific receptor sites can be obtained from the overlay and recorded on Appendix A.
- 1. Select the appropriate overlay that corresponds to the determined stability category and match the overlay with the release point on the map.
- 2. Rotate the overlay until the plume centerline is oriented in the direction of the compass heading.
- 3. Identify key receptor locations in the path of the dispersing plume and record on Appendix A, column 1.
- 4. Xu/Q values on the overlay are shown as isopleth
'I'i lines printed directly upon the overlay. Each k s/ isopleth line is labeled with a capital letter to indicate its relative strength. The numerical value corresponding to the letter is shown in the far, lower right corner of the overlay. Plume centerline values a.re marked by plus marks (+)
directly along the centerline. Each plus mark corresponds to the downwind distance adjacent to the (+) mark. The Xu/Q associated with each centerline distance is indicated in the lower right cornec of the overlay, directly to the lef t of the Xu/Q value associated with the isopleth lines (capital letter values). Utilizing these values, it is possible to interpolate Xu/Q values - for any area bounded by the outer =ost isopleth of each overlay. Record the appropriate Xu/Q for each specific receptor site on Appendix A, column 2.
- 5. Obtain the wind speed (mph) at 35ft FROM which the wind blows from the meteorological computer printout (angular degrees from due north) and record on Appendix A, column 3.
- 6. Complete calculations and record X/Q values for k;;7) the appropriate receptor location on Appendix B, column 4 PVP6 0 COA (8@
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PVNGS EMERGENCY PLAN QCEDURE i
1 REVISION DOSE ASSESS}ENT Page 8 of 15 1 i i
4.3.5 Calculate the Whole Body Gamma Dose Commitment from noble gases for each key receptor site, Appendix B, Section A.
Only one receptor site should be used for calculation sheet (Appendix B).
4.3.5.1 Obtain the average gamma decay energy (Mev/ dis) utilizing the ef fective age of the noble nas at the .
yaceptor site from Appendix C and record on Appendix B, ftction A.
4.3.5.2 Complete calculations to determine the dose rate.
4.3.5.3 Determine the exposure time based upon duration of the i
release and record in column B.
4.3.5.4 Complete calculations in Section A to determine the dose, i
4.3.6 Calculate the thyroid inhalation dose commitment from all i
radioiodines, Appendix B, Section B.
rs. 4.3.6.1 Complete calculations in Section B to I-131 Int. Dose
! (gj) Rate, column 6.
4.3.6.2 Obtain the ratio of integrated thyroid dose from all l
iodines to integrated dose from I-131 as a function of ef fective age at receptor site from Appendix D and record in column 7.
t 4.3.6.3 Complete calculations of Section B.
i 4.3.7 Update and refine dose calculations every hour and upon i
significant (as indicated below) changes in one or more of j the following parameters using Appendix B, Sections A and B. .
o Release Rates (+ 20% change) o Duration of the Release (+ 20%)
i o Existing Meteorological Conditions
- (UD - 25' change Stability - j; I category)
(WS - j; 20% change) , 4.3.8 Sum previous exposures using Appendix B, Sections A and B. a 4.3.9 Compare the dose commitments in Appendix B to the protective 4
,r.
action guidelines (EPIP-15) to make of fsite protective } Is_/ action recommendations to the State. i b2N Mk 40~62) 4 i k *
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PVNGS EMERGENCY PLAN PROCEDURE p '*' IMPLEMENTING PROCEDURE EPIP-14B Pa e 1 of 1 REVISION DOSE ASSESSMENT 1 Page 9 of 15 i DETERMINATION OF X/Q Windspeed Receptor Site Xu/Q at 35ft (mph) Factor X/Q Location (Overlay) Met Computer (m/sec/ mph) sec/m3
/ / o.447 =
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__~ _ . _ _ _ _ _ _ g b K; 3:IZ 3 EFIP-143 Fage 1 of 1 Rev. 1 Fage 10 of 13 A CALCULATION OF Wi! OLE 20DY AND THYROID DOSE COMMITNEKIS , Reactor Shutdown Date/ Time ._ Receptor 1.ceation ' Section Ar Integrated External khole Body Dose (Noble Cases) i Effective *(1) Dose Conversion Plume Age at Noble cas X/Q Camma Decay Factor Arrival Receptor Site Release Rate (sec/cu.m) Energy rem-dis-cu.a. Dose Rate Esposure Time Lose Time (hr) App F (Ci/sec) Appendix A (Mev/ dis) App C Mev-Ci-hr (rem /hr) (br) (ree) x x x 9.5 E + O2 = x x x 9.5 E + O2 = x = x x x 9.5 E + O2 = x = x x x 9.5 E + 02 - x = _m x x 9.5 E + O2 = x =
- NOTE (1): From Appendix F .
Section !!: Thyroid Inhalation Dose commitment from All Radiodines
- Dose Commitment Conversion Plume Effective *(1) I-131 Release Factor I-131*(3) 1-131 Int Dose Connaitment Erposure Dose Commitment Dose Comeitment Arrival Age Rate X/Q rem-cu.m. Dose Rate Ratio All todines/ Time Adult *(2) Child Time (hr) (Ci/sec) sec/m(3) hr-Ci (rem /hr) 1-131 App D (hr) (rem) (rem) x x 1.86E + 06 =
x x 1.86E + 06 = x x = x2 = x x 1.86E + 06 = x x = x2 = x x 1.86E + 06 = x x = x2 = x x 1.86E + 06 = x x = x2 =
- NOTE (1): From Appendix F 6
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'i 1 APPENDIX E EPIP-145 Page 1 of 1 peu. 1 Fase 13 of 15 1 . '
- EFFECTIVE ACE" DETERMINATION OF NOBLE CASES AS A FtTNCTION
, OF TRANSIT TIME AND THE EFFECTIVE ACE AT RELEASE TIME =
Downwind Distance Windspeed F.ffective Effective (5) of- at Transit (4) Age Age Receptor Site 33ft Time at Release at Receptor Site Location of neceptor (miles) (mph) (hr) (hr) (hr) 4
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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX F YJ IMPLEMENTING PROCEDURE EPIP-14B Page 1 of 1 REVISION D6SE ASSESSMENT 1 Page 14 of-15 ALTERNATE STABILITY CATEGORY DETERMINATION Visually observe the windspeed (m/sec) at 35ft. Utilize the following key to determine the atmospheric stability category. I 35 Foot Day Time Insulation Windepeed Thin Overcast or _4/8
~
m/sec) 3/8 1 Strong Moderate Slight Cloudiness Cloudiness 2 A A-B B i-2-3 A-B B C E 3-5 F 3 B-C C D E 5-6 C C-D D D 6 D C D D D D The night. neutral class, D, should be assumed for overcast conditions during day or i o Sampling time of ten minutes. o Night refers to the period from one hour before sunset to one hour af ter sunrise. , l o Class D may be assumed for overcast condition during day or night, regardless of windspeed, o
" Strong" incoming solar radiation; solar altitude greater than 60* with
( clear skies. o " Slight" incoming solar radiation; solar altitude from 15' to 35' with l clear skies. 4 l i 6 l f I P/256 0CDA 68.82)
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CPERIX C EPIP-148 Fase 1 of 1 4 Bew. 1 Fase 15 of 15 )A , e SITE BOUNDARY Xu/Q VALUES *
- Xu/Q Wind Direction Distance Stability Category t FROH (a) (mi) A B C D E F C
. S (168.75 - 191.25) 0.64 1.1 (E-6) 8.8 (E-i,) 2.8 (E-5) 8.1 (E-5) 1.4 (E-4 ) 2.8 ( L-4 ) 4.6 (E-4 ) ,
SSW (191.25 - 213.73) 0.66 1.1 (E-6) 8.8 (E-6) 2.3 (E-5 ) 8.1 (E-5) 1.5 (E-5) 2.8 (E-4) 4.6 (E-4) SW (213.75 - 236.25) 1.37 2.1 (E-7) 3.1 (E-6) 1.4 (E-5) 4.5 (E-5) 8.5 (E-5) 1.7 (E-4 ) 3.3 (E-4) ' W5W (236.75 - 253.75) 1.22 2.1 (E-7) 3.1 (E-6) 1.4 (E-5) 4.5 (E-5) 8.5 (E-5) 1.7 (E-4 ) 3.3 (E-4 ) W (258.75 - 281.75) 1.20 2.1 (E-7)- 3.1 (E-6) ' 1.4 (E-5) 4.5 (E-5) 8.5 (E-5) 1.7 (E-4) 3.3 (E-4 ) WNW (281.75 - 103.75) 1.22 2.1 (E-7) 3.1 (E-6) 1.4 (E-5) 4.5 (E-5) 8.5 (E-5) 1.7 (E-4 ) 3.3 (E-4 ) IN (303.75 - 326.25) 1.27 2.1 (E-7) 3.1 (E-6) 1.4 (E-5) 4.5 (E-5) 8.5 (E-5) 1.7 (E-4) 3.3 (E-4 ) tiNW (326.25 - 348.75) 1.70 6.6 (E-8) 1.4 (E-6) 8.4 (E-6) 2.9 (E-5) 5.7 (E-5) 1. 2 ( E-4 ) 2.5 (E-4) N (348.75 - 11.25) 1.46 6.6 (E-8) 1.4 (E-6) 8.4 (E-6) 2.9 (E-5) 5.7 (E-5) 1.2 (E-4) 2.5 (E-4 ) NNE ( 11.25 -' 33.75) 1.00 1.1 (E-6) 8.8 (E-6 ) 2.8 (E-5) 8.1 (E-5) 1.5 (E-5) 2.8 (E-4) ' 4.6 (E-4 ) NE ( 33.75 - 56.25) 0.66 1.1 (E-6) 8.8 (E-6 ) 2 8 (E-5) 8.1 (E-5) 1.5 (E-5) 2.8 (E-4) 4.6 (E-4 ) ENE ( 56.25 - 78.75) 0.55 1.2 (E-5) 4.'3 (E-5) 8.9 (E-5) 2.1 (E-4 ) 3.3 (E-4 ) ' 5.1 (E-4 ) 1.1 (E-3) E ( 78.75 - 101.25) 0.54 1.2 (E-5) 4.3 (E-5) 8.9 (E-5) 2.1 (E-4 ) 3.3 (E-4) 5.1 (E-4 ) 1.1 (E-3) ESE (101.25 - 123.75) 0.55 1.2 (E-5 ) 4.3 (E-5) 8.9 (E-5) 2.1 (E-4 ) 3.3 (E-4 ) 5.1 (E-4 ) 1.1 (E-3) SE (123.75 - 146.25) 0.65 1.1 (E-6) 8.8 (E-6) , 2.8 (E-5) 8.1 (E-5) 1.5 (E-5) 2.8 (E-4) 4.6 (E-4) SSE (146.25 - 168.75) 0.66 1.1 (E-6 ) 8.8 (E-6) 2.8 (E-5) 8.1 (K-5) 1.5 (E-5) 2.8 (E-4) 4.6 (E-4 ) (a) Based on 22 1/2' sectors. ' PLLME CENTERLit;E Xu/Q VALUES Stability Xu/rf values Category 2 mi 5 mi 10 mi A 5.5 (E-8s 2.6 (n;-8) 1.4 (E-8) a 7.8 (E-7) 3.6 (E-8) 1.8 (E-8) C 5.8 (E-6) 1.5 (E-6) 3.9 (E-7) D 2.1 (E-5) 5.8 (E-6) 2.0 (E-6) E 4.2 (E-5) 1.3 (E-5 ) 5.0 (E-6) F 9.5 (E-5) 3.2 (E-5) 1.4 (E-5) C 2.0 (E-4 ) 7.4 (E-5 ) 3.3 (E-5) 4 I 4 e g
- e. ,.
4
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PVNGS EMERGENCY PLAN [ROCEDURE o O IMPLEMENTING PROCEDURE EPIP-15
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REVISION PROTECTIVE ACTION GUIDELINES 0 Page 1 of 11 ASSIGNZD COPY PVNGS SM # f-M i- 1 APPROVED BY: . .j M-w-j,v. DATE- [ f f
, , ,,DATEEFFECTIVE
, ///-d 9 9 __ DN-1669A/0196A PV216 0 COA (6 2
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PVNGS EMERGENCY PLAN [ROCEDURE
] IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 0 Page 2 of 11 TABLE OF CONTENTS .
SECTION PAGE NUMBER ( 1.0 OBJECTET 3
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 4
,. 4.3 Instructions S N./
APPENDICES Appendix A - Recommended Protective Actions 8 Appendix B - Whole Body and Thyroid Guidance Charts 9 Appendix C - Reduction in External Gamna Dose From Passing . 10 Cloud l - Appendix D - Reduction in Inhalation Dose from Passing Cloud 11 l l i l t PY216 OCD4 (8 th v-e e
PROCEDURE PVNGS EMERGENCY PLAN NO. O IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 0 Page 3 of 11 1.0 OBJECTIVE , 1.1 The objective of this procedure is to provide a basis for relating actual or projected plume exposure doses to the Environmental ~ Protection Agencies (EPA) Protective Action Guides (PAG's). With this relationship defined, APS personnel can more effectively recommend appropriate protective actions . to county and state agencies.
