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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-101 Re Classification of emergencies,EP-103 Re Alert Response & EP-104 Re Site Emergency Response.Revised Index Encl
	ML20054F299
Person / Time
Site:	Peach Bottom
Issue date:	05/25/1982
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20054F261	List: ML20054F260; ML20054F262; ML20054F299;
References
	PROC-820525, NUDOCS 8206160042
	Download: ML20054F299 (140)
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                                                                                 . <         ED IN9EV EMERGENCY PLAN PROCEDURES INDEX              .      PAGE 1 REvo 16 ;
                                                                              ){~

RECUVUI PEACH 30TT0". UNITS 2 AND 3

     ,                                                                                       05/25/82 y 'l - 21902                                      REVIEW     REV. REVISICN bu32tS                                 111LE                  __DAIE_      39t __2Alf.__

EP-101 CL ASSIF ICATION OF EMERGENCIES 05/23/82 5 05/23/92 EP-10? UNUSUAL EVENT RESPONSE 05/23/82 5 05/23/92 ? EP-103 ALERT RESPONSE 05/11/82 fI Ar 05/11/92 EP-104 511E EMERGENCY RESPCNSE 05/23/82 5 05/23/92 EP-10S GENERAL EMERGENCY RESPD SE 05/23/82 5 05/21/P.2 ? EP-110 P E R i> 0 f.'. E l ASS E"JL Y ANO ACCOUNTABILITY 04/14/87 0 04/14/92 EP-201 TECHNICAL SUPPORT CENTER (TSC) ACTIVATION 05/11/82 3 05/11/92 EP-202 OPfkATIONAL SU' PORT CENTER (CSC s ACTIVAT ION 04/08/92 2 04/04/?2 EP-203 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION 05/11/82 3 35/11/92 EP-205 RA0!ATION PROTECTION TEAM l AC T I VA T ION 04/08/82 3 04/08/32 EP-2GSA CHEMISTRY SAMPLING AND ANALYSIS GRGUP 05/25/82 4 05/25/82

E P- ?LS A RE T AILVING AND CH ANGING S AMPLE

      .3           FILIEd5 AB.O C ART R IDGE S FROM THE ORY. JELL RA3!ATION MUNITOR DUO. I N G EMLRGENCIES                                       05/25/82       0     05/25/62 ?

EP-205A OBTAINING REACTOR WATER SAMPLES . 5 FROM S AM3L E SINK S FOLLOWING ACCI DENT CONDITIONS _5/25/82 0 05/25/t? : EP-2CSA 03TAlteING LIQUID RADWASTE SAMPLES

      .8           FROM RA0 WASTE SavPLE SINK FOLLOWING ACCIDENT CO.0ITIONS                               05/25/82       0     05/25/82 0 EP-205A       OST A ihl %G S AuPL ES FROM CONDENSATE 9        -

SA*0LE S i t< K FCLL9 WING ACC19ENT CON'ITIONS J 05/25/82 0 05/25/82 : EP-?OSA OdT A INIt.G OF F-S AS S AMPL ES FROM

      .10          TH E Of F-G A S H YC'< O GE N AN AL YlER FOLL 0 w ! NG AC C I DE N,T,,C7ND I T I ONS       05/25/82       0     05/25/82

( ED-205A SA93LE PREPARATl?N AND CHEMICAL

     .11           ANALYS!5 OF HIGHLY RADIDALTivt 8206160042 820611 DR ADOCK 05000277                           -

PDR

           .                                . EMERGENCY PLAN PROCEDURES INDEX                      ,

PAGE 2 REvo 18 0 PEACH BOTTOM UNITS 2 AND 3 05/25/82

e REVIEW REV. REVISION ML1BE3 111LE _DAIE2 N0a . .__D al E_

LIQUID S AMPL ES 05/25/82 ~0 05/25/92

EP-205A SAMP1.E PREPARATION AND ANALYSIS -

ol? 0F HIGHLY R ADIOAC TIVE P ART ICUL AT E FILTERS AND IODINE CARTRIDGES 05/25/82 0 05/25/82

      .EP-205A          SA*PLE P' REPARATION AND ANALYSIS OF
       '.1 3           HIGHLY hADI0 ACTIVE GAS SAMPLES                       05/25/82              0   05/25/82

EP-205B RADIATIO SURVEY GR OU PS 04/08/82 2 04/09/92 EP-205C P E R 5 0'.N E L DOSI"ETRY BI7 ASSAY ,

AND RESPIRATORY PROTECTION GROUP 04/Od/S2 2 04/08/S2 EP-206 FIRE AND DAMAGE TEAM ACTIVATION 04/19/62 4 04/19/82 EP-206A FIRd FIGHi!NG GROUP 04/19/82 2 04/19/82 EP-206B EMExGENCY REPAIR GROUP 05/23/32 2 05/23/82

EP-207 PERSONNEL SAFETY TEAM ACTIVATION 05/11/82 4 05/11/82 EP-207A SEARCH AND RESCUE 04/14/82 2 04/14 /R2

( EP-2078 PERSONNEL ACCOUNTABILITY , 05/11/82 3 05/11/82 EP-207C FIRST AID 04/14/82 2 04/14/82 EP-2070 PERSONNEL MONITORING ANL . DECONT AMIN AT ION . 04/08/82 2 04/OR/92 EP-207E VEHICLE AND EVACUEE CONTROL

PR OC E DUR E- 04/08/82 0 04/09/92 EP-207F VEHICLE DECONTAMINATION PROCEDURE 04/14/32 0 '04/14/82 EP-208 SECURITY TEAM .

04/01/81 0 04/01/81 EP-209 TELEPHONE LIST FOR EMERGENCY USE 04/26/82 4 04/26/92 EP-209 IMMEDIATE NOT IFIC AT ION CALL LIST APPENDIX A 04/26/82 4 04/26/82 EP-209 PHILADELPHIA EL EC TR IC APPENDIX B COMP ANY OFFICIALS 07/23/81 1 07/23/81 EP-209 PEACH BOTTOM STATION SUPERVISION j APPENDIX C *% %. 04/08/82 4 04/03/32 ( EP-209 ON SITE EMERGENCY TEAM LEADERS APPENDIX D-1 04/08/92 3 04/08/92 l

             . _ . . ..     .    . . . _ ~        . .  ..L..    .. .         .. . ... ..- -     ..    - - . . . _ ,.

    #~
               .                         EMERGENCY PLAN PROCEDURES INDEX

REve 18 0

  .,                                        PEACH BOTTOM UNITS 2 AND 3            ,

05/25/82

REVIEW REV. REVISION GU3BEB lilLE __Di1E__ $Da __2ilE__

EP-209 RADIATION SURVEY TEAM APPENDIX D-2 04/26/82 3 04/26/82 EP-209 FIRE AND DAMAGE TEAM APPENDIX D-3 04/26/82 3 04/26/82 EP-209 PERSONNEL SAFETY TEAM APPENDIX D-4 04/26/82 3 04/26/82 EP-209 SECURITY TEAM APPENDIX D-5 , 04/26/82 3 04/26/82 EP-209 RE-ENTRY AND RECOVERY TEAM APPENDIX D- 6 04/26/82 2 04/26/82 EP-209 TECHNICAL SUP,POR T C ENTE R TEAM APPENDIX D- 7 04/26/82 3 04/26/82 EP-209 CORPORATE EMERGENCY TE AM LEADERS AND APPENDIX E SUPPORT PERSONNEL 04/26/82 4 04/26/82 EP-209 U. S. GOD.RNMENT AGENCIES ( APPENDIX F . 04/08/82 2 04/08/82 EP-209 EMERGENCY MANAGEMENT AGENCIES APPENDIX G 10/16/81 2 10/16/81 EP-209 CCWP ANY CONSULTANTS APPENDIX H 10/16/81 2 10/16/91 l EP-209 FIEL D SUPPORT PERSONNEL APPENDIX I-1 04/14/82 6 04/14/92 , EP-209 RAD SERVICES CALL LIST I APPENDIX I-2 . 05/06/82 4 05/06/82 EP-209 NEARBY PUBLIC AND INDUSTRIAL USERS APPENDIX J 07/23/81 1 07/23/81 EP-209 MI SCELL ANEOUS APPENDIX K 07/23/81 1 07/23/81 EP-209 LOCAL PECO PHONES ' APPENDIX L - 07/23/81 1 07/23/81

l. EP-209 0E L E TED DEL ET ED APPENDIX M N

( dP-209 MEDICAL SUPPORT GROUPS . APPENDIX N 04/26/82 3 04/26/82 1 7 . . _ . . . . _ _ _ , . . ._ .. .

