ML20092F916
| ML20092F916 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/01/1989 |
| From: | Fitzwater L GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092F288 | List:
|
| References | |
| CON-IIT05-002-132A-90, CON-IIT5-2-132A-90, RTR-NUREG-1410 LO-LP-40101-11, NUDOCS 9202190556 | |
| Download: ML20092F916 (54) | |
Text
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GEORGIA POWER POWER GENERATION DEPARTMENT V0GTLE ELECTRIT ORNERATING PLANT b
TRA!NING !.ESSON PLAN
~
TITLE:
EP!P OVERVIEW FUMBER:
Lo-LP-40101-11-c PROGRAM LICENSED OPEDATOR TRAIN 1hD REVISION:
11 sME:
L. MY 10/20[09 DATE:
h,h%--
A
/ d ///87 INSTRUCTOR GUIDELI.fE5s I.
LESGON FORMAT A.
Lecture with Visual Aids II.
MATERIALS NEEDED A.
White Board with Markers 8.
Overhead Projector C.
Transparencies III.
EVALUATION i
A.
Written or oral Exam in conjunction with other Lenson Plans IV.
REMARKS A.
Training in Emergency Plan is a requirement per IEN 84.042 and Procedure 6f)602-C. Responsibilities and care darange assessment for SRO's is sequired per 60601-C.
Sec 4.1.3.3.o(2) Rev 2 3.
Performanen-based inst ructional units (IUs) are attached to the lesson plan as student handouts. After the lecture en EPII-a, the student should ce given mdequate self-study time for the IUs.
The instructor should direct self-study activities and be c.vailable to answer questions that may arine concetning the ?U material. After-self-study, the student will perform, simulate, observe, or d.'acons tas identifind on the civ. ster signoff criteria-1ist) the task covered in the instrue.tianal uult in the prerence of an evaluator.
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LO-LP-40101-11-C Licenned operator objectivet for this lesson plan can be found in the Licensed Operator System Master Plan Section 2.3 (Qualift.ation Jignoff criteria)
P.ev 4 Cluster 40 SRO EMERGENCIES
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LO-LP-40101-11-c INTENTIONALLY LEFT BLANK-i i
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LO-LP-40101-11-C 4
REFERENCESt tegneMy -
1.
PLANT VuOTLE IROCEDURES:
91001-C, EMERGENCY CLAGSITICATION AND IMPLEMENTING INSTRUCTIONS 91002-C, EMFRGENCY NOTIFILATIONS 91101-C, EMERGEhCY RESPONSE ORGAN!!ATION
's 1102-C, DUTIES OF THE EMERGENCY JIRECTOR 91201-C, ACTIVATION AND OPERATION 07 THP-TECHNICAL SUPPORT CENTER 91202-C, ACTtVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTUR 91203-C, ACTIVATION AND OPERATION OF 1HE EH.7RGENCY OPERATION FACILITY 3
91204-C, EMERGENCY RESPONSE COMMUNICATIONS 91301-C, EMERGENCY EXPOSURE FUIDELINES 91304-C, COMPUTERIZED AND MANUAL BACKUP METHOUS FOR RELEASE RATE AND DOSE CALCULATIONS 91305-C, PROTECTIVE ACTIOS' GUIDELI!45 91401-C, ASSEMBLY AND ACCOUNTABILITY P?402-C, SEARCH AND RESCUE 91403-C, SI'tt EVACUATION 91501-C, RECOVERY 91502-C, CORE DA;1 AGE ASSE.10 MENT 91503-0, CONTROL AOOM INSTRUMENTATION OUTPUT FOR ASSESSMENT OF CORE DAMAGE 2.
COMMITMENTS APID OTHER REQUIPEMENTS:
IEN 84.042 FF 89.007 FEECBACK FR0st E DRILL FF 89.000 Yut0BAL7 FPOH E DRILL 3.
STUDENT HANDOUTS LO-HO-40101-001 4.
TRANSPARENCIES:
LO-TP-40101-001 FOUR EMERGENCY CLASSES LO-TP-40101-UO2 NOTIFICATION OF UNUSUAL EVENT LO-TP-40101-003 ALERT LO-TP-40101-00A SITE AREA EMERGENCl LO-TP-40101-005 GENERAL EMERGENCY LO-TP-40101-006 EMERGENCY RESPONSE ORGANIZATION LO-TP-40101-007 ON-SHIFT EMERGENCY RESPOMSE ORGANIZATION LO-TP-40101-000 ACTIVATION OF EMERGENCY RESPONSE ORGANIEATION LO-TP-40101-009 TSC MANAGER LO-TP-40101-010 OSC MANAGER LO+TP-40101-011 EOF MANAGER LO-TP-40101-012 ALERT SITE BOUNDARY RADIATION LEVELS LO-T?-40101-013 SITE AREA BOUNDARY RADIATION LEVELE LO-TP-40101-014 GENERAL EMEPGENCY SITE BOUNDARY RADIATION LEVELS 4
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LO-LP-40101-11-C
REFERENCES:
LO-TP-40101-015 CSF's MONITORED TO DETERMINE FISSION PRODUCT BARRIER BREACH LO-TP-40101-016 CSF's MONITORED TO DETERMINE FISSION PRODUCT BARRIER STATUS LO-TP-40101-017 EMERGENCY EXPOSURE LIMITS f,0-TP-40101-018 OASITE PROTECTIVE ACTIONS LO-TP-40101-019 OFFSITE PROTECTIVE ACTIONS LO-TP-40101-020 RECOVERY OROANIZATION LO-TP-40101-021 FUEL DAMAGE VERSUS ELEVATED FUEL ROD TEMPERATUPES LO-TP-40101-022 EMERGENCt' CLASS DETERMINATION SCENARIO #1 L3-TP-40101-023 EMERGENCY CLASS DETERMINATION SCENARIO #2 LO-TP-40101-024 EMERGENCY CLASS DETERMINATION SCENARIO #3 LO-TP-40101-02S EMPRCENCY CLASS DETERMINATION SCENARIO #4 5.
INSTP.UCTIONAL UNITS LO-tU-40101-001 MAKE EMERGENCY CLASSIFICATION LC-IU-40101-002 MAFE EMERGENCY NOTIFICATION LO-IU-40101-003 PERVORM MANUAL OFF.91TE DOSE CALCULATIONS LO-IU-40101-004 IMPLEMENT EMERGENCY PROTECTIVE ACTIONS AND RECOMMENDATIONS LO-IU-40101-005 IMPLEMENT SITE EVACUATIONS LO-IU-40101-006 TMPLEMENT RECOVERY ACTIONS LO-IU+40101-007 ASSEMBT E AND DISPATCH FIRE BRIGADE 6
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a LO-LP-4010,1-11-C III.
LESSON OUTLINE:
NOTES 1.
INTRODUCT10N A.
This lesson will provide the student with an indoctrination into EPIP's, with particular emphasis on EP1P's that the licensed operator is responsible for or directly interfaceo with in the event of an emergency.
B.
Present Lesson Objectives 11.
PRESENTATION A.
Overview Starta IEN 84.042 1.
These are four claselfications of emergencies objective 2 In order of severity (least to worat) they ares a.
Notification of Unusual Event (NUE)
LO-TP-40101-001 b.
Alert c.
Gite Area Emergency d.
General Emergency 2.
Summary of Classes a.
Notification of Unusual Event Handout #1 Page 2 Events which indicate a potential LO-TP-40101-002 degradation of the level of safety of the plant.
b.
Alert Events which involve an actual or LO-TP.40101-003 potential substantial degradation of the level of safety of the plant.
c.
Site Area Emergency Kvents which involve actual or likely LO-TP-40101-004 major failures of plant functions needed for protection of the public d.
General Emergency Events which involve actual or Lmminent LO-TP-40101-005 substantial core degradation or molting with the potential for loss of 6
9
a LO+LP-40101-11-c 111. LESSON OUTl1NE:
NOTES Containment integrity.
An evacuation of of f-site personnel is implemented for this emergency.
3.
The Emergency Plan Implementing Procedure (EPIP'e) are a group of procedures that implement each aspect of the emJrgeecy from initiation to recovery from the emergency 4.
The Emergency Plan is an agreement between GPC, state, local, and federal officiale and specifies the actions of each in the event of an emergency.
The EPIP's implement GPC's responsibility with respect to the Emergency Plan.
5.
The Emerconey Director (ED) has the overall objective 1 authority and responsibility for the The OSOS initially implementation of the EPIP's.
fille the position of ED if the General Manager is not on-site When using EPIP's, cross through or cross FP-89.007 a.
out steps in checklist as they are completed 6.
The Key EPIP's are Objective 3 a.
Duties of'tha Fmergency Director Handout #1 Pages 3 (91102-C) - provides instructions tu and 4 the FD in fulfilling his responsibility for overall coordinauton and direction of the FAiergency Response Organiaation Eme'rgency classification (91001-C) b.
