ML20215A054
| ML20215A054 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/21/1986 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20215A045 | List: |
| References | |
| PROC-861121-02, NUDOCS 8612110144 | |
| Download: ML20215A054 (40) | |
Text
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Page 2 of 4 Revision 66 11/03/86
.4 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX
================
==================================
DATE OF LAST DATE SIGNED PERIODIC PROCEDURE REV.
BY SUPER.
REVIEW NUMBER NO.
TITLE
=========
=
================= ion of Post-Accident===
10/23/86 EP-231 12 Operat Sampling Systems (PASS) 04/01/86-10/23/86 CANCELLED EP-232 Retrieving and Changing Sample EP-233 7
Filters and Cartridges from the Containment Leak Detector during Emergencies 04/01/86 10/23/86 Obtaining Containment Gas Samples EP-234 7
from the Containment Leak Detector during Emergencies 04/01/86 10/23/86 Obtaining Reactor Water Samples EP-235 6
from Sample Sinks following Accident Conditions 03/14/85 10/23/86 Obtaining Cooling Tower Blowdown
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EP-236 5
Line Water Samples following Radioactive Liquid Release after Accident Conditions 04/01/86 10/23/86 Obtaining the Iodine / Particulate EP-237 8
and/or Gas Samples from the North Vent Wide Range Gas Monitor (WRGM) 04/01/86 10/23/86 Obtaining Liquid Radwaste Samples EP-238 5
from Radwaste Sample Sink following Accident Conditions CANCELLED 06/24/86 10/23/86 EP-240 Sample Preparation and Handling EP-241 10 of Highly Radioactive Liquid p
I 03/28/85 10/23/86 Samples Sample Preparation and Handling EP-242 5
of Highly Radioactive Particulate Filters and Iodine Cartridges 06/24/86 10/23/86 Sample Preparation and Handling EP-243 7
Hof Highly Radioactive Gas Samples 03/12/85 10/23/86 Offsite Analysis of High Activity EP-244 3
Samples,,,
12/12/84 10/27/86 EP-250 2
Personnel Safety Team 04/01/86 04/01/86~
l EP-251 3
Plant _Sarvey Group
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09/02/86 07/31/86 Search and Rescue /First Aid Group 12/12/84 12/12/84 EP-252 8
Personnel Dosimetry, Bioassay, l
EP-253 0
and Respiratory Protection Group 8612110144 861121ADOCK 05000352 PDR
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t Page 3 of 4 Revision 66 11/03/86 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX_
==
===============================================
OF LAST DA DATE SIGNED PERIODIC PROCEDURE REV.
BY SUPER.
REVIEW NUMBER NO.
TITLE
==
=============================
02/04/85 1
Vehicle and Evacuee Control Group EP-254 3
12/12/84 10/23/86 Vehicle Decontamination EP-255 2
12/12/84 10/23/86 Fire and Damage Control Team EP-260 2
12/12/84 10/23/86 EP-261 2
Damage Repair Group CANCELLED EP-272 EP-273 CANCELLED CANCELLED
(
02/10/86 10/23/86 Fire and Damage Team Phone List EP-276 7
10/27/86 10/23/86 Personnel Safety Team Phone List EP-277 10 10/06/86 10/23/86 g
Security Team Phone List 05/12/86 10/26/84 EP-278 8
Emergency Operations Facility EP-279 8
7 (EOF) Group Phone List 05/12/86 10/23/86 Technical Support Center (TSC)
EP-280 9
Phone List 10/27/86 10/23/86 Government and Emergency EP-282 7
Management Agencies Phone List 10/27/86 10/23/86 EP-284 7
Company Consultants and Contractors Phone _ List 10/27/86 10/23/86 Nearby Public and Industrial EP-287 4
Users of Downstream Water 10/27/86 10/23/86 Staffing Augmentation-12/18/85 10/23/86 I
EP-291 9
Chemistry Sampling and Analysis EP-292 9
Team Phone List 05/27/86-10/23/86 Dose Assessment' Team Phone List 10/27/86 10/27/86 EP-294 9
Operating the Evacuation Alarm EP-301 2
and River Warning System 12/12/84 10/23/86 EP-303 3
Local Evacuation 10/27/86 10/23/86 Partial Plant Evacuation EP-304 4
10/27/86 10/23/86 EP-305 6
Site Evacuation er
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Page 1 of 4 i
3g63148150 Revision 66 11/03/86
[
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LIMERICK GENERATING STATION
[
EMERGENCY PLAN PROCEDURE INDEX k
[
==
= = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =
r D
j DATE SIGNED PERIODIC PROCEDURE REV.
BY SUPER.
REVIEW NUMBER NO.
