ML20134K804

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Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 13 to EP-101, Classification of Emergencies & Rev 4 to EP-207A, First Aid/Search & Rescue Group
ML20134K804
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 08/09/1985
From: Cooney M
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20134K796 List:
References
PROC-850809-01, NUDOCS 8508300446
Download: ML20134K804 (33)
v • d • e


Text

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EP Irriex ..!

+

, ,, DERGENCY PIAN PMX2DURES INGDC Page 1 Rev. 52

  • 7 PEPG B0lTM UNITS 2 AND 3 07/31/85
  • Review Rev. Revision Number Title Date No. Date M __

D-101 Classification of Emergencies 07/12/85 13' 07/12/85

  • 4 EP-102 Uhusual Event n p se 06/26/85 10 06/26/85 EP-103 Alert Rerpense 06/26/85 H 06/26/85 EP-104 Site lhergency Response

Activatim 10/12/84 7 10/12/84 EP-202 Operations Support Center (OSC)

Activation 01/23/85 7 01/23/85 EP-203 anergency Operations Facility (ECF)

Activatim 10/12/84 7 10/12/84

{ EP-203A Alternate Bnergency Operations Facility (E(F) Activation 10/12/84 0 10/12/84

-4 EP-205 DELETED 09/12/84 ,

EP-205A Chemistry Sampling and Analysis Group 09/18/84 5 09/18/84 EP-205A Operatim of Post Accident Satpling

.1 Station 09/20/84 5 09/20/84 EP-205A Cbtaining Drywell Gas Sanples

.2 fran Contairunent ALi ).ere Dilution Cabinets 05/26/82 0 05/26/82 EP-205A Retrieving and Changing Sanple

.3 Filters and Cartridges fran the Drywell Radiation Manitor During r

anergencies 04/25/83 1 04/25/83 EP-205A Obtaining Drywell Gas Samples ~~"

.4 fran the Drywell Radiation Monitor Sangling Station 05/25/82 0 05/25/82

  • EP-205A Obtaining Rarctor Water Samples

.5 from Sample Sinks Following Accident Cmditions 05/25/82 0 05/25/8,2 --

EP-205A Cbtaining Canal Discharge Water co5 2 0 M g fted -

. ... -._ ... _ r .L3Maunosrab 8508300446 8500(W PDR ADOCM 05000277 F PDR

EP Index -T

~,

..-' ,, ENEPGENCY PIAN PROCEDURES INDEX Page 2 Rev. 52

  • PEACH B01'ItM IMITS 2 AND 3 07/31/85
  • Review Rev. Revision Ntanber Title Date No. Date

.6 Sanples FoHowing Radioactive Liquid ..

Releases After Accident Ccriditions 05/25/82 0' 05/25/82 EP-205A Obtaining the Iodine and Particulate

.7 Sanples fr a the Main Stack and Roof Vents PoHowing Accident Canditions H/21/83 2 H/21/83 1 EP-205A Obtaining Liquid Radwaste Sanples ~

.8 from Radwaste Sanple Sink Following l Accident Carrlitions 05/25/82 0 05/25/82 EP-205A (btaining Sarples frcan condensate

.9 Sanple Sink Following Accident Canditions 05/25/82 0 05/25/82 EP-205A Obtaining Off-Gas Sanples fran l .10 the Off-Gas Hydrogen Analyzer l Pbliowing Accident Conditions 05/25/82 0 05/25/82 EP-205A Sanple Preparation and Handling

.11 of Highly Radioactive Liquid Samples 02/29/84 2 02/29/84

( EP-205A

.12 Sample Preparation and Handling of Highly Radioactive Particulate Filters and Iodine Cartridges 01/10/84 3 01/10/84

  • EP-205A Sanple Preparation and Handling of

.13 Highly Radioactive Gas Sanples 02/29/84 2 02/29/84 EP-205A Offsite Analysis of High Activity

.14 Sanples H/23/83 0 H/23/83 EP-205A Guidelines for the Order of

.15 Analysis an Post-Accident Samples 02/29/84 0 02/29/84 EP-205B Radiatimt Survey Groups 09/18/84 5 09/18/84 EP-205C Personnel Dosimetry Bioassay and Respiratory Protection Group 09/20/84 3 09/20/84 EP-206 DELETED 04/27/83 ,

EP-206A Fire Fighting Group 01/10/84 6 01/10/84 EP-206B Damage Repair Group 05/31/83 3 05/31/83 EP-207 Personnel Safety Team Activation 09/20/84 6 09/20/84 I EP-207A- Search and Rescue 07/31/85 4 07/31/85 *

=

l EP Index _  ;

DERGENCY PLAN PROCEDURES INDEX Page 3

~, .

pey, 52 o PEAG BOTICH UNITS 2 AND 3 07/31/85

  • Review Rev. Revisicn Number Title Date No. Date f

i EP-207B DELETED 04/27/84 .:,

EP-207C DELETED 06/26/85 EP-207D Evacuation Assembly Group 04/25/83 3 04/25/83 EP-207E Vehicle and Evacuee Control

j. Procedure 08/01/83 2 08/01/83 EP-207F Vehicle Decontamination Procedure 05/31/83 1 05/31/83 EP-208 Security Team 05/31/83 1 05/31/83 EP-209 Telephone List For Bnergency Use 05/20/85 10 06/11/85 EP-209 Inmediate Notification Call List Appendix A 05/20/85 9 01/11/85 EP-209 DELETED 11/04/81 Appendix B EF-209 Peach Bottan Station Supervision

(

Appendix C .