ED responsibility providas instructions for the classifica-tion of off-normal events into one of four emergency classification levete.
It also provides initial implementing instructions to the ED Emergency Notification (91002-C) c.
ED makes Emerg.
provides instructions to complate Motification initial and follow up nottfication to CPC cn-site and off-site emergency response personnel and to Georgia, South Carolina, local counties, and NRC officials, d.
Site Evacuation (91403-C)
ED determines need provides instructions for the early for evacuation and dismissal or evacuation of non-essential orders evacuation.
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e LO-LP-40101-11-C
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LESSON OUTLINE:
EOTES personnel from the plant site in the ev1nt of an emergency Assembly and Accountability (91401-C) e.
KD orders assembly provides instructions for the assembly and accountability of non-essential personnel to their designated assembly area and the Assembly area is accounting of personnel to identify the Admin. Bidg.
those who may be missing for VEOP personnel-
- 1) ops-personnel should badge into con-FF 89.000 trol room or <;all control-rcom on al+vt er higher classification
- 2) Personnel receiving call-in should ask for badge number (not ACAD(
f.
P.t otective Action Guidelines (91305-C)
ED implements on-
- provides instructions for the on-site and site Prot. Actions-off-site protective actions alternativos to and reco m tD.(iA ensure plant and off-site personnel safety off-site Prot.
in the event of an emergency Act. Prot. Actions on-eite Early Dismissal site W aeuation Off-site Seek Shelter Evacuation g.
Recovery (91501-C)
ED.datermines provides instructions for determining recovery criteria when the emergency condition will be and mobilizes the terminated and the recovery phase Recoverty initiated.
It also doucribes the process organization used to notify and activate the recovery organisation for imreediate and long term recovery operations, h.
Core Daanage Assessment (91502-C) -.
Chemistry is provides a method to classify red estinate responsible-for the extent of core damage through core assessment.
fissiota product release measurements, operation in part, s
reactor vessel level indications, and providen data to core exit thermocouple temperatures chemistry per along with other auxiliary readings 91503-C,;" Control Instrumentation Data Record for 7.
Emergency Response Organization (ERO)
Core Damage 1
Assessment".
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4.
The Emergency Response Organir.ption la activated by the ED.
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LO-LP-40101-11-C III.
LESSON OUTLINE:
NOTES b.
The Emergency Response Organization is made up of 4 groups.
Each group has defined (by the EPIP's) c.
responsibilities d.
The 4 groups are LO-TP-40101-006 1,
The Technical Support Center (TSC)
Group 2)
Tt.e Emergency Off-site Facility (EO?) Group
- 3) The Operations Support Center (OSC) Group n
4)
The Control Room e.
On back nhifts and for the time frame LO-TP-40101-007 that it takes to 4.ctivate the ERO the On Shift Emergenej Reeponse Organization (OSERO) La activated (members shown data) f.
The Activation of the ERO's for emergency LO-TP-40101-008 classes is:
- 1) Notification of Unusual Event - OSERO
Site area and Ooneral Emergency -
Ecr is activated initially OSERO:
then TSC, EOF, OSC, for Site and Control Room General Emergencies q.
For both the ERO and the OSERO, the ED has functional authority over all the groups 5.
The EU when the OSERO is in effect is the OSOS L.
The BD for the ERO is the Senior VP g
Huclear Operations or the Genera; Hanager
- j. Each ERO group is headed by a Managst 8.
Technical Support Conter Group i
a.
The ED activates the TSC Objective 49 n
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Lo-LP-40101-11-C 111.
LESEN CUTLINg NOTf3 j
b.
The TEC Manager heads the TSC group LO-TP-40101-009
- 1) Primary - Plant Manager
- 2) Alternates - General Manager, Manager oporations, operation 4 Superintendentu c.
The TSC is a located adjacent to the control room and is equipped with it.atrumentation that allows monitoring of many plant parameters d.
The TSC group is made up of plant i
supervisors and plant staff The tunctions of the TSC group are Handout #1 Page $
o.
objective 4
- 1) Provide in plant radiological HP Supervisor assesoment and protective actions roccaroendations
- 2) Engineering and technical analysis for Enginaaring Supv.
control taom support
- 4) Coordination of emergency maintenance Maincenance supv.
i
- 5) Direction of post acet & t and plant Chetnistry supv.
l chemistry sampling and analyhte, evaluation of chemistry data, core damage assessment
- 6) ~ Planning and implementation of Logistical support TSC Support Coord.
3 (Docuttent Control)
Supv.
(Nuclear Shift
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Supv)
- 8) The TSC upper limit of habit. ability is objective 50 1
?
a)
Whole body dose 100 mr/h'in TSC b) 1.odine activity 2.1 E-07 uci/cc in TSC
- 9) The TSC Hanager relocates to the backup location of the Control room 9.
Operations Support Center
- 0 9
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LO-LP-40101-11-t' III.
LESSON OLITLINE:
NOTES s.
The ED orders activation of the OSC objective 49 b.
The OSC is located on the second floor of the Maintenance Duilding c.
The Ohc Hanager is the Maint. Manager.
The LO-TP-40101-010 Alternates are the Maint. Supervisor (2),
Superintendent (s) d.
The OSC serves mainly as a staging area for the deployment of Rad lologscal Emergency Teams (RET's) e.
The functions of she OSC are:
Objective 4 Ha.adout #1, Page 6 1)
Serve as the assembly and staging area for personnel pooled for emergency response 2)
Roopond to request from the ED and the TSC concerning deployment of RET's
- 3) Nat.0gement of emergency equipnent and supplies
- 4) Coordination of movement of personnel on-site f.
Function of RET's Objective $
Handout #1, Page 7 1)
Search and Rescue Team - performs Por 91402, emergency search and rescue of
" Search and individuals that are unaccounted for Rescue" or disabled 2)
First Aid Team - performs first aid Per 91306 for radiological and non-radiological "Conteminated injuries and personnel decontanination Injury" as required 3)
Damage Assessment / control Team - a Per 91306 selected group of personnel who
" Contamination perform damage assessment and Monitoring and control activities as needed Decontamination" 4)
Repair and Modification Team - a for 91306 selected group of personnel who
" contamination perform repair work and modify Honitoring and systems, equipment, etc., at Decontamination" needed b
5)
In Plant Monitoring Team - performa Per 91302-C 11 4
o LO-LP-40101-11-C III.
LESSON OUTLINE:
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NOTES in plant onmpling and surveys.
The "In Plant Sarnpling HP Supv. uses this information when and Surveys" Protectivo Action recommandations.to the ED
- 6) Dack-Up Fire Brigat e - Back up mupport i
to the normal shift fira brigade g.
The OSC upper limit of habitability is Objectiw 50 1)
Whole Body dose rato of 100 mr/hr in OSC 2)
Iodine activity of 2.7 E-07 oci/cc in OSC h.
The OSC Manager then rakes the decision to relocate
+,o the backup location of '.:he TSc 10.
Emergency operations facility Group a.
The ED orders activation of the EOF Objective 49 b.
The primary EOF is located at the VEGP Training Center The EOF Hanager le the Outage and Planning LO TP-40101-011 c.
Hanager with Plant Training and l'mergency C;li,Y Activated on Preparedness Manager, Health Physics a Site and General superintan.ient backupo Emerg.
d.
The ECF serves mainly as the liaison and coordinator between GPC and of f-site authorities The functions of the EOF group are Objective 4 o.
- 1) Direction and control of CPC Handour. #1, Page 8 Per " Duties of COF off-site emergency response Manager"
- 3) Communication of radiological infor-EOF Hanager mation to state and local emergency response agencies 4)
Support of initial activaties Eor Manager associated with planning for re-entry or recovery operation 12 l
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o LO-LP 40101-11-C I!!.
LESSON OUTLINES NOTES
- 5) Access control for EOF 6)
Processing of personnel who requite 20T Security authorization to enter site coordination
- 7) Requesting assistance from local law security 3
autitorities coordinator
- 8) Performance of off-site dose calcula-Dose Assessment cien Manager
- 9) Direction of Field Monitoring Teams Dose Ass. Manager Via Hon. Team Coordinator
- 10) Coordination with state and Federal Does Ass._ Manager Groups. performing radiological assessment
- 11) Development of protective action Dose Ass. Manager recommendations 125 Assumption of logistics support Eor Support functions from the TSC Coordinator
- 13) Pecviding press releases when Public Information authorized by the ED Mar.ager f.
Thw EOF upper limit of habitablity is Objective 50 1) 100 mr/hr wholn body 2)
Iodine a:tivity 2.7 E-07 uCi/cc g.
When inhabi*.able, the EOF manager will relocate the EOF to the bach up location at the CPC district office in Waynesboro 11.
Recovery Organization objective 4 a.