TITLE
=
= = = = = = = = = = = = = = = = = = = = = = = = = = = =
03/25/85 Classification of Emergencies EP-101 4
07/28/86 07/28/86 k
EP-102 11 Unusual Event Response 10/27/86 07/28/86 Unusual Event Notification Forms EP-102 1
s (Appendix 1) 07/28/86 07/28/86 EP-103 14 Alert Response 10/27/86 07/28/86 EP-103 1
Alert Notification Forms q
(Appendix 1) 3 07/28/86 07/28/86 Site Emergency Response 10/27/86 07/28/86 l
__ -104 13 Site Emergency Notification Forms EP
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2 EP-104 1
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(Appendix 1) 07/28/86 07/28/86 General Emergency Response 10/27/86 07/28/86 E
~
13 EP-105 General Emergency Notification EP-105 1
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(Appendix 1)
Forms 10/27/86 10/23/86 Written Summary Notification 10/27/86 10/23/86 EP-106 5
Personnel Assembly and
=
E EP-110 7
A Accountability 25 7
10/23/86 F
Site Emergency Coordinator N.ll/03/86 11/03/86 EP-120 4
Technical Support Center (TSC) m' l EP-201 6
e.
04/01/86 Activation
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OperationsSupportCenter{w\\ptv.04/Ql/86 QSC EP-202 5
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a Emergency Operations facil5,ty,'-
1 5/2.7/86
<t,304/01/85 P
Activation
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Security Team
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l EP-210 6
Dose Assessment Team
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25/85 10/23/86 EP-211 2
Field Survey Group giv EP-220 CANCELLED
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CANCELLED h
EP-221 CANCELLED 03/14/85 10/23/86 EP-222 Chemistry Sampling and Analysis EP-230 5
Team e
Page 4 of 4 p
Revision 66
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11/03/86 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX j
===================================================================r.
DATE OF LAST PROCEDURE REV.
DATE SIGNED PERIODIC NUMBER NO.
TITLE BY SUPER.
REVIEW
==============================================================
EP-306 4
Evacuation of the Information 10/27/86 10/23/86 Center i
EP-307 3
Reception and Orientation of 10/27/86 10/23/86 Support Personnel EP-312 5
Radioactive Liquid Release 01/09/86 01/09/86 EP-313 2
Distribution of Thyroid Blocking 12/12/84 10/27/86 Tablets EP-314 1
Emergency Radiation Exposure 03/29/85 12/06/84 Guidelines and Controls EP-315 8
Calculation of Offsite Doses 09/02/86 01/09/86 during a Radiological Emergency using RMMS in the Manual Mode EP-316 4
Cumulative Population and Near 02/10/86 02/10/86
(
Real-Time. Emergency Dose e
Calculations for Airborne Releases Manual Method EP-317 5
Determination of Protective 09/02/86 10/23/86 Action Recommendations EP-318 2
Liquid Release Dose Calculations 04/01/85 04/01/85 Method for Drinking Water EP-319 2
Fish Ingestion Pathway Dose 03/29/85 03/29/85 Calculation l EP-325 4
Use of Containment Dose Rates to 11/03/86 11/03/86 L
Estimate Release Source Term EP-330 5
Emergency Response Facifity 10/27/86 10/23/86 Habitability EP-333 1
Adjustment of Wide Range Gas 05/08/85 05/08/85 Nonitor Conversion Factors EP-401 3
Entry for Emergency Repair and 04/01/86 04/01/86 Operations EP-410 3
Recovery Phase Implementation 03/29/85 10/23/86 EP-500 2
Review and Revision of Emergency 12/12/84 10/23/86 Plan O
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l 3gf3j4gjgg EP-201, Rev. 6 Page 1 of 20 MJR/jmv PHILADELPHIA ELECTRIC COMPANY t
p LIMERICK GENERATING STATION 11 3 &
EMERGENCY PLAN IMPLEMENTING PROCEDURE I
EP-201 TECHNICAL SUPPORT CENTER (TSC) ACTIVATION l
l l
CAUTION: VERIFY HABITABILITY FOR ACTIVATION.
I
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1.0 PARTICIPANTS 1.1 Emergency Director shall direct the activation of the Technical Support Center.
1.2 Shift I& C Technician shall activate the equipment in the TSC.
s Communicators shall man assigned phones and 1.3 communications log.
l.
1.4 Status Board Recorders shall obtain and post formation on assigned status boards.
1.5 chehe
- cian shall
.oy.m a habitability 2.0 ACTIONS - IMMEDIATE 2.1 Emergency Direct 2.1.1 Assign a Shift I 's.t Techn'ician.to perform the steps
[
in Appendix EP-20lM, Techriicil' Supii (f' Center HVAC Q
System ' Emergency' Mode and to.perfor~m the steps in l
Appendix EP-201-2, TSC Activation-Check-off List.
of.,
Assignanindividualthehu'diesofTSCCommunicator l
2.1.2 and direct the'individuh10t'o perform the steps' outlined in Section'2.3 of this procedure.
2.1.3 Direct a HP Technician to perform a habitability check,
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of the TSC per EP-330, Emergency Response Facility.
l Habitability, if_not already completed.
y 7
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I l
l l
EP-201, Rev. 6 Page 2 of 20 MJR/jmv 2.1.4 Ensure that incoming personnel to the site enter the protected area through the guard station storing their
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badge; the TSC Guard Station or the Admin guard l
station.
l l
2.1.5
.If the security computer is not operable ensure Security maintains a sign-in, sign-out log for personnel reporting.
