ML20041A092

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-101 Re Classification of Emergencies & EP-401 Re Entry for Emergency Repair Operations & Search & Rescue.Revised Index Encl
ML20041A092
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/04/1982
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20041A086 List:
References
PROC-820104-01, NUDOCS 8202190083
Download: ML20041A092 (46)
v • d • e


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EP Index EMERGENCY PLAN PROCEDURES INDEX -

M Page 1 PEACH BOTTO!! UNITS 2 AND 3

\v ls ih( - Rev. 8

  • 01'/04/82
  • ECEM Review Rev. Revision Number Title -

Date No. Date

. JAN 151982 t

, w. J. nWL ,

VEP-101 Classifi' cation of Emergencies 01/04/82 2 01/03/82

  • I EP-102 Unusual Event Immediate Actions 12/07/81 1 12/07/81 * ,

EP-103 Alert Immediate Actions ,

12/07/81 2 12/07/81

  • EP-104 Site Emergency Immediate  ;

. Actions 12/07/91 1 12/07/81

  • l
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EP-103 General Emergency Immediate Actions 12/07/81 1 12/07/81 1 i

. EP-201 Technical Support Center (TSC) I Activation 12/07/81 1 12/07/81

  • EP-202 Operational Support Center (OSC) Activation 12/07/81 1 12/0,7/81
  • l EP-203 Emergency Operations Facility (EOF) Activation 12/07/81 0 12/07/81
  • EP-205 Radiation Protection Team Activation 12/22/81 1 l'2/22/81 * '

EP-205A Chemistry Sampling and ,

Analysis Group 12/07/81 0 12/07/81

  • EP-205B Radiation Survey Groups 12/07/81 0 12/07/81 *

) EP-205C Personnel Dosimetry Bioassay and Respiratory Protection Group 12/07/81 0 12/07/81

  • l r EP-206 Fire and Damage Team Activation 12/07/81 2 12/07/81
  • EP-206A Fire Fighting Group 12/07/61 0 12/07/81
  • EP-206B Emergency Repair Group 12/07/81 0 12/07/81 *

? EP-207 Personnel Safety Team Activation 12/07/81 1 12/07/81

  • EP-207A Search and Rescue 12/07/81 0 12/07/81
  • EP-207B Personnel Assembly and Accountability 12/,07/81 0 12/07/81 * -

EP-207C First Aid 12/22/81 0 12/22/81

  • d P-207D , Personnel Monitoring and Decontamination 01/04/82 0 01/04/82 * ,,

8202190083 820211 PDR ADOCK 05000277 - '

F PDR -

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. _ - - - . - - - - - - - - - - - - - - - - - - - - 1

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  • Page 2 i -

?.. Rev, 8*

PEACH BOTTOM UNITS 2 AND 3 01'[04/82

  • Review Rev. Revision Number Title
  • Date' No. Date EP-208 Security Team 04/01/81 0 04/01/81 EP-209 Telephone List For Emergency Use 07/23/81 2 07/23/31 l EP-209 Immediate Notification Call List i Appendix A 11/02/81 3 11/02/81 EP-209 D'ELETED
  • Appendix B EP-209 Peach Bottom Station Supervision
  • Appendix C 11/19/81 3 12/07/81
  • EP-209 on Site Emergency Team Leaders Appendix D-1 11/19/81 2 10/16/81
  • EP-209 Radiation Survey Team -

Appendix D-2 10/16/81 2 10/16/81 EP-209 Fire and Damage Team Appendix D-3 10/16/81 2 10/16/81 EP-209 Personnel Safety Team Appendix D-4 10/16/81 2 10/16/91 EP-209 Security Team Appendix D-5

, 11/19/81 2 10/16/81

  • EP-209 Re-Entry and Recovery Team s.

Appendix D-6 11/02/81 1 11/02/81 EP-209 Technical Support Center Team Appendix D-7 11/02/81 2 11/02/81 EP-209 Corporate Emergency Team Leaders and Appendix'E Support Personnel 11/02/81

% 3 11/02/81 EP-209 U. S. Government Agencies

  • Appendix F 11/19/81 1 08/27/81
  • EP-209 Emergency Management Agencies Appendix G 10/16/81 2 10/16/81 EP-209 Company Consultants Appendix H

, 10/16/81 2 10/16/81 EP-209 Field Support Personnel .

Appendix I-1 -

11/02/81 3 11/02/81 EP-209 Rad Services Call List .

Appendix I-2

, 10/16/81 2 10/16/81

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EP Index Page 3 EMERGENCY PLAN PRCCEDURES INDEX ,

L

~), , ' PEACH BOTTOM UNITS 2 AND 0 b4 82

  • Review Rev. Revision

) Number Title -

Date No. Date EP-209 Nearby Public and Industrial Users Appendix J 08/27/81 1 08/27/81 EP-209 Miscellaneous Appendix K 08/27/81 1 08/27/81 EP-209 Local PECo Phones

. Appendix L 11/19/81 1 08/27/81

  • EP-209 Emergency Administrative and Logistics Appendix M Personnel ,

08/27/81 0 08/27/81 EP-209 Medical Support Groups Appendix N , 11/19/81 2 10/16/81

  • EP-301 Operating the Evacuation Alarm and Pond Page System 04/01/81 0 04/01/81 EP-303 Partial Plant Evacgation 12/22/81 1 12/22/81

.' EP-304 DELETED ,

EP-305 Site Evacuation 12/22/81 1 12/22/S1

  • EP-306 Evacuation of the Information Center 12/22/81 1 12/22/81 *

.. VEP-311

  • Handling Personnel with Serious Injuries, Radioactive Contamination Exposure, or Excessive Radiation 6

Exposure Emergency Director Functions 01/04/82 1 01/04/82

  • EP-312 Radioactive Liquid Release (Emergency Director Functions) 04/01/81 0 04/01/81

. i EP-316 Cumulative Population Dose Calculations 04/01/81 0 04/01/81 ,

. l EP-317 Direct Recommendations to County O Emergency Management Agencies 03/31/81 0 03/31/81 EP-320 Procedure for Leaking Chlorine

  • 04/01/81 0 04/01/81 KIP-401 Entry for Emergency Repair, Operations, and Search and J Rescue 01/04/82 1 01/p4/82
  • EP-500 Review and Revision of Emergency J Plan (FSAR Appendix 0) 04/01/81 0 04/01/81
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EP-101

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PHILADELPHIA ELECTRIC COMPANY

PEACH BOTTOM UNITS 2 AND 3 EMERGENCY PLAN IMPLEMENTING P ROCEDURE

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EP-101 CLASSIFICATION OF' EMERGENCIES PURPOSE To define the method of classification of an event or condition at the Peach Bottom Atomic Power Station into one of four emergency classifications as described in the Peach Bottom Atomic Power Station Emergency Plan.

REFERENCES

1. Peach Bottom Atomic Power Station Emergency Plan Section Title

, 4.1 Classification System

2. NUREG 0654 Criteria for Preparation and Evaluation'*of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power

. Plants.

3. EP 102, Unusual Event Immediate Actions

. 4. EP 103, Alert Immediate Actions

5. EP 104, Site Emergency Immediate Actions
6. EP 105, General Emergency Immediate Actions

. APPENDIX ,

EP 101-1 Classification Table ACTION LEVEL

  • 3 This procedure will be implamented whenever shift Supervision detects conditions which meet or exceed the Emergency Action Levels in Appendix EP 101-1, Classification Table.

IMPLEMENTATION OF THIS PROCEDURE DOES NOT CONSTITUTE IMPLEMENTATION OF THE EMERGENCY PLAN.

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Rev. 2 WJK:lhd PRECAUTIONS ,

THE JUDGEMENT OF THE EMERGENCY DIRECTOR IS VITAL IN PROPER CONTROL OF AN EMERGENCY AND MAY TAKE PRECEDENCE OVER GUIDANCE IN THE EMERGENCY PLAN IMPLEMENTING PROCEDURES.

IMMEDIATE ACTIONS ,

1.0 Shif t Supervision or Emergency Director shall:

1.1 Select affected categories related to station events or

-' conditions at this time.