Recovery organization staff shall be responsible fors
- 1) Assuming assigned potitions and ensuring that support st-aff are available asid properly briefed
- 2) Ensuring that relict personnel are fully briefed prior to relinquishing their responstbilitter 12.
Health Physics Group objective 4 l
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LO-LP-40101-11-C
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LESSON OUTLINg NOTES a.
The HP Group provides the following key functions during an emergency:
1)
Performs off-site dose calculations 2)
Discusses on-site and in plant radiological conditions 3)
Provides on-site and off-site radiation protection measures 13.
Chemistry Group objective 4 a.
The chemistry Group provides t:
s following key function during an emergency
- 1) Assess cora damage from accident operatione provides data to chemistry 2)
Evaluates in plant chemistry analysis for damage assessment
- 3) operates Pass B.
Duties of the Emergency Director (9110?-c) 1.
The ED position is normally filled by the objective 7 Vice President, Nucisar or the General Manegar, Nuclear Plant.
The first alternate is the Assistant General Manager Plant Operations.
The second alternate is the Assistant General Manager Plant Support. The third alternate is the Manager, Operations 2.
The OSos wili initially fill the position Objective 6 if neither of the primeries are on-site 3.
The Emergency Director has the following objective 8 responsibilities which cannot be delegated Handout #1, Page 9 a.
Classifying and declaring the EPIP " Emergency emergency, including upgrading, down-classification and grading, or termination Implementing In-structions" 91305-C b.
Recommending protective actions to "Protectiv9 Action off-site authorities and content of Guidelines" messages 9130$-c c.
Deciding to evacuate'non-ensential
" site Evacuation" personnel from the site at the Alert 91403-c 14 I
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_.. _ _ _... _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _. _ _.. _ - _ _ _. _ ~.. _ _ _._... _. _ _
-e LO"LP-40101-11-C III._ LESSON OUTLINE:
NOTES classification level i
'd. Authorizing personnel radiation exposures
" Emergency in excess of 10CFR20 limits, if necessary Exposure" i
i e.
Deciding to request assistance from
)
federal support groups f.
Dwe! ding to notify off-site
" Emergency
_i authorities responsible for emergency Notif icat toris" t
measures 91002-C 4.
Other ED responsibilities ares a..
Maintaining communications with off-site
" Emergency-authorities regarding all aspects of nesponse emergency response-Communicationsa 91204-C i
b.
Provide overall direction for management of procurement of site-needed materials, equipment, and supplies, docunentation, accountability, and_ security function c.
Direct the notification and activation Activation of Tsc, of the emergency organization; including toF, osc 91201, amergency response facility activotion 202, _ 203-C d.
Coordinating and directing VEGP emergency operations Modifying EPIP's and adjusting Emergency Obje?tive 9 a.
9esponse organization staffing, as needed.
The ED is the only individual authorized to approve modifications to-EPIPs f.
Coordinating NRC activities to reduce duplication of effort and reduce the impact on plant staff during the weergency_
situation 1
9 The 0808 when acting as the ID shall The primary ED is l
either be in the_ control room or the TSC=
normally in the TSC-(Alwrt) or EOF (Site or General)
- h. 'For any emergency classification of, alert or higher, the OSOS must.be relieved by the primary ED as soon as possible C.
Emergency Classification (91001-C)
P a
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- _. _. ~. _. _ _
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LO-LP-40101-11-C III.
LESSON OUTLINE
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NOTES I
i 1.
The osos is reopensible for the initial clac.iification of an emergency and filling the position of ED until relieved a.
Mark through or cross cut steps in checP.-
FF 89.007 lists as they are completed 2.
When classifying an emergency, the following objective 12 categories are considered as the criteria Handout #1, for classification Fage 10 a.
Plant Power b.
Technical Specifications c4 Radioactivity d.
Plant Systems Status e.
Natural Phenomenon t
f.
Man-Made Haaards g.
Security I
h.
Fission Product Barriers 1.
Shutdown Systems j.
Other - a category or emergency not Damage to spent specifically in which a condition Fuel in threaten the safety of the plant or containment or public spent fuel area 1
3.
Emergency classification objective 12
(
Handout #1, Page 11 a.
Notification of Unusual Event classifications
- 1) Plant Power i
a) Loss of on-site pI off-site A.C.
j power r
i
- 2) Technical Specifications 1
l a)
Loss of ESF, PERMS monitor or Effluent Air Flow Inst. requiring Plant shutdown per Tech Specs I
b)
Exceeding RCS leak rates per 16
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e 10-LP-40101-11-c III.
LESSON oui 51Nga NOTES Tech speco c) Exceeding RCs activity per Technical Specifications d) Any Tech Spec. safety limit violation 3)
Radioactivity a) Trannportation off-site of a i
contaminated injured victLa b
b) Crose fallod fuel monitor exceeds 2E+4 epm above normal or confirmed > Tech Spec by lab analysis c) Radioactive effluent exceeds Toch Liquid and gaseous Specs limits au specified in the Off-site Dose calculation Manuti (ODCM)
- 4) Plsnt Systems a)
Rapid depenesurization of the secondary system I
b) Turbine rotating component failure causing rapid plant shutdown c) ECCS discharge to reactor vassal An;r SI d)
Reactor protection actuation withcut suberiticality e)
Failuru of a safety or relief valve to racione in a safety reluted system 5)
Natural Phenomenon a) Any earthquake felt or duf acted -
on-nite b) Tornado or hurricane on-site c) lire in the plant lasting longer than 10 minuten l
- 6) Han-made Hazards l
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LO-LP-40103-11-C III.
LESAON OUILINZ NOTES a) Aircraft crash on-site b) Train derailment on-site c) on-site explosion I
d) On-site toxic gas release
'/ ) Security a) Unusual aircraft activity overhead b) Security threat or attempted sabotage 8)
Fission Product Durrier a) Not considered for this classif j cation 9)
Shutdown Systems a)
Not costsidered for this classification
- 10) other a)
Loss of all meteorological data b) Loss of both site telephone L d l
ENN switches l
b.
Alert 1)
Plant Power a)
Loos of all off-site and on-risa l
A.C.
power l
b)
Loss of all vital D.C. power
- 2) Technical Specifications l
l a) Not considered for this classification
- 3) Radioactivity LO-TP-40101-012 a)
Site boundary dose rats greater than.5 neem /hr whole body or 1.5 mrem /h thyroid 10 4
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LO-LP-40101-11-C III.
LESSON OUTLINE:
~
NOTES b) Radiation level or airborno con-An incroace of tar.ination which indicates degrada-1000 cimes normal tion in the control cf radioactive material
- 4) Plant Systems a) Turbine failure causing casing pen-etration and damage to safety systems b) Evacuation of control room antici-pated or required with control of shutdown system established from shutdown panels
- 3) Natural Phenomenon a)
Earthqu?.ke greater than.12 g.
b)
Suatained hurricane winds sustained greater than 90 mph c) Tornado striking plant structure or the protected area l
- 6) Man-Made Hazards a) Aircraft crash or missile impact inside the protected area b)
Explosion damage affecting safety l
system l
c)
Uncontrolled toxic or flammable gaeva entering the pentacted area 7)
Security l
a) Ongoing security comprisw which l
reselts in intruders within the Protected Area B)
Fission Pa*oduct Barrier Examples clad damage as determined from a) Breach or challenge of I of 3 CFMS fission product barriers 9)
Shutdown Systems Example: Loss of all RHR 19 b
s LO-LP-40101-11-C III.
LESSON O'JTLINE:
~
NOTES g
a) Complete loss of any function which roe'.lta in insbility to maintain cold shutdown
Precautionary Ectivation of the TSC as a precaution, Emer.
clanotfication Site Area Emergency c.
must be an Alert i
- 1) Plant Power a)
Loss of all Off-aite aqd all on-site AC power for more than 15 minutas b) Lone of all vital DC power for more than 15 minutes g
- 2) Technical Specificationo a) None considered for tnia classification
- 3) Dadioactivity a)
Site boundary dces rates Projected LO-TP-40101-013 or measured greater than 50 mrem /h whole body b) Creater thr.n 250 mram/h thyroid
- 4) Plant Systems a) Evacuition of the control room and control of abutdown systsms not established from uhutdown panelo in 15 minates
- 5) Natural Phenomenon
)
a)
Plant not in cold shutdown and earthquake greater than.2g 2I custained winds greater than 100 mph.
b) Fire tesulting in the loss or ehenostve degradation of cny aafety-related function
- 6) Min-Made Hazards 9
)
- o e
J.-LP-40101-11-C
~
III.
LESSON OUfLillEt
~ f IC I a) F1&nt not in cold shutdown anda (1) Aircraft crash affecting vital structures by Lmpact or fire (2) Severe damage to safe shutdown equipment from missiles or explosion (3) Uncontrolled flammable gaseo entering t!.e vital areas (4) Uncontrolled toxic gases in the vital area restricting access causing a safety problem
- 7) security
&\\
ongeing security compromise which results in intruders in the vital area 8)
Fission Product barrier a) Brtach or challenge of 2 of 3 Clad and RCS fission product barriers piping b)
Known LOCA greater than makeup capacity 10)
Shutdown Systems a)
Complete loss of any function which results in inability to meintain hot shutdown
- 11) Othet a)
Major damage to spent fuel in the contairment or fuel handling building d.