2.2 Shift I&C Technician shall:
2.2.1 Use attached Appendices EP-201-1 and EP-201-2 to turn on lighting, and Particulate, Iodine and Noble Gas j
(PING) Monitor, obtain key to TSC key locker and to place the HVAC in ' Emergency' Mode.
- THETSCE IN THE
" NORMAL" MODE, IF NOT, STAR EM IN ACCORDANCE WITH S81 CHNICAL SUPPORT CENT AIR
)
CONDI l
y irector shall:
2.3 i
01-9, TSC Phone Check List, verify l
2.3.
tions capability exists from the TSC.
2.3.2 Inform the Emergency Director when the communications capabilities have been veri ed or f any discrepancies. If there lems, have the Shift I&C technician cal 6d ask for telecommunications on-ca rsonne.
U 2.3.3 Man communications lines as directed by the Emergency Director and maintain a communications documentation i
containing information received from and sent to emergency response personnel and offsite agencies.
The log shall include as a minimum the following information:
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)
Messages received or sent j
Name of person'information was received or s.ent to ifnd location Name and initials of person making entries
EP-201, Rev. 6 l
Page 3 cf 20 MJR/jmv 2.3.4 Inform the Emergency Director promptly of all significant information received from other emergency response personnel and offsite agencies.
3.0 ACTIONS - FOLLOW-UP i
3.1 Emergency Director shall:
3.1.1 Ensure that the Security Team Leader activates the Access Control and Accountability Groups, in accordance with EP-208, Security Team.
3.1.2 Direct the communicator to call in additional personnel if needed.
Use EP-280, Technical Support Center Phone List.
3.1.3 Assure that individuals are available as Status Board Recorders for necessary status boa:ds.
LGS Plant Parameter Status Board Plant Parameter Trends Board i
[
Event Chronology Status Board Offsite Communications Status Board Staff Assignment Status Board Fire / Damage Status Board.
WHERE APPLICABLE, MAINTAIN DOCUMENTATION ON STATUS BOARDS 1
3.1.4 Direct the Status Board Recorder (s) to perform the steps outlined in Section 3.2.
l 3.1.5 Assign individual (s) as necessary to man communication i
lines, and direct the individual (s) to. perform the-steps outlined in Section 3.3 of this. procedure.
If necessary, assign a communicator to the Field 3.1.6 Survey Group Leader for sending field survey data, and other information to.the Emergency Operations Facility j
i (EOF) and to perforri the steps outlined in Section 3.3 i
l
. of this procedure.
3.1.7 Assign individuals to be data display operators.
l 1
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EP - 2 0.1, Rev. 6 l
Page 4 of 20 MJR/jmv 3.1.8 Inform the Control Room when the Technical Support Center is operational and manned, assuming control of its designated responsibilities.
3.1.9 Brief the TSC staff on their arrival and periodically (normally every 30 minutes) on the status of the pertinent plant conditions.
3.1.10 Contact the various Team Leaders for per..dic status updates as necessary.
3.2 Status Board Recorders shall:
3.2.1 Fill in their assigned status board (s).
Format and content of the status board are given in the following appendices:
Appendix EP-201-3, LGS Plant Parameter Status Board Appendix EP-201-4, Plant Parameter Trends Status Board Appendix EP-201-5, Event Chronology Status Board s
Appendix EP-201-6, Offsite Communications Status Board Appendix EP-201-7, Staff Assignment Status Board Appendix EP-201-8, Fire / Damage Status Board 3.2.2 Contact the following individuals for the various status board information.
Data Display Operators for plant parameter status and plant parameter trend information.
l TSC Communicator or Control Room for event chronology information.
l TSC Communicator for offsite communication information.
l TSC Communicator for staff assignment information.
l Personnel Safety Team Leader for site radiological status.
Field Survey Group Leader for field survey status.
Fire and Damage Team Leader for Fire / Damage Status Board.
l EP-2 0.1, Rev. 6 Page 5 of 20 MJR/jmv 3.2.3 As information is received, post on assigned status board and maintain documentation of appropriate status board entries.
3.2.4 Transmit plant status information and event chronology information to appropriate Status Board Recorders at the EOF, if activated.
3.2.5 Review and update the status board as changes in plant conditions or information warrant.
3.2.6 Inform the appropriate Team Leaders as significant changes in status board information are noted.
3.3 Communicators shall:
3.3.1 When directed, use EP-280, Technical Supp6rt Center Phone List to call in additional personnel.
3.3.2 Man assigned communication lines or consoles.
3.3.3 Maintain a communications log containing information received from and sent to other emergency response 7
facilities and other support organizations.
The log shall include as a minimum the following information:
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)
Summary of messages received or sent Name of person information was received from or sent to Name and initials of person making entries 3.3.4 Inform the Emergency Director or appropriate Team Leader promptly of all significant information received from or sent to members of the emergency response organization or support organizations.