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIS-02, "PVNGS Emergency C1sasification" 2.1.2 EPIP-14A, " Release Rate Determination" 2.1.3 EPIP-14B, " Manual Offsite Dose Projection" () 2.1.4 EPIP-17, "Offsite and Site Boundary Monitoring" 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 Manual'of Protective Action Guides and Protective Actions for Nuclear Incidents; as revised May, 1980; { EPA-520/3-75-001 l 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 imple=ent the protective actions. 3.2 A protection action guide under no circumstances implies an acceptable dose. 3.3 PAG's for the general public are given in ranges. The lowest values should be used if there are no major local constraints ( , in providing protection at this level. Local constraints =ay, ! however, make the lower values icpractical to use, but in no ! case should the higher value be exceeded in determining a need i for protective action. PY216 00CA (8.83 1
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PROCEDURE PVNGS EMERGENCY PLAN NO. O IMPLEMENTING PROCEDURE EPIP-15 REVISION
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PROTECTIVE ACTION GUIDELINES 0 Page 4 of 11 3.4 The projected dose and affected offsite areas will depend upon the curies released, release rate, duration of the release, isotopic mixture of the release (varies with effective age) and meteorological conditions. 3.5 At times, selection of protective actions must be considered subjectively as conditions beyond the scope of this procedure . exist. 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 4.1.1 Dose estimates which population groups may potentially receive, are calculated in accordance with EPIP-14B. This dose esti= ate 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 f3 action are sufficient to offset any undesirable features
) of the protective action.
The Protective Action Guide (PAG) is the projected dose to individuals in the population which warrants taking protective action. It is used only in an ex post facto effort to minimize the risk from an event which is occurring or has already occurred. 4.1.2 The authority and responsibility for the decision to notify and recommend protective actions to the appropriate authorities belongs to the Emergency Coordinator until he is relieved of this responsibility by the Emergency , Operations Director. 4.1.3
- The Radiation Protection Coordinator will be responsible l for apdating and refining dose assessments for critical l receptor site. locations and evaluating appropriate protective actions.
4.1.4 The Radiatica Protection Coordinator will be responsible for relaying dose assessment and protective action evaluations to the Emergency Coordinator. 4.2 Prerequisites i.2.1 An ALERT, SITE E!ERGENCY, or a GENERAL EMERGENCY has been
'/ declared in accordance with EPIP-02.
PV2t6 OCD4 (S 82) e
PVNGS EMERGENCY PLAN PROCEDURE 3 NO. IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 0 Page 5 of 11 4.2.2 Projected whole body and thyroid dose rates and integrated dose for critical receptor site locations have been calculated in accordance with EPIP-14B, and such doses warrant evaluating, and if necessary, recommending protective actions. 4.3 Instructions - 4.3.1 Radiological Protection Coordinator / Radiation Protection Monitor 4.3.1.1 Update and refin, dose estimates for critical receptor site locations upon significant changes in one or more of the following parameters: o Release rates. o Duration of the releases. o Isotopic mixture of the release (varies as a function of effective age).
- -s o Meteorological conditions.
~'
4.3.1.2 Should the projected doses indicate that sheltering or evacuation should be considered, determine the effectiveness of these protective actions as described below. NOTE PAG's for the general population are contained in Appendix A. Associated thyroid guidance charts and whole body charts are summarized in Appendix B. .
- a. 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+IN+T3+TT Where: Tp = Time delay after occurrence of the incident associated with notification of responsible officials, interpretation of duta, and the decision to evacuate as a protective action. l Pv216 000A .8 82) e h
PVNGS EMERGENCY PLAN PROCEDURE
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IMPLEMENTING PROCEDURE EPIP-15 REVISION
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PROTECTIVE ACTION GUIDELINES 0 Page 6 of 11 T.N = Time required by officials to notify people to evacuate. Tg = Time required for people to mobilize and get under way. l l TT = Travel' time required to leave the affected. - areas. If evacuation is completed before the plume arrives, then evacuation is 100 percent effective. To determine the time of exposure 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 +,IT f Where:
.(;j TB = Time projected before release begins.
TT = Time projected for plume travel for given windspeed and downwind distances from the start of release. To calculate TT refer to procedure EPIP-143. Evaluate constraints against evacuation. Compare ! the estimated evacuation time T(EV) with the l estimated plume arrival time, T(PA). Under the j following co'nditions evaluate the benefits of sheltering vs. the benefits of evacuation. -
- 1. In cases where there is no tic.e to evacuate prior to the arrival of the plume.
- 2. The projected evacuation time and time before plume arrival are nearly equal.
If evacuation appears to offer a significant reduction in dose (greater than sheltering) recommend evacuation to the appropriate county
- and/or state officials.
PV24 000A 18 82)
PROCEDURE PVNGS EMERGENCY PLAN N O. IMPLEMENTING PROCEDURE EPIP-15 REVISION PROTECTIVE ACTION GUIDELINES 0 Page 7 of 11
- b. Sheltering Effectiveness o If evacuation does not offer significant dose avoidance or if local constraints prevent evacuation recommend th4t officials war.n the affected population to:
- 1. Seek shelter.
- 2. Close windows.
- 3. Turn off ventilation systems.
- 4. Seal cracks in doors with wet rags.
o Control access to the affected area. o Evaluate the possibility of evacuation after the plume has passed:
/ 1. After the plume has passed, evaluate the significance of ground deposition in accordance with EPIP-17.
- a. Determine if dose rates are sufficient to warrant subsequent evacuation.
I 2. Multiply the projected dose by the l external shielding factor, Appendix C). Compare the projected dose to the PAG for whole body gamma dose. I ! o tvaluate the significance of inhalation dose. (Shielding factors for inhalation doses are presented in Appendix D). Shielding factors are for a sealed, wood-frame house. l
- 1. Multiply the projected dose by the inhalation shielding factor to determine the reduction in inhalation dose from the plume. Cocpare the projected dose to the PAG for thyroid dose.
1 o Determine the critical organ of concern, the - _ whole body or the thyroid. Compare the PAG l for the critical organ to the PAG for that-organ. I mucoa is m l
F .i w.) .'.). i 2 h REC 01@! ENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY AND THYROID ' DOSE 3 FROM EXPOSURE TO A CASE 0US PLUME 7 - Projected Dose (rem) to m T 4 the Population Recommended Actions (a) Comments $ r" 2 y mg Whole Body - less than 1.0 No planned protective actions (b). Previously recommended O E y) - Offsite authorities may issue an protective actions may be E 2m Thyroid - less than 5 advisory to seek shelter and reconsidered or terminated. yE await further instructions. $ gm3 Monitor environmental radiation d g levels. O y o oz Whole Body - 1.0 to 5 Seek shelter as a minimum. If constraints exist to 5 OO Consider evacuation /unless prevent full-scale evacuation, N O -< Thyroid - 5 to 25 constraints make it impractical. special consideration should C mm Ifonitor environmental radiation be given for evacuation of M UF levels. Control access to children and pregnant women. hg affected areas. m Whole body - 5 and above Conduct mandatory evacuation. Sheltering is an alternative , !!onitor environmental radiation if evacuation can not be Thyroid - 25 and above levels and adjust area for promptly accomplished. mandatory evacuation based 5 on these levels. Control $ '$3' ' access to affected areas. 5
- h@
7 s (a) These actions are recommended for planning purposes. Protective action decisions at the , g m time of the incident must take existing conditions into consideration (e.g., weather, plume arrival time). (b) At the time of the incident, officials may implement low-impact protective actions in y , keeping with the principle of maintaining radiation exposures as low as reasonably g gh achievable (ALAL\). ' m om os O sk O >4 m m 5 ___- a
PVNGS EMERGENCY PLAN PROCEDURE
., NO. APPENDIX B IMPLEMENTING PROCEDURE EPIP-15 Page 1 of 1 REVISION PROTECTIVE ACTION GUIDELINES 0 Page 9 of 11 WHOLE BODY GUIDANCE CHART -
IF THEN i Projected dose less than 1 rem No Action Shelter dose less than 5 rem. Shelter
- l Shelter dose equal to or greater than 5 rem and evacuation dose equal to or greater than Shelter
- shelter dose.
Shelter dose equal to or greater than 5 rem and evacuation dose less than Evacuate Shelter dose NOTE: Considerations and methodoligies for assesing protective actions have been discussed. The actual selection of protective actions must be considered subjectively, as many factors beyond the scope of this f ~1; procedure may exist which, in the judgement of the Emergency Operations
% Director and/or Ecergency Coordinator override the criteria contained in this procedure.
i The' following guidance Charts summarize protective actions and the - conditions dictating each type of action. THYROID GUIDANCE CHART IF THEN Projected dose is less than 5 re n No action - Shelter
- for -
l Shelter dose is less than 25 rem children & l wonen of child l bearing age. Shelter dose equal to or greater than , 25 rem and evacuation dose equal to or Shelter
- greater than shelter dose.
l Shelter dose equal to or greater than 25 rem and evacuation dose equal to Evacuate or less than shelter dose.
'
- Shelter is to be with ventilation control. Ventilation control means turning off air-conditioners or fans, closing doors and
( windows thus preventing access of outside air. PV2'6 0CCA (8 82)
1 PVNGS EMERGENCY PLAN PROCEDURE
^ NO. APPENDIX C IMPLEMENTING PROCEDURE EPIP-15 Page 1 of 1 REVISION PROTECTIVE ACTION GUIDELINES 0 Page 10 of 11 REDUCTION IN EXTERNAL GA!D4A DOSE FROM PASSING CLCUD SHIELDING FACTOR (a)
STRUCTURE OR LOCATION AVERAGE ' RANGE
- a. Outside 1.0 -
~
- b. Vehicles 1.0 --
- c. Wood frame house (no basement)(b) o,9 _
- d. Basement of wood house 0.6 0.1 to 0.7(c)
- e. Masonry house (no basement) 0.6 0.4 to 0.7(c)-
- f. Basement of masonry house 0.4 0.1 to 0.5 CC)
- g. Large office or industrial building 1.2 0.1 to 0.3(c,d)
I
^
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 mainly due to different wall materials and different geometries. l (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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PROCEDURE PVNGS EMERGENCY PLAN N O. APPENDIX D IMPLEMENTING PROCEDURE EPIP-15 Page 1 of 1 REVISION
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PROTECTIVE ACTION CUIDELINES 0 Page 11 of 11 INHALATION SHIELDING FACTORS FOR A WOOD HOUSE, - SNUG DOORS, CLOSED WINDOWS G ' S 1.0 ' * * * * * * *
- 8 mph (3.6 M/S) .
3 . d o o .8 - 4 mph 6 . (1.8.M/S) . s
- 3
$ .6 - -
5 0 . s .
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b Wind Speed = 1 mph (.447 M/S) g ., g i c
.2 "
C p L Note: 1; mph = 0.447 M/S , 5 5 . , . . , . . . E
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O l O 2 4 6 8 10 l l . EXPOSURE TIME (HRS) l l '. PV2'6 0CCA 48 80) { l
PVNGS EMERGENCY PLAN PROCEDURE N O. p IMPLEMENTING PROCEDURE EPIP-16 REVISION ONSITE- SURVEYS AND SAMPLING 0 Page 1 of 18 l ASSIGNED COPY
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PVNGS SBI & ( J
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l l APPROVED BY: Mh. ,_--,f_ y- _ DATE [ . T p.sIE EFFECTIVE ///-4-[7 DN-1629A/0190A h2*6 000418,82) l .
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PVNGS EMERGENCY PLAN PROCEDURE NO.
.',' IMPLEMENTING PROCEDURE EPIP-16
(,a.J REVISION ONSITE SURVEYS AND SAMPLING 0 Page 2 of 18 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 3 -
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 P::erequisites 5 (~ s, 4.3 Instructions 7
\I-APPENDICES l
Appendix A - Ecergency Onsite Monitoring Data Sheet: 13 Beta / Gamma Dose Rate Measurements Appendix B - E=ergency Onsite Monitoring Data Sheet: 14 Particulate and Radiolodine Samples l . l Appendix C - Emergency Onsite Monitoring Data Sheet: 15 Soil, Water, Vegetation and Surface Contamination Samples Appendix D - Site Area Survey Map 16 Appendix E - Gross Particulate and Gross Iodine Air 18 Concentrations i i ! m,. m o .a l 4 ..-
PVNGS EMERGENCY PLAN PROCEDURE N O. O. IMPLEMENTING PROCEDURE EPIP-16 REVISION ONSITE ' SURVEYS AND SAMPLING 0 Page 3 of 18 1.0 OBJECTIVE - To provide a procedure for emergency onsite radiological monitoring and surveys to be undertaken in the event of a release of radionuclides from PVNGS. Instructions for the implementation of the program, collecting samples, and performing surveys are provided. Onsite emergency monitoring - should be be performed by PVNGS personnel.
