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 M

Page 1 EMERGENCY PLAN PROCEDURES INDEX

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Rev. 8

  • 01'/04/82
  • PEACH BOTTO!! UNITS 2 AND 3 v

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

I l

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

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 *

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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

12/22/81

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

01/04/82

  • 8202190083 820211 PDR ADOCK 05000277 F

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Rev, 8*

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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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$i EP Index l

L EMERGENCY PLAN PRCCEDURES INDEX Page 3

' PEACH BOTTOM UNITS 2 AND 0

b4 82 *

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Review Rev. Revision Date No.

Date

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

01/04/82

  • 6 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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s EP-101 Page 2

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s 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 EP 101-1 Category 1.

Unplanned Shutdown 1, 2, & 3 2.

Personnel Injury 3&4 3.

Primary Contain-ment Integrity 4,5,6,& 7 4.

Radioactive Material Release 7, 8, 9, & 10 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 Operation 21 & 22
12. Control Room 22 & 23 Evacuation

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13. Security

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ER-101 Page 3 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."

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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 Offsite Plant Staff State and local Government Licensee Support Response Notification Response _

.- k nt Emergency Action Level Class Response _

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

None mest L.C.O.

Unusual Invt.atigate EP-102 None c2)cny Ecram Scram Alarm Event cause of oth:r than scram. Deter-mine status of plant safety sys-tems.

b1) scram with 1) scram alarm and Alert GP-3 EP-103 Technical Sup-Manager - Elec.

Near Site EOC set up.

Bureau of Radiation Pro-rort Center set Prod. reports to tection contacts triple low

.2 ) double low lefe'l E-26 Headquarters Emer-gency Control Center. facility for technical up. Assist Icv;,1-no alarm (-48") and EP-103 shift to investigate News Center set up.

data.

LOCA indi

  • 3) triple low le' vet c:ted salarm (-130") and~

equipment

  • 4) incrense in cont failure.

ainment pressure to greater than 1 psig but less than 2 psig on PR-2/3508 7.

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APPENDIX EF-101 1

'4 INTERRETATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS

'Page 2 of 2 3, Rev. A -

Licensee Plant Staff Offsite Event Emergency Action Imvel Class Response Notification

Response

Support Response. State and local Government t;2) unplanned 1) scram alarm M Alert GP-3 EP-103 Technical Manager - Elec.

Near site EOC set up.

scram and 2) double low level E-25 Support Cen-Prod. reports to Bureau of Radiation fro-IDCA alarm (-48*) and EP-103 ter set up.

Ileadquarters Emer-tection contacts facility (small

3) triple low le M Assist shift gency Control Cen-for technical data.

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

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
1) scram alarm a_nd Site 2-14 EP-104 Technical
  • Manager - Elec.

Near site EOC set up.

n 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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containment high

2) Evacuate non-equipment News Center set up.

4 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

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10 R/hr on RI-8/9103A/C j,

and RI-8/9103D/D o

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

Licensee Plant Staff Offsite Event Emergency Action Imvel Class Response Notification Rerponse Support Response State and Tocal Covernment

  • d) acram with 1) scram alarm a_n_d General E-26 EP-135 Technical Manager - Elec.

Near site EOC set up.

failure of 2) double low level Emergency Support Cen-Prod. reports to Bureau of Radiation Pro-e ICCS to alarm (-48*) and ter set up.

Headquarters Emer-tection contacts facility I

recover or 3) triple low le M Assist shift gency Control Cen-for technical data, maintain alarm (-130*) and to investigate ter. E0F set up.

1sval and

4) active fuel range equipment fail-News Ceater set up.

LOCA 1evel indication ure. Analyze 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-f utes and area surveys around the

6) conta M ent high l

P ant.

pressure alarm e

l (2 psig) and,

,ontainment pres-t 7) c sure greater than l

20 psig on PR-2/3308 "and e

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  • 8) M tainment dose rate greater.than 4

10 R/hr on Rg-8/9103 A/C and RI-8/9103 U/D I

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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.