      ,                                                   EMERGENCY PLAN PROCEDU.7ES INDEX                                                . PAGE 4 REvo 18 *
        -                                                        PEACH 80TTOM UNITS 2 AND 3                                                     05/25/82 *

REVIEW REV. REVISION Sk3HER TITLE __ DALE __ SQa __QAl[__

l . EP-209 STAFFING AUGMENTATION - 60 MINUTE APPENDIX P CALL PROC'EDURE . . 03/05/82 1 03/05/82 E P.-301 OPER ATING THE EV ACUATION AL ARM AND POND PAGE SYSTEM e 04/01/81 0 04/01/81 EP-303 PARTIAL PLANT EVACUATION 12/22/81 1 12/22/81

                                  'D E L.E T ED
             .EP-304                                             ,                                                                     ,

LP-305 SITE EVACUATION 03/05/82 3 03/05/82 EP-306 EVACUATION OF THE INFORMATION CENTER 05/25/82 2 05/25/82

EP-307 RECEPTION AND ORIENTATION OF SUPPORT
PERSONNEL 04/f2/82 0 04/12/B2 EP-311 HANDLING PERSONNEL h!TH SERIOUS INJURIES, RADIDACTIVE CONTAMINATION EXPOSURE, OR EXCESSIVE RADIATION EXPOSURE EMERGENCY DIRECTOR FUNCTIONS 04/08/82 3 04/08/82

( EP-312 , R ADI0 AC T IVE L IQJID RELE ASE (EMERGENCY DIRECTOR FUNC TIONS) 04/01/81 0 04/01/81 EP-313 CONTROL OF THYROID 8 LOCKING (K!) T ABL E T S 04/08/82 0 04/08/82 EP-316 CUMULATIVE POPULATION DOSE CALCULATIONS 05/06/82 2 05/06/82 l EP-317 DIRECT RECOMMENDATIONS TO COUNTY ! EMERGENCY MANA3EMENT AND CIVIL DEFENSE AGENCIES 04/14/82 0 '04/14/82 EP-318 LIQUID RELEASE DOSE CALCULATION ~ METHOD FOR DRINKING WATER 05/06/82 0 05/06/82 EP-319 LIQUID RELEASE DOSE C ALCUL ATION METHOD FOR FISH 05/06/82 0 05/06/82 EP-320 PROCE DUR E FOR LE AKING CHLORINE

03/12/82 1 03/12/82 EP-401 ENTRY FOR EMERGENCY REPAIR, OPERATIONS, AN3 SEARCH AND RESCUE 04/08/82 3 04/09/82 EP-500 REVIEW AND REVISId4~0F EMERGENCY

( PLAN.(FSAR APPENDIX 01 04/01/81 0 04/01/91 ( . . . .

HP-101 l

                                                           ---_    ';.                       P. e. p . 1 . .I t, u. . v . ' . '
         . +

EGl':LLh g;.yL - pt,i r s : . ..( (LADELPilIAELECTRICCOMPANY PEACH BOTTOM UNITS 2 AND 3 EMERGENCY PLAW IMPLEMENTING PROCEDURE EP-101 CLASSIPICATION OP LNLE*ENCICS PURPOSE To define the method of clnusificatiors of so event or conili Lion inLu ont-of four emergency classifications as described in the Emerquncy Plan. Additionally this proceduru details thu method of do-uucalaLion from one emergency action level to another. REFERENCES

1. Peach Bottom Atomic Power Station Emergency Plan

2. NUREG 0654 Criteria for Preparation and Evaluation of Radiological Emergency Responso Plans and Preparedness in Support of Nuclear Power Plants.

3. EP 102, Unuuual Evuut immediate AcLivuu k 4. EP 103, Alert Immediate Actions

5. EP 104, Site Emergency Immediate Actions

6. EP 105, General Emcrgency Immediato Actions ACTION LEVEL Implemented this procedure whenever Shift Supervision detectu conditionu which meet the Emergency Action Lcvols in Appendix EP 101, Classification Table.

IMPLEMMNTATTON Ol' Tilt!; PRfX.'MDURH IX)MS NUI' L1)N ;TJTLITU IMPLEMENTATION OF THE EMERGENCY PLAN.

PkMCAUTIONS THE JUDGEMENT OF THE EMERGENCY DIRECTOR IS VITAL IN PROPER CONTHOI. OF AN EMERCENCY AND TAKES PRECEDENCE OVER GUIDANCE JN TilM EMERGMNt'Y Pl.AN PROCEDURE. IMMEDIATE ACTIONS ( l.0 Shift Supervision or Emergency Director shall: 1.1 Select affected categories related to station events or conditons.

   - . -           --,n      .      .,--.v     . - . - - -             -        .~

W ifP-lOl P. . . . ;' . .: t, s c. .v . e. IMMEDIATE ACTIONS (cont'd)

.(

Roference l'ayen in Appendix

 ;      Category                                              EP-101 Unplanned Shutdown                                           1 Personnel Injury                                             2 Primary Containment Integrity                                                    3 Radioactive Material Release                                                      4 Firo                                                         5 .

Environmental G Loss of Power 7 Secondary Containment U Instrument Failure 9 ( Fucl Damagc 10 Hazards to Station Operation 11 Control Room Evacuation 12 Security Sec Contingoney Plan 1.2 Beginning at the indicated page in Appendix EP 101, review the Emergency Action Levels for all cat.cyories selected. i 1.3 If the most severo cvents or condi tions are cl.inni t'ieti .in { an Unusual Event, implement EP 102, " Unusual Event Hosponso." 1.4 If the most sovere events or conditions nro classified as an Alert, implement EP 103, " Alert immudi.ite Hospunne."

1.5 If the most severe events or conditions arc classified ns a site Emergency, implemer.a EP 104, " Site Emergoney i<osponne."

1.6 If the most severe events or conditions are classified as a l General Emor,qcncy, impicmont EP 105, "Gonoral Emorgency Responso." l l t m

[h.hhh EP-}01

      .                                                                       l'. nje t est 1, l<e U . 's FOLLOW-UP ACrIONS
 .(      l.0 If event is classified as Alert, Site Energency, or General Emergency, Shift Supervision or Emergency Director shall:

1.1 Periodically ov 43 u.ato the ovent clanui fic.iLion .su lintud on 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 tno Site Emergency Coordinator and Corporate Headquarters prior to classification reduction). The NRC and appropriate off-sito authoritics 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 minimum. 1.2 . Provide written summary within eight hours to the NRC concerning basis and circumstances surrounding reduction of emergoney action level or closcout of the omorgency. 2.0 When the emergency has been mitigated and the power plant and auxiliarios have been placed in a safe shutdown condition, only then will a decision be made as to whether a recovery phase in :)unt i fical. 'n. un t er t he recovery phaso .'after the cmcrgency or accident uitu.itivo is conuideseil k no longer in effect, the concurrence of the Sito Emerqcncy Coordinator, Emergency Director, the lancrqcan y (JunLrol 01ficer .it Corporate Headquarters, and Federal and State Government Liaison is required. The recovery phase is a departure from an cmergency situation. The Site Emergency Coordinator and Emergency Director evaluates plant operating conditions as wol) as the in-plant and out-of-plant radiological conditions in tinis slucision. Noti fica tions to the various individuals and agencies that the recovery phase has been implemented is the responsibility of the Site Emergency Coordinator. I

un u2DM atn*-00I l'o:Ju 1 of 12, Rev. s. U N kL A N N5 b S Ui[TD O WN UNUSUAL EVENT .( A3,t; n-UNPLANNCD SilUTDOWN

SCHAM W1Til THit*LE LO 1.1;V1:1.