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-17, "Offsite Surveys and Sampling" 2.1.2 EPIP-18, " Emergency Exposure Guidelines"
,t 2.1.3 EPIP-38, " Emergency Equipment and Supplies Inventory"
- ~ h
\_/ 2.2 Developmental References 2.2.1 NUREG-0654, Rev. 1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and j Preparedness in Support of Nuclear Power Plants" USNRC,
! 11/80 l 2.2.2 NUREG-0737, " Clarification of TMI Action Plan Requirements" USNRC, 11/80 2.2.3 75RP-92248, Airborne Radioactivity Sampling and Measurement l 2.2.4 75RP-92217, Radioactive Contamination Survey Procedure 3.0 LIMITATIONS AND PRECAUTIONS , 3.1 Emergency radiation exposures in excess of PVNGS , l administrative limits must be authorized by the Emergency Coordinator in accordance with EPIP-18. 3.2 Under the following conditions monitoring personnel should withdraw from the area immediately and relay this information to the Radiological Protection Coordinator. I ! 3.2.1 If the area beta / gamma dose rate is equal to or greater than 10R/hr. W216 ECa i4 82) 4 y
J PROCEDURE PVNGS EMERGENCY PLAN N O. b:< v IMPLEMENTING PROCEDURE' EPIP-16 REVISION ONSITE S'URVEYS AND SAMPLING 0 Page 4 of 18 3.2.2 If airborne activity is suspected at the survey location and the monitoring team is not wearing full protective clothing and respirators. The following conditions may indicate airborne radioactivity: 3.2.2.1 A continuous air monitor is in alarm condition. 3.2.2.2 Observation of steam. 3.3 Use appropriate protective clothins, equipment, and respirators (EPIP-38). 3.4 Clearly label contaminated areas and control access and egress from the area. 3.5 Check batteries and perform source check . test on survey i instruments to be used. 3.5.1 Allow warm up time for high range survey equipment. (- 3.6 (. > While in route to the survey location keep the survey meter on, with the meter set on the high scale and switching down as necessary. 3.7 Check fuel level in vehicles to be used. 4.0 DETAILED PROCED"RE 4.1 Personnel Indoctrination 4.1.1 As delineated in EPIP-01, the Radiation Protection Monitor . until relieved by the Radiological Protection Coordinator is responsible for the implementation of this procedure. i 4.1.2 Persons involved in air and environmental gross gamma and beta sampling should be familiar with operation of the air samplers, cartridges, filters, and survey instruments. 4.1.3 Members of Survey Teams should proceed to the Operations l Support Center for instructions. The Radiological l Protection Coordinator shall: 4.1.3.1 Supervise the formation of Monitoring Teams.
; o The Monitoring Team Leader will com=unicate with the Radiological Protection Coordinator every one i
half hour via hand held radio. r P/2 *6 KO A t& 82) l . . n ,. -.
PVNGS EMERGENCY PLAN PROCEDURE N O. O IMPLEMENTING PROCEDURE EPIP-16 s.". s REVISION ONSITE SURVEYS AND SAMPLING 0 Page 5 of 18 4.1.3.2 Brief and dispatch Monitoring Teams. 4.2 Prerequisites 4.2.1 An ALERT or more severe emergency _ has been classified per the provisions of EPIP-02. 4.2.2 Don protective clothing and respiratory apparatus if necessary. 4.2.3 Obtain appropriate sampling equipment. 4.2.3.1 Equipment located in the emergency lockers is listed in EPIP-38. As a minimum, each Survey Team should assemble the following types of equipment for the appropriate type of sample collection:
- a. All Survey Teams:
- Legal TLD, Job TLD and Alarm Dosimeter
(
)
- Low and High Range B/ Survey Meter
- Portable Radio l
l - (10) Plastic Bags (small)
- Labels
- Tape
- (2) Pens .
l I
- Site Area Survey Map (Appendix D)
- b. Air Sampling Survey Teams:
- CPM Survey Meter -
- Portable Sampler for Particulate and Radiciodine Samples
- (5) Silver Zeolite (AgX) Cartridges for Environmental Samples k
[ .(
- Box of Particulate Filters PV216 000A is Sh 7e y_ . - -
PROCEDURE PVNGS EMERGENCY PLAN nO. p) 2 IMPLEMENTING PROCEDURE EPIP-16 REVISION ONSITE SURVEYS AND SAMPLING 0 Page 6 of 18
- Manual Air Pump for Noble Gas Samples (i.e.,
Rubber Bulb)
- Noble Gas Collection Chamber
- Watch (with Second Hand)
- c. Soil, Vegetation, and Water Samples, and TLD Monitoring Sampling Teams:
- Shovel
- Tape Measure
- Scissors or Knife
- Liter Bottle
- Pipette with Rubber Bulb a
_, - (6) TLD's
- d. Surface Contamination Survey Teams:
l - Smear Papers Tape Measure 4.2.3.2 In addition, it is suggested that the following items be considered: o Protective clothing and/or respirators . Coveralls, hoods, shoe covers l Respiratory equipment (self containIed or filter mask) o Plastic Sheeting o Rope o Caution, Radiation Area Sign o Inverter (if a vehicle is the power source for air sampler)' _) o 100 ft. Extension Cord (f.or air sampler) FY2t6 KDA 49 th
PROCEDURE PVNGS EMERGENCY PLAN NO. IMPLEMENTING PROCEDURE EPIP-16 (3 REVISION ONSITE SURVEYS AND SAMPLING - 0 Page 7 of 18 4.2.4 Record serial numbers of' dosimeters, survey instruments and air samplers in Appendices A and B. 4.2.5 Check batteries and perform source check tests on survey instruments. Allow warm up time for high range survey equipment. 4.2.6 Obtain background readings from survey instruments (window open and window closed, if appropriate). Record background values on Appendices A and B. 4.2.7 Complete Appendices A, B, and C headings. 4.3 Instructions 4.3.1 General Instructions 4.3.1.1 Air (radioiodine, particulates, and noble gases), gamma / beta, soil, vegetation should be sampled as
- directed by the Radiation Protection Monitor or , (]j Radiological Protection Coordinator.
_4.3.1.2 Time and locations of TLD changes shall be determined by the Radiological Protection Coordinator. 4.3.1.3 Survey meters should be left on while in transit. All inplant readings above 10R/hr and outside readings above 0.2mR/hr should be reported to the Radiological
~
Protection Coordinator. 4.3.2 Gross Radioactivity Measurement 4.3.2.1 Use one of the following instrument types (in order of preference): r
- a. Extended probe
- b. 0-5 R/hr survey meter
- c. 0-50 R/hr survey meter 1
4.3.2.2 While in route to the survey location keep the survey meter on, with the meter set on the high scale, switching down as necessary. 4.3.2.3 Upon arrival at the sursey location evaluate radiological conditions: f i
,.Y PV2te 000A t8 $2n
PVNGS EMERGENCY PLAN PROCEDURE N O. (', IMPLEMENTING PROCEDURE EPIr-16 ~ REVISION . ONSITE SURVEYS AND SAMPLING 0 Page 8.of 18
- a. Visual observation of presence of steam, failed piping or equipment, external radiation levels, surface conta=ination, airborne contamination; relay this information to the Radiological Protection Coordinator. Record findings on
, Appendix A.
- b. mR/hr at 3 feet above ground level:
- Determine the gross mR/hr at 3 feet with the beta shield closed. Subtract the "
Background:
window closed" value (from Appendix A). Record the net mR/hr value in Appendix A.
- Determine the gross mR/hr at 3 feet with the beta shield open. Subtract the " background:
window open" value (from Appendix A). Record the net mR/hr value in Appendix A. 77, c. mR/hr at 3 inches above ground level (repeat step () b above with the meter at three inches).
- d. Net beta dose rates:
1 The net beta dose rate is the net gamma / beta value l (window cpen) minus the net gamma value (window closed). Record values for beta dose rate in Appendix A. 4.3.3 Particulate and Radioiodine Air Samples (Appendix B) NOTE - 1 . , For environmental radioiodine air samples, l silver zeolite (AgX) cartridges will be l used, and counted in the field. NOTE - 2 Air sam le volumes should be 1 m3 ( (35.3ft ). l 4.3.3.1 Connect the air sampler to a 120V AC power source or: 4.3.3.2 Connect inverter and extension cord to car battery. (. .,s.j
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PW2'6 00CA e8 82) g-ye a
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PVNGS EMERGENCY PLAN PROCEDURE
- N O.
IMPLEMENTING' PROCEDURE EPIP-16 REVIS!ON ONSITE SURVEYS AND SAMPLING 0 Page 9 of 18 4.3.3.3 Assemble the sample head. The particulate filter should be upstream from the iodine cartridge. Attach the sample head to the air sampler. 4.3.3.4 Start the sampler in the variable position. 4.3.3.5 Adjust the flow rate. The maxi =um flow rate should be 4 CFM. It is suggested that the flow rate be 3 CFM. 4.3.3.6 Determinethesamplingtimenecessarytocollecta sample volume of 36ft . Record the sampling time . (in minutes) on Appendix B. 4.3.3.7 Calculate the flow rate in CFM using the following method: CFM (Initial) + CE4 (Final) = CFM (Sample Collection)
~
Where: (CFM (Initial), (CFM Final) and CFM (Sample Collection) are the initial flow rate, final
, flow rate, and mean flow rate, respectively, in CFM. Record the mean flow rate value on Appendix C.
4.3.3.8 Calculate the sample volume as follows and record in Appendix C. V(ft3) = CFM (Sample Collection) x Sample Collection Time (Minutes) l 4.3.3.9 Disassemble the sample head. Place the particulate - filter in a plastic bag, and label the bag with the j date, time, location, and sample volume. 4.3.3.10 For non environmental samples, place the charcoal cartridges in a plastic bag, and label with the date, time, location, and sample volume. 4.3.3.11 Environmental samples, Radioiodine Air Cone (uC1/cc).
- a. Hold the meter probe with an open window in contact or within one'(1) inch and perform a minimum (1) minute count on the AgX filte" immediately after sampiing, to obtain a 5.alue of gross iodine CPM. Record the value of gross iodine CPM on Appendix B.
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PVNGS EMERGENCY PLAN PROCEDURE NO. ( IMPLEMENTING PROCEDUP.E EPIP-16 REVISION ONSITE' SURVEYS AND SAMPLING 0 Pato 10 of 18
- b. Record the background count rate (CPM) on Appendix B. If NCPM is less than calculated MDA then. report MDA.
- c. Utilizing the information on Appendix E determine the gross particulate and gross radioicdine air concentrations. If Appendix E cannot be utilized, -
calculate t he air concentrations from the survey _, readings (CPM) and sample volume 3(ft ) utilizing Appendix B and the following equation.
- d. Complete calculations in Appendix B. Calculation:
uCi-ft3 A uCi , Net CPM x fl.6E-11) dom cc cc CFM (Sample Coll) x Collection Time (!!in) x Ee (cpm /dpm) Where: A = Iodine Activity uCi/cc Net CPM = Net Count Rate Conversion = (4.7E-07uci/dpm) - 2.83E+04cc/f t3 Factor Utilizing a Filter Efficiency of 0.96 CFM = Sample Collection Rate Ec = Counting Efficiency (cps /dpm)
- e. Place the AgX filter in a plastic bag, label the bag with the date, time, location, and sample volume. .
- f. Submit samples to the Chemistry Lab for analysis after completion of survey.
l 4.3.4 Noble Gas Air Samples , 4.3.4.1 Assemble the filter holder assembly as follows:
- a. Insert AgX cartridge into AgX holder. AgX cartridges may be used repeatedly during a one day period.
_ b. Place filter paper upstream of the AgX cartridge ( in the holder. PV2'6 GCDA at 02: L
PVNGS EMERGENCY PLAN [ROCEDURE o. IMPLEMENTING PROCEDURE EPIP-16 REVISION ONSITE SURVEYS AND St.MPLING 0 Page 11 of 18
- c. Attach holder to the manual gaseous collection chamber.
- d. Attach rubber bulb to petcock of gas collection chamber.
4.3.4.2 Collect noble gas air sample as follows:
- a. With both petcocks open, compress the rubber bulb slowly at least ten (10) times to collect a representative sample.
- b. Close both petcocks on the gas collection chamber.
- c. Disconnect the gas collection chamber from the rubber bulb and AgX holder.
- d. Place the gas collection chamber in a plastic bag. Label the bag with the sample location, date, and time.