05/20/85 16 06/11/65 EP-209 On Site anergency Team Leaders -

Appendix D-1 05/20/85 12 06/12/85 EP-209 Dose Assessment Team Appendix D-2 05/20/85 16 05/02/85 EP-209 Fire and Damage Team Appendix D-3 05/20/85 14 06/12/85 EP-209 Personnel Safety Team Appendix D-4 05/20/85 17 06/12/85 EP-209 Security Team Appendix D-5 05/20/85 12 06/12/85 EP-209 Re-Entry and Recovery Team Appendix D-6 05/20/85 4 01/11/85 EP-209 Technical Support Center Group Appendix D-7 05/20/85 16 06/12/85

  • EP-209 Chemistry Sampling & Analysis Team 05/20/85 2 06/12/85 Appendix D-8

( EP-209 Corporate anergency Team Leaders and Appendix E Support Personnel 05/20/85 13 06/12/85

, - - - - - , , - - , - - - - - , . - - . ..w-,-- --- - - --

^

EP Irriex - - - -

. ., IMEGENCY PIAN PROCEDURES INDEX Page 4 Rev. 52

  • PEAG BOITW UNITS 2 AND 3 07/31/85
  • 4 Review Rev. Revision Number Title Date No. Date i

EP-209 U. S. Goverranent Agencies Appendix F 05/20/85 5 06/24/83 EP-209 Meergency Management Agencies

/ Appendix G 05/20/85 6 06/12/85 EP-209 0:sgeny Consultants -

Appendix H 05/20/85 11 06/12/85 EP-209 Field Support Personnel Apperrlix I-l 05/20/85 17 06/14/85 EP-209 Chemistry & Health Physics Contractor Appendix I-2 Call List 05/20/85 16 06/12/85 EP-209 Nearby Public and Industrial Users Appendix J Of Downstream Waters 05/20/85 7 05/03/85 i

EP-209 Miscellaneous Appendix K 05/20/85 6 06/24/83

('

EP-209 rnnal PECo Phones -

Appendix L 05/20/85 6 01/11/85 ,

i EP-209 DELETED 10/21/84 Appendix M EP-209 Medical Support Groups Appendix N 05/20/85 9 06/14/85 EP-209 Staffing Augmentation - 60 Minute Appendix P Call Procedure 05/20/85 12 06/12/35 EP-210 Dose Assessment Toma 09/18/84 1 09/18/84 EP-211 Baergency Radiation Exposure Guidelines and controls . 06/28/85 0 06/28/85 EP-301 Operating the Evacuation Alarm and Pond Page System 12/23/82 1 12/23/82 .a EP-303 Partial Plant Evacuation 06/20/83 2 06/20/83 .

EP-304 DELETED 12/04/81 EP-305 Site Evacuation 06/21/83 5 06/21/83 ,_ ,

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EP-306 Bracuation of the Information Center 05/25/82 2 05/25/82 i

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EP Index --

. .. DERGENCY PIAN PROCEDURES INDEX Page 5 Rev. 52

  • PEAOI BOI'IQ4 LNITS 2 AND 3 07/31/85
  • Review Rev. Revision Number Title Date No. Date

!~

EP-307 Reception and Orientation of Support .:

Personnel 09/18/84 1'09/18/84 D-311 Ocntaminated Injury 06/28/85 4 06/28/85 D-312 Radioactive Liquid Release (Bnergency Director Functions) ,

09/20/84 2 09/20/84 EP-313 Cm trol of Thyroid B3;ocking (KI)

Tablets 09/20/84 1 09/20/84 EP-315 Corporate Canputer Dose Calculations 10/12/84 0 10/12/84 EP-316 Omilative Population Dose c21011ations for Airbourne Releases Manual Method 10/12/84 6 10/12/84 EP-316 Worksheets/ Meterological C21mi1=tions Appendix A 11/08/84 7 11/08/84 kt-316 Activity After Reactor Shutdown Appendix B 10/12/84 6 10/12/84

(

EP-316 Index of X/Q Outputs for Off-gas

  • Appendix C Stack Releases 10/12/84 6 10/12/84

! EP-316 Relative Dispersion Values for Ener-l Appendix D gency Dose c21ci1= tion Procedure 10/12/84 6 10/12/84 l

EP-316 Percent Isotopic Abundance vs. Decay Appendix E Time Since the Reactor Shutdown 10/12/84 6 10/12/84 EP-316 Population Distribution by Cm pass Appendix F Sector - Sumner Day 10/12/84 6 10/12/84 EP-316 I-131/I-133 Per nt Abundan m vs.

, A@endix G Time Since Reactor Shutdown 10/12/84 6 10/12/84 EP-316 Iodince Sourm Term fran 'ICS Field Appendix H Data 10/12/84 6 10/12/84

~~

EP-316A Reading the Rapid Dose Assess-ment I Program into the TI-5C 10/03/84 1 10/03/84 ,

EP-316B culmilating Rapid Dose

[ Assessnent on the TI-59 .

10/03/84 1 10/03/84 EP-316C Reading the Refine Dose Assessment

( I Program onto the TI-59 10/15/84 0 10/15/84 ,

J

-n . -

  • EP Index C.

. . . . . . " ENERGENCY PIAN PROCEDURES INDEX Page 6 Rev. 52

  • PEPG BOF104 (2iITS 2 AND 3 07/31/85 *

, Review Rev. Revision Numb _er Title Date No. Date EP-317 Direct Reommendations to County ..

Emergency Management and Civil Defense Agencies 10/12/04 3 10/12/84 EP-318 Liquid Release Dose C21cilation Method for Intake Water at Downstream Facilities 04/13/83 1 04/13/83 EP-319 Liquid Release Dose P21011ation -

Method for Fish 04/13/83 1 04/13/83 EP-320 Procedure for Leaking Chlorine 03/12/82 1 03/12/82 EP-325 Use of the Contaiment Radiation Monitor to Estimate Release Source Term 06/09/82 0 06/09/82 EP-401 Entry for Emergency Repair and Operations 09/15/84 5 09/15/84 EP-500 Review and Revision of Emergency Plan (FSAR Appendix 0) 04/01/81 0 04/01/81 t

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PHILADELPHIA ELECTRIC COMPANY +

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q I PEACH BOT'IOM UNITS 2 AND 3 ~

EMERGENCY PLAN IMPLEMENTING PROCEDURE i

EP-101 CLASSIFICATION OF EMERGENCIES PURPOSE:

To define the method of classification of an event or condition into one i of four emergency classifications as described in the Emergency Plan.