General Emergency
- 2. ) Plant Power a)
None considered for this classificatien 2)
Technical Specifications 6
a) tione considered for_ this q
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LO-LP-40iO1-11"c III.
LESSON OUTLINRt NOTES J
classification 3)
Radine.;* ivity LO-TP-40102-014 a)
Sito boundary pro 412ted or actual dose rate greater than 1 ram /h whole body 2I 5 rem /h thyroid
- 4) Plant Systems a) Loss of physical control of the plant
- 5) Natural Phenomenon a) None considered for this clanoitication
- 6) Man-Mado Hazards a) None considered for this classification
- 7) Security a)
Lono of physical control of plant j,
- 8) rianion Product barrior a) areach or challenge of 3 of 3 Clad, RCS and fission product barriers Ctet.
- 9) Shutdown Systems a)
None considered for this classification 9
- 10) Other a) None considered for this classification D.
Use of Figures and Data Sheets in EPIP 91001-C 1.
Data Sheet 1 is used to document classification determination 2.
Fission product barrier status le first Objective 11 determined by the operators The barriera ares 22 W
e
>A_u A~m.
i.
t LO-LP-40101-11-C III$ LSSSON OYTLINE:
~~~
~~
~
NOTES j
ruel pellet matrix and cladding a.
b.
RCS pressure boundary c.
Containment system 1
I 3.
One way the operator can determino breach LO-TP-40101-015 or challengs to the barriers is by Objective 11 l
monitoring the plante Critical Safety Functions (OSF's) via the SPDS/ERP computer or i
19200-C.
The CSF's ares a.
Reactivity (subcriticality) b.
Core Cooling c.
Heat sink d.
RCS Integrity e.
Containment Integrity 4.
To determine fission product barrier statuan Fuel / cladding Integrity - 6 rad or orange LO-TP-40101-016 a.
terminus from reactivity, or core cooling objectivo 10/11 I
indicates a broach.
A red terminus froe heat sink indicates a breach b.
RCS - a red or orange terminus from core l
cooling or RCS integrity indicates a l
breach l
l c.
Containmer.t integrity - a red or crongs tarminue from containment integrity indicatua a breach 5.
After the fissica product batrier status in determined, rigure 4 from 91001-C is used to determine the emergency classification and if other factore should be considered in the classification 6.
A checklist for each classification exist in 91001-C that guides the 3D in his initial actions and notifications 7
An emergency is downgraded as follows:-
Objective 14 l
a.
The ED determines that conditions are favorable for downgr.eding an emergency 23 I
e
+
r
4
(.
LO-LP-40101-11-C III.
LESh0F OUTLINE:
~ ~ ~
NOTES
?
-~
b.
Notification will be made to t9 ate, local and fedoral officials notifying them that the emergency has been downgraded Complete all actions that are necesaary c.
for that emergency classification E.
Emergency Notifications (91002) 1.
This procedure provides instructions to Pt complete on-site and off-site emergency notifications 2.
The following is a list of responsibilities and actions:
The Emergency Director is responalble for a.
approving initial and follow-up messages to the federal, state and ' local of f-site authorities as well an designating CORmunicator/ Recorders to transmit these messagas. (91002-C) b.
Tho Emergency Director is responsiblo for Objective 15 f
the declaion to notify federal, state, and local off-site auchorities that an emergency has been declared and to recommend any protective actionc (91002-c) c.
A communicator shall start immediately to ED designates inform both on-site and off-site personnel communicator with required liraits d.
Initial notification of G+orgia, Burke objective 16 County, SRS, South Carolina, Aiken County, Objective 17b Barnwall County, and Allendale county off-cite authorities shall be accomplished within 15 minutes of the declaration of an omsegency or en upgrado to a mora severe omargency classification level (91002)
- 1) The primary means for accomplishing objective 20 thase notifications in the Emergency Notification Network (ENN).
(91002-C) 4 2)
If the ENN 10 70t worhing, commercial telephones should be used to make the notifications for Georgia.
A backup ENN phone in used as backup Objective 22
)
for South Carolina 24 a
LO-LP-40101-ll-C III.
LF.SSON C'UTL7NE:
~
NOTES 3)
If the commercial telephones age not working, radios should be used
- 4) 'Once a working line of communication is established, the notifications must be accompliehad in accordance WITH the checklists found in EPIP 91002-C r
e.
The NRC must be notified as.soon as Objective 16 possible within 60 minutes of the objectave 17a declaration of the emergency or whenever an emergency is u,? graded to a more severe emergency claselfication (91002-C sec. 4.2)
- 1) The primary means for accomplishing Red phone in this notitication is the Emergency control room and Notification System (ENS). (91002-C)
TSC Objective 21 2)
If the ENS is not working, commercial Objective 23 telephones should be used to inake the notification (91002-C)
- 3) once a working line of communication is established, the notification must l
be accomplished in accordance with the checklist (91002-C) 771?.ow-up messages must we completed and Objective 28 e.
i transmitted ts the state and locul l
off-site authorities whenever thoro is a significant change in plant conditions or at least overy 30 minuten (91002-C) l l
F.
Follow-up messages to the NRC should be Objective 19 l
accomplished whenever there is any further degradation, any change in one class to another, or termination of the emergency.
l G.
2mergency Commurications 1.
Dnergency Notification Network (ENN) a.
Black phone objective 20 b.
Used to notify Georgia and south Carolina stace, country and sRP authoritieu c.
The phone is located in the control t aom, TSC, EOF, and'the county and state emergency centers 4
LO-LF-40101-ll-C III.
LESSON OUTLINE:
NOTES d.
The ENN network is energized by litting the receiver.
All speakers are energized To speak the button on the hand set'must e.
be depressed f.
A dedicated two digit phonn is tho backup objecti"e 22 ENN for South Carolina.
Also, coteoretal telephones and SRP radio in TCC are backups g.
The commercial phone system is the backup objective 2?
for Georgia.
Another backup is tlo Burke County radio located in the TSC 2.
Emecqency Notification System (ENS)
Objectivs 21 Black phone with red dial face in control a.
room, TSC, EOF, and Nhc Resident Inspectors Office b.
Used for notification to the NRC Ret' ion II D
in Atlanta The phone is activated by lif tint) the c.
reeviver.
The phone at the NRC office will ring s
d.
The backup to the ENS is the Commercial Objective 23 phone system 3.
Radios Rad.o base stations are placed a.
strategically within the plant for security and maintenance b.
Various other radlos in the TSC, control room and otherTlocations are used for communication with on-site Radiological Emergency Teams and off-site authoritieu H.
Site Evacuation 1.
The site evacuation procedure provides.
instructions for the early dismiscal or evacuation of non-essencial personnai including visitors at VEGP in the event of an emergency.
2.
The Emergency Director is responsible for determining the need fc ovacuation and 26 A
LO-LP-40101-11-C-III.
LESSON OUTLINE:
NOTES selecting evacuation routes 3.
The Security Coordinator is responsible for Objective 25 conducting the evacuation and directing the security force to assist in various ntages of the evacuation 4.
A sice svaruation is required to protect or.-
wbjectivu 24 sito non-essential personnel from radiation exposure or physical harm 5.
The Emergency Director shall determine the need for evacuation given existing or anticipated conditions, after consulting with:
a.
H.P. Supervisor b.
Dose Assessment Manager c.
TSC Manager d.
EOF Manager 6.
The ED has two options:
a.
Early dismiscal at which time all non-essential personnel are sent home early b.
Evacuation of personnel to an assemble VEGP Recreation site Area primary aseembly point; Plant Wi3 son Secor.da ry 7.
Evacuation or early dismissal shall be ordered (if feasible) for an emergency classification of Site Area or General 8.
An early dismissal o.? noa-essential-personnel is noraally conducted for an Alert I.
Assembly and Accounuability 1.
Avanably and accountability is ordered by the Objective 27 FD for any emArgency classificat4on of Alert or higher.
2.
The primary assambly point for non-essential Objective 26 personnel 2e the VEGP recreation facility 3.
The backup location is Plant Wilson and 4
e.g.,
it wind would be usad if radiological conditions conditions were 4
27 9
4 d
f
-ys e
T "-
)
LO-LP-40101-11-C a
III.
LESSCH 00TL1HE:
NOTES did no* allcw the primary recreation area toward the to be used
{
recreation ares j
4.
Accountability is required to possibly identify any endangered personnel in the "Sonrch and protucted area that are unable to leave kescus" used to rencue utaccounted for personnel 5.
The Security Coordinator is responsible for the accounting of personnel Objective 20 6.