3.4 HP Technician shall:
3.4.l' Periodically confirm habitability per EP-330, Emergency Response Facility Habitability.
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I i
EP-201, Rev. 5 Page 6 of 20 MJR/ j.nv 4.0 APPENDICES 4.1 EP-201-1 Technical Support Center HVAC System
' Emergency' Mode 4.2 EP-201-2 TSC Activation Check-Off List 4.3 EP-201-3 LGS Plant Parameter Status Board J
4.4 EP-201-4 Plant Parameter Trends Board 4.5 EP-201-5 Event Chronology Status Board 4.6 EP-201-6 Offsite Communications Status Bohrd 4.7 EP-201-7 Staff Assignment Status Board 4.8 EP-201-8 Fire / Damage Status Board 4.9 EP-201-9 TSC Telephone Check List 5.0. SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to describe the instructions and actions required for the activation, manning, and operation of the Technical Support Center (TSC).
5.2 Criteria for Use 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 Emcraency Director.
5.3 Special Equipment None 5.4 References 5.4.1 Limerick Generating Station Emergency Plan
^
5.4.2 NUREG 0654 - Criteria for Preparation and Rev. 1 Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
l*
EP-201, Rev. 6 Page 7 of 20 MJR/jmv 5.4.3 NUREG 0696 - Functional Criteria for Emergency Response Facilities.
5.4.4 EP-280 - Technical Support Center Phone List.
5.4.5 EP-330 - Emergency Response Facility Habitability 5.4.6 S81.1.B - Startup of the Technical Support Center Heating, Ventilation and Air Conditioning System 1
I i
I EP-201, Rev. 6 Page 8 cf 20 MJR/jmv APPENDIX EP-201-1 TECHNICAL SUPPORT CENTER HVAC SYSTEM ' EMERGENCY' MODE 1.
When the Shift I&C Technician arrives at 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 System.
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 column of the. display area to its " EMERGENCY" position in order to actuate the emergency mode.
VERIFY THE FOLLOWING:
3.
Fan ME-03 is activated.'
i 4.' The fan flow rate is 3000 cfm as read on the airflow monitor panel in the mechanical equipment room.
5.
MD1 closes.
6.
Exhaust Fan ME-07 stops.
7.
Inform the Emergency Director that the HVAC System is functioning in the ' Emergency' mode.
1
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EP-201, Rev. 6 Page 9 of 20 MJR/jmv APPENDIX EP-201-2
[
TSC ACTIVATION CHECK-OFF LIST Time of notification to activate the TSC L
Display Room Activation Check-Off l
Light Switches (1 & 2)
Open Key Locker
- a j EVAC Switch to Emergency Mode k
ERIS "Toshiba" Console 10-2423 l
TRA Maintenance Terminal 10-Z426 l
ERIS "Toshiba" Console 10-2424 l
Versatec Printer / Plotter 10-Z4 7 Fire & Damage Radio Base St 5
Field Survey Radio Ba I
"Decwriter" Print g
RM-11 R it "Tekt 585 86 e
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-N r supply for all printer / plotters hard copy units.
HVAC Maintenance Equipment Room Check-Off Fan ME-03 is activated MD-1 : loses to prescribed emergency postion
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Air flow monitor reads 3000 CFM on panel 7
Exhaust fan ME-07 stops (yheck light)
/ as notifLed of E
V Problems found during activation L
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I I&C Technician Signature
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I EP-201, Rev. 6 Page'10 cf 20 MJR/jmv APPENDIX EP-201-3 l
LGS PLANT PARAMETER STATUS BOARD-UNIT
. LGS PLANT PARAMETER ' STATUS - UNIT sgy,,,,
REACTOR PARAMETER TIME CORE PLATE POwtR s
LEVEL Inshes PRESSURE sale PRESSURE CONTROL-RE ACTIVITY CONTROL
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APPENDIX EP-201-3 (CON'T) 1 sNT es s
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CONTAINMENT PARAMETER COMMENTS suPPREsslON POOL TEMP
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SUPPRESSION POOL LEVEL ft CONTAINWENT
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EP-201, Rev. 6 Page' 12 of 20 MJR/jmv
.t APPENDIX EP-201-3 (CON'T)
RADIOLOGICAL PARAMETERS TIME COMMENTS NORTH STACK UC1/s e UClsses SOUTH ST ACK UC3/se 9/W R AD MONITOR R/ht t-REFUEL FLOOR EXN mr/hr AIR EJECTOR OFFG AS arthi RtX ENCL EXM mt/hr R ADWASTE EXM CPW SAMPLES NORTM STACK FLOW ofm G888/5 80 DIN E/ SABEOUS SOUTH STACK FLOW elm Ucuse UC1/s e UCUse TlWE REACTOR g
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Page 14 of 20 MJR/jmv i
APPENDIX EP-201-5 EVENT CHRONOLOGY STATUS BOARD l
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.Page 15 of 20 MJR/jmv j
APPENDIX EP-201-6 OFFSITE COMMUNICATIONS STATUS BOARD DATE:
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OFFSITE I TIME COMMUNICATIONS RESPONSE / COMMENT l
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MJR/jmv APPENDIX EP-201-7 STAFF ASSIGNMENT STATUS BOARD i
DATE:
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l EMERGENCY TITLE l NAME I EMERGENCY TITLE l NAME l
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Emergency i
Shift i
l Director l
Superintendent i
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l l l Team Leader Supervisor l
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TTire and Damage l Team Leader l
Dose Assessment i
Team Leader i
Chem. Sampling &
Analysis Team Leader j
Field Survey Site Emergency Group Leader Coordinator Security Team Leader Technical Support
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Team Leader US NRC Representative OSC Coordinator Emergency Support j
Officer i
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EP-201, Rev. 6
,Page 17 of 20 MJR/jmv i
i APPENDIX EP-201-8 FIRE / DAMAGE STATUS BOARD DATE:
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TIME I
LOCATION DESCRIPTION REPAIR STATUS I
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Page 18 of 20 j
MJR/jmv I
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APPENDIX EP-201-9 TSC PHONE CHECK LIST
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Test Phones for Dial Tone yrs /No I.