1) controlled shutdown duc to failurc 1) scram alarm and to meet L.C.O.

2) any scram other than planned 2) double low level alarm (-48") and

3) triple low level alarm (-130") and

4) increase in containment pressure to greater than 1 psig but loss than 2 psig on PH-2/3508 SCHAM WITII UMAJ.l.1.EAK

1) scram alarm and

2) double low love) alarm (-48") and

3) triplo low lovel alarm (-130") alu l_

4) containment higli pressure alarm (2 psig) and '

5) containment pressure 2 psig or greater un PH 2/3bOH

(

SITE EMERGENCY GENCHAL EMERGENCY SCRAM WITH LOCA SCRAM WITil LOCA g NO ECCS

1) scram alarm and 1) scram alarm and

2) doubic low lovel alarm (-411") and 2) double low lovel . alarm (-4H") a t i,d

3) tripic low level alarm (-130") and

3) triple low lovel alarm (-130") pu,d

4) containment high pressure alarm (2 psig) and 4) activo fuel range Icvc1 indication Sa) containment pressure 10 psig or shows less than -226" on 11-2/3-/-

3-9]A, H and greater un PR 2/JSOU g b) failure to rusel triple juw level iSb) containment dose rate greater than 105 R/hr on RI-8/9103A/C and alarm after 3 minutos and

6) containment high prossu'r'c' ajarni

RI-8/9103B/D (2 psi g) and

7) containment presuure greater than 20 psig on PR-2/3508 Ed

8) containment dose rate greater th.ui 106 H/hr un HJ-H/9103A/C and .

RI-8/9103 B/D (

Al'l:END1 X l;l*- 1 O l l'. erJ< * ;* e e l' I ;' o Ice v0 '. PERSONNEL INJURY : UNUSUAL EVENT ! .( ALUMT I _ INJURIES REQUIRING AMBULANCC AND 48 IIOUR TRT:ATMUNT

1) Verbal reports or direct observation N/A I INJURY WITH EXCESS RADIATION EXPOSURE OR r CONTAMINATION

1) Contaminated injury warranting off-site medical treatment E

2) an acute whole body exposure greater than 3 h t -

SITE EMERGENCY . . . GENCHAL EMERGENCY 4 N/A N/A e

                                                                                               -.-.----..1

Al'l'EN!JAX Fl*- 1 U l l'.ago 3 o f l a, so.v. S PRIMARY CONTAINMENT

r i UNUSUAL EVENT _ _ _ . . '

  .I                                                                             ALEHT NON-ISOIABLE I.EAV. AGE  ,

TOSS OF PHIMARY CONTAINMl;NT INTAGluTY

1) Primary contairmient leakraLu 1) Huautor 11uilding vuot rad uf fluenL is greater than 0.5 percent of volume per 24 hrs at 49.1 psig or_ high rad alarm and inability to

2) N 2 makeup system is not capable of maintain pressurc greater than maintaining pressure (not due to 0.25 psig on narrow range lack of N2 ). PR-2/3508 or 2)

Torus Room firal alarm with level decrease in t'.>ruu FAILURE TO ISOLATE PENETRATION MIEN ISOLATED BY A TRANSIENT

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

( SITE EMERGENCY -_. GENERAL EMERGENCY LOSS OF PRIMARY CONTAINMENT INTEGRITY WITH LOCA

1) erratic containment pressure N/A fluctuations abovo alarm setpoints of 1.5 psig, and_ ,

l

2) Group II and III ibulation alarms, i

and ! 3) E tainment dose rate greater than 105 R/hr on RI-8/9103A/C and RI-8/9103B/D and

4) Roactor Building area h2cjh temper- g ,,,g ,,g ,y ature alarm, or Area Itadia L a.on .

e:on t i nued Monitors on PR 2/3-16-55 POTENTIA!.14)SS OF PHJ MAHY CONTAINMENT ll1Gil l l abnormally high, a,nd Reactor nldg. RADIATION vent rad effluent high alarm, or i) containmenL high pressure alarm. Main Stack Rad offluent on PR 0 (2.0 psig), and 051 increasing due to SGTS opera- 2) scram, and tion.

3) conteniemeent <loso rate greater Liian

( lof* R/br on 910311/11, andHI-it/9103A/c .init au-st/

4) Reactor BTdQ Area Rad Monitors Alarining, and

5) Vent Stack Rad Effluent monitor high alarm

_ _ . - . _ . = _ . - .;

Al*PENDIX _- EL',-l[I ' I aep. 4 e el I.', i t. .v . *. RADIOACTIVE RELEASE - i UNUSUAL EVENT -. '__ _.. . .. .. [ .( ALuny h INSTANTANCOUS RELEASE EXCECDING TECil ACTUAL OR POTl;NTIAI. RMI. CASE O.01 lu;M i I SPECS WiiO!.C h0DY OH 0.05 Id.M TilYuolls

1) A spike on rad effluent monitors: 1) I a) Main Stack greater than 6 x 103 Uncontrollable release for more than -

cps on RR O-17-051, or 20 minutes from the: , b) Reactor Bldg vent greater than a) main stack greater than 1 x 103 m 8 4 x 10 4cpm on RR-2/3979 or on RR 0-17-051 or 1 b) Reactor Bldg vee greater than

2) Analysis of particulate filters or 5 x 104 cpm on kR-2/3979 or ['

charcoal cartridgc: a) Main Stack greater than 5, x 10 1

2) Continuod particulato or iodinc re- ,

uCi/sec, o_rr lease such that analysis of particu- ! b) Reactor Bldg vent greater than late filter or charcoal cartridge t 4 x 101 uci/sec results in the following estimated i relcaso rates: a) main stack greater than 5 x 102 uci/ l sec or , RELEASE EXCEPDING TECll SPEC l QUARTERLY LIMIT b) ReacEr Bldg vont greater than " 3 x 103 uCi/ soc ,o_r

3) Containment dose rate greater than {

1) A report of the summation of 104 R/hr on RI-8/9103 A/C and 1

individual release data within RI-8/9103 B/D l the quarterly period. f 6

CITE EMERGENCY GENCHA1. nMnHGUNcy ACTUAL OR POTENTIAL RELEASE 0.01 REM WHOLE BODY OR O.05 REM THYROID ACTUAL OH POTENTIAI HELEASE 0.01 HUM WiiOLE BODY OR 0.05 REM TIIYROID

1) Uncontrollablo relcaso for more 1) than 20 minutes from the: Uncontrollabic releauc for m re than ;

a) main stack greater than 1 x 104 20 minutes from the: ' a) main stack great.cr than J x 105 cp3 cps on RR 0-17-051 o_r on RR 0-17-051 or b) Reactor Bldg. vont yrcatcr than h) Huaut or hiely vent greater th.us 5 x 100 c1xn on HR-2/3979 or

2) 5 x 100 cpm on RH 2/3979 g continued particulate or iodine re- 2) continued particulate or iodino re-lease such that analysis of particu- Icaso nw:h that suialysis of partien-lato filter or charcoal cartridge results in the following estimated latu l'ilter ear charcoal ca r t e isl< n- !

release rates: results in the tullowing usLimated a) main stack greator than 5 x 103 release rates: uCi/sec or a) main utocl.- greater Lhan 's x IU4 uCi/ sec or b) Reactor 4 Bldg vent greater than b) Reactor Bldg vont greater than 3 x 10 uCi/se:: or 3 x 105 uCi/sec or

3) containment dose rate greater than 3) contairunont doso rato greater than 105 R/hr on HI-U/9103A/C and I

( RI-8/9103B/D lO ' H/br on Hi-H/9101A/C . uni RI-8/9103B/D

Al'PENDJX FI'-IO1 l'. iip * 'e a el ' 13, luev. 5 FlRE UNUSUAL LVENT ( ALEuT FIRE IN PHOTECTED AREA LASTING 10 MIN. OR MORi; APTIlt INITI AI. A'1*rlRl"fL *10 FIRE WilICll, COU),D, ,MAK,1; AN_l;;C,CS J,NOl' EXTINGUISli IT