Reference i

Pages in

- Appendix Category EP 101-1

1. Unplanned -

Shutdown 1, 2, & 3

2. Personnel Injury 3&4
3. Primary Contain- .

. ment Integrity 4,5,6,& 7

4. Radioactive 7, 8, 9, & 10 Material Release ,
5. Fire 10, 11, & 12
6. Environmental 12, 13, 14, & 15
7. Loss of Power 16, 17, & 18 e

9

8. Secondary .

Containment 19

9. Instrument Failure 19
10. Fuel Damage 19, 20, & 21 3* 11. Hazards to Station -

21 & 22 Operation

> 12. Control Room .

Evacuation 22 & 23

^

3 13. Security

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ER-101 3

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^1.2 Beginning at the indicated page in Appendix EP 101-1, review the Emergency Action Levels for all categories selected above.

1.3 If the most severe events or conditions'are classified .'

as an Unusual Event, implcment EP 102, " Unusual Event Immediate Actions." ,

1.4 'If the most severe events or conditions are classified 4

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as'an Alert, implement EP 103, " Alert Immediate Actions."

1.5 If the most severe events or conditions are classified

< as a Site Emergency, implement EP 104, " Site Emergency Immediate Actions."

~ 1.6 If the most severe events or conditions are classified as a General Emergency, implement EP 105, " General EmergencyeImmediate Actions." ,

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- APPEhDIE EP.101 1 Page 1 og 23,Rev.3.

INTERREIATIONSHIP BRIWEEN INCIDD.'TS AND EMERGENCY ACTIONS Plant Staff Offsite Licensee Support Response State and local Government Notification Response _ _

  • Emergency Action Level Class Response _

.- k nt Jap 1 ened None shutdown None None EP-102 c1) controlled The process of shut- Unusual Correct Event the op-chutdown ting down the Unit du) to condition None failura to. None None .

mest L.C.O. Unusual Invt.atigate EP-102 c2)cny Ecram Scram Alarm Event cause of oth:r than scram. Deter-mine status ,

of plant safety sys- ,

tems.

Near Site EOC set up.

EP-103 Technical Sup- Manager - Elec. Bureau of Radiation Pro-Alert GP-3 rort Center set Prod. reportsEmer-to b1) scram with 1) scram alarm and E-26 Headquarters tection contacts triple low .2 ) double low lefe'l up. Assist gency Control Center. facility for technical EP-103 Icv;,1-no alarm (-48") and -

shift to News Center set up. data.

LOCA indi *3) triple low le' vet . investigate

  • c:ted salarm (-130") and~ equipment
  • 4) incrense in cont ainment pressure failure.

to greater than 1 psig but less

.' than 2 psig on

- PR-2/3508 7.

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- - APPENDIX EF-101 1 INTERRETATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS

'Page 2 of 2 3, Rev. A -

Licensee Plant Staff Offsite Emergency Action Imvel Class Response Notification Response Support Response. State and local Government Event Alert GP-3 EP-103 Technical Manager - Elec. Near site EOC set up.

t;2) unplanned 1) scram alarm M Prod. reports to Bureau of Radiation fro-

', scram and 2) double low level E-25 Support Cen-

  • alarm (-48*) and EP-103 ter set up. Ileadquarters Emer- tection contacts facility IDCA for technical data.
3) triple low le M Assist shift gency Control Cen-

$ (small to investigate ter. News Center Isak) alarm (-130") and,

4) containment high equipment set up.

. pressure alarm failure.

(2 psig) ag

5) containment press-ure 2 psig or grea-ter but less than 10 psig on PR 2/3508
6) tnplanned n
1) scram alarm a_nd Site 2-14 EP-104 Technical
  • Manager - Elec. Near site EOC set up.

scram and 2) double low level Emergency 1) Observe Support Cen- Prod. reports to Bureau of Radiation Pro-IDCA - alarm (-48*) aj rad off- ter set up. Headquarters Emer- tection contacts facility ECCS oper- 3) triple low level luent in- Assist shift gency Control Cen- for technical data.

cting klarm (-130*) and,. strumentation to investigate ter. SOP set up.

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4 containment high 2) Evacuate non- equipment News Center set up. .

pressure alarm essential failure.

_ ._12. P8_i3) and _ ... . personnel Analyze actual 5a) containment pres- or potential sure 10 psig or consequences greater but less of radioactive

  • than 20 psig on release. .

PR 2/3508 or

' A5b) containmenTdose ,a s q ragegreaterthan 10 R/hr on RI-8/9103A/C e

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APPENDII EP.101 1 INTERRELATIONSHIP BETWEEN IWC1 DENTS AND EMERGENCY ACTIONS Page 3 of 23 hv@

Licensee Plant Staff Offsite Emergency Action Imvel Class Response Notification Rerponse Support Response State and Tocal Covernment Event General E-26 EP-135 Technical Manager - Elec. Near site EOC set up.

  • d) acram with 1) scram alarm a_n_d Support Cen- Prod. reports to Bureau of Radiation Pro-failure of 2) double low level Emergency ter set up. Headquarters Emer- tection contacts facility e ICCS to alarm (-48*) and Assist shift gency Control Cen- for technical data, I recover or 3) triple low le M alarm (-130*) and to investigate ter. E0F set up.

maintain equipment fail-News Ceater set up.

1sval and *

4) active fuel range ure. Analyze LOCA 1evel indication shows less than actual or po-

-226' on LI-2/3 t(ntial conse-3-91A,D and quences of radioactive

5) failure W reset release. Con-I triple low level duct radiation I alarm after 3 min-utes and area surveys ,

f 6) conta M ent high around the e pressure alarm P l ant.

l (2 psig) and,

  • t 7) c

,ontainment pres- *

  • , sure greater than l 20 psig on PR-2/3308
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  • 8) M tainment dose

< rate greater.than 104 R/hr on Rg-8/9103 A/C .

. and RI-8/9103 U/D .

I J 2. Personnel' Imjury 3

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  • c) injurice Verbal reports or Unusual Activate EP-1C2 Consult with Incal physician None ,

j requiring direct observation Event Personnel PECO Medical may report to the

  • transport safety Team. Director if facility.

{ via ambu- Prepare in- required.

1ance to jured for "

  • offsite . transport i medical fac- to offsite 7 ility for medical

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. treatment for facility.

greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

  • Pending Installation & Calibration cf Containment Monitors  ;,, ;, ,,. .-._ -- _ ,g

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  • Tage 4 of 23e .A INTERRELATIONSHIP BETWEEN INCIDLHTS AND EMERGENCY ACTIONS 7lant Staff offsite.

Licersee. Support Response State and Iocal Government Class Response Notification Response _

_Eutergency Action IAvel None M Consult with Local physician may Unusual As above EP-102 PECO Hedical report to the facility.

b) I2jrry in. 1) Injury offsitewarrantingmedical Event plus per-Director RMC consulted.

~ involving form pre-cucecs treatment and liminary rrdis-

2) an acute wEoTe body decontam-tion ex- exposure greater ination porure than 3 rem or con- .

teszina-tion

. Primary Con- .

tainment '* '

Intsgrity 15one Assist shift

01) nrn-
1) Primary containment Unusual 1) mine deter-of- in search for leskrate is greater Event leak icolable fect of Isakage then 0.5 percent of leakage when volume per 24 hre. on plant primary at 49.1 psig or status contai- I) If N makeup y system *
2) observe ment i's not capable of containment:

integrity , maintaining pressure a) pressure required (not due to lack of b) oxygen con-N). y ', centration .

  • c) dose rate
3) shutdown Unit if warranted .

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APPDOII EP.101 1 INTERREIATIONSHIP BEDIEEN INCIDENTS AND EMERCENCY ACTIONS Page 5 of 23, Rev. S Licensee Plant Staff Offsite Emergency Action Level Class Response Notiff. cation Response Support Response State 'and local Government Ev nt EP-102 Assist shift None None

'd2)feilure to incorrect valve pos- Unusual 1) isolate manually - in investigating isolate any ition during Group I, Event

2) observe reason for p imtration II, or III iso- failure whsn auto. lation alarms contain-icoletinn ment al pressure to initia-

c) dose rate

3) shut down Unit if warranted Technical Manager - Elec. Near Site EOC set up.

