ML20127F598
| ML20127F598 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/30/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20127F590 | List: |
| References | |
| PROC-850430-01, NUDOCS 8505200521 | |
| Download: ML20127F598 (137) | |
Text
{{#Wiki_filter:.__ Pr.g3 1 of 5 Revision 35
. 04/01/85 LIMERICK GENERATING STATION 3850072850 EMERGENCY PLAN PROCEDURE INDEX e
l PROCEDURE REV. , DATE SIGNED DATE OF LAST NUMBER NO. TITLE' BY SUPER. PERIODIC REVIEW EP-101 4 Classification of Emergencies 03/25/85 EP-102 8 Unusual Event Response 03/28/85 EP-103 9 Alert Response '03/28/85
- EP-104 9 Site Emergency Resconse 03/28/85 EP-105 9 General Emergency Response 03/28/85 EP-10G 4 Written Summary Notification 04/01/85 EP-110 6 Personnel Assembly and Accountability 03/14/85 EP-120 3 Site Emergency coordinator 04/01/85 EP-201 4 Technical Support Center (TSC) Activation 03/29/85 03/29/85 EP-202 3 Operations Support Center (OSC) Activation 12/12/84 EP-203 5 Emergency Operations Facility (EOF) Activation 04/01/85 04/01/85 EP-208 4 Security Team 12/12/84 EP-210 3 Dose Assessment Team 12/12/84
- EP-211 2 Field Survey Group 03/25/85 EP-220 CANCELLED
. EP-221 CANCELLED EP-222 CANCELLED EP-230 5 Chemistry Sampling and Analysis Team 03/14/85 EP-231 8 Operation of Post-Accident Sampling Systems (PASS) 03/29/85 EP-232 CANCELLED 8505200521 050430 PDR ADOCK 05000352 F PDg
PCg3 2 of 5 Revision 35
, 04/01/85 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX P
PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-233 5 Retrieving and Changing Sample Filters and' , Cartridges from the Containment Leak Detector During Emergencies 03/14/85 EP-234 5 Obtaining Containment Gas Samples from the Containment Leak Detector
- During Emergencies 03/14/85 EP-235 5 Obtaining Reactor Water
- Samples from Sample Sinks Following Accident Conditions 03/14/85 EP-236 5 Obtaining Cooling Tower Blowdown Line Water Samples Following Radioactive Liquid Release after Accident Conditions 03/14/85 EP-237 7 Obtaining the Iodine /
Particulate and/or Gas Samples from the North Vent Wide Range Gas Monitor (WRGM) 03/28/85 EP-238 4 Obtaining Liquid Radwaste Samples from Radwaste
- Sample Sink Following Accident Conditions 12/12/84 EP-240 CANCELLED EP-241 8 Sample Preparation and Handling of Highly Radioactive Liquid Samples 03/14/85 EP-242 5 Sample Preparation and Handling of Highly Radioactive Particulate Filters and Iodin ~e -
CJ-tridges 03/28/85 EP-243 5 Sample Preparation and Handling of Highly Radioactive Gas Samples 12/12/84 EP-244 3 Offsite Analysis of High Activity Samples 03/12/85
Pcg3 3 of 5 Revision 35
, 04/01/85 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX i
PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW { EP-250 2 Personnel Safety Team 12/12/84 l EP-251 2 Plant Survey Group 12/12/84 EP-252 5 Search and Rescue /First Aid Group 04/01/85 04/01/85 EP-253 0 Personnel Dosimetry, Bioassay, and Respiratory Protection Group 12/12/84 , EP-254 3 Vehicle and Evacuee Control Group 02/04/85 EP-255 2 Vehicle Decontamination 12/12/84 EP-260 2 Fire.and Damage Control Team 12/12/84 EP-261 2 Damage Repair Group 12/12/84 EP-272 4 Philadelphia Electric Company Officials Phone List 02/04/85 EP-273 4 Limerick Station 1 Supervision Call List 02/11/85 EP-275 CANCELLED EP-276 5 Fire and. Damage Team Phone List 01/24/85 l EP-277 6 Personnel Safety i Team Phone List 02/11/85 EP-278 5 Security Team Phone i List 03/25/85 EP-279 4 Emergency Operations , Facility (EOF) Group Phone List 01/22/85 EP-200 6 Technical Support Center Phone List 03/12/85 EP-282 4 Government and Emergency Management
- Agencies Phone List 01/22/85 EP-284 4 Company Consultants and Contractors Phone List 01/22/85 EP-287 3 Nearby Public and Industrial Users of Downstream Water 02/11/85 2
Prgo 4 of 5 Revision 35 04/01/85 4 LIMERICK GENERATING STATION ,
- EMERGENCY PLAN PROCEDURE INDEX i .
, PROCEDURE REV. DATE SIGNED DATE OF LAST l NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW
- EP-291 5 Staffing Augmentation 02/25/85 l EP-292 7 Chemistry Sampling and
, Analysis Team Phone
- List 03/14/85
+ EP-294 5 Dose Assessment Team 3 Phone List 02/04/85 EP-301
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1 Operating the Evacuation i Alarm and River Warning
. System 12/12/84 i
EP-303 3 Local Evacuation 12/12/84 EP-304 3 Partial Plant Evacuation 12/12/84 EP-305 5 Site Evacuation 03/25/85 EP-306 1 Evacuation of the Information Center 12/12/84 EP-307 2 Reception and Orientation of Support Personnel 12/12/84 EP-312 3 Radioactive Liquid . Release 02/25/85 EP-313 2 Distribution of Thyroid i Blocking Tablets 12/12/84 EP-314 1 Emergency Radiation
! Exposure Guidelines , and Control's 03/29/85 . EP-315 5 Calculation of Offsite
- Doses During a (Potential)
Radiological Emergency i Using RMMS in the
, Manual Mode 04/01/85 EP-316 3 Cumulative Population and Near Real-Time Emergency Dose Calculations for Airborne Releases Manual Method 04/01/85
, EP-317 3 Determination of Protective Action Recommendations 03/25/85 EP-318 2 Liquid Release Dose calculations Method for Drinking Water 04/01/85 04/01/85
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, Paga 5 of 5 Revision 35
, 04/01/85 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST
. NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW
{ EP-319 2 . Fish Ingestion Pathway , Dose Calculation 03/29/85 03/29/85 EP-325 3 Use of Containment Dose Rates to Estimate Release Source Term 02/27/85 EP-330 4 Emergency Response Facility Habitability 03/14/85 EP-401 2 Entry for Emergency Repair and Operations 12/12/84 EP-410 3 Recovery Phase Implementation 03/29/85 EP-500 2 Review and Revision of Emergency Plan 12/12/84 t 9 6 t 0 m4 m w
. .l EP-106, R3v. 4
. Page 1 of 6
. 3850072860 v^W/ /r9-9
#W t PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE I
I k EP-106 WRITTEN
SUMMARY
NOTIFICATION h, . l.0 PARTICIPANTS I Emergency Director shall direct the Shift Technical
? 1.1 ! Advisor or other assigned Engineer to write a F summary report following the closecut of an unusual i event or the closecut or de-escalation of an Alert, r Site Emergency or General Emergency.
5~ Shift Technical Advisor or assigned engineer shall 1.2 write a summary report.
.k i
2.0 ACTIONS - IMMEDIATE s. (
- 2.1 Emergency Director shall:
2.1.1 Direct the Shift Technical Advisor or assigned r engineer to prepare thejwritten summary in accordance with this p ocedure. E COMPLETE WITHIN O S OF CLOSEOUT OR DE-ESCALATION P l OF AN ALERT, SI. RGENCY OR GENERAL EMERGENCY;
, ! COMPLETE WITH' -
. ' S OF CLOSEOUT OF AN UNUSUAL i l EVENT.
2.2 Shift Tec. or'shall: i 2.2.1 Obtain
%~ ary information to complete ) Appendp '
6 Emergency Clase Closecut/ Reduction J., Repo 6.g 2.2.2 F [n* ollowing informat n y, eT a.
~
L' nter the num i th'e p f fet*g - g units. If th kn,t,ccc4dirEd a ft '1.
,- J both units, e .
h, E e L s 2-Enterthedocketnumbebt ie 11 eee. - gt e toSem 1ee - os2 g bq LeS em 2 esoegg g . . .. .. ... .. _=. . .~... _ ....
l l . EP-106, Rev. 4 l Page 2 of 6 VAU/JLP/rgs
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- c. Item 3 - Enter the total number of pages.
- d. Item 4 - Enter a concise description of r
- the event.
f
; e. Item 5 - Enter the date of the event.
7
- f. Item 7 - Enter the date of the report.
[ g. Item 8 - Enter name and docket number of Unit 2 if the event occurred at both units. LGS UNIT 2 05000- (353)
$ h. Item 9 - Enter the operating mode.
A ff 1. 2. Power Operation Startup 7
- 3. - Hot Shutdown
- 4. - Cold Shutdown L- 5. - Refueling
- i. Item 10- Enter the percent of licensed thermal power at which the reactor was operating when the event occurred.
$ j. Item 12 - Enter the name of the Shift g,t Superintendent. .
e f~ h. Item'17 - Enter a brief description of
' the circumstances and reasenc - behind the closecut of the
- Unusual Event or the closecut or
' de-esenlation of the Alert, Site
- Emergency or General Emergency.
'(
e. 2.2.3 Submit the report to the Emergency' Director. I k 3.0 ACT!ous - FOLLOMUP 3.1 Enerconey Director challt , l 3.1.1 Review the report for completeness and accuracy.
! 3.1.2 Have the Station Superintendent or Assistant Station Superintendent and the Operations Engineer or Technical Engineer review the report. This may require review over the telephone.
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EP-106, Rev. 4 [. Page 3 of 6 ); - e VAW/JLP/rgs- , (
,. 341.3 Have the report telecopied within eight at twenty-four hours as appropriate to the NRC Operations Center or Region I office via the following phone number:
'/ :;. .. .. . .y NRC Operations Center I 1 M
f - ~ ' .: Sh MY
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l.A. _Qi,.l _ ',Ti..!k . , . ( . :_ , <:3, . Region I Office *
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97 , a ,. ~...-- ) 0$ '. ;h , . 3.1.4 Call and verify that the report was received:
.- 1
'NRC Operation Center
/
Region I Office 3.1.5 If the port cannot be telecopied, have t h report hand delivered within eight hours to the f I Region I Office 631 Park Ave. V King of Prussia, PA 19406 l 3.1.6 Forward a copy of the report to NRMS. i 4.0 APPENDICES
- 4 .1 EP-106-1 Emergency Class Closecut/De-escalation Report a
5.0 SUPPORTING INFORMATION
* '\ '
5.1 Purpose .. 9,,,
.4. ,' -
j The purpose of this procedu
, 4 g/
guidelines for the eight. ~ cl.Ao'ptov%de ttentsummary (- i notification to the N f i'hgeJ,osecut or de , I escalation of an Ale . ' ' '- i "Eme3g6ncy or General I Emergency Classif '.n'd f'or the twenty-four hour written .otification to the NRC
, following clo .f'an ynusual Event.
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-l EP-106, RGv.'4 Page 4 of 6 VAW/JLP/rgs
- 5.2 Criteria for Use .
! This procedure shall be implemented following a I closecut of an Unusual Event or the closecut or de-escalation of an Alert, Site Emergency or General l'
Emergency Classification per EP-101 Classification of Emergencies. . 5.3 Soecial Ecuipment
? None . 5.4 References t ! 5.4.1 NUREG 0654, Criteria for Preparation and Evaluation
- Rev. 1 of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 5.4.2 EP-101 Classification of Emergency m
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, . . EP-106, RGv. 4 l
Page 5 of 6 P . VAW/JLP/rgs k . c . PACE 1 0F 2 f E0(if / DC.ESCALATIOl( REP ()RT g,, FAC2LITT mA#g (1) 00CET mesta (a) Pne'3 jl LInstater samanATIso sTATZon nNIT 09 3g0:0:0; g g I er ; as 117LE (4) .
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l' EVENT SAft (s) REPORT DATE (7) OTIER FACTLTTits trVELVED (8)
. 80 DA Ta no DA Ta ' FACILITT hAMES DoctET aufsta (5) f I f I 1 I f I
5 I l I I f f I f I f f h ' OPERAT1st THIS EPOET 15 SutFTTTD PURSUANT TO Tit EEUUTEliporf tF 10 CFR f r *=* ***=m8 == *W(ll)
" UI 20.402(b) 10.40s(s) so.73(a)(2)(tv) - T3.71 (b) u"nt - to.40s(a)(1)(t) so.W(s)(1) So.73 (a)(2)(v) 73.71 (c)
' ' to.40$(a)(1)(st) J,.
' so.as(c)(2) - so.73 (a)(2)(ett) te
- as.40sta)(1)(1st) so.73(a)(r)(t) -
so.73 (a)(2)(es)(A) *ofwa
*1= as 8a (seectriut3
<- an.40sta)(1)(tv) so.7a(a)(r)(tt) -
ro.sestaittitv) w tsrett,irgest so.73,(a)(a)(es)(s) an t tair,it.) Ltcrastt contact sca fu t 3 trrh tr)
, 5AME TELEPMcNE su s te .
, IIIFT SUPEILINTIMBeirr 2,1,3 3,2 ,7 ,1,2 ,0 ,0 ,
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- y suPPLDENTAL REPORT EIPCCTED (14) Mo OA TR (If yes, templete EXPECTD EIPECTG sleMI55tGB 1 fts $12MI55*0m Daft) E En DATE (15) t t t A85 TRACT (Liett to 1400 sposes, t.e., appresteetely fiftees stasle. space twowritten Ifees) (16)
This report la to entisfy the 8 hour writtes og===ary requirasset fee a elesecut of an Alert, Site Eastgesey or Generet "A 7. Sa asserdasse with NUREC-0654 la land +4a. 29 Lessa var.+te. seamsay regptremset 4.% =Jamaawt en Gemet Gsent. /
. Itse '17 of this report is a brief description of the eleseest of the event. If applicable, a LEE will follow in the Pequired time fress.
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. l EP-106, Rav. 4
. Page 6 of 6 VAW/JLP/rgs 3
f Pact 2 or 2 I N- J
$ CLOSEOUT / DE-ESCALATION REPORT
'b kh CY{f IE 06-1 LTCYNEZE ZYENT REPat? (1.Et TEXT CONTINDATION f FA;3LITT IWE (1) DOCET frupsta (2) PAGE I3)
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! r. . b r j. IL ' l VMINCATioM c P- NRc. Re.ce.pT op: 8f. PORT" VeRie:Ep SY NT E. l^
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j J j EP-120 Rev. 3 ) F*S* f4 s 3850072870 . JAW /MJM/mc PHILADELPHIA ELECTRIC COMPANY N# LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE D EP-120 SITE EMERGENCY COORDINATOR 1.0 PARTICIPANTS 1 1.1 Site Emergency Coordinator shall supervise the activation snd manage the activities of the Emergency Operations Facility.
;, 2.0 ACTIONS-IMMEDIATE 2.1 Site Emeroency Coordinator shall direct the Load . Dispatcher to activare the Site Emergency Coordinator's call list.
2.2 Site Emergency Coordinator for Site and General emergencies shall: 2.2.1 Proceed to the Emergency Operations Facility. 2.2.2 Become cognizant of the situation directly from the Emergency Director.
#') .- '2.2.3 Announce t%1E6FIpstsonnel chat rhe_is assuming the 2
Emergencyipj (e.c. tor that[.hef,is (assuming control ofrole of
~
the emergency r'5s'p6 hse'organhaMioH. f! 2.2.4 Supervise the activ13s atloQ ~ g W .'.'glgfythe EOF. 2.3 Site Emergency _Coordinbtor'shall as appropriate request tile. collection et; environmental station
-g ,
samples pH@C4al5.,) i&lQe,(e jhd been a radioactive material release.
- m. 2.4 Through the Dose Assessment Team Leader, direct all radiation surveys conducted in off-site areas.
- When field data becomes available, discuss the ~'
relationship of field data to calculated data with l Dose Assessment Team Leader and Health Physics and Chemistry Coordinator in order to resolve any discrepancies. t
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l EP-120 Rev. 3
' Page 2 of 4 VAW/MJM/mc y
i 2.5 Request activation of corporate support functions i through dialogue with the Emergency Support Officer.
' 2.6 Obtain protective action recommendations from the ; l Dose Assessment Team Leader. ,
2.6.1 Discuss recommendations with the Emergency Director J and Emergency Support. Officer to assure that all parties are informed of the recommendations before j they are made to government authorities.
?
2.6.2 Meet with the Commonwealth of Pennsylvania i representatives in the Emergency Operations Facility to ensure that questions on protective actions to be applied are answered prior to formal (_ recommendation. C 2.6.3 Provide protective action recommendations to Pennsylvania Bureau of Radiation Protection. 2.6.4 Update these recommendations as new data become available or conditions change.
~
2.7 Upon completion of EP-318, Liquid Release Dose Calculations for Drinking Water, implement EP-287, e if necessary. b 3.0 ACTIONS - FOLLOW-UP 9 '
/ 3.1 Site Emercency Coordinator is responsible for the ', following:
3.1.1 Maintaining awareness of plant status and being
- alert to potential off-site consequences of the emergency.
3.1.2 Conducting periodic briefings for Emergency y Operations Facility personnel. 3.1.3 Coordinating between the on-site emergency l personnel and the off-site emergency personnel, g when activated, to obtain necessary additional ~.. facilities, equipment, supplies, personnel, or
-~
3 technical services.
- i 3.1.4 Coordinating with the Emergency Support Officer concerning personnel, equipment, and materials expected to arrive at the plant site.
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! EP-120 Rav. 3 ;
Page 3 of 4 l VAW/MJM/mc l 3.1.5 Ensuring preparations are made for check-in of ! incoming personnel, especially with regard to site i
, area access control, indoctrination of visiting personnel, maintenance of proper security, issuing dosimeters and preparing exposure records, and f
distribution of protective clothing and equipment. he 3.1.6 Providing management direction for the 1 establishment and functioning of the Emergency g Support Center.
} 3.1.7 Continuing to supervise the operation of the Emergency Operations Facility.
L i 3.1.8 Reviewing with the Emergency Director the current status of information provided to governmental
! agencies and relieving the Emergency Director of
[- this responsibility. The Site Emergency p, Coordinator will then serve as the primary contact c for Federal, State, and local emergency response
@ agencies which dispatch personnel to the plant p vicinity, and will provide status and assessment information to governmental agencies.
r. f~ 3.1.9 Provide direction for Philadelphia Electric emergency response personnel who are dispatched to the plant site and for support personnel activated by Philadelphia Electric Company. r-3.1.10 Keeping the Emergency Support Officer and the Emergency Director apprised of actions taken and of f[ consequences off-site. NU l 3.1.11 Coordinating with the Emergency Director and the i- Emergency Support Offi_cer to determine when to i terminate the initial phase and enter the recovery phase, informing various agencies and organizations when the modification is to be implemented. T
- b. 4.0 APPENDICES l None p.