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via ambu-Prepare in-required.

1ance to jured for i

medical fac-transport offsite 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

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

State and Iocal Government Licersee.

Support Response Notification Response _

Class Response M

_Eutergency Action IAvel None

b) I2jrry in. 1) Injury warranting Unusual As above EP-102 Consult with Local physician may PECO Hedical report to the facility.

offsite medical Event plus per-RMC consulted.

Director

~ involving treatment and form pre-rrdis-

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

. Primary Con-tainment 15one Intsgrity Assist shift

  • None
01) nrn-
1) Primary containment Unusual 1) deter-EP-102 icolable leskrate is greater Event mine of-in search for fect of leak then 0.5 percent of Isakage leakage volume per 24 hre.

on plant when at 49.1 psig or primary status contai-I) If N makeup system i's not capable of

2) observe y

containment:

ment

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

centration y

c) dose rate

3) shutdown Unit if warranted e s

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APPDOII EP.101 1 INTERREIATIONSHIP BEDIEEN INCIDENTS AND EMERCENCY ACTIONS Page 5 of 23, Rev. S Licensee Plant Staff Offsite Ev nt Emergency Action Level Class Response Notiff. cation

Response

Support Response State 'and local Government

'd2)feilure to incorrect valve pos-Unusual 1) isolate EP-102 Assist shift None None isolate any ition during Group I, Event manually -

in investigating III iso-

2) observe reason for p imtration II, or lation alarms contain-failure whsn auto.

ment icoletinn to initia-al pressure b) oxygen tid by a concen-transient tration c) dose rate

3) shut down Unit if warranted

' b) 1000 of

1) Reactor Building Alert 1)Jetermine EP-103 Technical Manager - Elec.

Near Site EOC set up.

primary vent rad affluent location of Support Center Prod. reports to Bureau of Radiation Pro-cintain-

. high rad alarm and' breach and set up. Assist Headquarters Emer-taction contacts facility 1solate shift in in-gency Control Cen-for techni:a1 data, ment in-

- 2) Inability to main:

tngrity tain pressure greater

2) observe con-vestigation of ter. News Center than 0.25 psig on par-tainment leakage.

set up.

whan pri-mary con

  • row range PR-2/3508 al pressure b) oxygen teinment or 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-contain-conditions:

E-25, or ter set up.

Headquarters Emer-tection contacts facility 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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? vert Emergency Action 14 vel Class Response Notification

Response

Support Response State and 14 cal Covernment c2)Mtential 1) containment high Site 1107-3 EP-104 Technical Manager - Elec.

Near site EOC set up.

' 1cco cf pressure alarm Emergency 210T-45 Support Cen-Prod. reports to Bureau of Radiation Pro-3rimary (1.5 peig), a_nd,

3) Determine ter set up.

Headquarters Emer-tection contacts facility.

rentsin-21 scram, and_

location Perform Dose gency Control Cen-for technical data.

ent inte *3) containment dose of breach assessment, ter. EOF set up.

& isolate Perform Dose Assess-9rity with ragegreaterthan ment.

t.igh pri-10 R/hr on 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 01)In tant-1)A spike ** on rad Unusual OT-44 or EP-102 None None None anscus re-

  • ef fluent monitors:

. Event OT-45 cxding

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

3x 10 cpm on RR-2/3979 or

2) Analysis of particu-late filters or char-coal cartridge a) Main Stack greater 1

than 5 x 10 uCi/ sec d2I b) Reactor Building vertt greater than I

4 x 10 uC1/sec

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)CIf tolecse rate is not decreasing or controllable, see event 4b,c & d e

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INTERREIATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Event Einergency Action Level Clasa Response Notification

Response

Support Response State and local Governnet a2) Releale A report of the summa-IJnusual Investigate EP-102 None None None 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-lease within quartsrly a

11:it limits b).Actu,1

1) Uncontrollable release, Alert OT-44 or EP-103 Technical Support Manager - Elec.