4.3.4.3 Disassemble the AgX holder and contents as radioactive material. 4.3.5 Soil Samples (Appendix C) 4.3.5.1 Measure an area of 1 m2 on the ground (if possible). l 4.3.5.2 Collect soil from that area to a depth of less than 1 1/4 inch. Record the area and approximate depth of i the sample on Appendix C. 4.3.5.3 Place the soil sample in a bag. Lebel the sample with the location, date and time'of collection. 4.3.6 Vegetation Samples (Appendix C) 4.3.6.1 Measure an area of 1 m 2, 4.3.6.2 Cut the vegetation to a height of 1-2 cm being careful not to contaminate the vegetation sample with soil. 4.3.6.3 Place the vegetation sample in a bag. Label the sample with the location, date, and time of collection. v' Pv2'6 00CA i8 42)
PVNGS EMERGENCY PLAN PROCEDURE N O. (~~ lMPLEMENTING PROCEDl'aE EPIP-16 REVISION ONSITE SURVEYS.AND SAMPLING 0 Page 12 of 18 4.3.7 Water Samples (Appendix C) 4.3.7.1 If surface water is available, collect 1 liter of water with a pipet, and place in a 1 liter sample bottle. 4.3.7.2 Seal bottle, and label with the location, date, and time. 4.3.8 Surface Contamination Samples 4.3.8.1 Obtain survey map of area to be surveyed. 4.3.8.2 Number plastic bag and survey map with corresponding number for each location. 4.3.8.3 Secar an area (100 cm2 ) by making an "S" shaped curve about 12 inches long. If the area is less than 100cm2 smear all accessible surfaces. Care should be taken not to cross-contaminate smears. (' ~ ' 4.3.8.4 Place smear paper in plastic bag. Label with date, ) time, location, and area of smear. ' 4.3.9 Take samples to the Chemistry Laboratory for counting. . l l i M Pv216 0CDA i8:b2
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ONSITE' SURVEYS AND SAMPLING 0 Page 17 of 18
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REVISION ONSITE SURVEYS AND SAMPLING 0 Page 18 of 18 GROSS IODINE AND GROSS PARTICULATE AIR CONCENTRATION
- SAMPLE VOLUME NCPM 10ft3 20ft3 30ft3 40ft3 uCi/cc uC1/cc uCi/cc uCi/cc 300 4.80E - S 2.40E - 8 1.60E - 8 1.20E - 8 400 6.40E - 8 3.20E - 8 2.13E - 8 1.60E - 8 500 8.00E - 8 4.00E - 8 2.67E - 8 2.00E - 8 600 9.60E - 8 4.80E - 8 3.20E - 6 2.40E - 8 700 1.12E - 7 5.60E - 8 3.73E - 8 2.80E - 8
- 800 1.28E - 7 6.40E - 8 4.27E - 8 3.20E - 8
.s
( , 900 1.44E - 7 7.20E - 8 4.80E - 8 3.60E - 8 1000 1.60E - 7 8.00E - 8 5.33E - 8 4.003 - 8 1500 2.40E - 7 1.20E - 7 8.00E - 8 6.00E - 8 2000 3.20E - 7 1.60E - 7 1.07E - 7 8.00E - 8 3000 4.80E - 7 2.40E - 7 1.60E - 7 1.20E - 7 5000 8.00E - 7 4.00E - 7 2.67E - 7 2.00E - 7 7000 1.12E - 6 5.60E - 7 3.73E - 7 2.80E 10000 1.60E - 6 8.00E - 7 5.33E - 7 4.00E - 7 l 20000 3.20E - 7 1.60E - 6 1.07E - 6 8.00E - 7 30000 4.80E - 6 2.40E - 6 1.60E - 6 1.20E - 6 40000 6.40E - 6 3.20E - 6 2.13E - 6 1.60E - 6 l 50000 8.00E - 6 4.00E - 6 2.67E - 6 2.00E - 6
- 1
*Assuces a counter efficiency of.0.01 (cp:/dpm).
-
- Refer to Section 4.3.3.13 for equations and parameter descriptions.
*uCi/cc = C1/M3 Pv2'6 ORCA to.82) a
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PVNGS EMERGENCY PLAN Qceouse
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IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE SURVEYS AND SAMPI,ING 0 Page 1 of 16 ASSIGNED COPY l a. PVNGS SM # L, d. (.. 4 l APPROVED BY:
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PROCEDURE PVNGS EMERGENCY PLAN NO. IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE SURVEYS AND SAMPLING 0 Page 2 of 16 TABLE OF CONTENTS , PAGE NUM3ER SECTION 3 1.0 OBJECTIVE 0 3
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 4 4.0 DETAILED PROCEDURE 4
. 4.1 Personnel Indoctrination 4
4.2 Prerequisites 4.3 Instructions 5 APPENDICES Appendix A - E=crgency 0FFSITE Monitoring Data Sheet: 10 Beta /Canca Dose Rate Measurements Appendix B - Emergency 0FFSITE Monitoring Data Sheet: 11 l Particulate and Radioiodine Samples Appendix C - Emergency dFFSITE Sampling Data Sheet: Soil, 12 Water and Vegetation Samples" Appendix D - Map Indicating Offsite Sampling Locations 13 Appendix E - Sample Types and Locations 14 Appendix F - Gross Particulate and Gross Iodine Air 16 Concentrations PV216 CCCA (8482) 49 1
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PVNGS EMERGENCY PLAN PROCEDURE
.- N O.
( IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSir' S'URVEYS AND SAMPLING 0 Page 3 of 16 mm 1.0 OBJECTIVES . Toprovideaprocedureforemergencyo[fsiteradiological monitoring and field surveys to be undertaken in the event of airborne release of radioactive gases and particulates from l PVNGS. Instructions for implementing the program, locating sampling points, collecting samples, and performing field surveys are pro,vided. Offsite emergency sampling will be performed by PVNGS personnel until appropriate state authorities assume responsibility for conduccing surveys.
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-01, "PVNGS Emergency Organization" 2.1.2 EPIP-02, " Emergency Classification" , 2.1.3 EPIP-14B, " Dose Assess =ent" 2.1.4 Psily Performance Check List (with Counter Efficiencies) 2.1.5 EPIP-38, " Emergency Equipment and Supplies Inventory" 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" USNRC, 11/80 2.2.2 75 RP-9ZZ48, Airborne Radioactivity Sampling and Measurement i i 3.0 LIMITATIONS AND PRECAUTIONS 3.1 Use appropriate protective clothing, equipment, and respirators (EPIP-38). 3.2 Clearly label contaminated areas and material, control access and egress from the area. 3.3 Methods of co=munication between field survey teams and onsite i facilities consists 6f hand-held radies, and/or radio equipped ! vehicles. 3.4 Check fuel level in vehicles to be used. PV216 0004 68r82) i . c * -:~ .
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PVNGS EMERGENCY PLAN PROCEDURE
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IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE SURVEYS AND SAMPLING O Page 4 of 16 4.0 DETAILED PROCEDURE , 4.1 Personnel Indoctrination 4.1.1 As delineated in EPIP-01, the Radiation Protection Monitor until relieved by the Radiological Protection Coordinator is responsible for the implementation of this procedure. - 4.1.2 Persons involved in air and gross gamma and beta sampling should be familiar with operation of the air samplers, cartridges and filters, noble gas chambers, and survey instruments. 4.1.3. Members of survey teams should proceed to the Operations Support Center for instructions. The Radiological Protection Coordinator shall:
. 4.1.3.1 Supervise the formation of Monitoring Teams.
o The Monitoring Team Leader will communicate with the Radiological Protection Coordinator.every one half hour via portable radio. 4.1.3.2 Brief and dispatch Monitoring Teams. 4.2 Prorequisites 4.2.1 An ALERT or more severe emergency has been classified per the provisions of EPIP-02. 4.2.2 Don protective clothing and respiratory apparatus if necessary. 4.2.3 Obtain appropriate sampling equipment. j 4.2.3.1 Equipment located in the ccergency lockers is listed in EPIP-38. As a minimum, each Survey Team should assemble the following types of equipment: o Appendix D and E - lbp and Locations of Offsite r Sampling Locations l o Legal TLD, Job TLD and Alarm Dosimeters l 1 o (2) B/ Survey Meters o Portable Air Sampler o (6) TLD's (Environmental) Pv24 0t0A ta a ) 7
PVNGS EMERGENCY PLAN PROCEDURE,
,. ' N O.
IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE BURVEYS AND SAMPLING O Page 5 of 16 o (6) Silver Zeolite (AgX) Filters o Box of Particular Filters o (20) Plastic Bass (small) o (10) Radioactive Material Labels
- o tape o Watch (with Second Hand) o Inverter o 100 ft. Extension Cord o Scissors or Knife s,
o Shovel 7 ( o Tape Measure o (2) Liter Bottles o Pipette with Rubber Bulb o Noble Gas Collection Chamber o Vehicle , 4.2.4 Record serial numbers of survey instruments and air l samplers in Appendices A and B. l [ 4.2.5 Check batteries and perform source check tests on survey instruments. l 4.2.6 Complete Appendices A, B, and C headings. l 4.3 Instructions 4.3.1 General Information i 4.3.1.1 The sampling locations are those within a 22.5 degree sector on either side of the wind direction, unless l - otherwise directed by the Radiological Protection ( Coordinator.' The wind direction is determined for and recorded in EPIP-14B. Sampling locations are indicated on the Map of Offsite Sampling Locations, (Appendix D). ewsecon usm
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PVNGS EMERGENCY PLAN PROCEDURE
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. IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE SURVEYS AND SAMPLING 0 Page 6 of 16 4.3.1.2 Air (radioiodine, particulates, and noble gases),
gamma / beta, soil, vegetation and surface water (if available) should be sampled at each sampling location. 4.3.1.3 Change TLD's at each sampling location. Time and locations of future TLD changes shall be determined by the Radiological Protection Coordinator. 4.3.1.4 Survey meters should be left on while in transit. All offsite readings above 0.2 mR/h should be relayed to the Radiological Protection Coordinator. These sites should be extensively surveyed. 4.3.2 Gross Radioactivity Measurement (Appendix A) 4.3.2.1 mR/h at 3 feet above ground level:
- a. Determine the gross mR/h at 3 feet with the beta shield closed. Subtract the "
Background:
window
-closed" value (from Appendix A). Record the net -
mR/h value in Appendix A.
- b. Determine the gross mR/h at 3 feet with the beta shield open. Subtract the " background: window i
open" value (from Appendix A). Record the net mR/h value in Appendix A. 4.3.2.2 mR/h at 3 inches above ground level (repeat steps a and b above with the meter at three inches). 4.3.3 Particulate and Radioiodine Air Samples (Appendix B) i NOTE - 1 For environmental radioiodine air samples, silver eolite (AgX) cartridges should be used, and counted in the field. l NOTE - 2 Air sample volumes should be 1 m3 (35.3ftJ ). 4.3.3.1 Connect the air sampler to a 120V AC power source or: i 4.3.3.2 Connect inverter and extension cord to car battery. 4.3.3.3 Connect air sampler to cord, and turn on car. mc3 xca is m P r 9 * ~
PROCEDURE PVNGS EMERGENCY PLAN N O.
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A) IMPLEMENTING PROCEDURE Erle-17 REVISION OFFSITE S'URVEYS AND SAMPLIl!G 0 Page 7 of 16 4.3.3.4 Assechle the sample head. The particulate filter should be upstream from the iodine cartridge. Attach the sample head to the air sampler. 4.3.3.5 St t et the sampler in the variable position. 4.3.3.6 Adjust the flow rate. The maximum flow rate should be 4 CFM,. It is suggested that the flow rate be 3 CFM. 4.3.3.7 Determinethesamplingti=enecessarytocollecta sample volume of 36ft . Record the sampling time (in minutes) on Appendix 3. 4.3.3.8 Calculate the flow rate in CFM using the following method: CFM (Initial) + CEi (Final) = CFM (Sample Collection)
's Where: (CFM (Initial), (CFM Final) and CFM (Sample
/ Collection) are the initial flow rate, final flow rate, and mean flow rate, respectively, in CFM.
4.3.3.9 Disassemble the sample head. Place the particulate filter in a plastic bag, and label the bag with the date, time, location, and sample volume. 4.3.3.10 Perform a minimum (1) minute count on the AgX filter immediately after sa=pling, to obtain a value of gross iodine CPM. 4.3.3.11 Calculate the sample volume as follows. V(ft 3) = CFM (Sample Collection) x Sample Collection t Time (Minutes) 4.3.3.12 Calculate the net count rate from the radioiodine sample by subtracting the background count rate.
-4.3.3.13 Utilizing the information on Appendix F determine the gross particulate and gross radioicdine air concentrations. If Appendix F cannot be utilized, calculate the air concentrations from the survey w readings (CPM) and sample volume (ft 3 ) utilizing
( ,) Appendix B ahd the following equation: PV216 0CCA (8 92)
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6 PROCEDURE l PVNGS EMERGENCY PLAN f) .. IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE SURVEYS AND SAMPLING 0 Page 8 of 16
, uCi-ft3 uCi , Net CPM x (1.6E-11) dpm cc cc CFM (Sample Coll) x Collection Time (Min) x Ee (cpm /dpm)
Where: A = Iodine Activity uCi/cc Net CPM .