Accountability reports by the Samtrity Coordinator must be made to the ED within 30 minutes 7.
The OSOS and the TSC and OSC manager are respons!tle for accountability of personnel a
assigned to the control room, TSC, and OSC B.
The accounting of control room, TSC, and OSC shall be made within 30 niinutes of the order J.
Search and Rescue 1.
Search and Reicue proceduto provides instructior.s for the search and renc'ae of -
individuals who may be missing or disabled in the protected area.
2.
The Emergency Direccor shall be responsible Objective 29 for Laplementing this procedure by directing the TSC Manager to dispatch a asarch and rescua team 8
If the OSC has not been activat6d, tbo a.
on-Shift H.P. Foreman shell-form the team using available staff 4
3.
The OSC mArager shall to responsible fora Objartive 30 a.
Forming b.
Briefing c.
71spatching the search and rescue taon Objectiva 31 4.
The Search and Rescue Teas Leader shall be responsible for following:
a.
Following instructions 23
M LO-LP-4010*-11-C III.
LIS. TON OUTLINE:
NOTES t
b.
Maintaining Communications with OSC L
Menager or M.P. Foreman 5.
Each team aust consifat of at least two Objective 32 members.
Each team member nuet be familiar witA the plant and first aid training
?
6.
Exposuree in excess of 10CFR20 limits shall be appro,ed hf the Emergency Director 7
'.'he Emergency Director shall direct the TSC Man 67se or HP Foreman to form a search and rescue team as soon as he is made aware of a miss;ng er disabled person
'. The following guidelines shall be employed caring :be rescue effort.
Protective clothing and respiratory a.
protuction may be worn b.
Joe et lifelines and respiratory prut 3ction for areas that are amohe or steam fille >'.
Inforn. the control room of projected c.
3 actions K.
Emorgency Expobure Guidolinee 1.
The purpose of this procedure is to provide instructions and tiontrols for radiation expos' area in excena if 10CFR20 occupatronal limita during-emergency conditions V
2.
The Emergency Director has the ag).e authority objective 33 for all radiation exposures in excesu of 10CFR20 lLnits 3.
Personnel authorized to receive exposures in excess of 10CFR20 limits should meet the following critoria*.
Personnel must be frmiliar with the riaka a.
of oxposuri to higher radiation dosos which are likely.
b.
Should have current radiation exposure history and receive a briefing.
For exposures greater.JAgn 25 rem personnel Objective 35 should be volunteers. Conalder golunteers above the ArdL.9J._iLMIIA.
29
?
P LO-LP-40101-ll-C
~
k III.'
LESSON OUILINE:
53TES
~
Females should not be of child bSaring Objective 35 c.
age and capabil'ty excupt for urgent lifesaving actions 4.
The whole body emergency exposure limits ares-Objective 34 5 Rem for sampling a.
LO-TP-40101-617 b.
25 Rem for protective or carrective action c.
75 Rem to save a life L.
Protective Action Guidelines 1.
Protective actions for on-site and off-site personnel are planned provisions to ensure their safety in the event of an emergency 2.
The Emergency Director la responalbl-e for implementing on-site protective action 3.
The EU is responsible for recommendina off-site protective actienu Only the scates can er. force protective actions 4.
Protective action recommendations shal' be made on the casi's of current or projected pl ant condition and/or calculated or measured dose rates a
5.
The MP Supervisor is responsible for evaluating on-site radiological conditions for making on-site protective action recommendations to the ED 6.
The Dose Asseeseent Manage is responsible for making off-site dose estimates and' recommending off-site protective' actions 7
.The on-site proteJtive actions are:
LO-TP-40101-018 m
Ob$ective 36 Non-essential personnel early 4.
Per Sito dismissal or plant evacuation Evacuhtion E?IP -
mandatory for Site Area or General Emergency b.
Distributing potaantum lodine (KI).
KI is a iodine for plant workers 4
.iboorption blocker of the thyroid c.
Use of additional festmetry, respiratory protect.:n. and-protectivu e
~ ~ ~ ~ ~ ~ -
~ ~ ~
I LO-LP-40101-11-C
-I-LESSON OUTLINE:
NOTES clothing 8.
Off-site Protective Actions are LO-TP-70101-019 Objective 37 Evacuation of off-site personnel of at Minimum evac. for a.
least a 2 mile radius General Etergen;y based on meteorological in f o rmat ion b.
Further ovacuation of affecting sectors An option if off-site doses do not reach Recommend personnel to seek shelter, the evacuation c.
close windows, secure ventilation threshold systems, etc.
H.
Recovery 1.
This procedure providos instructions for determinir.g wher. the emergency condition will be terminated and the recovery phaso initiated It also describeo the process usad to a.
notify and activate the recovery organization as well as its functions and rengonsibi11 ties, includ'.ng management s'
of resources fos long-term recovery operations 2.
The Emergency Director direces the notification and activation oC the recovery organization.
(Concults with V.P. Nuclear Operations).
3.
The Recovery hanager shall have overall
_ Objective 40-responsibilliy for restoring the plant to a normal operating configuration.
The primary for this position is the VECP General H'an6ger Nuclear Plant c
4.
Recognizing the following conditions the Objective 33 Emergency Director has decided to terminate Handout #1, the emergency conwition:
Page 15 a.
Plant radiation levela are stable or Objective 29 deereasing with time b.
The affected reactor is in a stable
-ondition and can be maintaineo indefinitely in a stable condition Fire or ot.ier similar emergency c.
31 I
~
LO-LP-40101-11-C III.
LESSON OUTLINE:
~~~
NOTES conditions i.o longer constitute a hazard to safety-celated systems, equipment, or personnel.
d.
Radioactive releases to the environment have ceased or been controlled to within permissible license limits e.
Discussiono with GPC management, VEGP Emergency Response organization, and off-site authorit!.es do not result in identification et any valid reason for not terminating the emergency 5.
When the ED has formally. terminated the emecgency, command is transferred to the Recovery Manage and Recovery Organization 6.
The Recovery Organizatien le made up of LO-TP-40101-020 individuals who manago and direct personnel Objective 4 who a.
Perform required maintenance b.
Develops recovery schedule Provides HP support during the entire c.
recovery period N.
Computerized and Manual Backup Method for Release Rate and Dose Calculations 1.
The purpose of this procedure is to provide instructicas for personnel to estimate-radiclogical releases resulting in off-site doses which would require the Lmplementation of protective action recommendations.
2.
The OSOS or designee shall initially be Objective 413 responsible for deternining release rates and carrying out initial of f-site-dose calculations a
a.
H.P. Supervisor la responsible if the TSC is activated Objective 41b b.
Dcae Assessment Manager is responsible if the EOF is activated 3.
.'he primary method of calculation of of f-site doces is the VIBRANT computer dose calculation' j.
32
s LO-LP-40101-11-C III.
LESSON OUTI.IhEs NOTES 4.
The calculation uses the following input cata' Objective 44 Handout #1, Page 21 a.
Windspeed and direction (primarily f rom ERF computer) b.
Plant radiological and effluent data (primarily from ERF computer)
Direct measurement of effluent path with a c.
portable inst.
5.
The Output of the VIBFANT calculation in Objective 45 a.
Vlume arrival time b.
Direction (X/Q) c.
Whole body doses d.
Infant thyroid doseo Handout #1, Page 22 e.
Doses at preset downwind distancon 6.
The manual beckup method is used av a Objective 42 backup nothod and is used with any of The OSOS will in the following Fout Accident Accident all probability l
Monitors (PAM's):
une this method when initiolly l
determining off-site dosca a.
RE 12444C Unit 1 Plant Vent b.
RE 12444C Unit 2 Plent Vent c.
RE 12839C Unit.1 & 2 Turbine Building d.
RE 005/006 containment aldg Upper Level Area' Rad-High-Range e.
RE 13119 S/G (4) Main Steam Line f.
RE 13120 s/G (1) Main Steam Line g.
RE 13121 S/G (2) Main Steam Line h.
RE 13122 S/G (3) Main Stean Line 7.
The rediation monitor readings are then used as input data with worksheets in the procedure 33 4
4 e
LO-LP-40101-ll-C III.
LESSON OUTLINE:
~~~~~
NOTES 8.
The worksheet then yield the following Objective 43 information.
a.
Iodine doce at site boundary b.
Emergency Classification c.
Protective action recommendations O.
Control Room Instrumentation Output for Aasessment of Core Damage / Core Damage Asoc1ement (Procedure 91502-C) 3 1.
Provides a method of classify and estimating 91503-C the extent of core damage 2.
coordinated by chemistry personnel 3.
Chemistry makes all damage estimatea using objective 47 information that may be provided by other groups 4.
Oparatione department Objective 46 Collect and record infocmation obtained a.
91503-C from Control Room instrumentatien needed in assosament of core damage b.
