ML20209J144

Public Version of Emergency Plan Implementing Procedures, Including Rev 4 to EP-106, Written Summary Notification & Rev 3 to EP-120, Site Emergency Coordinator. Related Correspondence

ML20209J144
Person / Time
Site:	Limerick
Issue date:	04/01/1985
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20209J141	List: ML20209J136 ML20209J144
References
OL, PROC-850401, NUDOCS 8511110368
Download: ML20209J144 (137)

Text

{{#Wiki_filter:, Paga 1 of 5 Revision 35 04/01/85 3850072850 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY 90PER. 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 Response 03/28/85 EP-105 9 General Emergency Response 03/28/85 EP-106 4 Written Summary l Notification 04/01/85 EP-110 6 Personnel Assembly and Accountability 03/14/85 i EP-120 3 Site Emergency Coordinator 04/01/85 EP-201 4 Technical Support Center 4 (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 4 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 i l 8511110368 850430 PDR ADOCK 05000352 F pm L

A: Pcga 3 of 5 R2 vision 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 FP-250 2 Personnel Safety Team 12/12/84 EP-251 2 Plant Survey Group 12/12/84 4 EP-252 5 Search and Rescue /First Aid Group 04/01/85 04/01/85 t 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 Supervision Call List 02/11/85 EP-275 CANCELLED EP-276 5 Fire and Damage Team Phone List 01/24/85 EP-277 6 Personnel Safety Team Phone List 02/11/85 EP-278 5 Security Team Phone List 03/25/85 EP-279 4 Emergency Operations Facility (EOF) Group Phone List 01/22/85 EP-280 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 l l

Pcg: 4 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-291 5 Staffing Augmentation 02/25/85 EP-292 7 Chemistry Samplino and Analysia ream Phone List 03/14/85 EP-294 5 Dose Assessment Team Phone List 02/04/85 EP-301 1 Operating the Evacuation Alarm and River Warning System 12/12/84 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 Padioactive Liquid Release 02/25/85 EP-313 2 Distribution of Thyroid Blocking Tablets 12/12/84 EP-314 1 Emergency Radiation Exposure Guidelines and Controls 03/29/85 EP-315 5 Calculation of Offsite Doses During a (Potential) Radiological Emergency 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 l Drinking Water 04/01/85 04/01/85

Pcg2 2 of 5 Rsvicion 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-233 5 Retrieving and Changing Sample Filters and Cartridgec frca 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 i Handling of Highly Radioactive Particulate Filters and Iodine Cartridges 03/28/85 EP-243 5 Sample Preparation and Handling of Highly c Radioactive Gas Samples 12/12/84 EP-244 3 Offsite Analysis of High Activity Samples 03/12/85 ( L__

Paga 5 of 5 Ravision 35 04/01/85 e LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER R20. TITLE BY SUPER. PERIODIC REVIEW EP-319 2 Fish Ingestion Pathway Dose Calculation _03/29/85 03/29/85 Er-325 3 Use or Containment i Dose Rates to Estimate Release Source Term-02/27/85 i EP-330 4 Emergency Response

l Facility Habitability 03/14/85 l

EP-401 2 Entry for Emergency j 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 i i 1 I i I i t i i i i

l EP-106, Rev. 4 Pace 1 of 6 3850072860 V^*'gir95 e /g/s) ( PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE ? EP-106 WRITTEN

SUMMARY

NOTIFICATION L b V 1.0 PARTICIPANTS P 1.1 Emergency Director shall direct the Shift Technical Advisor or other assigned Engineer to write a sucmary report following the closecut of an unusual event or the closecut or de-escalation of an Alert, Site Emergency or General Emergency. 1.2 Shift Technical Advisor or assigned engineer shall write a summary report. Y 2.0 ACTIONS - IMMEDIATE 2.1 Emergency Director shall: 2.1.1 Direct the Shift Technical Advisor or assigned engineer to prepare the written sucmary in I accordance with this procedure. k COMPLETE WITHIN 8 HOURS OF CLOSEOUT OR DE-ESCALATION p' OF AN ALERT, SITE EMERGENCY OR GENERAL EMERGENCY; st. s W COMPLETE WITHIN 24 HOURS OF CLOSEOUT OF AN UNUSUAL M l EVENT. 1 F 2.2 Shift Technical Advisor shall: i 2.2.1 Obtain the necessary information to complete Appendix EP-106-1 Emergency Class Closecut/ Reduction Report. 2.2.2 Fill,in the following informatien o ' @ f r..- W \\ 9 a. Item 1 - Enter the num crel th' p be ge N.vkn,r'oUsh .4t units. If th IQ p g,,N $',Y f' bet p nhts,, t a I Q f. r s', p s. [* V,* G '< ' ** 4 V ,cr i W UIkem!)">., Enter:t e d. ke e. r.j b.'.. ge L. me ~ 86ed ju f LJi "d M Jp q @,- J LGS UNI 1 Sh0$ Q 1 nW ' tGS U m 2 0500 9 ) 0

a s l EP-106, Rev. 4 Page 2 of 6, VAU/JLP/rgs ~ c. Item 3 - Enter the total number of pagen. d. Item 4 - Enter a concise description of the event. r e. Item 5 - Enter the date of the event. B f f. Item 7 - Enter the date of the report. I 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.

1. - Power Operation

2. - Startup

3. - Hot Shutdown i

4. - Cold Shutdown t

5. - Refueling

( i. Item 10- Enter the percent of licensed thermal power at which the reactor was operating when the event [' occurred. p. j. Item 12 - Enter the name of the Shif t I Superintendent. i L h. Item *17 - Enter a brief description of the circumstances and reasons ~ behind the closecut of the Unusual Event or the closaout or de-escalation of the Alert, Site Emergency or Gene:al Emergency. i F 2.2.3 Submit the report to the Energency Director. y! : ,'tw 3.0 ACTIOMS - FOLLOUUP 3.1 Emergency Director chall: 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. M

l, r:P-106, Rev. 4 t' Page 3 of 6 ,y VAW/JLP/rgs-J l 'Q-3.1.3 Have the report telecopied within eight of twenty-l four hours as appropriate to the NRC Operations Center or Region I office via the following phone 4 number l l V eg ~ 3.1.4 Call and verify that the report was received: isammuum ammajr 3.1.5 If the Y port cannot be telecopied, hav e report i hand delivered within eight hours to ther Region I Office f 631 Park Ave. - Q King of Prussia, PA 19406 l 3.1.6 Forward a copy of the report to NRMS. 4.0 APPENDICES L 4.1 EP-106-1 Emergency Class Closecut 1 n Report 5.0 SUPPORTING INFORMATION ( 5.1 Purpose The purp to dure is to provide guide ght hour written summary notif NRC following closecut or de, escal lert, Site Emergency or General Emergen' C s ification and for the twenty-four hour wr en summary notification to the NRC followin closecut of an Unusual Event. I V ,,..--,,-.+-,+~,e-.--.-.,. -. -.-....-e-. ..-,-.-..w. m--

F l EP-106, Rev. 4 Page 4 of 6 VAW/JLP/rgs 4 5.2 Criteria for Use This procedure shall be implemented following a l closecut of an Unusual Event or the closeout or de-escalation of an Alert, Site Emergency or General I Emergency Classification per EP-101 Classification of Emergencies. 5.3 Special Ecuipment p None 5.4 References 5.4.1 NUREG 0654, Criteria for Preparation and Evaluation Rev. 1 of Radiological Emergency Response Plans y and Preparedness in Support of Nuclear y Power Plants p A E-5.4.2 EP-101 Classification of Emergency tr r 1, 4*

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l l EP-106, Rov. 4 Pago 5 of 6 f VAW/JLP/rgs 1 Ql I, S f$lE (IT / DE-ESCALATION REPORT PACE 1 0F 2 i g l g FACILITV NAPE (1) 00ctIT munste (2) Past 3 } LIMERICK CENERATINC gTATION DNIT Og5gogogog g ; 1 y l TITLE (4) tyt*1 anti (5) stPorT DATt (F) cTER FACILifft3 INYCLVD (8) so ca va no na vs FACILlir aA 45 00csti murett (1) H I f f I f I e i-I f l l l l t i i 1 t 4 OPERATING THIS EPorT 15 SutrTTTED PUtsuAKT TO TE Rf0UIRDifMT F 10 Cff it ar = e as== ea ie=s (11) s a MW 20.402(b) 20.405 (c) 50.73 (a)(2)(tv) 73.71 (5) ( 20.405(a)(1)lt) 50.38(t)(1) 50.73 (a)(2)(v) 73.71 (c) r_\\' 20.405(s)(1)[tt) 50.N(s)(2) 50.73 (a)(1)(vit)

3. CTER (seectfr tr.

20.405(a)(1)(tti) 50.nla)(2)(1) 50.n (s)(2)(du)(A)

1. 11** *"8.1".. Test) 20.405(e)(1)(tv) 50.73(a)(2)(11) 50.73, (a)(2)(WE )(B)

~' P0.aragnyft)(,) y 93f.gr,)t4,qg am 9 rage,gt.) LICEaSEE C05 TACT 60R 1HI5 LI N lt) RAME TEttPMOME RJISfR sIIrr st'PTAINTElfDENT 2,1, 5 3,2,7,1,2,0, p, v r-g SUPPLEMENTAL RIP 0af EIPECTED (14) 8C DA YR (If yes. templete 11PECTG gg SUtM1551tu f l ftS $USM11110m DATE) E E0 DATE (15) g I t A351RACT (Liett to 1400 spaces.1.e., appresteately fifteen stagle-space typewritten itses) (16) Thie report is to edtiefy the 8 hour writtee ouemery requirement for a elooeout of as Alert, lite Emergency or Ceneral Emergency. La eqpirtaaet f*lbefy *Jasse6taccordance with EUEEC-0654 Appendis land 4As. 241eer v.tts. soy of ea themsel sweaf. Item 17 of this report le a brief description of the clomeout of the event. If applicable, a IAR will follow ta the required time frees. E r A

o l EP-106, Rev. 4 Page 6 of 6 VAW/JLP/rgs 1 I rict er a f 3gssetscouriOt-tsextxticsatraar 7 bietwstrtrINTarPct?(t_r TEXT CONTINUATION 0.- FCILITT wt (1) cxtri haeta gr) pa:t g3) V F 0,5,0 c,0i ; e or i TEIT +- y L [ t ,~ O 4 9 b ti N.1\\ ( w ~ VMINCATIOM O P-NRc" REC 63PT OF SE.PCRT VMINED W NTL

^ I EP-120 Rev. 3 3P50072870 "^S* 4 VAW/MJM/mc t b# PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE F r L EP-120 SITE EMERGENCY COORDINATOR r 6 c 1.0 PARTICIPANTS 1.1 Site Emergency Coordinator shall supervise the activation and manace the activities of the Emergency Operations Facility. L E 2.0 ACTIONS-IMMEDIATE 2.1 Site Emercency Coordinator shall direct the Load Dispatcher to activate the Site Emergency g Coordinator's call list. L. 2.2 Site Emergency Coordinator for Site and General emergencies shall: 2.2.1 Proceed to the Emergency Operations Facility. p-b 2.2.2 Become cognizant of the situation directly from the gg Emergency Director. f') 2.2.3 Announce go[EDFI'petsonnel $ hat 7 e is assuming the h r Emergency (pl(fc}qr:pey Coordingtor[and inferm the role of Site > Emerge g[ that,he'.i) asduring control of { the emergency resp 6nse'organitat6oh. 2.2.4 Supervise the ac d {theEOF. n i ( t: - jC q 2.3 Site Emergency Coordinator'shall as appropriate request the-pollectiqn pt,' envircnmental station 2 samples p sEPaC4All.,! it;Qj.e(e Q been a ~ radioactive material release. - [, 2.4 Through the Dose Assessment Team Leader, direct all radiation surveys conducted in off-site areas. L-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.

.~ j EP-120 Rev. 3 Page 2 of 4 VAW/MJM/mc k 2.5 Request activation of corporate support functions through dialogue with the Emergency Support Officer. I 2.6 Obtain protective action recommendations from the l Dose Assessment Team Leader. I 2.6.1 Discuss recommendations with the Emergency Director ( [ and Emergency Support. Officer to assure that all parties are informed of the recommendations before they are made to government authorities. 2.6.2 Meet with the Commonwealth of Pennsylvania representatives in the Emergency Operations Facility to ensure that questions on protective actions to be applied are answered prior to formal recommendation. k'. ' 2.6.3 Provide protective action recommendations to Pennsylvania Bureau of Radiation Protection. -N 2.6.4 Update these recommendations as new data become L. available or conditions change. 2.7 Upon completion of EP-318, Liquid Release Dose l Calculations for Drinking Water, implement EP-287, l if necessary. US 3.0 ACTIONS - FOLLOW-UP ~ i 3.1 Site Emercency Coordinator is responsible for the following: L. 3.1.1 Maintaining awareness of plant status and being alert to potential off-site consequences of the e-emergency, i' 3.1.2 Conducting periodic briefings for Emergency q 1 Operations Facility personnel. l 'r ( 3.1.3 Coordinating between the on-site emergency personnel and the off-site emergency personnel, L when activated, to obtain necessary additional facilities, equipment, supplies, personnel, or 5. technical services. 3.1.4 Coordinating with the Emergency Support Officer concerning personnel, equipment, and materials expected to arrive at the plant site.

l EP-320 Rev. 3 Page 3 of 4 VAh'/MJM/mc [* n 3.1.5 Ensuring preparations are made for check-in of incoming personnel, especially with regard to site area access control, indoctrination of visitino personnel, maintenance of proper security, issuing dosimeters and preparing exposure records, and distribution of protective clothing and equipment. V 3.1.6 Providing management direction for the g establishment and functioning of the Emergency p Support Center. v1 (.. 3.1.7 Continuing to supervise the operation of the y Emergency Operations Facility. 3.1.8 Reviewing with the Emergency Director the current status of information provided to governmental i, agencies and relieving the Emergency Director of this responsibility. The Site Emergency Coordinator will then serve as the primary contact for Federal, State, and local emergency response i I,'. agencies which dispatch personnel to the plant vicinity, and will provide status and assessment 4[ information to governmental agencies. 3.1.9 Provide direction for Philadelphia Electric L*' '~ i emergency response personnel who are dispatched to the plant site and for support personnel activated by Philadelphia Electric Company. 3.1.10 Keeping the Emergency Support Officer and the Emergency Director apprised of actions taken and of consequences off-site. f~ i YI ' l 3.1.11 Coordinating with the Emergency Director and the %,d 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. 4.0 APPENDICES None L hh e 1 ~.!! ^ '

1 ~* l l EP-120 Rev. 3 l Pace 4 of 4 VEW/MJM/mc ( 5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to provide guidelines to delineate the responsibilities and actions of the Site Emergency Coordinator. 5.2 Criteria For Use L The position of Site Emergency Coordinator is normally activated at a Site or General Emergency or at the discretion of the Emergency Director. l 5.3 Special Ecuipment f None 5.4 References .J 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 2 k-l 5".4.6 EP-C-315 Recovery of Emergency Radiological l Environmental Monitoring Samples from Peach Bottom y l Units 2 and 3 and Limerick Units 1 and 2 7 Ip kl PT * .v f; i e '~

EP-203, Rev. 5 Page 1 of 20 3850072880 vow /3LP/$mv ,?q V PHILADELPHIA ELECTRIC COMPANY //jbl LIMER3CK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE 1 EP-203 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION 1.0 PARTICIPANTS 1.1 First person 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 Emergency Coordinator shall direct operation r at the EOF. 1.4 Status Board Recorders shall obtain and post information. 2.0 ACTIONS-IMMEDIATE PERSONNEL ARE DESIGNATED AND ASSIGNED GENERAL DUTIES IN THE EOF BY EP-279, EOF GROUP PHONE LIST. y 2.1 First person arriving ~shall: N / 2.1.1 Obtain keys, if necessary, Jog-EOFbfrom pher i ru r. H Plymouth Dispatch office andiopen EOF,,<. ,ei c t' L [ '..:r! d I. !.? ( l 2.1.2 Perform appendices EP-203-9 and'EP-203-10.3 u M C .ty 2.1.3 Assign the first available person &~.the entrance of the EOF to control access until' security \\ arrives and to establish a log for the pur ses sf n e* j], personnel accountability. q, q,3 pe r-if er ENSURE THAT PERSONNEL SIGN b' 0 l INDIVIDUALS ON ACCESS LIST QB,CLE RE0iBjs.PER,SONN5L (. *, l-PRESENT ARE ALLOWED TO ER. IOF.h ACCESS LIS3; O Q. h, '. s \\ *\\i:p. UL l.