Additionally this procedure details the method of de-escalation from

. one emergency action level to another. .

4 RF7ERENCES:

1. Peach Bottom Atomic Power Station Emergency Plan
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-lUS, General Emergency Immediate Actions 4 ACTION LEVEL:

Implemented this procedure whenever Shift Supervistoa detects conditions which meet the Emergency Action Levels in Appendix EP 101, Classification Table.

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

t PRECAUTIONS:

THE JUDGEMENT OF THE EMERGENCY DIRECTOR IS VITAL IN PROPER CONTROL OF AN EMERGENCY AND TAKES PRECEDENCE OVER GUIDANCE IN THE EMERGENCY PLAN i PROCEDURE.

IMMEDIATE ACTIONS:

e 1.0 Shift Supervision or Emergency Director shall:

l.1 Select affected categories related to station events

'{ . or conditions.

i 0

) EP-101 1

,' ., )

' Eaga 2 of 3, R'.v. 13 I

IMMEDIATE ACTIONS (cont'd) i Reference  !

Pages in Appendix Category EP-101 Unplanned Shutdown 1 Personnel Injury 2 Primary Con *mimaant Integrity 3 Radioactive Material Release 4 Fire 5 Environmental 6 Loss of Power 7 Secondary containment 8 Instrument Failure 9

(-

Fuel Damage 10 4

Hazards to Station Operation 11 Control Room Evacuation 12 Security , ,

See Contingency Plan 1.2 Beginning at the indicated page in Appendix EP 101, review

! the Emergency Action Levels for all categories selected.

'1.3 If the most severe events or conditions are classified as I an Unusual Event, implement EP 102, " Unusual Event Response."

i

! 1.4 If the most severe events or conditions are classified as

!. an Alert, implement EP 103, " Alert Immiediate Response." , , . _ ,

1.5 If the most severe events or conditions are classified as '

a Site Emergency, implement EP 104, " Site Emergency Response."

1.6 If the most severe events or conditions are classified as a

.. General Emergency, implement EP 105, " General Emergency Response." -.

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l l u .=- : ~ . . -.~~;.---- .:~~---. . . . . . -. . - : 2 - --- - - - -~_ - - .; . _

8 - . . - - . __ _ - , _ _ .____ _ _ _ _ _ _ _ _ _ _ _

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~, *T EP-101

. 'Paga 3 of 3, R:v. 13 j FOLICW-UP ACTIONS i

1.0 If event is classified as Alert, Site Emergency, or General Emergency, l Shift Supervision or Emergency Director shall:

J f 1.1 Periodically evaluate, the event classification as listed on i attached Appendix EP-101. Based upon results of corrective

' action taken to recover from the emergency situation, escalation '

! or de-escalation of the emergency action level classification will be decided upon by the Emergency Director or Interim Emergency Director. (It is preferable, but not mandatory, to obtain concurrence from the Site Emergency Coordinator and Corporate Headquarters prior to classifichtion reduction). The NRC and appropriate off-site authorities at the Emergency Operations Facility all be informed of the decision to move from one emergency class to the next. All agencies or personnel listed in checkoff lists of EP's 102, 103, 104, and 105 shall be informed as a =4n4=_=.

1.2 Provide written sm - ry within eight hours to the NRC concerning

basis and circumstances surrounding reduction of emergency action i level or closecut of the emergency.

. 2.0 If event is cl'assified as an Unusual Event, Shift Supervision or Emergency Director shall periodically evaluate the event classifi-

- cation as listed on attached Appendix EP-101 and escalate or de-( escalate the emergency action level if necessary. All appropriate agencies or personnel shall be notified using the appropriate check- .

off lists of EP-102, 103, 104, 105.

3.0 When the emergency has been mitigated and the_ power plant and auxiliaries I have been placed in a safe shutdown condition, only.then will a decision

! be made as to whether a recovery phase is justified. To enter the recovery phase after the emergency or accident situation is considered l no longer in effect, the concurrence of the Site Emergency ,

Coordinator, Emergency Director, the Emergency C'ntrdl o Officer at j Corporate Headquarters, and Federal and State Government Liaison l is required. The recovery phase,is a departure from an emergency situation. The Site Emergency Coordinator and Emergency Director j evaluates plant operating conditions as well as the in-plant and i out-of-plant radiological conditions in this' decision. Notifications i to the various individuals and agencies that the recovery phase has been implemented is'the responsibility of the Site Emergency i Coordinator.

4 7

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APPENDIX EP-101 -

3 ~', Paga 1 of 12, Rev.'*12 UNPLANNED SHUTDOWN UNUSUAL EVENT AbdT l UNPLANNED SHUTDOWN SCRAM WITH TRIPLE LO LEVEL l

1) controlled shutdown due to failure 1) scram alam and  ;

to meet L.C.O. 2) double low level alarm (-48") and

2) any scram other than planned 3) triple low level alarm (-130") and ,
4) increase in containment pressure '

to greater than 1 psig but less than 2 psig on PR-2/3508

. SCRAM WITH SMALL LEAK

, 1) scram alam and

2) double low level alam (-48") and
3) triple low level alarm (-130") and
4) containment high pressure alam (2 psig) and
5) containment pressure 2 psig or greater on PR 2/3508

(

\ .~ .