=
Net Count Rate Conversion Factor = (4.7E-07uci/dpm) - 2.83E+04cc/ft3 Utilizing a Filter. Efficiency of 0.96 CE! = Sample Collection Volume Ee = Counting Efficiency (cpm /dpm) 4.3.3.14 Place the AgX filter in a plastic bag, label the bag with the date, time, location, and sa=ple volume. I 4.3.3.15 Count the particulate filter. Record the gross counts (cpm) on Appendix B. 4.3.4 Noble Gas Air Samples 4.3.4.1 Assemble the filter holder assembly as follows:
- a. Insert AgX cartridge into AgX holder. AgX cartridges may be used repeatedly during a one day period.
t
- b. Place filter paper upstream of the AgX cartridge in the holder.
- c. Attach holder to the manual gaseous collection chamber.
l d. ' Attach rubber bulb to petcock of gas collection chamber. 4.3.4.2 Collect noble gas air sample as follows:
- a. With both petcocks open, compress the rubber bulb slowly at least ten (10) times to collect a f 'y representative sample.
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- b. C1cse both petcocks on the gas collection chamber.
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s PVNGS EMERGENCY PLAN [R MD'JRE r ,' IMPLEMENTING PROCEDURE EPIP-17 REVISION OFFSITE SURVEYS AND SAMPLING 0 Page 9 of 16
- c. Discernect the gas collection chamber from the rubber bulb and AgX holder.
- d. Place the gas collection chamber in a plastic bag. Label the bag with the semple location, date, and time.
4.3.4.3 Disassemble the AgX holder and treat contents as radioactive material. 4.3.5 Soil Sa=ples (Appendix C) 4.3.5.1 Measure an area of 1 m2 on the ground (if possible). 4.3.5.2 Collect soil from that area to a depth of less than 1/4 inch. Record the area and approximate depth of the sample on Appendix C. 4.3.5.3 Place the soil sample in a bag. Label the samp].e with the location, date and time of co11cetion. (N-') 4.3.6 Vegetation Samples (Appendix C) 4.3.6.1 Measure an area of 1 m 2, 4.3.6.2 Cut the vegetation to a height of 1-2 cm being careful not to contaminate the vegetation sample with soil.
- 4.3.6.3 Place the vegetation sample in a bag. Label the
[ sample with the location, date, and time of collection. ( 4.3.7 Water Samples (Appendix C) 4.3.7.1 If surface water is available, collect 1 liter of l water with a pipet, and place in a 1 liter sample
- bottle.
i i 4.3.7.2 Seal bottle, and label with the location, date, and time. 4.3.8 Milk Samples (Appendix C) f , 4.3.8.1 At milk sampling locations collect one liter of-milk I and place in a 1 liter sample bottle. 4.3.8.2 Seal bottle, and label with the location, date, and f time. l I f 4.3.9 Take sc=ples to the Chemistry Laboratory for counting. ! PV216 (COA tt 8h I l I n y-- -
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m Z APS C11a Bend Substation p. OO 7 TLD, Aiz SE8 Arlington School 8 TfD SSE5 Corner of 363rd Ave. & SPP Rd. f gg 9 RD 10 TLD S5 Corner of 371st Ave. & SPP Rd. h UI T SES Corner of 355th Ave. & Ward RJ. $ il 12 T1.D T!.D ESES Corner of 33?th Ave. & Dottins Rd. CM 13 TI.D E5 Corner of 339th Ave. & B-S Rd. T2 14 Ti.D !!NE 2 N1 ti Site Boundary M tc:E Site Boundary 14A TLD !!NE2 !!uckeye-Salome Rd. & 371st Ave. 15 TLD, Air 16 IJE2 tie Site Boundary Ti.D EllE2 ENE Site Boundary 17 TI.D E2 E Site Boundary
??A Air E4 351st Ave., I mi. S of B-S Rd. 32 Zo 10 TLD 19 TLD T.SE2 SE2 ESE Site Boundary SE Site Boundary Q Oy 20 TI.D SSE2 SSE Site Boundary 5 o 3 ,o m 2L T!.D, Air 22 T!.D SSU3 S3 S Site Boundary SSW Site Boundary z y @
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- g 34 *LD IMJ5 m M Corner Belmont Rd. & Van Buren Rd.
35 iLD, Air 2cN9 Tonopah, Palo Verde Inn Fire Station P Qb 36 TLD IS Corner of Wintersburg Rd. & Van Buren h "U M 37 38 TLD TLD ICIES Corner of 363rd Ave. & Van buren m M2 39 t:E5 Corner or 355th Ave. & Yuma Rd. 343rd Ave., 1/2 at. S of L. Buckeye p- OO 40 T1.D ' TLD, Air, Water ENE5 N3 Tra!!er Park; Water at Red Quatt Str. d g< M gY 41 TI.D WrN20 !!arquahala Valley School d 42 TLD N8 Ruth Fisher School 8 OI 43 TLD N45 Vulture Mine Rd. School, Wickenburg C )> 44 45 TLD, Air ENE35 APS E1 Ittrage Office (Sun City) M2 TLD ENE50 APS Dect Valley Office IT1 46 Water, Beg. NfN9 McArthurs Farm Tonopah 47 Water fan 6 Winters' Wells 48 bater SSE4 Well 14dbb 49 Water ECE4 Glover Restdence 351st Ave. & Dobbins - Road 50 Milk NE7 Balsley Dairy, 331st Ave. & Van Buren 'D 2
$1 Milk, Veg. E15 Butler Dairy, Fato Vende Rd. & Southern .O g"U 52 Vegetation E15 E
Cambron Farm. Mitter Rd. & Broadway 5 o 53 Hilk E20 Kerr Dalry. Dean & Buckeye Rds. m 54 Hilk E25 lioffman Dalry Airport & Dobbins 5 eo H U Z y c. 55 H11k E25 Imeck Dairy, Jackrabbit & Ilazen Rds. g m 56 Hlik E50 Mineso Dairy, Kyrene & Cuadalupe Rds. W O N (a) Table J-1, NUREC-0654; distances (in alles) are from centerline of Unit 2 containment. 5
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9 PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX F {') ~- IMPLEMENTING PROCEDURE EPIP-17 Page 1 of 1 REVISION OFFSITE SURVEYS AND SAMPLING 0 Page 16 of 16 GROSS IODINE AND GROSS PARTICULATE AIR CONCENTRATION
- SAMPLE VOLUME CPM 10ft3 20ft3 30ft3 40ft3 uCi/cc uCi/cc uC1/cc uCi/cc -
300 4.80 - 8
- 2.40 - 8 1.60 - 8 1.20 - 8 400 6.40 - 8 3.20 - 8 2.13 - 8 1.60 - 8 500 8.00 - 8 4.00 - 8 2.67 - 8 2.00 - 8 600 9.60 - 8 4.80 - 8 3.20 - 8 2.40 - 8 700 1.12 - 7 5.60 - 8 3.73 - 8 2.80 - 8 800 1.28 - 7 6.40 - 8 4.27 - 8 3.20 - 8
! / 900 l'.44 - 7 7.20 - 8 4.80 - 8 3.60 - 8 1000 1.60 - 7 8.00 - 8 5.33 - 8 4.00 - 8 1500 2.40 - 7 1.20 - 7 8.00 - 8 6.00 - 8 2000 3.20 - 7 1.60 - 7 1.07 - 7 8.00 - 8 3000 4.80 - 7 2.40 - 7 1.60 - 7 1.20 - 7 5000 8.00 - 7 4.00 - 7 2.67 - 7 2.00 - 7 7000 1.12 - 6' 5.60 - 7 3.73 - 7 2.80 - 7 l 10000 1.60 - 6 8.00 - 7 5.33 - 7 4.00 - 7 i
20000 3.20 - 7 1.60 - 6 1.07 - 6 8.00 - 7 30000 4.80 - 6 2.40 - 6 1.60 - 6 1.20 - 6 40000 6.40 - 6 3.20 - 6 2.13 - 6 1.60 - 6 50000 8.00 - 6 4.00 - 6 2.67 - 6 2.00 - 6
*Assu=es a counter efficiency of 0.01 (cp:/dpm).
- Refer to Section 4.3.3.13 for equations and parameter descriptions.
- *uC1/cc = Ci/M3.
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i PVNGS EMERGENCY PLAN QcEcune IMPLEMENTING PROCEDURE p/ Q EPIP-18 REVISION EMERGENCY EXPOSURE GUIDELINES 0 Page 1 of 10 ASSIG?iED COPY 5,9 / ,r PVNGS SM # L Y. l
. l APPROVED BY:
e / - - Mway
.- - - DATE [ f, [
/ DATE EFFECTIVE //)-/o- 9S' DN-1632A/0190A h.).
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Pv216 OCCA (8 82) i
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PVNGS EMERGENCY PLAN PROCEDURE NO. c., IMPLEMENTING PROCEDURE EPIP-18 REVISION EMERGENCY EXPOSUF E GUIDELINES 0 Page 2 of 10 TABLE OF CONTENTS . SECTION PAGE NUMBER 1.0 OBJECTIVE 3
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4.2 Prerequisites 5
- 4.3 Instructions 5 ks <
APPENDICES Appendix A - Radiation Exposure Permit 7 I Appendix B - Maximum Permissible DOSE EQUIVALENT for 8 Occupational Workers, 10CFR20 Values and PVNGS Values Appendix C - Emergency Exposure Limits 9 i l i l
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PROCEDURE PVNGS EMERGENCY PLAN NO. A.s IMPLEMENTING PROCEDURE EPIP-18 REVISION EMERGENCY EXPOSURE GUIDELINES 0 Page 3 of 10 1.0 OBJECTIVE . 1.1 This procedure address's e required authorization (Emergency Coordinator), guidance, and maximum exposure criteria in the event of a radiological emergency where it becomes necessary for emergency workers to exceed established PVNGS or 10CFR20 quarterly or annual exposure limits. .
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-16, "Onsite Surveys and Sampling" 2.1.2 EPIP-26, " Potassium Iodide (KI) Administration" 2.2 Levelopmental References f e>, 2.2.1 NCRP Report #39, 1971 Basic Radiation Protection Criteria
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2.2.2 EPA-520/1-75-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.2.3 10CFR20, Standards for Protection Against Radiation 2.2.4 PVNGS Quarterly and Annual Exposure Linits l 3.0 LIMITATIONS AND PRECAUTIONS i 3.1 The Emergency Coordinator must authorize doses in excess of . PVNGS Administration and/or 10 CFR 20 Limits but not greater than 100 rem. Emergency exposure limits are contained in Appendix C. 3.2 Personnel authorized to receive exposures in excess of occupational limits established by PVNGS (Appendix B) should meet the following criteria: 3.2.1 Personnel shall be volunteers. 3.2.2 Women of child-bearing age and capability shall not be permitted to receive emergency exposures (i.e., exposure
., greater than PVNGS Administrative Limits).
/ 3 .
)
3.2.3 Personnel shall be familiar with the hazards of exposure ! received under emergency conditions. PV216 000A 18,82) E aw
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PROCEDURE ym PVNGS EMERGENCY PLAN NO. ( ,,- IMPLEMENTING PROCEDURE Epip-18 REVISION EMERGENCY EXPOSURE GUIDELINES 0 Page 4 of 10 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 should be limited to one occurrence in a life time. 3.3 Administrative methods to minimize personnel exposure (such as ALARA) should remain in force to the extent consistent with i timely zescue, corrective and protective actions. 3.4 Personnel shall wear dosimeters appropriate for the measurement of anticipated exposure levels. These shall include: 3.4.1 Thermoluminescent Dosimeter (Legal). 3.4.2 Thermoluminescent Dosimeter (Job). f_
\,;; 3.4.3 Extremity Dosimeters, if appropriate (Appendix B, Note 2).
3.4.4 Alarm Dosimeters (in high radiation areas). ._ 3.5 If necessary, potassium iodide (KI) tablets should be administered in accordance with EPIP-26. 3.6 Protective clothing and/or respirators should be used as appropriate. 4.0 DETAILED PROCEDURE . 4.1 Personnel Indoctrination ! 4.1.1 The Emergency Coordinator is required to authorize i emergency exposures, up to but not exceeding the limits specified in Appendix C. 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 categories: 1) lifesaving actions, 2) corrective and/or
- c. protective actions, and 3) sampling under emergency
( ;) conditions.
- pmsmonice O
PROCEDURE PVNGS EMERGENCY PLAN NO. O it/ IMPLEMENTING PROCEDURE EPIP-18 REVISION ENERGENCY EXPOSURE GUIDELINES 0 Page 5 of 10 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's doses as low as is reasonably achievable.
; 4.2 Prerequisites 4.2.1 An e=ergency condition has resulted in the need to conduct lifesaving actions, and/or corrective or protective actions and/or sampling activities uhich might result in doses exceeding PVNGS occupational limits.