1

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• l EP-203, Rev. 5 Page 2 of 20 VAW/JLP/jmv 2.1.4 Assign an individual (as soon as one is available),

che duties of the Site Emergency Coordinator Communicator. The Communicator shall perform the steps outlined in Section 2.2. 2.2 Communicator for the Site Emergency Coordinator r shall: 2.2.1 Use EP-279, Emergency Operations Facility Group 7 Phone List to call in additional personnel to staff (J the EOF, if necessary. L b 2.2.2 Inform the Site Emergency 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 containing information ^ received from and sent to other facilities and i other organizations. ENSURE ALL PERTINENT ACTIONS AND NOTIFICATIONS.ARE n LOGGED. 2.3 Security personnel shall: 1 2.3.1 Post themselves at the front of the EOF. F-l 2.3.2 Control access to the EOF by allowing personnel who l exhibit badges listed below access. u hE~ l Philadelphia Electric Identification Cards / D',- Bechtel Construction Site Badge kJ Bureau of Radiation Protection Identification Cards b Pennsylvania Emergency Management Agency Cards i Nuclear Regulatory Commission Identification Cards 1 Federal Emergency Management Agency Identification I. Cards l Y ~ l City of Philadelphia L l l l All other personnel recuesting access snould be l cleared through the Site Emergency Coordinator, l Emergency Preparedness Coordinator, or the Planni.ig I and Scheduling Coordinator.

l EP-203, Rev. 5 Page 3 cf 20 VAW/JLP/jmv 3.0 ACTIONS FOLLOW-UP SITE EMERGENCY COORDINATOR SEALL ASSUME CONTROL AFTER HE HAS ARRIVED AND IS COGNIZANT OF THE SITUATION. 3.1 Site Emercency Coordinator shall: Y 3.1.1 Assign personnel to be status board keepers and direct them to perform the steps outlined in ?. section 3.3 of this procedure. L* b i a. LGS Plant Parameter Status Board F b. Plant Parameter Trends Board c. Event Chronology Status Board h d. Staff Assignment Status Board Headquarters Support Request Status Board l e. W f. Offsite Communications Status Board Y l g. Dose Assessment Status Board I h. Field Survey Group Status Board 3.1.2 Ensure that an individual has b'een assigned as the Site Emergency Coordinator's Communicator. F 3.1.3 Inform the Technical Support Center when the / Emergency Operations Facility is operational, i manned and in control of its designated responsibilities. [ ~ 3.1.4 Brief the EOF Staff periodically on the status of the emergency and pertinent plant conditions. 3.1.5 Direct transmission of all Status Board information to appropriate Headquarters Emergency Support Center Status Board Recorders. ,r C 3.1.6 Perform actions in EP-120, Site Emergency (( Coordinator. kb 3.2 Dose Assessment Team Leader shall: d b 3.2.1 Complete the Dose Assessment Team Activation in l accordance with EP-210, Dose Assessment Team. ~

l EP-203, Revo 5 Page 4 of 20 VAW/JLP/jmv 3.3 Status Board Recorders shall: 3.3.1 Fill in their assigned status board (s). t Format and content of the Status Boards are given in the following appendices: [ a. Appendix EP-203-1, LGS Plant Parameter Status Board E b. Appendix EP-203-2, Plant Parameter Trends Status Board c. Appendix EP-203-3, Event Chronology Status Board d. Appendix EP-203-4, Staff Assignment Status Board e. Appendix EP-203-5, Headquarters Support Requests Status Board y f. Appendix EP-203-6, Offsite Communications Status Board l g. Appendix EP-203-7, Dose Assessment Status Board I h. Appendix EP-203-8, Field Survey Group Status l Board e 3.3.2 Contact the following individuals for the various Status information, gn t a. TSC Plant Parameter Status Board Recorder for {/. Plant Status information. 'j b. TSC Event Chronology Status Board Recorder for Event Chronology information. c. Site Emergency Coordinator's Communicator for Staff Assignment Information and Headquarters Support Requests. d. Emergency Director's Communicator Site Emergency Coordinator's Communicator or Control Room Communicator for offsite communication g information. V e. Field Survey Group Leader for field survey data. O

r e 9 :'. + *a s, l l EP-203, Rev. 5 j Page 5 of 20 l VAW/JLP/jmv l l l ~ l f. Dose Assessment Team Leader for radiological I data. 3.3.3 Post appropriate information on assigned status board and maintain a log of all status board entries. . =? ,t 3.3.4 Review and update the status boards as changes in 1 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. 4.0 APPENDICES 4.1 EP-203-1 LGS Plant Parameter Status Board 4.2 EP-203-2 Plant Parameter Trends Board k-4.3 EP-203-3 Event Chronology Status Board 4.4 EP-203-4 Staff Assignment Status Board ~ t:7 l 4.5 EP-203-5 Headquarters Support Request Status Board l-f 4.6 EP-203-6 Offsita Communication,s Status Board _a y l 4.7 EP-203-7 Dose Assessment Status Board l 4.8 EP-203-8 Field Survey Group Status Board g 4.9 EP-203-9 EOF Equipment Activation 1 4.10 EP-203-10 EOF Phone Check-List I 'i3 5.0 SUPPORTING INFORMATION g 5.1 Purcose ~ The purpose of this procedure is to provide i guidelines for the activation, manning, and conduct of operations of the Emergency Operations Facility (EOF). t

l EP-203, Rev. 5 Page 6 of 20 VAW/JLP/jmv 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 Emergencies, or at the discretion of the Emergency Director. p 5.3 Special Ecuipment I F None. L' 5.4 References t 5.4.1 Limerick Generating Station Emergency Plan 5.4.2 NUREG 0654 - Criteria for Preparation and f Rev. 1 Evaluation of Radiological en ~ Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. E ~- b p 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 r-l 5.4.6 EP-120 - Site Emergency Coordinator .;p !~ '/: W 'fr g t ~ g. C 4-c $.5 L i e

7-l EP-203, Rev. 5 Page 7 of 20 VAW/JLP/jmv l APPENDIX EP-203-1 LGS PLANT PARAMETER STATUS - UNIT .g7,,,, REACTOR PARAMETER TIME CORE PLATE D P-pelg f POWER s LEVEL lachee ?:. PRESSURE nest PRESSURE CONTROL 7 U RE ACTIVITY CONTROL L 4 L e CF Roos NOT INSERTED PAST OS [ SSLC 'INJ AVAll U N AVAll REASON S R V'S A S C D E F G 'N J K L M N g A OPEN 5 CLOSED [ C WAS I SSLC TANK LEVE4 OPEN ggL, LEVEL CONTROL SYSTEM INJ AV All UN AV AIL SIEASON gygygg FW A ON OFF RECIRC A CRD A ESW A g MPCI 8 C RCIC COND A O 3 i COMMENTS pc C CS A j D [ LPCI A E ? f ",6 8 RNRSW A 8 i. C i O COND TR ANS REFUE6 TRANS SSLC FmE WATER em e.. e eneeee

l EP-203, Rev. 5 Page 8 of 20 VAW/JLP/jmv l APPENDIX EP-203-1 (CONT'D) SHT S el S CONTAINWENT PARAMETER C OMJA ENTS SUPPRESSION POOL TEMP 'F 'I DRVWELL TEMP DRYWELL PRESSURE nel8 SUPPRESSION POOL LEVEL ta C O NT AINM E NT EO %H2 g dONTAINWENT CONTROL l swF swP pfy O L UNAVAIL REASON l NN [p,Oav SPRAY C OL A I I e C q. b RHRSW ON AVAIL UNAVAgL REASON s. 4 A S 'C n 0 IS OL ATIONS ISQLATED EXCEPilONS I M Siv fl RHR V ^ Ill RWCU H' In NP CI k V R CIC va oc PsAGL & SaW8LE VII P CIO vist $[rggl[e SGTS ON A V AIL UN AV A8L REASON FAN A -{ p. ~ 64 TR AIN A r,-I S 4 CONTAINMENT MS RECOMOINERS r ON A V AIL UN AV AIL REASON A 0 g. p, d w w y -M .e 9 9g4 O 9 *.

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EP-203, Rev. 5 Pace 9 Of 20 VEW/JLP/jmv t l APPENDIX EP-203-1 (CONT'D) R ADIOLOGICAL PAR AMETERS TIME COMMENTS NORTH STACK U Cl/c c U Cl/s e c SOUTH STACK U Cl/c c D/W R AD MONITOR R/hr REFUEL FLOOR EXM mt/ht AIR EJECTOR OFFS AS er/hr R/X ENCL EXM mt/hr R ADW ASTE EXH CPM SAMPLES E MORTH STACK FLOW sfm h GRSS/S SODINE/ GASEOUS SOUTH STACK FLOW _ofe U Cl/ c c UC4/ce U Cl/e s TIME REACTOR WATER METEOROLOGICAL PAR AMETERS [ SUPPRESS TIME WATER w. AVER AGE WIND DIRECTION (from) AVER AGE AMBIENT TEMP 'F P R E CIPIT ATIO N I STASILITY CLASS NORTH STACK AVER AGE WIND SPEED mph OROUND AVER AGE WIND SPEED aph SOUTH ELEVATED STACK POWER SUPPLIES f L SUPPLYtNG AVAfL 'UN A V AIL 9FASON 220kw CFFSITE SOURCE SCohn OFFSf7E SOURCE h i

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Y'C 101 SFGD S01 SFSD SUS SUS Sus DIE S E L AVAIL UN AV All REASON l f-D- -i

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~. - _ - - - . + -*.-., c. u. _.- . ~. I EP-203, Rev. 5 Page 12 of 20 VAW/JLP/jmv ~ APPENDIX EP-203-4 seas STAFF ASSIGNMENT STATUS BOARD 9 TITLE NAME LOCATION BADGENO l g 3 r I SHIFT SUPERINTENDENT t SHIFT SUPERVISOR EMERGENOY DIRECTOR L SITE EMERGENOY COORDINMOR / EALTH PHYSICS / CHEMISTRY COORDINATOR i [. L-FIELD SURVEY GROUP PECO SECURITY I -- EMERGENOY PREFEREDESS COORDINATOR CORC. COMMUNICATION LIAISON K I w. 8 p l> l PROCEDURE SUPPORT COORDINCOR c (;$'- PLANNING & SCHEDULING COORDINATOR f k MECHANIC AL ENGINEERING LIAISON g_ ELECTRIC AL ENGINEER LIAISON EMERGENCY SUPPORT OFFICER I -p== ,3i'C*"." ...,f***-*

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wi .~ EP-203, Rev. 5 l Page 15 of 20 a VAW/JLP/jmv APPEtIDIX EP-203-7 REv. e arries 1 DOSE ASSESSMENT STATUS BOARD il i DATE! BO ARD UPD ATE TIME AM PM COMMENTS: RELEASE O C CURING AN TICIP AT E D WHEN AM PM -l LOC ATION OF RELE ASE: NORTH STACK US SOUTH ST ACK OTHER sg U2 SOUTH STACK ESTIM ATED DUR ATION ON RELE ASE HRS. YlME OF SCR AM: RELE ASE MONITORED VES NO SOTS EFFICENCY NORTH VENT U S SOUTH VENT U2 SOUTH VENT DE S C RIS E NOSLE GAS UCitCC UCitSEC UCitCC UCitCC k IO DINE UCllCC UCitCC UCitCC ,f FLOW R ATE CFM CFM CFM l ) WIND SPEED MPH DIRECTION (FROM) ST ABILITY CL ASS AFFECTED SECTOR (S) i INT E ROR ATE D DOSE TIME TO l CENT E RLlef t PLUME (SASEO 8 CALCUL ATED DOSE R ATE FIELO DOSE R ATE R SO N RE ACH PAO 4 OOSE ARRIV AL PROJECTMN TIME W.B. THY. W.B. THY. W 9. THY. W.B. THY. SITE SOUND AR5 4 5 2.8 MIL E S l ... Mit E S 10.0 MIL E S PEAK RECOMMENDED PROTECTeVE ACTION l 1 1

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l EP-203, Rev. 5 Page 17.of 20 VAW/JLP/jmv APPENDIX EP-203-9 EOF EQUIP.V.ENT ACTIVATION

1..