' b) 1000 of 1) Reactor Building Alert 1)Jetermine EP-103 Bureau of Radiation Pro-vent rad affluent location of Support Center Prod. reports to primary cintain- . high rad alarm and' breach and set up. Assist Headquarters Emer- taction contacts facility

- 2) Inability to main: . 1solate shift in in- gency Control Cen- for techni:a1 data, ment in- vestigation of ter. News Center tngrity tain pressure greater 2) observe con- .

whan pri- - than 0.25 psig on par- tainment leakage. set up.

mary con

  • row range PR-2/3508 al pressure teinment or b) oxygen intsgrity 3) Torus Room flood concent-io rsquired- alarm with level de- ration crease in torus c) dose rate
3) shut down Unit if warranted o

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APPEND 1I EP-101-1 INTERREIATIONSHIP BETWEEN INOIDENTS AND EMERGENCY ACTICNS Page 6 of 23. Rev. 3 Licensee Plant Staff Offsite Event Emergency Action I4 vel Class Response Notification Response Support Response Stat _e and Incal Government 6111 m of The correct combina- Site E-3, EP-104 Technical Manager - Elec. Near site EOC net up.

primary tion of the.following Emergency E-6, Support Cen- Prod, reports to Dureau of Radiation Pro- .

conditions: E-25, or ter set up. Headquarters Emer- tection contacts facility contain-ment int- E-26 Perform Dose gency Control Cen- for technical data.

Ggrity 1) erratic containment 07-3 Assessment. ter. EOF set up.

with LOCA pressure fluctua- News Center set up.

tions above alarm setpoints of 1.5 psig And

2) Group II and III iso-lation alarms, g.nd
  • 3) Containment dost rate .

greater than 10J R/hr on RI-8/9103A/C and .

RI-8/9103B/D aj

  • 4m) Reactor Building area high tenperature .

alarm, gr

.b) Area Radiation Monit- -

ors on RR 2/3-18-55

- ' abnormally high, g.nj -

Sa) Reactor Building vent rad effluent high alarm, 12 I

. b) Main Stack Rad effluent *

., on RR O-17-051 increasing '

due to SGTS operation.

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i APPENDIX EP-101-1 Page 7 of 23. Rev.JL INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Response Support Response State and 14 cal Covernment

? vert Emergency Action 14 vel Class Response Notification Manager - Elec. Near site EOC set up.

c2)Mtential 1) containment high Site 1107-3 EP-104 Technical

  • Support Cen- Prod. reports to Bureau of Radiation Pro-

' 1cco cf pressure alarm Emergency 210T-45 Headquarters Emer- tection contacts facility.

3) Determine ter set up.

3rimary (1.5 peig), a_nd, gency Control Cen- for technical data.

21 scram, and_ location Perform Dose rentsin- of breach assessment, ter. EOF set up.

ent inte *3) containment dose & isolate Perform Dose Assess-9rity with ragegreaterthan 10 R/hr on ment.

> t.igh pri-nary con- RI-B/9103A/C and toinment RI-8/9103E/D, and rcdistion 4) Reactor Buildi W Area Rad Monitors Alarming, and ,

5)Feiit Stack Rad Effluent monitor high alarm .

> Radioactive Mat". rial Re-1r.4co EP-102 None None None 01)In tant- 1)A spike ** on rad Unusual OT-44 or anscus re-

  • ef fluent monitors: . Event OT-45 * '

leaco ex- ~ al' Main Stack great 3 cxding er than 4.4 x 10 cps T2chnical on RR 0-17-051, pr Specifi- bl. Reactor Build,ing cation

  • vent gfeater than 3x 10 cpm on RR- ,

liisit s .

2/3979 or

2) Analysis of particu-late filters or char-
  • coal cartridge
  • a) Main Stack greater '

than 5 x 10 1uCi/ sec d2I ,'

b) Reactor Building ,

vertt greater than 4 x 10I uC1/sec *

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Pending Installation & Calibration of Containment Monitors '

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INTERREIATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Support Response State and local Governnet Event Einergency Action Level Clasa Response Notification Response EP-102 None None None A report of the summa- IJnusual Investigate a2) Releale creceding tion of individual re- Event source of ths Tech- lease data within the release. Op-

  • Eics1 Spec-~ quarterly period. erste to re-ifiestion duce the re-quartsrly a lease within 11:it limits
1) Uncontrollable release, Alert OT-44 or EP-103 Technical Support Manager - Elec. Near site EOC set up.

2 b).Actu,1 0T-45 Center set up. Prod, reports to Bureau of Radiation Pro .

ar po- for more than 20 min- Assist shift steadquarters Emer. tection contacts facility Activate testict utes, from the:

Radiation Pro- to investigate gency Control Cen- for technical data. Dis-rsiscso a) Main stack greater ter. News Center patch survey teams to ob-than 1.2x1@ cps on tection Team source of re- ,

that gives to monitor lease and in set up. tain radiation data near doao af RR 0-17-051 or site. Initiate public b) Reactor Building vent in-plant and assessment of 0.01 ree radiological notification.

whoto greater than 3.44 x plume path, consequences.

body cr god cpm on RR-2/3979 Augment shift

. 05 <res *

,. or

  • in evacuation to thy- 2) @ ntinued particulate and personnel .

told *

. .or iodine release such accountability ,

that analysis of particu- efforts, late filter or charcoal cartridge resulth in the

. following specifig .

activities:

a) Hain stack greater than 4.7x10 uC1/sec or b) Reactor Building .,

vent greater than .

1.23x104 uC1/sec or -

  • 3) Containment dose rat T l greater than 10 2 R/hr
  • j on RI-8/9103 A/C and  ; ,

. RI-8/9103 S/D

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APPt.NDIX El-101 Page 9 of 23. Rev. 2.

INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Emergency Action h vel Class Response Notification Response Support Fesponse State ani Eocal Governswsst Event-e) Actus1 of 1) Uncontrollable release, Site Acticate EP-104 Technical Sup- Hanager - Elec. Near site EOC set up.

potentist for more than 20 minutes. Emer- Radiation port Center Prod. reports to Head. Bureau of Radiation Pro-r:1:sse from the: gency Protection set up. Assist quarters Emergency tection contacts facility Team to shift to in- Control Center. EOF for technical data.

that gives a)Mainstackgreater monitor in- vestigate set up. News Center Initiate public notification.

. doso of than 1.2x10 cps on Dispatch survey temas to ob-0.1 res RR 0-17-051 or plant and source of set up.

plume path, release and tain radiation data near site, thole b) Reactor BuilTing body or vent greater than Evacuate non- in assessment Bureau of Radiation Protection 0.5 rea 3.44x105 cpm on essential, of radiological recommends protective actions.

to thy. RR-2/3979 or plant per- consequences. Count ses impicment recommend-roid 2) Continued particulate sonnel. Ac- Augment shift ations.

or todine release such tivate Per- in evacuation that analysis of partic- sonnel Safe- and personnet

  • ulate filter or ty Tean. accountability charcoal cartridge re. OT-44 or efforts.

suits in the following 0T-45 -

specific activities: EP-317 e

a)Hainstackgreater

, than 4.7x10 uCi/sec

- or b) Reactor Bdilding vent greater than 1.23 x 105 uC1'/sec

  • or *

, *3) Containment dose rate greater than 103 R/hr on RI-8/9103 A/C and ,,

RI-8/9103 B/D ,

  • Pending installation 4 calibration of containment monitors -

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APPEND 11 EP.101-1 Page 10 of 23, Rev. A INTEFRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite .

Bnergency Action Emvel Class Response Notification Response Support Response State and local Covernment.

Event General Investigate EP-105 Technical Sup- ECF set up. Deter. Near site EOC set up.

d) Actual or 1) Uncontrollable release,lbsergency mine need for off- Bureau of Radiation Pro-potential .for more than 20 source of port Center release, set up. Assist site support. Har- tection contacts facility r:ltas' minutes. from the: shift to in- ager - Elec. Prod. for technical data. Initiate that gives a) Main Stack greater than Activate dose of 1  !.2x105 cps on Radiation vestigate source reports to Head- public notification. Dispatch j of release and quarters Emergency survey teams to obtain rem Whole RR 0 17-051 or Protection Body or 5 . b) Reactor Buil Hng Team to son. In assessment Control Center. Ac- radiation data near site.

r2o Thy- vent greater than itor in-plant of radiological quire offsite sup- Eureau of Radiation Pro-rold 3.44x106cpm on RR 2/3979 or- and plume consequences. port deemed necess- tection recoemends

2) Continued particulate path. Evacuate Augment shift ary. News Center Protective Actions.

or lodine release such non-essential in evacuation set up. Counties implement that analysis of partic- plant personnel, and personnel reconenenda t io ns.

utste filter or char- Activate Per- accountability coal cartridge results sonnel Safety efforts. ,

in the following Team.

specific activities: EP-317 0T-44 or m)Mainstackgreater 0T-45 than 4.7x10 uC1/sec or~

  • 17) Reactor Building vent greater than
  • 8 1.23:106 uCi/sec or )
  1. 3) Containment dose rat T greater than 10 4 R/hr on RI-8/9103 A/C and .