4.3 Instructions 4.3.1 Authorization NOTE The ic21owing actions shall be perfor=ed to document emergency radiation exposures. , (ed.{j) Although it is preferable to perform these steps before the exposure is received, the i Emergency Coordinator may, at his discretion, verbally authorize the
- emergency exposure with documentation to be I
completed at a later time. I i 4.3.1.1 The Radiological Protection Coordinator will provide the Emergency Coordinator with a radiological ! evaluation of the situations and conditions requiring i emergency exposures. l 4.3.1.2 The Radiological Protection Coordinator or his designee shall complete and sign a Radiation Exposure Permit (REP, Appendix A), detailing specific 7 protective equip =ent, procedures and allowable i emergency doses. 4.3.1.3 The Emergency Coordinator shall authorize the emergency exposure by: a) signing the REP, or b) through verbal authorization to the Radiological i Protection Coordinator who will then initial the time of approval. , / .'N l \c/ i
- m,. - . .
PVNGS EMERGENCY PLAN [ROCEDURE o-gP g t- IMPLEMENTING PROCEDURE EPIP-18 REVISION EMERGENCY EXPOSURE GUIDELINES O Page 6 of 10 4.3.1.4 Individual (s) authorized to receive emergency . exposures shall sign the REP, thereby agreeing to all conditions contained in the permit.
- a. Individuals shall obtain all equipment specified in the REP (Appendix A).
4.3.2 Personnel Exposure Control 4.3.2.1 Individuals shall abide to all conditions specified in the REP. 4.3.2.2 Individuals shall not enter any area where dose rates are unknown or unmeasureable with instruments immediately available. Prior to enter 'ng any radiation area:
- a. Allow time for meter warm up.
f?; b .' Check meter response with a check source.
%dP
- c. Enter suspected radiation areas with the meter set on the high scale, switching to lower scales as necessary.
4.3.2.3 Personnel shall complete the assigned task. t l 4.3.2.4 Personnel unable to complete the task within the I 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:
- a. Obtain initial esti=ates of the radiation dose of exposed personnel as quickly as possible.
- b. Update and re fine dose estimates at a later time.
1
- c. Immediately report exposures in excess of 10CFR20 (Appendix B) to the Manager of Nuclear Operations who will then report to the NRC per 10CFR20.403 l and 10CFR20.405.
t ,. I l PV216 0CDA (S.52) 1 -
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PROCEDURE i PVNGS EMERGENCY PLAN NO. APPENDIX A i O IMPLEMENTING PROCEDURE EPIP-18 REVISION Page 1 of 2 i-
- EMERGENCY EXPOSURE GUIDELINES 0 Page 7 of 10 l STANDARD RADIATION EXPOSURE PERMIT PVNGS Unit
- REP #
VALID FROM: TO JOB #: REP STATUS REP TYPE: TASK #: COMPONENT: JOB DESCRIPTION:
. MAP #: LOCATION:
REP REQUIRED BY: PROCESSING PRIORITY: RADIATION SURVEY CONDITIONS: . MAP #: SURVEY #: AIR SAMPLE ID #: TOTAL MPC FRACTION: BETA / GAMMA (mr/hr): CONTAMINATION (DPM): [h 7 WET / DRY: RADIATION PROTECTION REQUIREMENTS:
- 1. P.C. Requirements
- No Personal Outer Clothing Rubber Gloves ( 2 pr) i Lab Coat Surgeons Cap l
Plastic Shoe Covers Full Hood i Plastic Booties P.C. Coveralls ( 2 pr) l Rubber Shoe Covers ( 2 pr) Plastic Suit I - l 2. Respiratory Requirements i Full Face w/Cannister Bubble Hood ( Full Face w/ Supplied Air Stay Time min /hr SCBA R.G. 1.16 Class
- 3. Dosimetry Devices
' Legal TLD Radiation Survey Inst. ! Job TLD ,Special Dosimetry j Self-Indicating Dosimeter l -- u> l PV216 000A 1482) 4
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a PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX A () IMPLEMENTING PROCEDURE EPIP-13 Page 2 of 2 REVISION EMERGENCY EXPOSURE GUIDELINES O Page 8 of 10 1 STANDARD RADIATION EXPOSURE PFRMIT (CONT'D)* i 4. Special Instructions: l i ~ i 5. i i i ! SIGN 0FFS AND APPROVALS: Requested by: SS/ Unit Ready ! RP Preparation: Withdrawn / Canceled by: l RP Approval: Completed by: 4 I PERSONNEL ASSIGNED TO REP: I k FIRST IN LAST OUT AVAIL AVAIL TOT RES TOTAL TOTAL CODE # NAME DEPT WB (MR) MPC HR TIME HR WB(R) MPC HR e l j PVM-0CCA 10 829 l l
PROCEDURE PVNGS EMERGENCY PLAN NO. APPENDIX B (' IMPLEMENTING PROCEDURE EPIP-18 Page 1 of 1 REVISION DiERGENCY EXPOSURE GUIDELINES 0 Page 9 of 10 PVNGS ADMINISTRATIVE DOSE LIMITS /diD MAXIMUM PERMISSIBLE DOSE EQUIVALENT FOR OCCUPATIONAL WORKERS (10CFR20) DOSE LIMITS PVNGS ADMINISTRATIVE LIMITS 10CRF20 LIMITS Critical Organ mrem / quarter mrem / year mrem / quarter mrem / year Whole Body, Head and Trunk, 1,000 4,000 1,2501 -5,000 Active Blood-Forming Organs, . Lens of the Eye or Gonads Hands, Forearms, Ankles, Feet 15,000 N/A 18,7502 Skin of Whole Body 6,000 N/A 7,5002
) Other Organs (Thyroid), 5,0004 Tissues and Organ Systems 3
Pregnant Women (With 500erem 500 mrem 500 mrem Respect to the Fetus) 9 months 9 months 9 months
- 1. 3,000 millirem is permitted in a calendar quarter or 12,000 millires 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 lifetime exposure history is recorded on the NRC's Form 4 or equivalent. Doses exceeding 1,250 mres/ quarter must be reported to the NRC per 10CFR20,403 and 10CFR20.405. i
- 2. The licensee is required to supply appropriate personnel nonitoring equipment and sh'all require the use of such equipment by each individual that receives or is likely to receive a dose in any calendar quarter in excess of 257. of the applicable 10CFR20 value.
- 3. NCRP, ICRP Guidance.
- 4. NUREG C737.
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PVNGS EMERGENCY PLAN PROCEDURE
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) IMPLEMENTING PROCEDURE EPIP-18 Page 1 of 1
, REVISION EMERGENCY EXPOSURE GUIDELINES 0 Page 10 of 10 EMERGENCY EXPOSURE LIMITS Sampling Under Corrective or Lifesaving Accident Conditions
- Protective Actions . Actions ***
Whole Body (rem) 5 25 100. -
. Thyroid (rem) 25 125 NO LIMIT ****
Extremities (rem) 75 100** 200**
- NUREG 0737, Nov. 1980
** NCRP Report #39, 1971
*** EPA Protective Action Guides, July 1980
**** Thyroid exposure should be minimized to the extent feasibic by the use of
[]/s. respiratory protection and/or thyroid prophylaxis. However, no upper limit is specified for lifesaving action since complete loss of thyroid function may be considered an acceptable risk for saving life. L PY2'6 0004 is an
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e PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE gprp_19 REVISION ONSITE EVACUATION O Page 2 of 20 TABLE OF CONTENTS SECTION
}' AGE NUMBER 1.0 OBJECTIVE 3 2.0 REFERENCLd 3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 4 4.1 Personnel Indoctrination 4 4 .,2 Pr.e re quisite s'- 4 ,. 4.3 Instructions 5 ts.
APPENDICES Appendix A - Bechtel/PVNGS Pre-Evacuation Assembly' Plan 8 Appendix B - APS Construction Personnel Accountability 13 and Assembly Implementing Procedure Appendix C - Personnel Monitoring List 17 Appendix D - Onsite Evacuation Check-off Sheet 18
, FIGURES Figure 1 . -ls "> : tr Exclusion and Property Boundary 19 e
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IMPLEMENTING PROCEDURE gp1p_19 REVISION ONSITE EVACUATION O Page 3 of 20 1.0 OBJECTIVE 1.1 To provide guideline information pertinent to evacuation of onsite personnel including company, construction, contractors and visitors who are not engaged in emergency response activities.
2.0 REFERENCES
l 2.1 Implementing References 2.1.1 EPIP-02, "PVNGS Emergency Classification" { 2.1.2 EPIP-15, " Protective Action Recommendations" 2.1.3 EPIP-16, "Onsite Surveys and Sampling" ! .2.1.4 EPIP-20, " Personnel. Accountability" . ()
- 2.2 Developmental References i ss l 2.2.1 NUREG-0654 Rev.1, " Criteria for Preparation and
! Evaluation of Radiological Emergency Response Plans and l Preparedness in Support of Nuclear Power Plants" i 2.2.2 PVNGS Emergency Plan, Rev. 2 i j 2.2.3 Eechtel/PVNGS Pre-Evacuation Assembly Plan j 2.2.4 APS Construction Personnel Accountability and Assembly E Implementing Procedure t l 3.0 LIMITATIONS AND PRECAUTIONS i ( ' L.1 This procedure must be conducted in an orderly fashion to ! avoid personnel injury. l
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE pp7p_19 REVISION ONSITE EVACUATION O Page 4 of 20 4.0 DETAILED ?ROCEDURE 4.1 Personnel Indoctrination 4.1.1 In the event of an emergency at PVNGS, it may be desirable to minimize the number of nonessential personnel onsite. If the emergency involves a radiological release or the , potential for a release then evacuation of nonessential personnel is desirable, or may be required, to minimize
" exposure. The Emergency Coordinator will have the
- pen:ibility for maklug this decision.
4.1.2 This procedure is intended to apply to evacuations where persons may receive abnormal external exposure and/or persons or automobiles / buses may be contaminated. It assumes a major event has occurred at Unit 1 and Unit 2 ] and/or Unit 3 is under construction. In the event of an - emergency it may be desirable to send individuals home; cases of this nature'would be handled as an early (, . ' dismissal from work. An orderly sequence of dismissal ~ - should be gi'ven by the Emergency Coordinator and Security should provide traffic control in this event. 4.2 Prerequisites 4 4.2.1 The plant is in an emergency condition where the potential , or actual levels of a ms..iur radiological release is evident or a SITE or GENERAL- EMERGENCY has been declared. l Personnel accountability has been completed per EPIP-20. 4.2.2 Personnel under the direction of the Bechtel Field Construction Manager have assembled at their assigned locations per the "Bechtel/PVNGS Pre-Evacuation Assembly Plan" (Appendix A) and are awaiting further instructions. 4.2.3 Personnel under the direction of the APS Nuclear ! . Construction Manager have assembled at their assigned locations per "APS Construction Personnel Accountability and Assembly Implementing Procedure" (Appendix B) and are awaiting further instructions. 4.2.4 APS Nuclear Department Operations personnel are at their
. assigned emergency organization positions. All nonessential personnel are assembled at one of the following locations: .
PV2?6 0C04 48 8.1 -
PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE gprp_19 REVISION ONSITE EVACUATION O Page 5 of 20
- a. Operational Support Center / Access Control Point
- b. Service Building
- c. Administration Annex Building First Floor
- d. Water Reclamation Facility
- e. Visitors Center
- f. Security Firing Range I 4.2.5 j The Emergency Cooruinator has determined per EPIP-15 that -
the emergency situation waftants evacuation of
-nonessential personnel.
4.3 Instructions 4.3.1
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The Emergency Cocrdinator will determine the deployment of emergency response personnel within the Operational Support Center and the Service Building. It may be necessary to direct emergency response personnel in the OSC and Service Building to hardened facilities, i.e., the ( . Control Room, Technical , Support Ce,nter and Emergency j ~, Operations Facility based upon rad.iological conditions.' i 3
'*i ? 4.3.2 If the Emergency Coordinator determines that evacuation is warranted, the Security Director will monitor and supervise the evacuation process. .
4.3.3 The Security Director will:
- a. Assess emergency conditions with the Emergency Coordinator to determine the expediency needed in evacuation and, if radiological conditions warrant, the evacuation route in which to take.
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- b. Arrange with the Bus Transportation Supervisor to deploy buses to the assembly areas where required.
- c. Coordinate with the Bechtel' Field Construction Manager and the APS Nuclear Construction Manager for evacuation of their personnel and inform them if offsite reassembly will take place and where.
- d. Estimate on the number of vehicles and personnel involved in the evacuation and determine if any further personnel accountability is required at the site prior to the evacuation, i r
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PVNGS EMERGENCY PLAN Qcewas IMPLEMENTING PROCEDURE EPIP-19
-N REVISION ONSITE EVACUATION O Page 6 of'20
- e. Inform the Security Force of the evacuation and announce over the station Public Address System for nonessential personnel to evacuate, the evacuation route and if conditions warrant, evacuate to an offsite reassembly location (give location).
