ML20081B152
| ML20081B152 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/30/1983 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T, Schwencer A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation |
| References | |
| PROC-831130-03, NUDOCS 8403070361 | |
| Download: ML20081B152 (165) | |
Text
___ __ .
EP-20'1 Rev. 0 Page 1 of 20 V' W/ G/rgs
/
PHILADELPHIA ELECTRIC COMPANY f^
4/o LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-201 TECHNICAL SUPPORT CENTER (TSC) ACTIVATION 1.0 PURPOSE The purpose of this procedure is to describe the instructions i '
and actions required for the activation, manning, and operation of the Technical Support Center (TSC).
2.0 RESPONSIBILITIES 2.1 The Emergency Director or Interim Emergency Director shall direct the activation of the Technical Support Center by performing the necessary steps of this procedure.
2.2 shif t I & C Technici An shall activate the equipment in the TSC.
2.3 Communicators shall man assigned phones and communications log.
2.4 Status Board Recordars shall obtain and post information on assigned status boards.
2.5 Health Physics Technician shall perform a habitability check of the TSC. .
3.0 APPENDICES 3.1 EP-201-1 Technical Support Center HVAC System ' Emergency' Mode 3.2 EP-201-2 TSC Equipment Activation
j.
t 3.5 EP-201-5 Offsite Communications Status Board 8403070361 831130 3 PDR ADOCK 05000352 ,
y PDR
, , . . . ----e . - , , , - , , - - - . . . - - - , , _ , .
m
- EP-2Ol Rev. O Pace 2 of 2C V5W/ MPG /rgs 3.6 EP-2Ol-6 Staff Assignment Status Board 3.7 EP-201-7 Site Radiological Status Board 3.8 EP-2Ol-8 Field Survey Status Board 3.9 EP-201-9 Fire / Damage Status Board 3.10 EP-201-10 Dose Assessment Status Board 3.11 EP-201-11 TSC Telephone Chec% List 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT -
i None 6.0 SYMPTOMS
- Nons 7.0 ACTION LEVEL 7.1
! - Activate the TSC when an event has been classified as an Alert, Site Emergency or General Emergency in accordance with EP-101, Classification of Emergencies, or at the discretion'of the Emergency Director'.
8.0 PRECAUTIONS i 8.1 Verify TSC habitability prior to or during activation. , j 8.2 Ensure TSC ventilation system is operating and that air samples are taken periodically to measure potential airborne contamination.
l 8.3 Incoming personnel should enter the protected area i through the TSC Guard Station. m i
l l
l
... . l l
1
, EP-201 Rev. O Page 3 of 20 VAW/ MPG /rgs 8.4 If the security computer is not operable, maintain a sign-in, sign-out log for pertonnel reporting to the TSC.
8.5 Ensure that pertinent' actions and notifications are logged.
9.0 PROCEDURE 9.I IMMEDIATE ACTIONS 9.1.1 Emergency Director or Interim Emergency Director shall:
9.1.1.1 Assign an I & C Technician to perform the steps in Appendix EP-201-1 Placing the Technical Support Center HVAC System in the
' Emergency
Activation.
l 9.1.1.2 Assign an individual the duties of Emergency Director's Communicator and direct the individual to perform the steps outlined in Section 9.1.3 of this procedure.
9.1.1.3 Direct a HP Technician to perform a habitability check of the TSC per EP-330 Energency Response Facility Habitability.
9.1.1.4 Obtain status updates on plant conditions from the Contro! Ecom and have a log of
, . significant events and actions maintained.
, The Event Chronology Log shall include at least the following: '
l A. Date and Time (use 24 hr. notation) l B. Significant Event C. Significant Action i 9.1.2 Shift IEC Technician shall:
9.1.2.1 Use attached Appendices EP-2Ol-1 and t
EP-201-2 to turn on lighting, and Particulate, Iodine and Noble Gas Monitor
' PING), and to place the HVAC in Emergency Mode, t
EP-201 Rev. 0 Page 4 of 20 VAW/ MPG /rgs 9.1.3 Emergency Director's Communicator shall:
9.1.3.1 Using Appendix EP-201-ll TSC Telephone Checkoff List, verify communications capability exists from the Technical Support
' Center.
9.1.3.2 Inform the Emergency Director when the communications capabilities have been verified or of any discrepancies.
9.1.3.3 Man communications lines as directed by the Emergency Director and maintain a Communications Log containing information received from and sent to Emergency Centers and offsite agencies.
The log shall include as a minimum the following information:
A. Date and Time (use 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time notation)
- B. Messages received or sent C. Name of person information was received or sent to and location D. Name and initials of person making entries 9.1.3.4 Inform the Emergency Director promptly of all information received from on site groups and offsite agencies.
9.2 FOLLOW-UP ACTIONS 9.2.1 Emergency Director shall:
9.2.1.1 Ensure that the TSC Guard Station is activated.
9.2.1.2 Direct the communicator to call in additional personnel if needed. Use EP-280 Technical Support Center Group Phone List.
9.2.1.3 Assure that individuals are available as Status Board Recorders for necessary status boards. -
A. Plant Parameter Status Board l
. _ _ _- - -_ -_ _ - . _ .. . ~ . . . _ _ . . - _ _ _ _ _ _ _ _ _-_- _ _ .
EP-201 Rev. O Page 5 of 20 VAW/ MPG /rgs B. Event Chronology Status Board C. Offsite Communications Status Board D. Staff Assignment Status Board E. Plant Radiological Status Boar 6.
F. Field Survey Status Board.
. G. Fire / Damage Status Board.
H. Dose Assessment Status Board.
9.2.1.4 Direct the Status Board Recorder (s) to perform the steps outlined in Section 9.2.2 of these Follow-up Actions.
I 9.2.1.5 Assign an individual to, man the communication lin'es to the Control Room and Operations Support Center and direct the individual to '.*erform the steps outlined in Section 9.2.3 5f this procedure.
9.2.1.6 If necessary, assign two individuals to man the telephone consoles and direct the individual to perform the steps outlined in Section 9.2.3 of this procedure.
9.2.1.7 If necessary, assign a communicator to the Field Survey Group Leader for sending field
_.rvey data, and other information to the Emergency Operations Facility (EOF). And, to perform the steps outlined in Section 9.2.3 of this procedure.
~
9.2.1.8 Assign individuals to be data display operators.
9.2.1.9 Inform the control room when the Technical Support Center is operational and manned and assuming' control.
9.2.1.10 Brief the TSC staff on their arrival and periodically (normally every 30 minutes) on the status of the. emergency and pertinent plant conditions.
9.2.1.11 Contact the various Team Leaders for status ~
updates.
s 1
= . - + , . - - - .. .v. . . .. -
,,,~,--,r,,- -. - - ---- ,.- ~--,r,, ,,,--. , .-. --
,,.,,,m_, ,- . _ _ , , -
1
- EP-3Ol Rav. O
-' Page 6 of 20 VAW/ MPG /rgs 9.2.2 Status Board Recorders shall:
9.2.2.1 Fill in their assigned status board (s).
Format and content of the status board are given in the following appendices:
A. Appendix EP-2Ol-3, Plant Parameter Status Board B. Appendix EP-2Ol-4, Event Chronology Status Board C. Appendix EP-2Ol-5, Offsite Communications Status Board D. Appendix EP-2Ol-6, Staff Assignment Status Board E. Appendix EP-2Ol-7, Plant Radiological Status Board F. Appendix EP-2Ol-8, Field Survey Status Board G. Appendix EP-2Ol-9, Fire / Damage Status Board H. Appendix EP-2Ol-10, Dose Assessment Status Board 9.2.2.2 Contact the following individuals for the various status board information.
A. Data Display Operators for plant status inf ormati on. ,
B. Emergency Director's Communicator to Control Room for event chronology information.
i C Emergency Director's Communicater for off site communication information.
D. Emergency Director's Communicator for staff assignment information.
E. OSC Coordinator for site radiological status.
F. Field Survey Group Leader for Field Survey Status.
EP-201 R3v. O
'. Page 7 of 20 VAW/ MPG /rgs Ge Fire and Damage Team Leader for Fire / Damage Status Board.
H. Dose Assessment Team Leader for Dose Assessment Status Board.
9.2.2.3 As information is received, post on assigned status board and maintain a log record of all status board sntries.
Transmit plant status information and event chronology information to appropriate Status Board Recorders at the EOF, if activated.
, 9.2.2.4 Review and update the status board as changes in plant conditions or information warrant.
9.2.2.5 Inform the Emergency Director as significant changes in status board *information are noted.
9.2.3 Communicators shall:
9.2.3.1 When directed, use EP-280 Technical Support Center Group Phone List to call in additional personnel.
9.2.3.2 Man assigned communication lines.
9.2.3.3 Maintain a Communications Log containing information received from and sent to other emergency response facilities and other support organizations.
The log shall include as a ninimum the
- following information:
A. Date and time (use 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time notation)
B. Summary of messages received or sent C. Name of person information was received from or sent to
'I D. Name and initials of person making entries .
EP '401 Rev . O Page 8 of 20 VAW/ MPG /rgs 9.2.3.4 inferr. the Emergency Director or appropriate Team Leader promptly of all information received from or sent to members of the emergency response organization or support organizations.
9.2.4 HP Technician shall:
9.2.4.1 Periodically reverify habitability per EP-330 Emergency Response Facilities Habitability.
10.0 RETERENCES 10.1. Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation of Rev. 1 Radiological Emergency Response Plans and Preparedaess in Support of Nuclear Nuclear Power Plants.
10.3 NUREG 0696 Functional Criteria for Emergency Response Facilities.
10.4 EP-280 Technical Support Center Group Phone List.
10.5 EP-330 Emergency Response Facilities Habitability 10.6 S81.1.B Startup of the Technical Support Center Heating, Ventilation and Air Conditioning System G
G S
O
- EP-201 Rev. O Page 9 of 20 VAW/ MPG /rgs APPENDIX EP-201-1 TECHNICAL SUPPORT CENTER HVAC SYSTEM ' EMERGENCY MODE'
- 1. The TSC HVAC System should be operating in the ' Normal' mode per procedure S81.1.B Startup of The Technical Support Center Heating, Ventilating, and Air Conditioning Syst9m. If not, start up the system per S81.1.B.
A TWO POSITION MANUAL SWITCH, LOCATED IN THE DISPLAY AREA ON THE EASTERN COLUMN IS PROVIDED FOR SWITCHING THE TECHNICAL SUPPORT CENTER' S HEATING, VENTILATION & AIR CONDITIONING SYSTEM FROM THE NORMAL MODE OF OPERATION TO THE EMERGENCY MODE OF OPERATION.
- 2. Turn the control switch on the eastern colunn of the display area to its " EMERGENCY" position in order to actuate the emergency mode.
- 3. Inform the Emergency Director that the HVAC System is
- functioning in the ' Emergency' mode.
IMMEDI ATELY FOLLOWING INITIATION OF THE EMERGENCY MODE, THE FOLLOWING ACTIONS WILL OCCUR IN THE MECHANICAL EQUIPMENT ROOM.
VERIFY VISUALLY THAT ACTIONS B, E and F TAKE PLACE.
A. The filter for Unit ME-03 is activated provided its respective On-Off-Standby Switch is in the " STANDBY" position.
B. Once Fan ME-03 is activated, Dampers (MD4, MDS, and MD6) open to prescribed positions.
C. MD4 modulates under the control of the airflow monitor to maintain a 3000 cfm flow rate as read on the airflow
~
monitor panel in the mechanical equipment room.
D. MD5 and MD6 open to admit 2000 efm and 1000 cfm l respectively.
l E. MD1 closes and MD2 opens to a new prescribed position to admit 5200 cfm.
[ F. Exhaust Fan ME-07 stops, i
l L
- ,_,- .~ - . - . . , , . _ . _ , . , . . _ , . . . . _ , _ . _ . _ , _ , , . _ _ , . . , _ _ ,. . ._ . - _ _ , . _ . , _ _ , _ _ _ _ _
~
EP-201 Rev. O Page 10 of 20 VAW/ MPG /rgs APPENDIX EP-201-2 TSC EQUIPMENT ACTIVAT!_ON
- l. Enter the TSC Display area and turn on display area lighting switches on the wall by the enter door and by the conference room.
, 2. Turn on the Particulate-Iodine-Noble Gas Monitor (PING) located in the equipment room.
L
- 3. Turn on CRT's per posted procedures.
- 4. Check the radios in the equipment room for operability.
~
- 5. Inform the Emergency Director when the TSC Equipment setup is l complete and of any equipment problems.
8 d
S i
i l- .
1' D
l .
t l
l l
IP-201 Rev. D
^ Page 11 of 20 vnW/ MPG /rgs APPENDIX EP-201-3 IJ3S PLANT PAR @lffRR 5ffft1S - IJNTT NO.
DATE: __
Meteorological Parametern Time Radio 1ngical Parameters Time Reactor Parameters Time 1 Ave. Wind Nor th Stack __ con mr/hr Power Speed - moh fevel inches Ave. Wind Direction (from) .
North Stack Flow c fm ~
Ave. Radiation Reading mr/hr Pressure psig South Stack con ar/hr Ave. Ambient Temp.- I South Gtack Plow c fm Containment P.'.rameters Precipitation Drywell pressure psiq D/W Rad Monitor mr /hr Stability Class mr/hr Drywell Temp f Refuel Ploor Exh. Suppression Pool Temp f Wind Speed ( ) (Tower 1)
Air Ejector Of fgas mr/hr in Wind. Speed ( ) ( Tower 2 )
com *Sunpression Pool Level R/W Monitor Containment 10 %If2 J _ _ _ _ _ _ _
Reactivity Control Time invel Control Time Containment Control Time F.W.A. On IJnava ll / Reason Sup. Sup.
- Of Rods not inserted R Pool Pool D/W S/D tlaava i1/
C -RilR Cool Spray Snray Cool Reason CRD A A i Snt.C Ini. tinava i i /Rea son B a
n H= m C D
C ROTC Cond. A B RIIRSW On, Unava il /Reanon SBI.C Tank I,evel ,
C A NA. B_
i Pressure Control Time _
B _C ..
9
-# Bypass Valves Onen D 4
EP-201 Itev . O Page 12 of 20 VAW/ MPG /rgs SRV's AB"- E F G II .T K L M N S T.PCI A Open R 1901ations Isolate <gExceptions C T MSIV ginserl______ __
II RilR Wa si Open __D RilRSW A III RWCtl s Power 5tidrIfles f[de VII Conta inment D
Source Sunnlyinq Ilnava il / Reason C VII MISC 22D kv ~
D Co n<T. - SGTS On _llnava il /Rea son 1__o f f s i t e ,_
Train A 500 k9' Trann.
2 offsite ftdfuel .B ,
Trans. Fan A -
5fif.C B D- 1 -
D- 2 Containment 112 Recombinern ON Unava 11/Rea < ion D- 3
_A D- 4 - --__
Dia n Offnite Dieself IInava il D1 1 D1 2 ~~
D1 3 ~
.DI 4 9 0 4
EP-201 Rev. O
.. Page 13 of 20 VAW/ MPG /rgs APPENDIX EP-201-4~
EVENT CHRONOLOGY STATUS BOARD DATE:
TIME EVENT EVENT NO.
e h
e 9
e P
I: .
t i
l c
l
EP-201 Rev. O Page 14 of 20 VAW/ MPG /rgs 7 PPENDI:: EP-201-5 OFFSITE COMMUNICATIONS STATUS BOARD DATE:
OFFSITE TIMS COMMUNICATIONS RESPONSE / COMMENT e
e e
- e
- e
[
I.
e*
I MAME f LOCATION TITLE Shift Superintendent
- Shif t Supervisor Emeraency' Director Personnel Safety .
Team Leader Fire / Damage Team Leader Site Emergency Coordinator .
Health Physics / Chemistry Coordinator Radiation Protection Team Leader Dose Assessment Team Leader Chemistry Sampling & Analysis l Team Leader Tield Survey Group Leader EOF Liaison Procedure Support -
Coordir.ator Planning and Scheduling Coordinator Mechanical Engineer Liaison Electrical Engineer Liaison Emergency Support Officer .
e 4
w-p -w-- --,- -+- - g.- -++-g, --w
+-v -m , ,.w -- - - - - .ur. w,, _,m- ,,-,4 77g . ng
~
'P-2Ol Rev. O Pace 16.of 20 AW/ MPG /rgs APPENDIX EP-2Ol-7 PLANT RADIOLOGICAL STATUS BOARD DATE:
TIME i LOCATION RADIATION mR/hr AIRSORNE uCi/cc O
e E *,
9 6
9 9
9 O
e
.c.
, -_ , - , - _ _ . m,-__, .,y- ,m-
EP-201 Rev. O Page 17'of 20
. VAW/ MPG /rgs i
APPENDIX EP-201-8 FIELD SURVEY STATUS BOARD DATE:
BETA & IODINE TIME LOCATION GAMMA (ar/hr) (uCi/ce) COMMENT 9
e 4
e 0
- 9 0
1 e
p- - - - y-,- .w
.- 2P-201 Rev. O Pace 18 of 20 9AW/ MPG /rgs APPENDIX EP-2Ol-9 FIRE / DAMAGE STATUS BOARD DATE:
TIME LOCATION DESCRIPTION REPAIR STATUS 4
i e
49 e
9 e
O O
e
- - - - - - - - - - - n ,,,,, , y ,.-w,_,. __n., . - , , . . - , _ . , . .
EP-201 Rev. O Paqe 19 o f 20 VAW/t1PG/rgs APPENDIX EP-201-10 -
DOSE ASSE$SMENT DATA ST4TilS BOARD Wi nti Direction: NOBLE GAS IODINE
\
Turb. Class: T= T= T= T= T= T= T= T= T= T=
- Datet Windsneed Tmph) Release Point:
Dose Rate (mr/hT Inteq ra tied Dose ( r) ,
Dose FA fi2 hr (r) Est. Reica'se Dos,e_in T46 hr_[rl Potential Release Dose Ra te ( mr 7hr[
Inteqrated -Dose ( r) Source Term Study Hose in TI2 hr TF) Est. Activity:
Unse fn fiii hr fr) Est. Release Rates Dose Rate ( mr /h r[
Integra ted Dose ( r) itiqhest off Site iione in T+2 hr TrT Dose Rate:
589e in Tt6 hr frT Dose Rate GrIhr) _
Inteqrate1 Dose ( r)
Dose in T+2 hr fE) 6dse fn~ff6 hr fE)
Done RatNTmilGfT Inteqrate Dore [ r)
Dose fn T+1 hr Ti[
Unne in fiflIETE '
Done Ra te imE7hr)
Integrated Done 7)
Done [d Tiflir fff _
O S
w O
~
EP-201 Re e . O Page 20 of 20 VAW/ MPG /rgs APPENDIX EP-201-ll TSO PHONE CHECK LIST Test Prelude Phones for Dial Tone YES/NO a
$172 000 (Light Blue Phone)
- 142 Corporate Spokesmap. (Ash Phone)
- 162 Control Room / EOF (crange Phone)
- 152 Management Circuit (Grey Phone)
- 167 EOF (Ivory Phone)
NEC (Red Phone)
- 158 Conference Room (Brown Phone)
- 157 Emergency Director Office (Brown Phone)
- 137 Bareau of Radiation Protection (Green Phone)
- 132 Bureau of Rad. Protection-Technical (White Phone)
- 112 Emergency Notification (Blue Phone)
- 127 Evacuation Assembly (Beige Phone)
- 149 Maintenance Coordination (Brown Phone)
- 122 Field Survey (Yullow Phone) .
Test Station Phones for Dial Tone ERFDS C'omputer Terminal Emergency Analysis Team Phone Fire / Damage Team Leader Telecopier Technical Engineer Emergency Director Office Emergency Director Conference Room NRC Office Personnel Safety Team Leader Radiation Protection Team Leader Personnel Dosimetry
- Field Survey Group Leader l Chemistry Sampling and Analysis Team Leader j' Dose Assessment Team Leader
- RMMS Computer Terminal l
Security Supervisor Personnel Accountability Site Emergency Planning Coordinator __ ~
Status Boards
! EP-202 Rsv. O
- Page 1 of 7 VAW/MP rgs ko/"[]
r PHILADELPHIA ELECTRIC COMPANY d }M LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-202 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION _
1.0 PURPOSE
_The purpose of this procedure is to provide guidelines for the actions required by the Operations Support Center Coordinator to activate, man and manage the Operations -
Support Center (OSC).
2.0 RESPONSIBILITIES 2.1 The Operations support Center Cecrdinator shall activate the OSC by performing the necessary steps in this procedure.
3.0 APPENDICES 3.1 Appendix EP-202-1 OSC - Operator Assignment Status Board
- 3.2 Appendix EP-302-2 OSC - HP Assignment Status Board 3.3 Appendix EP-202-3 OSC Plant Status Board 4.0 PREREQUISITES None O
j
~
EP-202 Rev. O Page.2 of 7 VAW/ MPG /rgs 5.0 SPECIAL EQUIPMENT 5.1 Portable Area Radiation Monitor 6.0 SIMPTOMS None 7.O ACTION LEVEL J
7.1 The Operations support Center is activated when an event has been classified as an Alert, Site or General Emergency in accordance with EP-lOl, Classification of Emergencies, or at the discretion of the Emergency Director. .
8.0 PRECAUTIONS 8.1 Verify habitability of Operations support Center in
- accordance with EP-330 Emergency Response Facility Habitability. -
- 8.2 Personnel shall log in ar.d out of the Operations Support Centers in order to maintain personnel accountability.
, 9.0 PROCEDURE -
\
l 9.1 JMKEDIATE ACTIONS 9.1.1 Operations Support Center Coordinator shall:
9.1.1.1 Assign an individual the duties.of Operations Support Center Communicator and Status Board Keeper. Use Appendices EP-202-1, EP-202-2, EP-202-3 for status board formats. .
9.1.1.2 Ensure that a log,of pertinent actions is kept.
l l
[
l l
l l _
EP-202 Rev. O Page 3 of 7 VAW/ MPG /rgs .