SITE EMERGENCY GENERAL EMERGENCY SCRAM WITH IOCA SCRAM WITH LOCA & NO ECCS

1) scram alarm and . 1) scram alarm and
2) double low level alam (-48") and 2) double low level alarm (-48") and
3) triple low level alarm (-130") ,and 3) triple low level alam (-130") and
4) containment high pressure alam 4) active fuel range level indication (2 psig) and shows less than -226" on LI-2/3 Sa) containment pressure 10 psig or 3-91A, B and greater on PR 2/3508 or 5) failure to reset triple low level Sb) containment dose rate greater than alarm after 3 minutes and 105 R/hr on RI-8/9103A/C and 6) containment high pressure alarm RI-8/9103B/D (2psig) and

,7) containment pressure greater than ~ , ~

20 psig on PR-2/3508 or

8) containment dose rate greater than
  • 106 R/hr on RI-8/9103A/C and .

Pl-8/9103 B/D .

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APPENDIX EP-101' -

    • ': Pcg3 2 of 12, R;v. 13 PERSONNEL INJURY .

uNuSou EvEN, uER, f

N/A INJURY WITH EXCESS RADIATION EXPOSURE OR CONTAMINATION ,

1) Contaminated injury warranting off-
  • . site medical treatment or
2) an acute whole body exp 7o ure '

greater than 3 R SITE E.M CY GENERAL EMERGENCY I

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N/A N/A i

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APPENDIX EP-101 -

N Pig 3 3 of 12, Rev. 1[

4 .

PRIMARY CONTAINMENT -

UNUSUAL EVENT ALERT

[

NON-ISOLABLE LEAKAGE ; LOSS OF PRIMARY CONTAINMENT INTEGRITY

1) Primary containment leakrate 1) Reactor Building vent rad effluent is greater than 0.5 percent of high rad alarm and inability to
volume per 24 hrs, at 49.1 psig or maintain pressure greater than i
2) N2 makeup system is not capable of 0.25 psig on narrow range maintaining pressure (not due to PR-2/3508 or j lack of N2). 2) Torus Room flood alarm with level i , decrease in torus

- FAILURE TO ISOLATE PENETRATION WHEN

1) incorrect valve position daring Group I, II, or III isolation alarms

(.

4 SITE EMERGENCY GENERAL EMERGENCY LOSS OF PRIMARY CONTAINMENT INTEGRITY WITH LOCA .

" ~ ~

1) erratic containment pressure N/A

, fluctuations above alarm setpoints ~

of 1.5 psig, and

2) Group II and III isolation alarms, and
3) Containment dose rate greater than 105 R/hr on RI-8/9103A/C and RI-8/9103B/D and SITE EMERGENCY
4) Reactor Building area high temper-continued

^ "

itor P 2 -8 abnormally high, and Reactor Bldg.

  • vent rad effluent high alarm, g 1) containment high pressure alarm.

Main Stack Rad effluent on PR 0 (2.0 psig), and 051 increasing due to SGTS opera- '2) scram, and tion. 3) containment dose rate greater than -.

(

105 R/hr on RI-8/9103A/C and RI-8/

9103B/D, and

4) Reactor BTd7 Area Rad Monitors Alarming, and
5) Vent Stack Rad Effluent monitor high alarm es

APPENDIX EP-101 _.

, , , 'l Pig 3 4 of 12, Rev. I't R ADIO ACTIVE RELEASE I UNUSUAL EVENT ALERT INSTANTANEOUS RELEASE EXCEEDING TECH ACTUAL OR POTENTIAL RELEASE O.01 REM SPECS WHOLE BODY OR O.05 REM THYROID

1) Liquid effluent release exceeding 1) Uncontrollable release for more than Tech. Spec. 3.8.B.1 20 minutes from the: 4
2) Gaseous effluent release exceeding a) main stack greater than45 x 10 ces

. Tech. Spec 3.8.C.1 which may be -

n RR 0- U-051 o_r,,

' detected'by Ehe following:

a. If all releases are from one )ReactoEEldsventgreaterthan (2.5 x 10 cpm on RR-2/3979 or release point

, , 1. A spike on the main 4 stack 2) ' Continued particulate or iodine re-

?- greatet' than 1.8x10 cps on lease such thaT analysis of partrcu -

late filter or charcoal cartridge RR-0-17-051 or- results in the following estimated 2

2. A spike on the reactor bidg. release rates:

5 vent greater than 3x10 cpm - a) main stack greater than 5 x 10 2uC1/

o nn RR-2/3979 g 3,e op -

, b. If the release is from more than b) Beac Er Bldg vent greater than

! one release point 3 x 10 3uC1/sec or i 3) Containment dose rate greater than

1. Aspikeonthemagnstack 104 R/hr on RI-8/9103 A/C and RI-8/9103

._ greater than % 10 cps on B/D

~ ' ~ -

RR-0-17-051 o_r

2. A s' pike on the ' reactor bldg. ,

' 5 g ngp g g than 1x10 ep, _ _ . _ _ . _

SITE EMERGENCY GENERAL EMERGENCY

,;_ ACTUAL OR POTENTIAL RELEASE O.1 REM ACTUAL OR POTENTIAL RELEASE 1.0 REM WHOLE BODY OR 0.5 REM THYROID WHOLE BODY OR 5.0 REM THYROID .