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] l EP-120 Rsv. 3 4 , Page 4 of 4 i VAW/MJM/mc
, 5.0 SUPPORTING INFORMATION 5.1 Purcose t
i 1,- The purpose of this procedure is to provide i guidelines to delineate the responsibilities and I actions of the Site Emergency Coordina*or. p 5.2 Criteria For Use t i The position of Site Emergency Coordinator is -i normally activared at a Site or General Emergency i or at the discretion of the Emergency Director. i
} 5.3' Special Ecuipment a
None y
- 5.4 References 9;
's 5.4.1 EP-203 Emergency Operations Facility (EOF) Activation _ 5.4.2 EP-307 Reception and Orientation of Support Personnel 5.4.3 EP-317 Determination of Protective Action
- Recommendations 5.4.4 EP-287 Nearby Public and Industrial Users of
- Downstream Water
- {- 5.4.5 EP-C-218 Health Physics and Chemistry Coordinator
' ,'r a L 5'.4.6 EP-C-315 Recovery of Emergency Radiological .
< Environmental Monitoring Samples from Peach Bottcm
; Units 2 and 3 and Limerick Units 1 and 2
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l EP-203, Rev. 5 Page 1 of 20 3850072880 v^wnLPdmv xn t PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION (/[/[ EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-203 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION
?
1.0 PARTICIPANTS 1.1 First eerson arriving at the EOF shall activate the EOF by performing the necessary steps in this procedure. 1.2 Communicator for the Site Emergency Coordinator
- shall man communication lines and log information.
1.3 Site Emeroency Coordinator shall direct operation at the EOF.
;- 1.4 Status Board Recorders shall obtain and post information. 4 2.0 ACTIONS-IMMEDIATE g Y
.. t 7 PERSONNEL ARE DESIGNATED AND ASSIGNED GENr L I " N THE E EOF BY EP-279, EOF GROUP PHONE LIST. ~$
' '9 4
4+h
," 2.1 First eerson arriving shalla y
- ' . A 2.1.1 Obtain keys, ifnecessarY[ ~
. rom the Plymouth Dispatch offf EOF,..
. } t.h.gip.s 'j gy)f
. :x:
.. c l 2.1.2 Perform appendices. 4 BP-203-10.- h e 2.1.3 a ke person b.s.m o"the m zfr entrance Assignthefir[
of the EOF t Sag
- ess until'securitykarrives for the pur ses 4f W
' ~
and to esta - _ personnel ac a 2. t y . y aq .m p. g u ejne y ENSURE THAT PE $1NEL SIGN h5 AND . ON l INDIVIDUALS ON ACCESS LIST OR CLEARED BY PERSONNEL PRESENT ARE ALLOWED TO ENTER THE EOF. ACCESS LIST l IS IN CABINET NUMBER 3. 9 . .j
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l _ EP-203, Rev. 5 Page 2 of 20 VAW/JLP/jmv t 2.1.4 Assign an individual (as soon as one is available), the duties of the Site Emergency Coordinator Communicator. The Communicator shall perform the steps outlined in Section 2.2. [ 7 2.2 Communicator for the Site Emergency Coordinator shall: e f 2.2.1 Use EP-279, Emergency Operations Facility Group Phone List to call in additional personnel to staff
'f the EOF, if necessary.
u f 2.2.2 Inform the Site E=ergency Coordinator when the
, above communications capabilities have been
- verified or of any problems.
2.2.3 As personnel arrive, man communications lines on the Site Emergency Coordinator's desk and maintain a communications log centaining information received from and sent to other facilities and E other organizations. I ENSURE ALL PERTINENT ACTIONS AND NOTIFICATIONS ARE b LOGGED. 2.3 Security cersonnel shall:
-- l 2.3.1 Post themselves at the front of the EOF.
t 2.3.2 Control access to the EOF by al'1owing personnel who c exhibit badges listed below access. .h l Philadelphia Electric Identification Cards / i l Bechtel Construction Site Badge i Bureau of Radiation Protection Identification Cards l l Pennsylvania Emergency Management Agency Cards I. I Nuclear Regulatory Commission Identification Cards a v l Federal Emergency Management Agency Identification
*i l Cards l City of Philadelphia r
-- All other personnel requesting access should be cleared through the Site Emergency Coordinator, Emergency Preparedness Coordinator, or the Planning l and Scheduling Coordinator.
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? EP-203, Rav. 5
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- - VAW/JLP/jmv t
3.0 ACTIONS FOLLOW-UP SITE EMERGENCY COORDINATOR SEALL ASSUME CONTROL AFTER HE HAS ARRIVED AND IS COGNIZANT OF THE SITUATION. I 3.1 Site Emercency Coordinator shall: g 3.1.1 Assign personnel to be status board keepers and y direct them to perform the steps outlined in ff section 3.3 of this procedure. v LGS Plant Parameter Status Board f , a. [ -
- b. Plant Parameter Trends Board
- c. Event Chronology Status Board h d. Staff Assignment Status Board l e. Headquarters Support Request Status Board rr r
- f. Offsite Communications Status Board
_ l g. Dose Assessment Status Board i h. Field Survey Group Status Board l 3.1.2 Ensure that an individual has b'een assigned as the Site Emergency Coordinator's Communicator.
% 3.1.3 Inform the Technical Support Center when the
, t Emergency Operations Facility is operational,
; manned and in control of its designated 3 responsibilities.
tr. 1 3.1.4 Brief the EOF Staff periodically on the status of I the emergency and pertinent plant conditions. t I 3.1.5 Direct transmission of all Status Board information
-l to appropriate Headquarters Emergency Support gg Center Status Board Recorders.
i 3.1.6 Perform actions in EP-120, Site Emergency H l Coordinator. L 3.2 Dose Assessment Team Leader shall: r 3.2.1 Complete the Dose Assessment Team Activation in l accordance with EP-210, Dose Assessment Team. 7
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l EP-203, Rev. 5 Page 4 of 20 I- VAW/JLP/jmv 3.3 Status Board Recorders shall: 3.3.1 Fill in their assigned status board (s). Format and content of the Status Boards are given I in the following appendices: t a. Appendix EP-203-1, LGS Plant Parameter Status i Board . '[ b. Appendix EP-203-2, Plant Parameter Trends Status Board
, c. Appendix EP-203-3, Event Chronology Status l Board
- d. Appendix EP-203-4, Staff Assignment Status Board
- e. Appendix EP-203-5, Headquarters Support y Requests Status Board
- f. Appendix.EP-203-6, Offsite Communications Status Board l g. Appendix EP-203-7, Dose Assessment Status Board
_. l h. Appendix EP-203-8, Field Survey Group Status l Board ,
. 3.3.2 Contact the following individuals for the various 7 Status information. ,
h a. TSC Plant Parameter Status Board Recorder for Plant Status information.
- b. TSC Event Chronology Status Board Recorder for Event Chronology information.
- c. Site Emergency Coordinator's Communicator for er. Staff Assignment Information and Headquarters yg Support Requests.
- d. Emergency Director's Communicator Site 3 Emergency Coordinator's Communicator or Control p Room Communicator for offsite communication L_ information.
- e. Field Survey Group Leader for field survey data.
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- d l EP-203, Rev. 5 Page 5 of 20 VAW/JLP/jmv 4
- f. Dose Assessment Team Leader for radiological data.
T .
! 3.3.3 Post appropriate information on assigned status board and maintain a log of all status board g , entries.
E 0 3.3.4 Review and update the status boards as changes in 4 plant conditions or information warrant. 3.3.5 Inform the appropriate Coordinator, Team or Group Leader as significant changes in status board information are noted. P 4.0 APPENDICES F 4.1 EP-203-1 LGS Plant Parameter Status Board i, 4.2 EP-203-2 Plant Parameter Trends Board 4.3 EP-203-3 Event Chronology Status Board 4.4 EP-203-4 Staff Assignment Status Board l 4.5 EP-203-5 Headquarters Support Request Status Board i gg 4.6 , EP-203-6 Offsite Communications Status Board
-\
.h l 4.7 EP-203-7 Dose Assessment Status Board ') l 4.8 EP-203-8 Field Survey Group Status Board F-4.9 EP-203-9 EOF Equipment Activation
. l 4.10 EP-203-10 EOF Phone Check List A .
t,, h 1 5.0 SUPPORTING INFORMATION .
! 5.1 Purcose E
The purpose of this procedure is to provide guidelines for the activation, manning, and conduct of operations of the Emergency Operations Facility (EOF). f
l , EP-203, R;v. 5 l Page 6 of 20
*. VAW/JLP/jmv s
5.2 Criteria for Use The EOF is activated when an event has been classified as a Site Emergency or General Emergency in accordance with EP-101, Classification of L l Emergencies, or at the discretion of the Emergency L Director. 7 Special Ecuipment
/ 5.3 l' None Y
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. ;, 5.4.3 NUREG 0696 - Functional Criteria for Emergency Response Facilities.
5.4.4 EP-279 - Emergency Operations Facility Group Phone List
~~
l 5.4.5 EP-210 - Dose Assessment Team
, l 5.4.6 EP-120 - Site Emergency Coordinator.
9 I-rb t 'k e w t
.4
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-.l g EP-203, Rev. 5 Page 7 of 20 VAW/JLP/jmv
- l. APPENDIX EP-203-1 1GS PLANT PARAMETER STATUS - UNIT. .ny , ,, ,
REACTOR PARAMETER TIME f h_ POWER-LEVEL inches CORE PLATE PRESSURE song PRESSURE CONTROL
.V1 REACTIVITY CONTROL L - + Tun SvPASS valva 8 OPEN P
e'OF RODS NOT INSERTED PAST 08 SSLC INJ AVAIL U N AVAIL REASON S R V'S A 8 C D E F G H J K L M N 8 [ A OPEN k 8 CLOSED P C {' ,,, SSLC TAMIC LEVEL g g g,, MEN LEVEL CONTROL SYSTEhl INJ AVAll UN A V AIL REASON STATUS f E" ON OFF RECIRC A CRD A 8 B ESW A NPCI 8 RCIC
- C l .
COND A D b 8 COVVENTS
,_ C b CS A h 8 e C D
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! T - D I COND TR ANS REFUEL TR ANS 88LC FME WATER
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. [ EP-203, Rev. 5 Page 8 of 20 VAW/JLP/jmv l APPENDIX EP-203-1 (CONT'D)
SHTSofS CONTAINMENT PARAMETER COMMENTS I
- SUPPRESSION POOL TEMP 'F DRYWELL TEMP 'l
. ORYWELL PRESSURE =elg
- SUPPRESSION POOL LEVEL ft CONTAINMENT 5O g %H2 i
dONTAINMENT CONTROL swP sWP gj y A VAlt REASON ch Nm Av SPRAY C OL U AVAIL A . e 5 O' 8 e i t.' oG I y RHRSW ON AV AIL UNAVAIL REASON A i- S
- C
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. IS OL ATION S ISOLATED EXCEPTIONS I I MSiv l .
l Il ' k H R N lll ~ RWCU BY HPCI l- v RCIC ,
we PG PURGL A S AMPLE Vil PCIO Vill $kM[g hs SOTS ON A V AIL UN A V AIL REASON l *t FAN A e i
TRAIN A 8 i t- ! CONTAINMENT MS R E C O M SIN E R S
< ON l AVAIL UNAVAIL REASON i
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- j l EP-203, Rev. 5 Page 9 of 20
. VAW/JLP/jmv
, l APPENDIX EP-203-1 (CONT'D) i 1
RADIOLOGICAL PARAMETERS TIME COMMENTS P NORTH STACK UCl/e c UCl/ses SOUTH STACK UC1/se D/W RAD MONITOR R/hr
~
t - REFUEL FLOOR EXN ar/kr l' I AIR EJECTOR OFFS AS arthr
?
[H R/X ENCL EXH mr/hr f- RADWASTE EXM CPM SAMPLES NORTH STACK FLOW efe p, SOUTH STACK FLOW eRSS/S sO DIN E/ oASEOUS TIME
, ,, , - ofa UCl/ce UCl/se UCI/se v-r, ;-
f[.
- REACTOR WATER METEOROLOGICAL PARAMETERS
{ SUPPRESS TIME WATER AVER AGE WIND DIRECTION (from) AVERAGE AMSIENT TEMP *F AIR
' PRECIPITATION STASILITY CLASS NORTH
- p. AVER AGE WIND SPEED mph IIAEK OROUND AVERAGE WIND SPEED sop h SOUTH g
ELEVATED STACK l[ POWER SUPPLIES -
~5
(, suePtVf MG AV Att *UNAVAft REASON
- 2
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-' S00kw OFFSfTE SOURCE 4.-
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EP-203, Rev. 5 l
~ Page 12 Of 20 VAW/JLP/jmv APPENDIX EP-203-4 sies
! STAFF ASSIGNMENT STATUS BOARD I
, NAME LOCATION BADGENO TITLE h SHIFT SUPERRITENDENT
< SHtFT SUPER \1SOR i
i! EMERGENCY DIREWOR
.P f
! i SITE EMERGENCY COOfIDINMOR i t . IEALTH PHYSICS / CHEMISTRY COORDINMOR
- FIELD SURVEY GROUP lw PECO SECURITY EMERGENCY PREFRREDESS COOR0lNATOR p
r i
' CORP. COMMUNICATION LIAISON y
,D 'I
.i l :C-s PROCEDURE SUPPORT COORDINKOR I'
a _ , - PLANNING & SCHEDULING COORDINATOR I MECHANICAL ENGINEERING LIAISON c' ,.,_ ELECTRICAL ENGINEER LIAISON EMERGENCY SUPPORT OFFICER b l
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. Q EP-203, Rev. 5 f
g l Page 13 of 20 ij -VAW/JLP/jmv
.}
h APPEllDIX EP-203-5 4
.'_ I, HE ADQUARTERS...SUPPORT RE. Q UEST STATUS BOARD ....
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RESPONSE STATUS -
' TIME SUBMITTED,TO ITEM . .
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EP-203, Rev. 5 l Page 15 of 20 I j VAW/JLP/jmv
. APPENDIX EP-203-7 1
REY.1 S/2/es
.i
'3 DOSE ASSESSMENT STATUS BOARD 4
3
,a 80 ARD UPD ATE TIME AM PM COMMENTS:
DATE!
')l AM PM RELEASE O C CURIN G AN TICIP AT E D WHEN
' LOC ATION OF RELE ASE: NORTH ST ACK Ut SOUTH STACK OTHER U2 SOUTH STACK
.i ESTIM ATED DUR ATION ON RELE ASE HRS. TIME OF SCR AM:
8078 EFFICENCY
,j RELE ASE MONITORED YES NO l
A HORTH VENT U t SOUTH VENT UE SOUTH VENT - D E S C RIS E NOBLE GAS UCl#CC UCllSEC UCl/CC UCllCC IO DIN E UCl/CC UCl/CC UCl/CC FLOW R ATE CFM CFM CFM
,- 1 WIND SPEED MPH DIRECTION (FROM)
ST ABILITY CL ASS AFFECTED SECTOR (S)
. INTEROR ATEG DOSE TIME TO CE NT ERLIN E PLUME ( 4 SEDg g RELEASE C ALCUL ATED DOSE R ATE FIELD DOSE R ATE DOSE AR RIV A L PR OJE CTIO N TIME W.B. T HY. W .B . THY. W .S . THY. W .S . THY.
7 { SITE SOUND AR) o i
. 1 2.0 MIL E S 8.0 Mit E 8 10.0 MIL E S PEAK g
RECUMMENDED PROTECTIVE ACTION t I i f . I
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c' s 1 f l EP-203, Rev. 5 Page 16 of 20 VAW/JLP/jmv- f 1 l APPENDIX EP-203-8 ; FIELD SURVEY GROUP STATUS BOARD j W.B. DOSE R ATE (REM /HR1 THY. DOSE RATE DEMAS) W.8JTHY. R ATIO 800dNE CONCENTRATE (uCucc) GROUPINFO e TIME LOC. g PROJECTED ACTUAL PROJECTED ACTUAL PROJECTED ACTUAL PROJECTED ACTUAL (MR) (MPC-Hf
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- Page 17 of 20 ,
,e. , VAW/JLP/jmv ' p i . APPENDIX EP-203-9
.. EOF' EQUIP.v.ENT ACTIVATION 1
[ 1. Turn on Ligh'ts in EOF.using switch (es) to the left of the door.
- 3.-
-{ l -2.. Turn on CRT'-s' using posted procedures. I; 3.. Check radio base station'for operability. S 4.- Inform Site Emergency Coordinator or Site Emergency.
~ Coordinator. Communicator when activation is complete, and of-3 any problems discovered.
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L.. ..). p - I . EP-203, Rev. 5 Page 18 of 20 VAW/JLP/jmv 0 7 APPENDIX EP-203-10 - f EOF PHONE CHECKOFF LIST y ." $f .k = . i.%.l 'i, . BRP - Rad -_----__--
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l EP-203, Rev. 5 Page '. 9 of 20 VAS/JLP/jmv , l f APPENDIX EP-203-10 (CONT'D)
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- l. EP-203, Rev. 5 Pace 20 of 20 7AS,JLP/jmv l
E f
- p. APPENDIX EP-203-10 (CONT'D)
EOF PHONE CHECKOFF LIST
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h l . - EP-252, Rev. 5 3850072890 [*'*y jr 2
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Sp PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION
-EME" AGENCY PLAN IMPLEMENTING PROCEDURE EP-252 SEARCH AND RESCUE /FIRST AID GROUP d
1.0 PARTICIPANTS 1.1 Personnel Safety Team Leader shall control the
, Search and Rescue /First Aid Group's exposure and ; provide offsite medical support, as necessary.
1.2 Search and Rescue /First Aid Groun Leader shall direct operations of the group. 1.3 Search and Rescue /First Aid Group members shall perform rescue operations and administer First Aid. 1.4 Operations Support Center (OSC) Coordinator shall form Search and Rescue /First Aid Groups. 2.0 ACTIONS - IMMEDIATE , 2.1 Personnel Safety Team Leade 4
, - 2.1.1 Contact the Operation .
r der Coordinator at the Ope ~ rations Su, t (OSC) and direct him to form Search , O First Aid Group (s). _ - x
.i s ., .
2.1.2 Inform th ( rector that Search and
+
Rescue /Fi Gro p(s) have been fory &and of their ' o enter the plang ferrsdaich and
'resc .s . C ': ')
! AT CATE M'gSS t h ;t.It P pelts (% [ UTILIZING PLA i .