4.3.4 Nonessential personnel will evacuate the site in a safe and orderly fashion and will await return until further
- notification.
4.3.5 'The Security Director vill have Security Guards routinely check APS trailers and buildings outside the protected area to ensure all nonessential personnel have left the premises,
- a. If nonessential personnel are found on the premises identify the individual (s) and report their presence
, to the Security Director.
b.
, Instruct and ensure that.the personnel evacua't'e the premises if evacuation is/has taken place or have them
-) report to their designated assembly area..
. .s 4.3.6 Reassemble at an offsite area.
4.3.6.1 The Emergency Coordinator in conjunction v'ith the Radiologica] Protection Coordinator, will determine the evacuation route. If radiological conditions warrant reassembly of evacuating personnel, one offsite assembly area may be used (Palo Verde Inn in i . Tonopah). A suggested route to each is shown on l Figure 1. Ample water and space is available at each i j location to set up decontamination areas and parsonnel and equipment monitoring points.
- 4.3.6.2 The Security Director upon organizing transportation l
and receiving instruction from the Emergency l . Coordinator as to evacuation route will:
- a. Contact the Radiological Protection Coordinator and assure that qualified monitoring personnel are dispatched for monitoring at the offsite assembly area.
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- b. Appoint an Evacuation Team Leader for each major assembly area. Bechtel and APS Construction will l'
assist for areas under their control. PV216-0 COA 18,82) *
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PVNGS EMERGENCY PLAN pcewas IMPLEMENTING PROCEDURE EPIP-19 (" REVISION ONSITE EVACUATION O Page 7 of 20 4
- c. Send emergency supplies to offsite-assembly areas as required.
- d. Inform the Evacuation Team Leaders of the location of the offsite assembly area and the route to follow.
4.3.6.3 The Security Director will determine from the e i 1 Emergency Coordinator whether assistance will be required from the county and/or State, to clear the evacuation route and/or the offsite assembly area. He will notify the offsite assembly area in advance of the arrival of the evacuation group. 4.3.6.4 The Evacuation Team Leaders should instruct personnel evacuating to:
- a. Proceed in caravan fashion along the designated
, route-to the offsite ass'embly area.
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,-- b. Personnel without their own transportation should
(~~ either obtain a ride with a driver in their , assembly a.ea or ride the bus. 4.3.6.5 At the offsite assembly area, each assembly area Evacuation Team Leader will assure that personnel are monitored and cleared before release and individuals i names and social security numbers are recorded (on , Appendix C). 4.3.6.6 The names and addresses of evacuees suspected of having received a dose in excess of 250 mrem and those
.ree; iring any decontamination sball be obtained before the persons are allowed to leave the assembly area.
4.3.6.7 The Evacuation Team Leader shall keep the Security Director informed of the activities at the offsite assembly area. The results of the decontamination - effort will be reported to the Emergency Coordinator for his evaluation.- . 4
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PVNGS EMERGENCY PLAN PROCEDURE N O. IMPLEMENTING PROCEDURE
- gpip_19 ((f 5 REVISION ONSITE EVACUATION O Page 8 of 20 BECHTEL'S .
PVNGS PRE-EVACUATION ASSEMBLY PLAN Purpose Alert, assemble and account for all Bechtel employees of Bechtel
. Subcontractors, and Bechtel visitors in the event of an emergency at PVNCS, and prior to a site evacuation. -
Scope - This plan describes the methods and procedures necessacy to alert.. assemble and account for employees should an evacuation be necessary. General A safe and orderly process is necessary to assemble and account for personnel in preparation for an emergency that may require site evacuation. The locations for assembly are outlined in this plan. Accountability of personneU ' - at these assembly areas will be the responsibility of appointed supervisors. i These supervisors will report their findings to the Emergency Control Center
- either by phone or radio. Phone numbers are . .t _ . ,-radio FM Channel 3 (general use) UHF . EZ . Missing persons must be named. All personnel will remain in their appointed assembly areas until notification from the Emergency Control Center.
Search and rescue for unaccounted personnel within the protected area will be conducted by APS personnel. Outside the protected area, Bechtel will be responsible for accountability, search and rescue of Bechtel employees. Alerting l l Sirens will be used to alert personnel on the jobsite to procced to their appointed assembly areas. A continuous tone (2 minutes or longer if
, necessary) will signal the start of the assembly process. Sirens will be used to give the "all clear" signal which is three (3) short blasts from the siren. Flashing lights or horns will be installed in areas where the sirens are not audible. All vehicle traffic will stop during assembly.
EMERGENCY CONTROL CENTER (ECC) This center will coordinate all Bechtel site emergency operations excluding the protected area. The center is located at the Field Construction Managers office area. All accountability reporting from assembly areas will be directed to either the Project Superintendent or the Project Services - Superintendent, who will record and report to the Field Construction Manager. Pv21s M0a ts.32)
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1 1 PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDH A
- IMPLEMENTING PROCEDURE EPIP-19 Pace 2 of 5 REVISION ONSITE EVACUATION O Page 9 of 20 BECHTEL'S PVNGS PRE-EVACUATION ASSEMBLY PLAN (CONT'D)
The Project Superintendent or the Project Services Superintendent will assume the responsibilities of the FCM in his absence. Shift Superintendents will j assume the responsibilities of this plan on the off shifts. The ECC will then report personnel accountability status to the Security Director of the PVNGS Emergency Organization and will be relayed to the Bechtel ECC for action. A. Assembly Areas and Procedures
- 1. When the protected area (Unit 1) is established (a short period prior to fuel load), all personnel covered in the purpose and scope of this plan and working within the protected area will assemble as follows:
- a. Bechtel manual employees will clear the Unit I security gate.and report to their respective craft shacks'and await additional instruction. ,
, b. Bechtel non-manual gersonnel will clear the Unit l security gate
( ' l) and report to their discipline at the Unit 1 Field Office and
- await additional instruction.
- c. Bechtel subcontractor manuals and non-manuals will clear the Unit .
1 security gate and report to their respective offices or shacks and await additional instruction.
- d. All other personnel will report to their respective disciplines.
- e. Visitors will accompany their hosts.
- 2. Protected Area Procedures
- a. The alerting procedure will be confined to the protected area only and will not be audible to other areas of the jobsite.
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- b. The process of removing personnel from the protected area (Unit 1) is merely an alert and does not mean that a site emergency has been established. The alert for a site pre-evacuation assemble is outlined under " Alerting" in thi-s plan. -
- c. Personnel evacuated from the protected area (Unit 1) and assembled in their assigned areas, may then be subject to the site plan, and would proceed as the balance of this plan indicates.
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PVNGS EMERGENCY PLAN PROCEDURE NO' IMPLEMENTING PROCEDURE gpip_19 (39,^5 s,- REVISION ONSITE EVACUATION O Page 10 of 20 BECHTEL'S PVNGS PRE-EVACUATION ASSEMBLY PLAN (CONT'D)
- 3. Manual Employees All Bechtel and Bechtel Subcontractor manual employees will proceed to the parking lots by going through their regularly assigned badge alley. Employees must brass out and remain in the parking lots. The appointed supervisor will report " unaccounted badges" to the ECC by phone or' adio.
- 4. Non-Manual Employees
, a. Constryction Office Personnel Thest, persons will report to their discipline assembly areas located around the pe,rimeter of-the building (see map for location). The supervisor will report accountability to the ECC byJp' hone or~ radio. . s (i b. Personnel Assigned in the Field i These persons will assemble at their assigned discipline field office. The supervisor will report accountability to ECC by phone , or radio.
- c. Bechtel Subcon'.ractor Non-Manuals 1 These persons will assemble at the receiving dock area on the a north side of the main warehouse.' Members of the Bechtel l Subcontractor group will be present and will be responsible for an accountability report to the ECC by phone or radio. ,
- d. Procurement and Narehouse Personnel All procurement and warehouse personnel will assemble directly l north of the Procurement Office. The supervisor will report
, accountability to the ECC by phone or radio. i i
- e. Safety and First Aid Personnel -
l These persons will assemble at the Safety Office. The supervisor will report accountability to the ECC by phone or radio. I
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE APPENDIX A YPIP-19 Pace 4 of 5 REVISION ONSITE EVACUATION O Page 11 of 20 BECHTEL'S' PVNGS PRE-EVACUATION ASSEMBLY PLAN (CONT'D)
- f. Water Reclamation Personnel These persons will assemble at the WRF Field Office. The supervisor will report to the ECC by phone or radio. .
- g. Timekeeping Personnel All Timekeeping personnel will report to their assigned badge alley / timekeeping office. The supervisor will report accountability to the ECC by phone or radio. Timekeeping personnel will aid in manual personnel accountability,
- h. Visitors All visitors will be the responsibility of their hosts and must remain in their company. Supervisors will report all visitors in -
their assembly areas, by name, to the ECC, by phone or radio along
'L - with routine reports.
B. General Accountability Unit and Area Superintendents, Lead Engineers and Craft Supervisors will be assigned reporting duties to provide coverage at the assembly areas, etc. Their responsibilities will be to report accountability and provide general supervision and coordination of activities. Accountability reports to the ECC will be accomplished by Unit or Area Superintendents. C. Education and Training
- a. A pamphlet will be dispersed to all site personnel (including subcontractors) to inform them of the procedures established in i this plan.
- b. An explanation of this plan will be incorporated into the manual and non-manual new hire orientations.
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- c. The job-wide Safety Tool Box meetings will be used to present the plan to the jobsite. These meetings may be used to provide a refresher for the plan if needed,
- d. APS will train Bechtel employees who enter the protected area, concerning accountability response within the protected area.
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. ONSITE EVACUATION O Page 13 of 20 APS CONSTRUCTION PVNGS EMERGENCY PLAN PERSONNEL ACCOUNTABILITY AND ASSEMBLY IMPLEMENTING PROCEDURE a
SCOPE This procedure describes the immediate emergency personnel assembly and accountability actions to be taken by the following groups of onsite personnel: o APS Nuclear Construction Department employees APS Site Quality Assurance employees
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o l . i ) o APS Visitor's Certer employees o SRP Switchyard Construction employees . o Construction Security Cuards o Visitors, vendors, APS contractors, tour guests under the jurisdiction of the above groups. This procedure is based on the situation of a Unit 1 emergency while Unit 1 is operational and Units 2 and 3 are still in the construction stage. l l ACCOUNTABILITY l l 1. Employees of the Nuclear Construction and Site Quality Assurance Departments routinely log in and out of the Site Construction Office such that their whereabouts are known to the Nuclear Construction Manager or his designee at all times. The locations of visitors and contractor personnel who are the responsibility of these two groups are also' included - in the log. APS Visitor's Center employees and visitors are the
- responsiblity of the Visitor's Center Director or his alternate. He is accountable to the Nuclear Construction Manager for purposes of accountability when this procedure is in effect. SRP Switchyard construction employees are also , accountable to the Nuclear Construction
/ Manager and are logged in and out of the construction area.
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE APPEEIX s EPIP-19 Page 2 of 4 REVISION ONSITE EVACUATION O Page 14 of 20 Page 2
- 2. Employees and visitors who enter the Unit 1 controlled area or the Water Reclamation Plant becoce the responsibility of the Nuclear Operations Department and for purposes of this procedure, are considered visitors to that group.
- 3. Personnel located outside the chain-link construction feace are considered to be outside the owner-controlled area. Accountability is not required.
Nuclear Construction personnel outside this area but onsite will carry a portable radio, however, for direction in the event of a site evacuation.
- 4. Personnel such as SP Railroad employees who may not be escorted will be issued a card which advises them of actions required in the event of an emergency.
- 5. The Nuclear Construction Manager will appoint a designee to act for him during his absence and outside of normal day-shift hours.
IMMEDIATE ACTIONS
- 1. When Nuclear Construction, Site QA personnel end their visitors located in Unit 1 are directed to evacuate, they will do so either through the Security Building or the Security Trailer exit located at plant north of the Fuel Building,
- a. Personnel exiting via the Security Building will assemble at Area #2 (see Figure 1).
- b. Personnel exiting via the Security Trailer will proceed to Area #1 to assemble.
- 2. SRP and other personnel 1.ocated in the switchyard will assemble in Area #3.
I 3. Personnel located elsewhere within the chain-link fenced construction area vill assemble in Area #1, which is the APS Nuclear Construction Office. l . 4 Visiter's Center personnel will assemble at the Visitor's Center parking l lot, Area #4. Tour guests within the construction area vill be escorted by their host / guide out to Area #4
- 5. APS contractor personnel having site access badges will have received
- training in emergency procedures and will proceed to the appropriate area as though they were employees of Nuclear Construction.
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. IMPLEMENTING PROCEDURE eprp_19 (,3$f 4a 1 REVISION ONSITE EVACUATION O Page 15 of 20 Page 3 SUBSEQUENT ACTIONS
- 1. Personnel accountability measures are the responsibility of the Nuclear Construction Manager. It is the responsibility of each supervisor to know the general location of his personnel, visitors and contractors at all times. -
- 2. The Nuclear Construction Manager or his alternate will appoint a Nuclear Construction Department staff member for each assembly area to go to his area and identify the head count and personnel not accounted for by nace and last known location. The results will be forwarded to the Nuclear Construction Manager or his designee.