Turn on Lights in EOF using switch (es) to the left of the door. 2. Turn on CRT's using posted procedures. W.< 3. Check radio base station for operability. t.>: 4. Inform Site Emergency Coordinator or Site Emergency Coordinator Communicator when activation is complete, and of any problems discovered. r 1 I k: e C N-F W F r e. nt*f* f-p e ~ i ~ l l l I

EP-203, Rev. 5 l' Pace 18 of 20 VAW/JLP/jmv i APPEND:X EP-203-10 EOF PHONE CEECKOFF LIST / D (Green) SRP - Rad White) BRP - Tech. pyy,A ? i Dose Assessment l Q (Yellow) Dose Asses./Fld. Survey g Dose Assessment Table l [W-'e-a Dose Assessment Table i HP & Chem. Table f, D HP&C HP & Chem. Table i HP & Chem. Coordinator r ~ l " NL HP & Chem. Coordinator ERFDS/ Operator F l RMMS Modem Field Survey M Yellow) Field Survey 1 6 ) 6 NRC Table p - -- - - - --E N . ts. 6 O NRC Table 5- - - N3C Table (? W NRC Table {, [ =_ 3 M 's.Y' NRC Table s ei p, w*E[ \\'c w NRC Ta . \\, M NRC T bl le N.. O NRC T --o------- /

.. + ; a, l' EP-203, Rev. 5 l Page 19 of 20 VAS/JLP/jmv l I l l l APPENDIX EP-203-10 (CONT'D) EOF PHONE CHECF.0FF LIST NRC Table NRC Desk NRC Table NRC Table NRC Table SEC Communicator's Desk @ & TSC/ EOF (Orange) SEC Communicator's Desk l M MSC/ EOF (Ivory) Sec's Desk [ Management (Grey) Sec's Desk l [ Corp. Spokesman SEC Communicator's Desk 1 f Emergency Preparedness EOF Corp. Comm. Liaison EOF Corp. Comm. Liaison ,p-------- t%- g Security a,---------- 17 4. p lj Security g *, s~... M EOF Engineering Liaison N, ' c ' i I g;;A EOF Engineering Liaiso 2,,, i---------- (. t Procedures Support g. . /-,,,.,f, i Planning & Senedulinc ~Coord'.'# \\ ..,,~..:-4 i .. -A Berks Cty. m

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l. EP-203, Rev. 5 Page 20 of 20 VAS/JLP/jmv 1

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l APPENDIX EP-203-10 (CONT'D) EOF PHONE CHECKOFF LIST ' TSC/ EOF (Ivory-Spk) Sec. Office N [ D CR & TSC/ EOF (Orange) Sec. Office (' Management (Grey) Sec. Office e l ,(Brown) Sec. Office j NRC Office N NRC Office NRC Office 2m Rem-w' t .m 1 t/276 NRC Office ) ^"7 NRC Office b a 7 l N/A NRC Regional Operations Ctr NRC Office U. I p Conference Room

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l EP-252, R:v. 5 3850072890 ['J Urs i. u

1. M, PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN !MPLEMENTING PROCEDURE I

EP-252 SEARCH AND RESCUE /FIRST AID GROUP w F;' l.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 Group Leader shall direct eperations of tne group. 1.3 Search and Rescue /First Aid Group members shall p 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 Leader shall: toifl 2.1.1 Contact the Operations Support Center Coordinator at the Operations Support Center (OSC) and direct k him to form Search and Rescue /First Aid Grcup(s). r-2.1.2 Inform the Emergency Director that Seargh and Pescue/First Aid Group (s),,have been. ripj ich and and of their intentigns t n'ter. the plan *'f II 's e 4 I) ) -escuf. operations... 1R k 1.i '.;, '. ', i; ?. ) (5 D v* -uArTExP.T,TO.. LOCATES [;ssfNe.<EEN JU'ST,PR;dA ,a1 it i rItIzING [, [g'.7 PLANT' PAGING SD(Sepcy1NoTH EAR (a Ja:D RE,SquE(GgbUP(S). L g g 0 q y :. > $ .a

r l EP-252, Rev. 5 Page 2 of 12 l. VAW/JLP//rgs l 2.1.3 Obtain emergency exposure limits from the Emergency l Director if appropriate. If later search and rescue operations are necessary, the Emergency Director may adjust the radiation exposure limits l accordingly. CAUTION IF WAITING FOR EMERGENCY DIRECTOR APPROVAL COULD ENDANGER PERSONNEL, THE SEARCH AND RESCUE /FIRST AID GROUP LEADER MAY DECIDE TO H REMOVE INJURED PERSON. I i l CAUTION g l PLANNED RADIATION EXPOSURES SHOULD BE LIMITED l TO THE ADMINISTRATIVE GUIDE LEVELS IN APPENDIX l l l EP-252-1, EMERGENCY EXPOSURE GUIDELINES. l 2.1.4 If offsite mediEal help is necessary, have the ~ l ambulance, hospital or physician contacted by the l Emergency Director or designee using Appendix EP-f 252-4, Medical Support Groups Phone List. Always state the number of individuals involved, type of I I injury and if contamination is involved. F 2.1.4.1 Contact Pottstown Memorial Medical Center and Goodwill ambulance as first choice. ye 2.1.4.2 If Goodwill is not available contact Trappe LA ambulance. W 2.1.4.3 If evacuation of the EPZ has been declared, contact R.VC to arrange for a helicopter and use of Hospital of University of Pennsylvania. } 2.1.4.4 If medical support is required on site;- dontact one of the local pnysicians. 2.1.5 Notify security so that the offsite medical response group's access to the Restricted Area can be expedited, if necessary. L-c 2.1.6 Recall the Search and Rescue /First Aid Group (s) when search and rescue operations are no longer l necessary. t I l l s 4....

l EP-252, Rev. 5 Page 3 of 12 l-VAW/JLP//rgs 2.2 OSC Coordinator shall: 2.2.1 Select volunteers from available personnel to form Search and Rescue /First Aid Group (s). EACH GROUP SHALL CONSIST OF AT LEAST THREE MEMBERS; I 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. k-2.3 The Search and Rescure/First Aid Grouc Leader p shall: e 2.3.1 Ensure that each member has the necessary respiratory equipment, radsurvey equipment, anti-g contamination clothing, and personnel dosimetry if time permits. This material _can be obtained from r. emergency surv.ey kits at the OSC or from normal HP stocks. 2.3.2 Discuss the situation with the Personnel Safety ._ Team Leader. The following information should be obtained prior to performing search and rescue L operations: A. Number of missing persons. B. Name of individuals. b C. Last known location of individuals. Y:j; D. The job being worked. E. Any significant plant conditions that may affect the searen and any special instructions. I 2.3.3 Ensure the group is eqQipped with a first aid kit, I stretcher and blanket, or can get them enroute. I See attached Appendix EP-252-2 for listing of first aid equipment location in the plant. 2.3.4 Coordinate Search and Rescue /First Aid Groups to minimize duplication of effort and unnecessary radiation exposure. 2.3.5 Direct the groups to the last known location of the missing individual. If necessary, expand the search to adjacent areas. Ensure most expeditious routes available are taken to minimize team exposure. d -i

-l-EP-252, Rev. 5 Page 4 of 12 I, VAW/JLP//rgs t, 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 y administration of first aid. 2.3.8 Report to the Personnel Safety Team Leader the I extent of the individual's injuries and recommend supplementary medical actions as necessary (i.e., hospitalization). Complete Appendix EP-252-3 (if F possible) and attach to injured person prior to transporting in ambulance. L 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 Grcup Members shall: k f,i 2.4.1 Locate the missing person (s). F E - ~~~ 2.4.2 Administer first aid, if necessary. I" t 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. Er f') CAUTION RADIAfION EXPOSURE AND GROUP MEMBER CONTAMINA-l TION SHOULD BE MINIMIZED AS MUCH AS PRACTICAL.l l V 1 CAUTION i I r IF GROSS EXTERNAL CONTAMINATION IS FOUND, ! h INTERNAL'CONTAM; NATION SHOULD BE SUSPECTED. I 2.4.4~ . Transport the injured person to a site first aid y facility if practicable. ..:.......~. -7

l EP-252, Rev. 5 Page 5 of 12 l VAW/JLP//rgs 2.4.5 . Perform the following if the injured person is contaminated. A. Wear necessary anti-contamination clothing if practicable. r B. IF INJURY IS NOT SEVERE, DECONTAMINATION SHALL BE ATTEMPTED. I C. Prepare the person for transportation by covering the contaminated area with a protective wrap. Avoid excessive wrapping to b prevent dehydration of the person. IF THE INJURED PERSON IS GOING TO BE TRANSPORTED TO AN OFFSITE MEDICAL FACILITY, IT MAY NOT BE FEASIBLE TO BRING THE PERSON TO THE FIRST AID FACILITY. INSTEAD, MOVE THE PERSON I TO A SAFE PLACE WHICH IS EASILY ACCESSIBLE FOR D' THE TRANSFER TO A VEHICLE. ns D. When transporting the victim to an offsite h medical facility, a Health Physics Technician shall accompany the victim to assist the medical staff. E. A second HP technician shall also report to the hospital. F 2.4.6 Recover any contaminated articles of clothing that may have been removed from the person for isotopic analysis. k V 3.0 ACTIONS - FOLLOW-UP 3.1 Search and Rescue /First Aid Group members shall: 3.1.1 Report results of their actions to the Personnel Safety Team Leader. L 3.1.2 Follow normal decontamination and disposal procedures when their tasks are complete, j 4 h~ 3.2 Personnel Safety Team Leader shall: J 3.2.1 Verify the victim's arrival at the medical facilities. l o

I l EP-252, Rev. 5 Page 6 of 12 l-VAW/JLP//rgs 3.2.2 Inform the Emergency Director of results of search and rescue /first aid efforts. l 3.2.3 Direct the Emergency Director to inform the l Medical Director and Claims / Security as to the identity and condition of the victim (s). 3.2.4 Direct a Health Physics Technician to accompany the victim to the hospital and to call when informed by g 4 the hospital that his services are no longer P/ needed. Direct the technician to return dosimetry [ to site to be read and leave survey equipment at hospital. 3.2.5 Arrange for inventory and restocking of first aid kits, if necessary. 7 F 4.0 APPENDICES 4.1 EP-252-1 Emergency Exposure Guidelines b L. t 4.2 EP-252-2 First Aid Equipment Locations 4.3. EP-252-3 Injured Personnel Report Form 4.4 EP-252-4 Medical Support Group Phone List V. [] 5.0 SUPPORTING INFORMATION 5.1 Purpose LP' The purpose of this procedure is to define the requirements and the actions of the Search and +- Rescue /First Aid Group. y 5.2 Criteria for Use E This procedure shall be implemented whenever I personnel are known to be missing or are injured. h 5.3 Soecial Ecuipment L 5.3.1 First Aid Kit ( " Em

I-I l EP-252, Rev. 5 Page 7 of 12 l' VAW/JLP//rgs I s ~ 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. 4 9 e O W G I D HWI! no w_ 1 1 Ae

l EP-252-1, Rev. 5 Page 8 of 12 1-VAW/JLP/rgs APPENDIX EP-252-1 itERGENCY EXPOSURE GUIDELINES Projected Whole Body Thyroid Authorized Function Dose Dose Bv Y-[

1. Life Saving and Reduction of Injury 75 rem

• 375 rem Emergency **

Director

2. Operation of Equipment to Mitigate an Emergency 25 rem

• 125 rem Emergency **

Director

3. Protection of Health and Safety of the Public 5 rem 25 rem Emergency **

Director

Reference:

EPA-520/1-75-001 Table 2.1

• • Such exposure shall be on a voluntary basis W

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l 1 EP-252-2, Rev. 5 ) Page 9 of 12 l l VAW/JLP/rgs j l l APPENDIX EP-252-2 FIRST AID EQUIPMENT LOCATIONS First Aid 7 Kits Blankets Stretchers Unit 1 Reactor Enclosure h 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 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 ff 352' Change Area (701) X X X e,- M Unit 1 Turbine Enclosure 200' Near Room 261 X X 217' 325A Corridor-aux Equip & Piping (Area 7 Line 13) X X 302' Equip Exhaust Filter (621) l 239' Inside Battery Room 443 X t l 269' Outside Stairway 30 X L. l 269' Outside Room 545 X X X l 269' Inside OSC X l 269' Inside Control' Room X I 6

l EP-252-2, Rev. 5 Page 10 of 12 l VAW/JLP/rgs 4 ~ l APPENDIX EP-252-2 l FIRST AID EQUIPMENT LOCATIONS First Aid Kits Blankets Stretchers t l Control Enclosure l 200' Inside Stairway 7 X X' g ; 9 l 217' Outside Room 336 X l 217' Inside Battery Room 323 X X l 217' Stairwell #7 X X X l 217' Inside Battery Room 324 X N: l 239' Stairwell #7 X X X 14 l 239' Inside Battery Roon 425 X g l 239' Inside Battery Room 436 X ~ l 254' Stairwell #7 X X l 289' Stairwell #7 X X X ~~ l 304' Stairwell #7 X l 332' Stairwell #7 X X X r l 352' Stairwell #7 X l-Radwaste Enclosure [ 217' Conv. Chem Lab (411) X X l 217' Rad. Chem Lab (418) X l 217' Radwaste Contrc] Room (415) X X 9 X" l 217' Between Rooms 417 & 418 X k l 217' Southeast of' Room 415 X d I_ l 191' Outside Stairway #2 X l 162' Outside Stairway #2 X 1 ..e y

l EP-252-3, Rev. 5 Page 11 of 12 el VAW/JLP/rgs APPENDIX EP 252-3 INJURED PERSDNNEL REPORT FORM (PREPARE IN DUPLICATE) Injured Person's Name E Age Badce No. Or Social Security No. ?.-4 Male Female F I Type and Location of Injury r i ii E Radioactive Contamination Yes No Level l-i Location b Radiation Exposure Estimate Where Did Injury Occur p-t g*g. Prepared by First Aid Group Leader / SIGNATURE ya' 9bA Group Members I s If practicable forward original, with the person, to the site L, first aid facility or hospital as appropriate. 1 [ . g. < k. .....4

m s Page 12 of 12 VAW/JLP/rgs t APPENDIX EP-252-4 ,J MEDICAL SUPPORT GROUP PHONE LIST _T Local Physicians ( Office Home _._ m g.,. .. _ m. - +er _^ - m, Q.,.. _ g..x - ? I T Pottstown Memorial Medical Center (Contaminated or otherwise) 1 j ggpgr;..- a3 m _ zn m ; #, c, j .w s.. w c;.n. -. m,,. -_, R. - = :: : auq_e m_g.y 3 - ~ - _. w_ - _- 3., w a I Radiation Management Corocration (Serious Contamination /of Exposure

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• Serious Contamination / Exposure is:

Whole Body Exposure greater than 25 REM or skin exposure greater than 150 REM or extremity exposure greater than 375 ( u reaterREM or contamination causing ocdy contacted reading of than 1 MR/HR cr suspected or actual inhalation er ingestion of measurable quantities of radioactive material. .+ f f'w 7 e F,. \\< m em r. .t h y c/ M,.; % '>, h..,.,,lg '3 a ,1 .t o o. ~' [_;t .\\; )

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l EP-315, Rav. 5 3850072900 Pago 1 of 13 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERA"'ING STATION EMERGENCY PLAN IMPLEMENPING PROCEDURE EP-315 CALCULATION OF OFFSITE DOSES DURING A (POTENTIAL) RADIOLOGICAL EMERGENCY USING RMMS IN THE MANUAL MODE ) 1.0 PARTICIPANTS 1.1 The Shift Technical Advisor (STA) shall initiate dose calculations upon indication that an effluent monitor setpoint has been exceeded. l 1.2 The Shift Superintendent shall evaluate the dose l results, declare the appropriate EAL based on releases, and assist the Emergency Director in making l protective action recommendations if warranted. I 1.3 The Dose Assessment Team Leader (upon activation of tha TSC, and/or the EOF) shall direct dose calculations, evaluate the results, and assist the Emergency Director with EAL declarations and l protective action recommendations. l 1.4 The RM-ll Operator in the TSC shall provide radiation release data to the Dose Assessment Team Leader and the RM-21A Operator. b 1.5 The RM-21A Operator shall use this data and b meteorological information to generate offsite dose H estimates using the RMMS computer. 1.6 The calculator shall assist the RM-21A Operator with data entry problems and periodically update the Status Board Keeper. 2.0 ACTIONS IMMEDIATE r I 2.1 Control Room Operation \\ h 2.1.1 Upon receiving MTi ind kaf1 5.that an effluent release in etceps'of instantaneous Technical Specifications r?ay ha've oceprTed, an offsite dose calculhtion sgall'b'e Q V initiated by the STA t evduag,\\the ff) d'* 5 ~

a l EP-315, Rev. Page 2 of (li MAC/n release. He shall also request the l Chemistry Department to take an effluent aG l the point of release. } INDICATORS OF EXCEEDED SETPOINTS - RM-ll ALARMS, AN RM-ll tr CHANNEL BLINKS, CHEMISTRY ANALYSES. FOR INDICATIONS BASED @ g a k..;# CHEMISTRY ANALYSES, GO DIRECTLY TO STEP 2.1.8. g. I f" 2.1.2 The following channels on the RM-ll consolG provide an indication of a potential Technical Specification release if in a blinking red state and audibly alarming: North vent South vent y-CHNL 4 DESCRIPTION CHNL f DESCRIPTION r / f 4TE076 N STACK TOTAL EFFLUENT f 2IE075 N STACK VENT EFL IOD 2IE185 S STACK VENT EFL I i SIE075 N STACK VENT EFL IOD SIE185 S STACK VENT EFL Io 3GE075 N STACK VENT EFL GAS 3GE185 S STACK VENT EFL G = 6GE075 N STACK VENT EFL GAS 6GE185 SSTACKVENTEFLGb L. 4TE076 WILL BLINK IN YELLOW (' FOR AN IODINE ALARM, DO NOT DECLARE AN UNUSUAL EVENT UNTIL THE CHEMISTRY SAMPLE BECOMES AVAILABLE FOR EVALUATION. [ COMMON CHANNELS: (2IE075, SIE075) ; [ !) (3GE075, 6GE075) ; (2IE185, SIE18 5) ; (3GE185, 6GE185). i 2.1.3 When the RM-ll alarms or a specified channC l blinks in red, enter GRID I. I { 2.1.4 Access the channel (displayed by an alphanumeric code in an alarming / blinking state) by enterino the following: 'I L (Numeric portion of the code, SEL, 10 MIN TREND) q' i ' R* If a North Vent (NV) channel has alarmed, enter (407 (; as the numeric code. l 2.1.5 Note the value units ~in the ( A_ upper right hand corner of the RMMS'consold in the RMMS Log. This represents the concentration (uCi/cc) or release rate (uci/sec) at this channel. For simultaneo valid alarms on 2 common (same stack, same, type), channels, take the average of the 2 concentrations. p MW w.