I ~

1) Uncontrollable release for more 1) Uncontrollable release for more than than 20 minutes from the: . .. 20 minutes from the: .

a) main stack greater thag,6.5,x 10 3 a) main stack greater than 1 x.1.0_6_.

i{ cps on RR _0-1,7 -051 cg ,

,on RR _0-17-051 g ,

b) Reactor Bldg. vent greater than I b) Reactor B1'dg vent greater than 5 1 x 106 cpm on RR 2/3979 o_r_,

l

( ,5 x 10 cpm on RR-2/3979 o_r j  ;

2) continued particulate or iodine re- l2) continued particulate or iodine re-lehss such that analysis'of particu- __

late filter or charcoal cartridge lease Auch that.analysia,of.particu .

late filter or charcoal cartridge

'f results in the following estimated . results in the following estimated release rates: 3 release rates:

4 a) main , stack greater than'5 x 10 _ a) main stack greater than 5 x 10 uC1/

uCi/sec or sec_oz

} ..b) Reactor Bldg vent greater than ' -

  • t b)ReactgrBldgventgreaterthan 3 x 10 uCi/sec or 3 x 105 uCi/sec or
3) cogtainment dose ra E greater than )) cc tainment dose ra E greater than 10 R/hr on RI-8/9103A/C and 1 . R/hr on RI-8/9103A/C and RI-8/9103B/D ... __ RI-8/9103B/D ,

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Pig 3 5 cf 12, Rev. . 13 - -

F1RE 12tOSUAL EVElff ALERT I

l FIRE IN PROTECTED AREA LASTING 10 MIN. FIRE WHICH COULD MAKE AN ECCS INOP

> OR MORE AFTER INITIAL ATTEMPTS TO l EXTINGUISH IT 1) Fire alarm and verbal report from SSV

1) Alarm and verbal report from SSV i

e

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SITE M GENERAL EMERGENCY FIRE WHICH MAKES AN ECCS INOP FIRE WHICH CAUSES DAMAGE TO PLANT SYSTEMS SUFFICIENT TO LEAD TO OTHER GENERAL .

1) Fire alarm and verbal report EMERGENCIES from SSV ,
  • * ~
1) Fire alarm and verbal report from SSV, and IDCA symptoms, ECCS, or containment failure

. .a

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, ' APrEADIX 4'P-101 esgo6of12,Reva[3_..;

ENVIRONMENTAL

~ ~

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UNUSUAL EVENT ALERT EARTHQUAKE  ; EARTHQUAKE

1) An actual earthquake detected by 1) An actual earthquako beyond the seismic instrumentation systems Operating Basis Earthquake (OBE)

ABNORMAL POND LEVEL ABNORMAL POND LEVEL

1) Conowingo Pond level on LI-2/3278A, 1) Conowingo Pond level on LI-2/3278A,B, B,Cs , , C:

a) greater than 113 feet or,r a) greater than 115 feet or_

b) less than 104 feet without prior. b) less than 98.5 feet without prior notification by L.D. notification by L.D.

TORNADO TORNADO

1) A tornado is observed on site 1) A tornado strikes the Power Block with identiff able* plant damage -

HURRICANE HURRICANE

1) Hurricane is expected to cross 1) Station is experiencing a hurricane the station with winds greater than 100 mph

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SITE EMERGENCY GDIERAL EMERGENCY EARTHQUAKE

1) An earthquake greater than Design . . . ..

Earthquake as detected on seismic

, instruments ,

ABNORMAL POND LEVEL

1) Conowingo Pond level on LI-2/3278A,B,C exceeding the following limits:

a) greater than 116 feet g b) less than 87 feet 4

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APPF.NDIX EP-101 -

P q3 7 cf 12, R;v.13 LOSS' OF POWER UNUSUALEVEUT ALERT LOSS OF OFFSITE OR ONSITE IDSS OF OFFSITE AND ONSITE AC POWER FOR

POWER LESS THAN 15 MnTUTES
1) turbine generator trip with Startup 1) turbine generator trip with Startup Auxiliary transformer SU2 and SU3 Auxiliary transformer SU2 and SU3 unavailable for service for more unavailable for service and than 60 seconds or 2) failure of all diesel generators to
2) loss of voltage on the four 4160 energize their busses.

volt emergency busses or 480 volt load centers abpplied from the four LOSS'OF ALL DC POWER FOR LESS THAN 15 MIN.

4160 volt emergency busses for more

. , than 60 seconds. 1) less than 105 volts on the 2/3A,B,C

& D distribution panels as indicated on Panels 2/3AD03, 2/3CD03, 2/3BD03, 2/3DD03 and

2) less than 21 volts on the 24 volt distribution panels as indicated on Panels 2/3AD28, 2/3CD28, 2/3BD28, 2/3DD28 and
3) loss of all alarms I . .

SITE EMERGENCY GENERAL EMERGENCY IMSS OF OFFSITE AND OtlSITE AC POWER FOR LONGER THA!! 15 MINUTE 3 .

1) turbine generator trip with SU2 and

. SU3 unavailable for service for

  • longer than 15 minutes and
2) failure of all diesel generators to energize their busses for longer than 15 minutes t4GS OF ALL 125 VDC POWER FOR f4NCER THA!! 15 MINUTES .
1) less than 105 volts on the 2/3A,D, Cs0 distribution panels as indicated
  • on Panels 2/3AD03, 2/3CD03,2/3DD03, .

2/30D03 for longer than 15 minutes and

2) less than 21 volta on the 24 volt -.

I- distribution panels as indicated on Panels 2/3AD20, 2/3CD20, 2/3D020 2/3DD20 for longer than 15 min. and

3) loss of all alartna for longer than 15 min.

E f G E:iD!!3 E p . g g i P;9e 3 cf 12, Rev.13 --.!

i SECOND ARY C@NTAINMENT UNUSUAL WENT ALERT

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IDSS OF SECONDARY CONTAINME!TP INTEGRITY

1) loss of secondary containment integrity for greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 6

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INSTRUMENT FAILURE, UNUSUAL EVENT ALERT SICNIFICANT IDSS OF ASSESSMENT Oft COM-MUNICATION CAPABILITY IN THE MAIN CONTZL ROOM

1) complete loss of all Main Control Room comunication equipment N/A O

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e 4 SITE EMERCENCY CCNCRAI. EMERCENCY e s 84

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" cmemoo cmo66 .

i P ge 10 cf 12, Rev. 9 3 ---

FUEL D AM AGE UNUSUAL EVENT ALERT POSSIBLE FUEL DAMAGE I FUEL DAMAGE

1) Air ejector discharge rad monitor 1) Air ejoctor discharge rad monitor

. high alarm and an increase of 500mR/ indicating greater than 2.5 x 104 mR/

hr within 30 minutes or a level of hr on RR 2/3-17-152, or i 2.5 x 103 mR/hr as indicated on 2) !!1gh coolant activity 7f 300 uC1/gm RR-2/3-17-152, or_ dose equivalent I-131, and main steam