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APPENDIX EP-201-10 TSC PHONE CHECK LIST (CONT'D) i Test Phones for Dial Tone YES/NO i
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APPENDIX EP-201-9 I
TSC PHONE CHECK LIST Test Phones for Dial Tone YES/NO 1
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3863148170 EP-210 Rev. 6
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Page 1 of 5 MJR/MAC/nlp PHILADELPHIA ELECTRIC COMPANY llf] h LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-210 DOSE ASSESSMENT TEAM l
1.0 PARTICIPANTS 1.1 Shift Technical Advisor (STA) performs dose assessment activities as necessary or until relieved by the Dose Assessment Team Leader.
~
1.2 Dose Assessment Team Leader (DATL) directs the activities of the Dose Assessment and Field Survey Groups and advises the Emergency Director or Site Emergency Coordinator on Protective Action Recommendations consistent with EP-317.
1.3 The Dose Assessment Team shall include the Dose
]
Assessment Team Members and the Field Survey Group.
2.0 ACTIONS-IMMEDIATE 2.1 Shift Technical Advisor shall:
2.1.1 Perform necessary dose calculations using the Emergency Plan procedures (*) listed in Reference Section 5.4.
2.1.2 Advise the Emergency Director on pft$tective action i
recommendations in accordance wiph'BP-317, Determination of Protective Adhion Recommendations.
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The Dose Assessment Teanf 9eadeh 's;-/
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2 activated imple l'
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DATL/TSC, DATL/ EOF) shall incidde the transmittal of any available informati,on.fgon' Appendix EP-210-1.
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2.2.3 Assemble and brief Dose Assessment Team Members.
2.2.4 Direct Dose Assessment Team members to perform dose calculations using the Emergency Plan procedures (*)
l listed in Reference Section 5.4.
f 6
EP-210 Rev. 6 Page 2 of 5 MJR/MAC/nlp i
2.2.5 Request the Field Survey Group Leader to assemble the appropriate number of personnel to form Field Survey Squads.
A Squad is comprised of a Health Physics technician and a driver.
2.2.6 Contact the Emergency Director in the TSC or Site Emergency Coordinator in the EOF when the Dose Assessment Team is ready to assume responsibility for dose assessment activities.
2.2.7 Assign dose assessment calculation responsibilities to t
. each Dose Assessment Team Member.
2.2.8 Implement EP-317, Determination of Protective Action Recommendations, when dose calculations become available.
2.2.9 Advise the Emergency Director or Site Emergency
~
Coordinator on protective action recommendations in accordance with EP-317, Determination of Protective Action Recommendations.
2.3 Dose Assessment Team Members shall:
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2.3.1 Continuously trend applicable plant process radiation monitor levels.
2.3.2 Continuously trend meteorological parameters.
2.3.3 Update the DATL of any significant change in radiation or meteorological parameters, especially changes in stability class and plume direction.
2.3.4 Perform any dose assessment procedures as directed by the DATL.
2.3.5 Update status board (or status board keepers).
3.0 ACTIONS-FOLLOW-UP 3.1 The Dose Assessment Team Leader shall perform the following as required:
3.1.1 Review dose calculation parameters.
3.1.2 Coordinate the placement of Field Survey groups, through the Field Survey Group Leader, prompting him to periodically brief the. Field Survey squads on plant and release staus.
3.1.3 Coordinate with Technical Support personnel periodically to ascertain plant status and release pathway and impact of operator actions on releases.
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EP-210 Rev. 6 Page 3 of 5 MJR/MAC/ nip l
3.1.4 Request from the Chemistry Sampling and Analysis Team Leader inplant and effluent samples as necessary, and SGTS filter efficiency.