RI-8/9103 g/o

5) Fire -

t i) fire in protected Alarm and verbal report from SSV Unusual Event Shift fire team Sta. Supt.

Load Disp.

Notify local fire fighting Local fire fight-ing support organ-None croo last- Fight fire NRC support organ- irations stand by -

ing 10 min. PEM inations to to lend assistance.

sr more . YorkEm stand by if  ;

Manager - necessary

  • i Corp. Como.

.4*

  • Pending installation 4 calibration of containment monitors e

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APPENDIX EP-101-1 Page 11 of 23, Rev. .L INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Extergency Action Level Class Response Notification Response Support Response State and local Government Eve *t Fire alors and verbal Consider EP-103 Technical Sup- local fire fighting Near site EOC set up.

b) fire which Alert shut down port Center set organizations res- thJreau of Radiation Pro-could prevent , report from SSV en ECC with avail- up. Request pond as necessary. tection contact s f acility systes(s) from able equip- local fire Manager - Elec. for technical data.

ment. fighting organ- Prod. reports to me:tirs its Shift fire 1:ations to lleadquarters Emer-

. functional .

brigade assist in fire gency Control requiremedts

- fight fire, fighting if nec- Center. News Center-activate essary, set up.

Personnel Safety Team Fire alars and verbal . Site Consider shut EP-104 Technical Sup- local fire fighting Near site EOC set up.

s) fire which Emer- down with port Center set

  • organizations res- Bureau of Radiation Pre-prevents an report from SSV ECC systee(s) gency available up. Request pond. Manager - Elec. tection contacts facility froe meeting equipment local fire Prod. reports to for technical data. Initiate its funct-fighting organ- Headquarters Emer- public notification. Bureau tonal require ' - inations to gency Control Con- of Radiation Protection ments assist in fire ter. EOF set up. recommends Protective Actions.

. fighting if nec- News Center set up. Counties implement Protective

.essary. Augment Actions.

shift in evacu-

'. stion and ac-g countability efforts. ,

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APPENDIX EP-101-1 Page 12 of 23, Rev. a.

INTERREI.ATIONSHIP BEWEEN INCIDENTS AND EMERCENCY ACTIONS Plant Staff Offsite Licensee Support Response State and local Governnw.mt

Response

twent Ibaergency Action Imvel class Response Notification _

Technical Sup. Local fire fighting Near site EOC set up. .

Fire alarm and verbal Ceneral Shut down. EP-105 d) fise which port Center ornnizations res- Bureau of Radiation Pro-cauros dam- report from SSV.-and ' Emergency Verify avail-able isola- set up. Request po..d. Hanager - Elec. tection contacts fa-111ty rg3 to plant 1DCA symptoms. ECCS, or tions. Use local fire Prod. reports to for technical data. Initiate systems suf- containment failure. available core fighting organ- Headquarters Emer- public notification. Bureau of ficient to cooling cap- irations to gency Control Cen- Radiation Protection reconsends 1ead to ability. assist in fire ter. LOF set up. Protective Actions. Counties athIr gen. e fighting. Aug. News Center set up, implement Protective Actions, cr21 eser- ment shift in Near site LOC set up.

gencies evacuation and accountability efforts.

6.Bavironmental EP-102 None None None An actual earthquake Unusual SE-S c!) Earthquake detected by seismic Event instrumentation .

Iyst. ems.

Hone None Nome Conowingo Pond level* on Unusual SE-3 EP-102 a2) Abnormal Pond level L1-2/ 3278A,B,C ,

Event

1) greater than 113 ' ,g .

feet (C.D.), of .

2)1ess than 104

_ feet _(C.D.1 ,.

.i' without prior l<

.. notification by *

,e L.D. ,

e

. .8'

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APPDdDIX EP-101 1 Page 13 of 23. Rev.3.

INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Plant Staff Offsite Licensee Support Response ' State ' end Incal Government

Response

. Event Emergency Action Imvel Class Response Notification EP-102 Assist in the None None a3) TIrrado A tornado is observed on tfnusus! Inspect sta-site. Event tion for inspection of

, damage. Re- the station for

. pair any, damage. Assist

  • damage, in any repairs.

Shift Supervision be. Unusual Prepare sta- EP-102 Assit in pre- None NearsiteEOCsetupf

, a4) Itsrricane 11 eves a hurricane la Event tion building paring the sta-espected to cross the for high winds. tion and moving

+ station Move equipment equipment into buildings ,

(portable gen- i erators, trash ,

cans., barricades, .

i ,

etc)

An actual earthquake boyb Alert SE-5 EP-103 Technical Sup- Nanager.- Elec. Near site E0C set up b1) Barthquake Bureau of Radiation Pre-beyond un- the Operating Basis Earth- ,

port Center set Prod, reports to ,

usu21 event quake (OBE) levels, as in- up. Assist in Headquarters Emer- tection contacts facility Irvsts dicated by alarm. .

the station in- gency Control Cen- for technical data.

s spection and re- ter. News Center

\ pair. set up, Conowingo Pond level on Alert SE-3 EP-IC3 Technical Sup- Manager - Elec. Near Site EOC set up.

b2) Abnormal port Center Prod. reports to Bureau of Radiation Pro-Pind 1.evel L1-2/ 3278 A,8,C *'

bey:nd un- 1) greater than 115 set up. Headquarters Emer- tection contacts facility ,

usual event feet (C.D.), og gency Control Cen- for technical data. ** .

Itv31s 2) less than 98.5 ter. News Center  !

feet (C.D.)

  • set up.

.without prior notifi-cation by L.D. ,

s. 4' i
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APPENDIX EP-101 1 INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Page 14 of 23. Rev. A Licensee . Plant Staff Offsite Event Einergency Action favel Class Response Notification Response Support Response

  • State and focal Government
b3) Tornado A tornado strikes the Alert lionitor EP-103 , Technical Sup- Hanager - Elec. Near site EOC set up.

beyond Power Block with station for port Center set Prod. reports to Bureau of Radiation Pro-unusual identifiable plant abnormal- up. Assist fleadquarters Emer- tection contacts facility ev:nt damage ities and , Shift investi- gency Control for technical data.

levels damage. Acti- gate damage and Center. News vate Per- assessment of Center set up.

. sonnel Safety radiological Team. consequences.

Augments shift in evacuation and account-i ability efforts.

-b4)ltarrirame Station is orperiencing Alert Monitor EP-103 Technical Sup. Hansger - Elec. Near site EOC set up, beyond un- a hurricane with winds station for port Center set

  • Prod, reports to Bureau of Radiation Pre-usual greater than 100 mph abnormal. up. Assist Headquarters Emer- . tection contacts facility event . itles and shft in monit- gency Control Cen- for technical data.

Iowels damage. Acti- oring the sta- ter. News Center vate Per- tion for ab- s et up.

. sonnel Safety '

normalities and -

a Team. damage. .

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APPENDIX EP-101 1 INTERRELATIONSHIP BETWEEN INCIDENTS AND EMEPGENCY ACTIONS Page 25 of 23. Rev.1 Licensee Plant Staff Offsite tv nt Emergency Action Level Class Response Notification Response Support Response State and 1xal Covernment

41) E;rthquake An earthquake greater Site SE-5 EP-104 Technical Sup. Manager - Elec. Near site EOC set up.

beyond Alert than Design Earthquale Emergency port Center Prod. reports to Bureau of Radiation Pro-1sysla as detected on seismic set up. Assist Headquarters Emer- tection contacts facility instruments shift in in. gency Control Cen- for technical data.

specting sta- ter. EOF set up.

tion for dam. News Center set up.

age. Assist in repair of dam-age. Assist in evacuation and accountability efforts.

c2), Absoraal Conowingo Pond level on Site SE-3 EP-104 Technical Sup. Manager - Elec. Near alte EOC set up.

Fond level L1-2/3278A.B.C exceeding Energency port Center . Prod. reports to Bureau of Radiation Pro-beyond the following 11mits: set up. Headquartera Baer- tection contacts facility Alcrt 1) greater than 116 gency Control Con- for technical data.

levels feet (C.D.) or ter. EOF set up.