- 3. The status of personnel accountability will ba forwarded by the Nuclear
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Construction Manager to ,the Security Director or his alternate (located in the Security Building) for relay to the PVNGS Emergency Coordinator. 4 Unaccounted for personnel will then be subject to the action described in Emergency Plan Implementing Procedure No. 21.
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J. R. Mann
-February 12, 1982 e
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APPENDIX C IMPLEMENTING PROCEDURE EPIP-19 Pace 1 of 1 REVISION ONSITE EVACUATION O Page 17 of 20 i PERSONNEL MONITORING LIST Person ' Social Security Monitor 4 Monitored _ Number Reading Disposition a 'l i j
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PVNGS EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURE , sprp_19 $g!.Tf1 REVISION ONSITE EVACUATION O Page 18 of 20 EMERGENCY C00RDINATOR'S ONSITE EVACUATION CHECK-OFF SHEET Action Initials / Time
- 1. Personnel Assembly / Accountability has been completed /
(APS, APS Construction, Bechtel, Water Reclamation, o protected
- area) .
- 2. Security check to ensure all personnel have evacuated /
the Administration Building and trailers outside the '
, protected area.
- 3. SITE or GENERAL EMERGENCY has been declared or the /
situation, as de.termined by the Emergency Coordinator, warrants evacuation.
- 4. Arrange Eor bus , transportation offsite . ~
.for. '
/ -
,_, nonessential personnel.
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- 5. Inform the Bechtel's E: ergency Control Center's,, /
ff the evacuation and evacuation route if conditions warrant. .
- 6. Inform APS Nuclear Construction Office of the evacuation. /
- 7. Announce the evacuation of the Public Address System (if /
warranted, the evacuation route).
- 8. Activate the site siren for evacuation (2 minutes /
continuous tone).
- 9. If reassembly at an offsite location is necessary, /
i inform the offsite location and ensure that Emergency ! Kits are delivered. e o m s ocos <un ,
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PVNGS EMERGENCY PLAN PROCEDURE NO. FIGURE 1 IMPLEMENTING PROCEDURE EPIP-19 Page 2 of 2
/ ; REVISION ONSITE EVACUATION O Page 20 of 20 FIGURE 1 OFFSITE ASSEMBLY AREA Palo Verde Inn When exiting from the west side of the plant site, travel north on Wintersburg Road. Turn west on the Buckeye-Salome intersection. Follow the Buckeye-Salome Road to Tonopah, Arizona. Entrance to the Palo Verde Inn is located approximately 1/2 mile south of Interstate 10 at the south side of the Palo Verde Trailer Park.
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.a' PERSONNEL ASSEMBLY AND ACCOUNTABILI"Y 0 Page 1 of 21 1
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE ,m_,, n .
...j REVISION PERSONNEL ASSEMBLY AND ACCOUNTABILITY .
O Page 2 of 21 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 3 .
2.0 REFERENCES
3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDUPI 4 4.1 Personnel Indoctrination 4.2 4 i Prerequisites 4.3 Instructions
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,w APPENDICES Appendix A - Personnel Accountability Responsibility 10 Appendix B - Individual Accountability Sheet 11 l
l FIGURES i ' Figure 1 - Administration Anner Building Cafeteria Assembly Plan 12 i [ . . ATTACHMENTS Attachment I "Bechtel PVNGS Pre-Evacuation Plan" i 13 l Attachment II "APS Construction Personnel Accountability t and Assembly Implementing Procedure" 18
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE ,_., n REVISION j PERSONNEL ASSEMBLY AND ACCOUNTABILITY 0 Page 3 of 21 1.0 OBJECTIVE 1.1 To provide for personnel accountability within 30 minutes from the time the emergency accountability signal is activated (i.e., ALERT or higher classification).
- 1.2 To maintain personnel accountability for the duration of the t
emergency condition. '
2.0 REFERENCES
2.1 Implementing References 2.1.1 EPIP-02, "PVNGS Emergency Classification" 2.1.2 EPIP-04, " ALERT Implementing Actions" 2'.l.3 EPIP-05, " SITE EMERGENCY Implementing Actions" 2.1.4 EPIP-06, " GENERAL EMERGENCY Implementing Actions" 2.1.5 EPIP-19, "Onsite Evacuation" 2.1.6 EPIP-21, " Search and Rescue" 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. 2 2.2.3 Bechtel PVNGS Pre-Evacuation Plan 2.2.4 APS Construction Personnel Accountability and Assembly Implementing Procedure 3,0 LIMITATIONS AND PRECAUTIONS L1, This procedure must be implemented in an orderly fashion to avoid confusion and personnel injury.
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- PVNGS EMERGENCY PLAN PROCEDURE NO.
IMPLEMENTING PROCEDURE EPIP-20 REWSION (' ' ~ PERSONNEL ASSEMBLY AND ACCOUNTABILITY 0 Page 4 of 21 3.2 Instructions for plant security personnel assumes that the emergency is not security related. If a breach of security exists, the appropriate PVNGS Security Plan Implementing Procedures shall be implemented. 3.3 If during this procedure an assembly area outside the protected area appears likely to exceed 2 mR/hr, a site
- evacuation in accordance with EPIP-19, "Onsite Evacuation", .
will be initiated. 3.4 Personnel performing critical operations such as fire fighting, giving aid to injured, performing werx which could endanger the life or safety of personnel if left unattended, do not need to immediately report to their accountability area. However, they should do one of the following:
- a. Secure the operation to'a safe condition and then proceed to their accountability area.
- b. If the operation will take'more than five 'inu'tes m to
- secure, notify the Security Shift Captain at ext. 4444.
- c. s)
- 4.0 DETAILED tROCEDURE -
l 4.1 Personnel Indoctrination 4.1.1 In the event of an emergency situation at an operating unit, it is imperative that personnel onsite are notified of the situation, their whereabouts identified for safety 1 and security purposes, and that they respond in a coordinated effort to the emergency. l 4.1.2 An emergency accountability signal is provided to alert personnel within the protected area of the affected unit that an emergency exists. 4.1.2.1 The accountability signal will be broadcast over the affected unit's Emergency Public Address system. A l tone generator, activated from the C.ontrol Room, l allows for the selection of a preset emergency signal through the PA system. A verbal announcement may follow, providing specific instructions. ,
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??Ir-20 REVISION
*y PERSONNEL ASSEMBLY AND ACCOUNTABILITY 0 Page 5 of 21 4.1.2.2 If there are two or more units within the protected area, and the situation does not necessitate activation of the emergency siren, the Emergency Coordinator will notify the unaffected unit (s) to initiate the emergency accountability signal for that/those unit. This will ensure that personnel accountability, within the protected area, is achieved.
4.1.2.3 Flashing red lights have been p ovided in containment and other areas where background noise levels may preclude auditory perception of the PA system. 4.1.2.4 Actuation of the emergency PA system requires specific approval of the Shift Supervisor or the Emergency Coordinator. It will be activated for an ALERT or more severe classification. 4.1.3 If the emergency condition is such that the entire plant
- site should. initiate protective actions, the emergency A..
siren will be used. Activation of the siren will result in the assembly and accountability of all site personnel. (1 For an UNU'JUAL EVENT or ALERT, this siren may be sounded from any of the unit Control Rooms at the discretion of I the Shif t Supervisor or Emergency Coordinator; activation of the siren is mandatory for a SITE EMERGENCY or more severe classification. 4.1.3.1 When hearing the e=ergency siren each site employee, APS visitor, Bechtel Construction, contractors, APS Construction, and visitors will report to designated assembly areas. Each area will have an Assembly Area Supervisor, who shall notify the Security Shift Captain at ext. 4444 of personnel accountability results. t 4.2 Prerequisites l The Shift Supervisor or Emergency Coordinator d2clares an ALERT, SITE EMERGENCY or GENERAL EMERGENCY per EPIP-02, or Jetermines personnel accountability is desirable and activates the emergency accountability signal and/or emergency siren, l depending upon the scope of required response. 1 I 9 e A .- emsow, asm . _w - , m *% Y [*
l PVNGS EMERGENCY PLAN QcewRe l IMPLEMENTING PROCEDURE ,, , , _., n i p REVISION Q> PERSONNEL ASSEMBLY AND ACCOUNTABILITY 0 Page 6 of 21 4.3 Instructions 4.3.1 Upon activation of the accountability signal, plant security personnel shall respond as follows: 4.3.1.1 Those assigned to the Central Alarm Station (CAS), the Secondary Alarm Station (SAS), the perimeter posts, and other fixed posts shall remain at their assigned ~ areas and await further instructions. 4.3.1.2 Those on routine patrol within the protected area shall report to the Security Building via portable radio for accou ' __ icy and further instructions. 4.3.1.3 Those _ routine patrol outside the protected area sh .A call into the Security Building for instructions. 4.3.2 Upon activation of the accountability signal, other - personnel within the . protected area shall respond as follows: - k[,' 4.3.2.1 Personnel assigned emergency organization positions at
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the Control Room, Satellite Technical Support Center, Operational Support Center, Technical Support Center,- Service Building, or Emergency Operations Facility will report to their respective emergency locations. 4.3.2.2 Personnel within the radiation control area shall proceed through access control in a normal manner and report to the Operational Support Center Coordinator for accountability and further instructions. 4.3.2.3 APS personnel and visitors within the protected area . and not engaged in emergency recovery actions (i.e., 4 non- essential personnel) shall proceed to the nearest security exit, " badge out", and proceed to the Administration Annex Building First Floor. i Figure 1 is a diagram of the Administration Annex ; Building First Floor showing designated assembly areas. l 1 4.3.2.4 Bechtel and APS Construction, contractors, and '
, visitors within the protected area, will proceed to the security exit and proceed to assigned locations
, per Attachments 1 and 2 of this procedure.
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE EPIP-20 C. REVISION Q') PERS9NNEL ASSEMELY AND ACCOUNTABILITY 0 Page 7 of 21 4.3.3 Upon activation of the emergency siren, plant security personnel shall respond as follows: 4.3.3.1 Those assigned to the CAS, SAS, perimeter posts and other fixed posts shall remain at their assigned areas and await further instructions. 4.3.3.2 Other security force personnel shall report to the ~ Security BuildEng via portable radio for accountability and further instructions. 4.3.3.3 Personnel at the Security Firing Range will be contacted by the Security Shif t Captain, informed of the situation, and provided instructions as necessary. 4.3.4 Upon activation of the emergency siren, personnel identified in Section 4.3.2 shall respond in the same manner as for "act$vation of the accountability signal".
' Personnel outside the protected area shall respond as , ,
follows: eTS.
'ia? 4.3.4.1 Nuclear Operations personnel including contractors and visitors, outside the protected area and near one of j the following facilities shall report to: -
(1) Visitor's Information Center Auditorium (8:00 a.m.
.to 4:30 p.m., 7 days a week)
(2) Water Reclamation Facility (3) First Floor, Administration Annex Building whichever is closest. - l 4.3.4.2 Nuclear Operations nonessential personnel located outside the protected area will report to the Administration Anner Building First Floor. - 4.3.4.3 Bechtel and APS Construction, contactors, and visitors will proceed to their assigned locations per Attachments 1 and 2. t
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PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE EPIP-20
. 3 REVISION
;' PERSONNEL ASSEMBLY AND ACCOUNTABILITY 0 Page 8 of 21 4.3.5 ' Personnel accountability within the protected area will be accomplished as follows:
4.3.5.1 Each assembly area has an Assembly Area Supervisor responsible for determining personnel accountability within that area (see' Appendix A). 4.3.5.2 The Security Director will obtain a copy of the . computer printout of personnel who were in the protected area when the emergency (ALERT or more severe) was declared. 4.3.5.3 The Assembly Area Supervisor (AAS) in the Control Room (s), TSC, OSC(s) Main Access Control Point (s), Services Building, and EOF obtains the names and badge numbers of individuals who have reported to the area by completing the Individual Accountability Sheet . (Appendix B). The AAS then advises the Security S.C.
.at ext., of the personnel and their baQge numbers that are accounted for.. -
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, 4.3.5.4 If individuals are not accounted for, the Security S.C. has those individuals' names announced over the unit's intercom syste_m, requesting a response. If there is a response, that individual will be told to j
report to one of the accountability areas. If there is no response, a Search and Rescue Team will be
, assembled per EPIP-21, " Search and Rescue".
4.3.5.5 From these reports the Security S.C. will inform the Security Director who will determine overall accountability within the protected area and report it to the Emergency Coordinator within 30 minutes after the emergency was declared. ' 4.3.6 Personnel accountability outside the protected area will be accomplished as follows: 4.3.6.1 The AAS at the Administration Annex Building,
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