3.1.5 Contact the Load Dispatcher or the National Weather Service for an extended weather forecast.
3.1.6 Transmit (potential) plume direction status to Security Team Leader.
Update with changes.
3.1.7 Report dose projection and field survey results to offsite organizations, as requested by the Emergency Director, or Site Emergency Coordinator.
3.2 Turnover of Dose Assessment Responsibilities 3.2.1 All turnovers of Dose Assessment responsibilities-should include the transmittal of the information listed in Appendix EP 210-1, as available.
3.2.2 The transfer of Dose Assessment responsibility from the TSC to the EOF shall occur.upon agreement by the Emergency Director, the Site Emergency Coordinator and the Dose Assessment Team L6aders'at the TSC and EOF.
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4.1 Turnover of Dose Assessment R,esponsibilities
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5.0 SUPPORTING INFORMATION
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,i The purpose of this procedure is to provide guidelines:
for the activation of the Dose Assessment Team in the Technical Support Center (TSC) and the transfer of Dose Assessment functions to the Emergency Operatiotts
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Facility (EOF).
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5.2 Criteria for Use
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5.2.1 The Dose Assessment Team should be activated,and this procedure implemented at the discretion of tha' Emergency Director or when'the Technical Supp' ort s
Center (TSC) is activated.j' i
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5.3 Special Equipment i.
None
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EP-210 Rev. 6 Page 4 of 5 MJR/MAC/nlp 5.4 References 5.4.1 EP-222, Field Survey Group 5.4.2 EP-294, Dose Assessment Team Phone List 5.4.3 *EP-315, Calculation of Offsite Doses During a Radiological Emergency Using RMMS in the Manual Mode 5.4.4 *EP-316, Cumulative Population and Near Real-Time Emergency Dose Calculations for Airborne Releases Manual Method 5.4.5 *EP-317, Determination of Protective Action Recommendations 5.4.6 *EP-318, Liquid Release Dose Calculations Method for Drinking Water 5.4.7 *EP-319, Fish Ingestion Pathway Dose Calculation 5.4.8 *EP-325, Use of. Containment Radiation Monitor to Estimate Release Source Team
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.l EP-210 Rev. 6 Page 5 of 5 MJR/MAC/ nip AFPENDIX EP 210-1 i
TURNOVER OF DOSE ASSESSMENT RESPONSIBILITIES Turnove'r of dose assessment responsibility from one Dose Assessment l team / location to another Dose Assessment team / location should include the transmittal of any available information listed below:
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Time of reactor trip / scram
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Release point
- 3. ' Effluent type (gas or liquid)
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Start time'ofsrele'ase,'
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Estimated duration of release',
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6.
Containment informations primary containment leakage, drywell i
purge status 7.
Post LOCA radiation monitor readings e
8.
Meteorology:
Wind speed, wind direction, sigma theta, delta 4
temperature, ambient temperature
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Stability class h.
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- 10. (Potential) rele'ase type (ground, elevated, mixed mode)
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x l 11. Method (s) used to calculate doses 3
A ~l 12. Source term basis v
l 13. Results of dose calculasic sU\\
A.
Location, value - peak h Q, depleted X/Q, undepleted X/Q, peak Whole Body gamma dose rate, peak thyroid dose B.
Time to reach Protective Action Guides q'
1
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Whole body gamma dose rate - site boundary, 2 mi, 5 mi, 10 mi a
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D.
Phone 9. wherie "grelieved" DATL can be reached E.
-Protective Action' recommendations, if any were made N
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- 14. Field Survey Squad (s) status,19 teams available, dispatched, time dispatched, location and results, team, exposures.
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PHILADELPHIA ELECTRIC COMPANY g gf LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-325 USE OF CONTAINMENT DOSE RATES TO ESTIMATE RELEASE SOURCE TERM 1.0 PARTICIPANTS 1.1 Dose Assessment Team shall perform these calculations.
2.0 ACTIONS-IMMEDIATE l
2.1 Obtain time after shutdown in hours.
2.2 Determine the CONTAINMENT DOSE RATE using one of the following methods, li:ted in order of preference:
i 2.2.1 Using the Containment Post Loca Monitor readings from RR-26-191A,B,C,D (291A,B,C,D) on Panel 10C600 (20C600) in the main pentrol room or from 4
the Radiation Meteorological $ $lnitoring System take the averag.eggRp te)2 highest (RMMS);
readings.
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y 'p o.V. %. h Containment Area (Ita.diatilon.<:., Monitor reading from 2.2.2 Channel 14 on thefARM reconter in the main c o n t r o l r o o s r. h ?
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L 2.2.3 If the abb.vd'. ins'truinentat'lon %sCapt Mvailable, l
request the. Personnel-Safety. Team't,eader to obtain a portable survey, mete 0 reading at'one of l
the locations indicated.'i,n" Appendix EP-325-6..
Perform the following calediation to estimate the containment dose ra'teNus'ing the dose reduction factor, A, for thei/ appropriate location and time from Appendix EP-425-6.