9.1.1.3 Direct the Operaticas Support Center communicator to verify operability of the telephones between the OSC and the TSC and Control Room and maintain the OSC log and status board.
9.1.1.4 Notify the Control Room when the Operations Support Center is aanned and that communications are satisfactory between the Technical Support Center and the Operations Support Center.
P.1.1.5 Procure equipment and supplies necessary to
- assist in respondir.g to the emergency.
9.1.1.6 Have an HP Technician set up a portable area radiation monitor (if available) or use a survey meter to monitor radiation levels.
9.2 '
~ FOLLOW-UP ACTIONS' 9.2.1 Operations Support Center Coordinator shall:
9.2.1.l; - Remain available for contact with the
. . Control Room or TSC in order to provide assistance as' needed by Emergency Teams.
9.2.1.2 Direct personne1' entering or leaving the Operations Support Center to log in or out
- using the Operations Support Center log.
9.2.1.3' Contact the Energency Director for additional manpower, if needed.
9.2.1.4 Upon leaving the Operations Support Center for any reason, delegate the duties to the remaining senior operator or HP technician.
!' 9.2.1.5 Assign a HP Technicikn to periodically reverify habitability using EP-330 Emergency
' Response Facility Habitability.
10.0 -
REFERENCES '
10.1 Limerick Generating' Stati on , Emergency Plan i
k
-e w
,m- g _.
._ . _ . . , , __ . . , _ . r.. . _ _ . . ._ _ ___. ___,.._.._ ._ _ _ _ _.._.-_....._ , __ _ - _ ._ _-_ .__ . _ _ ____
EP-202 Rev. O
- Page 4 of 7 VAW/ MPG /rgs 10.2 Nureg 0654, Criteria for Preparation and Evalaation of Rev. 1 Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
10.3 Nureg 0696 Functional Criteria f or Emergency Response Facilities.
10.4 10 CFR 20 10.5 E2-330 Emergency Response Facilities Habitability 8
0 9
4 l
e
- < EP-202 K6v. O Page 5 of 7
.VAW/ MPG /rgs APPENDIX EP-202-1 OSC - OPERATOR A551GNh5NT STA*fUS DOARD DATE: .
ESTIMATID MAINTENANCE RETUFS JOB . OPERATORS TIME TIME DESCRIPTION SE!N(NAME) CALLED er e%
4 0
/
s
/ *:
$ "m o
O D
5 4
9 e
e S
- e ,
e m
M g
d
- " -~ ~ e --4 - - -
4 EP-202 Rev. O
. Page 6 of 7 VAW/ MPG /rgs APPENDIX EP-202-2 OSC - HP ASSIGNMENT STATUS BOARD DATE:
ESTIMATED HP'S SENT RADIATION RETURN JOB TIME DESCRIPTION ( NAMES) PROBLEMS TIME D
e l
f
{
e e
9 l
O e
I a
__=.. .- . . - . _ _ . . _ .. . - . . . .
~
EP-202 Rsv. O Page 7 of 7 VAW/ MPG /rgs 2
APPENDIX EP-202-3 OSC F3ANT STATUS BOARD' UNIT TIME:
i 13 KV Bus 1: 2: HPCI:
1 Condensate Pumps A B: C RCIC:
Rectre Pdaps A B: ,
4 KV Bus D 1: D 2: D 3: 34:
Diesel D 1: D 2: D 3: D 4:
RHR A B: C D:
RHRSW A: B: C: ' D: 5 Core i Spray A ____ Ba C: D:
SBLC A B: C ,
SBGT A SBGT Filter Fans A: B: B SBGT Filter
. Containment H2 Reco_mb. A B:
HPCI: _
RCIC:
SBGT Filter: At B i
l -
i l
l l'
. 4 4
EP-203 Rev. O i
, Page 1 of 17 VAW/ PG/rgs M
,,/,,/Y3 PHILADELPHIA ELECTRIC COMPANY
- LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-203 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION 1.0 PURPOSE The purpose of this procedure is to provide guidelines f or
- - the activation, manning, and conduct of operations of the Emergency Operations Facility (EOF).
70 RESPONSIBILITIES ,
2.1 The Dose Assessment Team Leader or other individual appointed by Emergency Director shall activate the EOF by performing the necessary steps in this procedure.
2.2 The Site Emergency Coordinator Communicator shall man
- 1. communication lines and log information.
2.3 The Site Emergency Coordinator shall direct coeration at the EOF.
2.4 The Status Board Recorders shall obtain and post inf ormation .
3.0 APPENDICES 3.1 EP-203-1 Plant Parameter S'tatus Board 3.2 EP-203-2 Event Chronology Status Board 3.3 EP-203-3 Staf f Assignment Status Board 3.4 EP-203-4 Head 2uarters Support Requests Status Board 3.5 EP-203-5 Offsite Communications Status Board 3.6 EP-203-6 Field Survey Status Board 3.7 EP-203-7 Dose Assessment Data Status" Board
EP-203 Rov. O i
. Page 2 of 17
. VAW/. MPG /rgs l
3.9 EP-203-9 EOF Phone Check List !
3.0 EP-203-9 EOF E7uipment Activation 4.0 PREREQUISITES None 5,0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS None 7.0 ACTION LEVEL 7.1 The EOF is activated when an event has been classified as'a site emergency or general emergency in accordance with EP-101. Classification of emergencies, or at the discretion of the Site Emergency Coordina?or or Emergency Director.
8.0 PRECAUTIONS 8.1 Maintain accountability of personnel and staff reporting to the EOF through.out the incident.
4 4
v -,4- , m , w- ry --e+ - , , . - - , , ,--
EP-203 Rev. O
. Page 3 of 17
VAW/ MPG /rgs 9.0 PROCEDURE 9.1 IMMEDIATE ACTIONS 9.1.1 The Dose Assessment Team Leader or alternate shallt
- 9.1.1.1 Obtaa.a keys for EOF from the Plymouth Dispatch office.
NOTE: ENSURE THAT ONLY INDIVIDUALS WITH OFFICIAL BUSINESS ARE ALLOWED TO ENTER THE EOF. IF THE DOOR IS TO BE LEPT OPEN, AN INDIVIDUAL WILL BE STATIONED AT THE DOOR TO CONTROL ACCESS.
9.1.1.2 Assign an individual if available, the duties of the Site Emergency Coordinator Communicator and direct the individual to perform the steps outlined in Section 9.1.2 of these immediate actions or perform them himself.
9.1.1.3 Obtain status updates on plant conditions f rom the Control Room or Technical Support c Center and maintain a record of all significant e' vents and actions.
9.1.2 The Site Emergency Coordinator Communicator shall:
9.1.2.1 Use Appendix EP-203-9 to activate the EOF e qui pment .
i 9.1.2.2 Verify communications capability by L completing Aspendix EP-203-3, EOF Phone Check List.
9.1.2.3 Use EP-279, Emergency Operations Facility Group Phone List to call in additional
, personnel to staff the EOF, if necessary.
9.1.2.4 It.?orm the Dose Assessment Team Leader or alternate when the above communications capabilities have been verified or of any problems.
l l
l l
l
EP-203 Rcv. 0
- Page 4 of 17 _
, VAW/ MPG /rgs 9.1.2.5 Man communications lines in the Site i Emergency coordinator Of fice and maintain a communications log containing information received from and sent to other facilities and other organizations. l NOTE: ENSURE ALL PERTINENT ACTIONS AND NOTIFICATIONS ARE LOGGED.
9.1.2.6 Establish a log book for purposes of accountability in which people can sign-in and out as they enter or leave the EOF.
9.2 FOLLCW-UP ACTIONS NOTE: SITE EMERGENCY COORDINATOR SHALL ASSUME CONTROL AFTER HE HAS ARRIVED AND IS COGNI" ANT OF THE SITUATION.
9.2.1 S(te Emergency Coordinator shall:
9.2.1.1 Assign an indiv' lual to each of the '
following status board groups and direct the individual to perform the steps outlined in section 9.2.4 of this procedure.
A. Plant Parameter Status Board B. Event Chronology Statua Board C. Staff Assignment Status Board D. Headquarters Support Requests Status Board E. Off site Communications Status Board F. Field' Survey Status Board G. Dose Assessment Data Status Board 9.2.1.2 Ensure that an individual is assigned as the Site Emergency Coordinator Communicator.
9.2.1.3 Inform the Technical Support Center when the Emergency Operations Facility is operational and manned and will assune control of its '
designated responsibilities.
9.2.1.4 Brief the EOF Staff periodicially on the status of the emergency and pertinent plant
- conditions.
EP-203 Rev. 0
- Page.5 of 17
- VAW/ MPG'rgs 9.2.1.5 Direct a Communicator to transmit all Status Board information to the HeadSuarters Emergency Suoport Center Status Board Recorder.
9.2.3 Dose Assessment Team Leader shal?:
9.2.3.1 Assign individuals to perform Dose Projection Calculations at the EOF in accordance with EP-210, Dose Assessment Team Activation., if a release of radioactive material has occurred or is expected.
9.2.4 Status Board Recorders shall:
9.2.4.1 Fill in their . assigned status board (s ) .
Format and content of the Status Doards are given in the following appendicas s
A. Appendix EP-203-1, Plant Parameter Status Board B. Appendix EP-203-2, Event Chronology Status Board C. Appendix EP-203-3, Staff Assignment Status Board D. Annendix EP-203-4, Headqqarters Support Requests Status Board -
E. Appendix EP-203-5,.Offsite Communications Status Board i
F. Appendix EP-203-6, Field Survey Status
- Board i G. Appendix EP-203-7, Dose Assessment Data l- Status Board l
l 9.2.4.2 Contact the following individuals for the various Status Board information.
A. TSC Plant Parameter Status Board Recorder for Plant Status information.
I B. TSC Event Chronology Status Board Recorder for' Event Chronology information.
k
EP-203 Rev. 0 Page 6 of 17
. VAW/ MPG /rgs C. Site Emergency Coordinator Communicator f or Staf f Assignment Information and Headquarters Support Recuests .
D. Emergency Director, Site Emergency Coordinator, or Control Room for offsite communication information.
E. Field Survey Group Leader for field survey data.
F. Dose Assessment Team Leader for Dose Assessment Data.
9.2.4.3 Post approcriate information on assigned status board and maintain a log record of all Status Board entries.
9.2.4.4 Review and update the Status Board as changes in plant conditions or information warrants.
, 9.2.4.5 Inform the appropriate Coordinator, Team or ,
Group Leader as significant changes in Status Board information are noted.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation oi Rev. 1 Radiological Emergency Response Plans ani Preparedness in Support of Nuclear Power Plants
~
10.3 NUREG 0696 Functional Criteria for Emergency Response i
Facilities.
10.4 EP-279 Emergency Operations Facility Group Phone List 10.5 EP-210 Dose Assessment Team Activation i
l I
t l -- ,
i l
. 203 Rev. C Page 7 of l~
VAw/MPc/rge APPENDIX EP-203-1
_I/IS PLANT PAREN_R_TE_l_i~sf_Ki_i_lf __UN_IT NO.
Date Rad iolort ica l Parameters Time Reactor Parameters Ti.ne Meteorological Parameters Time No r th S tack cos mr/hr Power 1 Ave. Wind Spemi aph North Stack Flow c fm IcVel inches Ave. Wind Direction ( f rom)
South Stack cps ar/hr Pressure nsig Ave. Radiation Read ing _ mr/hr South Stack Flow c fm Containment Parameters Ave. Ambient Temp. f
~~
D/W Rad Monitor mr/hr DrywdiT pressure psig Precipitation Re fuel Floor Exh. mr/hr Drywell Temp f Stability Class Air Eiector Offqas ar/hr Suppression Pool Temp f Wind Speed ( )
R/W Monitor com
- Suppression Pool T,evel in Wind Speed ( ) .J(Tower Tower 2) 1)
Containment %O 1:112 Reactivity Control Time Inve l Control Time Containment Control Time 9 Of Rods not' inserted F.W.A. On linava ll /Rea son Sup. Sup.
B Pool Fool D/W S/D IInava i1/
C RIIR Cool Spray Spray Cool Reason Silt.C InJ. Ilnava 11/Rea son CRD A A n
~K~~ R il ilPCI C C RCIC D Codd. A SilI.C Tank lave 1 B RIIRSW On Unavap / Reason C A Pressure Control Time C.S.A. 11 11 C C __
D filypa9s Valves Open D __
-203 Rev. I Paga R of 1*
VAW/ MPG /rg-SRV's A R C D F. P G 11 J K L M N 9 LPCI A Opan _
B Isolations Isola ted /Excegtlons Closed C I t1SIV Was_ @en D II RIIR
- Power Sunn1 ices Time RIIRSW A III RWCtl B VII Containment Soia rce Sunnlyinq IJnava i1/ Reason C VII MISC 220 kv D ~
1 of fsite Cored . SGTS On Unavall/Reaaon 500 kv Trans. Train A 2 offsite Re fuel B Trans. Fan A D- 1 .5R LC - B D- 2 Containment 112 Recombiners -
D- 3 ON Unava i 1/Roa' son D- 4 A B
Bus Offsite Dieself IJnava il D1 1 D1 2 D1 3 D1 4 .
\
- EP-203 Rsv. O Page 9 of 17 VAW/ MPG /rgs 4
APPENDIX EP-203-2 EVENT N?.ONOLOGY STATUS BOARD Dater TIME EVE!:T EVENT NO. .
0 e
9 9
4 6
i 1
e e
em
. . EP-203 Rev. 0
' ~
Page 10 of 17 VAW/ MPG /rgs APPENDIX EP-203-3
- , STAFF ASSIGNMENT ETATUS BOARD Date:
TITLE NAME LOCATION SHIF" SUPERINTENDENT SHIFT SUPERVISOR F.MERGINCY DIRECTOR FIRE / DAMAGE TEAM LDR.
PERSONNEL SAFETY TEAM LDR.
SITE EMERG. COORD.
HEALTH PHYSICS / CHEM. COORD.
RADIATION PROTECTION TEAM LDR.
DOSE ASSESSMENT TEAM LEADER FIELD SURVEY GROUP LEADER EOF LIAISON - CORP. COMM.
PROCEDURE SUPPORT COORDINATOR L
DLANNING AND SCHEDULING COORDINATOR
. g-MECH. ENGR. LIAISON ,
ELEC. ENGR. LIAISON EMERGENCY SUFFORT OFFICER CORP. SPOKESMAN OSC COORUINATOR e*
- ,- - - - - w v , y.-
~
f; EP-203 Fev. 0 -
Page 11 of 17
- VAW/ MPG /
rgs APPENDIX EP-203-4
- HEADOUARTERS SUPPORi REOUESTS S*.'ATUS BOARD Date:
TIME SUBMITTED TO ITEM RESPONSE STA*US O
e e
+
4 Y
l.
9 i
I t
4 I
L .-
l l
l-t-
. _ _ _. __. _ _ . . . _ _ . . . _ _ , _ _ , ~ _ . . _ . _ . _ . . _ . _ _ . , _ _ _ _ _ - - . , _ . - , . . _ _ . _ . , _ _ _ _ _ _ _ . _ . . . _ _ _ _ - , _ _ . _ _ . . - . . - _ _ . . - , _ . . .
EP-203 Rsv. O Page 12 of 17 VAW/ MPG/
rgs AoPEND!X EP-203-5 OFFSITE COWrJNICATIONS STA*US BOARD ,
Date:
OFFSITf '
, *I 54E COMMUNICATIONS RESPONSE /COMMEN" J
S e
e i
e
( -
i
~
EP-203 Rov. O
- Page 13 of 17 VAW/ MPG /rgs 1
APPENDIX EP-203-6 FIELD SUP.VEY STATUS BOARD Date BETA & IODINE TIME LOCATION GAWA(mr/hr) (uci/ce) COMMENT i e
a
, l O
O
- e e
b l
l l
t t
EP-! ,ev. d Page 14 of 17 VAW/ MPG /rgs.
APPENDIX EP-203-7 Dose AssMs4RErT7 1KTK .9fK70s noARn wind Direction: NOBLE GAS IODINE Turb. Class: T= T= T= T= T= T= T= T= T=
Date:
Windsnoed fmoh I Release Point:
Inne Rate ( mr /hr )
Integrat M Done ( r) iiose in Tt2 hr fi) Est. Release Dose in T46 hr (r) ~
Done Rate (mr/hr) Potential Release
_ Integrated Ibse ( r)
Do9e 11: TF2 hr (r) Source Term Study Dose in T66 hr (r)
Dose Ra te ( mr /lir) Est. Activity In teg ra t,ed Done ( r)
Done in T+2 hr (r) Est. Release Rate Dose in T&6 hr (r)
Done Rate liighest Off Site IntegratN(mr/hr)
Dose ( r) Dose Rates Done in T&2 hr (r) iione I'n~f+T hr fit '
Dose Rate {Er/hr)
Integrate Ib 9e ( r) '
Dose in T+2 hr ffT -
Ibse in TtG hE TE)
Dose Rate (mr[h'ET In teg ra tevi Dose ( r)
Do39 in T+2 hr (r)
J J
, 9 e
. EP-203 Rev. O
- Page 15 of 17 VAW / MPG / rgs APPENDIX EP-203-9 EOF PHO"E CHE;*KOFF LIST Test Prelude Phones For Dial Tone Yes/No 178 OSC (Light Blue Phone) ,
163 CR & TSC/ EOF (Orange) 168 TSC/ EOF (Ivory) 153 Management (Grey) 143 Corp. Spokesman (Ash) 123 Field Survey (Yellow) 133 BRP Tech. (White) 133 BRP Rad (Green )
153 SEC's Office (Brown)
Test Station' Phones For Dial Phone SEC's Desk SEC's Communicator NRC O f fi ce NRC Office Dose Assessment Team Leader .
Dose Assessment Team HP&C Coordinator ,
i l
Field Data Mcnitoring i
State & Local Office PEMA I __ - _ _
_ = - . . _ . = . -_-.
,EP-203 Rev. O Page 16 of 17 -
.VAW/ MPG /rgs
, EOF Telecopier EOF Telecopier ,
Electrical Eng. Liaison Mechanical Eng. Liaison .
Procedure Support Coordinator INPO Planning Coordinator 6345 EOF Liaison (Corp. Comm.)
BRP Conference Room SEC's Office Emergency Preparedness Medical Director Montgomery Chester e
Berks ERFDS Terminal hMMS Terminal f
l l
- EP-203 Rev. 0
- e ,
Page.17 of 17 VAW/ MPG /rgs APPENDIX EP-203-9 EOF EQUIPMENT ACTIVATION
. 1. Turn on Lights in Eo? using switch (es ) to the left of the f door.
- 2. Turn on CRT's using posted procedures, a
- 3. check radio base station for operability.
1 4. Inform Dose Assessment Team Leader or Site Emergency coordinator when activation is complete and of any problems discovered.
e J'
e e
I , e e
+
+
F "-
- 9- 9 tw twW* T pya e v- ---e eniMwe- _w=-er y-
- g<v- e- --w-*=* --w-r-v r-+=.er-----w--w- --
~
EP-210 Rev. O Page,1 of 4
. AJMPG/rgs st/$}
PHILhDELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATT.ON EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-210 DOSE ASSESSMENT TEAM 1.0 PURPOSO The purpose of this procedure is to provide guidelines fo:-
the Dose Assessment Team.
J' 2.0 RESPGNSIBILITIES 2.1 The Dose Assessment Team Leader shall direct the Dose Assessment Team, and formulate any protective action recommendations .
3.O APPENDICES None 4.0 PREREQUISITES None 5.O SPECIAL EQUIPMENT None i
l 6.0 SYMPTOMS 6.1 An actual or potential release of radioactive material beyond the site boundary in excess of technical specifications . ,
- EP-210 Rev. O Page 2 of 4 VAW/ MPG /rgs iw 7.0 ACTION LEVEL 7.1 The Dose Assessment Team shall be activated at the discretion of the Emergency Director.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 IMMEDIATE ACTIONS 9.1.1 The Dose Assessment Team Leader shall:
9.1.1.1 WHEN THE TSC ONLY IS BEI'NG ACTIVATED assemble the team at the Technical Support Center.
9.1.1.2 WHEN THE TSC AND EOF ARE BEING ACTIVATED TOGETHER activate the EOF in accordance with EP-203 Emergency Operations Facility (EOF)
~
. Activation and assemble the team there.
(
i 9.1.1.3 Direct the team members to perform dose calculations with the RMMS computer or l
manually using the following procedures: ,
EP-316 Cumulative Population Dose Calculations for Airborne Releases EP-318 Liquid Release Dose Calculation Method for Drinking Water l:
! EP-319 Fish Ingestion Pathway Dose Calculation l
l EP-325 Use of Containment Radiation Monitor l to Estimate Release Source Term 9.2 POLLOW-UP ACTIONS 9.2.1 The Dose Assessment Team Leader shall:
9.2.1.1 When the Dose Assessment Team has been activated, call the Shift Technical Advisor l
and relieve him of performing dose calculations.
EP-210 R v. O
~
Page 3 of 4 -
VAW/ MPG /rgs 9.2.1.2 IF THE TEAM IS PRESENTLY AT THE TSO AND NOW THE EOF IS To BE ACTIVATED, call an Alternate Dose Assessment Team Leader end direct him to do the following steps:
- A. Call in additional Dose Assessment Team members using EP-294 Dose Assessment Team Phone List.
B. Activate the ECF in accordance with EP-203 Emergency Operations Facility (EOF)
Activation.
C. When the EOF team is ready, the team in the TSC may be relieved or may transfer to the EOF.
D. Perform the necessary steps of this procedure. ,
9.2.1.3 Report results of calculations to Site Emergency Coordinator and Emergency '
Director. If requested by the Site Emergency Coordinator, report results to Bureau of Radiation Protection.
These results should include a comparison of actual field survey data (received from Radiation Protection Team Leader) and discussion of source terms (received from Chemistry Sampling & Analysis Team Leader).
9.2.1.4 Direct Dose Assessment Team to perform additional calculations as necessary.
9.2.1.5 Have the Status Board Keeper post .
calculations.