.2) less than af Teet News Center set up.

. (C.D.) .

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APPflelX hP-101-1

, Page 16 of 23, a v, g ,

INTERRELATIONSHIP BENEEN INCIDENTS AND EMERGENCY ACTIONS Plant Staff Offsite Licensee Support Response State and focal Government

Response

twent Einergency Action IAvel Class Response Notification 7.14ss of Power None None None

1) turbine generator trip Unusual E-10 EP-102 c) Imss of cffsite with Startup Auxiliary Event power transformer SU2 and sources or SU3 unavailable for

. ons.It s ,

service for more than power esp- 60 seconds or a.bility 2) 1.oss of voltage on the four 4160 volt emer-gency busses or 480 ,

volt load center sup-plied from the four 4160 volt emergency ~

busses for more than 60 seconds.

E-10 EP-103 Technical Sup- Manager - Elec. Near site EOC set up. .

b1) Imse of 1) turbine generator trip Alert port Center set Prod. reports to Eureau of Radiation Pro-cffsite with Startup Auxiliary Headquarters Emer- tection contacts facility transformer SU2 and . up.

power and ,

gency Control Cen- for technical data. .

loss of $43 unavailable for ter. News Center

-l all onsite. service and set up.

, AC Power 2) failure W ay diesel for less generators to energize

l than 15 their respective busses
  • i l minutes .

I i l If conditions

  • s l 1) and 2) ,

{ ~ esi E for more ;e than 15 minutes.. ,

e s this is a Site .

Emergency, see

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APPENDIX EP-101-l' Page 17 of 23, now,3, DtTERREIATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offaite Baergency Action 14 vel Class Response Notification Response Support Response State and Iocal Goverrueent Event EP-103 Technical Sup. Hansger - Elec. Near site EOC set up.

b2) less of 1) Less than 105 Volts on Alert Bureau .of Radiation Pro.

c!! DC the 2/3A,B,C 4 D distrib- port Center Prod. reports to set up. Headquarter s Emer- tection contacts facility power for ution panels as indi-for technical data.

1:ss than cated on Panels 2/3ALO3, gency Control Con-15 minutes 2/3cD03, 2/3BD03, ter. News Center 2/3DD03 and set up.

If cond!- {} Less tha D 1 Volts on tit,ns 1) the 24 Volt distribu-rnd 2) tion panels as indt.

TEJ 3) cated on Panels '

ExTit for 2/3AD28, 2/scD2a, larger 2/3BD28, 2/3DD28 and ~'

than 15 3) less of all alarms cinutes, .

. this is s

~ o Site Emir.

g1ncy.

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APPENDIX EP-101 1 Page 18 of 23. Rev. A INTERRELATIONSHIP BEWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Emergency Action Imvel Class Response Notification Response Support Response State 'and local'Covernment Event pt) less of 1) turbine generator trip Site E-10 EP-104 Technical Sup- Manager - Elec. Near site EOC set up.

cfflite with SU2 and SU3 un- Emergency port Center Prod. reports to Bureau of R4Jiation Pro-pow:r and svellable for service set up. Headquarters Emer- tection contacts facility itss of for longer than 15 gency Control for technical data.

cll casite minutes and Center. EOF set up.

AC power 2) Failure oT~alil diesel News Center set up.

far longer - generators to th:n 15 energize their re-cinutes spective tusses for longer than 15 minutes .

c2) Imse of 1) Less than 105 Volts on Site Technical Sup- Manager - Elec. Near site EOC set up.

oil 125 the 2/34,8,C 4 D Emergency port Center , Prod. reports to Bureau of Radiation Pro.

VDC power distributian panela set up. Headquarters Emer- tection contacts facility fJr longer as indicated on Panels gency Control Con- for technical data, than 15 2/3AD03, 2/3CD03, ter. EOF set up.

minutes 2/3BD03, 2/30D03 for News Center set up.

longer than 15 minutes and *

3) UTs than 21 Volts on the 24 Volt distrilu-tion panels as indi-  ;

cated on Panels s

. 2/3AD28, 2/3CD28, ,

  • 2/3BD28, 2/3DD28 .

for longer than 15

. minutes and

3) 1.oss of aIT alarms
  • for longer than 15 -

minutes -

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APPEND 11 EP.101-1 Page 19 of 23 , Rev. 3, INTERRELATIONSHIP BETWEEN II/CIDENTS AND EMERGENCY ACTIONS Plant Staff offsite Licensee State and tocal Government Response ___ 5_upport Response

" Event . . . Emergency Action Level Class Response Notification 6

,S. Secondary Cee-tainment In-t:grity lione None t.ons of Secondary Coa- Ifnusual CT-49 EP-102 Assist in c) 1.oss of evaluation ark!

Secondary tainment Integrity for Event repair o f

  • Containment greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, damage.

Integrity When Socord ary Contalnment Integrity required

  • None None
1) Complete loss of all Unusual EP-102 9.1:stnment ,

e Failure Main Control Roce Event communication equip- .

s) Signifi- ment cant loss

  • I a.f assess. * .

a cent or cos- ,

a munication .

I capability ,

! in the Main ',

Control Room. g

10. Fu;1 Damage Cf-10 EP-102 A 9e . home

'c) Possible 1) Air ejector discharge Unusual

  • fuel rad monitor high Event l' damage alarm and an increase *

. of 500 mR/hr within -

30 minutes or a level ,

  • of 2.5 x 103 mR/hr as *.

! Andicated on RR 2/3-17-152, or, i*

2) Iligh reactor coolant .e
  • g'.

activity as determined

' by sample analysia 'e g

equal to or greater - ,

. than 3 uC1/gm dose equivalent 1-131

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n APPENDIX tr-101-1 Page 20 of 23, Rev. 3 INTERRELATIONSHIP BEWEEN INCIDENTS AND EMERGENCY ACTIONS Plant Staff Offsite Licensee Response Support Response ' State and focal Government Event Emergency Action Level class Response Notification Manager - Elec. Near site EOC set up. BRP OT-10 EP-103 Technical b) Puel 1) Air ejector discharge Alert Support Center Prod. reports to contacts facility for rad monitor indicating 07-5 Headquarters technical data, Damage set up.

greater than 2.5 x 10 4 Emergency Control mR/hr on RR 2/3-17-152 Center. News

.-- or Center set up.

2a) lifgh coolant activity

- of 30 uC1/gu dose (

equivalent 1-131, and 2b)HainSteamLinehlF high radiation alarm

  • with resultant scram or alara, fG 1 bundle
3) Spent damage resulting in a ,

refueling floor area indiation or high radiation alora on fuel pool vent plenum r'ad monitor

  • EP-104 Technical Manager - Elec. Near site ECC set up, Site GP-4 BRP contacts facility .

Emergency Support Center Prod. reports to e) Puel )) Fb11owing conditions E-5.

set up. lleadquarters for technical data.

Damage in occur: Emergency Control (acts 3 of a. Failure of control Center. EOF set

  • Alert rods to fully insert up. News Center on a scram and ,

levsts . set up. ,

b. Higher than3rnal readings on LPRM's

. adjacent to not-

  • fully-inserted rods and *

+e

c. High Coolant activit f -

as determined by sample analysis equal -

to or greater than .

300 uC1/gm dose . . .

! equivalent 1-131 **

or o .-

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APPEND 11 EP-101 1 Page 21 of 23, Rev. S.

INTERREIATIONSHIP BETWEEN INCIDENTS AND EMEitGENCY ACTIONS Licensee Plant Staff Offsite Support Response State 'and local Government tv-nt Einergency Action I4 vel Claes Response Notification ye ynne

2) Najor damage to spent Site CP-4 EP-104 Technical Sup. Manager - Elec. Prod. Near site EOC set up fuel in fuel poc! or Emergency E.5 port Center reports to Head- BRP contacts facility set up. quarters Emergency for technical data, un:overing of spent fuel as confirmed by Control Center.

a fuel pool ares EOF set up. News Cent er set up.

radiation monitor ,

, , alarm and:

a. Refuel floor exhaust radiation monitor high alarm. or
b. Refuel floor 7 tea radiation monitor alarm or *
3) Observed major damage to spent fuel EP-105 Technical Manager - Elec. Near site EOC set up.

d) Feel *1) when at least 2 of 4 General Support Center Prod. reports to BRP contacts facility Damage la contalment rad.noni- Emergency set up. Headquarters - for technical data, cacess of

  • torsindicateigvels .