2) high reactor coolant activity as line high-high radiation alarm with determined by sample analysis equal resultant scram alarm, or to or greater than it uCi/gm dose 3) spent fuel damage resulting in a equivalent I-131 refueling floor area radiation monitor

- . alarm or a hi,n radiation alarm on refuel floc. exhaust rad monitor'

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SITE EMERGENCY GENERAL EMERGENCY FUEL DAMAGE FUEL DAMACE

1) Following conditions occurs . D When at least 1 of 4 containment rad a) failure of control rods to fully monitors indicato levels greatnr insert on a scram and , than 106 R/hr on RI-0/9103A/C and b) higher than normal readings on RI-0/9103D/D and containment pressure LPnMa adjacent to not-fully- exceeds 10 poig on PA 2/3500 t- inserted rods and '

c) at least 2 of U 2 4 containment rad monitors indicato levels

' greater than 10 5 R/hr on RI-0/9103A/C and RI-6/910)D/D.

2) Major damage to spent fuel in fuel *-

pool or uncovering of spent fuel as confirmed by a fuel pool area e radiation monitor alam ands e al refuel floor exhaust radiation '

monitor high alam, o_r, b) refuel floor area radiation .

I monitor alarm or

3) Observed major daEgo to spent fuel l

APPLNDIX EP-101

's ) P ge li cf 12, Rev. 13 e '. . o' .. . ,

HAZARDS g UNUSUAL EVENT ALERT MODERATE HAZAPDS SEVERE HAL\RDS

1) Aircraft crash on or near site 1) Aircraft crash on the facility or l as determined by Shift Supervision missile impacts into the Reactor or Bldg. Diesel Generator Bldg. or
2) Significant explosion on or near HPSW pump structure as determined site as determined by Shift by Shift Supervision o_rr Supervision g 2) Explosion damage to facility affecting
3) Toxic gas release on or near site plant safety as determined by Shift as determined by Shift. Supervision Supervision o_r
3) Chlorino gas detected in tho e

Control Room ,

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$ 0 SITE EMERCDICY GENERAL EMCRGD4CY

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P g] 12 cf 12, Rev. , 1-3 a

,. .3 CONTR@L R@@M EV ACU ATION UNUSUAL EVENT ALERT REMOTE CCNTROL ESTABLISHED

1) Evacuation of Main Control Room anticipated or required and control

"!" established at remote shutdown panels as determined by Shift Supervision

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SITE EMEncENCY GENERAL EMERCENCY REMOTE CONTROL NOT ESTABLISifED

1) Evacuation of Main control Room
  • and control of shutdown systems * * **

not established at rerote shutdown panels in 15 minutes as determined N/A by Shift Supervision S %

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I' b D-207A CONMDLLED APPR07D COM, Pege 1 of 12, Dev. 4

j s YOID PREVIOUS ISSUE NelW 4

DISTRIBUTION PIR A 4 ,

, I anImuu1A naemIc muu PEROI BOFICM IMITS 2 Att 3 7,yj.yf BMGMN PUM IMPUMNfING PIOCEDURE EP-207A FIRSP AIIVSEMOt AND RES3]E GROUP PURPOSE:

1.0 S e purpose of this procedure is to define the requirements and provide guidance to conduct first ald/ search and rescue operations.

RESPOl8IBILITIES:

1.0 'the anergency Director is responsible for:

1.1 Activation of entire Personnel Safety Team or First Aid /

Search and Rescue Group 1.2 Approval of obtaining offsite medical assistance.

[ 2.0 personnel Safety Team Imader shall: ,

2.1 Infom the muergency Director of Group activities and status '

2.2 Request Dnergency Director agproval of and obtain offsite medimi assistance if requested by Group Leader.

3.0 First Al# Search and Rescue Group fMr shall:

3.1 Director Group operations.

3.2 Maintain caneunications with Personnel Safety Team reader.

4.0 First At# search and Rescue Group k nitors shall 4.1 Perfom operations assigned by Geog !4ader.

4.2 Maintain consnunications with Group I4ader.

Acrtrw u M L 1.0 21s procedure shall be laplanented whenever personnel are known to be missing, injured, or as required by the Dnergency Director.

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EP-207A Page 2 of 12, Rev. 4

, PRECAUTIGIS ,

, 1.0 Personnel participation in First Ald/ Search and Rescue operations shall be voluntary. .

i 2.0 A&ere to proper radiological controls as much as practicable.

l 2.1 This activity is exempt fran Radiologien1 work permit (RMP) j requirements.

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i 3.0 Personnel exposure should be limited to the administrative guide levels in Appendix FP-207A-1, Dnergency Exposure Limits.

, 3.1 The Bnergency Director may approve exposures in excess of quarterly Peach Botton guidelines.

3.2 Each group member shall control exposure in accordance with AIARA w&.

NorE IF WJTING IG DERGENCY DIRECTTR APPROVAL COULD DBANGER PERSCNEL, THE FIRST AID /SFAROf AND RISCXJE GOUP IKACER M DSCIM TO RDOVE TfE DUURED PElRSCN(s).

PROCIEURE:

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1.0 Irenadiate Actions .

1.1 Personnel Safety Team 14ader shall:

1.1.1 Cantact the First Ald/ Search and rescue Group Imader and direct him to form First Ald/ Search and Rescue Groups.

1.1.1.1 Each Group shall contain a mininun of three mmbers qualified as follow:

1.1.1.1.a Two m obers qualified in First Aid and CPR 1.1.1.1.b one munber a qualified Health Physics h ician.