-_2 n. . _. ~. _ - - - - - - - - - - ~ ~~- l EP-315, Rev. Page 3 of 2 MAC/n2 a 2.1.6 Note process flow N. (in the upper middle c the RM-ll console) in the RMMS Log. Process flow A is used only when offsite power has been lost or the fans to the majc f enclosures have been turned off. H UCI/SEC, OBTAINED FROM A NV CHANNEL, IN STEP 2.1.5, MUST BE CONVERTED TO UCI/CC: k $. l T. uCi/cc = uCi/see L (process flow) x (472) 2.1.7 mhe STA (RM-21A Operator) will logon to the RMMS-RM-21A system using the appropriate user name and password. 2.1.8 mhe RM-21A Operator will select the following options !?r: 2.1.8.1 56 - Emergency Dose Calculations, enter mfE 2.1.8.2 83 - Class A Dose Model, enter 2.1.8.3

1. 3 - All Manual Mode, enter THE OPERATOR SHALL GENERATE A HARD COPY OF ALL INFORMATION.
2. ~

2.1.9 Review the run control table. Edit the table to reflect the Appropriate release point (s). (COPY) if l Fj - Release point 1 = North vent 1( ! Release point 2 = South vent 1. Release point 4 = Hot Maintenance Shop Enter return to get back to "date of reactor trip". 4 2.1.10 Enter the following information: { ] 2.1.10.1 date of reactor trip - If the reactor has not tripped or scrammed, enter the start time of the release. 'I 2.1.10.2 time of release -Enter start time of relea t or the beginning of the period to be evaluated. This time must be equal to or s l later than the time of reactor trip. EAS*ERN SPANDARD TIME (EST) IS USED BY RMMS. EST IS EQUAL TO DAYLIGHT SAVINGS TIME MINUS 1 HOUR. 2.1.10.3 remaining duration of release - The operati must request that the Shift Supervisor provide him with an estimated duration of release. If the duration cannot be

l EP-315, Rav. P go 4 of 1 MAC/nig i estimated with confidence, enter 1 hour. (COPY) THE REMAINING DURATION OF RELEASE IS USED IN THE EAL TABLE WHICH PROVIDES TFE OPERATOR WITH INFORMATION REGARDING CLASSIFICATION OF AN EMERGENCY BASED ON RADIOLOGICAL RELEASES. IT IS ALSO USED IN THE PAG

SUMMARY

DISPLAY TO PROVIDE GUIDANCE ON WHEN PAGS MAY BE EXCEEDED. Ii 2.1.10.4 isotopic release data 1. f2 - isotopic percent fraction ] (sum = 100.0) 2. Select the desired isotopes based on the following criteria: l ALARMING MONITOR L 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 valuss. Values less than or equal to LLD preclude the need to perform dose assessment. [T l

• If the reactor has scrammed, enter the W.

isotopic abundance per Appendix EP-315-1, [} which is.also located in the EP-315 guide next to the RMMS console. CHEMISTRY ANALYSIS

• Utilize the isotopic mix used by chemistry to determine that the setpoint has been exceeded.

2.1.10.5 vent flow rate - see step 2.1.6, (COPY) t 2.1.10.6 gross concentration of the release ALARM - see step 2.1.5 4 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 -3

l EP-315, Rav. 2 Page 5 of 13 MAC/nig i l sensor data which corresponds to the prompt. (COPY) Refer to Appendix EP-315-2 If Data-Logger is unavailable, the Operator shall obtain the data from the following sources (listed in order of preference): 1. Control Room Strip Chart Recorders, refer to Appendix EP-315-2 y ~ < y l 2. National Weather Service (215) 597-084@ e 2.1.11 Review the Site Boundary Emergency Action Level Display for the current action leve', generate a hard copy and inform the Shif t Superinter. cent of the actio@ level. Repeat steps 2.1.8 through 2.1.11 for each release point l If this procedure is initiated due to an RM-ll alarm, repeat all calculations using the isotopic mix provided by Chemistry as soon as the mix becomes available. c. 2.1.12 For a current action level of unusual event or greater, generate a hardcopy of the following reports, unless otherwise directed by the Dose Assessment Team Leader. 2.1.12.1 (X/Q) Display & ) 2.1.12.2 Projected dose summary 2'l.12.3 Summary report 2.1.13 Repeat steps 2.1.8 through 2.1.11 where any following condition is observed: 2.1.13.1 A new high alarm (blinking, audible) from any channel per step 2.1.2 is indicated on 5 the RM-ll console. e Ed 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. m V 2.1.13.3 An EAL value described on either the RM-ll 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 "=

l EP-315, nav. 9 Page 6 of 13 MAC/nl@ ASSESSMENT CALCULATIONS (AND/OR) IMPLEMENT THE NEXT STEP OF THIS PROCEDURE. To terminate the RMMS program, enter ( /E, return) 2.2 Dose Assessment Turnover to the TSC ? 2.2.1 Upon activation of the TSC, the RM-21A Operator in Control Room will provide the following information t@ the Dose Assessment Team Leader in the TSC. l 2.2.1.1 time of reactor trip or scram 2.2.1.2 location of release 2.2.1.3 time of release 2.2.1.4 estimated duration of release 2.2.1.5 Containment Radiation Monitor information to include: primary containment leakage, drywell purging, number of fans operating, hours purged 2.2.1.6 wind direction, ground and elevated 2.2.1.7 location and value of peak (X/Q), depleted and undepleted P 2.2.1.8 time to reach peak (X/0) 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 ratG 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-23A Operator in the Control Room can be contacted.

q

^ 2.2.1.13 Protective Action Recommendation (s) if any 1 were made 2.2.2 Upon turnover of dose assessment from the Control Room to the TSC, the Dose Assessment Team Leader shall: 2.2.2.1 Brief team members on plant and release status.

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l EP-315, Rev. 5 Page 7 of 13 MAC/ nip i 2.2.2.2 Assign personnel as RM-21A Operator, RM-ll Operator, Calculator, Field Survey Group Leader. 2.2.2.3 Contact Chemistry for the status of the r plant to include SGTS filter efficiency and isotopic breakdown of drywell air, effluent release and reactor water. p 2.2.2.4 Initiate and direct dose calculations. 2.2.2.5 Review dose calculation parameters. 2.2.2.6 Evaluate results (Summary Report and Projected Dose Summary) against whole body gamma and thyroid inhalation PAGs. 2.2.2.7 Periodically brief the Emergency Director on offsite dose results and assist him with PAe 0.. recommendations if conditions are warranted. h 2.2.2.8 Periodically update the BRP on plant conditions, meteorology, and actual or r potential releases. w. 2.2.3 The RM-ll Operator shall: l 2.2.3.1 Continuously assess radiological trends frod p-- the drywell high-range radiation monitors I and plant effluent monitors and inform the l Dose Assessment Team Leader and Calculator g. as conditions change. () 2.2.3.2 Update the Calculator and Dose Assessment Team Leader, on an approximately 15 minute. l E: basis, with information from the affecte.d radiation effluent monitors unless otherwisd directed by the Dose Assessment Team Leadero 2.2.3.3 Inform the Doce Assessment Team Leader immediately in the event that any EAL has been reached or exceeded. g r. { 2.2.4 The Calculator shall: s L 2.2.4.1 Obtain, approximately every 15 minutes, the 3 _- effluent release date from the RM-ll Operator. 2.2.4.2 Perform, as requested by the Dose AssessmenG Team Leader, EP-325 for input to the RMMS dose model.

] EP-315, Rev. 5 Page 8 of 13 MAC/ nip; 2.2.4.3 Select and calculate, as directed by the Dose Assessment Team Leader, isotopic breakdowns of the source term for input to the RMMS dose model. 2.2.4.4 Note on the dose model output cover sheet, f the time of the calculations and assumptions used. 7 ( 2.2.4.5 Update dose trending sheets as required. l 2.2.4.6 Review dose model results for key information. Immediately, inform the Dose Assessment Team Leader if dose model results indicate PAG levels may be met or exceeded. 2.2.4.7 Update the status board keepers with the requested information. I* L 2.2.5 The RM-21A Operator shall: Y 2.2.5.1 Log onto the RM-21A system using the appropriate user name and password. 2.2.5.2 Obtain meteorological data for the period of interest by selecting the following options: 1. 94 - Meteorological Data Collection and r-Processing 2. I: - meteorological Data Processing k 3. 43 - Review Current Averages -or- #4 Meteorological Data Averages, if the evaluation. is to be done with historical data. RESPOND TO ALL PROMPTS AND GENERATE A HARDCOPY. I 2.2.5.3 Return to the primary menu and repeat steps 2.1.8 through 2.1.10.7. ~ b GENERATB HARDCOPIES OF ALL SCREENS OR AS DIRECTED BY THE DOSE ASSESSMENT TEAM LEADER H L-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. 2.2.5.5 For a current action level of unusual event or greater, generate a hardcopy of the s

] EP-315, Dev. 5 Pcga 9 of 13 MAC/nig following, unless otherwise directed by the Dose Assessment Team Leader. 1. (X/0) Display 2. skin isopleth 3. gamma isopleth 4. inhalation thyroid isopleth r 5. projected dose summary 6. summary report 2.2.5.6 Repeat steps 2.2.5.3 through 2.2.5.5 where any following condition is observed, unless otherwise directed by the Dose Assessment Team Leader. p 1. meteorology changes significantly g 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 Teas Leader 2.3 Dose Assessment Turnover From the TSC to the EOF r ~ 2.3.1 Upon activation of the EOF, the Dose Assessment Team Leader in the EOF shall contact the Dose Assessment Team Leader in the TSC (X2620) and request: l 1. the information in steps 2.2.1 2. ground and elevated sigma-theta L (( 3. ground and elevated delta temperature n.k 4. stability class $~ l 5. basis for Noble Gas and Iodine source term 6. Field Survey Team information: # teams available, f teams dispatched, time i ~

I EP-315, R2v. I Paga 10 of 1l MAC/nl' teams dispatched, location and results, 2.3.2 The RM-21A Operator shall activate the RM-2l computer as follows: ) i 1. Lift phone receiver from cradle and pull the left switch hook into a full. 7 upward position. y 2. When a dial tone is present, dial 1-326-9510. One ring followed by a tone f should be heard. p 3. Press the switch hook down to the firs' r notch. This engages the RM-21A L terminal (Textronics 4014) to the VAX y Computer. 4. Log onto the RM-21A system using the appropriate user name and password. r H 2.3.3 All functions and responsibilities describei

(-

in step 2.2.2 are applicable except anythini y pertaining to the RM-ll. All necessary I'

• radiological data shall be obtained from thi RM-21 on an as needed basis.

L 3.0 ACTIONS FOLLOW-UP LD None h 5, ev "s 4. 0" APPENDICES L-4.1 EF-315-2 Data-Logger /RMMS Cross Reference ? 4.2 EP-315-1 Isotopic Abundance (LGS FSAR Table 15.6-14) s 5.0 SUPPORTING INFORMATION t 5.1 Purpose The purpose of this procedure is to provide guidelines to calculate offsite doses during a potential or actual radiological emergency. .~ _:2

l EP-315, Rev. Page 11 of 1: MAC/nl; 5.2 Criteria for Use 5.2.1 This procedure is used to evaluate offsite doses when the effluent stream (potentially: F exceeds the limits set forth in the E technical specification. This can be determined by a chemical analysis or an 5 alarm of an effluent monitor on the RM-ll. t: 1-: 5.2.2 Implement this procedure for either [ simultaneous, VALID alarms on two common ~ (2EIO75 & SIE075), operating channels or a VALID alarm on a single operating channel whose mate is inop. (3GE075 VALID alarm anc 6GE075 is inop). 5.2.3 The manual mode of RMMS will allow the operator to bypass the use of real time l radiological and meteorological data, L enabling him to enter date of his own choosing. r 5.2.4 Operation of RMMS in the manual mode is useful for investigating offsite doses during Emergency Plan exercises and in the I event that radiological or meteorological data are unavailable in the real time mode, r ~ 5.3 Special Equipment ([ 5.3.1 RM-21A consoles and User Guide v.:, - kJ 5.3.2 RM-ll consoles and User Guide L 5.3.3 EP-315 Guide next to RMMS Console 5.4 References 5.4.1 LGS FSAR Table 15.6-14 I 5 4 ik u

... n. . - - ~. - l EP-315, Rev. 5 Page 12 of 13 MAC/ nip APPENDIX EP-315-1 l LOCA ISO *0PIC PERCENT ABUNDANCE IN PRIMARY r i Q-l Time after reactor scram: t* Isotone 1-2 hrs'2-8 hrs'8-24 hrs' 24-96 hrs' 96-720 hrs 1 b Kr-83m 1.41 0.24 0.001 Kr-85 0.05 0.07 0.11 0.20 5.47 I Kr-85m 6.61 3.89 0.48 / Kr-87 5.64 0.36 / g. 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 I~ Xe-133 38.9 57.9 82.4 97.4 90.3 Xe-135m 0.05 g, Xe-135 32.3 31.5 14.5 0.11 k Xe-137 Xe-138 0.25 i i i I-131 32.0 36.1 47.5 88.4 100.0 r h! I-133 68.0 63.9 52.5 11.6 0.0 L If venting through SGTS with a design basis filter [ efficiency, and 0.5%/ day leakage rate, then: , a I-131 11.0 34.1 41.7 68.7 98.3 I-333 89.0 65.9 58.3 31,3 1.b5 References LGS FSAR USE ONLY IF REACTOR HAS SCRAHMED.

• L-'A__'___._'_l_.__.__.