Near site EOC set up.

2 ar po-for more than 20 min-0T-45 Center set up.

Prod, reports to Bureau of Radiation Pro.

testict utes, from the:

Activate Assist shift steadquarters Emer.

tection contacts facility rsiscso a) Main stack greater Radiation Pro-to investigate gency Control Cen-for technical data. Dis-that gives than 1.2x1@ cps on tection Team source of re-ter. News Center patch survey teams to ob-doao af RR 0-17-051 or to monitor lease and in set up.

tain radiation data near 0.01 ree b) Reactor Building vent in-plant and assessment of site. Initiate public whoto greater than 3.44 x plume path, radiological notification.

d consequences.

body cr go 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

2 R/hr j

greater than 10 on RI-8/9103 A/C and RI-8/9103 S/D t

4'

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APPt.NDIX El-101 INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Page 9 of 23. Rev. 2.

Plant Staff Offsite Licensee Event-Emergency Action h vel Class Response Notification

Response

Support Fesponse State ani Eocal Governswsst 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 than 1.2x10 cps on monitor in-vestigate set up. News Center Initiate public notification.

doso of 0.1 res RR 0-17-051 or plant and source of set up.

Dispatch survey temas to ob-thole b) Reactor BuilTing plume path, release and tain radiation data near site, 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 a)Hainstackgreater e

, 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 INTEFRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Page 10 of 23, Rev. A Licensee Plant Staff Offsite Event Bnergency Action Emvel Class Response Notification

Response

Support Response State and local Covernment.

General Investigate EP-105 Technical Sup-ECF set up. Deter.

Near site EOC set up.

d) Actual or

1) Uncontrollable release,lbsergency potential

.for more than 20 source of port Center mine need for off-Bureau of Radiation Pro-

release, set up. Assist site support. Har-tection contacts facility r:ltas' minutes. from the:

that gives a) Main Stack greater than Activate shift to in-ager - Elec. Prod.

for technical data. Initiate dose of 1

!.2x105 cps on Radiation vestigate source reports to Head-public notification. Dispatch rem Whole RR 0 17-051 or Protection of release and quarters Emergency survey teams to obtain j

b) Reactor Buil Hng Team to son.

In assessment Control Center. Ac-radiation data near site.

Body or 5 r2o Thy-vent greater than itor in-plant of radiological quire offsite sup-Eureau of Radiation Pro-6 and plume consequences.

port deemed necess-tection recoemends rold 3.44x10 cpm on RR 2/3979 or-path. Evacuate Augment shift ary. News Center Protective Actions.

2) Continued particulate 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

  • 17) Reactor Building

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0T-45 than 4.7x10 uC1/sec or vent greater than 8

1.23:106 uCi/sec or

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  1. ) Containment dose rat T 3

4 R/hr greater than 10 on RI-8/9103 A/C and RI-8/9103 g/o

5) Fire t

i) fire in Alarm and verbal report Unusual Shift fire Sta. Supt.

Notify local Local fire fight-None protected from SSV Event team Load Disp.

fire fighting ing support organ-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

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APPENDIX EP-101-1 INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Page 11 of 23, Rev..L Licensee Plant Staff Offsite Eve *t Extergency Action Level Class Response Notification

Response

Support Response State and local Government b) fire which Fire alors and verbal Alert Consider EP-103 Technical Sup-local fire fighting Near site EOC set up.

could prevent, report from SSV shut down port Center set organizations res-thJreau of Radiation Pro-with avail-up. Request pond as necessary.

tection contact s f acility en ECC 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 requiremedts brigade assist in fire gency Control fight fire, fighting if nec-Center. News Center-activate

essary, set up.