Emergency Control site greater than 10 R/hr on ,

emergency RI-8/9103 A/C and RI.8/9103 8/D Center. EOF set levels and containment pressure up. News Center exceeds 10 psig on set up.

PR 2/3508

\ .

11. Hastrds to -

Plant Operztlons c) Noderate 1) Aircraft crash on or t)nusual EP-102 Notifies None None Hazards near site as deter. Event local fire minted by Shift Super- and ambulance vision or squads as

2) EmploslE on or near appropriate. ,

site as determined by **

Shift Supervision or *

. se

3) Toxic gas release E or ,,

near site as determined -

by Shift Supervision, e

  • Ponding installation 4 calit: ration s f containment monitors .. ... .....

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WPf.NDig EP-101 1 INTERREIATIONSHIP REWEEN INCIDENTS AND EMERGENCY ACTIONS Page 22 of 23. Rev.3 Licensee Plant Staff Offsite Emnergency Action Level Class Response Notification Response Support Response State 'end local Government Event EP-103 Technical Manager - Elec. Near site EOC set up. BRP b) Severs 1) Aircraft crash on the Alert Support Center Prod. reports to contacts facility for Haarrds facility or missile impacts into the set up. Headquarters technical data.

Reactor Building. Emergency Control Diesel Generator Center. News Center .

Building, or teSW set up.

  • e pump structure as determined by Shift Supervision o_r, r
2) Explosion damage to facility affecting plant safety as determined by Shift Supervision or ,
3) Chlorine gas Etectd 3) Don in the Control Room 4-hour Scott -

Respirators. -

.. Centrol Rees ,

e Evacuation .

Alert SE-1 EP-103 Technical Managet - Elec. Near site BOC set up. IRP c) Eith Evacuation of Main ,

Support Center Prod. reports to contacts facility for remote Control Room anticipated control .or required with control set up. Headquarters technical data, at remote shutdown panels Emergency Control .

csttb.

11thed as determined by Shift Center. News Supervision. Center set up.

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f .APPESDII RP-101 1 (

INTERRELATIONSHIP BRDfEEN INCIDENTS AND EMER0ENCY ACTIONS Page 23 of 23 Rev. & ,

Licensee Plant Staff Offsite .

Event Emergency Action Imvel Class Response Notification Response Support Response State and Incal Government

  • b) Cithout Evw.:stion of Main Control Site SE.1 EP-104 Technical Support Manager - Elec. Naar site EOC set up. BRP -

remoto Roos end control of shut- Emer- Center set up. Prod, reports to contacts facility for down systems not estab. gency Headquart ers Emer-control technical data.

cstab- lished at remote shutdown gency Control 11shed panels in 15 minutes as Center. EOF set up, determined by Shift News Center set up.

Supervision.

l.8ecurity .

Thrxt

1) Security threat or * * * * . .

attempted sabotege or

2) Ongoing security ~ , ,

compromise or i

3) As determin M by j Shift Supervision. , '

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e o Detailed ta'the Peach Rottom Atomic Power Station Security Plan.

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a.EP-207D - -

Page 1 Rev. 0 .

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PHILADELPHIA ELECTRIC COMPANY //V[8 2-

' PEACH BOTTOM UNITS 2 AND 3

~

EMERGENCY PLAN IMPLEMENTING PROC 5 DURE EP-207D PERSONMEL MONITORING AND DECONTAMINATION 4

PURPOSE To define the actions of the Personnel Safety Team Personnel Monitoring and Decontamination Group.

REFERENCES

1. Peach Bottom Atomic Power Station Emergency -Plan Section Title 5.2.2.2.2 Personnel Safety Team 6.4.1.1.e Monitoring of Evacuees
2. Health Physics Operating / Chemistry Operating Procedures Number Title HPO/CO-5 Selection and use of Anti-Contamination Clothing l

HPO/CO-6 Personnel Contamination Survey Techniques HPO/CO-7 Personnel Decontamination Procedure j HPO/CO-8 Decontamination,of Tools and Equipment HPO/CO-100 Health Physics Guides used in the Control of Exposure to Radioactive Material

3. NUREG 0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans in Support of Nuclear Power Plants. .

APPENDIX ,

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EP-i07D Page 2 Rev. 0 3

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l 3 '

ACTION LEVEL 3 The Personne'l Monitoring and Decontamination Group shall be activated whenever the Personnel Safety Team Leader deems their services necessary and the event is classified as an j 3 Unusual Event, Alert, Site Emergency or General Emergency.

8 PRECAUTIONS ,

3

1. When monitoring personnel for contamination, do not contaminate the probe by allowing it to come in contact 3 with the person's body, clothing, or hair.
2. Personnel Monitoring areas should have a background

,,. level less than 300 cpm. Preferably less than'100 cpm if possible.

I 3 IMMEDIATE ACTIOMS 1.0 Personnel Safety Team Leader shall:

!3 l.1 Assign members from the Personnel Safety Team to form Personnel Monitoring and Decontamination Group (s).

s i 1.2 Appoint the most qualified person of the group to be

- the Personnel Monitoring and Decontamination Group

, O Leader and to carry out Section 2.0 of this procedure.

i 2.0 Personnel Monitoring and Decontamination Group Leader

i O shalli 2.1 Direct the group members to obtain the necescary equip-3 ment and supplies that will be needed for personnel moni-

! toring and decontamination.

l i 3, 2.2 Set up a monitoring area as close to the problem area l ,

or assembly area as practicable.

E

'O 2.3 Direct the frisking of personnel, as necessary.

2.4 Inform the Personnel Safety Team Leader of any person O who has been contaminated. Apply Guidance of HPO/CO-100 for significant contamination.

. O 2.5 Document any contaminated persons dame, and group

, affiliation.

O 2.6 Direct decontamination as deemed necessary from the frisking operation in accordance with HPO/CO-6 and 7.

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EP-207D Page 3 Rev. O j ) .

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b 3.0 Personnel Monitoring and Decontamination Group Members shall:

3.1 Obtain personnel decontamination equipment, deemed necessary by the Personnel Monitoring and Decontamination Group Leader, for performing monitoring and decontamination operations.

3.2 Proceed to an area designa#ted to be the monitoring area and, using the FRISKER, take a background contamination level reading. If the reading is greater than 300 cpm, inform the group leader of the average level and await his decision as to set up the monitoring station in this area or to choose another area with a lower background level.

3.3 ' Set up a monitoring station as follows:

3.3.1 Set up a contamination control point (e.g. step off pad, radiation rope).

3.3.2 Using rad-tape or rad-rope, set up boundaries, as necessary, to direct the personnel to the step-off T

pad and to control the spread of contamination.

3.3.3 Provide empty containers near the step-off pad for receiving contaminated objects (clothes, tools, etc) 3.4 Direct the people to be monitored toward the contamination control point.

3.5 Direct each person to remove contamination clothing using HPO/CO-5 Step 3.0 as a guide.

3.6 Frisk the hands of the person'to'be monitored, if his hands are not contaminated hand the person the frisker and direct him to frisk himself, as per HPO/CO-6.

_ 3.7 If the person's hands are contaminated, frisk the rest e

of their body and bottoms of their shoes, if no other contamination is found, direct the person to put on m

' anti-contamination cotton gloves and direct the person to a decontamination area listed below. If other parts of their body are found to be contaminated, direct the e person to put on anti-contaminated clothing as necessary, to prevent the spread of contamination. See HPO/CO-7, Personnel Decontamination. ,

PERSONNEL DECONTAMINATION AREAS

1. RADWASTE BUILDING, ELEVATION 135' ,

2.

O 3. PRESIDENT'S UTILITY BUILDING (PUB)

NORTH SUB STATION

'4. DELTA SERVICE BUILDING 5.

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, 3. 8 Direct personnel to deposit contaminated articles in U the containers provided.

3.9 Direct the personnel, who have been frisked and are i

IO " clean", to a clean area.

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3 3.10 Disassemble the contamination controlSeal pointthe when the containers monitoring operations are complete.

with rad- tape for future transport to the radwaste building when practicable. Properly mark containers to. identify contents and radiation levels.