Containment =
Survey (mR/hr) x A Dose Rate (R/hR)
Reading 1000
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l EP-325 Rev. 4 Page 2 of 9 VAW/ MPG /rgs 2.3 Determine Fuel Inventory Fraction (FIF) available for release using the appropriate graph and EP-325-1.
Post Loca Rad Monitor, RR26-191(A-D)
EP-325-2 Area Rad Monitor, Channel 14 EP-325-3 Portable Survey Meter EP-325-(2 or 3) 2.4 To evaluate leakage from primary containment to the reactor enclosure and then through Standby Gas Treatment l
System, use EP-325-4.
2.5 To evaluate the release rate due to drywell purging, use EP-325-5.
2.6 Use the estimated release rate to determine offsite projected doses.
The Dose Assessment Team Leader will select the appropriate calculation method (i.e, EP-316 Cumulative Population Dose Calculations for Airborne Releases or the RMMS Computer).
- 3. 0 g ACTIONS-FOLLOW UP s
None 4.0 APPENDICES 4.1 EP-325-1 Percent of Fuel Inventory Airborne in the Containment Vs. Approximate Source and. Damage Estimates l
4.2 EP-325-2 FIF = F (Containment Post Loca Rad Monitor) l 4.3 EP-325-3 FIF = F (Containment Area Rad Monitor-Channel 14)-
4.4 EP-325-4 Primary Containment Source Term 4.5 EP-325-5 Drywell Purge Source Term 4.5 EP-325-6 Portable Survey Meter -
Dose Reduction Factor "A"
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l EP-325 Rev. 4 Page 3 of 9 VAW/ MPG /rgs 5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to estimate the activity in the containment following a LOCA, and then to determine release rates into the environment via leakage or purging.
5.2 Criteria for Use 5.2.1 This procedure shall be implemented by the Dose Assessment Team when containment release rates l
are to be estimated and a containment' atmosphere sample is not available.
5.3 Special Equipment None 5.4 References s
5.4.1 Limerick Generating Station Emergency Plan, Section 6.2.3.1 Containment Monitors 5.4.2 BLP-28640 Containment Radiation Monitors Post Loca Dose Rates vs. Time Curves 5.4.3 FSAR Table 15.6-14 Loss of Coolant Accident:
Activity Airborne in Primary Containment 5.4.4 EP-316-Cumulative Population Dose Calculations For Airborne Releases 5.4.5 Letter E. C. Kistner to G. M. Leitch dated
]
September 17, 1984 on Emergency Preparedness Action Item 50-352/84-18-49.8 5.4.6 Letter E. C. Kistner to G. M. Leitch dated' November 21, 1984 on Emergency Preparedness Appraisal Action Item 50-332/84-18-498 s
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EP-325 Rev. 4 Page 4 of 9 VAW/ MPG /rgs APPENDIX EP-325-1 PERCENT OF FUEL INVENTORY AIRBORNE IN THE CONTAINMENT VS. APPROXIMATE SOURCE AND DAMAGE ESTIMATE (FIF)
Fuel
% Fuel
- Curve Inventory Inventory No.
Fraction Released Approximate Source and Dtmage Estimate l
1 1
100.
100% TID-14844, 100% fuel damage, potential core melt l
.5 50.
50% TID noble gases, TMI source l
2
.1 10.
10% TID, 100% NRC gas activity, total clad failure, partial core uncovered l
.03 3.
3%~ TID, 100% WASH-1400 gap activity, major clad failure l
3
.01 1.
1% TID, 10% NRC gap, Max. 10%
clad failure l
4 1N3 1
.1% TID, 1% NRC gap, 1% clad failure, local hekting of 5-10 fuel assemblies l
5 1N4 01
.01% TID,.1% NRC gap, clad failure of 3/4 fuel element (36 rods) l 6
INS -
1.0N3
.01% NRC gap, clad failure of a few rods l
IN6 1.0N4 100% coolant release with spiking l
7 SN8 5.0N6 100% coolant inventory release l
1N8 1.0N6 Upper range of. normal airborne noble gas activity in containment
- 100% Fuel' Inventory =100% Noble Gases +25% Iodines +1% Particulates-
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EP.325 Rev. 4 Page 5 of 9 VAW/ MPG /rgs APPENDIX EP-325-2 FIT = F (CONTAINMENT POST LOCA RAD MONITOR)
RR26-191A, B,C, D
l Time After Shutdown
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Fuel Inventory Fraction (FIT) 1 1
2
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1N3 5
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l EP-325 Rev. 4 P' age 6 of 9 VAW/ MPG /rgs APPENDIX EP-325-3 FIT = F (CONTAINMENT AREA RAD MONITOR - CTIANNEL 14) l '%
Time After Shutdown - Hours y.-...