1) Fire aliarm and verbal report, from SSV

1) Alarm and verbal report from SSV 9

l e ( . SITE EMERGENCY GENCHAL EMERGENCY FIRE WilICll MAKl'S AN ECCS INOP FIRU WillCll CALISI:S DAMAGil TO PLANT SYST1;MS

1) Fire alarm and verbal report SUFFICIENT EMERGENCILS I TO LEAD TO OTHER GENERAL from SSV

1) Fire alarm and verbal report from SSV, and IDCA .<iymptoms, ECCS, or cont.iinnent failurc 6

               .                       *                                                                              ..-    _. i

APPENDIX EP-101 p,irpt 6 of 12, Hov. ', E5EIR O N ME N T A L UNUSUAL EVENT I ALCler EART11QUAXE ; EARTliQUAKU

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

ABNORMAL POND LEVEL ABNORMAL POND LEVEL

1) Conowingo Pond level on LI-2/3278A, 1)

B,C: Conowingo Pond level on LI-2/~1274tA,H, C a) greater than 113 feet or a) greater than 115 feet or b) less than 104 feet without brior 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 identifJable plant damage

           ,           HURRICANE HURRICANC

1) Hurricane is expected to cross

1) Station in experiencinci.i h u r r i c. n u -

the station with wisph; greaLur Lhan 1U0 mph ( - SITE EMCRGENCY .. GENCHAL I M RGUNCY CARTilQUAKU

1) An earthquake greater than Design Earthquake as detected on seismic j instruments j ABNORMAL POND LEVUL

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

a) grouler Lhara lit feuL g b) less than 87 feet (

l'.sen 7 ol' 12, ke .v . 'i LOSS OF POWER UNUSUAL EVENT

                                                                                                                    ,    < ALut<T t'

LOSS OF OPPSITE OR ONSITU. LOSS OF OPPS17 E AMs UN!;1TH AC l' owl:R FOR POWER L,US,L;' PIA,N, ,1,'.,,, MI N')TE!.

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 ~f6r service and than 60 seconds or 2)

2) loss of voltage on the four 4160 failare of all dicsol generators,to energica their,buuucs. <,

volt emergency busses or 480 volt ' e; [ ' load centers supplied from the four 4160 volt emergency busses for more wSS OF ALL DC POWEk POH LCSS TIMN 15' MIN.

         ,   than 60 seconds.                                                                '

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

                                                                                                         & D distribution panels as indicated on Pancis 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 t                          -

1 SITE EMERGENCY GENERAL EMERGENCY LOSS OF OPPSITE AND ONSITE AC POWER POR LONGER THAN 15 MINUTES

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 LOSS OF ALL 125 VDC POWER FOR LONGER illAN 15 MINUTES

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 for longer than 15 minutes .

and

2) less than 21 volts on the 24 volt distribution panels as indicated on

( Panels 2/3AD28, 2/3CD28, 2/3BD28 , 2/3DD28 for longer than 15 min. and '

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

i e

l j

wra a cyovunrv Ess-}Oj l'.itic H ul 12, Rev. 'i SECONDARY CONTAINMENT _ _ _ . UNUSUAL 1, VENT . A1.ERT LOSS OF SECONDARY CONTAINMDJT INTEGRITY

1) loss of secondary cont.ainment integrity for greater than 12 h ours N/A 9

o 9 9 e t - SITE EMERGENCY GENElML EMERGudCY N/A . N/A e

QQ'

                 }$ffjf QW RWY                               J
                                                                     . - ' TQ: ^ " *          \
                                                                                       ^
                                                                                                    -nPPENDIX EP-101 Page 9 of 12, ucy,G INSTRUMENT FAILURE
                                                                                                                 ~ ~ - -

UNUSUAL EVD4T

       .                                                                                        ALuct SIGNIFICANT LOSS OF ASSESSMENT OR COM-MUNICATION CAPABILITY IN T!!!; MAIN CONTROL ROOM

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

t ( -

                             "**" '*""*""C'

cEuewa. eMuuuuucy 9

N/A N/A

 ~ - - - ~                           - - . - _ _ - - - - - _ - - -

                                              ?    .

s l'. o p

10 ol' 12, i<o v . ',

       ~          '                              - - . . ~ - - - -    -

FUEL D AM AGE UNUSUAL EVEttr

 *(                                                                                               Angscr POSSIBLE FUCL DAMACC    -

PUEL DAMAGU

1) Air ejector discharge rad monitor high alarm and an increase of 500mR/ 1) Air ejector discharge rad monitor indicating greater than 2.5 x 10 mR/ 4 hr within 30 minutes or a level of hr on RR 2/3-17-152, or 2.5 x 103 mR/hr as indicated on 2) High coolant activity of 300 uCi/gm RR-2/3-17-152, o_rr

2) high reactor coolant activity as dose equivalent I-131, and main steam determined by sample analysis equal line high-high radiaticn alarm with to or greater than 2 uti/gm dosc resultant ucr.am al.orm, or l equivalent I-131 3) spent fuel damage resulting in a refueling floor area radiation monito r alam or a high radiation alarm on refuel floor exhaust rad monitor

( - SITE EMERGENCY GENERAL EMURGENCY PUEL DAMAGE PUEL DAMAGC

1) Following conditions occur:

a) failure of control rods to fully 1) When at least 2 of 4 containment rad insert on a scram and moisitorn indicate levoln gre. iter than 106 R/hr on RI-8/9103A/C and b) higher than normal readings on LPRMs adjacent to not-fally-RI-8/9103b/D and constainment pressurc inserted rods and exceeds 10 psig on PR 2/3508 c) at least 2 of the 4 containment rad monitors indicate levels greater than 105 R/hr on RI-8/9103A/C and RI-8/9103B/D.

2) Major damage to spent fucl in fuci pool or uncovering of spent fuel as confirmed by a fuel pool arca radiation monitor alarm and:

a) refuel floor exhaust radiation - monitor high alarm, or b) refuel floor area radiation monitor alarm or ( 3) Observed major da Ege to spent fuel

i Al'i'I'.NI e I X El' Ieil

l '. i 3. . Il ..) 1 :', lie v.

HAZARDS . ._. s UNUSUAL EVENT ( - Al l~: lit MODERATE IIAZARDS SEVEs<E jlAf.Ajp< ,N

1) Aircraft crash on or near site 1) Aircraft cresh on the facility or as determined by Shift Supervision or missile impacts into the Reactor Bldg. Diesel Generator Bldg. or

2) Significant explosion on or near

site as determined by Shift llPSW pump structure as determineal Supervision or by Shift Supervision or

2) Explosion d.un.49e tre facili ty .s lTeelis..;

3) Toxic gas rolcase on or near site plant s.ifety .i:. tietermineel liy Slii rt as dotormined by Shift Supervision Supervision g ',

3) Chlorine gas detected in the Control Room .

l

           .                                                                                                                                     1'

( SITE EMERG124CY . . . _ . . GENEl<AL. EMERGENCY (. __. . .._._.i

                                                ?Y
                                ?

o

                                       - f$                                                                       "                               '

s W Al'I'ENI)1 X fil'*! O l l'.itle 1 */ est l *!, lo v. '. CONTROL ROOM EV ACU ATION UNUSUAL EVENT A1.UHT f(K.M(IT.M Ct)NTidJI. E.!;TAlli.1 ;tlHIJ

1) Evacuatiors ol' Maint Control Room

anticipated or required and control g established at remote shutdown panels t as determined by Shift Supervision r

i n 4 4

                                                                                                                                              -- . .i     .

SITE EMERGENCY GENERAE EMEHGENCY a ( RCMOTE CONTROL NOT ESTABLIS!!LD "

'a

1) Evacuation of Main Control Room "

and control of shutdown systems I, not established at remote shutdown d panels in 15 minutes as determined , N/A ' by Shift Supervision ; P i i t i f i ( 6 e t, (

      %d
  ..         *                                                      .. 3                                       EP-)D2 PAGE 1 OF 3 I         REV. 5

( N .