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, PHILADELPHIA ELECTRIC COMPANY -

PEACH BOTTOM UNITS 2 AND 3

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EP-401 ENTRY FOR EMERGENCY REPAIR, OPERATIONS, AND l' SEARCH AND RESCUE PURPOSE -

To define the method for providing instructions for entering areas that have become adversely affected by the emergency conditions. This procedure is for use during _,

emergency repair, operations, or search and rescue efforts.

REFERENCES 1 , ,

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1. ' Peach Bottom Atomic Power Station Emergency Plan Section Title I 5.2.2.2.1 Radiation Protection Team

. \

5.2.2.2.2 Personnel Safety Team 6.4.1.1 e Monitoring of Evacuees -

6.4.1.1 g Re-entry

2. NUREG 0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. '
3. Health Physics Operating / Chem.istry Operating Pro-cedures .

Number Title '

) HPO/CO-4 Radiation Work Permits HPO/CO-9 Respiratory Protection Program APPENDIX '

. e EP 401-1 Emergency Exposure Limits (Emergency Plan Table 6.1) , ,

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Rev. 1 WJK tljm ACTION LEVEL This procedure is implemented whenever personnel must enter

  • i an area of unknown radiological hazards for reasons of
  • emergency operation of equipment, or repairs, or search and '

rescue.

PRECAUTIOP . .

-1. A min _ m of two people will be. assigned to an entry team and at no time will anyone be allowed to travel through a potentially high radiation area unless they are within sight of another team member.

2. Foremdrgency operation or repair activites, personnel exposure should not exceed the limits of Appendix EP 401-1, -

Emergency Exposure Limits.

3. For search and rescue operations, personnel exposure should not exceed the limits of' Appendix EP 401-1, Emergency Exposure

, . 'o Limits.

4. Personnel who may exceed the exposure of 25 Rem will do so on a voluntary basis. .
5. Exposure to radiation greater than the limits imposed by the Peach Bottom Atomic Power Station limits or limits from 10 CFR 20 should be authorized by the Emergency Director.

, 6. Personnel performing an entry will be aware of the possible

', hazards associated with exceeding a dose of 25 Rem.

7. Monitor personnel. exposure closely with the personal dosi-meter.
8. Requirements of HPO/CO-4, Radiation Work Permits, are not i applicable.

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. IMMEDIATE ACTIONS - .

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. 1 1.0 Entry Team Leader shall: , ,

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1.1 Determine what task has to be performed and how many i people will be required to complete the' task.

l 1.2 Have the team members assemble the necessary tools and

- spare parts that will be required for the task. ,

1.3 Request the Emergency Director to provide maximum e g allowable dose and a projected stay time.

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what type of respiratory and protective clothing will

,be required for the entry.

NOTE: Follow good health physics practices.as much as

- ' practicable consistent with the urgency of the task. -

l 1.5' Equip the team members with the necessary personal dosimetry.

1.6 Have the Health Physics Supervisor provide a health physics qualified individual to accompany each team.

Equip this individual with a high range, beta-gamma

, detector (such as a Teletector).and monitor for the expected radiation levels. ,

1.7 Arrange for.relie*f of personnel as necessary. ,

' 1.8 Establish radio contact with the Control Room. .

1.9 Enter the area and perform the task. Inform the Emer-gency Director of what has been done. -

. 2.0 Entry Team (Operations or Repair) shall:

1 2.1 Assist the Team Leader in determining what has to be done, spare parts, tools, and how many people will be needed.

,2.2 Assemble the necessary equipment required to perform 3 . the task. . . .

2.3 Wear the appropriate respiratory and anti-contamination

.' clothing deem'ed necessary by the Radiation Protection Team Le ad e,r. ,

I . NOTE: Follow guidance'of HP0/CO-9, Respiratory Protection Program, consistent with' the urgency of the emergency task.

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3.0 Health Physics Supervisor shall:

6 3.1 Brief the Entry Team members of the h;zards of radiation ,

doses in excess of 25 Rem to the whole body.

I 3.2 Determind if radiopr*otective drug (KI) administration is necessary and, if so, prepare the necessary quantity" and administer it to the team members. ,

3.3 Ensure that the teams have met all the necessary and anticipated radiation protection requirements prior to r entering a contaminated or radiation area.

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WJK:ljm APPENDIX EP 401-1 EMERGENCY EXPOSURE LIMITS l Projected Whole Body Thyroid Authorized i Function Dose Dose By Life Saving and - Emergency

  • 1.

Reduction of Injury 75 rem

  • 375 rem Director

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2. Operation of Equipment ,

Emergency

  • to Mitigate an ,

Emergency 25 rem

  • 125 rem Director
3. Protection of Health Emergency an'd Safety of the Public 5 rem 25 rem Director
4. Other Emergency 10 CFR 20 '10 CFR 20 Emergency Activities limits limits Director
5. Re-Entry / Recovery Administrative. Administrative Activities Guidelines. . Gui.delines N/A

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  • Re fo rence : EPA-520/1-75-001 Table 2.1
    • Such exposure shall be on a voluntary basis .

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//IN1 i , PHILADELPHIA ELECTRIC COMPANY-PEACH BOTTOM UNITS 2 AND 3 b- EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-311 HANDLING PERSONtlEL WITH SERIOUS INJURIES, RADIOACTIVE CONTAMINATION EXPOSURE, OR ,

EXCESSIVE RADIATION EXPOSURE EMERGENCY DIRECTOR FUNCTIONS

. . PURPOSE ,

. To define the actions to'be taken by the Emergency Director -

in expediting medical care 'for personnel suf fering from serious '

injury, radioactive contamination exposure, or excessive radiation' exposure. ,

REFERENCES -

t

1. Peach Bottom Atomic Power Stat. ion Emergency Plan Section Title 6.0 Emergency Measures
2. EP 207 Personnel Safety Team Activaf. ion i
3. EP 207A Search and Rescue
4. EP 207C First Aid
5. NUREG 0654 Criteria for Preparation and Evaluation '

of Radiological Emergency Response Plans  !

, and Preparedness in Support of Nuclear Power Plants. l APPENDIX None .

ACTION LEVEL , , .

Udusual Event involving serious injuries, radioactive contamina- .

tion exposure, or excessive radiation exposure. ,

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1. Concern for the injury overides immediate concern'for radio-active contamination. .

IMMEDIATE ACTIONS

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1.0 Shift Supervision shall:

1.1 Assume the role of Emergency Director.

1.2 Activate the Personnel Safety Team in accordance with EP-207.

1.3 Notify the First Aid Facility to stand by to assist in

, the treatment of injured persons. (Day shift, Monday through Friday only). s 1.4 Carry out the steps from the applicable categories listed below, based on the recommendations of the Personnel Safety Team.

J Part A No Radiation -

Serious Injury Part B 1. Excessive Radiation Exposure -

No Serious Injury

2. Excessive Radiation Exposure -

Serious, Injury

3. Contamination Exposure -

No Serious Injury U 4. Contamination Exposure -

Serious Injury

5. Excessive Radiation and

? Contamination Exposure -

No. Serious Injury

6. Excessive Radiation and U contamination Exposure -

Serious Injury l '

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Part A: No Radiation Involved - Serious Injury 3 }

Criteria: Any serious injury warranting the attention

, of offsite medical support. .

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FOLLOW-UP ACTIONS , e l

O 1.0 Emergency Director l _

J 1.1 Based on the report and recommendations of the Personnel, Safety Team, determine if hospitalization is required. ,-

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1.' 2 If hospitalization is not required, request a local physician'to come to the site, or arrange to transport the injured persons to a local physician via company or personal vehicle (see EP 209, Appendix N for telephone numbers). ,

1.3 If hospit'alization is required, arrange to transport the injured persons via ambulance, or company or personal vehicle. , Contact the Nurse Shift Supervisor at Harford Memorial Hospital (see EP 209, Appendix N for telephone

- numbers).

EMPHASIZE TO THE NURSE SHIFT SUPERVISOR THAT THE INJURIES

  • DO NOT INVOLVE RADIOACTIVE CONTAMINATION, THAT THE INJURED PERSONS ARE TO BE TREATED USING ROUTINE HOSPITAL PROCEDURES, AND THAT THEY SHOULD BE ADMITTED TO THE CONVENTIONAL EMERGENCY ROOM.

1.4 Alert security personnel' to prepare to expedite admittance \

of the physicain or ambulance and to provide personnel dosi-metry, if necessary.

/ 1.5 Direct the Load Dispatcher to notify the Company Medical Director and Claims as required.