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1N4 6
1N5 7
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EP-325 Rev. 4 l
Page 7 of 9 VAW/ MPG /rgs
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APPENDIX EP-325-4 PRIMARY CONTAINMENT SOURCE TERM LEAKAGE Time After Shutdown uCi/s Release Rate 2 hrs 8 hrs 1 day 4 days 30 days of Radioiodines 150.5 93.6 52.4 19.5 1.5 uCi/s Release 1.16P6 2.86P6 4.67P6 5.71P6 1.91P5 Rate of Noble Gases Release Rate uCi Fuel inventory Release uCi Radiciodines s
Fraction Rates s
Radioiodines
=
X Release Rate uCi Fuel inventory Release uCi g
Fraction Rates s
Noble Gas s
Noble Gas
=
X Assumptions:
1)
Primary Containment Leakage is.5% per day 2)
Perfect mixing in primary and secondary containment Reactor enclosure recirculation fans on at 60,000 cfm 3)
Reactor enclosure recirculation filters 95% efficient 4) for iodine removal 5)
Standby gas treatment system fans on at 625 cfm 6)
Standby gas treatment system filters 99% efficient for lodine removal 7)
Secondary containment free volume is 1,800,000 cubic feet 8)
Loss of coolant accident drywell source ters 9)
No drywell purging
l EP-325 Rev. 4 Page 8 of 9 VAW/ MPG /rgs l
APPENDIX EP-325-5 RELEASE RATE DUE TO DRYWELL PURGE CALCULATION Time After Shutdown Curies 2 hrs 8 hrs 1 day 4 days 30 days Radioiodines 2.5P7 1.5P7 8.4P6 3.lP6 2.4P5 in drywell Curies 4.9P8 3.2P8 2.lP8 1.lP8 3.3P6 Noble Gas in drywell Curies In Drywell
-(1.53N4 x 1.lP4 cfm x DPH)
RELEASE x 1.lP4 cfm x 4.26N2 =
RATE l FIF x xe RF uCi/sec
-(1.53 x
)
x 1.lP4 x 4.26N2 = Iodine release rate x
xe f
(
-(1.53 x
)
x xe x 1.lP4 x 4.26N2 = Noble gas release rate ASSUMPTIONS 1.
Perfect mixing in primary containment.
2.
Primary containment volume is 391,250 cubic feet.
3.
Standby gas treatment filters 99% efficient for iodine removal.
4.
Source term - Loss Of Coolant Accident.
5.
RF = reduction factor Iodine = 100 Noble Gas = 1.0 l 6.
Drywell Purge Flow Rate = 11,000 cfm.
7.
DPH = Duration of purge, hours n
.s S EP-325 Rev. 4 l
Page'9 of 9 VAW/ MPG /rgs l
APPENDIX EP-325-6 PORTABLE SURVEY METER - DOSE REDUCTION FACTOR "A"
Portable Survey Time (Hours)
Meter Location 0
8 24 240 Outside Equip. Hatch Shield Door (253' el.
4" above. ground) 7.65P4 1.97P5 1.51P6 1.20P8 Bet. Shield Door and
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Equip. Hatch (253' el.
4 4" above ground) 3.2P1 3.6P1 4.9P1 7.9P1 Outside Drywell Wall at 253' el.
1.75P5 5.25P5 4.82P6 6.33P8 s
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
L
.E WASHINGTON, D. C. 20555 8
December 9, 1986
.....,o 50-352/353 Limerick l
MEMORANDUM FOR:
Chief, Document Management Branch, TIDC FROM:
Director, Division of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be made publicly available, jh$rs l l
=^ )
Donnie H. Grimsley, Director Division of Rules and Records,jp Office of Administration
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Attachment:
As stated e
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REQUL% TORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
A ION NDR:4!Nr?2f?20fft-DOC.DATE: 86/11/21 NOTARIZED: NO DOCKET O FA IL: 50-352 Limeric k Generating Sta' tion, Unit 1, Philadelphia Ele 05000352 50-353 Limerick Generating Station, Unit 2, Philadelphia Ele 05000353 AUTH.NAME AUTHOR AFFILIATION DALTROFF,S.L.
Philadelphia Electric Co.
RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Region 1.
Office of Director SUB JECT: Forwards CF version of revised emergency plan implementing procedures, including Rev 6 to EP-201, " Technical Support Ctr..." & EP-210. " Dose Assessment..." & Rev 4 to EP-325, "Use of Containment Dose Rates...."
DISTRIBUTION CODE: AX45D COPIES RECEIVED: LTR __ ENCL __ SI ZE:
h TITLE: Emergency Plan or Implementing Procedures (Proprietary)
NOTES: LPDR 2cys Transcripts.
05000352 LPDR 2cys Transcripts. Application for permit renewal filed.
05000353 RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME LTTR ENCL ID CODE /NAME LTTR ENCL DWR PD4 LA Y
1 1
1 MARTIN,R 1
1 INTERNALGDM[DRD d
1 1
IE/DEPER/EPD # 2.
1 1
1 1
REG FILES
$/
1 1
IE/DEPER/IRB p NOTES:
2 2
TOTAL NUMBER OF COPIES REGUIRED: LTTR 9
ENCL 9
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