                                                          ]4                                                     MY 2 31982 hr

PH I L A D'E L P H I A EL ECTRIC COMP ANY PE ACH BOT TOM UtJI TS ? AND 3 dMERGENCY PLAN I MPL emf tJ T ING Pit 0C E DUh

     %e                           -
                                                          .__....-a                                              -

EE:192_:_uG25UAL_E2E31_EESE30SE-

     %e be                  EUBEDSE hv                  TO DEFINE SITL RESPONSE IN THE. EVENT OF AN Ub< USUAL EVENT.

BEEEEEUCES

    %w 1.

PE ACH B O T T O'4 A T0'4f C POWER STATION EMERGENCY DL Af4 4' SEE110N TilLE ' 411 UNUSUAL EVENT i 4- 5.0 I DRG At<I Z AT I ON A L CONTROL OF EVERGENCIES b.l.1 UNUSUAL EVENTS

b. 2. NOREG 0654 1

CRITERIA FOR PREPARATION ANO EVALUATION OF HADIOLOGICAL EMERGENCY RESPONSE PLANS AND v PRC P ARE DNESS IN SUPDORT OF NUCLE AR Par!ER PLANTS. '

3. GP-15 LUC AL EVACUATION i.,

4. EP-101 CLASSIFICATION OF EttERGENCIES l

AEEEUUll s EP 102-1 UNUSUAL tVENT NOTIFICATICN CHECKOFF LIST s IM2fDIAIE_AEll0DS 1.0 SHIFT SUEERVISION SHALL: l 1.1 ASSUME THE RCL E OF I N T ER I .M EMERGENCY DIRECTOR.

                                  '12           ACTIVAIE EMERGENCY TEAMS AS NECESSARY.

1.3 DI.3ECT THE EVACUATION OF AFFECTE D hRE AS AS NECESS . AR i REFEA IU THE FOLLOWING PROCEDURE: GP-25 LUCAL E V A CU A T I OtJ 1.4 CONTACT THE STATION SUPERINTENDENT AND THE SHIFT TEC ADVISOR AND INFORM THEM OF THE SITUATION. O

?i e' ' EP-102 PAGE 2 OF 3 I nev. s EF: WAF L

                    '15      FILL QUT THE STANDARD EP 102-1 Ah7 GIVE      IT    PROMPT NOTIFICATION MESSAGE     IN APPENDI.

TO THE ASSIGNED COMMUNICATOP, (PO OR s HIGHER CLASSIFICATION) AND. DIRECT THE COMMUNICA

      ,      y COMMENCE        NOTIFICATION SPECIFIED IN THAT    APPENDIX. OF THE APPROPRI A TE PART IE NOTE:

d 00 NOT.uSL BLUE RINGDOWN PHONE FOR THESE CALLS. 1.6 CLOSELY MDNITOR CONDITIONS e- TO DETERMINE PRESENT HAZARDS TO PERSONNEL DEVELOP. AND POTENTIAL ACCIDENT CONDITIONS 2.0 d CCMMUNICATOR SHALL* 21 PERFORM NOTIFICATIONS ON p APPENDIX EP 102-1 USING THE STANDARD PROMPT NOTIFICATION MESSAGE APPENDIX. INCLUDED IN THAT SEE EP 209, APPENDIX A FOR ADDITIONAL TELEPHONE NUMBERS IF NECESSARY. 9 EOLLDs:UE_AC11DbS ' 1.0 9 EMERGENCY DIRECTOR SHALL: 11 9 PERIODICALLY ACC0dDANCE WITe EP EVALUATE THE EVENT CLASSIFICATION IN AND ESCALATE Oh 101, CLASS 1F,1 CATION OF EMERGENCIES 12 DEESC AL A TE THE CL ASSIFIC ATIDN AS NEC ES 9 UE TERMINE 4HICH SUPPORT PERSONNEL ARE,NFCESSARY FOR EMERGENCY FUNCTIONS.AND DIRECT THE SHIFT CLCRK TO CONTACT THOSE PERSONNEL. I IF SHIFT CLERK IS NOT AVAILABLtINDIVIDUAL. AVAILAdLt TnIS FUNCTION SHALL BE ASSIGNED TO ANY 2.0 SHIFT C L E P.K SHALL: 21 NOTIFY A 00! T IONA L SUPPORT PERSONNEL T O R~E POR THE PLANT AS DIRECTED BY THE EMERGENCY DIRECT 0k. 4 i ( e . h e

(

f. EP-IO2

[ ( DAGE 3 CF 3 - REV. S EF:WAF AEEENQ11_EE_102:1 USUSUAL_EYESl_NQILEICalLDS__CSEC50EE_L151 MESSAGE: THIS ( 15 ) (4 S NOT ) A DRILL. THIS ( 15)(15 NOT ) A ORILL. THIS IS PL ACH BOTTOM ATOMIC POWER STATION CALLING TO REPORT AN UNUSUAL EVENT HAS BEEN DECL AR ED ON UNI T NC. ____. TIME AND DATE OF UNUSUAL EVENT CLASSIFICATION IS__________. THE BASIC Ph03 TEM IS THE PL AraT STATUS IS (STASLE)(IMPROVING)(DEGRADING)(NOT K N O W (HAST HbEEN)(HAS FROM E P L A .'. T . NOT BEEN) AN ( A[R60RNE)(L IQUID) R ADIOAC TI VE RELEAS PROTECTIVF ACTIONS RECOMMENDED ARE (NONE)__________ _____________,__________THE AFFECTED POPULATION AREA IS (NONE)______ __________________________. MY NAME IS _________________, THIS (IS) (IS NOT) A ORILL. NOTIFICATIONS: NAME OF TIME OF PARTY COM'1UN I C A TOR '

                                                    *PERS3N_dESPDSDING                                                    INIIIALS
             &                                                                             UD11EICA1103 STATION. SUPT.

______2__________ ____________ Lnaa nisPA TCHER NRC OPERATIONS CENTER - ( R E D P HD.'.E ) PENfvSYLVANIA EMERG-F t 'r. Y MANAGEMENT AGENCY YORK COUNTY EMERG-

ENCY MANAGEMENT AGENCY PA. BUREAU OF RAD. PROTECTION ( WHI TE PHUNE OR MANAGER-PUBLIC

INFORMATIaN OR PAGER *

                                                                                        ~
                                                                                                            ~

TIME NOI!FICATIONS OF VERIFIEU A3bVE BYkAki((S~CUkPLETED_((((((((_((____((((!~~~ CATC' ~~~~~~~~~~~ (EMEkG.~UIEECTUki~~~~ FILE SYS-3-1

                                                                                           .       n.                                            e-r . .; . 3 .. ; . - , , - ; r,y ,

_, :. EP-103

                                                                     -'l -  ;                                                  DAGF 1 0F 6 REvo hls
                                        , -                                 l                               -

EDtwAF

                               / N.                      .hTW
  ,                                                                                                                                        y PHILADELPHIA EL ECTRIC COMP ANY j

PEACH BOTTOM UNITS 2 AND 3 [ EMERGENCY PL AN IMPLEMENTING PROCEDURE

                                                                                     ~                 e....        . .                      ...

EE:1Q3 _ALEEl_BESED11E . . , EUBEOSE . TO DEFINE SITE RESPONSE IN THE EVENT OF AN ALERT. ScEE653CES '-

1. PE ACH ~ BOTTOM ATOMIC POWER STATION EMERGENCY PLAN

                                                                      . 6,                                           .

S EE!.10!i 111LE L ___

                             ,    4 1.2                  alert                                                                                               ..
                                  $.0                    ORGANIZATIONAL CONTROL OF EMERGENCIES 6.1.2                  ALERT
           ).        NURtG Oc3%                        , CRITERIA FOR PREP AR AT !ON AND EV ALUATION OF

( R AD I OL OG IC AL EMERGEMY RESPONSE PLANS ANO PREPARE 0 NESS IN SUPPORT OF NUCLE AR POWER PL ANT S.