SYSTEMYJUSTs. PRIOR h'O ACf3 ALLY DISP jINGTHESEARg-ANDRESCUEpjtOgP(S). h . a ' W,n $ % g 3 b'L (
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a- .t, v.- . d b N, .. EP-252, Rsv. 5 ,, Pag 3-2 of 12 - l VAW/JLP//rgs u: - u'I j 2.1.3 Obtain emergency exposure limits from the Emergency j - Director.if appropriate. If later-search and t rescue. operations are-necessary, the Emergency
; . ' Director may adjust the radiation exposure 1,imits L' accordingly.-
E CAUTION
~
IF WAITING FOR EMERGENCY DIRECTOR. APPROVAL COULD ENDANGER PERSONNEL, THE . SEARCH AND
- f RESCUE /FIRST-AID GROUP LEADER MAY- DECIDE TO 11 REMOVE' INJURED PERSON.
U T l l L l CAUTION r .; _ PLANNED RADIATION EXPOSURES SHOULD BE LIMITED u- TO THE ADMINISTRATIVE GUIDE LEVELS IN APPENDIX
- j. , l'EP-252-1, EMERGENCY. EXPOSURE GUIDELINES.
j e
- 2.1.4 If-offsite'medicai help is'necessary, have the 1 ambulance, hospital or physician contacted by thel , - Emergency Director or designee using Appendix EP-252-4, Medical Support Groups Phone List. Always T
state the number of individuals involved, type of j injury and if contamination is involved. TV 2.1.4.1 Contact Pottstown Memorial Medical Center and r Goodwill ambulance as first. choice. 2.1.4.2 If Goodwill is not available contact Trappe ambulance. j i 2.1.4.3f If evacuation of the EPZ has been declared, contact !) RMC to arrange for a helicopter and use of Hospital ] of University of Pennsylvania. !j -
/
'., .2.1.4.4 If medical support is required on site). contact one ]i of the local pnysicians. j 2.1.5 Notify security so that the of'fsite medical a response group's access to the Restricted Area can. 1 be' expedited, if necessary. I{
- g 2.1.6 Recall the Search and Re: Ou /First Aid Group (s) j when search and rescio <: t. -lons are no longer
; necessary.
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- Page 3 of -12
- - l1 VAW/JLP//rgs
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( (% ' L2.12 OSC Coordinator shall: r 2.2.1 Select volunteers-from available personnel to form- [E f . Search and Rescue /First Aid Group (s).- EACH' GROUP SHALL CONSIST OF AT LEAST THREE MEMBERS; [ TWO MUST BE QUALIFIED IN FIRST AID AND ONE MUST BE , A HEALTH PHYSICS TECHNICIAN.. 2.2.2 -Appoint the most qualified ~ person as group leader.
; '2.3 The Search and Rescure/First Aid Group Leader
- shall
l _2.3.1. Ensure that each member.has the necessary i respiratory equipment, radsurvey equipment, anti-contamination clothing, and personnel'dosimecry if p time permits. This' material _can be obtained from , emergency surv.ey kits at the OSC or from normal HP-
- stocks.-
1
- 2. 3. 2 - Discuss the situation with the Personnel Safety ? . . __ Team Leader. The following information should be obtained prior to performing search and rescue - ,4 operations:
h A. Number of missing persons. B. Name of individuals. 3 C. 'Last known location of individuals. 1 D. -The job being worked. [ ' E. . Any significant plant conditions that may affect the searen and~any special instructions. 1: 2.3.3 Ensure the group is eqQipped with a first aid kit, stretcher and' blanket, or can get them enroute.- J See attached Appendix EP-252-2 for listing of first
- j. aid equipment location in the plant.
}. 2.3.4 Coordinate Search and Rescue /First Aid Groups to 3, minimize duplication of effort and unnecessary i radiation exposure. I' ;2.3.5' Direct the groups to the last known location of.the e missing individual. If necessary, expand the search to adjacent areas. Ensure most expeditious routes available are taken to minimize team i i exposure. l 3 # i.x.- _ . . , -
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! . EP-252, Rev. 5 Paga 4 of 12
- l- . VAW/JLP//rgs 4
2.3.6 Inform the Personnel Safety Team Leader of the actions of the group (s) and whenever the group locates any missing personnel, and the identity of located personnel.
,2.3.7 Determine the extent of the injury and direct administration of first aid.
2.3.8 Report.to the Personnel Safety Team Leader the extent of the individual's injuries and recommend supplementary medical actions as necessary (i.e., hospitalization). Complete Appendix EP-252-3 (if
.possible) and attach to injured person prior to transporting in ambulance.
2.3.9- Report to the Personnel Safety Team Leader when the Search and Rescue /First Aid Group has finished its task. 2.4 Search and Rescue /First Aid Group Members shall: 2 . 4 .1 - Locate the missing person (s). 2.4.2 Administer first aid, if necessary. IF-THE INJURY IS SEVERE, IMMEDIATE MEDICAL l TREATMENT IS OF THE HIGHEST PRIORITY AND RADIOLOGICAL = CONTROLS ARE SECONDARY. ,
. :2 . 4 . 3 Perform a radiation and contamination survey of the person and subsequently the area.
1 i
. CAUTION i .
. l RADIATION EXPOSURE AND GROUP MEMBER CONTAMINA-l TION SHOULD BE MINIMIZED AS MUCH AS PRACTICAL.I 1
i ^ CAUTION t i i IF GROSS EXTERNAL CONTAMINATION IS FOUND, I INTERNAL CONTAMINATION SHOULD BE SUSPECTED. I i 2.4.4 Transport the injured person to a site first aid facility if practicable. i
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f . l- EP-252, Rsv. 5 Page 5 of 12 1-VAW/JLP//rgs i
~
!b 2.4.5; . Perform the following if the injured. person is-1- contaminated.
-A. Wear necessary anti-contamination clothing if - practicable.
e
] 'B.- IF INJURY IS NOT. SEVERE, DECONTAMINATION SHALL JBE' ATTEMPTED.-
[ ~ C. Prepare the person for transportation by i" covering the. contaminated area with a j protective wrap. Avoid excessive wrapping .tcr prevent' dehydration of the person. J l_ IF THE INJURED PERSON IS GOING TO BE j TRANSPORTED TO AN OFFSITE MEDICAL FACILITY, IT 4 MAY NOT BE FEASIBLE TO BRING THE PERSON TO THE 4 FIRST AID-FACILITY. INSTEAD, MOVE THE PERSON [;
-~
.TO A SAFE PLACE WHICH IS EASILY ACCESSIBLE FOR
" THE TRANSFER TO A VEHICLE.
D. When transporting the victim to'an offsite medical facility, a Health Physics Technician shall accompany the victim to assist the medical staff. i E. A second HP technician shall also report to the y hospital. 2.4.6- Recover any contaminated articles of clothing that
- may have been removed from the person for isotopic I analysis.
I - 3.0 ACTIONS - FOLLOW-UP 3.1 Search and Rescue /First Aid Group members shail: 1 3.1.1 Report results of their actions to the Personnel
]f Safety Team Leader.
3.1.2 Follow normal decontamination and disposal procedures when their tasks are complete. 3 3.2 Personnel Safety Team Leader shall: 3.2.1 Verify the victim's arrival at the medical
;' facilities.
e 4
.- 1 . _ 2..
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l- - EP-252, Rsv. 5
'Page 6 of 12 VAW/JLP//rgs-
.l 2
h 3.2.2 Inform the Emergency Director of results of-search and rescue /first aid efforts.
'3.2.3 Direct the Emergency Director to inform the Medical Director and Claims / Security as to the g identity.and condition of the victim (s).
9 3.2.4 Direct a Health Physics Technician to accompany the
-{
1 victim to the hospital and to call when informed by
'the hospital that his services are no longer
- 3. needed. Direct the technician to return dosimetry j to site to be read and leave survey equipment at
-! hospital. 7 3.2.5 Arrange for inventory and restocking of first aid .{ kits, if necessary. 1 i 4.0 APPENDICES 4.1 EP-252-1 Emergency Exposure Guidelines 4.2 EP-252-2 First Aid Equipment Locations . 9 4.3 EP-252-3 Injured Personnel Report Form 4.4 EP-252-4 Medical Support Group Phone List a I
! 5.0 SUPPORTING INFORMATION n
i 5.1 Purpose 1 The purpose of this procedure is to define the requirements and the actions of the Search and
) Rescue /First Aid Group.
5.2 Criteria for Use
'l i This procedure shall be implemented whenever 'l personnel are known to be missing or are injured.
I 5.3 Soecial Eouipment
! 5.3.1 First Aid Kit
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, I EP--25 2, Ruv. - 5 Paoe 7 of 12 '
.l VA /JLP//rgs l
4 5.4 References j 5.4.1- Limerick Generating Station Emergency' Plan
- 5.4.2 NUREG 0654, Criteria for Preparation and Rev. 1 Evaluation of Radiological Emergency l'l- .
Response Plans and Preparedness In 1 o Support of Nuclear Power Plants. I l~ 7 l:-
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. Page 8 of 12-l VAW/JLP/rgs-
- e. .
4. APPENDIX EP-252-1 p EMERGENCY EXPOSURE GUIDELINES
- i-
- d -
; ' Projected 1
Whole-Body Thyroid Authorized '
} -Function Dose Dose- By .
'I ' c! 1. Life Saving and 4 Reduction of Injury 75 rem
- 375 rem Emergency **
[ Director 2.' Operation of. Equipment j to Mitigate an p Emergency 25 rem
- 125 rem ' Emergency **
, . Director
- 1-1 3. Protection of Health j and Safety.of the Public 5 rem 25 rem Emergency **
Director a
Reference:
EPA-520/1-75-001 Table 2.1
** Such exposure shall be on a voluntary basis
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EP-252-2, REv. 5
" Page 9 of.12
'l VAW/JLP/rgs.
APPENDIX EP-252-2 i ~ FIRST AID EQUIPMENT LOCATIONS First Aid
, Kits Blankets Stretchers Unit-1 Reactor Enclosure l- l 177' Outside Stairway 4 -X X. X 201' Outside Elevator X X
'201';Inside Pipe Tunnel X X
{ .l 217' Area 16 Line 18.5 X X l 253-Inside Stairway 4 X X X l1 253' By Personnel Airlock X X X
-l 283' Corridor near Elevator (509) X X 283' Near Fuel' Pool Cooling Room'(511) X X l 313' Outside' Room 609A X X X
; 313' Airlock to Fan Room (607) X X .,
-l 363' West of Room 603 X X 352' Change Area (701F X X X
; Unit 1 Turbine Enclosure 200' Near Room 261 X X J
i 217' 325A Corridor-aux Equip & Piping (Area 7 Line 13) X X 302' Equip Exhaust Filter (621)
.' l. 239' Inside Battery Room 443 X
, l 269' Outside Stairway 30 X
.l 269' Outside Room 545 X X X
- l' 269' Inside OSC X j l 269' Inside Control Room X
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- EP-252-2, Rav. 5
- Paga 10 of.12-
- l .
VAW/JLP/rgs
~
l , -APPENDIX ~EP-252-2 .
-l FIRST AID EQUIPMENT LOCATIONS t
First Aid Kits Blankets Stretchers
,.l Control Enclosure
[ l 200' Inside Stairway 7 X X
.l '217' Outside Room-336 X
'l. 217' Inside Battery Room 323 X X.
- l: 217' Stairwell 47 X X X l 217' Inside Battery Room 324 . X l 239' Stairwell #7 X X X l 239' Inside Battery Room 425 X l 239' Inside' Battery Room 436 X l '254'-Stairwell #7 X X
.,. ll 289' .'Stairwell #7 X X X I: 304' Stairwell'#7- X
.1 332': Stairwell #7 X X X
- l. 352' Stairwell #7 X d' 'l Radwaste Enclosure
-l 217' Conv. Chem Lab (411) X X
-l 217' Rad. Chem Lab (418) X
., l 217' Radwaste Control Room (415) X X l 217' Between Rooms 417 & 418 X l' 217' Southeast of. Room 415 X j l- l'91' Outside Stairway #2 X s 162' Outside Stairway #2 X 6
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VAW/JLP/rgs i " APPENDIX EP 252-3
}. INJURED PERSONNEL REPORT FORM-l (PREPARE IN DUPLICATE)
Injured Person's Name
; Age t
- Badge No. Or Social. Security No.-
; Male Female Type and Location of Injury i .
i =7- , Radioactive ~ Contamination Yes No Level
~
Location Radiation Exposure Estimate Where Did Injury Occur Prepared by First Aid Group Leader SIGNATURE
~
i Group Members . I' I-If practicable forward original, with the-person, to the site first aid facility or hospital as appropriate. 4 e a w a e 4 .e *$D'***4p*- * * * *
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Y * ' e . l - EP-252-4, Rev. 5 , Page 12 of 12 l l . VAW/JLP/rgs l APPENDIX EP-252-4 e i MEDICAL SUPPORT GROUP PHONE LIST , I Local Physicians ! Office Home ! Dr. Charles W. Delp , j Dr. Arthur Mann ! Pcttstown Memorial Medical Center (Contaminated or otherwise) ' t s own PA 5.9464 l Radiation Manacement Corecration (Serious Contamination /or I i Exposure
- multiple contamina't'ed 'pe r sonfe'll
l l Dr. Roger E. Linneman Preferred Alternate ' i l I I 1
'i Ambulance /. i
/ i Goodwill Ambulance Co. '
i- l t Trappe Ambulance Co. i l - rious Contamination / Exposure is: - ' - l j Whcle greaterBody than Exposure 150 REM greater or extremity than exposure 25 REM or g skin,_ e r te n. . l' REM or contamination causing bcdy contact te 3 . < i- greater than 1 MR/HR cr suscected or ac a ir ., a n or l ingestion of measurable quan'tities o ', a , iv' a erial. , l e a a ,ese, . e , me . . .. . e-e.-*=.= . ee == fe . , . , g .. m e woes w ' **
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' l' EP-315, Rav. 5
[F 3850072900 Pase 1 of 13 - C nip L -i- '
" .J f{ . ,.' PHILADELPHIA ELECTRIC: COMPANY p LIMERICK GENERATING STATION- !
EMERGENCY PLAN IMPLEMENTING PROCEDURE r i. J. L i EP-315 CALCULA* ION OF OFFSITE DOSES DURING A (POTENTIAL) [ RADIOLOGICAL EMERGENCY USING RMMS IN THE MANUAL MODE [ 4 k
' l'. 0 PARTICIPANTS ; 1.1 The Shift Technical Advisor (STA) shall initiate dose l- calculations upon indication that an effluent monitor setpoint has been exceeded.
l.2 The Shift Superintendent shall evaluate the dose results, declare the appropriate EAL based on releases, and assist the Emergency Director in making
] protective action recommendations if warranted.
{
. l.3- The Dose Assessment Team Leader (upon activation of the TSC, and/or the EOF) shall direct dose calculations, evaluate the results, and assist the T Emergency Director with EAL declarations and j l protective action recommendations.
i. l 1.4 The RM-ll Operator in the TSC shall provide radiation , release data to the Dose Assessment Team Leader and. i the RM-21A Operator. 1.5 The RM-21A Operator shall use this data and meteorological information to generate offsite dose ' estimates using the MMMS computer. a a 1.6 The calculator shall assist the RM-21A Operator with n data entry problems and periodically update the Status 3 Board Keeper. T , .
~2.0 ACTIONS IMMEDIATE 1
S-t 2.1 Control Room Operation ($.P,tI
.v b A hpy *~'
Lj '2.1.1 Upon receivi t an ndpade that p an l, effluent release in esce9s of spstantaneous h; Technical Specifications may have occyrted, an offsite dose calculItion agall**b*e $ V initiatedbytheSTAtq,egduag,gthe
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.] MAC/nlp q'
b II -release. He shall also request the
- i ~ .
= Chemistry Department to take an effluent at F the point of release.
'{ - , INDICATORS OF EXCEEDED SETPOINTS - RM-ll ALARMS, CHANNEL BLINKS, CHEMISTRY ANALYSES. CHEMISTRY ANALYSES, GO DIRECTLY TO STEP 2.1.8. q f 2.1.2 The following channels on the RM-11 console provide an indication of a potential
- l. l 7, cj Technical Specification release if in a
>' blinking red state and audibly alarming:
"s > ?! n . South Vent North Vent CHNL 4 DESCRIPTION ,[ ' CHNL 4 DESCRIPTION ,! p'. . v.y N' STACK TOTAL EFFLUENT S STACK VENT EFL IOD~ b 4TE076 2IE185 2IE075 N STACK VENT EFL~IOD SIE185 S STACK VENT EFL IOD I - 5IE075 N STACK VENT EFL IOD 3GE185 S STACK VENT EFL GAS f- E-3GE075 N STACK VENT EFL GAS 6GE185 S STACK VENT EFL GAS gg , 6GE075 N STACK VENT EFL GAS >4
****' 4TE076 WILL BLINK IN YELLOW '
**** FOR AN IODINE ALARM, DO NOT DECLARE AN UNUSUAL EVE
't T {' . THE CHEMISTRY SAMPLE BECOMES AVAILABLE FO
,[
COMMON CHANNELS: (2IE075, SIE075)
**** (3GE075, 6GE075) ; (2IE185, 5IE185) lfh;' (3GE185, 6GE185) .
1, f when the RM-11 alarms or a specified channe 2.1.3 blinks in red, enter G#.ID'!. j -
} 2.1.4 Access the channel (displayed by an
,i alphanumeric code in an alarming / blinking 1 1 state) by entering the following: j . 10 MIN TREND) 41 (Numeric portion of the code, SEL, channel has alarmed, enter-(407f f}! If a North Vent (NV) as the numeric code. units.~ (in the 2.1.5 Note the value S console upper right hand corner of the RMM.he in the RMMS Log. This represents t y j concentration (uC1/cc) or release rate
.l d' (uci/sec) at this channel. For simultaneo-talid alarms on 2 common (same stack, same 1
3 type), channels, take the average of the 2 concentrations. H.l - e n Li i: [.p -. . . ,.,_ . 4
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$ l EP-315, Rev. 5 y Page 3 of 13 MAC/ nip i
($ _ 2.1.6 Note process flow'N. (in the upper middle of jl the RM-ll console) in the'RMMS Log. 1- Process flow A is used only when offsite power has been lost or'the fans to the major
) enclosures have been' turned off. ?!' }- UCI/SEC, OBTAINED FROM A NV CHANNEL, IN STEP'2.1.5, MUST BE yy CONVERTED TO UCI/CC:
Up t* / uCi/cc = uCi/s'ec - lr (process flow) x (472) {' '2.1.7 The STA (RM-21A Operator) will logon to the RMMS-RM-
; 21A system using the appropriace user name and password..