)j El sl5, Rev. 5. t Page 13 of 13: I MAC/n1[p] . APPENDIX EP-315-2 DATALOCCER/RMMS CROSS REFERENCE RfetS MANUAL DATALOGGER DATALOGGER RM-21A SENSOR Channel No. & Met. Prompts Abbreviation Parameter Name Primary Secondary Ground Direction 0 30'Dir./(9 T1DRL 30 'DIRgg (0) *, 159'DIR/do(15) WDI Ground Sigma Theta 0 30'DIRjtT9 T1DRL 30'DIRg9 (0), 159 'DIRgo (15) WDI/DEV Ground Speed 1 30' Speed TlSPL 30 ' Speed (1), 159' Speed (16) l WSI l Ground Delta T 6 266'-26'fT TlDT U-L 266'-26'AT(6), 300'-26'dT(23) l DTI l Elevated Direction 2 175' DIR.ge Tl DRI 175' DIRAfe (2), 304' dirge (20) WD2 Elevated Sigma Theta 2 175' DIR.ATO Tl DRI 175' DIR/fe (2), 304 ' DIRfy'e(20) WD2/DEV l Elevated Speed 3 175' Speed TISPI 175' Speed (3), 304' Speed (21) WS2 Elevated Delta T 7 266'-26'AT T1DL U-L 266'-26'AT(7), 300'-26'gT(23) DT2 Elevated Amb. Temp. 10 26' Ambient T T2 AT L 26'AmbientI10), 26' Amb. T (24) TR1

• Channel number from Data-logger in parenthesis ().

l Wind Charts Wind Speed - red - (0-100 mph) ful'1 scale Sigma theta - black - (0-100 mph) full scale

EP-316, R;v. PCgc 1 of 6 3850072910 DMvnl- $d@ PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE F I EP-316 CUMULATIVE POPULATION AND NEAR REAL-TIME EMERGENCY DOSE CALCULATIONS FOR AIRBORSE RELEASES - MANUAL METHOD h 1.0 PARTICIPANTS 1.1 Dose Assessment Team Leader shall direct the Dose Assessment Team to perform the necessary p~ calculations within this procedure. 1.2 The Dose Assessment Team shall perform the calculations in this procedure. a rt 1.3 Stift Technical Advisor shall perform the necessar3 Filculations within this procedure until the Dose htoec9 ment Team is available. 2.0 AC'1ILM1/10ED' ATE 2.1 The twee Assessment Team Leader or Shif t Technical Ad m w shall: ~ 2.1.1 Perform or direct team members to perform the I_ appropriate calculations in this procedure from thi ( following p TN f )' h 2.1.1.1 APPENDIX EP-316-F RAPID DOSE ASSESSMENTS f,' (, ,3 g HIGRESTWHOLE'.(BODYDOSERATE O 1.1 RELEASES \\,, I,-;, y. ~,h\\ w l yl.2 HIGHEST THYROID DOSE RATE DUE TO RADIOIODINE Y \\ '. PILEASES- , ',. N.' qf l

2. I. l. 2.<y APPENDI1 EP-316-2 REFINED EOSE ASSESSMENTS

\\ S (\\ .I SOURCETERMANDMETEOROLGGICAL[D .- % 2.0 ,,, 7 - { I w 2.0.1 Sourc e rth b,,,,,t ) \\.rN~ ' I p ~ \\ Meteorolo\\\\ \\ l Y 2.0.2 gical D ta L \\'%- f y-I 2.1 CHI /O AND PLUME TRA L IME D TER:!INATION I N 2.1.1 Inputs needed. Releas\\,4ypf dft[r in tio 2.1.2 udd J"' -1

l EP-316, Rev. 3 Page 3 of 69 DMR/nlp i 8 5.0 SUPPORTING INFORMATION 5.1 PURPOSE The purpose of this procedure is to provide methods of estimating the site boundary and offsite f airborne concentrations and resulting whole and/or thyroid doses. This procedure is to be used when the,RM-21 portion of the Radiation and y ?. Meteorological Monitoring System (RMMS) is not 9 available. O i I 5.2 CRITERIA FOR USE 5.2.1 Set of 30 acetate overlays (see Appendix EP-316-4) and base map available for use. I 5.2.2 Analertorhigherlevelemergencyduetoagaseouq release of radioactive material has been declared in accordance with EP-101, " Classification of Emergencies" and the RM-21 portion of RMMS is E inoperable. l r 5.2.3 Calculations performed in -this procedure should be checked by an independent reviewer. y 5.2.4 Any section of this procedure may be independentlyi performed based on information needed.

5.4 REFERENCES

~ 5.4.1 Limerick Generating Station Emergency Plan f 5.4.2 10CFR20, Appendix B 5.4.3 NUREG-0654, Criteria for Preparation and Evaluatid Rev. 1 of Radiological Emergency Response Pl( (RG 1.101 and Preparedness in Support of Nuclea( Rev. 2) Power Plants 5.4.4 EP-210 Dose Assessment Team 5.4.5 EP-317 Determination of Protective.Ac, tion Recommendations k 5.4.6 EP-325 Use of the Containment Radiation Monitor @ Estimate Release Source Term 5.4.7 FSAR Table 11.3-1 Expected Annual Activity ReleaO from Gaseous Waste Management Systems ~ ?..

EP-316, R2v. Pcge 2 of 6 DMR/nl. 2.1.3 Overlay selection 2.1.4 Overlay orientation 2.1.5 CHI /O calculation I 2.1.6 Plume travel time 2.2 WHOLE BODY DOSE DUE TO NOBLE GAS RELEASES L 2.2.1 Plume centerline dose I 2.2.2 Determination of whole body dose rate from field survey data l 2.3 THYROID DOSE DUE TO RADIOIODINE RELEASES 2.3.1 Plume centerline dose a Ej 2.3.2 Determination of-thyroid dose from F.- field survey data. C 7 2.4 GROUND DEPOSITION PER UNIT AREA 2.'4.1 Assessment of offsite plume centerline deposition per unit area 2.1.2 Direct team members to complete Appendix EP-316-3 Summary Sheet for use with EP-317, " Determination F-of Protective Action Recommendations." CALCULATIONS SHOULD BE COMPARED AS SOON AS } PRACTICABLE TO FIELD SURVEY DATA.

• )

2.1.3 Report results along with protective action recommendations to the Site Emergency Coordinator,' r if activated, or Emergency Director. 4.0 APPENDICES 4.1 EP-316-1 Rapid Dose Assessments f 4.2 EP-316-2 Refined Dose Assessmentr, 4.3 EP-316-3 Summary Sheet 4.4 EP-316-4 Chi /0 Overlays E m

EP-316, Rsv. Page 4 of 6 DMR/nl-i l l 5.4.8 FSAR Table 15.6-14 LOCA: Activity Airborne in ( Primary Containment ] 5.4.9 Limerick Generating Station EROL Table 2.1-3 f l 5.4.10 10CFR50, Appendix I l 5.4.11 EP-101 Classification of Emergencies

b. 7 El l

5.4.12 Regulatory Guide 1.111, Revision 1, Methods of q f Estimating Atmospheric Transport and Dispersion of I Gaseous Eftluents in Routine Releases from Light-Water-Cooled Reactors. 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 Compliance with 10CFR50, Appendix I. u ] 5.4.14 Regulator Guide 1.23,ProhosedRevision1,"Onsitt r Meteorolo ical Programs." l 5.4.15 Postulated MCA data for LOCA from the RMMS. e 8 .t t Y b __ e B ,...g a

a. w.- EP-316, Rev. 3 Page 5 of 69 DMR/nlp APPENDIX EP-316-1 RAPID DOSE ASSESSMENTS 1.1 HIGHEST WHOLE BODY DOSE RATE DUE TO NOBLE GAS RELEASES r 1.1.1 Obtain gaseous release data for the North and South vents from one of the following locations (use the highest channel on Recorders): [ A. North Vent Wide Range Gas Monitor ),

1) RM-ll Display Console Channel 4TE-076

2) MCR Panel 00C691 (RM-23)

3) MCR Panel 00C624 (Strip Chart in uCi/sec)

B. South Vent Unit 1

1) Average of the RM-ll Display Console Chan 3GE-185 and 6GE-185 C.

South Vent Unit 2

1) Average of the RM-ll Display Console Channels 3GE-285 and 6GE-285 Calculate site boundary whole body dose rate.

1.1.2 U1 U2 NORTH SOUTH SOUTH OPERATION VENT VENT VENT P ff[. 1. Record the peak uCi/sec uCi/cc uCi/ effluent release 4; l rate and/or concentration whichever is I applicable. 2. Multiply by mR/hr mR/hr mR/hr mRs j conversion factor 3.94N6 uCi/sec 4.19P2 uCi/cc 4.19P2 uCi to determine site l boundary dose rate. .e 3. Site boundary dose mR/hr mR/hr mR, l rate. 4. Add all three mR/hr (total) { values. THIS IS A CONSERVATIVE SITE BOUNDARY WHOLE BODY DOSE RATE BASED ON THE ANNUAL AVERAGE CHI /O ISOTOPIC MIX I{ FSAR TABLE 15.6-14, AND NORMAL VENT FLOWS.

,. 2 EP-316, Rev. 3 Page 6 of 69 DM9/nig n l 1.2 RIGHESP THYROID DOSE RATE DUE TO RADIOIODINE RELEASES 1.2.1 Obtain the Iodine channel effluent concentration from the RM-ll Display Console: a) 2IE075 (North Vant) Ave. b) SIE075 (North Vent) p c) 2IElB5 (U1 South Vent) r Ave. d) SIE185 (Ul South Vent) l e) 2IE285 (U2 South Vent) Ave. f) SIE285 (U2 South Vent) r w ( {,l NORPH VEN* Ul SOUTH VENT U2 SOUTH VENT uCi/cc Iodine uCi/cc Iodine uCi/cc Iodine L l 1.2.2 Determine Inhalation Thyroid Dose Rate (Infant Thyroid in all cases) t-ti. F'! Iodine uCi/cc X conversion = mR/hr factor ? mR/hr North Vent X mR/hr = 3.61 P6 uCi/cc mR/hr Ul South Vent X mR/hr = 2.30 P6 uCi/cc mR/hr U2 South Vent X mR/hr = []. 2.30 P6 uCi/cc Total mR/hr h

• HIS IS A CONSERVATIVE SITE BOUNDARY "HYROID DOSE RATE BASED ON THE ANNUAL AVERAGE CHI /0, AND NORMAL VENT FLOWS.

r.4 ~. EP-316, Rev. Page 7 of 6-DMR/nl-APPENDIX EP-316-2 REFINED DOSE ASSESSMENTS 2.0 SOURCE PERM AND METEOROLOGICAL DATA r DATA SHEET 1 SHOULD BE COMPLETED FOR ALL SUBSECTIONS OF THIS SECTION. [ 2.0.1 SOURCE TERM DATA b 1. Establish date and time period (duration) of release. Enter on Data Sheet 1. 2. Record the release data. A. For the north vent noble gas releases, read the release activity in uCi/sec from the the RM-ll Display Console (Composite channel 4TE-076) or the strip chart recorders on Panel 00C624. ~ B. For the Ul South vent, obtain the release activity in uCi/cc and vent flow rate from the RM-ll Display Console (Average of channels 3GE-185 and 6GE-185). s. 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). ~ 3. Attach sample analysis for noble gas or iodine, if available. e 4. For the same time period, obtain the total iodine results r of reactor enclosure air and/or drywell air sample (s) and release point sample in uci/ce. l 5. Calculate SGTS filter efficiency. ~ 100 (freactor enclosure I and/or drvwell I)-release point (Ereactor enclosure I and/or drywell I) l NO*E @{l'.. SGTS filter efficiency will determine the factor to be g 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 METEOROLOGICAL 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 directior e m + e e

+w EP-316, Rev. Pcge B of G DMR/n2 a from the instrument recorders on Panel OBC 699. A. Wind Speed Primary: 175 Ft. Level Tower 1 (Channel 3)g Alternate: 304 Ft. Level Tower 2 (Channel 21)g p h-B. Wind Direction c:

1. 8' Primary:

175 Ft. Level Tower 1 (Channel 2)g p Alternate: 304 Ft. Level Tower 2 (Channel 20)E i L l C. Panel OBC 699 t' l Primary: XR - MS - 012B I r f l Alternate: XR - MS - 020B E I Record the average wind speed and wind direction at the f[;i E elevated tower level for the time period of interest. e 3 2. Determine the atmospheric stability class. L A.I Obtain the following meteorological parameters fron the Climatronics data logger: ~' A.l. Read DT2 (Channel 7; 266-26 ft) deg from Tower 1. If this value is r-available, continue to Section C l. g'Ny If D*2 is unavailable, use DT4. A.2. Read DT4 (Channel 23; 300-26 ft) deg K: from Tower 2. If this value is available, continue to Section C.2. If DT4 is unavailable, use WD2/DEV. A.3. Read WD2/DEV (Channel 2; 175 f t) from Tower 1. If this value is degrees a l available, continue to Section C.3. NOTE: IF WIND DIRECTION IS FROM 120 DEGREES AZIMUTH-180 DEGREES AZIMUTH, k i WD2/DEV IS UNAVAILABLE. USE WD6/DEV. l r-3 [.. A.4. Read WD6/DEV (Channel 20; 304 ft) F from Tower 2. If this value is degrees a _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. e

3 ' l w-EP-316, Rev. Page 9 of 6' DMR/nl: 9 ] B. In the absence of DT2, DT4, WD2/DEV, WD6/DEV, obtal: the following meteorological data from the National Weathe* Service (NWS) station in Philadelphia, PA e I B.l. Wind Direction (WD30) deg a ~ A e h B.2. Wind Speed (WS30) knot t, s $/ B.3. Cloud Cover (CLCVR) (tenths B.4. Cloud Ceiling (CLCEG, skip to Section C.S. 9 C. Turbulence Typing C.1 DT2 For DT2, type turbulence class according to Table 316-A. Record stability class on Data Sheet 1. If not available, go to C.2 below; Stability Class C.2 DT4 For DT4, type turbulence class according to Table 316-A.. Record stability class on Data Sheet 1. If not available, go to C.3 below; Stability Class pc g l'[ C.3 WD2/DEV a If wind direction is not between 120 and 180 degrees azimuth, WD2/DEV can be used (unaf fected by cooling tower). For WD2/DEV, type turbulence, class pcqordipg,to Table 316-7 r fCs, Record stability classioniDatY Sheet 1. If nc ,.~s pm Q h[r y Gj '.'ayailable,Fgoj.to (C.4 ;beloy,\\-\\.i) (;/ n [$3 I'.y~A 4 ,Sga ility Class Z 1 4 ..? 6:.. g*g V:- -T 0 'i" ( h l I. k) h d U L. {- - U A 5- " 'C. 4 WD6/DEV V l If wind direction is not between 45 and 95 degrees azimuth, WD6/DEV can be used (unaffected by cooling tower). For WD6/DEV, type turbulence class according to Table 316-q Record stability class on Data Sheet 1. If ne available, go to C.5 below. Stability Class

EP-316, R;v. 2 Page 10 of 69 DNR/nir C.5 NWS Technicue 5.1 Determine net radiation index (NRADI). For daytime, (one hour after sunrise to one hour before sunset), complete below, otherwise go to Section C.5.2. 5.1.1 Determine the insolation class number (ICLNO) as follows: Record nearest current hour of day Eastern Standard Time) h1 (military time) Record Date i-Using the above information, determine ICLNO from Table 316-B ICLNO 5.1.2 Using CLCVR (B.3), CLCEG (B. 4) and ICLNO, determine NRADI from Table 316-C and record in Section C.5.3. l Go to Section C.5.3. 5.2 Determine NRADI from Table 316-C for j nighttime using CLCVR (B.3) and record ia Section C.S.3. 5.3 Determine stability class from Table 316-using: NRADI (determined in either Section C.5.1 or Section C.5.2) 7 WS30 (determined in Section B.2) f,}' r es Stability Class b Record the stability class on Data Sheet 1.