Personnel Safety Team s) fire which Fire alars and verbal

. Site Consider shut EP-104 Technical Sup-local fire fighting Near site EOC set up.

prevents an report from SSV Emer-down with port Center set

  • organizations res-Bureau of Radiation Pre-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 assist in fire ter. EOF set up.

recommends Protective Actions.

ments 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 Licensee Plant Staff Offsite Support Response State and local Governnw.mt twent Ibaergency Action Imvel class Response Notification

Response

d) fise which Fire alarm and verbal Ceneral Shut down.

EP-105 Technical Sup.

Local fire fighting Near site EOC set up.

cauros dam-report from SSV.-and

' Emergency Verify avail-port Center ornnizations res-Bureau of Radiation Pro-able isola-set up. Request po..d. Hanager - Elec. tection contacts fa-111ty rg3 to plant 1DCA symptoms. ECCS, or systems suf-containment failure.

tions. Use local fire Prod. reports to for technical data. Initiate available core fighting organ-Headquarters Emer-public notification. Bureau of cooling cap-irations to gency Control Cen-Radiation Protection reconsends ficient to ability.

assist in fire ter. LOF set up.

Protective Actions. Counties 1ead to athIr gen.

fighting. Aug.

News Center set up, implement Protective Actions, e

ment shift in Near site LOC set up.

cr21 eser-gencies evacuation and accountability efforts.

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

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

1) greater than 113 ',g feet (C.D.), of 2)1ess than 104

_ feet _(C.D.1 without prior

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notification by

,e L.D.

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

INTERRELATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff Offsite Event Emergency Action Imvel Class Response Notification

Response

Support Response ' State ' end Incal Government a3) TIrrado A tornado is observed on tfnusus! Inspect sta-EP-102 Assist in the None None site.

Event tion for inspection of damage. Re-the station for pair any, damage. Assist

damage, in any repairs.

, a4) Itsrricane Shift Supervision be.

Unusual Prepare sta-EP-102 Assit in pre-None NearsiteEOCsetupf 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 i

(portable gen-erators, trash cans., barricades, etc) i b1) Barthquake An actual earthquake boyb Alert SE-5 EP-103 Technical Sup-Nanager.- Elec.

Near site E0C set up beyond un-the Operating Basis Earth-port Center set Prod, reports to Bureau of Radiation Pre-usu21 event quake (OBE) levels, as in-up. Assist in Headquarters Emer-tection contacts facility the station in-gency Control Cen-for technical data.

Irvsts dicated by alarm.

spection and re-ter. News Center s

\\

pair.

set up, b2) Abnormal Conowingo Pond level on Alert SE-3 EP-IC3 Technical Sup-Manager - Elec.

Near Site EOC set up.

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

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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 INTERRELATIONSHIP BENEEN INCIDENTS AND EMERGENCY ACTIONS

, Page 16 of 23, a v, g Licensee Plant Staff Offsite twent Einergency Action IAvel Class Response Notification

Response

Support Response State and focal Government 7.14ss of Power c) Imss of

1) turbine generator trip Unusual E-10 EP-102 None None None cffsite with Startup Auxiliary Event power transformer SU2 and sources or SU3 unavailable for ons.I s service for more than t

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.

b1) Imse of

1) turbine generator trip Alert E-10 EP-103 Technical Sup-Manager - Elec.

Near site EOC set up..

cffsite with Startup Auxiliary port Center set Prod. reports to Eureau of Radiation Pro-up.

Headquarters Emer-tection contacts facility transformer SU2 and 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 l

minutes i

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l If conditions

1) and 2) l

~ esi E for more

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  • s

{

than 15 minutes..

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this is a Site

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Emergency, see 7 c!)

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APPENDIX EP-101-l' DtTERREIATIONSHIP BETWEEN INCIDENTS AND EMERGENCY ACTIONS Page 17 of 23, now,3, Licensee Plant Staff Offaite Event Baergency Action 14 vel Class Response Notification

Response

Support Response State and Iocal Goverrueent b2) less of

1) Less than 105 Volts on Alert EP-103 Technical Sup.

Hansger - Elec.