RVLIS reading & tecording Objective 43
- 1) Determines if core was uncovered Section 5.1.1 2)
If so, estimate length of time in minutes Core exit thermocouple-temperatures c.
Section 5.2.2
- 1) All temperatures excoeding 1300 F
- 2) Corresponding core location and TC ID number on Data Sheet d.
Containment high range monitor and Sectiot 5.3.1 containment hydrogen monitor readings Determine volume of all RCS additions e.
during accident (Data Sheet 2; 1)
RWST 2)
BAST 24 t
LO-LP-40101-11-C III.
LESSON OUTLINKa NOTES
~~
3)
Accumulators ('<6,900 gallons) 5.
Data cheats transmitted to Chemistry department to coordinate with core damage assessment activities a.
If core was never uncovered and no core exit RC temperatures corresponding to saturation temp at RCS preocure were recorded, then no generalized coro damage is probable b.
The following Tables / Data sheets from 91502 ara used by Chemistry to interpret data from CR and assess damage 1)
TC temperature 1300 F; Table 1 LO TP-40101-C21 Handout #1, Pago'19 2)
Containment HR menitor and H Conc.
2 (Data Sheet 1, Sheet 2) c.
Chemistry also reqvesta post accident samples P.
EMERGENCY CLASS DETERMINATION SCENARIO Objective '13 I
1.
Scenario #1 A mechanic working inside a highly LO-TP-40101-022 a.
contaminated area suffers a deep laceration on his forearm that will require atitches and specialized medical attention. Surveys of the wound indicate internal contaminution. The-mechanic is l
sent to the hospital b.
Notification of Unusual Event l
2.
Scenario 92 i
Radical anti-nuclear terrorist aided by LC-TP-40101-023 a.
disgruntled plant employees gain accean to l
the pret.ected area and the control room L
with intruders controlling the actions of l--
the piant operatorn l
b.
Answer General Emergency - loss of physical centrol of plant l
3.
Scenario #3
't 4 -
d r-r y
LO-LP-40101-11-C III.
LESSON OUTLINE:
~
NOTES a.
Following & secondary side steam break LO-TP-40101-024 (outside of containgent) that occurred with the RCS at 450 t arid 1350 pegg, all cold leg temperatures drop to 240 ? in 11as than one hour b.
Alert classification 1.
Scenario #4 a.
Following a moderate I.OCA, prsseurizov LO-TP-40101-025 level cannot be maintained via the normal charging ficwpath, even with letdown isolatod b.
Site Area Emergency End: IEH B4.042 III.
SUMMARY
7.
Review the Objectiver 1.
NAME THE KEY INDIVIDUAL RESPON.9 IDLE FOR THE IMPLEMENTATION OF THE EPIPs Emergency Director (ED) 2.
STATE THE FOUR EMERGENCY CLASSIFICATIONS IN ORDER OF SEVERITV 2RC'M IEAST TO WORST Notification of Unusual hvens (NUE)
Alert Site Arun Emergency General Imergency 4
3.
OIVEN A LISI CP KEY EPIPJ, DESCRIBE THE PURPOSE AND USE OF EACH Duties of the Emergency Director (91102-C) n.
- Provides instrue* 'ons to the ED in fultilling his responsibility for overall coordination and direction of the Emergency Fesponsa Organization b.
Ernegency Classification (91001-C)
- Providue instructions for the clanaification of off-normal events into one of four emergency classification lesels.
It also provides initial implementing instructions to the ED Emergency Notification (91002-C) c.
- Provides instructions to complete initial 1
36 a
a m
LO-LP-40101-11-C III.
LESSON OUTLINE:
NOTES and follow up notification to GPC on-nite and off-sita emergency-response personnel and to Georgia, South Carolina, local counties, and NRC officials d.
Site Evacuation (91403-C)
- Provides instructions for thc early dismissal or evacuation of-non-essential personnel from the plant site in.the event of an emergency o.
Assembly and Accountability (91401-C)
- Provides instructions for the assembly of r.on-essential personnel to their designated _ assembly area and the accounting of. personnel to identify those who may be missing f.
Protective Action Guidelines.(91305-C)
Providen' instructions for the on-sita and off-site protective actions alternatives tc ensure plant and off-cite personnel safety in the event of an emergency g.
Recovery (91501-C)
- Provides instructions for determining when-the amergency condition will.be terminated and the recovory phase initiated.
It also dancribes the process-used to notify and activate the recovery organization for immediate and long term recovery operations-h.
Core Damage Asssssment (91502-C)
- Provides a method to classify and estimate the extent of core damage through 9
core fission product release neasurements..
reactor vessel level indications, and corn exit thermocouple _temperaturen along with other auxiliary readings-4.
DESCRIBE THE RESPONSIBILITY OF THE,TSC. OSC, EOF,. RECOVERY ORGANIZATION, AND HP AND
-CHEMISTRY GROUPS, AND STATF, WHO DEPLOYS THEN TSC - activated by ED Provides in-plant radiological-assessment and-
- protective.actione cocommendationu Provides engineering analysis for control _ Room support 37 s
1*-.
J
Lo-LP-40101-11-C III.
LESSON OUTbiNE:
NOTES Providos liaison between TSC and CR Coordination of emergency maintenance Directs post accident and plant chemistry sampling and analysis.
Evaluates chemistry data and provides core damage assessment Plans and Lmplemente logistical support Provides Seewse control and accountability in TSC OSC - activated by ED The functions of the OSC ares Serve as the assembly and staging area for a.
personnul pooled for emergency responoe b.
Raspond to requesto from the ED and the TSC concerning deployment of RET's e,
Management of emergency equipment and supplies d.
Coordination o! movenent of perwonnel on-site EOF - activated by ED The functions of the EOF group ares Direction and control of CPC off-site a.
emergency response b.
Assistance to the ED and sapervision of EOF Communication of radiological information c.
to state and local emergency response agencies a
d.
Support of initial activities associated with planning for re-entry or recovery operation a.
Acceos control for EOF f.
Processing of personnel who require authorization to enter site g.
Requesting assistance from local law 38 i
t
LO-LP-40101-11-C III.
LESSCH OUTLINT4 NOTES 3
authorities h.
Performance of off-site dose calculation 1.
Direction of Field Monitoring Teams
).
Coordination with state and federal groups performing radiological assessment k.
Development of protective action 1
recommendations 1.
Ansumption of logistics support functions from the TSC Providing press release when authorized by m.
the ED Recovery Organization - Deploy by ED 0
Responsible fort Assuming aanigned positions and ensuring a.
that support staff are available and properly briefed b.
Ensuring that relief pereonnel are fully briefed prior to relinguishing their reopensibilities Health Physics Group - Deployed by ED The Health Physica Group provides the following key functions during an emergency a.
Performs off-site dose calculatiens b.
Discusses on-site and inplant radiological conditions c.
Provides on-site and off-site radiation protection measureo Chemistry Group - Deployed by ED' The Chemistry Group provides the following key function during an emergency a.
Assess coro damage from accident b.
Evaluates in-plant chemistry analysta 39 i
LO-LP-40101-11-c Y557 LESSot! OUTLINE:
~
~
NO'IES e
c.
Operates PASS S.
LIST THE VARIOUS RADIOLOGICAL TEAMS. DESCRIBE THEIR F UNCTION, ALD STATE WHO DEPLOYS THEM Function of RET's - Deployed by ED Search and Rescue Team - performs emergency a.
search ard rescue of individuals that ate unaccounted for or disabled b.
First Aid Team - performs first aid for radiological and non-radiological injuries and personnel decontamination as required Damage Assessment / control Team - a selected c.
group of personnel who perform damage assesseant and control activities as needed d.
Repair and Modification Team - a selected group of personnel who perform cepair work and modify oystems, equipment, etc., as needed In-Plant Monitoring Team - performt in-e.
plant sampling and surveys.
'he Health Physica Supervisor uses thin information when providing Protective Action g
recommendations to the ED f.
Back-up Fire Brigade - back-up support to the normal chift fire brigade 6.
STATE WHOIFILLS THE INITIAL ED POSITION mlEN IHE PRIMARY IN NOT ON-SITE OSOS 7.
STATE WHO THE PPIRARIES AND FIRST ALTERNATES ARE FOR THE ED POSITION Primaries:
-Vice Prealdent, Nuclear or General Manager, Nuclear Plant First Alternates Analstant General Manager, Plant Operationa 8.
STATE FROM MEMORY ED DUTIES THAT CAH NOT BE DELEGATED (SRO ONLY) 1
f LO-LP-40101-11-C III.
LESSOfi OUTLINE:
NOTES Classifying and declaring the emergency, a.
including upgrading, downgrading, or te rmina t.1.on b.
Recommending protective actions to off-site authorities and control of messages c.
Deciding to ovacuate non-eacential personnol from the site at the Alert classification level i
d.
Authorizing personnel radiation e'nouttres in excess of 10CFR20 limits, if :.researy Deciding to request assistance from fe?. ora}
e.
oupport groups f.