1.1.1.2 All group msnbers should be familiar with the plant.

1.1.2 Inform the Dnergency Director that First Ald/ Search and Rescue ~

groups have been formed and will enter the plant.

1.1.3 Request amergency exposure limits from anergency Director if necessary.

1.1.3.11hese limits may be adjusted accordingly by the .

mnergency Director l

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'. " ' EP-207A Page 3 of 12, Rev. 4 1.1.4 st Bnergency Director approval of and obtain offsite ical assistance if requested by the First Aid / Search and '

Rescue Group Imader using Appendix EP-207A-4.

1.1.4.1 Use EP-209, Appendix N for additional telephone ntabers if needed.

1.1.4.2 Provide the offsite agency with the following information:

1.1.4.2.a Number of injured persons 1.1.4.2.b Estimated Time of Arrival (Hospitals Only) 1.1.4.2.c Type and extent of Injury 1.1.4.2.d If injury is contamianted 1.1.4.3 Notify Security that offsite medical personnel entrance to Restricted Area is expedited.

1.1.5 Recall First Ald/Seard and Rescue Group when no lcmger required.

1.2 First Aid Search and Rescue Group Imader shall

  • ( 1.2.1 Direct group members to obtain necessary radiation and ,

contanination protection equipnent. 21s equipment may include but is not limited tot 1.2.1.1 Respiratory Protection Equipnent 1.2.1.2 Rad surwy equipnent 1.2.1.3 Anti-Contamination clothing 1.2.1.4 Personal Dosimetry Wis equipnent can be obtained in the plant, or from emergency kits located at the PUB, North Substation, Delta Service Building, EN, or Aux. Cec.

1.2.2 Cbtain the following information prior to dispetdity; group to perform First Aid / Search and Rescue operations ._

1.2.2.1 thaber of missing / injured persons ,

1.2.2.2 None of individuals 1.2.2.3 Individual's last known location _,

I 1.2.2.4 Job individual was performing when last seen

s s, EP-207A Page 4 of 12, Rev. 4 1.2.2.5 Any significent plant conditions or special .

instructions i 1.2.3 Ehsure group is equipped with first aid kit, st;retcher, and

! blanket or can get them enroute.

i j 1.2.4 Attanet to contact missing indivi&aals using the plant paging

system.

1.2.5 coordinate First Aid / Search and Rescue groups to minimise duplication of effort, anount of time, and radiation expasure.

1.2.5.1 Direct gro ve to last known location of individaals using most expeditious route if practicable. Expand .

search to adjacent areas if required.

1.2.5.2 Determine extant of any in*ury and direct a& ministration of first aid.

1.2.5.2.A Ensure that any objects causing contaminated wounds are recovered or annared for isotopic identification if possible.

1.2.6 Inform Personnel Safety Team Leader of extent of injury, actions taken, actions to be taken, and any rectzmaandations to

(. call offsite assistanos.

  • 1.2.6.1 Ocuplete Appendix EP-207A-3 if possible and attach it to the injured person prior to the individual leaving the site.

1.2.7 Direct the First A14/ search and Rescue Group to transport the injured person to a Site First Aid Facility, if practicable.

1.2.7.1 Site First Aid Facilities are located:

1.2.7.1.A Radweste Building, Elevation 135' 1.2.7.1.B Site Medical Dispensary, outside the Security l Fence north of the Circ. Mater Ptap Structure 4

l 1.2.8 Act as llasen between site group and offsite assistance.

1.2.9 Inform Personnel Safety Team Leader when group has ocupleted ---

i its task and is reassembled and accounted for.

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, 1.3 First A14/ Search and Rescue Group Members shall L

{ 1.3.1 Iccate the missing persons and administer first aid as required l

( 1.3.2 Perform radiation and contanination survey of indivi&aal and area i

{

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EP-207A Page 5 of 12, Rev. 4 1.3.3 Transport injured person to Site First Aid Facility if practicable 1.3.4 If contamination is suspected: 4, 1.3.4.1 Wear necessary anti-contamination clothing if practicable NDE: IF M I!UURY IS SEVERE, DfEDIADE M!l DICE TREMNENr IS T M HIGHEET PRICRITY AND RADICIDGICE CONm0ES ARE SECONDARY.

1.3.4.2 Achinister appropriate first aid, being careful to limit the spread of contamination and li: nit personnel exposure. ,

1.3.4.3 Prepare the injured person for transport by covering the contaminated area with protective wrap. This may require placing the wrap on the stretcher and then covering the person after loading onto the stretcher.

1.3.4.4 Transport the individual to a convenient place to be picked up and transported offsite.

1.3.5 When transporting an injured person to an offsite medical

( facility, a Health Physics Technician shall acocupany the person to assist the medical staff. .

1.3.6 A second HP should also report to the hcrpital if available.

This is not required if a previous transport of injured has occurred and it is known that HP Technicians are at the hospital.

i 1.3.7 Recover any contaminated articles of clothing that may have l

been removed frcza the person for isotopic analysis.

1.4 Site Physicians Assistant or his designee shall:

i 1.4.1 Provide guidance to the First Ald/ Search and Rescue Group

~

Imader as much as practicable if requested by the Personnel Safety Team Leader.

2.0 votJANUP ACTIONS e

2.1 First A14/ Search and Rescue Group Mmbers shall 2.1.1 Pbilow normal decontmaination and disposal practices when task is ocepleted. _ _ ,

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EP-207A Page 6 of 12, Rev. 4

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2.1.2 Return to designated assembly area and report to the First ,

! Aid / Search and Rescue Group Leader.

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! 2.2 First AicVSearch and Rescue Group Imader shall: .

2.2.1 Return to designated assembly area.

2.2.2 Report results of any actions to the Personnel Safety Team Leader.

2.2.3 Account for all Group members. -

2.2.4 Inform Personnel Safety Team Leader of accountability. .

I 2.2.5 Arrange for inventory and restocking of first aid kits and facilities if necessary.