Near site EOC set up.

c!! DC the 2/3A,B,C 4 D distrib-port Center Prod. reports to Bureau.of Radiation Pro.

power for ution panels as indi-set up.

Headquarter s Emer-tection contacts facility 1:ss than cated on Panels 2/3ALO3, gency Control Con-for technical data.

ter. News Center 15 minutes 2/3cD03, 2/3BD03, 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

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than 15

3) less of all alarms
cinutes,

. this is s

~ o Site Emir.

g1ncy.

See 7 c2).

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APPENDIX EP-101 1 INTERRELATIONSHIP BEWEEN INCIDENTS AND EMERGENCY ACTIONS Page 18 of 23. Rev. A Licensee Plant Staff Offsite Event Emergency Action Imvel Class Response Notification

Response

Support Response State 'and local'Covernment 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~ali diesel News Center set up.

l generators to far longer 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 8

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APPEND 11 EP.101-1 Page 19 of 23, Rev. 3, INTERRELATIONSHIP BETWEEN II/CIDENTS AND EMERGENCY ACTIONS Licensee Plant Staff offsite

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

5_upport Response State and tocal Government 6

,S. Secondary Cee-tainment In-t:grity c) 1.oss of t.ons of Secondary Coa-Ifnusual CT-49 EP-102 Assist in lione None 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 9.1:stnment

1) Complete loss of all Unusual EP-102 None None e

Failure Main Control Roce Event communication equip-s) Signifi-ment cant loss I

a.f assess.

  • cent or cos-a munication a

I capability in the Main Control Room.

g

10. Fu;1 Damage home

'c) Possible

1) Air ejector discharge Unusual Cf-10 EP-102 A 9e 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,

  • g'.

.e i

2) Iligh reactor coolant activity as determined by sample analysia

'e equal to or greater g

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 Event Emergency Action Level class Response Notification

Response

Support Response

' State and focal Government b) Puel

1) Air ejector discharge Alert OT-10 EP-103 Technical Manager - Elec.

Near site EOC set up. BRP Damage rad monitor indicating 07-5 Support Center Prod. reports to contacts facility for 4

set up.

Headquarters technical data, greater than 2.5 x 10 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 alara, G 1 bundle or

3) Spent f damage resulting in a refueling floor area indiation or high radiation alora on fuel pool vent plenum Site GP-4 EP-104 Technical Manager - Elec.

Near site ECC set up, r'ad monitor e) Puel

)) Fb11owing conditions Emergency E-5.

Support Center Prod. reports to BRP contacts facility.

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 levsts on a scram and,

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 o.-

or

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APPEND 11 EP-101 1 INTERREIATIONSHIP BETWEEN INCIDENTS AND EMEitGENCY ACTIONS Page 21 of 23, Rev. S.

Licensee Plant Staff Offsite tv-nt Einergency Action I4 vel Claes Response Notification ye ynne Support Response State 'and local Government

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 un:overing of spent set up.

quarters Emergency for technical data, Control Center.

fuel as confirmed by a fuel pool ares EOF set up. News radiation monitor Cent er set up.

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 d) Feel
  • 1) when at least 2 of 4 General EP-105 Technical Manager - Elec.

Near site EOC set up.

Damage la contalment rad.noni-Emergency Support Center Prod. reports to BRP contacts facility set up.

Headquarters

- for technical data, cacess of torsindicateigvels site greater than 10 R/hr on Emergency Control Center. EOF set emergency RI-8/9103 A/C and RI.8/9103 8/D levels and containment pressure up. News Center exceeds 10 psig on set up.

PR 2/3508

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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 and ambulance minted by Shift Super-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 4

)

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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 Event Emnergency Action Level Class Response Notification

Response

Support Response State 'end local Government b) Severs

1) Aircraft crash on the Alert EP-103 Technical Manager - Elec.

Near site EOC set up. BRP Haarrds facility or missile Support Center Prod. reports to contacts facility for 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 c) Eith Evacuation of Main,

Alert SE-1 EP-103 Technical Managet - Elec.