Deciding to notify ef f-site anthorit ies responsible for emergency magt.e;ot 9.
STATE WHO HAS AUTHORITY TO JP! ME MODIFICATIONS TO EPIPS DURING AN RREMGENCY SITUATION Emergency Director (ED) 10.
LIST THE THREE FIfSION PRODUCT BA*AIERS THAT ARE FART OF THE CRITERIA FOR CLASSIFYING AN EHEnGENCY Fuel / cladding RCS Containment 11.
DESCRIBE HOW THE STATUS OF FISSION PRODUCT BARRIER INTEGRITY IS OBTAINED First determined by the operator by monitoring the CSF's using the SPDS/ERF. computer or 19200-C-12.
LIST AN EXAMPLE FOR THE FOLLOWING KEY FACTOR 3 THAT ARE CONSIDEPED NHEN CLASSIFYINC AN EMERGENCY:
NUE:
a.
PLANI ELECTRIC POWER Loss of on-alte or off-site power b.
TECHNICAL SPECIFICATIONS 41 l
1 1
r' s
LO-LP-40101-11-C III.
LESSON OUTLINE:
NOTES Loss of Engineered Safety Feature, PERMS monitor or Effluent Air Flow Inst.
requiring shutdown by Technical Specifications Exceeding RCS leak rates per Tech Specs Exceeding RCS attivity Ier Toch Specs Any Tech Spec safety limit violation c.
RADIOACTIVITY Trar.sportation of f-site of a cont aminated injured victim Gross f ailed fuel taonitor exceeds E+4 cpn above normal s
Raoloactive effluent Tuch Specs d.
PLANT SYSTEMS Rapid depressurization of the secondary system Yurbino rotating component failure causing rapid pltat shutdown ECCS discharge to reactor vessel Reactor protection actuation without sub-criticality Failure of a safety or relief valve to reclose in a safety related system e.
NATURAL PHENOMENON Any earthquake felt or defected on-site Tornado or hurricane Fire in the plant labting longer than 10 minut9s f.
MAN-MADE HA'ZARDS Aircraft crash on-site Train derailment on-site 42 l
\\
e LO-LP-40101-11-C
~'
III.
LESSON OUTLINE:
NOTES I
On-site explosic.7 On-site toxic gas release j
g.
SECURITY Unusual aircraft activity overhead I
Security threat or attempted sabotage i
l h.
FISSION PRODUCT BARRIER Not considered for this classification 1.
SHUTDOWN SYSTEMS Not considered for this classification Alert, Site Area, and General:
See 91001-C Page 7 of 12 13.
GIVEN AN EHERGENCY SCENARIO, STATE THE EMERGENCY CLASSIFICATION Refer to LP Section II.U. for examples of scenarios 14.
DESCRIBE THE PROCEDURE FOR DOWNGRADING AN EMERGENCY An emecg.ncy is downgraded as follows:
a.
The ED determines that conditions are favorable for downgrading an emergency b.
Notification will be made to state, local and federal officiale notifying them that the emergency has been downgraded Completa all actions that are necessary c.
'or that emergency classification 1b.
STATE THE INDIVIDUAL RESPONSI.BLE FOR MAF.ING EMERGENCY NOTIFICATIONS Emergency Director (ED) 16.
LIST THE STATE AND FEDERAL AUTHORITIES THAT ARE NOTIFIED IN AN EMERGENCY Georgia Burke County 43
, ~,
LO-LP-40101-11-C III.
LESSON OUTLINE:
NOTES Aiken County Barnwell County Allendale County NRC SRS 17.
STATE THE ALLOTTED TIME TO CONTACT THE:
a.
NRC As scon as possible after notifications to state and county agencies 111d Within 60 minutes b.
STATE AND LOCAL AUTHORITIES within 15 minutes 18.
DESCRIBE WHEN FOLLOW-UP MESSAGES ARE REQUIRED FOR STATE AND LOCAL OFFICIALS (SRO ONLY)
Whenever there is a significant change in plant conditions or at least every 30 minutes 19.
DESCRIBE WHEN FOLLOW-UP HESSAGES ARE REQUIRED FOR THE NRC (SRO ONLY)
Whenever there is any further degradation, any change in one class to another, or termination of ths emergency 20.
DESCRIBE THE COMMUNICATION SYSTEM FOR NOTIFYING STATE AND LOCAL OFFICIALS Emergency Notification Network (ENN) black phones, energized by lifting the receiver. To l
speak, the button on the hand set'must be depreesed 21.
DESCRIBE THE COMMUNICATION SYSTEM FOR NOTIFYING j
FEDERAL (NRC) OFFICIALS Emergency Notification System (ENS),
Black phone with red dial face.
It is activated by lifting the receiver 22.
LIST THE BACKUP COMMUNICATIONS FOR NOTIFYING STATE AND LOCAL AUTHORITIES 44 O
I LO-LP-40101-11-c III.
LESSON OUTLINE:
NOTES Scuth Carolings l
1)
SC Backup ENN (two digit phone) l 2)
Commercial telephonan l
3)
9A9L9.la 8 1)
Commercial telephcrie 2)
Burke County Radio in TSC 23.
LIST THE BACKUP COMMUNICATIONS FOR NOTIFYING FEDERAL OFFICIALS l
The commercial phone system 24.
STATE THE CIRCUMSTANCES REQUIRING SI?!E EVACUATION (SRO ONLY) i Whenever a Site Area er General Emergency is declared 2I l
Whenever the E.D. has determined that conditions warrant it 25.
STATE THE INDIVIDUAL RESPONSIBLE FOR-CONDUCTING l
THE EVACUATION The Secuilty Coordinator 26.
STATE THE TWO ASSEMBLY AREAS FOR VEGP NON-ESSENTIAL PERSONNEL VEGP recreation facility - primary Plant Wilson - backup 27.
STATE THE CIRCUMSTANCES REQUIRING ASSE;4BLY OF VEGP NON-ESSENTIAL PERSONNEL Emergency Level Alert or higher 28.
STATE THE GROUP RESPONSIBLE FOR PERSONNEL ACCOUNTABILITY Security Coordinator 45
. -. _.... ~.. -, ~. -
t-'.-
=e.
- LO-LP-40101-11-C III.
LESSON OUTLINE:
~
NOTES l
29.
STATE THE POSITION RESPONSIBLE FOR REQUESTING A SEARCH AND RESCUE TEAM Emergency Director 30.
STATE THE POSITION RESPONSIBLE FOR FORMING THE SEAi'CH AND RESCUE TEAM i-OSC Manager i
or If OSC la not activated tre onohlft Health Physics Foreman 31.
STATE THE POSITION RESPONSIBLE FOR DISPATCHING THE SEARCH AND RESCUE TEAM OSC Manager or HP Foreman if OSC not activated 32.
DESCRIDE THI' INDIVIDUALS THAT EACH SEARCH AhD RESCUE TEAM HUST CONSIST OF Two members familiar with the plant and first aid training 33.
STATE.THE SOLE AUTHOR.ITY' RESPONSIBLE FOR AUTHORIZING DOSES GREATER THAN 10CTR20 EXPOSURE LIMITS Espergency Director l:
l' 34.
STATE THE EMERGENCY WHOLE BODY LIMITS FOR THE' FOLLOWING (SRO ONLY) l
~
a.
SAMPLING UNDER ACCIDENT CONDITIONS 5 Rem j
b.-
CORRECTIVE OR PROTECTIVE ACTIC'4S -
I I-25 Rom c.
LIFE SAVING ACTIONS 75 Rom 35.
STATE WHAT GROUP OF PEOPLE SHOULD BE FIRST CONSIDERED FOR. EMERGENCY.EXPOSURI,'AND WHAT:
l GROUP SHOULD NOT BE' ALLOWED TO RECEIVE AN EMERGENCY EXFOSURE (SRO ONLY)
-46
.O l
<~
r""-
+
P o
LO-LP-40101-11-C III.
LESSON OUTLINE:
~
NCTES Volunteers above the age of 45 Females of child-boarlog age and capability 36.
STATE THE FOUR POSSIBLE ONSITE PROTECTIVE ACTION MEASURES AVAILABLE TO THE ED s.
Early dismissal b.
Plant evacuation c.
Distributing F.I tablets d.
Use of additional dosimetry, respiratory protection, and protective clothing 37.
STATE THE TWO POSSIBLE OFFSITE PROTECTIVE ACTION MEASURES AVAILABLE TO THE ED a.
Seek shelter b.
Evacuation 38.
STATE WHO IS RESPONSIBLE FOR THE TERMINATION OF AN EMERGENCY AND NOTIFICATION TO FEDERAL, STATE, AND LOCAL AUTHORITIES En.argency Director 39.
DESCRIBE THE FIVE PREREQUISITES AS LISTED IN THE PROCEDURE THAT MUST BE FACTOP.ED INTO THE i
OECISION IC TERMINATE AN EMERGENCY l
a.