2.3 Personnel Safety Team Leader shall:

2.3.1 Verify injured arrives at medical facility 2.3.2 Inform Emeroency Director of results of any action taken by First Aid / Search and Rescue Group.

2.3.3 Request that Emergency Director notify the Emergency Medical

( Director and Ccanunications Coordinator of identity and condition of injured. .

FDEL CNDITIWS 1.0 Injured person (s) being treated at hospital, by local physician, or has been transported for treatment.

2.0 Missing person (s) have been accounted for, or found.

l 3.0 Reports and briefings have been accomplished.

4.0 First Aid / Search and Rescue group dismissed by Personnel Safety Team Leader.

APPENDICES o

1.0 Appendix EP-207A-1, Bnergency Exposure Guidelines 2.0 Appendix EP-207A-2, First Aid Related Muipoent in Power Block

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( 3.0 Appendix EP-207A-3, First Aid / Search and Rescue - Injury Peport

! 4.0 Appendix EP-207A-4, Medical Support Group Telephone List i

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EP-207A Page 7 of 12, Rev. 4 i

REFERENCE _S_: ,

! 1.0 PBAPS Bnergency Plan 1.1 Section 5.2.1.5.7.1 First Aid / Search and Rescue Group 1.2 Section 5.2.1.6 Ncm-Corporate Support Personnel i

1.3 Section 6.7.1.1.6 Search and Rescue 1.4 Section 6.9.2 Decontaminatibn and First Aid l.5 Section 6.9.4 Medical Treatment 2.0 NUREG 0634 3.0 FP-207 Personnel Safety Team 4.0 PECo Official Bulletin, Serial No. 437-R3 I

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  • D-20'A Page 8 of 12, Rev. 4 l APPDIDIX D 207A-1 DIERGENCY EXPOSURE GUIDELINES
  • 1 Projected Whole Body Thyroid Authorized Ftmetion Dose Dose By
1. Life Sa' ting and Emergency **

Reduction of Injury 75 rem

  • 375 rem Director
2. Operation of BIuiht to Mitigate an Emergency **

Dnergency 25 rem

  • 125 ran Director
3. Protection of Health and Safety of the Bnergency Public 5 ran 25 rem Director
4. Other Emergency 10 CFR 20 10 CFR 20 Bnergency Activities limits limits Director
5. Re-Entry /1 Recovery Administrative Administrative Activities Guidelines Guidelines N/A

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Reference:

DA-520/1-75-001 Table 2.1 *

    • Such exposure shall be on a voluntary basis

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. . EP-207A Page 9 of 12, Rev. 4 l

APPENDIX EP-207A-2 FIRST-AID REEA'IED EQUIPMDTP IN POWER BIDCK

, First Aid Stretchers Kits Blankets Unit 2 Rx Bldg Elevator Stairwells 116' Elev X X X 135' Elev X X X 165' Elev X X X 195' Elev X X X 234' Elev X X X Unit 3 Rx Bldg Elevator Stairwells 116' Elev X X X 135' Elev X X X 165' Elev X X X 195' Elev X X X 234' Elev X X X Turbine Bldg Elevator 116' Elev X 135' Elev X 150' Elev X 165' Elev X

( Turbine Bldg

, Iaundry Room 116' Elev X X X .

Radwaste Bldg Medical /Decon Roca 135' Elev X* X Diesel Gen Bldg (Each Rocm) X Bnergency Cooling Tower X 2SU Switchgear Bldg X 3SU Switchgear Bldg X

  • 2 Orthopedic stretchers located here.

NOIE: 1/2 mile rays (emergency flashlights) are located just outside door to Unit 2 side of main control room in cabitiet. ----

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Page 10 of 12, Pev. 4 APPHOIX EP-207A-3 FIRST AID /SEABN AND RESCUE GROUP INRRY REECIE IGM .:

(PREPARE IN DUPLICA'!E)

DUIRED PERSCN'S NME AGE 3ARSHAW BADGE NO CR SOCIAL SEGRITY NO MAIR ED9JE TYPE AND ICCATIN T DUIRY RADIOAcrIVE CINEAMINATICN YES NO IEVEL IOCATICN

( RADIATICN EXPOSUPE ESTIMA'IE MIERE DID INARY OCCR PREPARED BY FIRST AID GROUP LEAIER SIGRL'UNS GROUP !G EERS t

e IF PRACTICABLE, IMHARD WIGINAL, WITH 'IHE PERSW, 'IO THE SITE FIRST AID FWTTY CR HOSPITAL AS APPBOPRIA'IE.

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. D-207A Page 11 of 12, Rev. 4 i

) APPENDIX EP-207A-4

} M!: DICAL SUPPORP GROUP PHONE LIST l

rn=1 Physicians f

~ Office Hcme 1st Ch [oice-

]

r 2nd Choices s

Harford Menorial Hospital (Contaminated or Otherwise)

    • chboard)

Radiation Management Corporation (Serious Ccntamination/cr Exposure

  • m11tiple contaminated perscnnel)

Dreferred AlternaH t=

D i

(Beepet .

Antulance l

Delta-Cardiff is first responder Fawn Grove is second responder if Delta-Cardiff is not available.

Both units are dispatched by York Country Control York County Control #

l Call Contro1 A Shift Cler (

Medical Director

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.... AuJch Ttne Only)

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Pager __

h tone, dial the ntaber you want him to call. .

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EP-207A Page 12 of 12, Rev. 4 i

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Pager -. . ,s _.

1[ Touch Tcne only) the tone, dial the ntsnber you want him to call.

  • Serious Ccotaminatiost / Dcposure is any of the following:

Whole Body Scposure greater than 25 REN; Skin exposure greater than 15n REM; Dctremity exposure greater than 375 REN; Contamination causing body ocatacted reading of greater than 1 MR/HR; Suspected oc actual inhalation or ingestion of measurable quantitles of radioactive material.

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