9.2.1.6 Receive results of field surveys from the Radiation Protection Team Leader and sample analysis from the Chemistry Sampling and Analysis Team Leader for use in calculations.
9.2.1.7 Use EP-317 Determination of Protective Action Recommendations to recommend protective action, if any, to the Site
! Emergency Coordinator or the Emergency Director for forwarding to state authorities.
i
_y ,, _
, . _ . _ _-_%_ , _,-___.----r-- y --s---* - - - +-r----ie-m- - - - - - - e----tm -
r--g e y-- --
EP-210 Rev. O
- Page 4 of 4
, VAw/ MPG /rgs 10.0 REFERENOES -
10.1 Limerick Generating station Emergency P Lan I
i 10.2 NUREG 0654, Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans in Support of Nuclear Power Plants 10.3 EP-316 Cumulative Population Dose Calculations for Airborne Releases 10.4 EP-317 Determination of Protective Action Recommendations 10.5 EP-318 Liquid Release Dose Calculations Method for Drinking Water 10.6 EP-319 Fish Ingestion Pathway Dose Calculation 10.7 EP-325 Use of Containment Radiation Monitor to Estimate Release Source Team 6
e 9
e 0
1
. EP-220 Rev. O Page 1 of 5 W/ G/rgs PHILADELPHIA ELECTRIt: COMPANY O LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-220 RADIATION PROTECTION TEAM ACTIVATION 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actione required to activate the Radiation Protection Team.
e 2.0 RESPONSIBILITIES 2.1 The shif t HP Senior Technician shall assume the role of the Interim Radiation Protection Team Leader,and perform the steps necessary in this procedure until relieved by the Radiation Protection Team Leader.
2.2 The Radiation Protection Team Leader shall relieve the Interim Radiation Protection Team Leader and perform the steps of this procedure not completed by the Interim Radiation Protection Team Leader.
3.0 APPENDICES 3.1 EP-220-1 Emergency Exposure Guidelines.
4.0 PREREQUISITES None 5.C SPECIAL EQUIPMENT None -
\ -
I l
l l
l
- - - -- - = .
EP-220.Rev. O Page 2 of 5
" VAW/ MPG /rgs 6.0 SYMPTOMS None 7.0 ACTION LEVELS 7.1 The Radiation Protection Team shall be activatad by
- the Emergency Director or Interim Emergency Director when necessary.
8.0 PRECAUTIONS
, 8.1 Planned radiation exposures should be limited to the ,
administrative guide levels in Appendix EP-220-1, Emergency Exposure Guidelines. -
1 9.0 PROCEDURE 9.1 IM_ MEDIATE ACTIONS 9.1.1 Shif t HP Senior Technician shall:
9.1.1.1 After discussing the situation with the Emergency Director or Interim Emergency -
Director, assume the role of Interim Radiation Protection Team Leader. !
9.1.1.2 Form a team from available people. Have the team members report to the Technical Support
,t Center or 'a location designated by th'a Emergency Director.
9.1.1.3 Form f unctional groups as necessary in accordance with the following groups:
EP-222 Field Survey Group Functions EP-221 Dosimetry,' Bioassay and Respiratory Protection Group Actions.
9.1.1.4 Direct group .to t, heir assigned emergency locations and direct them to check out and ready equipment.
,-.-.--r ..ms r w a- v - ,- +--m- -
--,-------------mn v-- -.v -- g ir--- v -
wrr - y- - - - -- .r --*- - + -
w
~
. < EP-220 Rev. O Page 3 of 5
" *- VAW/ MPG /rgs
- n. ,
s .
9.1.1.5 '
. When'tYogroups report back that they are ready to begin' group assignments, 12 form the (Interim) Emergency Director.
s .
, ~<vw 9.2 FOLLOW-U_P_ ACTIONS THE RADIATION PROTECTION TEAM LEADER MAY RELIEVE THE INTERIM RADIATION PROTECTION TEAM LEADER AT ANY POIh"r IN THE PROCEDURE 3 AND REPORT TO THE TSC.
~
9.2.1 - Radiation Protection Team Leader shall:
9.2.1.1 Coordinate dispatching the survey teams under direction of the Site Emergency Coordinator or the Emergency Director.
Report field survey data to the Dose Assessment Team Leader and Emergency Director, as necessary.'
9.2.1.2 Evaulate actions of the Personnel Dosimetry, Bigassay and Respiratory Protection Group.
9.2.1.3 Provide Radiation Protection Team Members with periodic plant or field status changes
~ which may affect the function.s of the team.
9.2.1.4 Periodically evaluate the situation to determine if additional groupsneed to be i assembled and assemble such groups.
9.2.1.5 Obtain additional personnel support, if necessary use EP-275 Radiation Protection Team Phone List.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0554, Criteria-for Preparation and Evaluation Rev. 1' of Radiological. Emergency Response Plans and Preparedness in Support of
. Nuclear Power Plants.
'h d
a e - y
~
EP-220 Rcv. 0 Page 4 of 5 . ,
. VAW/ MPG /rgs ;
10.3 EP-222 Field Survey Group Functions 10.4 EP-221 Dosimetry, Bioassay and Respiratory Protection Group Actions 10.5 EP-275 Radiation Protection Team Phone List 4
8 e
4 e
+
4 4
,.---n.. - ~ . . , , - . . . . , e- , , _ . ~ , , _ , . - , . . , ,,e - r ,,- , , , . . , - - , , , - , ,
.EP-220 Rev. 0
, Page 5'of 5
. .VAW/ MPG /rgs APPENDIX.EP 220-1 Emergency Excosure Guidelines -
i \
Projected -
Whole Body Thyroid Authorized Function Dore Dose By
- 1. Life Saving and Reduction of Injury '
75 rem
- 375 rem Emergency **
- - Director
Director
- 3. Protection of Health ' ,
and Safety, of -the Public S' rem. 25.r,em Emergency-s Director
limits limits Director
- 5. Re-entry / Recovery Stati o.n Station Activiti es Administra- Adminis- -
tive Guide- trative lines Guide- -
lines N/A
- Reference EPA-520/1-75-001 Table 2' 1 .
- Such exposure shall be on a voluntary basic
. m.
4 O
l n'
e t
I a
EP-222 Rev. 0
, Page 1 of 5 VAV/M /mla
'/' //i..
PFILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PIAN IMPLEMENTING PROCEDURE EP-222 FIELD SURVEY GROUP 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions of the Field Survey Group.
2.0 RESPONSIBILITIES 2.1 The Field Survey Group leader shall be responsible to direct the field survey squads by performing the necessary steps in this procedure.
2.2 The Field Survey Squad members shall be responsible to conduct field surveys as directed by the Field Survey Group leader.
3.0 APPENDICES 3.1 EP-222-1, Emergency Exposure Guidelines 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT 5.1 Radio 5.2 Field survey kits 5.3 Vehicle .
EP-222 Rev. O Page 2 of 5
,.0 VAV/ MPG /mla 6.0 SYMPTOMS 6.1 An actual or potential release of radioactive material beyond the site boundary in excess of technical specifications.
7.0 ACTION LEVEL 7.1 The Field Survey Group shall be activated by the Radiation Protection Team leader, when necessary.
8.0 PRECAUTIONS 8.1 The group members exposure should be limited to the guidelines in EP-222-1, Emergency Exposure Guidelines.
9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Field Survey Group leader shall:
9.1.1.1 Report to the Technical Support Center (TSC).
I 9.1.1.2 Discuss the situation with the Radiation Protection Team leader. This discussion should includes the release rate of radioactive material, wind direction and l
possible wind shifts.
I
! , 9.1.1.3 Form the necessary number of field survey squads'from available personnel. A squad consists of a Health Physics Technician and a driver.
9.1.1.4 Give each squad a radio and direct them to take the necesssary field survey equipment with them. The radios are located in the Communication Room'in the Technical Support Center and the field survey kits are located I
in the storage cicsets in the Personnel Entry Area of the, Technical Support Center.
9.1.1.5 Discuss the situation with each squad and direct them to specific locations in the field.
l t
L_.
. o
- EP-222 Rev. O
, Page 3 of 5 g VAV/ MPG /mla 9.1.2 Field Survey Squal members shall:
9.1.2.1 Report to the Field Survey Group leader at
, the Technical Support Center.
9.1.2.2 Obtain a field survey kit.- Be sure that a map and radio is available.
9.1.2.3 Inventory the kit and check equipment for I operability.
9.1.2.4 Card or sign out (if the security computer is not available) of the Technical Support Center, but keep dosimetry. Ensure that the direct reading dosimeters are zeroed.
9.1.2.5 Contact Security for the keys to a vehicle.
9.2 Follow-up Actions 9.2.1 The Field Survey Group leader shall 9.2.1.1 Maintain contact with the field survey squads and monitor squad members accumulated exposures.
9.2.1.2 Report results to the Radiation Protection Team leader and Field Survey Status Board keeper.
9.2.1.3 Provide the field survey squads with status updates as to release rate, wind direction,
[ etc. Direct the field survey squads to l ,
other locations as necessary.
9.2.1.4 Inform the. Radiation Protection Team leader
- for the need of additional personnel, if necessary.
9.2.2 Field Survey Group members shall:
l 9.2.2.1 Conduct surveys at the sites specified by the Field Survey Group leader in accordance with Health Physics Procedures.
When conducting field surveys from inside a vehicle, readings must be taken with the probe outside the. vehicle.
t EP-222 Rev. O Page 4 of 5 VAV/ MPG /mla 9.2.2.2 Report survey results to the Field Survey Group leader by radio. If the radio does not function properly, locate a telephone and report survey information. Use 327-1200 and ask for the Field Survey Group Leader on extension 122.
9.2.2.3 Await further instructions from the Field Survey Group leader.
9.2.2.4 Before returning the vehicle, survey vehicle for contamination. If contamination is found, inform the Personnel Safety Team leader and take the vehicle to the Vehicle Decontamination Facility located at the batch plant.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation of Rev. 1 Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
- o l
l e
e 1
l
EP-222, Rev O
, Page 5 of 5 VAV/ MPG /mla APPENDIX EP-222-1 Emergency Exposure Guidelines Projected Whole Body Thyroid Authorized Function Dose Dose Ibr
- 1. Life Saving and Reduction of Injury -75 rem
- 375 rem Emergency ** ;
Director
- 2. Operation of Equipment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
Director
- 3. Protection of Health and Safety of the Public 5 rea 25 rem Emergency Director
- 5. Re-entry / Recovery Station Station Activities Administra- Adminis-tive Guide- trative lines Guide-lines N/A 1 .
- Reference EPA-520/1-75-001 Table :2.1
- Such exposure shall be,on a voluntary basis e
9 a
O EP-230.Rev. O Page 1 of 9 l *.
PPG /rgs U/
PHILADELPHIA ELECTRIC COME ANY l LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE
.I EP-230 CHEMISTRY SAMPLING AND ANALYSIS TEAM ACTIVATION 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions of the Chemistry Sampling and Analysis Team.
2.0 RESPONSIBILITIES 2.1 The Emergency Director shall direct the Chemistry Sampling and Analysis Team Leader to activate a team, when required.
2.2 The Chemistry Sampling and Analysis Team Leader shall appoint a group leader and perform the steps necessary in this procedure.
2.3 The chemistry Sampling and Analysis Group Leader shall direct the group members by performing the steps necessary in this procedure.
3.O APPENDICES
~
3.1 EP-230-1 Emergency Exposure Guidelines ,
3.2 EP-230-2 Chemistry Sampling and Analysis COL 3.3 EP-230-3 Offsite Post Accident Sampling Analysis t
4.0 PREREQUISITES l
None O
e 5.0 SPECIAL EQUIPMENT None
- EP-230 Rev. O
~
- Page.2 of 9
.' VAW/MPO/rgs 6.0 SYMPTOMS None 7.0 ACTION LEVEL 7.1 The Chemistry Sampling and Analysis Group will be activated at the discretion of the Emergency Director.
8.0 PRECAUTIONS 8.1 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-230-1 Emergency Exposure Guidelines.
8.2 continuous coverage by the Health Physics Technician .
may substitute for the Psdiation Work Permit.
9.0 PROCEDURE
, 9.1 IMMEDIATE ACTIONS 9.1.1 The Emergency Director shall:
9.1.1.1 Direct the Chemistry Sampling and Analysis Team Leader to collect samples, as necessary, and analyze the samples or use offsite support groups for the analyses.
9.1.2 Chemistry Sampling and Analysis Team Leader
- shall:
9.1.2.1 Report to the Technical Support Center, if
- activated or other location to activate the l Chemistry Sampling and Analysis Team.
9.1.2.2 Appoint a group leader and have the group leader assemble a group. The Chemistry Lab, if habitable, should be used.
9.1.2.3 Discuss the type and sample frequency needed l
with the group leader. This di.scussion should also include a status of plant
~
conditions and hazards.
l i
EP-230 Rev. O
. Page 3 of 9 VAW/ MPG /rgs 9.1.3 Chemistry Sampling and Analysis Group Leader shall:
9.1.3.1 Assemble the Chemistry Sampling and Analysis Group. Ensure that a Health Physics Technician or HP Qualified Cnemistry Technician is available.
9.1.3.2 Direct the HP Technician to determine habitability of the Chemistry Lab. Use the area in accordance with EP-330 Emergency Response Facility Habitability.
IF THE CHEMISTRY LAB HABITABILITY IS DEGRADED, THE TEAM SHALL ASSEMBLE AT ANOTHER LOCATION SUCH AS THE TSC. TIME SPENT IN THE I.. LAB ANALYZING SAMPLES SHOULD BE MINIMIZED AND PROTECTIVE MEASURES SMALL BE EMPLOYED.
CONSIDERATION SHOULD BE GIVEN TO SENDING THE SAMPLES OFFSITE FOR ANALYSIS.
9.1.3.3 Direct the monitoring and sampling of release points, air monitors, and process monitors as required and in accordance with ALARA.
. 9.3.4 Chemistry Sampling and Analysis Group Members shall:
9.1.4.1 Assemble the necessary equipment needed to
- obtain and analyze samples. Label all sample containers before sampling. Use Appendix EP-230-2 as guidance to follow the
. progress of samples drawn and analyzed onsite.
l~ 9.1.4.2 Sample primary coolant and drywell l atmosphere as necessary with the following procedures:
f.
EP-231 Ooeration of Post Accident Sampling Station Following Accident Conditions i EP-232 Obtaining Drywell Gas Samples From j Containment Atmosphere Control System l
L I
EP-233 Retrieving And Changing Sample -
rilters And Cartridges From The l Drywell Radiation Monitor l
l i
I
~
- - EP-230 Rev. O
~
- Page 4 of 9 - .
- VAW/ MPG /rg s EP-234 Obtaining Drywell. Gas Samples From the Drywell Radiation Monitcar Samoling Station o
EP-235 Obtaining Reactor Water Samples From Samole Sinks Following Accident Conditions 9.1.4.3 In the event of a large radioactive liquid spill with potential for discharge to the Schuylkill River, obtain samples of the river water in accordance with:
EP-236 Obtaining Blowdown Discharge Water l' Samoles Following Radioactive Liquid Releases Following Accident Conditions 9.1.4.4 Use the following procedures to obtain samples, as necessary, from the various sample points.
Nort'h and South Stack EP-237 Obtaining the Iodine and Particula.te Samoles from The North and South Stack following Accident Conditions Liquid Radwaste EP-238 Obtaining Liquid Radwaste Samoles '
from the Radwaste Sample Sink Following Accident Conditions Off Gas EP-240 Of f Gas Samples from the Of f Gas Rydrogen Analyzer Following Accident Conditions KK Building or Suppression Pool EP-231 Doeration of Post Accident Sampling Station 9.1.4.5 Use the following . procedures for the preparation and analysis of highly radioactive samples.
4 EP-241 Sample Preoaration and -Chemical _
Analysis of Highly Radioactive Liquid Samples 1
l
. F.P-210 Rev. 0 '
Page .5 of 9 VAW/ MPG /rgs
- l -
EP-242 Sample Preparation and Analysis of High)y Radioactive Particulate Filters and Iodine Cartridges EP-243 Sample Preparation and Analysis of
' Highly Radioactive Gas Samples 9.1.4.6 Attach data sheets and analysis reports to Appendix EP-230-2 Chem Sampling & Analysis COL _for each sample taken. Give this information to the Chem Sampling and Analysis Group Leader.
9.2 FOLLOW-UP ACTIONS 9.2.1 The Chemistry Sampling and Analysis Team Leader shall:
9.2.1.1 Report the results of these analyses to the Emergency Director, the Radiation Protection Team Leader and Dose Assessment Team Leader.
9.2.1.2 Provide group members with periodic plant status changes including significant radiation exposure and radioactive contamination problems which may af f ect the f unctions of the team.
9.2.1.3 If necessary, use the post accident sampling analysis capabilities of Babcox and Wilcox by referring to Appendix EP-230-3 Offsite Post Accident Sampling Analysis for proper notification.
' 9.2.1.4 Provide additional personnel support, if necessary, using EP-292 Chemistry Sampling i and Analysis Team Phone List.
9.2.2. Chemistry Sampling and Analysis Group Leader shall:
1-9.2.2.1 Report results of samples and analysis to the Chemistry Sampling and Analysis Team Leader.
10.0 REFERENCES
10.1 LimerickGeneratingStationEmergencyPhan 1
i
= . .
EP-230 Rev. O Page 6 of 9 VAW/ MPG /rgs 10.2 NUREG 0654, Pracaration and Evaluation of Radiological Rev. 1 Em-rgency Ressonse Plans and Preparedness In Support of Nuclear Power Plants 10.3 EP-231 Operation of Post Accident Samoling Station 10.4 EP-232 Obtaining Drywell Gas Samoles From the Containment Atmosphere Control System 10.5 EP-233 Retrieving and Changing Sample Filters and Cartridges from the Drywell Radiation Monitor 10.6 EP-234 Obtaining Drywell Gas Samples from Drywell Radiation Monitor Samoling Station 10.7 EP-235 Obtaining Reactor Water Samples from Sample Sinks Following Accident Conditions 10.8 EP-236 Obtaining Blowdown Line Samples Following Radioactive Liquid Releases Following Accident Conditions 10.9 EP-237 Obtaining the Iodine and Particulate Samples from the North and South Stack following Accident Conditions 10.10 EP-238 Obtaining Liquid Radwaste Samples from the Radwaste Sample Sink Following Accident Conditions 10.11 EP-240 of f Gas Samples from the of f Gas Rydrogen Analyzer following Accident Conditions 10.12 EP-241 Sample Preparation and Chemical Analysis
. of Highly Radioactive Liquid Samples 10.13 EP-242 Samole Preparation and Analysis of Highly-l' Radioactive Particulate Filters and Iodine Cartridges 10.14 EP-243 Sample Preparation and Analysis of Highly Radioactive Gas Samoles 10.15 EP-292 Chemistry Sampling and Analysis Team Phone List 4
av b
l EP-230, Rev. O Page 7 of.9
- VAW/ MPG /rgs APPENDIX EP-730-1 Emeraency Excesure E Melines Projected Whole Body Thyroid Authorized Function Dose Dose g
- 1. Life Saving and Emergency **
Reduction of Injury 75 rem
- 375 rem Director
- 2. Ooeration of Equipment to Mitigate an 25 rem
- 125 rem Emergency **
Emergency Director
- 3. Protection of Health Emergency and Safety of the Public 5 rem 25 reta Director
- 5. Re-entry / Recovery Station. Station Activities Administra- Adminis-tive Guide- trative lines Guide-lines N/A
- Referencer EPA-520/1-75-OO1 Table 2.1
- Such exposure shall be on a voluntary basis f
l s
EP-230 Rsv. O
. . Page 8 of 9 VAW/ MPG /rg s APPENDIX EP-230-2 CHEM SAMPLING & ANALY.:TS COL TEAM ACTIONS SAMPLE TYPE: LOCATION: ,
1.
DATE: TIME:
- 2. ANALYSIS TO BE PERFORMED (LIST)
SPECIAL REVIEWED PREREQUISITES EOUIPMENT
- 3. PROCEDURES NEEDED (LIST) l i INITIALS SAMPLE GROUP ACTIONS f
- 1. TRAVEL ROUTE PLANNED
- 2. RP COVERAGE AVAILABLE
- 3. PROTECTIVE EQUIPMENT & DOSIMETRY ISSUED .
- 4. SAMPLE SURVEY BY HP
- 5. SAMPLE TRANSPORTED TO LAB i.
INITIALS ANALYSIS GROUP ACTIONS
- 1. LAB READY TO RECEIVE SAMPLE
- 2. MP COVERAGE AVAILABLE IN LAB
- 3. PROTECTIVE EQUIPMENT E DOSIMETRY ISSUED
- 4. SAMPLE RECEIVED IN LAB ,
- 5. DOSE RATE SURVEY DONE IN LAB AFTER SAMPLE RECEIPT
- 6. . RESULTS FORWARDED TO TEAM LEADER
~
~
. .- EP-230 Rev. O Page 9 of 9 VAW/ MPG /rgs APPENDIX EP-230-3 Offsite Post Accident Samoling Analysis Babcox and Wilcox Lynchburo Research Center Messace:
This is ( Name ) reeresenting the Chemistry Sampling &
Analysis Team of Limerick Generating Station. This is a request to provide post accident sample analysis at the Lynchburg Research Centeri All inquiries should be directed to ( Name ) at the following chone number . The following information is known concerning the samples:
Unit Number of samples Estimated shipping time '
Method of transportation (air or land)
Name of carrier Samole 1 2 3 4 Tyne (liquid, ga seou s, cartridge)
Measured Radiation Levels
- surface l -3 feet l- .
Remarks :
i Noti fications Emereenev Control Of ficer Wbrk Home J. P. Doran 804-522-5137 804-525-4251 Alternate Emeroencv Control Officer -
A. F. Olsen 804-522-5174 804-933-2517
---__m. , - ~ , - , - . - , _ , ,
EP-250 Rev. O Page.1 of 4
. - W/,PG/rgs PHILADELPHIA ELECThIC COMPANY (
LIMERICK GENERATING STATION -
EMERGENCY CAN IMPLEMENTING PROCEDURE EP-250 PERSONNEL SAFETY TEAM ACTIVATION 1.0 PURPOSE The purpose of this procedure is to provide guidelinet for the actions required to activate and assemble the Personnel d Saf ety Team.