Plant radiation levela are stable or decreauing with time 1
b.
The affected reactor is in stable condition and can be maintained indefinitely in e stable condition Fire or other similar emergency conditions c.
no longer constitute a hazard to safety-related systems, equipment, or personnel-d.
Radioactive releases ta the environment have ceased or been controlled to within permissable license limite Discussions with GPC management, VEGP e.
Emergency Responso Organization, and off-site authorities do not result in identification of any valid reason for not 47 S
1
/
LO-LP-40101-11-C III.
LEESON OUTLINE HOTES terminating the emergency 40.
'DTAT2 THE POSITION RESPONSIBLE FOR RECOVERY 4
OPERATIONS AND THE PHIKARY YOR THAT POSITION Recovery Hanager Primary is General Manager, Nuclear Plant 41.
STATE KHQ IS RESPONSIBLE FOR PERFORMING Orr.
SITE DOSE CALCULATIONS a.
INIT! ALLY OSOS oc designee b.
AFTER THE TSU IS ACTIVATED Health Physics Supervisor c.
AFTER EOF !S ACTIVATED Dose Assessment Hanagar
- )
42.
DESCRIBE THE INPUT AND WHERE IT IS OBTAINTD IN THE MANUAL BACKUP CALCULATION Radiation nonitor readings from plant vent etack U1/2, Turbine Building U1/2, Containmont Building, or main steam lanes 43.
DESCRIBE JRAT OUTPUT IS OBTAINED FROM THE MANUAL BACKUP CALCULATION Iodine dose at alte boundary Emergency classificatio.s Protective action recomm6ndations 44 DESCRIEE THE INPUT USED FOR COMPUTER s
CALCULATION OF OTFSITE DOSES Wind speed and direct. ion Plant radiological effluent data Direct measurement of effluent path wLth a rcitable instrument 45.
DESCRIBE THE OUTPUT THAT IS OBTAINED WHEN USING THE COMPUTER TO OBTAIN OFFSITE DOSE CALLULATIOH plume arrival time Direction (X/Q)
Whole body donos 48 O
__...~
~ _ _ ~ -. -....
l o
i l
LO-LP-40101-11-C LESSON OUTLINE:
NOTES I
Infant thyroid doses Domes at preset downwind distancea r
46.
STATE THE GROUP RESPONSIBLE FOR COLLECTICN OF DATA FOR CORE DAMAGE ASSESSMENT Operations Department 47.
STATE THE GROUP RESPONSIBLE FOR ASSESSING CORE DAMAGE chemiutry Department 48.
DESCR!El THE DATA AND THE INSTRUMENTATION TRAT IS USED IN THE ASSESSMENT OF CORE DAs3GE RVLIS reading and r4.ordings Coro cuit thermocouple temperatures conto'.nment high range monitor and containment hydrogen monitor readinge Volume of all RCS additions during accident 49.
STATE WHO IS RESPONSIBLE FOR ACTIVATION OF THE TSC, OSC, AND EOF Emergency Director (ED) 50.
STATE THE PRIMARY AND BACKUP LOCATION AND THE CRITERIA USED TO DETERMINE UPPER LIMIT OF KABITABILITY OF THE PRIMARY TSC, OSC, AND EOF I
Whole body dose 100 mr/hr in TSC, OSC, EOF Iodine activity 2.7 E-07 1
mci /cc in TSC, OSC, EOF TSC - Primary TSC l
Backup Control Room l
I OSC - Primary OSC dackup TfC EOF - Primary EOF Backup OPC District Office Waynesboro, coorgia i
f l
49 l
1.
L -..
I LO CL 40 06 LICENEED OPERATOR _0ILIECT1Yg3 10 LP 401pj,:,Q i
4 I
PURN 5E STA_fr.ntJui Following completion of this lesson, the student will possess those knowledges systematically identified for the performance i
of the EPIP OVERVIbi tasks.
j i
7II LIST 0F O M U.H5
~
1.
Name the key individual responetble for the implementation of the EPIPs.
i 2.
State the four emergency classifications in order of severity from least to worst.
3.
Given a list of key EPIPs, describ6 the purpose and use of each.
4 Describe the responeibilities of the TSC, OSC, EOF, Recovery Organization, and HP cnd Chemistry stoups during a declared emergency.
5.
List the various radiological teams, describe their function, and state who deploys them (91102+C).
(SRO only) i 6.
State who fills the initial ED position when the primary is not on site.
y l
\\
i 7.
State who the primaries and alternates are for the ED position.
f 8.
State from memory ED duties that cannot be delegated.
9.
State who has authovity to approve modifications to EPIPs during an emergency situation (91001.C).
10.
List the three fission product barriers that are part of the criteria for elassifying an emergency.
11.
Describe how the status ol' fission product barrier integrity is obta',ned.
1
OMECT1VES FOR 101.P t>0101 CONTIMUED.
- 12. 1.ist and ' cer!be the following key factors that a::s cons *,derc.1 v.ien clau 7png an emergsucy:
- a. Plant electric power
- b. Technical specifications
- c. Radioactivity
- d. Plant Systems
- e. Nae. ural Phanomena
- f. Men.Nade Hazards
- 6. S*curity
- h. Fission Prodiact Barrier
- 1. Shutdown Systems
- 1) tems of systems necessary to put plant in hot shutdown
- 2) Loss of systews necessary to put plant in cold shutdown
- 13. Given an emergency scenario, state the emergency classiff uation.
14.
Describe the procedure for downgrading an emergancy (91002 t:).
(SRO ONLY) 15.
state the individual responsible for a d in$ emergency notifications.
16.
List the stata and federal authorition that are notified in an emergency.
17.
State the allotted time to contact the (SRO ONLY):
- a. NRC
- b. State and local authorities 18.
Describe when follow up e'.ssages are required for state and local of ficial.s.
(SRO ONLY)
- 19. Describe when follow-up messages are required for the NRC (91204 C).
(SRO ONLY) 20.
Describe the communication system for notifying state and local officials.
- 21. Describe the casamunication system for notifying federal (HRC) officials.
22.
List the backup communications for notifying state and local authorities.
($R0 ONLY) 2
~~
- M J
ue
4 OBJECTIVES FOR LO.LP.40101 CONTINUED.
23.
List the backup coemunications for notifying federal officials (91403.C).
(SRO ONLY) 24.
State the circumstances requiring otte evacuation.
25.
State the indlvidual responsible for conducting *.he evacuation (91401 C).
26.
State the two assembly areas for VECP non. essential personnel.
27.
State the circumstances requiring assembly of VECP non. essential personnel.
2 28.
State the group responsible for personnel accountability (91402 C).
(SRO only) 29.
State the position responsible for requesting a search and rescue team.
30 State the position responsible for forming the search and rescue team.
31.
State the position responsible for dispatching the search and rescue team.
32.
Describe the individuals that nach search and rescue team must consist of (91301 C).
33 State the sole authority responsible for authorizing doses Ersator than 10CFA20 exposure limits.
- 34. -
State the eenrgency whole body limits for the following (SRO ONLY):
- a. soupling under accident conditions
- b. Corrective or protective actione
- c. Life saving autions 35.
State what group of people sho 21d be first consida:ed for emergency exposure, and what group should not be allowed to receive an emergency exposure (91305 C).
(SRO only) 4 3
t
OBJECTiVEd FOR E4 1.F.40101 COR1'INUED.
36.
Sumourise the evaluation and implemantation of Protective Action cuidelines as specified in the EPIP's.
37.
State the following two possible off. site protective action measures available to the ED (91301.C):
(SRO only)
- a. Seek shelter
- b. Evacuation 38.
State who is responsible for the termination of an emerger.cy and notification to federal, state, and local authorities.
39.
Describe the five prerequisites as listed in the procedure. that mast he factored into the decision to r.orminate an smorgency.
40.
State the position Temponsible for recovery operations and the primary for that position (91304.C).
41.
State who is responsible for performing off+ site dose calculations
- a. Initially
- b. After the TSC is activated
- c. After the EOF is activated 42.
Describe the input and where it is obtained in the manual backup calculation.
43.
Bescribe what output is obtained frota the manual backup calculation, b
44 Describe the input used for computer calculation of off site doses.
9 45, Dascribe the output that is obtained when using the computer to obtain off site dose calculation (91503.C).
46.
State the group responsible for collection of data for core damage assesserag.
47.
State the group responsible for assessing core tanage.
48.
Describe the data and the instrumentation tha'. is used in the assessment of core damage (91202.C. 91203 C).
(SR0 only) 4
-l
F ONECTIVES FOR LO.LP.40101 C0!(IIN1)ED.
49.
State who is responsible for activation of the TSC, OSC and EOF.
50.
State the primary and backup location and the criteria used to detonnine upper limit of habitability of the primary TSC, 050, and e
- EOF, I
O i
Page 5
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