EP-316, Rev. 3 Page 11 of 69 DMR/nlp TABLE 316-A CLASSIFICATION OF A*MOSPHEPIC STABILITY AT THE LIMERICE GENERATING S*ATION METEOROLOGICAL TOWER SITE f, BY EI*HER VERTICAL *EMPERATURE DIFFERENCE OR SIGMA THETA l I i t SIGMA THE*A DELTA T (deg F) STABILITY PASQUILJ ED6/DEV OR DESCRIP* ION STABILI' WD2/DEV DT4 DT2 CLASS l > 22.5 < -2.85 < -2.50 Extremely Unstable A 7 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 Slightiv Unstable C 7.5 to 12.4 -0.75 to -2.24 -0.66 to -1.97 Neutral D E ~ 3.8 to 7.4 2.25 to -0.74 1.98 to -0.65 Slightly Stable E 2.1 to 3.7 6.01 to 2.26 5.27 to 1.99 Moderately Stable F -~ < 2.1 > 6.2 > 5.28 Extremely Stable G fI b l Use of Parameters in Order of Priority: DT2 DT4 WD2/DEV (unavailable if wind direction is between 120 degrees azimuth - 180 degrees azimuth) WD6/DEV (unavailable if wind direction is between 45 degrees azinuth - 95 degrees azimuth) .;U L-m

EP-316, Rov. Page 12 of f DMR/n; TAB L'd 316-B ICLNO AS A FUNCTION OF HOUR AND DATE I Hour of Day (EST) All othc Date 7 8 9 lb 11 12 13 14 15 16 17 times 1/22 1 1 2 2 2 2 2 2 2 1 1 1 1/5 2/6 1 1 2 2 2 2 2 2 2 1 1 1 1/23 2/21 1 1 2 2 2 3 2 2 2 1 1 1 2/7 3/8 1 2 2 2 3 3 3 2 2 2 1 1 2/22 3/9 3/23 1 2 2 3 3 3 3 3 2 2 1 1 3/24 4/7 1 2 3 3 3 3 3 3 3 2 1 1 4/22 2 2 3 3 3 3 3 3 3 2 2 1 4/8 5/7 2 2 3 3 4 4 4 3 3 2 2 1 4/23 5/22 2 2 3 3 4 4 4 3 3 2 2 1 5/8 6/6 2 3 3 3 4 4 4 3 3 3 2 1 ) 5/23 e, 6/21 2 3 3 3 4 4 4 3 3 3 2 1 6/7 6/22 7/6 2 3 3 3 4 4 4 3 3 3 2 1 7/21 2 3 3 3 4 4 4 3 3 3 2 1 7/7 w 8/5 2 2 3 3 4 4 4 3 3 2 2 1 7/22 8/20 2 2 3 3 4 4 4 3 3 2 2 1 8/6 9/4

2., 2 3

3 3 3 3 3 3 2 2 1 8/21 9/19 1 2 3 3 3 3 3 3 3 2 1 1 9/5 10/4 1 2 2 3 3 3 3 3 2 2 1 1 9/20 10/19 1 2 2 2 3 3 3 2 2 2 1 1 10/5 1 F 10/20 - 11/3 1 1 2 2 2. 3 2 2 2 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 2 1 1 1 s 7), 's 12/4 12/18 1 1 1 2 2 2 2 2 1 1 1 1 f,; 12/19 - 1/4 1 1 1 2 2 2 2 2 1 1 1 1 V Source: Turnor, B.T., " Relationship Between 24-Hour Mean Air Qualit3 Measurements and Meteorological Factors in Nashville, TN, Journal-of-Air Pollution Control Association, October, 1961, pp 483-489. + l .~.

EP-316, Rav. Page 13 of 6 DMR/nl s TABLE 316-C NRADI DURING DAYTIME (FUNCTION OF CLCVR AND CLCEG) AND NIGHTTIME (FUNCTION OF CLCVR) CONDITIONS r Daytime Nighttime CLCEG g \\~ CLCVR < 7,000 ft 7,000-15,900 ft , > 16,000 ft b 0/10 1/10 2/10 NRADI = ICLNO NRADI = -2 3/10 4/10 ] 5/10 6/10 7/10 NRADI* = ICLNO -2 NRADI* = ICLNO -1 NRADI** = - k_ 8/10 p-9/10 10/10 NRADI =0

• If NRADI is less than 1, set NRADI equal to 1.

] **If CLCVR is 10/10 and the ceiling is < 7,000 Ft, NRADI equals 0. TABLE 316-D ~ STABILITY CLASS AS A FUNCTION OF NRADI AND WS30 t-NRADI WS30 Daytime Nighttime (Knots) 4 3 2 1 0 -1 -2 0 or 1 A A B C D F G 2 or 3 A B B C D F G 4 or 5 A B C D D E F G~. t 6 B B C D D E F E1 7 B B C D D D E VL 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 >12 C D D D D D D

~,.... - - m r--- r-m l / -.3 s EP-316, Rev. 3 Page 14 of 69 DMR/ nip DATA SHEET 1 (Section 2.0) hrs TIME PERIOD (RELEASE DURATION) DATE 2.0.1 SOURCE TERM INFORMATION Release Point Vent Flow Effluent Monitor Sample Analysis Attached (Y,N) (Yes or No) Rate (CFM) Information Noble Gas Iodine ll UCi/sec 9 North Vent uCi/cc Unit 1 South Vent uC1/cc Unit 2 South Vent

• North Stack Vent Flow = uCi/sec uCi/cc x 472 2.0.2 METEOROLOGICAL CONDITIONS Wind speed - elevated sph Wind direction - elevated deg az Stability class NAME/ TITLE:

DATE: TIME:

EP-316, Rev. T Page 15 of 61 DMR/nig 2.1 CHI /O AND PLUME TRAVEL TIME DETERMINATION Determine the centerline CHI /O value from the ground and/or elevated overlays, completing Worksheet 1 in the process. F 2.1.1 Inputs Needed 1. Record elevated wind speed, elevated wind direction, and stability class from Data Sheet 1. d 2. Determine the direction toward which the wind is 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. 3. Record release point identifier (i.e. north vent, U1 or U2 south vents) and vent flow rate from Data Shee( l' tl e. ',e 2.1.2 Release ~ Type Determination u 1. Utilizing release point, vent flow rate and elevated wind speed data, determine release type from Table 316-E. ~~ I 2. Identify release type on Worksheet 1. 2.1.3 overlay Selection "~ 1. Ground Release: Select overlay from Table 316-F. p ../ 2. Elevatti Release: Utilizing elevated wind speed, E stability class, release point and flow rate from Data Sheet 1, go to Table 316-G. Select overlay fr@ Table 316-G. 3. Mixed Mode 1/2 Release: Select overlay from Tables 316-F and 316-G. 4. Identify the overlays selected on the appropriate [ e, f portion of Worksheet 1. f! \\ 2.1.4 overlay orientation { y _1 1. Place overlay on base map. 2. Align overlay in bearing direction, using azimuth '~ indicators for guidance. Tape in place and tighten wing nut. M

EP-316, Rev. 3 Page 16 of 69 DMR/ nip 3. For mixed mode 1/2 release type, procedure has to be repeated for both ground and elevated overlays. 2.1.5 CHI /O Calculation 1. Ground release only r A. For each applicable distance, reference "centerl{ information box for Xu/O value. t B. Calculate and enter CHI /O values in Column A of Worksheet 1. C. Go to Section 2.1.6. 2. Elevated release only A. For each applicable distance, reference "centerli (' ' information box for Xu/O value. 3 B. Calculate and enter CHI /O values in Column C of

• Worksheet 1.

e 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. ~~ List ground CHI /O values in Column A, and elevated CHI /O values in Column C of Worksheet 1 5 B. Utilizing release point, vent flow rate and i 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. This is the portion of the plume downwashed (or ~ entrained) to the ground. C. Calculate elevated portion of plume (1 - ET ) as enter in Column D of Worksheet 1. This is the h\\ $ portion of the plume remaining elevated. k D. Calculate mixed mode CHI /O on Worksheet 1: [5[ 2.1.6 Plume Travel Time (Tp) 1. Ground, Elevated, or Mixed Mode Release: Tp (min) = Downwind Distance (miles) x 60.0 (min) 3

... _ =... ~ . ~. - . _. - ~ ~. t i EP-316, Rev. Page 17.of 6-DMR/nl. 1 Elevated Wind Speed (mph) hr .e 2. Record plume travel time in last column of i Worksheet 1. 1 i r e 9 J-A~ Ik l L. V v + r i T:: % L=

f..

e: - D 4 1 a t ..w. m--, ew. W ~ v.-r,,v- -,,,v-- ~-,,,-,,--,-e,-,, -rn -n.,,, n._, en.,n .-,w- ,--.,_,v.,-

EP-316, Rev. 3 Page 18 of 69 DMR/nlp TABLE 316-E RELEASE TYPING AS A FUNCTION OF VENT FLOW RATE, RELEASE POINT AND ELEVATED WIND SPEED NORTH VENT RELEASE r VENT TLOW ELEVATED WIND SPEED (MPH) ~ RATE (CFM) . 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 l 321,000-363,000 1 3.4 3.5 - 11.5 11.6 - 16.9 . 1 17.0 l"Y31,000-320,000 1 2.6 2.7 - 8.7 8.8 - 13.0 1 13.1 i 150,000-230,000 5 1.7 1.8 - 5.7 5.8 - 8.7 1 8.8 5 3,000* N/A N/A N/A All Ul OR U2 SOUTH VENT RELEASE VENT FLOW ELEVATED WIND SPEED (MPH) RATE (CFM) ELEVATED MIXED MODE 1 MIXED MODE 2 GROUND l 201,000-234,000 1 5.3 5.4 - 17.6 17.7 - 26.7 1 26.8 \\ 151,000-200,000 1 3.9

4. 0 - 13.2 13.3 - 19.9

> 20.0 l 109,000-150,000 1 2.8 2.9 - 9.4 9.5 - 14.2 1 14.3 1 61,000-100,000 5 1.8 1.9 - 6.2 6.3 - 9.3 1 9.4 40,000-60,000 5 1.2 1.3 - 3.8 3.9 - 5.7 1 5.8 S 3,000* N/A N/A N/A All u N/A - Not Applicable ~

• Represents release from isolated vents.

Always results i in ground level release.

EP-316, Rev. 1 Page 19 of 6@ DMR/nig TABLE 316-F GROUND LEVEL RELEASE OVERLAY SELECTION Stability Class Overlay Figure A GA 316-A B GB 316-B i C GC 316-C D GD 316-D E GE 316-E F GF 316-F G GG 316-G a ) a L I ~ r hm

m -g- - y- "" f'.h.N ' T' l ~ l . [$% 4 / Er *'16, Rev. S Page 20 of l DMR/ri) I TABLE 316-G ELEVATED RELEASE OVERLAY SELECTION f i ELEVATED WIND SPEED (MPH) Lg SOUTH VENT FLOW RATE NORTH VENT FLOW RATE STABILITY (CFM x 1,000) (CFM x 1,000) CLASS 386-410 321-385 231-320 150-230 201-234 151-200 101-150 61-100 40-60 OVEPLAY FIGURE A All All All All All All All All All EA1 316-H B > 6.5 > 6.5 > 4.5 > 3.5 > 7.5 > 5.5 > 3.5 > 2.5 > 1.5 En1 316-I 1 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.( 7 1.4 En2 316-J En3 316-K < 1.4 2.5-3.4 1.5-2.4 i 2.5-3.4 2.5-3.4 1.5-2.4 En4 316-L i 2.4 < 2.4 1 1.4 1 1.4 1 2.4 i 1.4 i 1.4 -> 5.5 > 3.5 > 7.5 > 5.5 > 4.5 > 2.5 > 1.5 Ecl 316-M C > 8.5 > 8.5 475-8.4 475-8.4 3 5-5.4 275-3.4 475-7.4 375-5.4 275-4.4 175-2.4 7 1.4 EC2 316-N EC3 316-0 2.5-4.4 2.5-4.4 1.5-3.4 1.5-2.4 2.5-4.4 1.5-3.4 1.5-2.4 < l.4 EC4 316-P < 2.4 1 2.4 1 1.4 11.4 1 2.4 5 1.4 1 1.4 l 475-7.4 475-7.4 3 5-5.4 2 5-3.4 4-> 7.5 > 5.5 > 4.5 > 2.5 > 1.5 EDL 316-0 'i D > 7.5 > 7.5 -> 5.5 > 3.5 ED2 316-R 5-7.4 375-5.4 275-4.4 175-2.4 < 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 ED4 316-T < 1.4 2.5-3.4 1.5-2.4 2.5-3.4 2.5-3.4 EDS 316-U < 2.4 1 2.4 1 2.4 i 1.4 1 2.4 1 1.4 1 1.4 l E > 2.5 > 2.S > 1.5 All > 1.5 > 1.5 All All All EE1 316-v EE2 316-W 1 1.4 1 1.4 175-2.4 175 9.4 i 1.4 EE3 316-X i 1.4 1 1.4 F > 2.5 > 2.5 > 1.5 All > 1.5 > 1.5 All All All EFl 316-Y EF2 316-7. 1 5-2.4 175-2.4 7 1.4 7 1.4 7 1.4 EF3 316-AA -< l.4 < 1.4 G > 2.5 > 2.5 > 1.5 All > 1.5 > 1.5 All All All EGl 316-Dn EG2 316-CC 175-2.4 1 5-2.4 7 1.4 7 1.4 7 1.C EG3 316-DD < l.4 < l.4

m v q N 's.h*' 3./ jg 1 EP-316, Inv..j Page 21 of Gj j ITIP/nig j ~! TNTT.E 316-11 RTPAltitEtTP CCITPICIDTP (I?r) ,IT)R ?rITITI VRTP RET.rASC i I 17.IVNITD MIf1D SPPJ7) (ftPit) l V QTP FIO T raTc (crti) 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 >.'0.0 9'l 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 1.00 321,000 - 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 } 150,000 - 230,000 0.00 0.0 3 0.12 0.16 0.19 0.19 0.53 0.78 1.00 1.00 1.00 1.00 1.00 1.t)0 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 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I f flote: E = 0.00 P.levated nelease E = 1.00 Ground Inicace 0.00 <C <1.00 tfixed iWe I:elcace s Source: Itgulatory GuiFe 1.111 Ibvision 1 i