2.0 RESPONSIBILITIES 2.1 A Shif t Health Physics Technician shall assume the role of the Interim Personnel Safety Team Leader and perform the necessary steps in this procedure.
2.2 The Personnel Saf ety Team Leader shall relieve the Interim Personnel Saf ety Team Leader and perform the necessary steps in this procedure.
3.0 APPENDICES 3.1 EP-250-1 Emergency Exposure Guidelines
[ .
4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None 6.O SYMPTOMS None
nP-250 Rev. 0
- Page 2 of 4
- VAW/ MPG /rgs 7.0 ACTION _ LEVEL 7.1 The Emergency Directo.r or Interim Emergency Director t shall activate the Personnel Safety Team a't his discretion.
8.0 PRECAUTIONS o R.1 Planned radiation exposures should be limited to the
+ administrative guide levels in Appendix EP-250-1 Emergency Exposure Guidelines.
9.0 PROCEDURE 9.1 IMMEDIATE ACTIONS 9.1.1 A Shift HP Technician shall:
9.1.1.1 Assume the role of the Interim Personnel-Safety Leader and discuss the situation with the Emergency Director or Interim Emergency Director.
9.1.1.2 Assign available personnel from the Operations Support Center (OSC) or Control Room to the required Personnel Saf ety Team Groups to carry out the following procedures, as necessary.
EP-251 Plant Survey Group Functions I
EP-252 Search and Rescue /First Aid l-EP-254 Vehicle and Evacuee Control Group l'
EP-255 Vehicle Decontamination Procedure l
l 9.1.1.3 Direct the group leaders to report the status and results of group activities via l ,
radios, telephone or plant page system.
l l
1
.. .. - . , . . _ . , , . _ . , _ . ~ . . _ , _ . - _ . _ . , _ _ . . _ . . . _ . , _ _
EP-250 Rev. O Page 3 of 4 VAW/ MPG /rg s 9.2 FOLLOW-UP ACTIONS 9.2.1 Personnel Safety Team Leader shall:
9.2.1.1 Reoort to the Technical Suceort Center and relieve the Interim Personnel Safety Team Leader.
9.2.1.2 Coordinate with Personnel Safety Team to Director with site provide radiologicalEmergency data / personnel injury / contamination status and site evacuation status.
9.2.1.3 Ensure Personnel Safety Team members are available at assembly areas (OSC on 269, Elev. Turbine Enclosure or designated evacuation assembly area). Use EP-277 Personnel Safety Team Phone List to call additional personnel, if necessary.
9.2.1.4 Assign additional team members to functional groues as necessary per step 9.1.1.2 of this procedure.
9.2.1.5 Designate groue leaders for the functional groups formed.
9.2.1.6 Maintain communications via any available means with the groups af ter they have been sent to perform their assigned tasks.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0354, Criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans and Preoaredness in Support of Nuclear Power Plants.
l l
10.3 EP-251 Plant Survey Group Functions
! 10.4- EP-252 Search and Rescue /First Aid i
10.5 EP-254 Vehicle and Evacuee Cont ol Group 10.6 EP-255 Vehicle Decontamination Procedure
~
10.7 EP-277 Personnel Safety Team Phone Lict i
EP-250 Rev. O Page 4 of 4 VAW/ MPG /rgs l l
APPENDIX EP-250-1 Emercenev Exoosure Guidelines .
Projected Whole Body Thyroid Authorized Function Dose Dose gv
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Equipment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
Director
- 3. Protection of Health -
and Safety of the Public 5 rem 25 rem Emergency Director
- 5. Re-entry / Recovery Station Station Activities Administra- Adminis-tive Guide- trative lines Guide-lines N/A
- Re ference: EPA-520/1-75-001 Table 2.1
- Such exoosure shall be on a voluntary basis e
S l .
I l
~
EP-261, Rev. O Page 1,of 5 G/rgs y /
PHILADELPHIA ELECTRIO COMPANY LIMERICK GENERATING STATION '
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-261 DAMAGE REPAIR GROUP 3.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions of the Damage Repair Group.
2.0 RESPONSIBILITIES 2.1 The Shift Supervisor shall assume the role of the Interim Fire and Damage Team Leader when directed by the Emergency Director or Interim Emergency Director and perform the necessary steps in this procedure.
2.2 The maintenance shif t assistant foreman shall assume the role of the Damage Repair Group Leader when directed and perform the necessary steps in this procedure.
2.3 The Fire and Damage Team Leader shall relieve the Interim Fire and Damage Team Leader and perform the steps necessary in this procedure.
3.0 APPENDICES 3.1 EP-261-1 Emergency Exposure Guidelines 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT -
None -
EP-261, Rev. O
~- Page 2 of 5
- VAW/ MPG /rgs 6.0 SYMPTOMS None 7.0 ACTION LEVEL 7.1 The Damage Repair Group rhall be activated whenever the (Interim) Emergency Director or Fire and Damage Team Leader deems their services necessary.
8.0 PR% CAUTIONS 8.1 Planned radiation exposures should be limited to the
- administrative guide levels in Appendix EP-261-1 Emergency Exposure Guidelines. ,
8.2 Continuous coverage by Health Physics Technician may substitute for the Radiation Work Permit.
l .
9.0 PROCEDURE 9.1 IMMEDIATE ACTIONS l
9.1.1 The Shift Supervisor shall:
9.1.1.1 Assume the role of Interim Fire and Damage Team Leader.
~
9.1.1.2 Contact the maintenance shift assistant foreman. Explain the situation and direct him to assemble a Damage Repair Group.
9.1.2 Maintenance Shift Assistant Foreman shall:
9.1.2.1 Assume the role of the Damage Repair Group Leader.
9.1.2.2 Assemble the Damage Repair Group. Contact the HP-OSC Coordinator for an HP Technician.
9.1.2.3 Explain the situation and what has to be done, to the group. .
9.1.2.4 Obtain necessary keys for the group.
EP-261, Rev. O Page.3 of 5 VAW/ MPG /rgs 9.1.2.5 Review applicable maintenance proc'dures and advise group members. ,
9.1.2.6 Provide information to the group on equipment and supplies.
9.1.2.7 Request system blocking as needed from the OSC Coordinator.
9.1.2.8 If necessary, request additional personnel or equipment f rom the Fire and Damage Team Leader.
9.1.2.9 Periodically update the Fire and Damage Team Leader of the status of the repair work.
9.1.3 Damage Repair Group Members shall 9.1.3.1 Report to the area. designated by the team leader.
9.1.3.2 Assemble necessary equipment (i.e., tools, parts, etc. for the pending operations) from locations on or of f-site designated by the Damage Repair Group Leader. The Operations Support Center (on 269' elevation Turbine Enclosure) should be contacted for radiation monitoring equipment needed to support the repair effort.
9.1.3.3 Follow the directions of the group leader.
9.1.3.4 Keep the Damage Repair Group Leader updated
- as to current status of emergency repair efforts.
9.1.3.5 The HP Technician s.hould obtain the necessary equipment from the OSC. When the
, group is conducting operations, the HP Technician shall advise group members of stay times based on current radiological conditions.
9.2 FCILOW-UP ACTIONS 9.2.1 Interim Fire and Damage Team Leader shall:
9.2.1.1 Periodically upda'te the (Interim) Emergency Director of the status of the. repair work.
i i
EP-261. Rev. 0
- Page 4 of 5 VAW/ MPG /rgs 9.2.2 Fire and Damage Team Leader shall:
9.2.2.1 Report to the Technical Support Center or a; directed by the Emergency Director.
9.2.2.2 Obtain an update of the situation and relieve the Interim Fire and Damage Leader.
9.2.2.3 Direct and coordinate emergency repair operations as necessary.
9.2.2.4 Provide team members with periodic plant status changes including significant radiation and contamination problems which may affect the functions of the team.
9.2.2.5 Periodically update the Emergency Director of the status of the repair work. Ensure that the plant status board in the TSC is updated as necessary.
9.2.2.6 Provide additional personnel support if
' necessary. Use EP-276 Fire And Damage Team Phone List for additional qualified maintenance personnel.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 EP-401 Entry f or Emergency Repair, Operations , and Search and Rescue.
10.3 NUREG 0654, Criteri'a for Preparation and Evalu'ation Rev. 1 of' Radiological Emergency Response Plans and Preparedness in Support of Nuclear
'. Power Plants.
t 10.4 EP-276 Fire And Damage Team Phone List e
l l
i EP-261, Rev . 0 l
)
. Page 5 of 5 VAW/ MPG /.rgs l a
APPENDIX EP-261-1 Emergency Exp3sure Guidelines Projected Whole Body Thyroid Authorized Dose By Dose Function
- 1. Life Saving and 75 res* 375 rem Emergency **
Reduction of Injury Director ,
- 2. Operation of Equipment to Mitigate an 125 rem Emergency **
Emergency 25 rem
- Director
- 3. Protection of Health 5 rem 25 rem Emergency and Safety of the Public Director 10 CFR 20 10 CFR 20 Emergency
- 4. Other Emergency limits Director Activities limits Station Station
- 5. Re-eatry/ Recovery Activiti es Administra- Adminis-tive Guide- trative lines Guide-lines N/A
Reference:
EPA-520/1-75-001 Table 2.1
- Such expcaura shall be on a voluntary basis e
e I
e
[
l i
l l
l
EP-301 Rev. 0
- Page 1 of 3
,* W/ PG/rgs l .)N)
PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-301 OPERATING THE EVACUATION ALARM AND RIVER WARNING SYSTEM 1.0 PURPOSE The purpose of this procedure is to describe how to operate the Evacuation Alarm and River Warning System.
2.0 RESPONSIBILITIES 2.1 Shif t persennel calling site evacuation shall perform this procedure.
3.0 APPENDICES
. None 1 4.0 PREREQUISITES 4.1 440v see ll4-B-R-C-17 is energized for River Warning System 4.2 AC power 13L circuit 35 is energized for River . Warning
- System 4.3 125v DC 1PP01-07 and 1PPO4-05 are energized l
i 5.0 SPECIAL EQUIPMENT f
None 6.0 SYMPTOMS ,,
None l
[
f
. ._. . _ ~ . _ - _ - _ - - .
+
EP-301 Rev. 0 Page 2 of 3 VAW/ MPG /rgs 7.0 ACTION LEVEL 7.1 A site evacuation is ordered by the Emergency Director or Interim Emergency Director.
7.2 A test of the system is authorized.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 TO ACTIVATE THE EVACUATION ALARM:
9.1.1 Set the " SIREN TONE GEhERATOR" tone selector switch located on MCR Panel 10C650 to one of desired positions:
9.1.1.1 SIREN (harmonic tone ) (Preferred) 9.1.1.2 PULSE (high pitched pulses) (Alternate) 9.1.1.3 STEADY (steady tone) (Alternate) 9.1.2 Set the " EVACUATION ALARM AND RIVER WARNING SELECT" switch located on MCR Panel 10C650 to one of the desired positions and then push the selector switch in.
9.1.2.1 CONT 1 - Sounds alarm in Unit 1 primary containment only 9.1.2.1 CONT 2 - Sounds alarm in Unit 2 primary containment only f 9.1.2.3 PLANT ALARM - Sounds alarm in entire
' plant EVACUATION ALARM OVERRIDES THE PA SYSTEM.
9.1.3 Sound the alarm for approximately 30 seconds. ,
9.1.4 Return the " EVACUATION ALARM AND RIVER WARNING SELECT" switch located on MCR Panel 10C650 to the "OFF" position to silence the alarm.
(
ss . - . .
- s
' EP-301 Rev. O O
Page 3 of 3 I ', VAW/ MPG /rgs t
' y; 9.2 'TO ACTIVATE'THE RIVER WAPSING SYSTEM:
- 9. 2.1, Set the " EVACUATION ALARM AND RIVER WARNING SELECT" switch located on MCR Panel 10C650
~
ic
" to one of the desired positions and push the
~ ^
select'or switch in.
- 9. 2.1. 1 ' MIKE - To broadcast live , depress the
- RIVER BROADCAST MICROPHONE" s
- pushbutt,on and proceed to give message.
-s ' . -
9.2'.1.2 . TAPE e To broadcast pre-recorded mecsage automatically.
9.2.2 ~ Verify.that the message is being broadcasted
' by observing response on the " RIVER B.ROADCAST SPEAKER VOLUME MONITOR" located on' -
MfR Panel 10C650. .
9.2.3 Return the " EVACUATION ALARM AND RIVER
-WARNING SELECT" switch located on the MCR
' Panel 10C650 to the "OFF" position to end
'- - ~
the broadcast.
3 10.0 itEFERENCES,' _
10.1 Lim 6 rick Generating Station Emergency Plan FSAR Se$ tion 9.5.2
~
10.2 10.3 E-1364 Wiring / Connection Diagram Rev. 3 tvacuation Alarm and River Warning Systems s- ,
e 2
t
\
EP-303 Rev. O Page 1 of 3
~
/rgs g/M PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-303 LOCAL EVACUATION 1.0 PURPOSE The purpose of this procedure is to provide the steps necessary to be taken by site personnel in the event that a local evacuation is required
- due to a localized uncontrolled hazard.
2.0 RESPONSIBILITIES 2.1 Personnel in an affected area requiring local evacuation shall evacuate the area and notify the control room.
2.2 Shift Supervision shall announce the evacuation and initiate cleanup / recovery of a local area by performing the necessary steps in this procedure.
3.0 APPENDICES None 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None ,
E 9
-e + .ymy.-- - ,,,,,,.-,..,~.eg- - - - - r ~ ,y=,-
l I
O e EP-303 Rev. O I Page 2 ef 3 VAW/ MPG /rgs 6.0 SYMPTOMS' 6.1 An a'larm condition t..m a local area radiation monitor or continuous air monitor.
Observation of a localized, uncontrolled or unexpected release, leakage or spill of radioactive 6.2 material or toxic agent which represents a hazard to personnel in a local area.
6'.3 Other localized hazard such as a room flood, firs ,
or smoka 7.0 A_CTION LEVEL This procedure shall be iuplemented by shif t supervision when the symptoms' in section 6.0 of this procedure is, occur.
This procedure ia for localized areas only, that hazards contained in a room or single elevation within an e.1cl os ur e . Thi's precedute may not require action under EP-101 Classification of" Emergencies.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immedia'te Actions 9.1.1 Personnel in the affected area not directly 1,nvolved in controlling the ,
hazard shall evacuate to a safe area.
Notify the control room of the type and location of the hazard.
9.1.2 Shif t Supervision'sha11:
9.1.2.1 Upon receipt of information of a
' localized hazard or f rom control room indications, make'the following announcement over the P.A. system "This (is) (is not)All a drill. This (is)
(is not) a drill. personnel evacuate the (location of hazard) and assemble at (location of assembly area)! This (is)
(ie not) a drill. This (is) (is not) a drill."
, - ,-. ,.n. .- --
EP-303 Rev. 0 Page 3 of 3
- VAW/ MPG /rgs 9.1.2.2 Forform actions that shall contain the hazard in a localized area.
9.2 Follow-Up Actions 9.2.1 Shift Supervision shall:
9.2.1.1 Direct health physics in the case of
- radiation hazard or chemistry in the case of a toxic reagent hazard tot A. Determine the extent of the hazard.
B. Post and limit access to the area as required.
C. Ensure that all personnel have lef t the hazard area. >
D. Report back to shift supervision on status.
9.2.1.2 Take actions necessary to terminate or cleanup the hazard, if needed refer to the Preparedness Prevention and contingency Plan.
9.2.1.3 Log the problem and notify the Station Superintendent within an appropriate time frame.
9.2.1.4 If the problem cannot be contained, direct the evacuation of ccher areas or
- the site in accordance with the following procedures,. ,
EP-304 Partial Plant Evacuation EP-305 Site Evacuation
10.0 REFERENCES
10.1 Limerick Generating Station' Emergency Plan 10."2 EP-304 Partial Plant Evachation w 10.3 EP-305 Site Evacuation 10.4 Limsrick Generating Station Preparedness Prevention and Contingency Plan.
l l- '
) ,
EP-110 Rev. O Page 1 of 6 VAVfMP /mla n/n/dC7 PHILADELPHIA ELECTRIC COMPANY s'rf/
LIMERIOK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-ilO PERSONNaL ASSEMBLY AND ACCOUNTABILITY 1.0 PURPOSE The purpose of this procedure is to provide the steps necessary when personnel assembly and accountability of PEco personnel and contractors is reg. tired when an Alert )
or partial plant evacuation is declared.
This procedure does not apply to Unit 2 Bechtel and sub-contractor personnel since they will be assembled per Bechtel procedures. -
2.0 RESPONSIBILITIES .
2.1 PEco personnel'and contractorr shall report to designated Emergency Assembly Areas for purposes of accountability.
2.2 Emergency Assembly Area Coordinators shall perform an accountability check of personnel at the designated area and report missing persons to Security.
2.3 Security shall assemble a list of missing persons for the Emergency Director.
2.4 The Emergency Director shall direct the Personnel Saf ety Team Leader to activate the Search and -
Rescue Group to locate missing personnel.
3.0 APPENDICES 3.1 EP-llO-1, Emergency Assembly Areas 4.0 PREREQUISITES .
None
. EP-110 Rev. O Page 2 of 6 r, VAV/ MPG /mla 5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS none 7.0 ACTION LEVEL This procedure should be implemented whenever an Alert is declared and may be executed when an UnuLual Event is declared at the discretion of the Emergency Director.
5 After a site evacuation is declared, this procedure no longer applies . ,
8.0 PRECAUTIONS 8.1 Only the following personnel may authorize support personnel without Limerick badges access to the
. site at an Alert, Site or General Emergency.
8.1.1 Site Emergency coordinator 8.1.2 Emergency Director 8.1.3 Security Team Leader 9.0 PROCEDURE .
9.1 IMMEDIATE ACTIONS l 9 .1.' l PECO PERSORNEL AND CONTRACTORS shall:
9.1.1.1 Report to the area designated in Appendix EP-110-1, Emergency Assembly Areas, when the announcement for personnel assembly occurs. .
. ,,e . a n , ~ - . . .,n-. - -
, 'EP-110 Rev. O Page 3'of 6
. VAV/ MPG /mla
~
9.1.1.2 Check themselves for contamination if '
leaving a radiologically controlled area.
If contaminated, contact Health Physics at the Operations Support Center.
9.1.1.3 Report to the Emergency Assembly Area coordinator for purpose of accountability.
9.1.1.4 Await f urther instructions f rom the i Emergency Assembly Area Coordinator.
9.1.2 EMERGENCY AREA ASSEMBLY COORDINATORS shall:
9.1.2.1 Perform accountability of personnel. If personnel are unaccounted for, check with the Technical Support Center first for those in your group who may have reported to the Technical Support Center.for emergency response roles. -
9.1.2.2 Report to Security the names of those identified as missing, if any. If possible, report the last known location of th,e missing persons.
9.1.2.3 Await further instructions from the Emergency Director.
9.1.3 Security shall:
9.1.3.1 Contact the Emergency Assembly Areas that
, have not reported in within 15-30 minutes after the assembly announcement is made.
9.1.3.2 Inform Emergency Director or Interim Emergency Director of the accountability
. status within 30 minutes after the assembly announcement ic made.
9.1.3.3 Suspend access to the protected area except for those involved in Emergency Response Teams until accountability check is completed.
9.2 FOLLOW-UP ACTIONS ;
9.2.1 Emergency Director or Interim Emergency Director shall:
, . , , . - - . .. , - - , . . _ . . , . . - , . . - - - . . . . ..n. ,. . , , , , . , -- ,- -- ,
i EP-110 Rev. O Page 4'of 6
- VAV/ MPG /mla 9.2.1.1 Contact the Personnel Safety Team Leader to activate the search and Rescue Grouc if required to locate missing personnel.
9.2.1.2 Contact the Personnel Safety Team Leader 4 for status updates.
REFERENCES 1.0 Limerick Generating Station Emergency Plan e e a
I e
e 9
9 0
9
. , , , , . - -- w . - - - - . ___ - - - - - -
110 Rev. O
/cqn 5 o f 6 VAV/HPG/010 APPENDIX EP-110-1 EMERGENCY ASSEMBLY AREAS PRIMARY ASSEMBLY AREAS ALTERNATE ASSEMBLY AREAS GROUP AND TELEPilONE NUMBERS AND TELEPilONE NUMBERS ASSEMBLY AREA COORDINATOR (S)
T chnical Support Technical Support Center None Emergency Director Display Area Ext. Personnel Sa fety Team Leader Canter Sta f f: .
Ad min. Bldg. Senior llP TA/Techn kian IIP TechnElans Operations Support Center 2ND Floor, flPEC Area Ext. - Ext.
Plant Operators Operations Support Control Room Senior Rank ing l Ext. P.O., A.P.O., or A.O.
Auxillary Plant Center Operators Ext.
Admin Guard Station None Security Assistant 5:!curTty Guards Ex t. Alt Capta in of the Guard Norma 1 Working Office None Supervisors Bechte1 or Subcontractors in Restricted Area
~
e e
O 9
I 14 Pav .' O *
. cqs 6 o f 6 VAV/ MPG /stlo APPENDIX EP-110-1 EMERGENCY ASSEMBLY AREAS PRIMARY ASSEMBLY AREAS ALTERNATE ASSEMBLY AREAS GROUP AND TELEPilONE NUMBERS AND TELEPilONE NUMBERS Control Operators ASSEMBLY AREA COORDINATOR (S)
Control Room Sa fe Shutdown Panels Shift Superinten. lent Acalt. Control Ext. For Units 1 and 2 AIL: Shift Supervisor Opsrators Sh i f t Superviston (Only I f Control Room Sta -
not habitable)
Choolstry Cold Lab 217 ' E1. 2nd Floor Admin Supervisory Chemist or Technicians Ridg. Chemistry Office Chemist Ext.