3. GP-15 LOC AL E V ACUA TION 4 EP-101 CLASSIFICATION OF EMERGtNCIES AEELUDllik EP-103-1 ALERT NOTIFICATION CHECK 0FF LIST FP-10 3-? P ERSONNEL CALL RECORD EP-103-3 EMERGENCY EXPOSURF LIMITS (EMERGENCY PLAN TABLE 6 1)

~~

EBELaull0SS -

1. PLANNEO RA0!ATION EXPOSURES SHOULO BE LIMITED TO THE ADMINISTRATIVE GU10E LE VEL S IN APPEN01X EP 103-4, EMERGENCY EXPUSUAL LIMITS.

IddEDIAIE AEllDSS ' -

1.0 SHIFT SUPERVISION SHALL: - ( 11 ASSUME THE ROL E OF INTERIM ENERGENCY DIRECTOR. -

12 AC { l V AIfi EHERGENCY TEAMS AS NFCFSSARY. - aq e39 h W 46**.4N'M*'* * = - -_ 9 _ ee,, _ g

                                                                               .-       g pgoT~~
           '                                                                            PAGL 2 OF 4
            -                                                                           MEV. Ah EDtWAF

( 1.3 DIRECT THE EVACUAil0N OF LFfECTED AREAS AS NECESSARY. REFER TO THE FOLL0alNG PF.0CE00RES: GP-15 LOCAL EVACUATION EP 305 SI T E EV ACU AT" ION EP loo EVACUATION OF THE INFORMATION CENTER ) 1.4 CONTACT THE ST AT ION SUPERINTENDENT AND THE SHIFT TECHNICAL ADVISOR. INFORM THEM OF THE SITUATION. 1.5 F ILL OUT THE STANDARD PROMPT NOTIFICATION MESSAGE CHECK-OFF APPENDIX FP 103-1 AND GivE IT TO THF COMMUNICATOR (PU UR HIGHE/ CL ASS!F IC ATION) AND DIRECT THE COMMUNICATOR TO COMMENCE NOTIFICATION OF THE ADPRODRIATE PARTIES AS SPECIFIEO IN SECTION 2.1 0F THIS *ROCEDURE. THE COMuu.10Af0R SH AL L MAN THE NRC 0.ED TELEPHONE ON A CONTINUluS UASIS IF REQul8th BY~ D ROCF DUR L A-31. IF COMMUNICATOR 15 R E 'JU I R L 3 F OR ORGLNI PLANT O P E R A T I ONS R E L A T E D TO 'THI 4 M L P. G5 NC f . THE t or.C U RRE N C E FOR SELURING THE PHONE SHOUL.D BE OBT AINED F RCM IHE t. < L PRIOd 10 SECURING THIS TELEPHONE. 1.6 JIW C T THE SHIFT CLERK TO ACTIVATE THE 60 MINUT E C ALL LIST USING IP 2U9 APD P. IF SHlfT CLERK IS NOT AVAILABLE. THIS ( FUNCIIUN SHALL PE AS$1GNED TO ANY AV AIL ABL E INDIVIDUAL. l.1 d!RELT ONF Of THE ON-shirt IEC TECHNICI ANS TO ACT IVA TI (HL llCHNILAL SUFPORT LENTLR AND EMERGENCY OPERAi!3NS FACILIlY IN ACCORDANCE WITH ED 201 AND EP-203. INFORM SHIFT CLEHF WHICH ICC TECHNICI AN WILL ACTIVATE THE LFNTLR$ Af UNIT 1 IN 9ROEa THAT THE CLERK WILL KNOW nHICH 4 LM A l tM NG l i.C Tf CHNI CI AN T O C ALL FOR THE PROMDI M0ulLIZAilCN PROCEDURL. 1.9 UldCCI THE DA0!Ai!0N PROTECTION TEAM LEADER 10 INITIATE SIIL PADIAilJN SURVEYS AS NECESSARY. IN ACCORDANCE WITH EP-

                       /05, RADIAildN PRO f f CT I ON IEAM.

1. 9 INITIA1E THE I MPL E ML NT A T ION OF EP 316.' CUMULATIVE POPULAllON DOSE CALCULATIONS, if NECESSARY. (EP-316 NELDED FUR AtfRT AS PER PG. 8 ITEM S OF LP-101 APP. 101-11. THE SHIFI T ELHNIC AL ADVISOR (SIA) COULO BE USF3 TO PERFORM THIS FUNCTION.

1.10 ASSIGN AN ODtRATIONS SUPPORT CENTER COOR DI N A T OR (SENIOR SH I F T PO OR APU AVAILABLE) AND DIRECT AV A IL A BC E SHIFT PERSONNIL 10 REPJR1 TO THE UPE R AT IONS SUPPORT CENTER ON 135' ELEY. TURSINE B L O ~, . AND 10 ACTIVATE IT IN ACCORDANCE WITH EP 202, If HA3!TAHLE. IF IHIS I:FER A T IONS SUPPORT CENIER IS N01 HABITABLE. DIRECT SHIFT P E R *, N 4 N i l 10 REPORT TO THE CONIROL ROOM. ( 1.11 C L'M,i( f NONI T OR CONDITIONS TO DETERMINE PRESENT HAZARDS

EP-101 PAGE } GF'd

                                    ,                                                                 CEvo V6
         .                                                                                            EQ dAF*

(' TO PERSONNEL AND POTENTIAL ACCIDENT CONDITIONS THAT MAY 0EvFLOP. 1.1/ IF R ELE ASE HA S OCCURHED, DISPATCH A PLANT SURVEY TEAM MEMBER TO QBTAIN A SITE BOUNDANY DOSE R A TE AS 500N . AS PRACTIC ABL E. 1.13 I F NECE SS ARY, INITIATE IMDL EMENT ATION OF EP-316 C EP-317 D I R T. C T R E C OM.M E ND A T I ONS TO COUNTY EMERGENCY MANAGEMENT A 2.0 COMMUNICATOR SHALL : 2.1 P ERFORM NOTIF IC 4 YIONS ON APPENDIX 103-1 USING THE ALERT

                             ;40l l F IC A T 10N CHECK OFF APPtNDIX EP 103-1. SEE EP 209, APPENDIX A FOR ADD]TIONAL TELEPHONE NUMBERS.

2.2 REPORT TO THE EMERGENCY DIRECTOR OR INTERIM EMERGENCY 31 RECTOR WHEN NOTIFICATIONS ARE C OMPL E TE . 2.3

                                                      ,4   .'                                  .

MAN THE HED NRC TELEPHONE IF REQUIRED BY A-31 UNTIL SITUAllON ST ABIL llES AND RED T E L EPHONE C OMMUN I C AT'10N' 4AY af S E C UR L O . 3.1 OPLRAi!GNS SUPP.7RT CENTER COORDINATOR OR HIS DESIGNEE SHALL: 3.1 ( ACTlv4TE THE OPERATIONS SUPPORT CENTER ON 135' EL E v . T UR H I N E utOG. IF IT IS HABITABLE, i f; ACCORDANCE WITH EP 202. 1F THIS

                            .lDLRATIONS SUPPdRT CENTER IS NOT HABITABLE, REPORT TO THE L Of.T R LL RODM.

e 4.0 MAblA!!ON PROTEC110N TEAM LEADER SHALL: 4.1 IN111AIE SITI R A D I A i l f }N SURVE YS IN ACCOPDANCE WITH CP-205. 4AulA110N DIRILIOR.PRil T EC T I ON TEAM WHEN DIRECTED SY THE EMEHGENCY 11HE HP FIELO OFFICL ON 116' ELEV. TURH. B L D ". . WILL SLRVE AS THE HPEC OSC). S.O SHIF T r. I C TLCHNICIAN 5 HALL:

l 5.1 ACilVATE THE TSC AND EGF dHEN DIRECTED.SY INTERIM

[MIAGtNCY DIRECTOR IN ACCORDANCE WITH EP'201 USING APPENDIX to-201-2.,

6.0 SH IF T CLEHK SHALL: ~

6.1 CONTACT INDIVIDUAL S ON EP 209 APP P TO CALL IN THOSE IN0lVIOUALS MINUTE CALLTO MAN TSC AND REQUIRED EMEPGENCY TEAMS (60 LIST). DOC UME N T CONT AC T S ON EP 209 APP P. , 6.2 INFORM INTERIM EMERGENCY DIRECT 0H OR EMERGENCY DIRECTOR WHE'i CONIACTS ARE COMPLETED.