1 9 p 36i v f /n 0 a oP P 0 T 2i 2 ,2 0 61 e 3 g 9 - a 1 PP F 0 0 1 0 7 1 4 0 6 ~ 1 t 0 7 5 F 1 j n 0 ) l 4 i = P 1 1 f 8 1 1 0 0 0 0 ( 1 2 0 0 0 0 ~ D 3 ~ J 1 0 0 0 1 1 1 ~ PP 0 7 0 6 0 0 0 G 1 2 6 0 0 0 2 i D 1 0 0 C 1 1 1 I I I 0 6 9 8 0 0 0 F 1 1 0 0 0 1 ~ D 1 0 0 0 1 1 1 m"~~ PT 0 5 8 7 0 0 0 A 1 1 2 0 0 0 N 0 J 1 0 0 0 1 1 1 D 0 3 6 0 4 0 0 1 1 2 9 0 0 )TU 9 0 0 0 0 0 0 E 0 0 0 0 1 1 ( 0 0 0 0 0 I 1 5 9 3 0 0 5 N 0 y P 1 2 1 1 1 1 1 T 1 1 7 0 0 TQ 8 2 0 0 0 n I 0 I E 0 0 0 0 1 1 o I C P 9 0 0 0 8 3 7 7 0 0 4 0 l I 2 0 1 1 1 1 0 1 1 4 0 0 P 6 r T 1 7 5 0 0 0 n y [ a R 0 0 0 0 1 1 0 3 V 8 0 0 0 o a i 5 0 5 1 0 0 3 T. n 0 2 0 1 1 1 1 0 1 1 2 0 0 ) 1 s T 1 P P I 6 7 0 0 0 n 0 A 0 0 0 0 1 1 f T T pf 7 0 0 0 o t t r' 0 O 0 6 2 9 4 0 2 S 0 1 2 0 1 1 1 1 {', 3 0 0 1 1 7 0 t I R 5 8 0 0 0 n 0 T A V 0 0 0 0 0 1 n 6 0 0 0 P I t 1 1 0 0 8 6 8 0 0 T 0 i 2 0 1 1 1 i 0 0 0 1 2 E W T n D 4 9 7 0 0 n 0 0 0 0 0 1 S r o 0 n 5 9 0 0 AET i ~ 0 0 1 1 3 0 TGR n 0 0 AP i 2 0 0 1 1 i 0 D. 0 1 1 0 ET v I 3 8 8 0 0 n 0 0 0 0 0 1 PI m e 0 E r 4 8 0 0 n DPu 9 ~ 0 0 0 2 3 0 0 1 1 0 0 1 1 i 0 0 0 0 1 0 TD 1 I r P' "P 2 5 8 0 0 n 0 0 0 0 0 1 A :r n 1 0 n VUi 3 7 0 0 0 0 0 0 0 0 J OX 1 8 0 P1 1 0 0 1 1 i 0 0 0 0 0 0 DCr e 1 7 1 3 B 0 0 n 0 0 0 0 0 1 d 0 W[T n 2 C. 0 0 0 iu 7 ~ 0 ~ c 1 0 0 1 1 i 1 1 6 0 0 n y 0 2 5 0 0 n r 0 0 0 0 0 o 6 0 0 0 0 0 00r t 1 0 0 1 1 i 0, 0, 0, 0, 0, 0 0. C a 0 3 0 0 n 0 l 2 4 0 0 n 4 0 0 0 0 01< u 3 0 5 0 6 g 5 2 2 1 1

==0 e 1 0 0 1 1 1 r 0 rT 0 9 8 3 0 a ) 0 EE0 0 1 i 1 2 9 0 n Or r 4 0, I 0 0 0 0 0 F (c e 1 0 0 0 1 1 0 0 0 0 0 3 c PE 0, 0, 0, 0, 0, 8 1 1 0 n 0 e r n 1 2 8 0 T 1 1 1 1 0 t u TRA 0 5 0 6 4 b o 3 S 1 0 0 0 1 1 VP 2 1 1 t 4 I 1 .1

~ V' ' ' ' ' ' } ' l ' n y(;,p q v ,r, s \\ ~ } ~vf .\\t I s' Q:Q '} s I EP-316, Rev. 3 ii Page 23 of 69 i DMR/ nip i WORKSiiEET 1 (Section 2.1) 4 CALCULATION TABLP - Cili /O DISPERSION FACTOR (PLUME CENTERLINE) AT LOCATIONS O Elevated Wind Speed: mph l Elevated Wind Direction: degrees azimuth Bearing: Sector Stability Class: Vent Flow Rate cfm Release Point Identifier: 1 Mixed Mode 1 Release Type: Ground Mixed Mode 2 Elevated Overlays Selected: Ground Elevated ( f Downwind A x B + C x D = E P1ume ET

• • Elevated Cili /O l-ET Mixed Mode 1 or 2 Travel Time Distance (Miles)

(sec/m3) (sec/m3) CHI /O (sec/m3) (min.) 0.5 2.0 5.0 10.0 OTTIER -2 GROUND CIII/O = xj (M ) x 2.237 (mph /m/sec) O ELF.VATED WIND SPEED (MPII) -2 L- - ^^ - .<,,n m m m -arn__ A_ m m L__

EP-316, Rav. 3 Page 24 of 69 DMR/nlp 2.2 WHOLE BODY DOSE DUE TO NOBLE GAS RELEASES 2.2.1 Plume Centerline Dose FOR " PUFF TYPE" RELEASES OR SHORT TERM RELEASES WITH F CONSISTENT METEOPOLOGY, TIME PERIOD CORRESPONDS WITH THE TOTAL PERIOD OF RELEASE. FOR LONG TERM RELEASES WITH CONSISTENT METEOROLOGY, THE TIME PERIOD CORRESPONDS WITH THE TOTAL PERIOD OF RELEASE. IF METEOROLOGY CHANGES (I.E. y WIND DIRECTION SHIFTS, ATMOSPHERIC STABILITY CHANGES, OR WIND SPEED CHANGES SIGNIFICANTLY), DIVIDE THE RELEASE INTO SEGMENTS ACCORDING TO SUCH SHIFTS. 1. For a release from the South vent, complete Worksheet 2. A. Record the release data in Columns A and B on 7 Worksheet 2 from Data Sheet 1. g-B. Record the vent flow rate from the appropriate R release point in Column C on Worksheet 2 from Data r Sheet 1. !.?r L C. Perform the operations indicated on Worksheet 2 to obtain release rate (Column E) in UCi/sec. Record in Column A of Work Sheet 4. 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 p conversion Factor based on the time since the reactor y rm } shutdown. Transfer gamma dose factor to Column D of [f Worksheet 4. l Table 316-J 0-2 hrs'2-8 brsl8 brs-1 dayll day-4 daysl4 days = 1 l T= lo hrs Rem-m uCi-hr 6.14N4 3.57N4 1.07N4 3.38N5 3.36N5 3.0 i lrb 3. Complete Worksheet 4 to calculate Gamma Dose at C locations of interest. A. Record the CHI /O dispersion factor from Worksheet 1 at each downwind distance of interest in Column t B. ' E' B. Record release duration from Data Sheet 1, and (_ enter in Column E o,n Worksheet 4. -=

EP-316, Rev. 3: Page 25 of 69 DMR/nlp. t C. Perform the calculations indicated on Worksheet 4, to obtain air concentration (Column C) and the resultant gamma whole body doses (Column F). 4. Determine Whole Body Man-Rem estimates by completing r ] Worksheet 5. Use Table 316-L Population Distribution. ) .\\. k w h i if ~ f r [ P $1 y b.'s l (- L L-h. U: 9 In 3 l. I '- g. W w m .m._.

39p 6i E n T vf/ A) eor RC R M E 6D EES ,2 S/ 6 AI 1 e EC a 3g LU - a E( ~ PP R E n = 3 ir ~ RO T ~ C AF S N 2 2 N DO 7 7 O I 4 4 y I S T R ) A E 2 L V 5, U N 2 C O 'j L C n A o C i t E X c T e A S R E ( E T 2 S A A R T E E. L W) F E OM 1 R CLF 1 1S FC Q* K S ( f R A T ] O G N 1 W E E V R_ L ( B 1 ON .X Y) TC IC V/ BIITC CU c A( j t t n n l S e e T T V V N I I h h O t t P u u A o o E S S SA 1 2 E L t t E i i R n n U U ..l i il I

.-y,- , e l r,- EP-316, Rev. a i Page 27 of 69 DMR/ nip WORKSHEET 3 (Section 2.2) CALCULATION TABLE - GAMMA DOSE FACTOR C A X B = Gamma Dose Decimal % Abundance .g NUCLIDE Isotopic Decimal % (Rem-m3) X Factor Abundance Factor uci-br (Rem-m3) uCi-hr Kr-83m 8.63 N9 Kr-85m 1.34 N4 Kr-85 1.84 N6 Kr-87 6.76 N4 Kr-88 1.68 N3 Xe-131m 1.04 NS Xe-133m 2.87 N5 Xe-133 3.36 N5 Xe-135 2.07 N4 3 lI_(C) Rem-m = uCi-br

gspw w w -5 ~' h, s 9 c\\. EP-316, Rev. ~,5 t Page 28 of 69 DMR/ nip WORKSIIEET 4 (Section 2.2) CALCULATION TABLE - PLUME CENTERLINE GROUND LEVEL WiiOLE BODY DOSE AT LOCATIONS OF INTEREST WIND DIRECTION: degrees i BEARING: sector RELEASE POINT {g A X B = C X D X E = F Chi /O Air Gamma Dose DISTANCE Isotopic Release Dispersion Concentration (Rem-m3)_ Release Duration Gamma Done (MILES) Rate (uCi/sec) Factor (sec/m3) (uCi/m3) Factor (uc i-h r )_ (Ifours) (Rem) i 0.5 { 2.0 5.0 10.0 other BASIS: CENTERLINE OF RELEASE PATII ONLY. TilESE CALCULATIONS ARE VALID FOR A CONSTANT ISOTOPIC AND RELEASE RATE, CONSTANT STACK FLOW RATE, CONSTANT DISTANCE, CONSTANT WIND SPEED, TURBULENCE CLASS. IF ANY OF TilESE FACTORS CIIANGE SIGNIFICANTLY, NEW VALUES MUST BE CALCULATED.

EP-316, Rev. Page 29 of 6 DMR/nl i WORKSHEET 5 (Section 2.2) WHOLE BODY MAN-REM ESTIMATES 4 GAMMA DOSE (Rem) POPULATION [ f LOCATION FROM COLUMN F IN BEARING L.. (MILES) WORKSHEET 4 X SECTOR = MAN-REM s r 0-1 ( s. 1-2 [ 2-3 j 3-4 F f= 45 i 5-10 J

• Use value at 7.0 mile distance l

Ii NAME/ TITLE: DATE: ~ TIME: ~ SECTOR: j.

h. a pp k

[. t c- ~

EP-316, Rev. Page 30 of 6 DMR/nl 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 TOTAL PERIOD OF RELEASE. FOR LONG TERM RELEASE WITH CONSISTENT METEOROLOGY, THE TIME PERIOD CORRESPONDS WITH THE TOTAL PERIOD OF RELEASE. IF METEOROLOGY CHANGES P (I.E. WIND DIRECTION SHIFTS, ATMOSPHERIC STABILITY CHANGES, OR WIND SPEED CHANGES SIGNIFICANTLY), DIVIDE TBS RELEASE INTO SEGMENTS ACCORDING TO SUCH SHIFTS. b 1. For each release point, complete Worksheet 7 to calculatC thyroid doses at locations of interest. A. Record the release points on Worksheet 7 from Data Sheet 1. l ra B. Record the release data in Column A on Worksheet 7 J' $/ y from Data Sheet 1. r;: UA C. Record th'e vent flow rate from the appropriate F release point in cfm in Column B on Worksheet 7 from Data Sheet,1. 2. Determine the Iodine Inhalation and Ingestion Dose Factol by completing Worksheet 6 when an updated isotopic mix from sample analysis is known. If an updated isotopic mix is not available, and the iodine monitors are isolated, perform the following: r A. U1 or U2 South vent release - obtain noble gas ~ concentration from Worksheet 2 Column B. If ventingl through SGTS, divide noble gas concentration by 340.) C If not venting through SGTS, divide by 3.4. l l t B. North vent release - obtain noble gas release rate l from Data Sheet 1. Divide this value by the product l of 472 and the vent flow rate to obtain nchle gas l h 9 concentration. If venting through SGTS, divide nob 1< q, gas concentration by 340. If~not venting through l 7[. ri SGTS, divide by 3.4. 5;, If an updated isotopic mix is not available, but the icaine monitors are available, perform the following: C. Multiply gross I-131 concentration by the appropria@ I-133 factor based on time since reactor shutdown l identified in Table 316-K, to determine I-133 concentration.

• 4"9-d e

e e+

• g

> gh g a 4 _22

EP-316, Rev. Page 31 of 6-DMR/nl l TABLE 316-K I-133 FACTOR VS TIME SINCE REACTOR SHUTDOWN r lT= 0 hrs 1 hr 2 hrs 4 hrs' 8 hrs 12 hrs 16 hrs' 20 hrs 24 hrs I-133

2. 0 '

1.9 1.8 1.8 1.4 [ 1.4 1.2 1.1 1.0 7 ] Factor u' L n F 3. Complete Worksheet 7 to calcu' late thyroid dose at locations of interest. A. Recor'd the CHI /O dispersion factor from Worksheet 1 at each downward distance of L interest. ~~ \\ B. Record release duration from Data Sheet 1 and h enter in Column G of Worksheet 7. r C. Perform the calculations indicated on Worksheet! I 7 to obtain air concentration (Column E) and thd resultant thyroid doses (Column H). 4. Determine Thyroid' Man-Rem estimates by completing l Worksheet 8. Use Table 316-L population F~ distribution. (,,,- 2.3.2 Determination of Thyroid Dose from Field Survey Data s ,, ~. l '. Obtain I-131 concentration in air near plume ec kJ centerline from field survey data. u { ' 2. Calculate the inhalation dose rate. f Concentration (uci) X 1.692 P6 (Rem /hr) X 1.75 X Estimated = Dose (! cc uCI/cc Release 1 l Duration (hrs) Record this dose on Worksheet 8, at the appropriate distance and perform, Thyroid Man-Rem Estimates. u L-e

• p p

a es, - m amam a um ilma

l - '. 7 = r, # ", '~ ~ 7 (-iy?] ] P ~~ - r v. T r.5 C-v r-EP-316, Rev. Page 32 of 69 DMR/ nip WORKSHEET 6 (Section 2.3) IODINE INilALATION DOSE FACTORS ( uCi/cc I-131 x-1.692) + ( uCi/cc I-133 x 0.407) = uCi/cc I-131 + uCi/cc I-133 Inhalation Dose Factors (Rem-m3) I-131 1.692 uCl-br I-133 0.407 IODINE INGESTION DOSE FACTORS ( uCi/cc I-131 x 1.21 x P3) + ( uCi/cc I-133 x 11.2) = uCi/cc I-131 + uCi/cc I-133 Ingestion Dose Factors (Rem-m3) I-131 1.21 P3 uCi-hr I-133 11.2

,f+' P ~r p ] rr ; f.f%j.mn 7 - - i rm ' ' '- i .j 4 EP-316, Rev. Page 33 of 69 j DMR/ nip 1 l WORKSilEET 7 (Section 2.3) 3 CALCULATION TABLE - PLUME CENTERLINE GROUND LEVEL TilYROID DOSE AT LOCATIONS OF INTEREST WIND DIRECTION: degrees DEARING: degrees RELEASE POINT E X F X G = II A X B X C X D = l Distance Concen-Vent CllI/O Iodine Air From Release Inhalation (Miles) testion Flow Rate Dispersion Concentration Worksheet Duration Iodine /Dore (uC1/cc) (cfm) Factor (sec/m3) (uC1/m3) ( AxBxCxD) 6 Dose (iiour s) (Rem) Factor

• 0.5 472 2.0 472 5.0 472 10.0 172 Other 472 II E

X F X G = A X B X C X D = 4 Distance Concen-Vent CllI/O Iodine Air From Release Iodine Inges-(Miles) tration Flow Rate Dispersion Concentration Worksheet Duration tion Dose ** (uCi/cc) (cfm) Factor (sec/m3) (uC1/m3) ( AxBxCxD) 6 Dose (liours) (Rem) Factor

• f O.5 472 2.0 472 5.0 472 10.0 472 Other 472 1 Basis:

Centerline of release path only. These calculations are valid for a constant isotopic 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 been included in the ingestion dose factor.