PECO Field Engineers Field Eng. Office None Senior PECO Supervisory ~
Encorted Plant Gate 3 None Senior Ranking PECO Escort Violtors Adainistrative Normal Working Of fice None Ad mi n. Engineer or Sta f f and Unescorted in Admin Bldg. or Alternate Senior En.Jineer Visitors (individual Supervisors in the Admin Bldg. or Annex report unaccounted for personnel to the Admin Engineer or Alternate) 9 9
O
EP-208 Rev. 0 l
. Page 1 of 6 i V W/NPG/rgs
. 'y( / / /
PHILADELPHIA ELECTRIC COM?ANY
/ .i
./ t g R'lL D/
LIMERICK GENERATING STATION \,
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-209 SECURITY TEAM ACTIVATION 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the activation and conduct of operation for the Security Team.
2.0 RESPCNSIBILITIES 2.1 The Guard Sergeant or alternate shall assume the role of the Interim Security Team Leader and perform the steps of this procedure until relieved by the Security Team Leader.
2.2 The Security Team Leader shall relieve the Interim Security Team Leader and perform the steps of this procedure not completed by the Interim Security Team Leader.
3.0 APPENDICES 3.1 Appendix EP-208-1 Access Control Group Location 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None
~
6.0 SYMPTOMS None
EP-203 Rev. 0
', Page 2 of 6 ,
VAW/ MPG /rgs l 7.0 ACTION LEVEL This procedure shall be implemented when an Alert or higher classification is declared, a site evacuation is declared or at the discretion of the (Interim) Emergency Director.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 The Guard Sergeant shall:
9.1.1.1 Assume the role of the Interim Security Team Leader.
9.1.1.2 Call the Security Tara Leader and team members using EP-278 Security Team Phone List, if necessary.
9.1.1.3 Assign available personnel to functional groups as necessary and direct them to perform the appropriate sections of this procedure.
A. Access Control Group (9.2.2)
B. Personnel Accountability Group (9.2.3)
C. Plant Security Group (9.2.4) 9.2 Follow-Up Actions 9.2.1 The Security Team Leader shall:
9.2.1.1 Report to the Technical Support Center.
l' 9.2.1.2 Review the current status of the emergency l
and relieve the Interim Security Leader.
l 9.2.1.3 Ensure that the necessary groups are staffed l
and performing the appropriate sections of
' ~this procedure. Augment groups ~as necessary.
l
EP-209 Rev. 0 Page 3 of 6 VAW/ MPG /rgs 9.2.1.4 Advise the (Interim) Emergency Director concerning the need for off-site security personnel, if necessary. Use EP-278 Security Team Phone List for these off-site agencies.
9.2.1.5 Coordinate the actions of off-site security team personnel if their assistance is required.
9.2.1.6 Have a log maintained throughout the incident.
9.2.1.7 Keep the (Interim) Emergency Director updated on status of the team's activities.
9.2.2 The Access Control Group shall:
o 9.2.2.1 Station a guard at each of the following locations to limit access to the plant when an alert or higher event is declared and a site evacuation is not needed unless the access point is locked:
A. Technical Support Center Perscnnel Exit Area B. Admin Guard Station Personnel Exit Area C. Main Access Gate (Gate 1)
D. Back Access Gate (Post 10) 9.2.2.2 When a site evacuation is declared, station a guard at the following locations per EP-254 Vehicle and Evacuee Control Group to limit access and to direct traffic flow.
See Appendix EP-209-1 for map locations.
l A. Technical Support Center Personnel Exit l Area B. Admin Guard Station Personnel Exit Area C. North Parking Lot D. Post #3 E. Main Access Gate (Gate 1) ,,
F. Gate #2 G. Back Access Gate (Post 10) l i
4
'EP-208 Fev. 0
.Page 4 of 6 VAW/ MPG /rgs 9.2.2.3 When a site evacuation is declared, the guards posted at the Technical Support Center and Admin Guard Station Personnel Exit Area shall direct personnel to deposit
[. security badges in the buckets provided but to keep dosimetry. If the security computer is not operable, compile a list of the badge numbers of those evacuating as they are leaving.
9.2.3 The Personnel Accountability Group shall:
9.2.3.1 In the event of a site evacuation:
A. Obtain the security badges or badge list if the computer is not operable of evacuated personnal from the Access Control Group.
B. If the security computer is operable,
' card out' all of the security badges l and compile a list of personnel that are-l' onsite.
C. If the security computer is not t operable, determine the personnel onsite. A suggested method is by crossing out all those badge numbers on the evacuee list and badges not in use
! from the master badge list and visitor's list.
l D. Determine from the guards stationed at the North Parking Lot and Post #3 if any Bechtel/ Subcontractor personnel are unaccounted for.
l E. Compile a list of'Bechtel/ Subcontractor personnel missing and a list of all those in the protected area from steps B or C. Inform the (Interim) Emergency Director of unaccounted for personnel so that EP-252 Search and Rescue /First Aid can be implemented.
l F. Forward the list of unaccounted
! personnel to the Personnel Safety Team Leader.
I
~
-, - ,---,---e e, --,---mv ,m,,,-w,,,- ,- -
,wn-w,m,----p--,,-my7,,,n ,, ..,--r--- ---w-.-n--
d
--l l
l
- I SP-208 Rev. O Page 5 of 6 VAW/ MPG /rgs 9.2.3.2 When personnel are assembled in accordance with EP-110 Personnel Assembly and Accountability and with Bechtel Project Evacuation procedure, check with the Emsrgency Area Coordinators and security at the North Parking Lot and Post #3 15-30 minutes after assembly was called for any unaccounted for personnel and compile a list for the Personnel Safety Team Leader.
. 9.2.4 The Plant Security Group shall:
, . 9.2.4.1 Maintain plant security in accordance with emergency securi y procedures, and as directed by the (Interim) Emergency Director.
9.2.4.2 In the event of a Partial Plant Evacuation, assist personnel in the evacuation of affected areas. .
10.O REFERENCES 10.1 Limerick Generation Station Emergency Plan 10.2 Limerick Generating Station Security Plan and Procedures .
10.3 EP-278 Security Team Phone List 10.4 EP-254 Vehicle and Evacuee Control Group 10.5 EP-llO Personnel Assembly and Accountability t
f
E9-203 Rev. 0
'Page 6 of 6 VAW/ MPG /rgs
'"n'S"J^* . .
o *#n"" MAIN a' ACCESS...
cATE 4'SQO.......-.yi......._
GMEROGNCY 5dPPORT CENTlh
- ,p'f AA1A o g
GATC 2 's,%
- $ PRAY PC 44 %.
\-
s,
'- s NORTH 's.
PARKING -g LOT j COOLING T0wth COOLING 70 min WNai i l WNt! !
= .
TECHNICAL IWan' POST 3 I I PAAEINO t
TURuthL QWILDINQ$
UNif I ; UNIT I ,
J R E ACT0n' OLOGL d
018584 G E N.
03t564A GLh. .
i i
'C"Ef e n. -
BACK LONGVIEW ACCESS ROAD GATE' j APPCNDIX EP-20B-1 LOCAT!ON OF A00nSS CONTP.0L PCINTS I
i r
. , . - - - --.,..,y -- . , - . . , , . - . - . .
EP-221 Rev. O Page 1 of 4 VAW/ MPG / mla PHILADELPHIA ELECTRIC COMPANY / Y LIMERICK GENERATING STATION \
EMERGENCY PIAN IMPLEMENTING PROCEDURE EP-221 PERSONNEL DOSIMETRY, BIOASSAY, AND RESPIRATORY PROTECTION GROUP 1.0 P'URPOSE The purpose of this pretedure is to provide guidelines for the actions of the Personnel Dosimetry, Bioassay and Respiratory Protection Group.
o 2.0 RESPONSIBILITIES .
2.1 The Personnel Dosimetry, Bioassay and Respiratory -
Protection Group Leader shall direct the issuance of emergency dosimetry, respiratory protective equipment and direct the bioassay program by performing the necessary steps in this procedure.
3.0 APPENDICES None .
4.0 PREI'EQUISITES None .
4 5.0 SPECIAL EOdIPMENT l-None l .
i l .._
l
EP-221 Kev. O Page 2 of 4 VAW/ MPG /mla 6.0 SYMPTOMS None 7.O ACTION LEVEL The Personnel Dosirstry, Bioassay, and Respiratory Protection Group shall be activated during an emergency whenever there is a need for issuirig dosimetry, respiratory protective devices or for bicassay monitoring as determined by the Radiation Protection Team Leader.
8.0 PRECAUTIONS None 9.0 PROCEDURE-9.1 Immediate Actions 9.1.' 1 Personnel Dosimetry, Bioassay, and Respiratory Protection. Group Leader shall:
9.1.1.1 Report to the TSC and discuss the sit'uation with the Radiation Protection Team Leader.
WHEN LEAVING THE RESTRICTED AREA, PERSONNEL REMAINING ON SITE SHALL CARD OR SIGN OUT (IF THE SECURIT'l COMPUTER IS NOT AVAILABLE) BUT KEEP DOSIMETRY. ,
9.1.1.2 Assemble the necessary personnel in the i Whole Body Counting Room in the TSC for a briefing of the situation.
9.1.1.3 Direct the group to perform the following tasks as necessary.
9.1.1.4 Emergency Dosimetry Issuance A. Take the emer'gency dosimetry devices from storage to the Personnel Entry Area at the TSC.
. EP-221 Rsv. O Pace 3 of 4 l
VAQ/ MPG /mla l
i i
B. Coordinate with Security, issuing dosimetry to emergency team personnel and off-site emergency response teams (i.e., ambulance crews, fir e-fighting crews, etc.). in accordance with Health Physics Procedures.
C. Maintain a list of the personnel to whom dosimetric devices are distributed in accordance with Health Physics Procedures.
3.1.1.5 Personnel Bioassay A. Verify that the Whole Body Counter is operational and calibrated. If need be, follow Health Physics Procedures to start up and calibrate the system.
B. Verify that a supply of bioassay specimen containers is on hand., Obtain more containers from the storeroom if.
needed.
C. Perform Whole Body Counts or collect
, bioassay samples from these individuals who are directed to report by the Radiation Protection Ioader.
MONITOR BACKGROUND RADIATION LEVELS IN THE WHOLE BODY COUNTER AREA. " IF DOSE RATE EXCEEDS (LATER) MR/HR, THE COUNTER CANNOT BE USED.
D. Have all personnel entering the Whole Body Counter Room perform a thorou.gh
. frisk. If contamination greater than or -
equal to 500 cpm above background is found, have the person report to the Personnel Decon Area at the Radwaste l Enclosure 217' or at the Technical l Support Center. Contamination less than 500 cpm above background will be reduced to acceptable levels in the Whole Body Counter Room showerbefore entering the Whole Body Counter.
9.1.1.6 Respiratory Protection A. Perform quantitative fit hestsas needed.
,------,-,-r-, - - - - -*
,-- -. - , , , - . rww9
~. . _ - -. ~ - _ _- - . . .. . - . .__ . . -
, EP-221 Rev. O ~ ~
Page,4 of 4
~
VAW/ MPG /mla 9
B. Distribute respiratory protective eouipment in accordance with Health Physics Procedures.
- 9.2 Follow-up Actions 9.2.1 Personnel Dosimetry, Bioassay, and Respiratory Protection Group shall:
9.2.1.1 Emergency Dosimetry Issuance A. Establish a dosimetric device collection station in the TSC Guard House.
B. Arrange to have dosimetric devices processed in accordance with Health Physics Procedures.
9.2.1.2 Personnel Bioassay A. Have the bioassay samples analyzed.
B. Compare the results of the bioassay analysis with the most recent analysis performed on the person (if available) prior to the emergency. If internal contamination is identified, notify the Radiation Protection Team Leader of the situation.
9.2.1.3 Respiratory Protection A. Recover respiratory equipment and prc cess for re-use in accordance with Health Physics Procedures, as the
, situation permits. .
9.2.1.4 Repori status and results to the Radiation Protection Team Leiader.
t 4
10.0 REFERENCES
10.1 Limerick Generating Station' Emergency Plan 10.2 NUREG 0654 Criteria fer Pr'eparation and Evaluation of Rev. 1 Radio'egierl Emergency Response Plans in Suppo t of Nuclear Power Plants.
p --.w -
,,-,q,--- , -- ---m,----.,,-n..,a y , . , ,. - -. -- - - ,+ . - - - - , - ,~.-.me r, m.-vm-,a-.,- , , , - . -, ,..,.n -
~
EP-251 Rev. O
. , , Page 1 of 4 V/ G/mla a //)~ 7 PHILADELPHIA ELECTRIC COMPANY R'/ w LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE-k EP-251 PLANT SURVEY GROUP 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions of the Plant Survey Group.
2.0 RESPONSfBILITIES 2.1 The Plant Survey Group leader shall be responsible to direct the plant survey group squads by performing the steps in this procedure.
2.2 The Plant Survey Group Squads shall be responsible to conduct surveys as directed by the Plant Survey Group leader.
3.O APPENDICES .
3.1 EP-251-1, Emergency Exposure Guidelines 4.0 PREREQUISITES ,
~
None 5.0 SPECIAL EQUIPMENT I
l Plant Survey Kit 6.0 SYMPTOMS .
None i
9
^
EP-251 Rev. O q Page 2 of 4 VAV/ MPG /mla 7.0 AC* ION LEVEL 7.1 The Plant Survey Group shall be activated by the Personnel Safety Team leader when necessary.
8.0 PRECAUTIONS 8.1 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-251-1, Emergency Exposure Guidelines ,
t 8.2 Continuous coverage by Health Physics Technicians may be substituted for a Radiation Work Permit.
9.0 PROCEDURE 9.1 Immediate Actions -
9.1.1 The Plant Survey Group leader shall:
9.1.1.1 Report to the Operations Support Center (OSC) or other assembly area as directed by Personnel Safety Team Leader.
9.1.1.2 Discuss the situation with the Personnel Safety Team leader.
l 9.1.1.3 Form the necessary number of plant survey
- . squads from availabla. personnel. A squad j shall consist of two individuals at .least l one of which is a Health Physics Technician.
9.1.1.4 Discuss the situation with each squad, and
. direct them to specific locations in the pl ant '.
9.1.2 Plant Survey Squad members shall:
9.1.2.1 Report to the Plant Survey Group leader at the Operations Support Center or other assembly area as directed by Personnel~
Safety Team Leader.
l l 9.1.2.2 Take the necessary survey equipment from the i equipment located in the Operations Support Center or normal Health Physics stores .
9.1.2.3 Ensure that the survey equipment is working properly.and have the equipment on when traveling through the plant to observe l changes in radiation conditions.
I
EP-251 Rev. O Page 3 of 4 1 VAV/ MPG / mla ,
9.1.2.4 Ensure that direct reading dosimeters a e
' zeroed before leaving the Operations support Center.
9.2 Follow-up Actions 9.2.1 The Plant Survey Group leader shall:
9.2.1.1 Report results to the Personnel Safety Team leader.
i 9 2.1.2 Provide the plant survey squads with status updates as to changes in plant conditions.
9.2.1.3 Direct the plant survey squads to other locations as necessary.
^
9.2.1.4 Inform the Personnel Safety Team leader for the need of additional. personnel if.
necessary. .
9.2.2 Plant Survey Squad me'sbers shall:
9.2.2.1 Conduct surveys as directed by Plant Survey Group Leader, use the methods outlined in Health physics Procedures modified as necessary to minimize exposure to survey squads.
9.2.2.2 Report survey results to the Plant Survey Group leader.
l 9.2.2.3 Post creas, as necess'ary, to prevent the
- spread of contamination and accumulation of large doses of radiation to operating ~
personnel.'
9.2.2.4 Report to the Operations Support Center or l
other assembly area for further instructions from the Personnel Safety Team leader.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.1 NUREG 0654, criteria for Preparation and Evaluation of Rev. 1 Radiological Emergency Response Plans in support of nuclear power plants .
~ , . . . . . - . _ .
~ ~ EP-251. Rev. O
- Page 4 of 4 VAV/ MPG /mla APPESDIX EP 251-1 Emergency Exposure Guidelines Projected Whole Body Thyroid Authorized Function Dose Dose By
~
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Equipment to Mitigate an Emergency **
Emergency 25 rem
- 125 rem Director
- 4. Other Emergency lo era 20 10 CFR 20 Emergency Activities limits limits Director
- 5. Re-entry / Recovery Station Station Activities Administra- Administra- .
i tive Guide- tive Guide-lines lines N/A
Reference:
EPA-520/1-75-OO1 Tabl e 2.1
- Such exposure shall be on a voluntary basis 1
I l
f
9
. EP-252 Rev. 0
+
Page 1 of 12 VA G/rgs PHILADELPHIA ELECTRIC COMPANY M ^
LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-252 SEARCH AND RESCUE /FIRST AID 1.0 PURPOSE The purpose of this procedure is to define the requirements and the actions of the Search and Rescue /First Aid Group.
2.0 RESPONSIBILITIES 2.1 The Pers'onnel Saf ety Team Leader 'shall control the Search and Rescue /First Aid Group exposure and provide offsite medical support by performing the necessary steps in this procedure.
2.2 The Search and Rescue /First Aid Group Leader shall direct operations by performing the necessary steps in this procedure.
f l 2.3 The Search and. Rescue /First Aid Group members shall perform rescue operatious by performing the necessary steps in this procedure.
APPENDICES 3.0 3.1 EP 252-1 Emergency Exposure' Guidelines 3.2 EP 252-2 First Aid Equipment Locations 3.3 EP 252-3 Injured Personnel Report Form 3.4 EP-252-4 Medical Support Group Phone List -
4.0 PR" REQUISITES None
, - n ---- ---r - - ~--- - - wn,- -,
PP-252 Rev. O
. Page 2 of 12 VAW/ MPG /rgs 5.0 SPECIAL EQUIPMEN-5.1 First Aid Kit 6.0 SYMPTOMS 6.1 Missing personnel or personnel with injury recuiring first aid.
7.0 ACTION LEVEL 7.1 The Search and Rescue /First Aid Group is activated whenever personnel are known to be missing or in need of help.
8.0 PRECAUTIONS 8.1 Personnsi shall participate in search and rescue operations on a voluntary basis.
8.2 Proper radiological controls shall be followed as much as practicable during search and rescue operations.
Continuous coverage by Health Physics technician may be substituted for a Radiation Work Permit.
8.3 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-252-1 Emergency Exposure Guidelines .
. 8.4 Lif e-saving first ai'd treatment has priority over decontamination or treatment for radiation exposure.
8.5 Radiation exposure and group member contamination should be minimized as much as practical.
8.6 If gross external contamination is found, internal contamination should be suspected.
8.7 Any material removed from a contaminated person shall be recovered for potential use for isotopic analysis.
8.8 The Search and Rescue /First' Aid Group Leader will maintain contact with the Personnel Safety Team Leader at the designated assembly area.
- - . , , ~ . - , _ _
s .
EP-252 Rev. O Page 3 of 12 VAW/ MPG /rgs 8.9 If first aid team is unable to move an injured person
- due to the nature of the injury, assistance of local ambulance personnel may be utilized.
9.0 PROCEDURE l
9.1 IMMEDIATE ACTION.e ,
9.1.1 Personnel Safety Team Leader shall:
9.1.1.1 Select a qualified person at the OSC to be the Search and Rescue /First Aid Group Leader and to carry out Section 9.1.2 of this procedure.
9.1.1.2 Inform the Interim Emergency Director or the Emergency Director that search and' rescue /first aid groups have been formed and of their intentions to enter the plant for search and rescue operations. (Atteupt to locate missing perse.(s) by utilizing plant paging system just prior to actually dispatching the search and rescue group (s )) .
9.1.1.3 Obtain exposure limits f rom the Emergency Director. If later search and rescue operations are necessary, the Emergency Director may adjust the radiation exposure limits accordingly. If waiting for
. Emergency Director approval could endanger personnel, the search and rescue /first aid group leader may decide to remove injured person.
9.1.1.4 If offsite medical help is necessary, have
, the ambulance, hospital or physician contacted by using Appendix EP-252-4 Medical Support Groups Phone List. Always state the number of individuals involved, type of injury and if contamination is involved.
9.1.1.5 Notify security so that the offsite medical response group's access to the Restricted Area can be expedited, if necessary.
9.1.1.6 Recall the search a*.d rescue groups when search and rescue operations are no longer necessary.
. EP-252 Rev. O Page 4 cf 12 VAW/ MPG /rgs 9.1.2 Search and Rescue /First Aid Group Leader shall:
9.1.2.1 Select volunteers f rom available personnel to form search and rescue /first aid squads.
Each squad shall consist of at least three members; two must be qualified in first aid and one must be a health physics technician.
9.1.2.2 Ensure that each member has the necessary respiratory equipment, radsurvey equipment,
, anti-contamination clothing, and personal dosimetry. This material can be obtained from emergency survey kits at the OSC or from normal MP stocks. .
9.1.2.3 Discuss the situation with the Personnel ,
Safety Team Leader. Th'e following information should be obtained prior to performing search and re:. oe operations:
A. Numbsr of missing persons.
B. Name of individuals.
- c. Last' known location of individuals .
D. The job being worked. .
L E. Any significant plant conditions that may affect the search and any special
, instructions.
9.1.2.4 Ensure the. group is equipped with a first aid kit, or can get one enroute. See
, attached Appendix EP-252-2 for listing of l first aid equipment location in the plant.
9.1.'2. 5 Coordinate search and rescue /first aid squads to minimize duplication of effort and unnecessary radiation exposure.
9.1.2.6 Direct the groups to the last known location of the missing individual. If necessary, expand the search to adjacent areas. Ens ure most expeditious . routes available are taken to minimize team exposure.
l 9.1.2.7 Inform the Personnel Saftey Team Leader of the actions of the group and whenever the group locates any missing personnel, and the identity of located personnel.