O 9

                                                                                           . _ _ . ._.        . - -     ..  ==..

EP-103 PAGE 4 0F 8 REVo 4 6 EDtUAF

         . .LLQs-VE_iLilCSS

1.0 LMINGENCY UIRECTUR SHALL:

1.1

PERIUDICALLY EVALUATE THE. EVENT CLASSIFICATION IN ACCORD-ANCE WITH CP 101, CLASSIFICATION OF EMERGENCIES, AND ESCALATE OR DETSC AL ATE THE CL ASSIFIC ATION, AS NECESSARY.

1.2 GBTAIN THE RESULTS OF THE CUMUL ATIVE POPUL ATION DOSE CALCULATIONS PRDIECTION AND ONSITE TE AM LEADER, RADIATION AS NECESSARY. SURVEYS FROM THE RADIAT 1.3 PERFJRM THt LMERGENCY ACTIONS AS NECESSARY TO MITIGATE CONDITIONS OF SITUATION. - 1.4 3ETERMINE WHICH 1DDITIONAL SUPPORT PERSONNEL ARE NECESSARY FOR EMERGENCY FUNCTIONS AND DIRECT THE SHIF T CLERK OR OTHE R ASSIGNED COMMUNICATOR ,A IN TSC TO CONTACT THOSL PERSONNEL. 1.5 PROVlat Stif PERSONNIL AITH P.A. SPEAKER AN OD'NfENENTS FOR LANY 6AJOR ME0 6fhC Y ACTION CHANGES LEVELS, IN PLANT EMERGENCY STATUS. SUCH AS C HA OF RAJIDACTIVE RELEASES (IF FVACUATIONS ANY). AND STARTING AND STOPPINJ. O STAllON SUPER INT E NDE NT SHALL : '

               ?.1 sEPJRi TU THt IECHNICAL SUPPORT CENTER OR CONTROL 8004 rJR A UklEFING OF THE SITUATION.

o 7./ ASSuML THE RJLE OF F.MERGENCY DIRECTOR BY FORMALLY RE INilRIM LMLRGENCY DIRECTOR ( SHIF T SUPERIf4TENDENT ) . AN HAS A S',0 >. E D T H E ROL E OF EMERGENCY DIRECTU1 TO THE ASSEMaLEU TE SUPPORI C E.N ,It R PERSONN'EL. 7.1 VERIFY THE EMERGLNCY CL ASSIFIC A TION.

              ?.4 VidifY THAT THE TECHNICAL SUPPORT CENTER, THE Lwl#GFhtY UP[ 4 AI 10NS F AC I L I TY , AND THE OPERATIONS SUPPURI CFAILR HAVL BEEN AC T IVA TE0.
                                                                                   ~ . .   .__

3.0 UPLRATIGAS SUPPORT CLNTER COORDINATOR SeiALL: 11 '

                      .011FY THF INT ER l" EMERGENCY DIRECTOR WHEN THEIR RESPECT OPERAll0NS SUPPORT CENTER I S AC TIVATED.

3.2 t SUPDORT

                     .NECESSARY.      THE CONTROL ROOM Afl0              I SHIFT $0PERVISION AS 4.0 RADIAilqN pry!LCTION TE AM LEADER SHALL:

c 4., REP .. , GR , , , .,D RE,UL,, OF CU UL.,,VE POPULAT,0, 00si CALCULATIONS IMtqh{hCY AND SITE DIRECTOR AS NECESSARY. RADIATION SURVEYS TO THE -

EP-lOn

PCGL 5 OF R R L v. Jr [p

                                ,                                                                       EU:wAF 5.0       SHiri CLERK OR ASSIGNED TSC COMMUNICATOR SHALL:

5.1 NOTIFY ADDITIONAL SUPPORT PERSONNEL TO REPORT TO THE PLANJ AS DIRECTED BY THE IN,TERIM EMERGENCY DIRECTOR. REFER TO EP 209. DOCUMENT ON APP EP-103-2. 5.? N0!!FY THE INTERIM EMERGENCY DIRECTOR WHEN THE ADDITIONAL SUPPORT PERSONNEL HAVE BEEN NDT IFIED. 6.0 SHIFI IEC TECHNICIAN SHALL: 5.I I NFOR M THE INTERIM EMERGENCY DIRECTOR WHEN THE TSC AND EOF ARL ACTIVATED. 6.2 ST AT ION HIMSELF AT THE *TSC AS DATA DISPLAY (CCTV) OPERATOR AS DIRECTED BY THE EMERGENCY DIRECTOR.

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EP-RO3 DCGE T CF 9 REvo 4 EO:cAF . s APPENDI~x IP 103-2 's' P.EB5dMEL_dE_SEdQSD e . i.. . DISPOSITION OF CALL NAVE OF TIME NO ESTTMATED CALL P!PSON CALLED CALLED ANSWER BUSY TIME OF ARRIVAL COMPLETED BY ___ ___ _ . .m _ _ .,_. __ ________ ____ __- _ ___ _____ -_ ________ ________s __ ___ __ ___._ ..___ __ ______ __ Fa sy;_3 g e 0 e

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1. LIFE SAVING AND .

l}E DUCT ION OF INJURY 75 REM

375 REM EMERGENCY **

DIRECTOR

2. OPfRAlION'OF EQUIPMENT TO MIIIGA1E AN '

EMERGLNCY - 25 REM

125 REM EMERGENCY **

DIRECTOR

3. PHOT EC T ION OF HLALTH, C ~ ,

                                                                                                                          .'s AND SAFt1Y OF THE PUBLIC                               5 REM                2 5 R E'1 EMERGENCY O! RECTOR                    --

4. OT HE R E F f d* C.F NC Y 10 CFR 20 10 CFR 20 EMERGINCY ACTIVIT!!> LIMITS LIMITS .

DIRECT)R ( .. Rt. -t N I R Y/e< b t OVE RY ADMINISTRA- ADMINIS-AC li Vl i l' 5 ilVF GUIDE- TRATIVE

                                                               ,         ' TINES               GUIDE-                       ,

LINES N/A 0 'It F t 41.N L E : EPA-520/1-75-001 TARLE ?.1 0 0 MIC+$ t x r O SUR F. SHAll HE ON A VOLUNIARY BASIS

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                                                             ~ FETCH BOTTOM UNITS 2 AN0 3     .

s, Et4RGENCY PLAN IMPLEMENTING PR O C T U'# R E EE:1ui___ Sill _EMEEGESCX_SESEDSSE v . EUdEDSi tur TO DEFINE THE SITE RESPONSE IN THE EVENT OF A SI TE E MERGENC Y. V - BEEEEEhCES

        \v            1.
                     . PEACH BOTTOM ATCMIC POWER STATION EMERGENCY PLAN v                          SEC110u     111Li 4 1.3        SITE EMERGENCY 5.0                                                      .

kv 6.1.3 G4GANIZATIONAL SITE EMERGENCY CONTROL OF EMERGENCIES ( 2. kW NUREd 0654 CHITERIA FOR PREPARATION AND EVALUATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPARE 0 NESS IN SUPPORT OF NUCLEAR PDwER PLANTS.