Near site BOC set up. IRP remote Control Room anticipated Support Center Prod. reports to contacts facility for control

.or required with control set up.

Headquarters technical data, csttb.

at remote shutdown panels Emergency Control Center. News 11thed as determined by Shift Supervision.

Center set up.

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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 control down systems not estab.

gency Headquart ers Emer-

' 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 ~

i compromise or

3) As determin M by j

Shift Supervision.

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Page 1 Rev. 0

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PHILADELPHIA ELECTRIC COMPANY

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' 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 None T

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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

!: O shalli i

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.

Proceed to an area designa#ted to be the monitoring area 3.2 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 pad and to control the spread of contamination.

T 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 anti-contamination cotton gloves and direct the person m'

to a decontamination area listed below.

If other parts of their body are found to be contaminated, direct the person to put on anti-contaminated clothing as necessary, e

to prevent the spread of contamination.

See HPO/CO-7, Personnel Decontamination.

PERSONNEL DECONTAMINATION AREAS 1.

RADWASTE BUILDING, ELEVATION 135' 2.

PRESIDENT'S UTILITY BUILDING (PUB)

O 3.

NORTH SUB STATION

'4.

DELTA SERVICE BUILDING 5.

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EP-207D

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- Page 4 Rev. 0

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Direct personnel to deposit contaminated articles in U

, 3. 8 the containers provided.

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

" clean", to a clean area.

i 3.10 Disassemble the contamination control point when the Seal the containers

3 monitoring operations are complete.

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

contents and radiation levels.

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.- m PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 AND 3

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. EMERGENCY PLAN IMPLEMENTING PROCEDURE

~

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

, i 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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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.

N IMMEDIATE ACTIONS l

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1 1.0 Entry Team Leader shall:

1 i

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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Rev. t WJK:ljm 1.4 Have the Radiation Protection Team Leader determine 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.

Have the Health Physics Supervisor provide a health 1.6 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.

I 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 entering a contaminated or radiation area.

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APPENDIX EP 401-1 EMERGENCY EXPOSURE LIMITS l

Projected Whole Body Thyroid Authorized i

Function Dose Dose By Emergency

  • 1.

Life Saving and Reduction of Injury 75 rem

  • 375 rem Director

'l 2.

Operation of Equipment Emergency

  • to Mitigate an 25 rem
  • 125 rem Director Emergency 3.

Protection of Health an'd Safety of the Emergency 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 1

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//IN1 PHILADELPHIA ELECTRIC COMPANY-i 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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PREC AU TIF.< S 1

1.

Concern for the injury overides immediate concern'for radio-

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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

l Part A:

No Radiation Involved - Serious Injury

}

3 Criteria:

Any serious injury warranting the attention of offsite medical support.

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a FOLLOW-UP ACTIONS e

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1.0 Emergency Director l

1.1 Based on the report and recommendations of the Personnel,

_J 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

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

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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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Rev. 1 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:

Whole body exposure'is 25 REM or more

.a.

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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Rev. 1 WJK:1jm 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 Criteria A person suffers one of the following:

Radioactive contamination exposure which causes a body a.

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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EP-311k

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FOLLOW-UP ACTIONS 1.0 Emergency Director shall:

s i

1.1 Based on the report and recommendations of the Personnel 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 the persons to a local physician via company or personal i

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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. Direct a health physics representative to accompany the 1.5 ambulance to the hospital or facility to advise the

.i hospital' staff concerning the radiation hazards,'to control and recover radiation waste, and to obtain personnel exposure data, if necessary.'

Direct the Load Dispatcher to notify the Company Medical

'1.6 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 Carry out the steps of Part B.3.

a.

b.

Carry out step 2.3 of Part B.2.

6.

Excessive Radiation and Contamination Exposure - Serious Injury Carry out the steps of Part B.4.

a.

b.

Carry out step 2.3 of Part B.2.

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