1 5 '
EP-252 Rev. O Page 5 of 12 VAW/ MPG /rgs 9.1.2.9 Determine the extent of the injury and direct administration of first aid.
.9.1.2.9 _ Report to the Personnel Saf ety Team Leader the extent of the individual's injuries and recommend supplementary medical actions as necess ary (i .e . , hospitalization) . Complete
-Appendix EP 252-3 (if possible) and attach to injured person prior to transporting in ambul ance .
9.1.2.10 Direct the first aid group to transport the injured person to a site first aid facility, if prarti cable.
Locations:
A. Radwaste Building,' Elevation 217'.
B. In Admini'stration Building elevation 217'.
9.1.2.11 Report to the Personne.1 Safety Team Leader when the search and rescue /first aid group
. has' finished its task.
9.1.3 Search and' Rescue /First Aid Scuad Members shall: .
9.1.3.1 Perform a radiation and contamination survey of the person and subsequently the area.
9.1.3.2 ~ Transport the injur'ed person to a site first
. aid f acility if practicable. .
9.1.3.3 Perform the following if the injured person is contaminated.
A. Wear necessary anti-centamination clothing if practicable.
IF THE INJURY.IS SEVERE, IMMEDIATE
, MEDICAL TREATMENT IS OF THE HIGHEST l
PRIORITY AND. RADIOLOGICAL CONTROLS ARE
' SECONDARY.
l B. Adm. nister appropri ate fiist aid, being l careful to limit the spread of I contamination and limit personal l e xpos ure .
~
~~
. 1 EP-252 Rev. O Page 6 of 12 VAW/MPO/rgs C. IF INJURY IS NOT SEVERE, DECONTAMINATION SHALL BE ATTEMPTED.
D. Prepare the person f or transportation by covering the contaminated area with a protective wrap. Avoid excessive wrapping to prevent dehydration of the person.
IF THE INJURED PERSON IS GOING TO BE TRANSPORTED TO AN OFFSITE MEDICAL FACILITY, IT MAY NOT BE FEASIBLE TO BRING THE PERSON TO THE FIRST AID FACILITY, INSTEAD MOVE THE PERSON TO A SAFE PLACE WHICH IS EASILY ACCESSIBLE FOR THE TRANSFER TO A VEHICLE.
E. When transporting the victim to an offsite medical facility, a Health Physics Technician shall accompany the victim to assist the medical staff.
9.1.3.4 Recover any contaminated articles of clothing that may have been removed from the
. person for isotopic analysis.
9.2 Follow-Up Actions 9.2.1 Search and rescue group members shall
- f. 9.2.1.1 Report results of their actions to the Personnel Safety Team Leader.
9.2.1.2 Follow normal decontamination and disposal procedures when th~eir tasks are complete.
l l .
9.2.2 Personnel Safety Team Leader shall:
9.2.'2.1 Verify the victim's arrival at the medical facilities. ,
9.2.2.2 Inform the Emergency Director of results of search and rescue efforts.
l 9.2.2.3 Have the ilealth Physics technician accompanying victim to the hospital, call l the Personnel Safety Team Leader / hen l
l informed. by the hospital that his urvices are no. longer needed. With the concurrence of the Personnel Safety Team Leader he may procede to another assignment.
+ , , - - , . - , - - - . - , . - , _ - -
l l
EP-252 Rev. O l Page 7 of 12 ;
VAW/ MPG /rgs 9.2.2.4- ~ Arrange for inventory and restocking of .
first aid kits, if necessary.
.9. 2. 3 - The Emergency Director shall:
9.2.3.1 Have the Medical Director and Corporate
- Communications inf ormed of the identif y and condition of the victim (s ) .
- 10.O
REFERENCES:
10.1 Limerick Generatin'g Station Emergency Plan ,
10.2
- hTREG 0654, Criteris' f or Preparation and.
Rev.1 2 valuation of R'adiological Emergency Response Plans and Preparedness. In Support of Nuclear Power Pli'nts.'
, 'E.
I e
V I
t e
l l
1
, i t
i
\ e l
l
\
J - , . - , - - -
,.1 - --- , , . . , ,
' EP-252-1 Rev. 0 Page 8 of 12 VAW/ MPG /rgs APPENDIX EP 252-1 Emergency Exoosure Guldelines Projected Whole Body Thyroid Authorized y_ction Dose Dose g
- 1. Life Saving and Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Eculpment to Mitigate an Emergency 25 rem
- 125 rem Emergency **
, Directo.r
, Director
- 5. Re-entry / Recovery Station Station Administra- Adminis-Acti viti es . tive Guide- trative -
. lines Guide-lines N/A
^
Reference:
EPA-520/1-75-001 Table 2.1
- Such exposure shall be on a voluntary basis 4
i EP 252-2 Rev. O Page 9 of l'2 l
VAW/ MPG /rgs APPENDIX EP-214-2 FIRS *-AID EQUI PMEN LOCATIONS FIRST AID STRETCHERS KITS BLANKETS Unit 1 RX En=1. Elevator Stairwells
. Elev. 177' X X X Elev. 201' X X X Elev. 217' X X X Elev. 239' X X X ,
Elev. 253' X X X Elev. 233' X X X Elev. 313' X X X Elev. 351' X X X Elev. 352' X ,
X X Unit 2 RX Encl. Elevator Stairwells .
Elev. 177' X X X-Elev. 201' X X X Elev. 217' X X X Elev. 239' X X X Elev. 253' X X X Elev. 293' X X X Elev. 313' X X X Elev. 331' X X X Elev. 352' .
Turbine Encl. East & West Stairwells Elev. 200' X Elev. 217' X Elev. 239' X Elev. 269.' X .
Turbine Encl.
Equipment Hatch Elev. 217' X X e
e
O
~
EP 2$2-2 Rev. 0
,' Phge.10 of 12
/
~
VAW/ MPG /rgs FIRST AID STRETCHERS KITS BLANKETS Control Enclosure Elevator Stairwells X X X
. Elev. 190' Elev. 200' X X X Elev. 217' X X X Elev. 239' X X X Elev. 254' X X X
. Elev. 269' X X X Elev. 239' X X X Elev. 304' X X X
. Elev. 332' X X X Radwaste Encl. North Stairwell X X Elev. l's2' Elev. 191' X X Elev. 217'* ,
X X Elev. 237' X X Elev. 257' X -
X Cire. Water Pump House X 220 Switchyard Encl. X 500 Switchyard Encl'. X 20TE: 1/2 Mile Rays (Emergency Flashlights) Are Located Just Outside Door To Unit 2 Side of Main Control Room In -
Cabinet.
, 9 e
~-
EP'252-3, Rev. v Page 11 of 12 o VAW/ MPG /rge APPEhT!X EP 252-3 INJURT.D PERSONNEL REPORT FORM (PREPARE IN DUPLICATE)
Injured Person's Name Age Badge No.,Or Social Security No.
Male Female Type and Location of Injury ,
Radioactive Contamination Yes No Level
. Location Radiation Exposure Estimate where Did Injury occur l
- l.
- Prepared by First Aid Group Leader SIGNATURE l
Gro'p u Members ,
1 l If practicable forward original, with the person, to the site
.first aid facility or hospital as aopropriate.
l .
~
l l
i I
l'
- , , - . . . - -- . , , . . . . , . , - , - . - , - - - - - - - - - - , - . - n , ,~..,---,,c.,.
. - . , ----,-,-,.-,-r - - . . .
- EJ'252-4, Rev. 0 .
i, - Page 12 of 12
- VAW/ MPG /rgs APPENDIX EP 252-4 MEDICE SUPPORT GROUNONE LIST Local Physicians Of fi ce Home Dr. Charles W. Delp 367-2259 Dr. A'rthur Mann 327-7105 323-8593 Pottstown Memorial Medical Center (Contaminated or otherwise) 1600 E. High St.
Pottstown, PA 19464 ,
327-7000 Radiation Management Corporation (Serious Contamination /or Exposure
- I multiple contaminated personnel) l l
Dr. Roger E. Linneman Preferred Alternate i
1-243-2955 1-243-2950 (Beeper. 1-894-7776)
Ambulance Goodwill Ambulance Co. 326-0500
- 5erious Contamination / Exposure is:
Whole Body Exposure greater than 25 REM or skin exposure greater than 150 REM or extremity exposure greater than 375 l REM or contamination causing body contacted reading of greater than 1 MR/HR or suspected or actual inhalation cr ingestion of measurable quantities of radioactive material.
s EP-304 Rev. O 2
Page 1 of 4
)7AW/)tPG/rgs f f/
PHILADELPHIA ELECRIC COMPANY /\\,
LIMEPlCK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PRO'.2 DURE EP-304 PARTIAL "LANT EVACUATION 1.0 PURPOSE The purpose of this procedure is to define the actions to be performed in the event that a partial plant evacuation is required due to uncontrolled hazards in two or more operating areas.
2.0 RESPONSIBILITIES 2.1 Personnel in aff ected areas requiring evacuation shall evacuate the area and notify the control room.
2.2 The Interin Emergency Director or Emerg(ncy Director shall direct the partial plant evacuation by performing the appropriate steps in this procedure.
3.O APPENDICES None ,
4.0 PREREQUISITES ,
None
~5.O SPECIAL EQ'JIPMENT None a-+
, - , - ,-, , - - , ,n.,, - --- . -r, , w--ee..-, , - - - , - - --,-,- ---r.--,e---s - , - - r w-
a EP-304 Rev. O Page 2 of 4
"' VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 An increase in the area radiation monitors or 4
continuous air monitor indications to greater than alarm' levels in two or more large operating areas .
6.2 Radiation levels greater than 100 mR/hr within two or more large operating areas which normally experience less than 10 mR/hr.
6.3 Airborne radioactivity greater than 3N9 uCi/cc for an unidentified isotope , (except for noble gas activity) or 10 MPC for identified isotopes in restricted areas in two or more large operating areas.
6.4 Release, leakage or spill of a toxic reagent such that the concentration of chemical vapors makes the areas uninhabitable in two or more large operating areas.
6.5 Other hazards such as flood or fire affecting two or more large operating areas 7.0 ACTION LEVEL This procedure shall be implemented by the Interim Emergency Director or Emergency Director when the symptoms of section 6.0 of this procedure occur. Two or more large operating areas is defined as two or more elevations in a single enclosure or one elevation in two or more enclosures.
8.0 PRECAUTIONS ,
None l
9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 Personnel in the affected area not directly involved in controlling the hazard shal3 evacuate to a safe area. Notify the control room of the type and locat '.on of the hasard.
n 3
EP-304 Rev. 0 Page 3 of 4 VAW/ MPG /rgs
. 9.1.2 The (Interim) Emergency Director or Shift Supervision shall:
9.1.2.1 Upon receiving information from personnel in the field that a hazardous condition or from control room indications, evacuate the affected areas. Assemble personnel for purposes of accountability per procedure
, EP-110, Personnel Assembly and Acco;ntability by making the following announcement:
"This (is ) (is not) a drill.' This (is) (is not) a drill. This is a Partial Plant Evacuation. Evacuato (locations of hazard ) .
All personnel report to Emergency Assembly Areas. This (is) (is not) a drill. This (is) (is not) a drill."
. . 9.1.2.2 If the hazard has a potential to spread to Unit 2, evacuate construction personnel by notifying Bechtel Safety (4222') or Bechtel Security (4390). Direct them to call for either:
PARTIAL EVACUATION - ASSEMBLY AREA between the Main Construction Office and the change House.
TOTAL PROJECT EVACUATION - ASSEMBLY AREAS at the upper parking lot and Post #3.
i 3.2 Follow-Un Actions l
[ ,
9.2.1 The (Interim) Emergency Director shal1:
' 9.2.1.1 Evaluate the situation and if conditions worsan call for an evacuation of the site in accordance with procedure EP-305 Site Evacuation.
9.2.1.2 If the hazard can be contained and when conditions permit, perform recovery / cleanup operations in accordance with EP-401 Entry for Emergency Repair and Operations.
l l
a.
EP-3 4 Rev. O Page 4 of 4 VAW/ MPG /rgs
~
10.0 REFERENCES
. 10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654 Criteria for Preparation and Rev. 1 Evaluation of Radiological Emergency Response Plans
- - and Preparedness in Support of Nuclear Power Plants 10.3 EP-110 Personnel Assembly and Accountability 10.4 EP-305 Site Evacuation 10.5 Bechtel Evacuation Procedures 10.6 EP-401 Entry for Emergency Repair and Operations e
G 9
' e l
e S
6
- - - - _ . - - . - - , . - , - .._ , . _m-- - - . . .-- y---
EP-305 Rev. O b Pace 1 of 4 VA0/ MPG /rgs PHILADELPHIA ELECTRIC COMPANY v // g LIMERICK GENERATING STATION \
EMERGENCY PLAN IMPLEMENTING PROCEDURE
~
EP-305 SITE EVACUATION 1.0 PURPOSE The purpose of this procedure is to define the actions to be performed if a site evacuation is required.
2.0 RESPONSIBILITIES 2.1 The Emergency Director or Interim Emergency Director shall direct the evacuation of the site by performing the necessary steps in this procedure.
2.2 Security shall perform ac' countability of personnel during the evacuation.
2.3 Bechtel/Subcontracter personnel shall evacuate in accordance with Bechtel procedures.
2.4 Non-essential Unit 1 personnel shall exit through the security areas and assemble at Post #3 prior to leaving the site.
< 3.0 APPENDICES l ', . None l 4.0 PREREQUISITES l
None l
I 5.0 SPECIAL EQUIPMENT I None ,
l l
I t
EP-305 Rev. O
.* Page 2 of 4 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 General Emergency has been declared.
6.2 An actual or potential release exceeding that specified as an Alert or Site Emergency levels in EP-101 Classifications of Emergencies.
6.3 Major toxic or hazardous gas release.
7.0 ACTION LEVEL This procedure shall be implemented when a symptom of section 6.0 occurs or at the discretion of the Emergency Director or Interim Emergency Director.
o 8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 Emergency Director or Interim Emergency Director shall:
9.1.1.1 Notify security that a site evacuation is being initiated and to carry out applicable security procedures.
3.1.1.2 Implement the evacuation of the information
. center in accordance with EP-306 Evacuation of the Information Center. (4256 or 495-6767).
9.1.1.s For an actual or potential adverse radiological condition, inform the Personnel Safety Team Leader and direct him to prepare for a site evacuation in accordance with EP-254 Vehicle And Evacuee Control Group.
9.1.1.4 . Inform Bechtel Safety (4222) that a site evacuation is being called.
.EP-305 Rev. 0
.Page 3 of 4
, VAW/ MPG /rgs 9.1.1.5 Select the Assembly Areas and Unit 1 exit points from the following:
Assembly Areas Unit 1 Exit Points Upper Parking Lot and Post 3 TSC and Admin Bldg Day shift Afternoon Shift Upper Parking Lot and Post 3 Admin Bldg Admin Bldg Night Shift Post 3 9.1.1.6 Direct the activation of the alarm in accordance with EP-301 Operating the Evacuation Alarm and River Warning System.
9.1.1.7 When the Personnel Safety Team leader is ready if needed per step 9.1.1.3, announce a site evacuation as follows:
" ATTENTION ALL PERSONNEL. THIS (IS)(IS NCT)
A DRILL. THIS (IS)(IS NOT) A DRILL. THIS IS A SITE EVACUATION. EMERGENCY TEAMS REPORT TO DESIGNATED AREAS.
~
NON-ESSENTIAL UNIT 1 PERSONNEL EXIT THROUGH THE (TSC)
(AND) (ADMIN BUILDING). PERSONNEL ASSEMBLE AT THE (UPPER PARKING LOT) (AND) (POST 3).
THIS (IS)(IS NOT)-A DRILL. THIS (IS)(IS NOT) A DRILL."
9.1.1.8 After the alarm has stopped, repeat steps 9.1.1.6 and 9.1.1.7.
9.1.1.9 Direct the workers at the RMC facility on Fricks Lock Road to evacuate. (326-9662).
9.2 Follow-Up Actions 9.2.1 Security shall:
9.2.1.1 Perform accountability of personnel in accordance with EP-209 Security Team Activation.
9.2.1.2 Inform the Emergency Director or Interim Emergency Director of unaccounted for personnel.
i i .
EP-305 Rev. 0 Page 4 of 4 VAW/ MPG /rgs
' 9.2.2 Emergency Director or Interim Emergency Director shall:
9.2.2.1 Direct the Personnel Safety Team Leader to initiate search and rescue operations for any unaccounted for personnel in accordance with EP-252 Search & Rescue /First Aid.
9.2.3 Bechtel/ Subcontractor Personnel shall:
9.2.3.1 Evacuate in accordance with Bechtel procedures.
9.2.4 Non-Essential Unit 1 personnel shall:
9.2.4.1 Exit the protected area through the Admin Guard House or Technical Support Center by carding out but retaining dosimetry unless otherwise instructed.
9.2.4.2 Report to the Post 43 area for evacuation instructions f rom Security.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation of Rev. 1 Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
i j 10.3 EP-252 Search and Rescue /First Aid 1
10.4 EP-101 Classification of Emergencies 10.5 EP-254 Vehicle And Evacuee Control Group 10.6 EP-30'l Operating the Evacuation Alarm and River Warning System 10.7 EP-306 Evacuation of the Information Center i
\
EP-307 Rev. O 4
Page 1 of 3 VAV/ /mla f
PHILADELPHIA ELECTRIC COMP ANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCED'JRE EP-307 RECEPTION AND ORIENTATION OF SUPPORT PERSONNEL 1.0 PURPOSE This procedure defines the actions to be taken to receive and train those support personnel who will be coming on site to respond to an emergency.
2.0 RESPONSIBILITIES 2.1 The Planning and Scheduling Coordinator shall direct the reception and orientation of support personnel by performing the necessary steps in this procedure.
2.2 Personnel from the Nuclear Training Section or their contractors shall train the support personnel by
, performing the necessary steps in this procedure.
3.0 APPENDICES None
~
440 PREREQUISI'"ES ,
4.1 1..srgency Support Center or other reception area is l ac '.i vated .
4.2 Off-site personnel needed for assistance and arriving at the reception area.
5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS
= -. - -
EP-307 Rev. O
. Page 2 of 3
.. I- VAV/ MPG /mla 6.0 SYMPTOMS None 7.0 ACTION LEVEL This procedure shall be implemented when the arrival of off-site support personnel requested by the Philadelphia Electric Company is anticipated and the Entergency Support Center or other reception area is activated.
8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 Immediate Actions 9.1.1 Planning and Scheduling Coordinator shall:
9.1.1.1 Direct the Security Team Leader to assign a Security Team Member to report to the Emergency Support Center or other designated area to issue security badges in accordance with security procedures.
9.1.1.2 Direct the Radiation Protection Team Leader to assign a Personnel Dosimetry, Bioassay, Respiratory Protection Group Member t'o report to the Emergency support Center or other designated area and issue dosimetry in accordance with Health Physics procedures.
9.1.1.3 Direct Training personnel through the Training Coordinator to report to the Emergency Support Center. ,
9.2 Follow-up Actions ,
9.2.1 Training personne,1 shall:
9.2.1.1 Request f rom the Planning and Scheduling Coordinator information regarding the team or staff e.o which the Support personnel are to report.
, . - - - - - , - - - - - - - - - - w ~ - -
~
EP-307 Rev. O'
. Page 3 of 3 "T VAV/ MPG /mla
9.2.1.2 Recuest from the Planning and Scheduling Coordit._ ' nf ormation regarding the pl ant status.
9.2.1.3 Assemble personnel in the classroom and i provide them with the following information: i A. Basic description of the plant status .
B. Work shift hours they will be assigned to.
C. Arrangements for hotels, meals and
- transportation.
D. Person to whom they are to report.
9.2.1.4 With the same group conduct a General Employee Training Class. Also, if necessary, conduct a General Respiratory Training Class and Respiratory. Fit" Test.
9.2.1.5 conduct training sessions on special topics as necessary such as use of potassium iod' de tablets , evacuation plans , etc.
9.2.1.6 Contact appropriate Station personnel assigned the responsibility for supervising the support personnel. Request j authorization to release personnel to these Station personnel and have them meet the support personnel at the entrancs of the Technical Support Center, if activated or
.- the Administration Building Guard Station.
9.2.2 Planning and Scheduling Coordinator shall:
9.2.2.1 Inform the Site Emergency Coordinator and Emergency Director when the designated Support personnel have been properly indoctrinated and trained and are ready for work in the plant or on the site.
REFERENCES ~
10.1 Limerick Generating Station' Emergency Plan I
l
O '
EP-312 Rev. 0 Page 1 of 4 VAW. MPG /rgs PHILADELPHIA ELECTRIC COMPANY b, j /
~
p.
t Ll$.5 LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-312 RADIOACTIVE LIQUID RELEASE 1.0 PURPOSE The purpose of this procedure is to provide guidelines for the actions to be taken when an uncontrolled licuid release of radioactive material occurs.
2.0 RESPONSIBILITIES 2.1 The (Interim) Emergency Director shall direct the steps necessary to terminate the liquid release and evaluate the' consequences of the release performed.
2.2 The Site Emergency Coordinator, if activated, or (Interim) Emergency Director shall direct the follow-up actions of notification of downstream water users and river sampling, if they are required.
l l
3.0 APPENDICES None 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None
ir ; -
, EP-312 Rev. O Page 2 of 4 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 An actual or suspected liquid release of radioactive material with a concentration greater than 1.5N5 uCi/cc (500 times the maximum MPC for any unidentified isotope in water).
6.2 Radwaste discharge radiation monitor exceeds alar &
setpoint of 1.4N4 uCi/cc.
t 7.0 AC'" ION LEVEL 7.1 This procedure shall be implemented when a liquid release occurs exceeding the criteria in section 6.0.
8.0 PRECAUTIONS None
- 9. 0 , PROCEDURE 9.1 Immediate Actio3s 9.1.1 The (Interim) Emergency Director shall:
9.1.1.1 Direct the immediate steps necessary to terminate the discharge to the river.
9.1.1.2 Direct the Chemistry Sampling and Analysis Team Leader to initiate sampling of the blowdown line in accordance with EP-236, Obtaining Blowdown Line Water Samples Following Radioactive Liquid Release After Accident Conditions, or to sample the river just downstream of the liquid discharge.