. 2.1.8 *he RM-21A Operator will select the following options:
e [( 2.1.8.1 46 - Emergency Dose Calculations, enter
'C
- f. 2.1.8.2 43 - Class A Dose Model, enter
'9 2.1.8.3 93 - All Manual Mode, enter
! THE OPERATOR SHALL GENERATE A HARD COPY OF ALL
. t. INFORMATION.
'l v- 2.1.9 Review the run control table.
Edit the table to reflect the Appropriate release point (s). (COPY) EP Release point 1 = North vent (!) Release point 2 = South vent
-kj Release point 4 = Hot Maintenance Shop Enter return to get back to "date of reactor trip".
2.1.10 Enter the following information: l 2.1.10.1 date of reactor. trip - If the reactor has not tripped or scrammed, enter the start
,1, . time of the release.
h 2.1.10.2 time of release -Enter start time of release [ or the beginning of the period to be B evaluated. *his time must be equal to or ' l later than the time of reactor trip. ;
,?
! \
,- EASTERN SPANDARD TIME (EST) IS USED BY RMMS. EST IS j EQUAL TO DAYLIGHT SAVINGS TIME MINUS 1 HOUR.
a 2.1.10.3 remaining duration of release - The operator must request that the Shift Supervisor y provide him with an estimated duration of
- release. If the duration cannot be t
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~ l EP-315, Rev.- 5 Page 4 of 13 MAC/ nip-4 i estimated with confidence, enter 1 hour. ]. (COPY) THE REMAINING DURATION OF RELEASE IS USED IN THE.EAL TABLE p WHICH PROVIDES THE OPERATOR WITH INFORMATION REGARDING CLASSIFICATION OF AN EMERGENCY BASED ON RADIOLOGICAL i- RELEASES. IT IS ALSO USED IN THE PAG
SUMMARY
DISPLAY TO y PROVIDE GUIDANCE ON WHEN PAGS MAY BE EXCEEDED. b 2.1.10.4 isotopic release data b
- 1. #2 - isotopic percent fraction
~\ (sum = 100.0)
- 2. Select the desired isotopes based on the following criteria:
'.. l
- h. ALARMING MONITOR c
h1 l *If the reactor has not scrammed, enter the
, isotopic abundance for the month. This information is provided by the chemistry department. The chemistry sampling data must indicate the presence of isotopes having activities greater than the LLD values. Values less than or equal ~to LLD preclude the need to perform dose assessment.
s f( l *If the reactor has scrammed, enter the isotopic abundance per Appendix EP-315-1, 's which is.also located in the EP-315 guide l next to the RMMS console. CHEMISTRY ANALYSIS
- Utilize the isotopic mix used by chemistry to determine that the setpoint has been i exceeded.
. 2.1.10.5 vent flow rate - see step 2.1.6, (COPY) 3 2.1.10.6 gross concentration of the release .F ALARM - see step 2.1.5 L- CHEMISTRY - taken from the analysis report Remember to convert (uCi/sec) to (uCi/cc) if necessary.
2.1.10.7 meteorological data - Obtain the data from the Meteorological Data-Logger and enter the 4
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4 f-a .g , e ,-g -pT_*.,u-; p - = - - 4
pm m,. . . . . . . . . . . . . _ . .[ ) J *.L . . .- . . - . - - .- q'
-l EP-315, Rev. 5 Page 5 of 13 MAC/ nip ~. l-_ sensor' data which corresponds to the prompt.
(COPY) Refer.to Appendix EP-315-2 i If Data-Logger is unavailable, the Operator y shall obtain the data from the following 3 sources- (listed in order of: preference): t:
? 1. . Control Room Strip Chart Recorders, k ..
refor to Appendix EP-315-2
- f r
l 2.- National Weather Service (215)-597-0846 f 2.1.11 Review the Site Boundary Emergency Action Level i Display for the current action level, generate a hard 1 copy and inform the Shift Superintendent of the action
] level, c
f **** Repeat steps 2.1.8 through 2.1.11 for each release. point
'**** If this procedure is initiated due to an-RM-ll alarm,
- e. l .
r- repeat all calculations using'the isotopic mix provided by Chemistry as soon as the mix becomes
.; available. , 2.1.12.For a current action level of unusual event or greater, generate a'hardcopy of the following reports, T- unless otherwise directed by the Dose Assessment Team
( Leader. l% 2.1.12.1 (X/Q) Display .W' 2.1.12.2 Projected dose summary i$ 2'1.12.3
. Summary report J ; 2.1.13 Repeat steps 2.1.8 through 2.1.11 where any',following condition is observed:
t a
} 2.1.13.1 A new high alarm (blinking,3 audible) from
.i any channel per step 2.1.2 is indicated on the RM-ll console. 2.1.13.2 An upward trend is observed in any channel per step (2.1.2) while it is in the high alarm state. 2.1.13.3 An EAL value described on either the RM-ll ,1 or RM-21A Operator Aid card is met or exceeded. l AT THIS TIME, IT IS AT THE DISCRETION OF SSVN TO TERMINATE THE PROCEDURE OR INSTRUCT THE STA TO PERFORM PERIODIC DOSE-v... .. n.. .
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l' ~ EP-315, Rev. 5 Rage 6 of 13 MAC/ nip ( ASSESSMEM? CALCULATIONS (AND/OR) IMPLEMENT THE NEXT STEP'OF THIS PROCEDURE. I j' To terminate the RMMS program, enter ( /E, return)
- r-j 2.2 Dose Assessment Turnover to the TSC
- k. 2.2.1 Upon activation of the TSC, the RM-21A Operator in
'-1 Control Room ~will provide the following information to
-the Dose Assessment Team Leader in the TSC.
- 6 l 2.2.1.1 time of reactor trip or scram a
j1 2.2.1.2 location of release i 2.2.1.3 time of release lc' 2.2.1.4 estimated duration of release d' {; 2.2.1.5 Containment Radiation Monitor information to E includes primary containment leakage,-
~
drywell purging, number of fans operating, hours purged 2.2.1.6 wind direction, ground and elevated . j- 2.2.1.7 location and val'ue of peak (X/Q) , depleted and undepleted 2.2.1.8 time to reach peak (X/Q) 57
?! 2.2.1.9 location and value of peak whole body gamma
'{; dose rate 2.2.1.10 location and value of peak thyroid dose rate
-lf l 2.2.1.11 whole body gamma dose rate at (Site boundary
! 2, 5, 10) miles 2.2.1.12 phone number where the RM-21A Operator in i the control Room can be contacted.
[\> 2.2.1.13 Protective Action Recommendation (s) if any were made
' 2.2.2 Upon turnover of dose assessment from the Control Room ,-' to the TSC, the Dose Assessment Team Leader shall:
i 2.2.2.1 Brief team members on plant and release status. 6 0 9
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; EP-315, Rev. 5:
Page 7aofil3' ti . MAC/ nip r. + ' 2.2.2.2 Assign personnel as RM-21A operator, RM-ll
- operator, Calculator, Field Survey Group 4
Leader. '
- i E ~
m 2.2.2.3 Contact Chemistry for the status of the-i plant ~to-include SGTS filter efficiency and i isotopic breakdown of drywell air, effluent
,. release and reactor water.
-2.2.2.4 Initiate and direct dose calculations.
2.2.2.5 Review dose calculation parameters.- i 2.2.2.6 Evaluate results (Summary Report and .'. Projected Dose Summary) against wholeLbody gamma and thyroid inhalation.PAGs. 3 J 2.2.2.7 Periodically brief the Emergency Director on tm offsite dose results and assist him with PAG ' fc recommendations if conditions are warranted. 2.2.2.8 ' Periodically update the BRP on plant conditions, meteorology, and actual or _. potential releases. 2.2.3 The RM-ll Operator shall: L 2.2.3.1 Continuously assess radiological trends from [' ' the drywell high-range radiation monitors and plant effluent monitors and inform the
?r' \ Dose Assessment Team Leader and Calculator
~ll as conditions change. (hb'- 2.2.3.2 Update the Calculator and 'Do'se Assessment Team Leader, on an.approximately 15 minute-3- basis, with information from the affected i radiation effluent monitors unless otherwise j' directed by the Dose Assessment Team Leader. i 2.2.3.3 Inform the Dose Assessment Team Leader t immediately in the event that any EAL has
- ' been reached or exceeded.
{ 2.2.4 The Calculator shall: 2.2.4.1 obtain, approximately every 15 minutes, the [k.' effluent release date from the RM-ll y Operator.
,'. 2.2.4.2 Perform, as requested by the Dose Assessment Team Leader, EP-325 for input to the RMMS dose model. ]
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.l EP-315, Rev. 5 F
Page:8 of 13 9- - MAC/ nip m ( . 2.2.4.3 Select and calculate, as directed by the Dose Assessment Team Leader, isotopic breakdowns of1the source term for input to g the RMMS dose model. . J. ' 2.2.4.4 Note on the dose model output cover sheet, - t~ the time of the calculations and assumptions c k-
;L used.
r 2.2.4.5 Update dose: trending sheets as required. l 2.2.4.6 Review dose model results for key. 4e information. Immediately, inform the Dose Assessment Team Leader if dose model results j indicate PAG levels may be met or exceeded. 4 '2.2.4.7 . Update the status board keepers with the 1 requested information. 'l 2.2.5 The RM-21A Operator shall 2.2.5.1 Log onto the RM-21A system using the
- y appropriate user name and password.
2.2.5.2 Obtain meteorological data for the period of interest by selecting the following options: [~
- 1. ~ 44 - Meteorological Data Collection and Processing
- 2. 43 - Meteorological Data Processing u.
;- 3. 43 - Review Current Averages -or- 44 Meteorologica1' Data Averages, if the , . evaluation is t'o be done with
<2 historical data. e
- i. RESPOND TO ALL PROMPTS AND GENERATE A HARDCOPY.
4 1 2.2.5.3 Return to the primary menu and repeat steps 2.1.8 through 2.1.10.7. [ GENERATE HARDCOPIES OF ALL SCREENS OR AS . ty, DIRECTED BY THE DOSE ASSESSMENT TEAM LEADER 2.2.5.4 Review the Site Boundary Emergency Action Level Display for the current action level, generate a hardcopy and inform the Dose Assessment Team Leader of the action level. I 2.2.5.5 For a current action level of unusual event or greater, generate a hardcopy of the I
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L 51 - l EP-315, Rav. 5 Page 9 of 13
'T MAC/nlp r- s- .r f -
C following, unless otherwise directed by the
- i. Dose = Assessment Team Leader.
ii_ 1. (X/0) Display -
,; 2. skin isopleth I- -
- 3. gamma isopleth is -
7 ;.
- 4. inhalation thyroid isopleth
'5. projected dose summary
- 6. summary report
'i. 2.2.5.6 Repeat steps 2.2.5.3 through 2.2.5.5 where e any following condition is observed, unless J! otherwise directed by the Dose Assessment ]! Team Leader.
- 1. meteorology changes significantly l- 2. new isotopic data is made available
- 3. An. upward trend is observed on any effluent channel
',, 4. An EAL value is met or exceeded
- 5. As directed by'the Dose Assessment Team Leader T .
., 2.3 Dose Assessment Turnover From the TSC to the EOF 2.3.1 'Upon activation of the EOF, the Dose Assessment Team Leader in the EOF shall L contact the Dose Assessment Team Leader in the TSC (X2620) and request
- 1 l 1. the information in steps 2.2.1
- .' 2. ground and elevated sigma-theta Q
9 3.. ground and elevated delta temperature
.y 1 4. stability class
] 5. basis for Noble Gas and Iodine source j term
- 6. Field Survey mesm informations i teams available, # teams dispatched, time
>. . e. -
l EP-315, R9v. 5. Pcg3 10 of 13 MAC/ nip
. i' .
. teams dispatched, location and results I!!" 2.3.2 The RM-21A Operator shall~ activate the RM-21 computer as follows:
1
- 1. Lift phone receiver from crad.le and pull the left switch hook into a full
-{ upward position.
( 2. When a dial tone is present, dial 1-
.- 326-9510. One ring followed.by a tone should be heard.
. 3. Press the switch hook down to the first notch. This engages the RM-21A terminal (Textronics 4014) to the VAX Computer.
- 4. Log onto the RM-21A system using the appropriate user name and password.
2.3.3 All functions and responsibilities described in step 2.2.2 are applicable except anything
+ pertaining to the RM-ll. All necessary radiological data shall be obtained from the
-- 4" RM-21 on an as needed basis.
2 , 3.0 ACTIONS FOLLOW-UP
" None 4
~
'4 4 . 0" APPENDICES -
4.1 EP-315-2 Data-Logger /RMfiS Cross Reference
, 4.2 EP-315-1 Is topic Abundance (LGS FSAR Table 15.6-14) ' t:
t. 5.0 SUPPORTING INFORMATION P 5.1 Purpose b The purpose of this procedure is to provide guidelines to calculate offsite doses during a potential or actual radiological emergency.
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i ' l EP-315, Rev. 5 ; Page~11 of 13 !
. MAC/ nip 1 4 5.2 Criteria for Use 5.2.1 This procedure is used to evaluate offsite doses when the effluent stream (potentially) exceeds the limits set forth in the F technical specification. This can be f determined by a chemical analysis or an j alarm of an effluent monitor on the RM-ll.
y f- 5.2.2 Implement this procedure for either simultaneous, VALID alarms on two common f P- (2EIO75 & SIE075) , operating channels or a i VALID alarm on a single operating channel-L whose mate is inop. (3GE075 VALID alarm and 4 6GE075.is inop). i
. t. . 5.2.3 The manual mode of RMMS will allow the
'F operator to bypass the use of real time l radiological and meteorological data, p(-i enabling him to enter date of his own jff choosing.
.f I 5.2.4 Operation of RMMS in the manual mode is-
' [; useful for investigating offsite doses during Emergency Plan exercises and in the l event that radiological or meteorological-data are unavailable in the real time mode.
~'
5.3 Special Equipment g 5.3.1 RM-21A consoles and User Guide
'i 5.3.2 RM-ll consoles and User Guide
(- .1
- .5.3.3 EP-315 Guide next to RMMS Console ,
c
- 1. 5.4 References P
- 5. 4.1 LGS FSAR Table 15.6-14 i t r
4
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l EP-315,.R3v. 5 Page 12 of 13-
, MAC/ nip s
APPENDIX EP-315-1 l LOCA ISOTOPIC' PERCENT ABUNDANCE IN PRIMARY t j- [ l' Time after reactor scram: A. .? Isotooe 0-2 hrs' 2-8 hrs 8-24 hrs, 24-96 hrs' 96-720 hrs _b, Kr-83m 1.41 0.24 0.001 Kr-85 0.05 0.07 0.11 0.20 5.47 4 Kr-85m 6.61 3.89 0.48 L Kr-87 ' 5.64 0.36 Kr-88 13.6 4.64 0.13 Kr-89
?. -
Xe-131m 0.18 0.27 0.41 0.61 3.80 Xe-133m 0.95 1.35 1.71 1.22 0.01 Xe-133 38.9 57.9 82.4 97.4 90.3 I
.Xe-135m 0.05
[ Xe-135 32.3 31.5 14.5 0.11 ( Xe-137 Xe-138 0.25 i I-131 32.0 36.1 47.5 88.4 100.0 I-133 68.0 63.9 52.5 11.6 0.0 , )'~ If venting through SGTS with a design basis filter f efficiency, and 0.St/ day leakage rate, then: I-131 11.0 34.1 41.7 68.7 98.3
. I-333 89.0 65.9 58.3 31.3 1.65 Reference LGS FSAR USE ONLY IF REACTOR HAS SCRAMMED.
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E1 215, Rev. 5 l " I Page 13 of 13 :
' MAC/ nip
-t:
f APPENDIX EP-315-2 DATALOGGER/RMMS CROSS REFERENCE i RMMS MANUAL DATALOGGER DATALOGGER RM-21A SENSOR Channel No. & Met. Prompts Abbreviation Parameter Name Primary Secondary 4 Ground Direction 0 30'Dir./69 TlDRL 30 ' DIR2f0 (0) * , 159'DIR//e(15) ,
' WDI .
Ground' Sigma Theta 0 30'DIR/79 TlDRL 30'DIR/IB (0) , 159 'DIRAfo (15) WDI/DEV
. Ground Speed 1 30' Speed TISPL 3 0 ' Speed (1) , 159' Speed (16) ;.
WSI i;
.TlDT U-L 266'-26'AT(6), 300 '-2 6 'AT ( 23)
Ground Delta T 6 266'-26'fT . DTI Elevated Direction 2 175' DIR./f6 Tl DRI 175' DIR/fe (2) , 304' DIR/fo(20) WD2 . t
. Elevated Sigma Theta 2 175' DIR./79 Tl DRI 175' DIR/fe (2) , 304' DIR/fe(20) .'
WD2/DEV Elevated Speed 3 175.' Speed TISPI 175' Speed (3), 304' . Speed (21) i WS2
^
Elevated Delta T 7 266'-26'AT TlDL U-L 266'-26'AT(7), 300 '-2 6 'g3T (23) DT2 Elevated Amb. Temp. 10 26' Ambient'I. T2 AT L 26' Ambientikl0) , 26' Amb. T (24). ' TRl
- Channel number from Data-logger in parenthesis () .
.]!lWindCharts ! Wind Speed - red - (0-100 mph) full =cale i
Sigma theta - black - (0-100 mph) full scale 1 Wind direction - red - (0-360-180) full scale I.?
- c. .
v-l EP-316, Rav. 3 l
. Page 1 of 69 3850072910 Devn19 ,
<l, PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE F
- u. EP-316 CUMULATIVE POPULATION AND N5AR REAL-TIME EMERGENCY DOSE
! CALCULATIONS FOR AIRBORNE RELEASES - MANUAL METHOD 1.0 PARTICIPANTS-l.1 Dose Assessment Team Leader shall direct the Dose Assessment Team to perform the necessary calculations within this procedure.
! 1.2 The Dose Assessment Team shall perform the
- calculations in this procedure.
1.3 shift Technical Advisor shall perform the necessary _lf calculations within this procedure until the Dose
~4
#' Assessment Team is available.
+
2.0 ACTIONS /IMMEDIATE ..
, 2.1 The Dose Assessment Team Leader or Shift Technical 1 Advisor shall: ~
2.1.1 Perform or direct team members to perform the appropriate calculations in this procedure from the
.g following:
2.1.1.1 APPENDIX EP-316-1 RAPID DOSE ASSESSMENTS [ i 1.1 HIGHEST WHOLE BODY DOSE RATE DUE TO NOBLE GAS RELEASES l 1.2 HIGHEST THYROID DOSE RATE DUE TO RADIOIODINE RELEASES p l' 2.1.1.2 APPENDIX EP-316-2 REFINED DOSE ASSESSMENTS
'l 2.0 SOURCE TERM AND METEOROLOGICAL D&TAS- ,b ao i c
( ' [ 2.0.1 Sourep pra $.maFi. ;E . ' M f A FD. t W i s" ,2.0.2 Meteogo,logi,ccal ta U* i i 2.1 CHI /O AND PLUME TRA E'Dd g RMINATION ee %I 2.1.1 Inputs needed O , p* . 2.1.2 n Releas%hypru- x dW*er l
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.. EP-316, Rav. 3
+ Page 3 of 69 .