All dose factors are derived from R.G. 1.109.

• • If November 1 through April 1 (non-grazing season) the ingestion dose is zero.

EP-316, Rev. Page 34 of 6 DMR/nl WORKSHEET 8 (Section 2.3) THYROID MAN-REM ESTIMATES THYROID DOSE (Rem) POPULATION LOCATION FROM COLUMN H IN BEARING f (MILES) WORKSHEET 7 X SECTOR MAN-REM = 0-1 1-2 2-3 3-4 r 4-5 5-10 I

• Use value at 7.0 mile distance IODINE r--

FIELD SURVEY uCI X 1.692 P6 X 1.75 X Estimated = INHALATION DOSE CONCENTRATION CC Release RATE (Rem) [^/ Duration (hours) l W N d NAME/ TITLE: DATE: TIME: SECTOR: (* l 6 9

] EP-316, ROV. Page 35 of f DMR/n1 2.4 GROUND DEPOSITION PER UNIT AREA 2.4.1 Assessment of Offsite Plume Centerline Deposition per Unit Area FOR " PUFF TYPE" RELEASES OR SHORT TERM RELEASES WITH f CONSISTENT METEOROLOGY, TIME PERIOD CORRESPONDS WITH THE TOTAL PERIOD OF RELEASE. FOR LONG TERM RELEASES WITH .? CONSISTENT METEOROLOGY, THE TIME PERIOD CORRESPONDS WITE r THE TOTAL PERIOD OF RELEASE. IF METEOROLOGY CHANGES (J (I.E. WIND DIRECTION SHIFTS, ATMOSPHERIC STABILITY t CHANGES, OR WIND SPEED CHANGES SIGNIFICANTLY) DIVIDE THE r RELEASE INTO SEGMENTS ACCORDING TO SUCH SHIFTS. I 1. Record the wind direction from Data Sheat 1 on WorksheeG l 9. Determine the direction toward which the wind is blowing (downwind sector) by adding 180 degrees to F average wind direction. If greater than 360 degrees, L aubtract 360 degreer from the sum. f. 2. Obtain the location of the farms of interest from the Environmental Sampling Coordinator. Select downwind b farms and enter distances from release points to these locations on Column A of Worksheet 9. 'h~~ 3. Enter the iodine air concentration values from Workshee9 7 Column E on Worksheet 9 Column B, C, or D, dependent upon the release point. 7-4. Enter estimated release duration from Data Sheet 1 in Column F of Worksheet 9. 5. Perform the operations indicated to obtain the plume [f centerline deposition per unit area (Column G) in Worksheet 9 in uCi/souare meters. f ? I 3 i .q \\ h 4

cr n e, t :.% l o EP-316, Rev. 3 i Page 36 of 69 DMR/ nip WORKSTIEET 9 (Section 2.4) PLUME CENTERLINE DEPOSITION PER UNIT AREA - (uCI/M2) c i WIND DIRECTION: degrees az BEARING: sector RELEASE POINT A B C D E l F l G* DEPOSITION RELEASE DEPOSITION IODINE AIR CONCENTRATION (uC1/m3) COLUMN E WORK' SHEET 7 1 VELOCITY DURATION PER UNIT AREA DISTANCE NORTH VENT Ul SOUTH VENT U2 SOUTli VENT (M/liR) (IfOURS) (UCI/M2) DOWNWIND 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36

• To calculate Col. G:

Assumes deposition velocity NAME/ TITLE: of 0.01 m/sec (36 m/hr) (B + C + D) xExF=G DATE: TIME:

s t EP-316, Rev. 3 Page 37 of 69 DMR/ nip TABLE 316-L l . POPULATION DISTRIBUTION O -10 MILES 1985 DISTANCE (MILES) 1: I I l Sector 0-1 1-2 2-3 3-4 4-5 5-10 10-Mile Total 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 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 11,028 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 SSW 12 656 331 551 288 1,986 3,824 SW 74 195 220 334 322 1,913 3,058 WSW 49 192 572 492 1,714 2,041 5,060 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 l Total 44'9 5,794 12,888 33,240 18,744 93,438 164,603 I f 9 8

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EP-316, Rev. 3 i Page 38 of 69 DMR/nlp l i APPENDIX EP-316-3

SUMMARY

SHEET sph 1.

a. Elevated wind speed deg a

b. Elevated wind direction

c. Stability class 5

2. Start Time of Release (military time) Actual or Estimate (Circle One) hrs 3. Expected Release Duration Yes/No 4. Calculated Data 1 a) Projected Wholc Body Dose (Worksheet 4) Attached b) Whole Body Man-Rem Estimates (Worksheet 5) Attached s 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) ~~ b) Thyroid Dose Rate (Data Attached) 6. Ground Deposition per Unit Area (Worksheet 9) Attached .EP 317 Recommendations: 1.0/1 gi .a i I

EP-316, Rev. 3 Page 39 of 69 APPENDIX EP-316-5 Chi /O Tables l DMR/nlp APPENDIX EP-316-4 CHI /O OVERLAYS The following figures display the Xu/Q overlays for both ground level and elevated releases. GROUND LEVEL OVERLAYS Figures 316-A through 316-G represent the ground level overlays in units of Xu/O (normalized for wind speed) for Pasquill stability Classes A through G, respectively. They should be applied for pure ground level releases and for the ground-level portion of a mixed mode release. ELEVATED OVERLAYS Figures 316-H through 316-DD represent the 23 elevated overlays in units of Xu/O. Tble 316-G identifies the elevated overlay selection process, which is a function of release point, vent flow rate, wind speed and stability class. They should be applied for pure elevated releases and for the elevated portion of a mixed mode I release. 9 i 1 I ~-- 9

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- - - ~~ L. -- ' _= l EP-318 Rev. 2 Face 1 Of 8 i 3850072920 ~ P"95 v^ y eq g',g5 l PHILADELPHIA ELECTRIC COMPANY j LIMERICK GENERAT!NG STATION f i EMERGENCY PLAN lMPLEMENTING PROCEDURE i ) i EP-318 LIQUID RELEASE DOSE CALCULATIONS METHOD FOR DRINKING WATER I 4 1.0 P1.RTICIPANTS 1.1 Dose Assessment Team shall perform,these calculations. l 4 t-2.0 ACTIONS-IMMEDIATE 2.1 The following assumptions werc utilized in this j i calculation: i 2.1.1 The Dose Conversion Factor is based on the most I limiting group (adult, teen, child, infant) using dose factors and consumption rates in Reg. Guide 1.109. 4 Adult 730 1/yr [ ] Teen 510 1/yr 1 Child 510 1/yr Infant 330 1/yr ] 2.1.2 The Decay Factor is based on the decay Of tne isotope l t over the transit time plus 12 hours (tice to reacn the } population via water system per Reg. Guide 1.,09). l 2.1.3 The total dose commitment is the dose wnien an 4 individual would receive after drinking wate witn tne radionuclides present at the concentrati: ale 21ated j to exist at the entrance to the water 'n ph a period equal to the duration of thef e Aror l example, if the release lastep M hou.c,ne I i individual is postulated an . L'2 cf his average daily water intaxe at : ed at inc fations. D i 2.2 DoseAssessmentTeamsh(fC y,,.p.. 6 i ..7 ,__._.v,.- ,v~.._,- ,...y. _,..., -. - -_..____..- _ - -,,

I EF-318 Rev. 2 Page 2 of 8 I VAW/JLP/rgs s 2.2.1 Obtain grab sample results on the concentration of Co-60, I-131, Cs-134 and Cs-137 released, from the Chemistry Sampling and Analysis Team Leader. l If the sample was taken prior to entering the Cooling l Tower Blowdown Line, a diluted concentration must be i determined by the following calculation: l Concentration (uCi) concentration x Release rate to Blowdown Line e I Released (c1 ) ( uCi) Blowdown line flow rate I (ce) 2.2.2 For each location of interest, enter the concentration of Co-60, I-131, Cs-134 and Cs-137 in uCi/cc released and the release duration in hours on the apprcpriate appendix. 2 2.2.3 Perform the calculation in eacn appendix fcr each location of interest to estimate the dose in millirem for the liver, wnole body and thyroid. 2.2.4 Report results to the Dose Assessment Team Leader. i 3.0 ACTIONS-FOLLOW-UP None 4 4 4.0 APPENDICES 4.1 EP-318-1 Citizen Utilities Home Water Company Intage 4.2 EP-318-2 Phoenixville Water Intake i 4.3 EP-318-3 Philadelphia Suburban Water Company Intake 4.4 EP-318-4 Norristown Water Intake 4.5 EP-318-5 Philadelphia Belmont Water Iratane f o I l

a- ^ - - - - - - - l EP-318 Rev. 2 Pace 3 of 8 i VA5/JLP/rgs 5.0

• SUPPORTING !NFORMATION 5.1 Purpose The purpose of this procedure is to provide the l

calculation method for estimates of individual 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 e.iver. 5.3 Special Ecuipment None l 5.4 Refecences 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, 1 Appendix I e 4 WW

I I l rP-318 Rev. 2 a Page 4 of 8 VAU/ MPG /mc l Appendix EP-318-1 Citizenn Utilition llome trater Company Intake _ (uCl) (mr/hr) Inotope concentration (cc ) xdone factor (uCi/cc) "xdecay factor =mr/hr [ Co-C0 959 1.0 l i g I-131 700 0.95 E Cs-134 ! 1.01P4 1.0 -og Cs-137 5942 1.0 dmr/hr) = nt/hr (whole hotly) l h Co-60 406 1.0 i g I-131 1591 0.95 3 d Cs-134 2.64P4 1.0 Cs-137 2.30P4 1.0 3 { I(a r/hr) = mr/hr (liver)_ N I-131 5.23P5 0.95 mr/hr(thyroid) Schuylkill River Relence !!itinej .l g k(ar/hr) x Usage Factor x Duration (hrc) x ra c t-> r = Doce (mr) p 6 1 0.40 0.0118 (whole body) U 0.48 O.0118 (liver) h g h pi 0.48 0.0118-(thyroid) [ P l Initials I Date 4 i

l[ l EP-310 Rev. 2 Page 5 of 8 l VAi!/f1PG/mc, l Ill l Appendix EP-318-2 Phoenixville 1:ater Intate (uci) (mr/hr) Icotope concentration (cc ) xdose factor (uci/cc) 'xdecay factor' =mr/hr Co-60 959 1.0 i x I-131 700 0.92 1 3 I Cs-134 1.01P4 1.0 t g Cs-137 5942 1.0 l*. I(mr/h r) = mr/hr (whole body) Co-60 406 1.0 j I-131 1591 0.92 l Cc-134 2.64P4 1.0 &" Cs-137 ' 2.30P4 1.0 l ,s ' Smr/hr) = mr/hr (l iver) 4 w { p I-131 5.23P5 0.92 mr/hr (thyroid) Schuylkill River Releace r11xing d 2 (mr/hr) x Usage ractor x nuration (hrn) x ractor Done (mr) =

i 1.0 0.0118 (whole body) 3 1.0 0.0118 (liver) h 1.0 0.0118 (thyroid) l Initials '

Date

l EP-318 Pev. 2 Page 6 of 8 i* VAW/f1PG/mc l l Appendix EP-318-3 Philadelphia suburban trater Company Intake l (uci) (nr/hr) Isotope concentration (ce ) xdose factor (uci/cc) 'xdecay factor' =mr/hr i i Co-60 959 1.0 l l ? I-131 700 0.90 t- . Cs-134 1.01P4 1.0 l e t 6 Cs-137 5942 1.0 l t limr/hr)= mr(whole body) l Co-60 406 1.0 l

s. 1-131 1

1591 0.90 E O Cs-134 2.64P4 1.0 Cs-137 2.30P4 1.0 m t j ((mr/hr) = mr/hr(liver) j+- h l I-131 5.23P5 0.90 nr/hr(thyroid) 6 i Schuylkill River Release 111 x ing i ad 1 (mr/hr) x Unage Factor x Duration (hrn)' x Pactor = Doce (mr)

n 0.22 0.0149 (whole body) g.

I 0.22 0.0149 (liver) s. 5 0.22 0.0149 (thyroid) l l Initials Date i

.__..____.__.____.___.__m._ .I ~ l EP-318 nov. 2 j Page 7 of 8 vat 1/t1PC/mc,l l Appendix EP-318-4 tbr r i ntown tra ter intate s t l (uci) (mr/hr) Isotope Concentration (cc ) xdone factor (ucl/cc) 'xdecay factor =mr/hr 6 i Co-60 959 1.0 o 4 'I-131 700 0.87 { e l Cs-134 1 1.01P4 1.0 e T \\ j Cs-137 5942 1.0 i 2(m r/h r) = mr/hr (whole body) i i Co-60 406 1.0 0.87 [ I-131 1591-I l 3 Cs-134 2.64P4 1.0 a Cs-137 2.30P4 1.0 I I 3 E(mr/hr) = mr/hr (l ive r) i o 1 % I-131 5.23P5 O.87 mr/hr(thyroid) ) l t Schuylkill niver Releace 111 x ing t g J (ar/hr) x Ucage Factor x Duration (hrn) x ractor = Dose (mr) .l 1.0 0.0091 (whole body) ,,, q u + 1.0 0.0091 (liver) { + f, ' : 1.0 0.0091 (thyroid) p lI 'Z l Initials Date rc ' '. i 4 l l

l l EP-318 Rev. 2 Page 8 of 8 VAU/!1PG/mc l Appendix EP-318-5 Philadelphia Belmont Uater Intake (uci) (mr/hr) Isotope Concentration (cc ) xdoce factor (uCi/cc) xdecay factor =mr/hr Co-60 959 1.0 l y I-131 700 0.80 o Cs-134 1.01P4 1.0 i o s 5 Cs-137 -5942 1.0 l Timr/hr) = mr/hr (whole body) h Co-60 406 1.0 I-131. 1591 0.80 I s., j Cs-134 2.64P4 1.0 Cs-137 2.30P4 1.0 e{ E(mr/hr) = mr/hr (1 ive r) A H I-131 5.23P5 O.80 mr/hr(thyroid) Schuylkill River Ecleace f*1xing 1 (mr/hr) am

Ucago Pactor x Duration (hrc) x Pactor Doce (mr)

= ~# .f g 1.0 0.0112 (whole body) I 1.0 0.0112 (liver) { A H -1.0 0.0112 (thyroid) l Initinic Date l .-}}