9.1.1.3 Direct the Dose Assessment Team Leader to estimate dose projections from the ingestion of drinking water and fish in accordance with EP-318, Liquid Release Dose Calculation Method for Drinking Water and EP-319, Fish
. Ingestion Pathway Dose Calculation.
EP-312 Rev. 0
- Page 3 of 4 VAW/ MPG /rgs 9.2 Follow-Up Actions 9.2.1 The Site Emergency Coordinator, if activated or (Interim) Emergency Director shall:
9.2.1.1 Based on results cf estimated dose projections for downstream water users and fish ingestion, have the Department of Environmental Resources notified.
A. 717-787-2121 B. 717-787-6800 C. 215-631-2400 (Regional Office) 9.2.1.2 If requested by the Department of Environmental Resources, direct the notification of the downstream domestic water users in EP-287 Nearby Public and Industrial Users of Downstream Waters.
9.2.1.3 If necessary, direct the Environmental Sampling Coordinator if activated, or Chemistry Sampling And Analysis Team Leader to have the river water near the intake for the following water companies at the appropriate time based on the Transit Time for that location.
The Transit Time is the time required for the material released to reach the location of interest.
Location Transit Time (hrs)
! A. Citizens Utilities Home 1.5 Water Company-Royersford B. Phoenixville Water 10 1
C. Philadelphia Suburban 16 Water D. Norristown Water 27 j E. Philadelphia Belmont Water 50 i
9.2.1.4 Direct that a log be kept for all samples taken.
l
EP-312 Rev. 0
.Page 4 of 4 VAW/ MPG /rgs
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 EP-236 Obtaining Blowdown Line Water Samples Following Radioactive Liquid Release After Accident Conditions 10.3 EP-318 f.iquid Release Dose Calculation Method For Drink.ng Water 10.'4 EP-319 Fish Ingestion Pathway Dose Calculation 10.5' EP-287 Nearb-' Public And Industrial Users Of Downstream Waters 10.6 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents a
10.7 10CFR Part 20 Appendix B l
l 1
l l-
4
'- EP-313 Rev. O Page 1 of 8 VAW/ MPG /rgs 4 ,.
PHILADELPHIA ELECTRIC COMPANY ;- /
'If0 ~
^
LIMERICK GENERATING STATION '
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-313 DISTRIBUTION OF THYROID BLOCKING TABLETS 1.0 PURPOSE Tha purpose of this procedure is to provide guidelines for the administration of potassium iodide (KI) to on-site personnel performing a necessary TAS for use as a thyroid blocking agent to provide protection against airborne.
radioiodine.
2.0 RESPONSIBILITIES 2.1 The Radiation Protection Team Leader shall determine if potassium todide is required and direct the administration of the tablets by performing the necessary steps in this procedure.
2.2 The Personnel Dosimetry, Bioassay and Respiratory
- Protection Group Leader shall administer the potassium iodide tablets by performing the necessary steps in this procedure.
L l
3.0 APPENDICES l
3.1 EP-313-1 Potassium Iodide Work' Sheet l
l 3.2 EP-313-2 Potassium Iodide Administration Record Form 3.3 EP-313-3 Potassium Iodide Consent Form 3.4 EP-313-4 Instruction And Record Sheet For Persons Receiving KI 4.0 PREREQUISITES None -
. EP-313 Rev. 0
. Page 2 of 8 VAW/ MPG /rgs 5.0 SPECIAL EQUIPMENT 5.1 Potassium Iodide tablets not beyond the expiration date.
6.0 SYMPTOMS 6.1 An actual or potential thyroid dose equal to or greater than 10 REM.
7.0 ACTION LEVEL This procedure shall be implemented by the Radiation Protection Team Leader when an actual or potential thyroid dose is equal to or greater than 10 REM for any individual.
8.0 PRECAUTIONS 8.1 The taking of potassium iodide (KI) tablets is voluntary for each individual involved.
8.2 Personnel having allergic reactions to iodine should be administered potassium iodide only if absolutely necessary.
8.3 Prior to administering potassium iodide, ensure that l
the tablets are not beyond the expiration date.
~
- l. 8.4 All persons using potassium iodide should be familiar with the following possible side ef f ects and report any noticed side effects to Radiation Protection Team Leader.
8.4.1 Skin rashes 8.4.2 Swelling of parotid glands (like mumps) l 8.4.3 Metallic taste in mouth i 8.4.4 Burning mouth and threat l
l 8.4.5 Sore teeth and gums -
i 9.4.6 Symptoms of a head cold 9.4.7 Gastric upset l
I l
r - -
, . - . . - - . . -,,-r . .-- , - , - . , . - - . , . . . . , . - -- - . - .
.o r
EP-313 Rev. 0
. Page 3 of 3 VAW/ MPG /rgs
- 8.4.8 Diarrhea 9.0 - PROCEDURE 9.1 Immediate Actions 9.1.1 Radiation Protection Team Leader shall
9.1.1.1 Determine the need for administering potassium iodide by completing Appendix EP-313-1 Potassium Iodide Worksheet for each individual needed to perform the task.
9.1.1.2 Discuss with the (Interim) Emergency Director that potassium iodide is needed and obtain his concurrence prior to the administration of the tablets.
9.1.1.3 Enter the names of each individual on Appendix EP-313-2 and direct the Personnel Dosimetry, Bioassay and Respiratory Protection Group Leader to administer the tablets per section 9.2.1 of this procedure.
9.2 Follow-Up Actions 9.2.1 The Personnel Dosimetry, Bioassay and Respiratory Protection Group Leader shall:
9.2.1.1 When directed by the Radiation Protection Team Leader, assemble the personnel to be treated at the Technical Support Center or other area and acquire an adequate supply of tablets from the Medical Facility or Decon Area in Radwaste.
9.2.1.2 Discuss with personnel the possible side effects of potassium iodide and that taking the tablets is voluntary. Determine if any personnel are aware of an allergy to iodine.
If an individual is allergic, discuss the situation with the Radiation Protection Team Leader.
9.2.1.3 Have each individual sign a copy of Appendix EP-3'.3-3 Potassium Iodide Consent Form,
.unless one is already on file. ~
EP-313 Rev. 0 Page 4 of 8 VAW/ MPG /rgs 9.2.1.4 Administer to personnel who already have been exposed to radiciodine first, preferably within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of exposure. The recommended dosage is 130 mg potassium iodide (100 mg iodide) per day for a minimum of three days but preferably 10 consecutive days.
9.2.1.5 Provide each individual receiving KI with a copy of Appendix EP-313-4 Instruction And Record Sheet For Persons Receiving KI and instruct them to report back each day for follow-up dosages. This form is for the
. individuals information only and is not needed to receive additional dosages.
9.2.1.6 Complete the information reauired for each person on Appencix EP-313-2 Potassium Iodide Administration Record Form. Use this information to administer follow-up dosages.
9.2.1.7 Inform the Radiation Protection Team Leader when completed.
9.2.2 Radiation Protection Team Leader shall:
9.2.2.1 Notify the Medi~ cal Director and Emergency Director of all persons who received potassium iodide.
9.2.2.2 Ensure that the potassium iodide is administered in the proper dosage and for the proper number of dessa.
i l
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan - Section l 6.4.2.3 l
l 10.2 NUREG 0654 Criteria for Preparation and Evaluation j Rev. 1 of Radiological Emergency Response l Plans and Preparedness in Support
! of Nuclear Power Plants 10.3 Reg. Guide 1.109 Calculation of Annual Doses to Man Rev. 1 from Routine Releases of Reactor Effluents for the Purpose of f Evaluating Compliance with l
I l
l i - .
EP-313 Rev. 0 Page 5 of 8 VAW/ MPG /rgs APPENDIX EP-313-1 POTASSIUM IODIDE WORK SHEET Date: Time:
Name:
Badge Numb.er Area To Be Entered:
I-131 Concentration (uCi/ccT TE KEYected Area:
Respiratory Equipment (Check one)
TYPE PROTECTION FACTOR (PF) ~
Air Purifying 50 __
Atmosphere Supplying 2000 SCBA 10,000 None 1 Time Needed To Complete Task: Hours i
Previous Thyroid Dose Accumulation During Emergency: REM Perform Calculation:
Total Tnyroid Dose = 1.361P6 x Concentration I-131 x Task Time x 1 (REM) uCi_ (Hours) FF--
+ Previous Thyroid Dose (REM)
Total Thyroid Dose = Rem If Dose equals or is greater than 10 Rem, recommend administration of potassium iodide. ,
I-t f
I i
l r
e-
- 4 e
9 C to e '
7
. eW W
> ON e
.e e E e C. D E <
m C3 % LC
- C3 % l m g,,
g ce> - _i 6
l i 65 _ _IW - ._ _
i l ._ __ --- LL_ _ _ _ - _1_ i C.
g i i
_L__L- 1 -- - ___ __ __L-- ____ _ - -
1 I i
6 _l L .
_ ._ _ _ - - _ L --
_ ___- _L_ - - _-
- 1. _ _ _ I
___ _L_L '
_u _ _ _ __ _ __ _ __ _m_ _L_ _
l I
_L____ _ _ --_ __ _ _ _ _ __ __ _ _ _ _ _ __
_ =
r C - -
= L.- --- L - - - -- - --- - - L L- -
A M ts:
C E-
-_L m 4 -- - - ___ __ _ _ _ _ -_ - _ _
__?
C C l O I I J W I I L-_
t 6
g - __
-- 6 - _ __ -- - - _ __ _ - -- ___
- Z NC LL i m __ _ _ _ _ _ _- __ ____ _ _ -- _ _. - - -
M E-
-4 mE
- p _ 6 -
CL tt)
Es: w 2
xw _ _ __-- =L -_ _ _ _ _ _ _ _ - _ _ _ _ _ ___
-E >
CC 2 T :. < <
W CL C. If 3*
CL C C
<w U L. 1--
l C _ - - - - --- - - -- -_ - - - _ - -- - - - L C
w e.
- l. M i v:
< 'E
(-=
w I.
2 e
, C i
l b
' .Q.
d' CC o m W
t r c
2 I I
Q__ _ __
, EP-313 Rev. O Page 7 of 9 VAW/ MPG /rgs APPENDIX EP-313-3 POTASSIUM IODIDE CONSENT FORM I volunteer to receive 130 milligrams per day for the next 10 days of the thyroid blocking agent potassium iodide. I have been informed by a representative of PECo that this drug will block the absorption of radio-iodine by my thyroid and thereby reduce the exposure to radiation of the thyroidi that potassium does not reduce the uptake of other radioactive materials by the body; nor, does it provide prot.ection against exposure from. external radiation. I also understand that there may be some side effects upon taking this drug.
Signature i Date l
l t
1
r EP-313 Rev'. 0
, o Page 8 of 3 VAW/ MPG /rgs APPENUTX'EP-313-4 INSTRUCTION AND RECORD SHEET FOR PERSONS RECEIVING KI Name Badge No.
CAUTION IF YOU FEEL SICK, REPORT IMMEDIATELY TO THE PERSONNEL
- DOSIMETRY, BIOASSAY AND RESPIRATORY PROTECTION GROUP LEADER, You have just received 130 mgs. of the thyroid blocking agent KI.
In order to be most effective you should receive an additional nine (9) doses over the next 9 days. Each day for the nex,t 9 days, take this form and report to the for a thyroid count and another KI Pill.
130 mg KI Tablet Thyroid Count Results Administered Date (Date. Time. Initials) (Date, Time, Initials) 3.
]
4.
5.
6.
- 7. ,
- 8. ---
9,
~
10.
.- - - _ . _ _ - . -- -- - . - . .~.
- EP-318 Rev. 0 .
Page l'of 8
- VA fMPG/rgs s/.4/)3 PHILADELPHIA ELECTRIC COMPANY Y' / ..
LIMERICK GENERATING STATION ,
EMERGENCY PLAN IMPLEMENTING PROCEDURE l EP-318 LIQUID RELEASE DOSE CALCULATIONS METHOD FOR DRINKING WATER t
1.0 PURPOSE The purpose of this procedure is to provide the calculation method for estimates of population exposure due to the ingestion of drinking water at various locations downstream
. of the plant.
g 2.0 RESPONSIBILITIES -
None
- 3.0 APPENDICES 3.1 EP-318-1 Citizen Utilities Home Water Company Intake 3.2 EP-318-2 Phoenixville Water Intake 3.3 EP-318-3 Philadelphia Suburban Water Company Intake 3.4 EP-319-4 Norristown Water Intake 3.5 EP-318-5 Philadelphia Belmont Water Intake 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None i
1 - . .
EP-318 Rev. 0
. Page 2 of 9 VAW/ MPG /rgs 6.0 SYMPTOMS 6.1 An actual or potential liauid release of radioactive meterial into the Schuylkill River.
7.0, ACTION LEVEL 7.1 This procedure shall be implemented when the criterion
- of s ection 6.0 is met.
8.0 PRECAUTIONS None i
9.0 PROCEDURE 9.1 The following assumptions were utilized in this
- calculation:
9.1.1 The Dose Conversion Factor is based on the most limiting group (adult, teen, child, infant) using dose factors and consumption rates in Reg. Guide 1.109.
Adult 730 1/yr Teen 510 1/yr
~
Child 510 1/yr Infant 330 1/yr 9.1.2 The Decay Factor is based on the decay of the isotope over the transit time plus 12
. hours (time to reach the population via water system per Reg. Guide 1.109).
E
l
- 1 EP-318 Rev. 0
. Page 3 of 3
. VAW/ MPG /rgs 9.1.3 The total dose commitment is the dose which an individual would receive aftir drinking water with the radionuelides present at the ,
concentrations calculated to exist at the l entrance to the water plant for a period equal to the duration of the release. Fo r example, if the release lasted 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the individual is postulated to consume 1/2 of his average daily water intake at the diluted concentrations.
~
9.2 Obtain grab sample results on the concentration of Co-60, I-131, Cs-134 and Cs-137 released, from the Chemistry sampling and Analysis Team Leader.
9.3 For each location of interest, enter the concentration of Co-60. I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours"on the appropriate appendix.
If *he sample was taken prior to entering the Cooling Toser Blowdown Line, a diluted concentration must be determined by the following calculation:
Concentration [uci\ " concentration Release rate to Blowdown L.no Released \ci / uCi cc Blowdown line flow rate 9.4 Perform the calculation in each appendix for each location of interest to estimate the dose in millirem for the liver, whole body and thyroid.
9.5 Report results to the Dose Assessment Team Leader.
10.0 REFERENCES
10.1 EROL 2.1.3.6 Surface Water Use 10.2 EROL.S.2.4.1 Liquid Pathways
- 10.3 EROL Appendix 5.2A Radiological Dose Model-Liquid i
Effluents 10.4 Reg. Guide 1.109 Calculation Of Annual Doses To Rev. 1 Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR F rt 50, Appendix I ,
t t
l l l
I 1 ;) i Ill l li
. )
R -
n .
(
O9s g ,
.fr e
s vs o/ o G D 4P1 t =
8 e/
1 qW 3 aA
- PV P _
E E
K
- A r
r t
I Y
N ,-
A P_
t f
O = X C +
R r gr E yo 8 T at no it 1
A cc 0 5 0 0 1 Wea 9 xc 0 DF 1 1 1 ia E MF M
O X l
I X S )
E - s I
T n r I o h
(
L i I t T a n
)
1 rc eo tc si N n/
E el at Z cC ea l r s
I nu eu l T o RD a I C i C t X X i n
I c
1 r c r
- h /
8 /i e 1 R C v 3 mu ~
i Rr P o E n lt o l c X i 5 4 4 4 ia I s P P P P kF D rr 1 3 4 1 0 2 l 8 N eo 6 9 0 0 2 6 0 3 4 ye 4 E evt 0 5 5 0 . 9 uq P snc 4 9 1 7 5 2 1 2 5 ha P ooa cs SI l l A _ D C F ,,
d y 1
i i r e r e o r e r e o<
e l y e l y r e l g e l y B d v ol v ol y v oi v od i
- t. h e i ha h t. ha 1, ho r e o _
I Wn L WB T i WH I WB e l r :
v o y e i h h t L W 1 a
- D 3'
Cjoo N 'l" N a e j/ s} 0 llfl
_ )
. R i m O9s g (
L . .f r e vo/ s s G o 5P D
_ M H e/ =
gW I
3 aA
- PV P
E a..
= X
+
r yo qr 8 E cc at no 1 0 2 0 0 it 1 K ea 9 xc 0 A DF 1 1 1 ia T MF N
I X X R
E T )
A s W n r o h i (
E.
i, t T a I rc n V tc eo X n/ si I ei at NcC E nu ea 1 r G o esh I
I C RT P
X X
c 2 r c
. - h / r 8 / i e 1 R C v 3 m u .
i
- Rr P o E n lt o l c X i 5 4 4 4 ia I s P P P P kF D rr 1 3 4 l 0 2 l 0
- N E evt eo 6 9 9 0 2 6 O.
3 4 ye uq 0 5 5 0 . . 9 1 P snc 4 9 1 7 5 2 1 2 5 ha P
A DCF ooa cs Sf i l
r y i 1 r e r e o r e r e o' e l v e l y r e l v e l y B 1 v oi v v ol y v oi v og l h o'
- i. he t. h i. ho i. hg r e o I WB f Wfl t
' f WB I Wg e l r :
v o y e
- i. h h t 7 W T h T
@ gaeH 2~ 0 $Ymo
I l f1 i li 1l
) l l llIIll
- )
R m
(
.O 8 s q
. .fr e
s s o/ o G D uPt t =
l a/
t 1 qW 3 aA
- PV P
E E
K A
T N
I Y
N A
P X M =
O ,
C r gr 9 R yo E at no it 4
Tcc 0 0 0 1 A ea 9 O. xc 0 W DF 1 I 1 ia MF N
A X R X R
1 1
)
B l s i
S n r o h
(
A i T t t
i a n P, rc eo T tc si E n/
D ei at A cC ea l r I nu eu I o RD I
I C P
X X c
3 r c r
- h / e R /1 v 1 R O 3 m n i Rr P o l c E n l c o 5 4 4 4 ia X i P kF T s P P P 2
D rr 1 3 4 1 0 2 l N eo 6 9 9 0 2 6 0 3 4 ye 2 E avt 0 5 5 0 9 ug P snc 4 9 1 7 5 2 1 2 5 ha P cn boa A I CF Si l d y i
d r e r e o r e r e o e l y e t y r e l Y e l y n d v ol v od y v od v oa in r e i
o i
i y r i io h i n i, Mg L MB L mB T i.
I wU T v
e l o
r y
=
e i i h t I
M T a D
$ aC'. , 2g.j
~ S au
( l lll _
e------ - - - - - - -- - - - - -
EP-318 .v. O Pcqa 7 er C VM/ MPG /rqa APPENDTX EP-11R-4 NORRISTOWM WATER INTAKE Ibse mR/hr Concentration Decay Conversion uCi/cc X uCi/cc X Factor =
Factor g T.t ve r 406 1.0
. t 0 WSole 959 no ly T.tver 1591
- N Whole 700 .87 7
s no IV t
, 'Ihy ro t el 5.23P5
~s T.ive r 2.64P4 1.0 0 Whole 1.01P4 slo ly 8
Liver 2.30P4 1.0
$ Miole 5942 nociv
+
Schuylkill River Release Mixing thage Factor X Duration (hrs) X Factor X = Dose (mR)
Tiver .
Whole no<1y 1.0 .0091 Tigro l <1 Da te : _ _
0
. )
R .
m
(
OCs g
.fr e
_ . s ve o/ o G D 8P M =
0 e/ qw _
1 .
3 aA
- PV P
. E
~
E K X A =
+
T 4
t I r qr 2 yo R at no i t 1
E cc 0 0 0 0 1 T t r a 8 xc 0 A DF 1 1 1 i a W MF T X N X 0
1
- )
L n E r B n o h
(
A i T t I
I a n P. rc eo t
T tc ni E n/
T' ei at A cC ea L nin l r I o eu l
i C RD P
X X c
5 r c r
- h / e 1 / I 1
f R C i v
3 mG Rr P o lt E n l c o 5 4 4 4 i a X i I s P P P P kF n rr 1 3 4 l 0 2 l ye O.
i r
E evt eo 6 0
9 5
9 5
0 0
2 6
O.
3 4
a ur i 1 P snc 4 9 1 1 5 2 1 2 5 ha P hoa cs A T CF SU l
e y
1 t ,
r e r e o r e r e o e l v e l y r e l v e l v B te v ol v ol y v o1 v oi r l i
L iy MB r 1, iy MB r h T
i L
io Mn i
L ho WB _ r e l e o r :
T v o y e d
i h t i M *l u T
~
gmaA % 4- [o 0 SaIj l
l
i
- l j - . EP-319 Rev. 0 Page 1 of 4 VAW4 MPG /rgs
/ ,
if f.
I PHILADELPHIA ELECTRIC COMPANY , (
LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-319 FISH INGESTION PATHWAY DOSE CALCULATION 1.0 PURPOSE The purpose of this procedure is to provide the calculation method for estimates of the maximum population exposure due to the ingestion of fish from the Schuylkill River.
2: 2.0 RESPONSIBILITIES None i
1
'3.0 APPENDICES I
3.1 EP-319-1 Maxirum Dose From Fish Ingestion 4.0 PREREQUISITES None j
5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS 6.1 An actual or potential liquid release of radioactive material into the Schuylkill River.
7.0 ACTION LEVEL 7.1 This procedure shall be implemented when the criterion o f - section 6.0 is met.
- - EP-319 Rev. O
- '
- age 2 of 4 VAW/ MPG /rgs t 9.0 PRECAUTIONS
, None l
9.0 PROCEDUR'E 9.1 The following assumptions were utilized in this
. calculation:
9.1.1 The Dese Conversion Factor is based on the most limiting group (adult, teen, child, infant) using dose factors and consumption rates in Reg. Guide 1.109.