DMR/nlp i 5.0 . SUPPORTING INFORf!ATION 5 5.1 ' PURPOSE [ir The purpose of this procedure is to provide methods f; of estimating the site boundary and offsite - airborne concentrations and resulting whole and/or. .- thyroid doses. This procedure is to be used when
'i ~the,RM-21 portion of the Radiation and
.7-Meteorological Monitoring System (RMMS) is not 5~ available. E' i 5.2 CRITERIA POR USE 5.2.1 Set of 30 acetate overlays (see Appendix EP-316-4) { and base map.available for use. 5.2.2 An alert or higher level emergency due to a gaseous L release of radioactive material has been declared E in accordance with EP-101, " Classification of Emergencies" and the RM-21 portion of RMMS is
); inoperable.
- 1. 5.2.3- Calculations performed in thi-s procedure should be i . checked by an independent reviewer.
; 5.2.4 Any section of this procedure may be independently -- performed based on information needed.
5.4 REFERENCES
6
;h 5.4.1 Limerick Generating Station Emergency Plan t?
5.4.2 10CFR20, Appendix B t 5.4.3 NOREG-0654, Criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plant (RG 1.101 and Preparedness in Support of Nuclear Rev. 2) Power Plants 5.4.4 EP-210 Dose Assessment Team 5.4.5 EP-317 Determination of Protective.Ac. tion Recommendations ' s L
- k. 5.4.6 EP-325 Use of'the Containment Radiation Monitor to j-- . Estimate' Release Source Term 5.4.7 FSAR Table 11.3-1 Expected Annual Activity Released from Gaseous Waste Management Systems 1
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-- EP-316, Rev. 3
- Page 2 of 69 DMR/nlp P
2.1.3 Overlay selection 2.1.4 Overlay orientation CHI /Q calculation 2.1.5 g. I 2.1.6 Plume travel time E) 2.2 ~WHOLE BODY DOSE DUE TO NOBLE GAS RELEASES
- r. .
+ 2.2.1 Plume centerline dose 1. I 2.2.2 Determination of whole body dose rate from field survey data k- l 2.3 THYROID DOSE DUE TO RADIOIODINE RELEASES l- 2.3.1 Plume centerline dose i. 2.3.2 Determination of. thyroid dose from h field survey data. (
- r:
2.4 GROUND DEPOSITION PER UNIT AREA L. . . - 2.4.1 Assessment of offsite plume centerline deposition per unit area 2.1.2 Direct team members to complete-Appendix EY-316-3 Summary Sheet for use with EP-317, " Determination _~~ of Protective Action Recommendations." to ]E CALCULATIONS SHOULD BE COMPARED AS SOON AS. hv. PRACTICABLE TO FIELD SURVEY DATA. r 2.1.3 Report results along with protective action recommendations to'the Site Emergency Coordinator, o if activated, or Emergency Director. 4.0 APPENDICES 4.1 EP-316-1 Rapid Dose Assessments [- 4.2 EP-316-2 Refined Dose Assessments g- 4.3 EP-316-3 Summary Sheet 4.4 EP-316-4 Chi /Q Overlays y; 4
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.. ~ EP-316, Rev. 3 mi ,
, Page 4 of 69
- / . DMR/nlp y
;5.4.8 FSAR Table 15.6-14 LOCA: Activity Airborne in-Primary Containment
.5.4.S Limerick Generating Station EROL Table 2.1-3 l
I -l 5.4.10f 10CFR50, Appendix I t l 5.4.11 EP-101 Classification of Emergencies r .. l 5.4.12 Regulatory Guide 1.111, Revision 1, Methods of Estimating Atmospheric Transport and Dispersion of 4 Gaseous Effluents in Routine _ Releases from Light-t Water-Cooled Reactors.. l t l 5.4.'13 Regulatory. Guide 1.109, Revision 1, Calculation of
= Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating F . .
'I - Compliance with 10CFR50, Appendix I.
r, l '5.4.14 Regulatory Guide 1.23, Proposed Revision 1, "Onsite y_ Meteorological Programs." h Postulated MCA data for LOCA from the RMMS.-
- [.
A l 5.4.15
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b . EP-316, Rav. 3 Page 5 of 69 DMR/nlp 1 APPENDIX EP-316-1 RAPID DOSE ASSESSMENTS l.1 HIGHEST WHOLE BODY DOSE RATE DUE TO NOBLE GAS RELEASES 1.1.1 Obtain gaseous. release data for the North and
- f. South vents from one of the following locations (use the highest. channel on Recorders) :
J- - 1
*( A. North Vent Wide Range Gas Monitor a
( 1)'RM-ll Display Console Channel 4TE-076 6 2) MCR Panel 00C691 (RM-23) h 3) MCR Panel 00C624 (Strip Chart in uCi/sec) 1 B. South Vent Unit 1 I
- !. 1) Average of the RM-ll Display Console Channt' f 3GE-185 and 6GE-185 C.
. South Vent Unit 2 ,x . ' % 1) Average of the R$-ll Display Console F Channels 3GE-285 and 6GE-285 - 1.1.2 Calculate site boundary whole body dose rate.
U1 U2
'r- .
NORTH SOUTH SOUTH OPERATION VENT VENT VENT e-99 1. Record the peak uCi/sec uCi/cc uCi/c hj) .
. effluent release .f j. l rate and/or 5 concentration . whichever is ' , l.( ' applicable. .
e i 2. Multiply-by mR/hr mR/hr 'mR/hr mR/h: .- [ l conversion factor 3.94N6 uCi/sec 4.19P2 'uCi/cc 4.19P2 uCi/i f_ - to determine site F l boundary dose rate.
- 3. Site boundary dose mR/hr mR/hr mR/h:
']- rate.
.V L-- , 4. Add all three mR/hr (total) .- 2 l values. l THIS IS A CONSERVATIVE SITE BOUNDARY WHOLE BODY DOSE l RATE BASED ON THE ANNUAL AVERAGE CHI /Q ISOTOPIC MIX IN FSAR. TABLE 15.6-14, AND NORMAL VENT FLOWS. 9 7._ . . .. .. . . _ . . . . . . . . , . _ . . . ._ .. _ . . _ . _ . . . . . _ . . . . _ . .
_ . . . , _ . _ _ . _ ..r l EP-316, Rav. 3 Page 6 of 69 DMR/nlp-J . J l . l.2 HIGHEST THYROID DOSE RATE DUE TO RADIOIODINE RELEASES 1.2.1 Obtain the Iodine channel effluent concentration from the RM-ll Display Console: I a) 2IE075 (North Vent) Ave, b) SIE075 (North vent)
. c) 2IE185 (U1 South vent)
Ave. 1 d) SIE185 (U1 South vent)
~l e) 2IE285 (U2 South vent)
Ave. f) ' 5IE285 (U2 South vent) -E
- s. __.
'$ NORPR VEN? Ul SOUTH VENT U2 SOUTH VENT i -. E uCi/cc Iodine uCi/cc. Iodine uCi/cc Iodine l 1.2.2 Determine Inhalation Thyroid Dose Rate (Infant
- r. Thyroid in all cases)
.. ?
r 3, Iodine uCi/cc X conversion = mR/hr factor .g
. North Vent X mR/hr = mR/hr 3.61 P6 uCi/cc Ul South Vent X mR/hr = mR/hr 2.30 P6 uCi/cc i
"E U2 South Vent X mR/hr - = mR/hr gj' 2.30 P6 uCi/cc kh Total mR/hr r l[ THIS IS A CONSERVATIVE SITE BOUNDARY *HYROID DOSE RATE BASED ON THE ANNUAL AVERAGE CHI /Q, AND NORMAL VENT FLOWS. 9 e e e 4
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. EP-316, Rav. 3
, Page 7.of 69 DMR/nlp APPENDIX EP-316-2 REFINED DOSE ASSESSMEMTS
'2.0 SOURCE PERM AND METEOROLOGICAL DATA l t'
DATA SHEET 1 SHOULD BE COMPLETED FOR ALL SUBSECTIONS OF THIS .:{J SECTION. ti l
.{.
2.0.1 SOURCE TERM-DATA t !
' .1. Establish date and time period (duration) of release.
7 Enter on Data Sheet 1.. f t I.
- f. 2. Record the release data.
3 A. For the north vent noble gas releases, read the I' release activity in.uCi/sec from'the the RM-ll Igp . Display Console (Composite channel 4TE-076) or the strip chart recorders on Panel 00C624. -
;Fi
(( B. For_the U1 South vent, obtain the release activity in_uCi/cc and vent flow rate'from the RM-ll Display I ' t' -Console (Average of channels 3GE-185 and 6GE-135) . .L
?'~ C. For the U2 South vent, obtain the release activity in uCi/cc and vent flow rate from the RM-ll Display Console (Average of channels 3GE-285 and 6GE-285) .
J-~ 3. Attach sample analysis for noble gas or iodine, if
- p. available.
.!f.g 4. For the same time period, obtain the total iodine'results "j.p of reactor enclosure air and/or drysell air semple (s) and release point sample in uCi/cc.
( , 9' l 5. Calculate SGTS filter efficiency. (7 reactor enclosure I and/or drvwell I)-release point '
- } 100
! . (Ereactor enclosure I and/or drywell I)
' t.
,lt l NO*E r(-. r L SGTS filter efficiency will determine the factor to be used to divide the gross' noble gas release rate (when iodine monitors are off-scale) in order to obtain the Iodine release rate. 2.0.2 METEORCLOGICAL DA?A
- 1. Read the' wind speed and wind direction from the Climatronics-datalogger. If the climatronics datalogger is not in service, determine the wind speed and direction 9
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4
. EP-316, Rav. 3 Page 8 of 69 DMR/nlp i
? 1 from the instrument recorders on Panel OBC 699.
A. Wind Speed Primary: 175 Ft. Level Tower 1 (Channel 3); Alternate: 304 Ft. Level Tower 2 (Channel 21); i B. Wind Direction
~
. Primary: 175 Ft. Level Tower 1 (Channel 2);
I Alternate: 304 Ft. Level Tower 2 (Channel 20); i: j' w-l C. Panel OBC 699
$ l Primary: XR - MS - 012B F
l Alternate: XR - MS - 020B Record the average wind speed and wind direction at the
. elevated tower level for the time period of interest.'
T 1,; 2. Determine the atmospheric stability class. l A.I Obtain the following meteorological parameters from' the Climatronics data logger: . 1 I~ A.l. Read DT2 (Channel 7; 266-26 ft) deg F rF from Tower 1. If this value is ,, available, continue to Section C.l. If D*2 is unavailable, use DT4.
]+. .
A.2. Read DT4 (Channel 23; 300-26 ft) from Tower 2. If this value is deg F available, continue to Section C.2.
. If DT4 is unavailable, use WD2/DEV.
A ' A.3. Read WD2/DEV (Channel 2; 175 ft) P from Tower 1. If this value is degrees az -js l available, continue to Section C.3. NOTE: IF WIND DIRECTION IS FROM 120 I DEGREES AZIMUPH-180. DEGREES AZIMUTH, WD2/DEV IS UNAVAILABLE. USE WD6/DEV.- - A.4. Read WD6/DEV (Channel 20; 304 ft) from Tower 2. If this value is degrees az l available, continue to Section C.4. NOTE: IF WIND DIRECTION IS FROM 45 DEGREES AZIMUTH-95 DEGREES AZIMUTH, WD6/DEV IS UNAVAILABLE. PROCEED TO B. r - .- ..- , . - . - . . ... - . ,_, e-- - mv '
..,n,- 5,v- '
a a. . o .. _. EP-316, Rev. 3 Page 9 of 69 DMR/nlp f
.f l B. In the absence of DT2, DT4, WD2/DEV, WD6/DEV, obtain i ' the following meteorological data from the National i
NWS) station in Philadelphia, PA I B.l. Wind Direction (WD30) deg az h; B.2. Wind Speed (WS30) knots B.3. Cloud Cover (CLCVR) __( tenths) B.4. Cloud ceiling (CLCEG, skip to Section C.S. ( ft 1 C. Turbulence Typing k C.1 DT2 R' For DT2, type turbulence class according to Tc N * -
' ' ' ' ' ' ' "'. Table,,316-A e . R.e.cpri, stab.ility. class .o.q,. Data,.:.
' Sheet 1. If nbt available, go to C.2 befo~w; . ..{
r p Stability Class C. df T4
-Y
- DT4, type turbulence class according to Y, ' T sle 316-A. Record stability class on Data
, herb 1. If not available, go to C.3 below';
, V ,..,; '
k-({;rje - m Stability Class ( .s.?", - C.3 ' [ ,s; W-l If, ., e rgetion is not between 120 and 180 de ryds, nuth, WD2/DEV can be used (unaf( type ,if( e cooling tower). For WD2/DEV, e class according to Table 316-A.
, Record 9 ili class on Data Sheet 1. If not ., availa e,, C.4 below.
c:
]
- Stability Class h -
C.4 WD6/DEV t - 5 . f I- If wind direc n et between 45 and 95 degrees azim , y can be used (unaffected by ,. ing tower). For WD6/DEV, type turbulence class according to Table 316-A. Record stability class on Data Sheet 1. If not available, go to C.5 below. i Stability Class 8 *( X g . _ . **"#
- e l agee gap ggp ,ey em. m ea . . - *4 .Y*% '"W %*we . _
- . ~ . . . . . 2. ...
.. :.: L .. . . . 2.&: . f. . . . .Y.
. EP-316, Rav. 3 Page 10.of 69
+
DMR/ nip
?, - C.5 NWS Technique 1 5.1 Determine net radiation index (NRADI) .
j For daytime, . (one hour af ter . sunrise to S one hour before sunset) , complete below, j otherwise go to Section C.5.2..
.y.
< 5.1.1. Determine the insolation class-k; number (ICLNO) aus follows:
) .
Record nearest current hour of day Eastern Standard Time) hr (military time)
' Record Date Using the above information, . . .~
determine ICLNO from Table 316-B
'e . ICLNO
! 5.1.2 Using CLCVR (B. 3) , CLCEG (B . 4) and ICLNO, determine NRADI from Table L 316-C and record in Section C.5.3.
, l Go to Section C.5.3.
- n 5.2 Determine NRADI from Table 316-C for f/ nighttime using CLCVR (B .~ 3 ) and record in Section C.S.3.
{} l f. . 5.3 Determine. stability class from Table 316-D
,' using:
i, NRADI- (determined in either Section C.5.1 !) or Section C.5.2) V WS30 (determined in Section B.2)
.f l r
~
C- Stability Class H Record the stability class on Data El Sheet 1. l (. l
, e I - - , . * * ..
' ~
, - . . . . . . .,~ ~'_.,,*.',.^
,.'~ .
~.
.a
. : ,: 013. ..
l I 1
, EP-316, Rev. 3 l Page 11 of 69 i DMR/nlp '
se
,, TABLE 316-A CLASSIFICATION OF-A*MOSPHERIC STABILITY AT THE LIMERICK GENERATING S'ATION f
. y-METEOROLOGICAL TOWER SITE BY EI*HER VER?ICAL 'f'EMPERA*URE DIFFERENCE OR SIGMA' THETA W
n9 e sg-( F [ SIGMA "HETA' DELTA T (deg F) STABILITY PASQUILL- [ WD6/DEV OR . DESCRIPTION STABILITY i, WD2/DEV DT4 DT2 CLASS t t- l > -22.5
-< -2.85 < -2.50 Extremely Unstable A ;g G
17.5 to 22.4 -2.56 to -2.84 -2.24 to -2.49 Moderately Unstable B 12.5 to 17.4 -2.25 to -2.55 -1.98 to -2.23 Slightly Unsta'le b C L. -7.5 to 12.4 -0.75 to -2.24 -0.66 to -1.97 Neutral D t 3.8 to 7.~4 2.25 to -0.74 1.98 to -0.65 Slightly Stable E ,r 2.1 to 3.7 6.01 to 2.26 5.27 to 1.99 Moderately Stable F V .
? < 2.1 1 6.2 1 5.28 Extremely Stable G V:.
a p l Use of Parameters in Order of Priority:
.A DT2- .
DT4
-I WD2/DEV (unavailable if wind direction is between --)- 120 degrees azimuth - 180 degrees azimuth)
- WD6/DEV (unavailable if wind direction is between L 45 degrees az~imuth - 95 degrees azimuth)
L. Y
.f w
4 5
. 1~
. I 1 9 t' f 4
...,.. . . . . - _...-<...y.. .-. : 7 -...y-.m.7~,... .- - - .
, - s-e._ - m ---- .y - ,
,, . , .~,.:-..-.:--. '
. . . . - - . - , a. - -. ---.~-:--- 2
a.. . . =:.e . EP-316, Rev. 3 Page 12 of 69
' DMR/nlp
~
h TABLE 316-B ICLNO AS A FUNCTION OF HOUR AND DATE f t' Hour of Day (EST) .All other 6 h Date 7 8 9 10 11 12 13 14- 15 16 17 times F 1/5 - 1/22 1 1 2 2 2 2 2 2 2 1 1 1 T- .1/23 - 2/6 1 1 2 2 2 2 2 2 2 1 1 1 l' 2/7 - 2/21 1 1 2 2 2 3 2 2 2 1 1 1 L - 2/22 - 3/8 1 2 2 2 3 3 3 2 2 2 1 1 3/9 - 3/23 1 2 2 3 3 3 3 3 2 2 1 1 i 3/24 - 4/7 1 2 3 3 3 3 3 3 3 2 1 1 C 4/8 - 4/22~ 2 2 3 3 3 3 3 3 3 2 2 1
. 4/23 -
5/7 2 2 3 3 4 4 4 3 3 2 ~2. 1 , ". 5/8' -
'.5/22 2 2 3 3 4 4 4 3 3 2 2 1 5/23 -
- 6/6 2 3 3 3 4 4 4 3 3 3 2 1
. s.- 6/7 -- 6/21 2 3 3 3 4 4 4 3 3 3 2 1 je 6/22 - 7/6 2 3 3 3 4 4 4 3 3 3 2 1
; 7/7 -
7/21 2 3 3 3 4 4 4 3 3 3 2 - 1 L 7/22- - 8/5 2 2 3 3 4 4 4 3 3 2 2 1-8/6- - 8/20 2 2 3 3 4 4 4 3 3 2 2 1 8/21 . - 9/4 2,,2 3 3 3 3 3 3 3 2 2 1 9/5 - 9/19 1 2- 3 3 3 3 3 3 3 2 1 1 9/20 - 10/4 1 2 2 3 3 3 3 3 2 2 1 1 10/5 - 10/19 1 2 2 2 3 3 3 2 2 2 1 1 c 10/20 - 11/3 1 1 2 2 2 3 2 2 2 1 1 - 1
*-- 11/4 -
11/18 1 1 2 2 2 2 2 2 2 1 1 1 11/19 - 12/3 1 1 2 2 2 2 2 2 1 1 1 lf
;a.