, 1.6 Notify the injured persons' families or emergency contacts.

1.7 Notify or authorize notification of the Superintendent, Generation Division - Nuciear (see EP 209, Appendix E for telephone numbers.)

J Part B: Radiation-Related Personnel Accidents -

1. Excessive Radiation Exposure - No Serious Injury Criteria: Acute whole body exposure greater than 3 REM.

FOLLOW-UP ACTIONS 1.0 Emergency Director shall:

1.1 Direct the Load Dispatcher to notify the Company Medical Director and Claims as' required. ./

2.d Station Superintendent (or the Assistant Station Superin-tendent) shall:

2.1 Notify the Superintendent, Generation Division - Nuclear.

3 2.2 Notify Radiation Management Corporation (see EP 209,

. Appendix N for telephone numbers). ,

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. WJK:ljm 2.3 Notify the Nucicar Regulatory Commission, Region I,

. - Office of Inspection and Enforcement by two communi-cations methods, if any of the following conditions exist:

.a. Whole body exposure'is 25 REM or more

b. Skin exposure is 150 REM or more
c. Extremity exposure *is 375 REM or more
) NOTICE WITHIN 24 HOURS IS REQUIRED IF EXPOSURES ARE AT LEAST 20% OF THE ABOVE VALUES.

THERE IS NO UEED FOR FIRST AID OR FOR URGENT TRANSFER OF THE PATIENTS TO A HOSPITAL BECAUSE OF THE RADIATION EXPOSURE. WHEN DETERMINED BY MEDICAL CONSULTATION THAT 1

HOSPITALIZATION IS NECESSARY THE PATIENTS WILL BE TRANSFERRED TO HARFORD MEMOPIAL HOSPITAL BY ROUTINE HOSPITAL PROCEDURES, OR THE RADIATION MANAGEMENT .

CORPORATION FACILITIES IN PHILADELPHIA.

2. Excessive Radiation Exoosure - Serious Injury Criteria: ,

A person suffers both of the following:

a. Any injury of sufficient magnitude to warrant the attention of offsite medical support; and
b. An acute whole body exposure of greater than 3 REM.

FOLLOW-UP ACTIONS

. 1.0 Emergency Director shall:

1.1 Based on the report and recommendations of the Personnel

. Safety Team, determine if hospitalization is required.

1.2 If hospitalization is not required,' request a local U physician to come to the site, or arrange to transport

, the injured persons to a local physician via company or personal vehicle (see EP 209 Appendix N for telephone _

numbers).

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1.3 If hospitalization is required, arrange to transport ,

the injured persons via ambulance, or company or personal vehicle. Contact the Nurse Shift Supervisor at Harford Memorial Hospital (See EP 209, Appendix N for telephone e numbers).

4 EMPHASIZE TO THE NURSE SHIFT SUPERVISOR THAT THE INJURIES TO NOT INVOLVE RADIOACTIVE CONTAMINATION, .

THAT THE INJURED PERSONS ARE TO BE TREATED USING ROUTINE HOSPITAL PROCEDURES, AND THAT THEY SHOULD BE ADMITTED TO THE CONVENTIONAL EMERGENCY ROOM.

1.4 Alert security personnel to prepare to expedite admittance of the physician or ambulance and to provide personnel dosimetry, if necessary.

1.5 Direct the Load Dispatcher to notify the Company Medical Director and Claims as required. .

1.6 Notify the injured persons' families or emergency con-  ;

tacts.

2.0 Station Superintendent (or the Assistant Station Superin-tendent) shall:

4 2.1 Notify the Superintendent, Generation Division -' Nuclear.

2.2 Notify Radiation Management Cc'rporation (see EP 209,-

Appendix N for telephone numbers).

2.3 Notify the Nuclear Regulatory Commission, Office of Inspection and Enforcement by two communications methods, if any of the following conditions exist:

a. Whole body exposure is 25 REM or more
b. Skin exposure is 150 REM or more ,
c. Extremity exposure is 375 REM or'more NOTICE WITHIN 24 HOURS IS REQUIRED IF EXPOSURES ARE AT LEAST 20% OF THE ABOVE VALUES. .

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3. Radioactive Contamination Exposure - No Serious Injury I Criteria -

A person suffers one of the following:

a. Radioactive contamination exposure which causes a body contact reading of 1 mR/hr using a GM detector following decontamination.
b. Suspected or actual inhalation or. ingestion of radioactive material resulting in a 1001 investigative level of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exposure.

CAUTION: GROSS EXTERNAL CONTAMINATION USUALLY RESULTS IN SOME INTERNAL CONTAMINATION.

FOLLOW-UP ACTIONS 1.0 Emergency D_inctor shall:

1.1 Direct the Load Dispatcher to notify the Company Medical Director and Claims as required. .

1.2 Direct the Personnel Safety Team Leader to perform iso-topic analysis to determine isotopic composition of the contaraination, with assistance from Radiation Management Corporation, as necessary.

2.0 Station Superintendent (or the Assistant Superintendent) shall:

2.1 Notify the Superintendent, Generation Division - Nuclear.

2.2 Notify Radiation Management Corporation (see EP 209, Appendix N for telephone numbers).

- 4. Contamination Exposure - Serious Injury Criteria 4

A person suffers both.of the following: .

O a. Radioactive contamination exposure which causes a body contact reading of 1 mR/hr using a GM detector

. or suspected or actual inhalation or ingestion of C

measurable quantities of radioactive material. ,

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b ., Any injury warranting the attention of offsite medical v ,

support.

CAUTION: ' GROSS EXTERNAL CONTAMINATION USUALLY RESULTS IN SOME

, O INTERNAL CONTAMINATION. .

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~ u FOLLOW-UP ACTIONS 1.0 Emergency Director shall: .

s 1.1 Based on the report and recommendations of the Personnel i

I Safety Team, determine if hospitalization is required.

1.2 If hospitalization is not required, request.a local physician to come to the. site, or arrange to transport i the persons to a local physician via company or personal vehicle (see EP 209, Appendix N for telephone numbers).

1.3 If hospitalization is required:

1.3.1 If Harford Memorial Hospital can handle the victims (depending on their number and exposure / contamination levels),

contact the Nurse Shift Supervisor at Harford Memorial I Hospital. (See EP-209, Appendix N for telephone numbers). l EMPHASIZE THAT THE INJURIES INVOLVE RADIOACTIVE CON- .

TAMINATION AND THAT THE INJURED PERSONS ARE TO BE 'J ADMITTED TO THE RADIATION EMERGENCY ' ROOM ACCORDING TO THE

" PROCEDURES FOR HANDLING RADIATION ACCIDENTS,.

1.3.2 If the number of contaminated injured personnel exceeds the capacity of Harford Memorial Hospital, coordinate with the Company Medical Director and Radiation Management Corporation for proper care

.of the victims. It may be necessary to notify the Radiation Management Corporation (RMC) Medical

. Facility at the Hospital of the University of Pennsylvania, Philadelphia, Pennsylvania. RMC, in consultation with the Company Medical Department, may conclude that the exposures require the prolonged, sophisticated treatment available at their facilities at the '.ospital of the University of Pennsylvania. RMC shall arrange for transport of the patients eithet by ambulance, personal vehicle, or helicopter. Provisions exist for helicopter transfer from pads at the plant site or

. , Delta-Cardiff.

1.4 Notify security personnel to prepare to expedite admittance of the local physician or ambulance and to provide personnel dosimetry, if necessary.

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1.5 . Direct a health physics representative to accompany the  :

.i ambulance to the hospital or facility to advise the  !

hospital' staff concerning the radiation hazards,'to control and recover radiation waste, and to obtain

' personnel exposure data, if necessary.'

'1.6 Direct the Load Dispatcher to notify the Company Medical Director and Claims as required. ,

1.7 Notify the injured persons'. families or emergency contacts.

2.0 Station Superintendent (or the Assistant Station Superi.n-tendent shall:

2.1 Notify the Superintendent, Generation Division - Nuclear.

2.2 Notify Radiation Management Corporation (see.'EP 209, Appendix N for telephone numbers). .

5. Excessive Radiation and Contamination Exposure - No t

Serious Injury

a. Carry out the steps of Part B.3.
b. Carry out step 2.3 of Part B.2.
6. Excessive Radiation and Contamination Exposure - Serious Injury -
a. Carry out the steps of Part B.4.
b. Carry out step 2.3 of Part B.2.

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