Adult 21 kg/yr Teen 16 kg/yr Child 6.9 kg/yr Infant O kg/yr 9.1.2 The Decay Factor is based on the decay of the isotope over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (time to reach the population per Reg. Guide 1.109.
9.1.3 The total dose commitment is the dose which an individual would receive after eating fish exposed by the highest concentration of diluted effluent for the duration of the release.
9.2 Obtain grab sample results on the concentration of Co-60 I-131, Cs-134, Cs-137 and P-32 released, from the Chemistry Sampling and Analysis. Team Leader.
9.3, on Appendix EP-319-1, enter the concentration of P-32, Co-60, I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours.
If the sample was taken prior to entering the Cooling Tower Blowdown Line, a diluted concentration must be determined by the following method:
Concentration uCi . concentration
- Release rate to Blowdown Line Released ci uci Blowdown line Efow rate
EP-319 Re'v. O
' Page 3 of 4 VAW/ MPG /rgs 9.4 Perform the calculation on Appendix EP-319-1 to estimate the maximum dose in millirem for the liver, whole body and thyroid for the fish ingestion pathway.
9.5 Report results to the Dose Assessment Team Leader.
10.C REFERENCES 10.1 EROL 5.2.4.1 Liquid Pathways 10.2 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 10.3 Reg. Guide 1.109 Calculation of Annual Doses To Rev. 1 Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10CFR Part 50, Appendix I
(
l l
l l
l
j1Illl ll
. O4a q
.fr v o/
e G .
R4P 2 M l 9 e/ d r 1 gW i i
3 aA o o PV r r P y y E h 1I
) T '
R m
( e l y e e od l y s io o l.
D o Mb _ Mn io r
e v r i e L v
' i
= L gr no 7 7 7 7 7 +
i t 5 5 5 5 5 xc 3 3 3 3 3 ia 0 0 0 0 0 MF N x O _
I n _
T eo _
S si F. at) )
G *as r N l rr m I eu R D (h
, (
e I
I s S x o I D F r yo l M at 5 0 2 0 0 a O
R cc ea 9
1 9
1 1 t
o F DF T E x S
O n D o i
1 t
P I a 1
t r I t X n A e M c ni oc Ca t c c
1 x 9 n 1 o 3 i
- s P r E e v
X n 6 I o P 6 5 5 5 5 n Cr 2 P P P P P N
E o r_c /
c 1 5 6 4 4 2 4 P
4 9 4 2 eth . 5 1 2 2 1 7 4 4 P 9c/ i 3 2 2 6 2 1 7 . .
P oaRC 7 5 5 3 A DFmi s l
e i
r e r o r e o r e r e :
e e e r e e v E l y l y l v l y l v ol v ol v ol y v ol v ol T i ho i io i.
t o h i t o i ho A L wB L MH T 4H 1 T L 4B 1 L NB D mnlA @*0 an7H t" 0 St . j l l' l1 l ,l
, EP-401 Rev. O Page 1 of 5 VAW-/ MPG /rgs Y ! *thl$5 PHILADELPHIA ELECTRIC COMPANY v LIMERICK GENERATING STATION \
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-401 ENTRY FOR EMERGENCY REPAIR AND OPERATIONS 1.0 PURPOSE The purpose of this procedure is to provide guidelines for entering areas for emergency repair and operations that have become adversely affected by the emergency conditions.
2.0 RESPCNSIBILITIES 2.1 A health physics technician shall advise personnel of radiological conditions when entry for emergency repair and operations is needed.
3.0 APPENDICES 3.1 EP-401-1 Emergency Exposure Guidelines 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None l 6.0 SYMPTOMS l
, None i-
1
)
. EP-401 Rev. 0
- Page 2 of 5 VAW/ MPG /rgs 7.0 hdION LEVEL 7.1 This procedure shall be implemented whenever personnel must enter an area of adverse or unknown conditions for reasons of emergency repairs or operation of equipment.
8.0 PRECAUTIONS 8.1 No one person shall be left alone during the entry.
8.2 Planned radiation exposures should be limited to the administrative guide levels in Appendix EP-401-1 Emergency Exposure Guidelines. Performance of a task involving exposure above 10CFR 20 limits should be voluntary and limited to once in a lifetime.
8.3 Through General Employee Training (GET). personnel performing an entry shs11 be aware; of the potential biological effects associated with exceeding a whole body acute dose of 25 Rem or more.
8.4 continuous coverage by a health physics technician may substitute for a radiation work permit.
8.5 If the atmosphere is known or suspected to be oxygen deficient or potentially toxic, appropriate Respiratory Protection Equipment shall be used.
8.6 Appropriate blocking procedures may be waived by the (Interim) Emergency Director in carrying out this procedure.
l' 8.7 The man-rem for the entry should be maintained ALARA.
i 9.0 PROCEDURE ,
9.1 Immediate Actions 9.1.1 Health Physics Technician shall:
9.1.1.1 Discuss the situation with the OSC Coordinator as to the type of job to be l performed and location. Find out the maximum allowable dose authorized by the (Interim) Emergency Director for"the task involved.
l
f 1
'-
- EP-401 Rev. O
,,~~
Page 3 of 5 VAW/ MPG /rgs 9.1.1.2 Determine from the Plant Survey Group L+.ader D the present conditions in the area, if
. known.
~
9.1.1.3 Based on conditions in the area, direct personnel as to the Anti-C, respiratory protection and dosimetry to be used in accordance with health physics procedures.
Provide recommendations in work practices that will assist personnel in maintaining
, exposures ALARA.
9.1.1.4 Have personnel who volunteered for the job sign in the OSC log book.
- 9.1.1.5 If airborne radiciodines are present in the working area, inform the Radiation Protection Team Leader so he can determine if potassium iodide tablets are needed in accordance with EP-313 Distribution of Thyroid Blocking Tablets.
9.1.1.6 Obtain appropriate survey souipment and accompany the individual or group to the working area.
9.1.1.7 While traveling through the plant, have survey meters on to observe changes in radiation levels.
9.1.1.8 Monitor radiological conditions in the working area. This should include airborne surveys, radiation surveys and contact dose rates on ecuipment being handled, if possible.
9.1.1.9 During the emergency repair or operation, estimate the dose being received and inform personnel who may be close to exceeding a i
dose guideline. Direct those to limit their
, exposure by leaving and being replaced by l others, if possible. If the HP technician is close to a dose guideline, contact the OSC for additional HP support. If none is available, terminate the job if possible and direct the group to leave the area.
l 8
i
- . - , , . -..,-.e.. .- _ - , ~. , ,,, . - - - - _ , . . ., .m , -..---._.r,-w ,.w.mr, . -- ,-
e EP-401 Rev. O Page 4 of 5 VAW/ MPG /rgs 9.2 Follow-Up Actions 9.2.1 Health Physics Technicians shall:
9.2.1.1 Return with the individual or groups when the operation is completed and estimate each individual's total exposures.
9.2.1.2 Report back to the OSC or other designated location.
9.2.1.3 Record whole body dose estimates for each person involved.
9.2.1.4 Have dosimetry processed so that the actual dose may be known.
10.0 REFERENCES
10.1 Limerick Generating Station Emergency Plan 10.2 NUREG 0654, Criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
10.3 EP-313 Distribution of Thyroid Blocking (KI) Tablets 10.4 NCRP Report No. 39 Basic Radiation Protection Criteria
- c
_..a - - - - - - . _ _ _
. j
. EP-401, Rev. O Page 5 of 5 VAW/ MPG /rgs APPENDIX EP 401-1 Emergency Exposure Guidelines Projected Whole Body Thyroid Authorized Function Dose Dose By
- 1. Life Saving and (Interim)
Reduction of Injury 75 rem
- 375 rem Emergency **
Director
- 2. Operation of Equipment to Mitigate an ( Inter. im)
Emergency 25 rem
- 125 rem Emergency **
Direct:r
- 3. Protection of Health (Interim) and Saf ety of the Public 5 rem 25 rom Emergency **
Director
Activities limits limits Emergency Director
- 5. Re-entry / Recovery Station Station Activities Administra- Adminis-tive Guide- trative '
lines Guide- N/A lines
Reference:
EPA-520/1-75-001 Table 2.1
- Such exposure shall be on a voluntary basis ,
~
f
EP-500 Rev. O
_Page 1 of 4 VAWMPG/rgs
{/
c, pcp>
PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE ,
EP-500 REVIEW AND REVISION OF EMERGENCY PLAN 1.0 PURPOSE This procedure describes the method for annual review of the Emergency Plan and the incorporation of any necessary revision.
2.0 RESPONSIBILITIES 2.1 The Superintendent, Nuclear Generation shall appoint an Emergency Plan reviewer.
2.2 The reviewer shall review the Emergency Plan in accordance with this procedure.
3.0 APPENDICES None 4.0 PREREQUISITES 4 f Nme 5.0 SPECIAL EQUIPMENT None 6.0 SYMPTOMS None
1 *
.. ,, EP-500 Rev. O Page 2 of 4 VAW/ MPG /rgs 7.0 ACTION LEVEL None
't 1
8.0 PRECAUTIONS None
. 9.0 PROCEDURE ,
9.1 Immediate Actions 9.1.1 The Superintendent, Nuclear Generation, shall appoint one member of the Electric Production Department staff to conduct the annual review of the Emergency Plan.
9.1.2 The staff member shall review the Plan and other documents indicated below and recommend revisions which are required as a result of the following considerations:
9.1.2.1 Written critiques and evaluations of drills and exercises, especially recommended corrective actions.
- 9.1.2.2 Changes in plant organization, structures or
- personnel or capabilities.
l 9.1.2.3 Changes in function, orgt.nization of I supporting organizations.
I 3.1.2.4 Changes in State or Federal regulations.
l
! 9.1.2.5 Interfaces in State or local emergency plans.
9.1.2.6 Modifications to the plant or site which could affect emergency planning.
9.1.2.7 Recommendations from other organizations, such as state, f ederal agencies and other l
l utilities, organizations and INPO.
l l 9.1.2.8 Changes in construction or operating status.
l
.~ . . -- - - _- _= . ..- -. _. . - . ..
5
,' EP-500 Rev. O Page 3 of 4 VAW/ MPG /rgs I
9.1.2.9 Significant changes in areas surrounding the site, such as changes in population density or land usage.
9.1.2.10 Adequacy of emergency equipment, training and readiness testing.
9.1.2.11 Changes in other plant operating or <
administrative procedures.
9.1.3 The reviewer shall confirm letters of agreement.
9.1.4 The reviewer shall document the results of his review in a letter to the Station Superintendent. The letter shall state the areas reviewed (with those listed above, as a minimum), the results for each area, and
, the recommended revisions.
9.1.5 If in the opinion of the person reviewing the plan, only minor changes are needed, the reviewer shall formalize the proposed changes and submit them for review by the Plant Operations Review Committee (PORC).
9.1.6 If in the opinion of the person reviewing the plan, substantial changes are needed, a three-person review committee shall be convened by the Superintendent, Nuclear Generation to develop the necessary changes.
The committee shall consist of one member from the LGS staff, one member from the i Electric Production Department not on the LGS staff, and one member appointed by the Nuclear Review Board (NRB) . The review
, committee shall recommend the necessary i changes to the Plant Operations Review Committee (PORC), based on the l considerations of Steps 9.1.2.1 through 9.1.2.11.
. 9.1.6.1 The recommended changes and any additional PORC recommendations shall be presented to 4
the Nuclear Review Board (NRB) for approval.
i 9.1.6.2 Proposed changes approved by the NRB shall be incorporated into the Emergency Plan by
.the person or persons who reviewed the Plan
. or their designees.
-l l
} . EP-500 Rev. O
! . Page 4 of 4 I VAW/ MPG /rgs 9.1.7 Revised pages of the Emergency Plan shall be l prepared and shall be distributed to personnel and groups on the Emergency Plan Distribution List. Holders of the Emergency Plan will be requested to acknowledge ,
receipt of the revised pages. The receipts j shall be returned to the Emergency .
Preparedness Section, who will ensure proper filing.
9.1.8 Emergency Plan Implementing Procedures shall be revised to reflect any changes in the Emergency Plan (the Implementing Procedures are also reviewed and revised, independent
- of the annual plan review, according to other prescribed administrative procedures).
- Controlled copies of revisions shall be distributed in accordance with Administrative Procedures.
9.1.9 If changes to the Emergency Plan affect contract support groups, they should be informed of these changes.
9.1.10 Discussion of changes shall be incorporated into craining programs, as appropriate.
10.0 REFERENCES
10.1 LGS Emergency Plan 10.2 NUREG 0554, Criteria For Preparation & Evaluation Rev. 1 And Of Radiological Energency Response Plans Preparedness In Support Of Nuclear Power Plants
,i+ p n <,uq(og, UNITED STATES
{
g g
r NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ,
k,, . . . . .8,o March 2, 1984 50-352/353 Limerick MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Divison of Rules and Records, ADM '
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The submitter of the attached document has expressed no desire to withhold any information contained therein. Therefore, this material may now be made publicly available.
, /
J. M. Felton, Director Division of Rules and Records -
Office of Administration
Attachment:
As stated I
d
,y , .< -. - , - - . - - , , .-- , ,
e .
I i
i PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 swistos L. DALTROFF voca Pesososm?
ELECTRIC PRODUCTIOss T?rrrrr" ::, 1:q re treterIat. :D-;i;
!i-J';
D r . "hcra." P. . f u r.i cy , Chi e f Pecion I Citico ci Inr.rection ene Fnforce:rer.t C. .i. Nuclear Eeculatory Cormiccion 6".1 Lar k Avenue rinc of Frusein, FA 19406
Dear Dr. Furley:
E r.cl oc ec ar e two c:ct 11. cf 7.fr..tcic' Generatine Ststien Emergency ll an I:tplementing F rcc.? tar 81.s. 'T h tu ,trocacure.: 'ecre previously transmittec uncer ceparate cover (Nevember 3C , 1583 anc tecenter 12, 1983) to A . Sch <er.cer , Chief-r. lc ar.: Jac Cranch No. 2 a nd t hc L 1rer ic k G.m's r n i : - C t.! ? ! .:n ;' t t : Ira : -c tor . C. c ?
procedures are heinc yrovi.i*,6 to r.upp . ment the procedures
, tra.ntmatte<i to you on Docer.ter 20, I '4 G 3 .
'1 he procc<.urer hel: c tr2necitted are tha fel!. 'i.'vi:
EF-iC1, Fev. O FF-70P, Fev. 0 EI-202, Fev. O FF-<!;,1cv. O EF-103, F ev . O EP-2:1, I:ev. O ET-110, Fev. 0 EF-052, F ev. O EP-220, Pev. 0 EF-304, F ?*r . O EF-212, Rev. O EF-305, Fe". C EF-230, Fev. 0 EF-307, Ten. O EI-250, I ev. C LF-317, .~ o - . G FF-It.1, F ev . O IP-313, Fr'v. O F1-3ua, F ee v . O EF-318, ? ev. O FF-303, Fev. C FF-329, Fe'?. O El-110, Fev. O
[d[
T1-401, Fa'r. C rF-500, rev. 0
'/
1 '
l.
3 fO Dr. Thcmas E. Murley rage
/: .:xicatret in tr.c attachcc lct:2re, carta.r. ct t '.. a enc)oted prcccCuret contain prcerletsr*; .r.icrrat cn. . hezeiore, t<e _ r *
- u e r t that thet e preciecure:t tc 'nthna;e irca rui..;c disclocure.
"50 corier have toon tent unscr sc;aratw cover tc the recunent Control Ceck.
'.ery trulj ycuts ,
~
~.. n c J Enc 2ccuro ec: Eccutent Centrol Coch U. S. Tuclear T coulctcry Cermission i t.: hingtcn , L .C. 1CIEE Sate Inniector - Lir; crick Cencrating Station (wfo attachment) t.. Echucncer, Livision of Licensing,;IC (veio attccheent)
. Attached service list (wfo attachr.ent) e J
PHILADELPHIA ELECTRIC COMPANY 2301 M ARhC'P t3TRCCT P O. BOX 8699 PHILADELPHI A. PA.19101 wmi;tus i. oaLinorr 12 5 a.u scos u sErYic'"pa'o's sees December 12, 1983 Re Docket Nos. 50-352
' 50-353 D
Mr. A. Schwoncer, Chief 1,icensing 11 ranch No. 2 Division of Licensing LJ . *; . Nucl .ir 1(uquiatory Commianion Wsshington, D.C. 20555 l>voc Mr. Schwoncer 1::nclosed are two copies 'of Limerick Generating Station E... regency Plan Implementing Procedures. These procedures,are aussiitted por regulations in 10 CFR 50, Appendix E,Section V.
'th procedures being submitted are the following:
EU-LLO, Rev. O EP-307, Rev. O EP-208, Rev. O EP-312, Rev. 0 EP-221, Rev. O EP-313, Rev. O EP-251, Rev. O EP-318, Rev. 0 HP-252, Rev. O EP-319, Rov. O EP-304, Rev. O EP-401, Rev. O EP-305, Rev. O EP-500, Rev. O Pursuant to Section 2.790 of the Commission's r eilu t a t i ons , it lu hereby requested that the tolophone numbers listed in procedures EP-252, EP-304, EP-305, EP-312 be withheld ir..m publie discirrsure. An af fidavi t settInq forth the groundn t i, support of thire request is attached hereto. ,
.. . - . _ . -- - - ._ . - _ . . _ . _ . - . . . ~
d D
.~ ,
N ii 1
+
' Page 2 Mr. A. Schwencer
%;. l k a .
Two copies nave been sent under separate cover to the
.' Docuteent. Control Desk.
. \
Very truly yourn, j u
.i :
- f. ( I ' I i'l
+.
6:neiocuro .
ee: Document'Co$ trol Desk
'p '
U.S. Nuclear-llequlatory Commission Wanhington,-DC 20555
~ Site Inspector - Limerick Generating-Stat on i s
+
0
-+
f a n
> b 4,
o h
f I t
i
+ g A
l 3 s.-
t A
h N.
g N c
.e g
4
( ga.
s," t . %
~
gY'-
i a
l l
s<: Judce Lawrence Hrenner (w/ nelosure)
Jud,'c Peter A. Morris (w/o enclosure)
Juaf'e Hichard F.: Cole (w/o enclosure)
Troy b. Conner, J r. , Mcq. (w/onclosure)
Ann P. Ilodcdon, 10;q. (w/ enclosure)
Mr. Frank R. Romano. ,
(w/o enclosure)
J Mr. Robert L. Anthony (w/ enclosure)
Mr. Marvin I. Lewin (w/ enclosure)
Ms. Phyllic Zit.pr (w/cnclosure)
Charles W. Elliott, Eca. (w/o enclosure)
Zori G. Ferkin, Eng. (w/ enclosure)
Mr. Thomas Gerunky (w/o enclosure)
- Director, Penna. Emerp,ency (w/o enclosure)
~
Manancment. Ageray Mr. Steven P. Hershey (w/ enclosure)
Annun Love, Esq. (w/cnclosure)
Mr. Joseph H. White, III (w/ enclosure)
Davio Wersan, Esq. (w/o enclosure)
J Rnhert. J. Sugarman, Esq. (w/o enclosure)
Martha W. Bush, K::q. (w/ enclosure)
Spence W. Perry, Mcq. (w/o enclosure)
Jay M. Cucierres. Esq. (w/o enclosure)
Alnmir Saf'et.y & !.icensing Appeal Board (w/o enclosure)
Atomic Saf'ety & l.icensing Board Panci (w/o enclosure)
Docket & Service SerLion (w/ enclosure) 9 i'
1
= pe a e
l l
CO.vy20NWEA!!PH 0F PENNSYLVAN1is .
- n ei .
COUNTY OF Pl!ILADl%PilIA S. L. Daltroff, beinq f i rs t duty nworn, dopocen and stateu au ,
foLlows:
i .'o.u p. u s y
- 1. lier in V ico Prcuidont of Plii i aitoL pla ia M i out c i s-
.. . 4 tu (horoinafter referrod to a ts the " Company" ); liv i t; .sul tan h..
exacutu thin Affidavit on behal f . of t tw Comp.iiiy: .u n i h. -
eu v i owerl:
RP-252, Rev. O MP - 3 0'i , Huv. O HP ~10 4 , Huv. O MP 'l l> , 1(o v . 0 (horcina f ter re f orred to au' " the Documentu" ), and krsown Llav contents thereof.
t.o i n-
- 2. The part of tlw Document o which are no uqh t withhold from public disclosure is thr+ listinq of the home
' telephono riumborn anil home addrosuon of omployoun of the Company, direct-line work telephono numbers of employees of the company which are not liuted in pubj.ie' ;u tophvuu di rucLuriou, and home and work numbers of emorgency responou support porconnel and organizations.
- 3. To the best of his knowledge, information and forth in the holief, the telephone numbers and addresses set
.-- -r-=e m- - - - --
P Docut:'ent s h'tve been treated as confidential information and have been withheld f rom public disclosure by' the Company.
- 4. Tlie home telephono numhors and home adelresuen ia the Documents chould be considered by the Nuclear Regulatory Commission as con fidential and proprietary information and he withheld f rom public disclo'sure on the grounds that disclosuro of ,
the home tolophone numborn and home addresses of the employacs of the Company and emergency support personnel could constituto an unwarranted invasion of the peruonal privacy of the individualn e involved, disclosure of the work tulophone numhorn of the Company's employees and of the emergency rosponse personnel and or ga nizati on s could adversely af f act the capability of prompt notification in the ovent of an emergency; such disclosure is not required in the public intorest; and such disclosure could advernoly affact the intorosts of the Company and its abili tv to offactively improment the iTotification requirements of the F.mergency Plan Procedures. .
, f
,, . 4 m K ., . ( _ . ..
Subscrlhed and sworn to bef ore me this l " day og s :, . . . . . .
. I.
l
- s. s/ if Notary Public JUDITH Y. FRANKLIN Notary Putstic. 3lui.s.. I'lui.s. Co.
My CommasWn Enoeros July 20.1907
--_ __