12/4 - 12/18 l' 1 1 2 2 -2 2 2 2 1 1 1 1 12/19 - 1/4 1 1 1 2 '2 2 2 2 1 1 1 1 i g Source: Turnor, B.T., " Relationship Between 24-Hour Mean Air Quality Measurements and Meteorological Factors in Nashville, TN, lp Journal-of-Air Pollution Control Association, October, 1961, i pp 483-489. l .
+
.h._
i
*" + + % a 4 -.,e -
q,. g g, 9 p. .g , , . , . , , , , . , , , , , , , ,__ , ,,
. . ;.-.~ %' -
. -. '~. '. '. . w . - , -
EP-316, Rev. 3 Page 13 of 69 DMR/ nip TABLE 316-C NRADI DURING DAYTIME (FUNCTION OF CLCVR AND CLCEG)
- f. AND NIGHTTIME (FUNCTION OF CLCVR) CONDITIONS L
-1 g-Nighttime
{. . Daytime CLCEG s' . f l CLCVR < 7,000 ft 7,000-15,900 ft ,
> 16,000 ft
?
0/10 r 1/10 1 2/10 NRADI = ICLNO NRADI = -2 3/10. l 4/10 l 5/10 r:- 6/10 . I; 7/10 NRADI* = ICLNO -2 NRADI* = ICLMO -1 ' NRADI** = -1 cd 8/10 . 9/10
, 10/10 'NRADI = 0
*If NRADI is less than 1, set NRADI equal to 1.
l **If CLCVR is 10/10 and the ceiling is < 7,000 Ft, NRADI equals 0.
. TABLE 316-D i STABILITY CLASS AS A FUNCTION OF NRADI AND WS30
- NRADI 4e WS30 Daytime Nighttime (Knots) 4 3 2 1 0 -1 -2 0 or 1 A A B C D F G i
; 2 or 3 A B B C D F G e
I 4 or 5 A B C D D E F C-6 B B C D D E F b_ 7 B B C D D D E 8 or 9 B C C D D D E 10 C C D D D D E
- 11 C C D D D D D
>l2 C D D D D D D b'
I 9 me- a %....ee, ,.y.-..g ,g..,_ w .I . . , .
.g, . , . , . ,. ,. ., _ g .g.. . . _ , , , , , , . , _ y_ , . , , . , ,
9 - , - g -.- eI4 q v -- m , e. - v - - , ->n 4 e - + - ,s
i e x .L J, c!.J : ;, n.....,. .. .,; Q -
. , , , ; ., w . = ... . . . ,c .rl-
. g ,, , , , . . , .
. ., g. ..,
,,.,.g.
?, .
. l,
' 'r
- EP-316, Rev. 3 , 'lf
[ Page 14 of 69 . ,
, DMR/nlp ,
3 ,
' DATA SHEET l- (Section 2.0) hrs., _
DATE TIME PERIOD (RELEASE DURATION): 2.0.1 SOURCE TERM INFORMAT_I_O_N_ < Effluent Monitor Sample Analysis Attached-(Y,N) Release Point Vent Flow Noble Gas Iodine (Yes or No) Rate (CFM) Information , ( North vent
- uci/sec .
l' 1v Unit 1 South vent uCi/cc f
'.a
(
- l. $ i' Unit 2 South Vent uCi/cc ; ;,
.p -j
- North Stack Vent Flow = uCi/sec uC1/cc x 472
; 2.0.2 METEOROLOGICAL CONDITIONS 1 .j ;
Wind speed - elevated mph i*
'j Wind direction - elevated deg az s 3
Stability class i NAME/ TITLE: ! DATE: __ f
; TIME: #
l I
. ,i
,_f -
- . .I'1
zz:.a: . _ a__ .y y a.y.g.;. . . 3,. ._ , _ R.-
= '
9-3
- EP-316, Rev. 3 Page 15 of 69
^{ ' DMR/nlp
!.l -
-+
y.
.2.1 CHI /Q AND PLUME TRAVEL TIME DETERMINATION ld. .~
t Determine the centerline CHI /Q.value from the ground and/or R-V . elevated overlays, completing Worksheet 1 in the process. 10 A ^ 2.1.1 Inputs Needed
'-1,.
Record elevated wind speed,-elevated wind direction, 'J h . 1. it- and stability class from Data Sheet 1. j 2. Determine the direction toward which the wind is 4 blowing (downwind sector bearing) by adding 180 degrees to average elevated wind-direction. If
' greater than 360 degrees, subtract 360 degrees from the sum. Enter on Worksheet 1 under bearing. ]. ,
j 3. Record release point identifier (i.e. north vent, U1 [m or U2 south vents) and vent flow rate from Data Sheet 3 1.
- Q
,? - 2.1.2 . Release' Type Determination
- 1. Utilizing release point, vent flow rate and elevated wind speed data, determine release type from. Table 316-E.
11' N_ -l 2. Identify release type on Worksheet 1.
-? 2.1.3 0verlay Selection
's- a^' l. Ground Release: Select overlay from Table 316-F.
'F0 Af 2. Elevated Release: Utilizing elevated wind speed, 30 stability class, release point and flow rate from
! Data Sheet 1, go to Table 316-G. Select overlay from Table 316-G.
4 Jk Select overlay _from Tables
- 3. Mixed Mode 1/2 Release:
NI 316-F and 316-G. u ,. y 4. Identify the overlays selected on the appropriate e portion of Worksheet 1.
. b Overlay Orientation E(
1 2.1.4 (,$. 1. Place overlay on base map. l 4 2. Align overlay in bearing direction, using azimuth
~i indicators for guidance. Tape in placa and tighten '
3~ wing nut. h g 3 >
~=
.p-.-- -
7., . p .,.f. y . , , . , . . . . . , , . , . ., _ . . , , ,
- 9. m o . . . m. _ .c .
~
,y . . . .. , _ , .
j . 30 . EP-316, Rav. 3 ' n . Page-16 of.69 q.' DMR/nlp l Y , l
- 1' 1: 3. For mixed mode 1/2 release type, procedure has.to be j 4'; repeated for both ground and elevated overlays.
O 2.1.5 CHI /O Calculation [?e 1. . Ground release only N s_ 7 A. For each applicable distance, reference " centerline' information box for Xu/Q value. - B. Calculate and enter CHI /Q values in Column A of.
~
Worksheet 1. r. j- ' C. Go to Section 2.1.6.
- 2. Elevated release only
]t.
A. For each applicable distance, reference " centerline (:<. z _., information box for Yu/Q value.
..~~
B. Calculate and. enter CHI /O values in Column C of
-- 'Worksheet 1.
C. Go to Section 2.1.6.
-~ 3. Mixed Mode 1/2 Release A. Perform procedure steps'2.1.5.1 and 2.1.5.2.
pr List ground CHI /O values in Column A, and
.A elevated CHI /Q values in Column C of Worksheet 1.
kd Utilizing release point, vent flow rate and
- p. B.
elevated wind speed data, determine entrainment
- coefficient (ET) from Table 316-H for a-North Vent release, or Table 316-I for a South vent release. Enter ET in Column B of Worksheet 1.
r ' This is the portion of the plume downwashed (or ,'.. entrained) to the ground. LF C. Calculate elevated portion of plume (1 - ET ) and 'k enter in Column D of Worksheet 1. This is the
.I portion of the plume remaining elevated.
'46-D. Calculate mixed mode CHI /O on Worksheet 1: J(L . 2.1.6 Plume Travel Time (Tp) k!
.i
- 1. Ground, Elevated, or Mixed Mode Release:
Ji Tp (min) = Downwind Distance (miles) x 60.0 (min) ! i-I i,i
-y h4 ; u ru + v y .y .p-a. gyt 9W aig* g , ga p *e..m3 g a p,. . . , , , , , , , . , , , , , , , , _ ,
^
. , , - . ,... .. . . . . . - - . . , . . - . - . - . . - . , - - , - . . . - . . - - - . . . . ----2 :L_.____
s_,~a . - a. .. ...:,a > . , . . .,_.. . . .
- 7; a, + . ,
, .-+- , ,* ; ..- , _ , . .._ . . . . _ _ .. ..._ .. ..-..___.... - _.. _ . . _ . - - . . ... - .
4 k . EP-3164 Rev. 3 Page 17 of 69 DMR/nlp w t Elevated Wind Speed (mph) hr L 2. Record plume travel time in last column of ( Worksheet-1. ll (. k i. c 1 (' ' b b
~ f, p ,
, .=
. 7. ;-
.L-L
/
w %-
.y e
x.-
- 3. +
;f .
y m h(-
} +*
- i*
.'h i
D
'I f
m h' tv la a I.. I I . *m == eewe. . - gency e. - .e. y e we oe . , -e.,s. 6.e e * - me a em .. o. -= . *
* -..w- 3 . . . , .,e.. .w.,-.. . - * .*e .. - ---. ,,....s
.-3 . - . .. . . . . ..--- ~ .y..
, ,9 2+ . ,, - m.y 7 . . . .-
* * $ ' L '
_a
~'
L. s. 1 . ._ . c. . . 9
' EP-316, Rev. 3 Page 18.of 69 DMR/nlp
- t 3 TABLE 316-E
. RELEASE TYPING.AS A FUNCTION OF VENT FLOW RATE, RELEASE POINT AND ELEVATED WIND SPEED .f.
L NORTH VENT RELEASE t
.N. ! . VENT FLOW ELEVATED WIND SPEED (MPH) ? RATE (CFM) t ELEVATED MIXED MODE 1 MIXED MODE 2 GROUND 386,000-410,000 1 3.8 3.9 12.6 12.7 - 19.0 1 19.1 D; l 321,000-385,000 1 3.4 3.5 - 11.5 11.6 - 16.9 1 17.0 f- .] 231,000-320,000 1 2.6 2.7 - 8.7 8.8 - 13.0 1 13.1 7
150,000-230,000 < l.7 1.8 - 5.7 5.8 - 8.7 1 8.8 l
< 3,000* N/A. N/A N/A All w
Ib Ul OR U2 SOUTH VENT RELEASE F- VENT FLOW ELEVATED WIND SPEED (MPH) , i RATE (CFM)
' ELEVATED MIXED MODE 1 MIXED MODE 2 GROUND Y
201,000-234,000 1 5.3 5.4 - 17.6 17.7 - 26.7 1 26.8
- [e l.
i.i l 151,000-200,000 < 3.9 4. 0 - 13.2 13.3 - 19.9
> 20.0 t 2.9 - 9.4 9.5 - 14.2 > 14.3
- l 109,000-150,000 < 2.8
,$ ] 61,000-100,000 < l.8 1.9 - 6.2 6.3 - 9.3 1 9.4 lh 40,000-60,000 < 1.2 1.3 - 3.8 3.9 - 5.7 1 5.8
; v.! 1 3,000* N/A ,N/A N/A All f.
~
h ,- ;; N/A - Not Applicable
~~
- Represents release from isolated vents. Alwavs results e in ground level release.
P 5 A .a. m
.+.br: g F 9,*4**O9 *. # r '4 4 .g9 - g , sg g g g W p y g _ p., ,,,
' ^
.t. _......._4.', ---.- .- . 6:, .. ,.. _ , - ~ . - . < - , , s .
[i '
.EP-316, Rav. 3
" Page 19 of 69 DMR/nlp L.
.t TABLE 316-F
.n I
GROUND LEVEL RELEASE OVERLAY SELECTION
.1.s-F Stability Class Overlay Figure A GA 316-A r
i B GB 316-B r C GC- 316-C 4 4 D - GD 316-D
?
316-E V. E GE
- t-0.
t ll ' F GF 316-F G GG 316-G w. s v i 1; a y i,V .
' D
! b e)
' 5h i
.M, i
', 3 5
.I-
.?
s
'l i !, -
i .v 3?
'd e 1 e ,
7, AN,f 8e *T I'p a ..s*-a.* + e ...e, - yusase g = *,= .~ m h ,. g -p--..m.. .- a . - .
--.,y 79,,,y,.s.- . _. _
s aw- s.z.a z :n~...w.:
, - . 2-.:..a:a ...a,- ..... . .
. .u 1
.x . .,; n)
.. D g .
s- " *~ P **b 7 % , _f: "P TT 5 7 ~ " '; v m f [ Y[1 ' 'T '7 .o . e.
- i. 'Er*'16,.Rev. 3 "
., . i Page: 20 of 69 " 'O DMR/, nip
'I hl TABLE 316-G.
O1-; . ?
-ELEVATED RELEASE OVERLAY' SELECTION
V 4 {i - . :i ELEVATED WIND SPEED (MPH) 4
.(
l NORTH VENT FLOW RATE- SOUTH VENT FLOW RATE
,j .j STABILITY 3RG-410 (CFM x 1,000) 321-385 231-320 150-230 201-234 151-200 (CFM x 1,000) 101-150 61-100 40-60 OVERLAY FIGURE l CLASS All All All All All All EAl 316-H
' ) A All All All 0, t
>.3.5 > 7.5 > 5.5 > 3.5 >.2.5 > 1.5 EB1 316-I B > 6.5 > 6.5 > 4.5 EB2 316-J 2j ' 3 3.5-6.4 3.5-6.4 2.5-4.4 1.5-3.4 375-7.4 275-5.4 175-3.4 175-2.f 7 1.4 ~
EH3 316-K j 5 1.4
. ~-
2.5-3.4 2.5-3.4 1.5-2.4
-- 2.5-3.4 1.5-2.4 --
4
< l.4 -- -- EB4 316-L j 1 1 2.4 5 2.4 < 1.4 < l.4 1 2.4 < l.4 ECl 316-M l-
~
> 3.5 > 7.5 > 5.5 > 4.5 > 2.5 > 1.5
> 8.5 > 8.5 > 5.5 316-N
- C 4~5-8.4 475-8.4 375-5.4 275-3.4 475-7.4 375-5.4 275-4.4 l~5-2.4 ~ 1.4 EC2
~
; 316-0 2.5-4.4 1.5-3.4 1.5-2.4 < l.4 -- EC3
- 2.5-4.4 2.5-4.4 1.5-3.4 1.5-2.4 EC4 316-P 5 1.4 1 1.4 l
i 2.4 1 2.4 1 1.4 1 1.4 1 2.4 .
> 3.5 > 7.5 > 5.5 > 4.5 > 2.5 > 1.5 ED1 316-Q
'l D > 7.5 > 7.5 > 5.5 ~
475-7.4 3 5-5.4 275-4.4 175-2.4 ED2 316-R.
~
;' 475-7.4 475-7.4 375-5.4 275-3.4 < 1.4 ED3 316-S-3.5-4.4 3.5-4.4 2.5-3.4 1.5-2.4 3.5-4.4 2.5-3.4 1.5-2.4 --
316-T 2.5-3.4 1.5-2.4 -- < l.4 -- ED4 2.5-3.4 2.5-3.4 -- --
~
EDS 316-U [ < 2.A 1 2.4 12.4 1 1.4 1 2.4- 1 1.4 1 1.4 -- -- I > 1.5 > 1.5 All All All eel 316-V E > 2.5 > 2.5 > 1.5 All 316-W 7 1.4 7 1.4 -- -- -- EE2 175-2.4 175-2.4 7 1.4 -- 316-X EE3
< l.4
- - 1.4
> 1.5 > 1.5 All All All EF1 316-Y F > 2.5 > 2.5 > 1.5 All 316-Z.
t : ~ 7 1.4 -- EF2 I 1.5-2.4 1.5-2.4 7 1.4
~
1.4- '-
-. -- EF3 316-AA
< l.4 < l.4 --
> 1.5 > 1.5 All All All EG1 316-BB
> <' > 2.5 > 2.5 > 1.5 All G
7 1.4 7 1.4 -- -- -- EG2 316-CC 175-2.4 175-2.4
' 7 1.4
-- -- -- EG3 316-DD
< 1.4 -
< 1.4 --
,I l'* i ,
d
i i ~ " ' _ ,. . c ;.. .. p,q. : . ., q, . .s. y ,_,
} . .
-h
-i .
EP-316, Ibv. .3 Page 21 of 69 It1P/n1p 1 TNti.E 316-11 ,
.,i
- ?. i nirPAlt!10TP CTITICIDrr (EP) J~
-, i.. l
,FOR FKRITI VDTP IETJ'ASE f .,
j ,: I ' i - ET.INATm t!IllD SPEFD (f1PII) ! i V D rr FIIII f j rate (cal) 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 13.0 14.0 15.0 16.0 17.0 10.0 19.0 >20.0 i l 38G,000 - 410,000 0.00 0.00 0.00 0.01 0.07 0.11 0.14 0.16 0.17 0.19 0.20 0.20 0.27 0.43 0.57 0.70 0.81 0.91 0.99 1.00
'[ '
i 321,000 - 385,000 0.00 0.00 0.00 0.05 0.10 0.13 0.16 0.17 0.19 0.20 0.21 0.36 0.53 0.67 0.80.0.91 1.00 1.00 1.00 1.00
! 231,000 - 320,000 0.00 0.00 0.04 0.10 0.14 0.17 0.19 0.20 0.27 0.50 0.69 0.84 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.'00
}
, .l 150,000 - 230,000 0.00 0.03 0.12 0.16 0.19 0.19 0.53 0.78 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 3,000 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 i l
.: tbte:
i E = 0.00 Elevated Eclease I E = 1.00 Ground Ibicane . r
'I i 0.00 <E <1.00 tiir.ed ible Ibicaco I i
t I
,; Source: Ibgulatory culde 1.111 Invision 1 a f 1 , t .! \;
i ,
., .-a. - . . . . .. .. ... . . - . . - - . .. .
- 1. . - l. . - ~ a. ,w . . N .. ... .a a . . . . ..2 3- gr~ ~- + rt' y ? } T"' W7? r ~"W* '
n-GWp d . :'
. .r I
EP-316, m v..'3 ' Page 22 of 69
; .IYm/ nip TABIP. 316-I
} l.
DTITAllUDTP (YTTPICIDTP (CP) ITXt Sotml VDTP IEITASE - t I i VDTP FIDT ETJNATID WITID SPEFD (f!Pfl) i PATE (cm) 1.0 2.0 3.0 4 . 0. 5.0 G.0 7.0 8.0 .9.0 10.0 11.0 12.0 13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 f; 201,000 - 234,000 0.00 0,00 0.00 0.00 0.00 0.05 0.08 0.11 0.13 0.15 0.16 0.17 0.18 I' 0 151,000 - 200,000 0.00 0.00 0.00 0.00 0.06 0.10 0.13 0.15 0.16 0.18 0.19 0.20 0.21 101,000 - 150,000 0.00 0.00 0.01 0.08 0.12 0.15 0.17 0.19 0.20 0.27 0.48 0.66 0.81 !' 61,000 - 100,000 0.00 0.02 0.11 0.1G 0.19 0.21 0.47 0.73 0.94 1. 00 1.00 1.00 1.00 j 40,000 - 60,000 0.00 0.13 0.18 0.20 0.74 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00
-l 3,000 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 i 2
I
?
tiote: CP = 0.00 ETJVATID IETTASE EP = 1.00 cnnurID RErrASE e < j 0.00 < ET < 1.00 t1Ir.Im riort IEITASE
,, Source: Ibgulatory Guide 1.111 Ibvision 1 13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 24.0 25.0 0.18 0.19 0.20 0.21 0.23 0.35 0.48 0.59 0.68 0.77 0.85 0.92 1.00 0.21 0.28 0.43 0.5G 0.C8 0.78 0.88 0.97 1.00 1.00 1.00 1.00 1.00 0.81 0.93 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 '
1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00
. e. ...s_, _ _ , , = - .. . , _ - --.-._.o _ . . . . , , _ . , _ _ _ , , _ . , . ,
^
r -- -r-., y - - , , ym _ . _ _ fvr .;s,-n 7. .. t t il EP-316, Rev. 3 .. i id Page.23 of,69- ,
. I, DMR/nlp i WORKSIIEET 1 (Section 2.1) i ll CALCULATION TABLE - CllI/O DISPERSION FACTOR (PLUME CENTERLINE) AT LOCATIO
- Elevated Wind Speed: aph degrees azimuth a Elevated Wind Direction:
Bearings. Sector Stability Class:
Vent Flow Rate cfm Release Point Identifier Release Type: Ground Mixed Mode 1 Mixed Mode 2 Elevated Overlays Selected: Ground Elevated x D = E Plume A x B + C Travel Tim'e
,i Downwind
- ET ** Elevated CllI/O l-ET Mixed Mode 1 or 2
- Distance CIII/O (sec/m3) (min.)
(Miles) (sec/m3) (sec/m3) l T 0.5 ,
! 2.0 5.0 10.0 OTIIER
-2
- GROUND CIII/O = Xq (M ) X 2.237 (mph /m/sec)
O ELEVATED WIND SPEED (MPil) ' i
.' -2 f
** ELEVATED CIII/O = X5 (M ) X 2.237 (mph /m/sec)
- - - - = * *= w e een t oengg )
,_- .e . . .- .__ _. s 1 . ._.
L s ; EP-316, Rev. 3 i Page 24 of 69- {i DMR/nlp l- .. . 1 p . 2.2 WHOLE BODY' DOSE'DUE TO NOBLE GAS RELEASES M: 2.2.1 Plume Centerline Dose I-
- FOR " PUFF TYPE" RELEASES OR SHORT TERM RELEASES WITH CONSISTENT ME*EOROLOGY, TIME PERIOD CORRESPONDS WITH THE l
TOTAL PERIOD OF RELEASE. FOR LONG TERM RELEASES WITH l~ j ; (~. p CONSISTENT METEOROLOGY, THE TIME PERIOD CORRESPONDS WITH THE TOTAL PERIOD OF RELEASE. IF METEOROLOGY CHANGES (I .E.
- p. WIND DIRECTION SHIFTS, ATMOSPHERIC STABILITY CHANGES, OR-
; WIND SPEED CHANGES SIGNIFICANTLY) , DIVIDE THE RELEASE INTO
{[ SEGMENTS ACCORDING TO SUCH SHIFTS.
! ' l.
For-a release from the South vent, complete Worksheet-i 2. 1 'l~p' p A. Record the, release' data in Columns A and B on ' t p- Worksheet 2 from Data Sheet 1. 1 B. Record'the vent flow rate from the appropriate [0- release point in Column C on Worksheet 2 from Data 37 Sheet 1. L C. Perform the operations indicated on Worksheet 2 to obtain release rate (Column E) in uCi/sec
. Record 4.
in Column A of Work Sheet 4. 7 . I~
- 2. Determine the Gamma-Dose Factor by completing Worksheet 3 when an updated isotopic mix.from a MCA sample analysis is known. *If no sample analysis is available, refer to Table 316-J to obtain the gamma dose f, ,
conversion Factor based on the time since the reactor 4
] shutdown.. Transfer gamma dose factor to Column D of i Worksheet 4. . F l* l Table 316-J *I T= lo hrs 0-2 hrs' 2-8 hrsl8 hrs-1 day 1 day-4 days <4 days-30 3
Lj- Rem-m uCi-hr 6.14N4 3.57N4 1.07N4 3.38N5 3.36N5 3. 09N! t 4 3. Complete Worksheet 4 to calculate Gamma Dose at locations of interest.
. y-A. Record the CHI /O dispersion factor from Worksheet
;g 1 at each downwind distance of interest in Column s
B. Record release duration from Data Sheet 1, and enter in Column E o,n Worksheet 4. o 4 h
. , , y .
# u._ , .
.+*-(- w
- 6 -** * ' ""
EP-316, Rev. 3. Page 25 of 69 DMR/nlp
' 8 l
C. Perform the c51culations indicated on Worksheet 4, i to obtain air _ concentration (Column C) and the resultant gamma whole body-doses (Column F) .
.i , 4. Determine Whole Body Man-Rem estimates by completing
_; I Worksheet 5. Use Table 316-L Population Distribution. l 7 F r
-[ t e
i I L _. I - r Ik i ?!. c a,
,i
- a
?
d 1
;. 4
' ' (o
- i ,
ij ((- - e m
.,e .,.
~ V W **wN
5I ' -
; ,' h. . ',
('!.p .( Iiiil l !! 9
~- -
39p. 6i - E n T vf/ A)
- R RC Re o. M E 6D- EES
',2 S/
6 AI 1 e EC . 3 g LU
- a E(
PP R E
. =
_ R O
. T C
A F S N 2 2 y N DO 7 7 4 O I 4 I S T R g 2
) A L
U E V N 2 C O L C n A o C i t E X , c T e A S R ( E E T 2 S A A R q T E E L W)
+p .
E E OM H R CLF S FC( K S R A T O G N W E E V
. L B
s - O N X" e v r
- u: Y) s, TC IC
- V/
. BII
,. TC 7
CU . A(
., t n
t n e
.g S e
. T V V N
I h h O t t P u u -
. A o o E S S S
. A 1 2 E
L t t E i i R n n U U iS I ; ,i ' . ' . I I -
;i '- tr ;. < ' : 4 ! .%
- g q
' ) ,1.
a 9
~ '
g y, . . -- ,. . > , g'..,- . 7- . .g 3 .,. e. , _pyg - : l-
- EP-316, Rev. a ,
s
.Page 27 of 69 DMR/nlp
.?
' WORKSHEET 3 (Section 2.2)
CALCULATION TABLE - GAMMA DOSE FACTOR , 4
< l A X B = C '
Gamma Dose Decimal % Abundance NUCLIDE Isotopic Decimal % (Rem-m3) X Factor Abundance Factor uci-hr (Rem-m3) *
- uCl-hr Kr-83m 8.63 N9 Kr-85m 1.34 N4 Kr-85 1.84 N6 Kr-87 6.76 N4 4 1,68 N3 4,
s Kr-88 , h ye-131m 1.04 N5 Xe-133m 2.87 N5 2 * . Xe-133 3.36 N5 [ . i, aj Xe-135 2.07 N4 r
*1 S
3 j: 1(C) = Rem-m ij t-uCl-hr - i L 3- { L
= "_ _ ;g_, ... ., a w, . , ,. . w , r . .. -
7 s ..
.. . l.
EP-316, Rev. 3 *
.i 'Page 28 of 69: .
9 DMR/nlp NORKSHEET 4 (Section 2.2) !- CALCULATION TABLE - PLUME CENTERLINE GROUND LEVEL WHOLE BODY DOSE AT LOCATIONS:OF INTEREST WIND DIRECTION: degrees BEARING: sector RELEASE POINT e B = C X D X E = F I' A X i: Chi /Q Air Gamma Dose
! DISTANCE Isotopic Release Dispersion Concentration (Rem-m3) Release Duration Gamma Dose
, 4 (MILES) Rate (uC1/sec) Factor (sec/m3) (uC1/m3) Factor (uci-hr) (Hours) (Rem)
.T. 0.5 b .j.
2.0 'l
., 5.0 <
, f.;
10.0 .:
,1
! l#
/p other __
4 ;, 1 BASIS: CENTERLINE OF RELEASE PATH ONLY. THESE CALCULATIONS ARE VALID FOR A CONSTANT ISOTOPIC l~ RELEASE RATE, CONSTANT STACK FLOW RATE, CONSTANT-DISTANCE, CONSTANT WIND SPE'ED, AND TURBULENCE CLASS. IF ANY OF THESE FACTORS CHANGE SIGNIFICANTLY, NEW VALUES MUST BE l CALCULATED. l i. I '.
- 'h A t.
d l I l
- - c._., - - m w., ut > n _ , : , ._- r - . , 2. : .- ._ , _ . _ ,
.)
. EP-316, Rev. 3 'l Page 29 of 69 ;
DMR/nlp WORKSHEET 5 (Section 2.2) WHOLE BODY MAN-REM ESTIMATES f: GAMMA DOSE (Rem) POPULATION
! LOCATION , .FROM COLUMN F IN BEARING (MILES) WORKSHEET 4 X SECTOR = MAN-REM D '
V. aj- 0-1 u-1-2 f
.2-3 t'
F L- .
!; 3-4 s
L: k 4-5.
- }.
L , 5-10
- F I - *Use value at 7.0 mile distance 1.
t
?
NAME/ TITLE: L. . t DATE: t. TIME: f_ SECTOR: 4... .. .. -.. . . _ _ . . . . . . . .. _ ..
.,.n_.,_,. .
- 7. ,,..,7 , ,.,
..z..=
- p. . ,.
m.. .
= ..n..- w ..= = _ =. ~ - e . ._.-
. =
. EP-316, Rsv. 3 Page 30 of 69 DMR/nlp
-2.3 THYROID DOSE DUE TO RADIOIODINE RELEASES 2.3.1 Plume Centerline Dose FOR " PUFF TYPE" RELEASES OR SHORT TERM RELEASES WITH
-. CONSISTENT. METEOROLOGY, TIME PERIOD CORRESPONDS WITH THE 4 TOTAL PERIOD OF RELEASE. FOR LONG TERM RELEASE WITH CONSISTENT METEOROLOGY, THE TIME PERIOD CORRESPONDS WITH
{. THE TOTAL PERIOD OF RELEASE. IF METEOROLOGY CHANGES (I.E. WIND DIRECTION SHIFTS, ATMOSPHERIC STABILITY (-' e CHANGES, OR WIND SPEED CHANGES SIGNIFICANTLY), DIVIDE THE
- { RELEASE INTO SEGMENTS'ACCORDING TO SUCH SHIFTS.
- l. For each release point, complete Worksheet 7 to calculate i~ thyroid doses at locations of interest.
I
!; A. Record the release points on Worksheet 7 from Data sheet 1. .
B. Record the release' data in Column A on Worksheet 7 from Data Sheet 1.
.r~~
C. Record th'e vent flow rate from the appropriate in release point in efm in Column B on Worksheet 7 from Data Sheet,1.
- 2. Determine the Iodine Inhalation and Ingestion Dose Factor
'-- by completing Worksheet 6 when an updated isotopic mix from sample analysis is known.
. F: If an updated isotopic mix is not available, and the ik. iodine monitors are isolated, perform the following:
.A. U1 or U2 South vent release - obtain noble gas concentration from Worksheet 2 Column B. If venting through SGTS, divide noble gas concentration by 340.
If not venting through SGTS, divide by 3.4. l B. North vent release - obtain noble gas release rate from Data Sheet 1. Divide this value by the product lE of 472 and the vent flow rate to obtain noble gas concentration. If venting through SGTS, divide noble Lf.f (j gas concentration by 340. If'r.ot venting through l l.: SGTS, divide by 3.4.
.y b If an updated isotopic mix is not available, but the iodine monitors are available, perform the following:
C. Multiply gross I-131 concentration by the appropriate t I-133 factor based on time since reactor shutdown l identified in Table 316-K, to determine I-133 concentration.
- eww "= i ---t, =
,w p- e . een e ge o gg. y- 4e j k*
- w ay e_ g.y -p=,,-
. = _ . - .. _9 any=_ pme ; . 9_ep g en,--n-+ m-: ++ 6 * * * - * * - ~ *p**gp ==we
- y. . .,.m. >
_ . _. w _ w , _g , 7gg . ;._,. 7 ,, . , . , , . , , z.2. . , .
,,,1 r,. ; : .
- n
- j,.. .
dI EP-316, Rnv. 3 i Page-31 of 69 0 'DMR/nlp l 4 ! l U
#i l TABLE 316-K a
- d. I-133 FACTOR VS TIME SINCE REACTOR SHUTDOWN 1
3 20 hrs' 24 hrs "h. lT= 0 hrs' l hr 2 hrs 4 hrs 8 hrs 12 hrs 16 hrs H D-M I-133 2.0 1.9 1.8 1.8 1.4 1.4 1.2- 1.1 -1.0 3 \ Factor i
- 3. Complete Worksheet 7 to calculate thyroid dose
, at locations of interest.
i A. Record the CHI /O dispersion factor from l' - Worksheet 1 at each downward distance of l interest. T' l B. Record release duration from Data Sheet 1 and L. enter in Column G of Worksheet 7.
, C. Perform the calculations indicated on Worksheet.
p 7 to obtain air concentration (Column E) - and the resultant thyroid doses -(Column H) . l 4. Determine Thyroid Man-Rem estimates by-completing 1-
] Worksheet 8. Use Table.316-L population distribation.
N Determination of Thyroid Dose from Field Survey Data e 2.3.2
.t.
- 1. Obtain I-131 concentration in air near plume
'M centerline from. field survey data. ; 2. Calculate the inhalation dose rate.
Concentration (uci) X 1.692 P6 '(Rem /hr) X 1.75 X Estimated = Dose (Rer I cc uCi/cc Release Duration (hrs) Record this dose on Worksheet 8, at the appropriate p ;(5[ distance and perform Thyroid Man-Rem Estimates. K g., . N e n - . . . , , . . . . . . . .. .- 2 #d.' '*****7 I h8"* .
.e, ,.en, y
,, s9 gg g, pp ..y,,,. , , , , , , , , , . q _, , , _
~ -
, r- w- n- ~ r n -
, y n ; ' + - ~
;-j '>~ v 7 -, v y w . - v r y y t o w y ,m g w,
"c i.
j[j bv EP-316,.Rev..
] ,
PageR32 ofL69 DMR/nlp; .
~ 2' ](j i' >
ic i WORKSHEET~6 (Section 2.3): , y . p s . J'
- b IODINE INHAT.ATION DOSE FACTORS ,
A ha Oi Y) ( uC1/cc I-131 x 1.692) + ( uC1/cc I-133 x 0.407) = , 9 uCi/cc I-131.+ uCi/cc I-133 '
~c4 ,.
1" F i
- Inhalation Dose Factors ' (Rem-m3) .f
; I-131 1.692 uCi-hr
~
I-133 0.407 ( s. i f .. IODINE INGESTION DOSE FACTORS
! i
! ( uCi/cc I-131 x 1.21 x P3) + ( uCi/cc I-133 x 11.2) =
uC1/cc I-131 + uC1/cc I-133 !. g Ingestion Dose Factors (Rem-m3) I-131 1.21 P3 uCi-hr I I-133 11.2 l 4 9 E .d
- t l .1' :
i
> n a
e
.f i i *l
V 'a
.;.w r, q ,i , s , , , ,
3 - ,
.o EP-316, Rav.
Page 33 of 69 5j DMR/ nip -j; a' y ; j .! WORKSHEF.T 7 (Section.2.3) II CALCULATION TABLE - PLUME CENTERLINE GROUND LEVEL
?
THYROID DOSE AT: LOCATIONS.OF INTEREST '
' degrees DEARING:- degrees RELEASE POINT WIND DIRECTION:
= E X F X G = H +
I A X D X C X D Iodine Air From Release Inhalation Distance Concen- Vent CHI /O
'< Dispersion- Concentration WorkSheet Duration Iodine / Dose (Miles) tration Flow Rate (Hours) (Rem)
(uC1/cc) (cfm) Factor (sec/m3) (uC1/m3) ( AxBxCxD) 6 Dose
., ' Factor
- 472 0.5
/j 2.0 472 j 5.0 472 e
;j ! 10.0 472 Other 472 -
- a. . .
, ?
= E X F X G = -H
, i A X B X C X D - !
1 ; Release Iodine Inges-Vent CHI /O Iodine Air From Distance Concen- tion Dose **
.t (Miles) tration Flow Rate Dispersion Concentration Worksheet Duration
- j i (uci/m3) ( AxBxCxD) 6 Dose (Hours) (Rem).
1 (uci/cc) (cfm) Factor (sec/m3) ** i. Factor *
- 0.5 472
-! 2.0 472 1 .' 5.0 472 10.0 472 Other 472 ,
Basis: Centerline of release path only. These calculations are valid for a constant isotopic I release rate, constant vent flow rate, constant distance, constant wind speed, and stability class. If any of these factors change significantly, new values must be calculated. Rem-m3
- Dose factors are in the units of uCi-hr . The deposition velocity of 0.01 m/sec has 4 been included in the ingestion dose factor. All dose factors are derived fror,R.G. 1.109t.
**If November 1 through April 1. (non-grazing season) the ingestion dose is zero.
.z . .. : .
...----.a..
- .-~.
~
_ ... _. . . - . .. 2- __..'
'f .
G . EP-316, Rav..-3.
* - Page.34 of 69 DMR/nlp
'1. '
- WORKSHEET 8 (Section 2.3) 9 THYROID MAN-REM ESTIMATES
-(
!L THYROID DOSE (Rem) POPULATION
- 0. LOCATION FROM COLUMN H IN BEARING
- (MILES) WORKSHEET 7 X SECTOR = MAN-REM d:
0-1 g-1
- 0 .1-2 3
4 2-3 3 q ,C 3-4 A-p 3.- 4_5
^
5-10 *
-l i.
*Use-value at 7.0 mile dis'tance
- IODINE-i- FIELD SURVEY uCI X 1.692 P6 X 1.75 X Estimated = INHALATION DOSE CONCENTRATION CC Relea'se RATE (Rem) f~ Duration (hours) 6'
.;- NAME/ TITLE:
I. DATE:
- TIME:
SECTOR:
'L m
'L f*' h
- m. { .
- ~
l
+ m,s-e e ; e - ~ .a s . a > + ._yg n. ,y g..,. e _
_.,,,..,nn.,, 7,n ,, . , . ,
- ._ .: - ._ 2 . . . . - _ . . . _ . . .__ .. -
, ( .e
- L _ - 3_; .2_ T _;. -; ; _
[_ . u.z .. 1 1 En-als, Rav. 3 I Page 35 of 69
]7 '
DMR/nlp A ~ T 2.4 GROUND DEPOSITION PER UNIT AREA
^
g T 2.4.1 Assessment of Offsite Plume Centerline Deposition per i Unit Area
.3 h ' FOR " PUFF TYPE"- RELEASES OR SHORT TERM RELEASES WITH CONSISTENT MET'E OROLOGY, TIME PERIOD CORRESPONDS WITH THE.
t TOTAL PERIOD OF RELEASE. FOR LONG TERM RELEASES WITH
$- CONSISTENT METEOROLOGY, THE TIME PERIOD CORRESPONDS WITH~
y THE TOTAL PERIOD OF RELEASE. IF METEOROLOGY CHANGES
';- (I.E. WIND DIRECTION SHIFTS, ATMOSPHERIC STABILITY.
J CHANGES, OR WIND SPEED CHANGES SIGNIFICANTLY) DIVIDE THE RELEASE-INTO SEGMENTS ACCORDING TO SUCH SHIFTS. if J
- r. 1. Record the wind direction from Data Sheet 1 on Worksheet 4
- 9. . Determine the direction toward which the wind is i- -- blowing (downwind sector) by adding 180 degrees to
- '_; average wind direction. If greater-than 360 degrees, gr. . subtract 360 degrees from-the sum.
-- e. ' F5
- 2. Obtain the location of the farms of interest from the
' El Environmental Sampling Coordinator. Select downwind
- le farms and enter distances from release points to these
~
locations on Column A of Worksheet 9. "I
- 3. Enter the iodine air concentration values from Worksheet
; 7 Column E on Worksheet 9 Column B, C, or D, dependent.
upon'the release point.
=-
'e - 4. Enter estimated release duration from Data Sheet.1 in Column F of Worksheet 9.
f4 5. Perform the operations indicated to obtain the plume
- i. centerline deposition per unit area (Column G) in
- p. Worksheet 9 in uci/ square meters.
-b
.i.
.k3
'V
.t i-i i 1 9
?
h e e- en 4 +
'WLw "'441% ( * *Y _~ 4 4
_ 4 ,N$ *W Mf*f% _# j' N * 's-
'M4 9.,...."N*. ' _ . ' . . , . - _ _ . _ . . . _ . _ . _ . _ . . . . _ _ . . . . - - _ . ._ . . ,. _ .
+
. . - ~
. 3. 7.-
.-_ ,,.,...e, ....
,,.y--.---. .
.c s, .. , _ . . , . , ..,,,,.,-9,.. , - , ,
EP-316, Rev. 3 '* If. ~ Page.-36 of 69 6 DMR'/ nip
- u. t a ' 't WORKSHEET 9 (Section 2.4) 4 PLUME CENTERLINE DEPOSITION PER UNIT AREA - (uCI/M2) 'I degrees at BEARING: sector RELEASE POINT i <
WIND DIRECTION: : i D E F GA A B C y DEPOSITION RELEASE DEPOSITION-4
] t DOWNWIND IODINE AIR CONCENTRATION (uCi/m3) COLUMN E WORK' SHEET 7 VELOCITY DURATION PER UNIT AREA (HOURS) (UCI/M2) ,_7 NORTH VENT Ul SOUTH VENT U2 SOUTH VENT (M/HR) y;j DISTANCE 36 36 i
36
- 36 I
i 36 4 36 1' 36 36 36 36 36 36 f' 36 36 l, 36
- To ca,1culate Col. G: Assumes deposition velocity j NAME/ TITLE: of 0.01 m/sec (36 m/hr) l DATE: (B + C + D) xExF=G
! TIME:
i , i i 1 i r ,
" u-e s, w .) -7 .-,; -.,,, . m g q +- . ,.
~-
-+ --
4 _ 4 .. a EP-316, Rev. 3 ..' Page137 of 69- - 1 DMR/ nip '
.I , .
rj l TABLE 316-L POPULATION DISTRIBUTION O -10 MILES ;, 1985 . DISTANCE,(MILES) 1
, l i 1 l
l' j Sector 0-1 1-2 2-3 3-4 4-5 5-10 10-Mile Total- . e N 60 712 933 414 786 3,296 6,201 NNE 48 1,135 254 499 212 2,533 4,681' NE 48 42 210 349 288 3,894 4,831 .j. ' ENE 12 60 207 397 237 5,359 6,272 E 21 156 282 406 436 5,341 6,642 ., ESE 30 186 309 279 604 9,620 11,0th,
+ SE 6 385 147 5,054 4,230 7,126 16,948-SSE O 204 306 2,861 1,704 22,544 27,619 ,
S 3 368 356 176 365 4,150 5,418 - i SSW 12 656 331 551 288 1,986 3,824 322 1,913 3,058 i s SW 74 195 220 334 WSW 49 192 572 492 1,714 2,041 5,060 l W 37 127 1,884 1,627 1,132 2,405 7,212. WNW 42 334 3,122 11,556 3,699 10,215 28,968 NW 21 300 1,953 6,955 1,366 4,176 14,771 NNW 36 742 1,802 1,'290 1,361 6,839 12,070 33,240 18,744 93,438 164,603 l Total 44'9 5,794 12,888 l' i.
.I , i I
1
-~ . .
r . EP-316, Rav. 3 Page 38 of 69 DMR/nlp I
; l APPENDIX EP-316-3
SUMMARY
SHEET
- 1. a. Elevated wind speed sph E'
[
- b. Elevated wind direction deg a n.
-c.' Stability class
. t-i
- 2. -Start Time of Release (military time)
!- Actual or Estimate (Circle One)
- (
) 3. Expected Release Duration hrs NL 4. Calculated Data Yes/No
- L
'b a) Projected Whole Body Dose (Worksheet 4) Attached lEy f!l, b) Whole' Body Man-Rem Estimates (Worksheet 5) Attached c) Projected Thyroid Dose (Worksheet 7) Attached
. d) Thyroid Man-Rem Estimates (Worksheet 8) Attached
- 5. Field Survey Data
[~ a) Whole Body, Dose Rate (Data Attached) !I b) Thyroid Dose Rate (Data Attached) P
- 6. Ground Deposition per Unit Area (Worksheet 9) Attached
- j. EP 317 Recommendats ms:
1_ 1.0/1 'L J'
!~
I; - A a e
- :- - .-z .. .- .. : . .
EP-316, R2v. 3 Page 39 of 69 APPENDIX EP-316-5 Chi /O Tables DMR/ nip I. APPENDIX EP-316-4
..,. , CHI /O OVERLAYS ;P .i k The following figures display the Xu/Q overlays for both ground
- J- level and elevated releases.
. t: k GROUND LEVEL OVERLAYS Y i Figures 316-A through 316-G represent the ground level overlays
! in units of Xu/Q (normalized for wind speed) for Pasquill stability '- Classes A through G, respectively. They should be applied for pure h ground level releases and for the ground-level portion of a mixed y mode release. ;g ELEVATED OVERLAYS b ~ Figures 316-H through 316-DD represent the 23 elevated overlays L- .
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APPENDIX EP-316-5 sj Chi /Q Tablea
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*3 EP-316,. ev. 3 s Page~64 of 69- .i 4 4 APPENDIX EP-316-5 '.
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APPENDIX EP-316-5. ' Ch1/Q Tables .i. DMR/nlp , i. 3 i> 31 3
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.(
4 APPENDIX EP-316-5
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EP-318 Rev. 2 Pace 1 of 8
.! l 3850072920 VA I' 'T P/rgs l l y//Ys9
- i PHILADELPHIA ELECTRIC COPSANY a- LIMERICK GENERATING STATION 4
EMERGENCY PLAN IMPLEMENTING PROCEDURE y 1 ?
- j. EP-318 LIQUID RELEASE DOSE CALCULATIONS METHOD FOR DRINKING WATER J
j 1.0 PARTICIPANTS j 1.1 Dose Assessment Team shall perform these calculations. i 1 1 . . 1 2.0 ACTIONS-IMMEDIATE 1
.1 The following assumptions were utilized in this calculation:
I!- 2.1.1 The Dose Conversion Factor is based on the most
.i. limiting group (adult, teen, child, infant) using dose l 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
..t.2 The Decay Factor is based on the decay of the sotope -, over the transit time plus 12 hours (time to reacn the j population via water system per Reg. Guide 1.109).
l 2.1.3 The total dose commitment is the dose wnien an individual would receive after drinkinc water,witn the radionuclides present at the concentrations
- h iculated
- -l to exist at the- entrance to the water ,pfantyd a
! period equal to the duration of tpefrele or i
d example, if the release lasteggEhou's, .. e '. 'l individualispostulatedtp(t:onsuse..b2'cfhisaverace !at ons.
~
daily water intake at t Ed 'iute'k lbdnc !! '5 PNt D f ,Y ] 2.2 Dose Assessment Team sh - M p{U g h$ gV a Ry R " 8.& 'i 'I 4
. _,A g. .,y_, . .
,3 .,,-..s- -
...,ma ,.-e-.,.+ .s~. -~~w '
} % y' "
.~=u , -. . . .
o , _.. Il EP-318 Rev. 2
. Page 2 of 8
.i l- VAW/JLP/rgs l!' ( 2.2.1 Obtain crab samole results cn1 the concentration,of Co-l 60, I-131, Cs-134 and Cs-137 released, from the j2 Chemistry Sampling and Analysis Team Leader. If the sample was taken prior to entering the Cooling JL Tower Blowdown Line, a diluted concentration must be - 4 determined by the following calculation: 1
- j. Concentration (uCi) = concentration x Release rate to Blowdown Line
. Released- (ci ) ( uCi) Blowdown line flow rate , (cc) 2.2.2 For each location of interest, enter.the concentration .l of Co-60, _ I-131, Cs-134 and Cs-137 in uCi/cc released i; and the release duration in hours on the appropriate appendix.
4
't 2.2.3 Perform the calculation in each appendix'for each t location of interest to estimate-the dose in millirem for the liver, whole body and thyroid.
2.2.4 Report results to the Dose Assessment Team Leader. i 3.0 ACTIONS-FOLLOW-UP None
; 4.0 APPENDICES ,
f 4 4.1 EP-318-1 Citizen Utilities Home Water Company Intake 4.2 EP-318-2 Phoenixville Water Intake 1 4.3 EP-318-3 Philadelphia Suburban Water Company Intaxe 4.4 EP-318-4 Norristown Water Intake 4 j 4.5 EP-318-5 Philadelphia Belmont Water Intake 9 n< 'l
? !I 4 .4 ~.
bsM- '
=r-e - A- + g p as w.a p em. w,tw+ Y
[ t-
- 4
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,. , .- . ...... . , . - . - .. - - . . . ~ _ - .
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l- ~ EP-318 Rcv. 2 Page 3 of 8
..-l VAW/JLP/rgs a
i;
- 5.0 . SUPPORTING INFORMATION l 5.1 Purpose ,
1 The purpose of this procedure is to provide the-
, l calculation method for estimates of individual, i
exposure due to.the ingestion of drinking water at [
. various locations downstream of the plant.
5.2 Criteria for use
~; , - 5.2.1 An actual or potential liquid release of radioactive , material into the Schuylkill River.
5.3 Special Eculpment .i
! None 5.4 References
- 5.'4.1 EROL 2.1.3.6 Surface Water Use 5.4.2 EROL 5.2.4.1 Liquid Pathways 5.4.3 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 5.4.4 Reg. Guide 1.109 Calculation-Of Annual Doses To
- l Rev. 2 Man From Routine Releases Of Reactor Effluents For The: Purpose Of Evaluating
, Compliance With 10 CFR Part 50, Appendix I f
- 4 I
i i c 1 's >{I '. { .i. j
.i f' .
i 4 MM v +,c- .- -- =,9.s ..,.4 m.- g 4.-,-- ,.e - e v.' .- pj .. .
.r . . _ . .
= - - ,:_,..
. _ . . # - , _ , , .- ; ,m , w _, ,.
s,lI:
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-l EP-310'Rev. 2 [
Page 4 of 8 / !i VAW/PIPG/me . , l Appendix EP-318-1 Citizenn Utilitlen Ilome Uater Company Intake i i (uCl) (mr/hr) >
}
Isotope Concentration (cc ) xdose factor (uCi/cc) xdecay factor =mr/hr .; Co-60 959 1.0 g I-131 700 0.95 i Cs-134 1.0lP4 1.0-Y - g Cs-137 5942 1.0 s dmr/hr) = mr/hr(whole body) Co-60 406 1.0
<t
.3 y I-131 1591 0.95 b
d Cs-134 2.64P4 1.0 l, I Cs-137 2.30P4 1.0 .
"j 3
Umr/hr) = { mr/hr(liver) i N I-131 5.23P5 0.95 mr/hr (thyroid) Schuylkill River Release flixing g lE_(mr/hr) x Usage Factor x Duration (hrs) x Factor = Dose - (mr) d
. 0.48 0.0118 (whole body) b d 0.48 0.0118 (liver)
# 0.48 0.0118 ( thyroid) :
I Initials l Date 1 6 4
,:.; r.: . . u. - . . ' . '
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. .. : s a.: , . x,. _ i Ji- .. q l l l EP-318? Rov. 2) j Pag 6 5 of 8
;VAU/f1PG/mc]
a l Appendix EP-318-2'Phoenixville Water Intake D i' (uci) (mr/hr) -}; Isotopo Concentration (cc ) xdoso factor (uci/cc) xdecay factor =mr/hr ' (l
. Co-60 959 1.0 ;'l' g I-131 700 0.92
! 2 Cs-134 1.01P4 3:
.l .
o 1.0
'l g Cs-137 5942 1.0 .
i I 1(mr/hr)= mr/hr (whole body) I. . Co-60 406 1.0 l I-131 1591 0.92 .
,' M Cs-134 2.64P4 1.0 w '
" Cs-137 2.30P4 1.0 l l
-i 5
~
l
% 8mr/hr)= mr/hr (liver) k
@ I-131 5.23P5 0.92 mr/hr (thyroid)
I Schuylkill River Release flixing
;t J 2E (mr/hr) x Usage Factor x Duration (hrs) x Factor = Dose (mr) l
'! d l . 1.0 0.0118 (whole body) ,
.I 3 4
! 1.0 '
6 0.0118 (liver) l 1 'i ' 6 1.0 0.0118 (thyroid) l I ! ;j l Initials
- Date I,
's .i h.
f
. ,. ~;1 ..,.....w,-:.~,~.. s.,.~. . = - . - , . :.-.-.~~~-----.~~-~~-~----1~ ; .
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! l EP-318 Rev. 2
~ Page '6 o f ' 8 Ig VAW/ MPG /mc ,
- l. Appendix EP-318-3 Philadelphia Suburban. Hater Company Intake.
(uci) (mr/hr) . Isotope Concentration (cc ) xdose factor (uci/cc) xdecay factor =mr/hr' }' I Co-60 959 1.0 ' 4 I-131 700 0.90 e t
. Cs-134 1.01P4 1.0 ;
o 5 Cs-137 5942 1.0 mr (whole body) F Smr/hr)= Co-60 406 1.0 3 u I-131 1591 0.90 I E U Cs-134 ' 2.64P4 1.0 Cs-137 2.30P4 1.0 e o Smr/hr) = mr/hr(1iver) .:
@ I-131 5.23P5 0.90 mr/hr (thyroid) -
Schuylkill River . Release Mixing q 2- (mr/hr) x Usage Factor x Duration (hrs) x Pactor = Dose (mr) ,, 3 4
- 0.22 0.0149 (whole body). .
-0.22 0.0149 (liver) u N 0. 22 0.0149 (thyroid) l Initials Date i '
r h 4
. . ,. . _ . .. . . - . . . .- . . ~ . . , - ..
.; S..l }.
l ~ EP-318 nev. 2 ~ Page '7 of 8, g-s VAW/f1PG/mc , l Appendix EP-318-4 11orristown Water. Intake (uCl) (mr/hr) Isotope Concentration (cc ) xdose factor (uci/cc) xdecay factor =mr/hr . Co-60 959 1.0- { 4'I-131 700 0.87 ;, E e Cs-134 1.OlP4 1.0 i "c 1 6 Cs-137 5942 1.0 f(mr/hr)= mr/hr (whole body) t Co-60 406 1.0 I-131 1591 - 0.87 i I 3 Cs-134 2.64P4 1.0 a Cs-137 2.30P4 1.0 E(mr/hr) = mr/hr(liver)
@ I-131 5.23P5 0.87 mr/hr(thyroid) i Schuylkill River Release 111x ing g 4 (mr/hr) x Usage Factor x Duration (hrs) x Factor = Dose (mr) 3 0
. 1.0 0.0091 (whole body) b
[ > 1.0 0.0091- (liver) l.
# 1.0 0.0091- (thyroid) 1 l Initials Date r
~-_~~_u._,,__~
c < ,.-~--~- - ~~
~~ ---
~~ +]l c~ c ._ _ ,.,_r
.i l EP-310 nov.'2: i Page 3..of'R- -,.
,; ' VAW/f1PG/,mc
,?'
i l Appendix EP-318-5 Philadelphi'a Delmont' Hater Intal:e
, (uCl) (mr/hr)
Isotope Concentration (cc ) xdone factor (uCi/cc) xdecay - factor =mr/hr Co-60 959 1.0 , I I-131 700 0.80 - e i e Cs-134 1.0lP4 1.0 g 0 I
; 5 Cs-137 5942 1.0 .
l' 1(mr/hr) = mr/hr (whole body) - -
. , 's ! Co-60 406 1.0 !
I-131 1591 0.80 e 3 Cs-134 2.64P4 1.0 s Cs-137 2.30P4 1.0 3o E(mr/h r ) = mr/hr (1Iver) ' A H I-131 5.23P5 0.80 mr/hr ( thyroi d) -
. Schuyll:lli River Release , !!!x ing m 1 (mr/hr) x Usage Factor x Duration (hrs) x Pactor = Dose (mr)
- s '
2 g 1.0 0.0112- (whole body) A i
. 1.0 0.0112 (livor)~ t-x 4 N 1.0 0.0112 (thyroid) l 1
l Initials Date
.t f
1 _ _ _ _ . _ _ _ _ _ __-_ ____.}}