3. EP-101 CLASSIFICATION OF EMERGENCIES .

AEEEG31CES EP 104-1 EP-104-2 SITE EMERGENCY NOTIFICATION CHECKOFF L IS T PERSONNEL CALL .(ECORD LP 104-3 EMERGENCY EXPUSURE LIMITS (EMERGENCY PLAN TABLE 6 1) ESECAU11 DSS ' 1. PLANNED RADIATION EXPOSURES' SHOULDTO ADMIN IS TR AT ION GUIDE LE VEL S BE THE LIMITED IN APPENDIX EP 104-4, EMERGENCY EXPOSURE LIMITS. 185EQ1Ali_AC11935

    .            l.0 SHIFT SUPERVISION SH ALL :

11 ASSUME THE Rutt OF INTER IM ' EMERGENCY DIRECTOR.

12 k IF NOT AL4 LADY DONE AT AN EARLIER EMERGENCY ACTION LEV 13 ACTIVATE E ME R G L NC Y TEAMS AS NECESSARY. DIRECT THE EVACUATION OF REFER TO THE FOLL OWit!G PROCE00k ES :AFFECTED AREAS A e

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EP-lO4 s,

PAGE 2 0F 9 l REV. 5 ESF WAF e [ - GP IS LOCAL cVACUATION EP 305 SITE EVACUATION

EP 3 0*; EVACUATION OF THE INFORMATION CENTER 1.4 CONTACT TSE STATION SUPERINTENDENT AND THE SHIFT TECHNICAL ADVIS3R, INFORM THEM OF THE SITUATION. 15 FILL DUT APPENDIX EP 104-1 S T ANDARD PR OMPT NOI!FICATIGN FESSAGE AND GIVE TT TO THE COMMUNICATOR

       -                     (P0 UR HIGHER CL ASSIF ICATION) AND DIRECT InE COMMUNICATOR TO COMMENCE NOT IF ICATION. 0F THE APPROPRI PROCEDURE.      ATE P ARTI ES AS SPEC IFIEO IN SECTION 2.1 UF THIS THE COMMUNICATOR SHALL MAN THE NRC RED TELE-PHONE ON A CONTINUGUS BASIS, IF REQUIRED BY A-31.           IF COMMUNICATUR IS REQUIRED FOR URGENT PLANT QPERATIONS RELATED TO THE EMERGENCY. THE CONCURRENCE FOR SECURING
                           ' THIS THETELEPHONE.

PHONE SHOULD BE OBTAINED FROM NRC PRIOR TO SECURIN 1.6 .

     ,                      IF NOT ALREADY ACC OMPL ISHED A T THE ALERT STAGE. OlkECT THE EP  209SHIF1 APP P. CLERK TO ACTIVATE THE 60 MINUTE CALL LIST USING V                                            IF SHIFT CLERK IS NOT AVAILABLE, THIS FUNCTION MAY BE ASSIGNED TO ANY AVAILABLE INDIVIDUAL.

1.7 ks DIRECT ONE OF THC ON-SHIFT IEC TECHNICIANS TG ACTIVATE TECHNICAL SUPPORT CENT.ER AND EMERGENCY OPERATIONS FA IN ACCORDANCE WITH EP 201 AND 203 IF NOT ALREADY ACTIVAT v IF NOT ALRCADY PERFORMED PREVIOUSLY, INFORM THE SHIFT CLERK W IEC TECHNICIAN WILL ACTIVATE THE CENTERS AT UNIT 1 IN THE PROMPT CLERK KNOWPROCEDURE. MOSILIZATION UHICH REMAINING ICC TECHNICIAN TO CALL 18 UIRECT THE R ADI AT ION PROTECTION TE AM L EADER TO INITIA

   .                      UN- AND OFF SITE RADIATION SURVEYS, AS NEC ESS ARY. IF NOT          .

ALREADY TEAM. DONE IN ACCORDANCE WITH EP 205, RADIATION PROTECTION 1.9 INI TI A TE THE IMPLE MENT AT ION OF COSE C ALCUL A T IONS, AS NECESSARY. EP 316, CUMULATIVE POPULATION 1.lC A SSIGN A 135' ELEV. TURB. BLOG. OPERATIONS SUPPCRT CEN C00kJINATOR (SENIOR PO OR APO AVAILABLE) IF NOT ALREA AND DIRECT AV AIL ABLE SHIFT PERSONNEL TO REPORT TO SUPPORT H ABIT ABL E.

CENTER AND TO ACTIVATE IT IN ACCORDANCE W IF THIS OPERATIONS SUPPORT CENTER IS NOT HABITABLE, DIRECT SHIFT PERSONNEL TO REPORT TO THE CONTROL RCOM.

1 11 C LOSE LY MONITOR CONDIT IONS TO DET ERMINE PRESENT H TO PERSONNEL DEVEL OP. AN9 POTENTI AL ACCIDENT CONDITIONS THAT M e

                 '.      *

EP-104 PAGE 3 OF 9

                                                                                ;   REV. 5 EGF: WAF
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1.12 IF RELE ASE HAS OCCURRED. DISPATCH A PLANT SURVEY TEAM MEMBER PRACl TO GitTAIN A SITE bDUNDARY DOSE RATF AS SODN AS IC ABLE. 1 13 IF NECESSARY, INITIATE IMPLEMENTATION OF EP-316 AND EP-317, DIRECT R AGENCIES. LC.UMME ND A T IOr.S T O C OUN T Y EMERGENCY MANAG 2.0 COMMUNICATOR SHALL: 2.1 P ERFORFr NOT IF IC AT IONS ON APPENDIX 104-1 USING THe STANDARD PROMPT NOTIFICATION MESSAGE INCLUDED. S EE E P-209 APPENDIX A FOR ADDITIONAL TELEPHONE NUM3ERS, I F RE QUIRED. 22 REPORT ARE COMPLETO T ED.THE E M ER GE NC Y DIRECTOR WHEN THE NOTIFIC

2.3 MAN THE REU NRC TELEPHGNE IF REQUIRED BY A-31 UNTIL SITUATION STARILI2ES AND RED MAY BE SECURED. TELEPHONE COMMUNICATIONS v 3.0 OPERATIONS SUDPORT CENTER CDORDINATOR OR HIS SHALL: DESIGNEE V 3.1 ACTIVATE ThE OPERATIONS SUPPORT CENTER ON 135' ELEV TUR BLDG, IF IT IS HABITABLE. IN ACCORDANCE WITH EP 202. V IF THIS OPEPATIONS SUPPORT CENTER IS NOT HABITABLE REPO TO THE CONTROL ROOM. V 9.0 RADIATIOtw PROTECT!0'4 TE AM L EAOCR SHALL. 91 INITIATE ON- AN] OFF SITE RADIATION SURVEYS IN V ACCORDANCE WITH EP 2D5. RADIATION PROTECTION TEAM,'WHEN DIRECTED BY T H 'c E MER GE NC Y DIRECTOR. IF THIS PERSON IS THE HP ENGINEER HE SHOULD REPORT TO THE EOF TO s .- COCRUINATE THIS F UNC T I ON. 5.0 SHIFT ICC TECHNICIAN SHALL: ' 51 ACTIVATE THC TSC AND EOF, ( l'F NOT ALREADY ACTIVATED DURING ALERT STAGE) IN ACCORDANCE WITH EP 201 USING .. APPENDIX EP-201-2 AND PROCEDURE EP-203. 6.0 SHIFT CLERK SHALL: 61 IF NOT ALREADY IMPLEMENTED OURING ALERT STAGE, CONTACT INDIVIDUALS UN EP 209 APP P TO CALL IN THOSE INDIVIDUALS T3 EP ON MAN TSCP.AND 209 APP EOF (60 MINUTE ChtL LIST). DOCUMENT C 62 I NFCONTACTS WHEN OR M INTERIM EMERGENCY ARE COMPLETED. DIRECTOR OR EMERGENCY

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              '                                                                   PAGE 4 OF 9 REV. 5 EOF: WAF
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          .       1.U EMERGENCY DIREC TO4 ShALL:

11 PERIODICALLY EVALUATE THE EVENT C L A S S I F IC A T I O Y, ACCORDANCE.NITH EP 101, CLASSIFICATION OF EMdRGENCIES AND LSCALATE OR DEESCALATE NECESSARY. THE CLASSIFICATION. AS ss 12 OBT AIN RESULTS OF CALCULATIONS AND THE CUMULATIVE POPULATION DOSE v ONSITE/OFFSITE RADIATION SURVEYS IHE RADIATION PROTECTION FRO" TE AM L EADER, AS NECESS ARY. 13 Le PROVIDE APPROPRI EVALUATIONS AT E INFORMATION FROM TO COMMUNIC ATOR THE PREVIO C ATION OF THE BUREAU OF IN THE EOF FOR NOTIFI-RADIATION PROTECTION. I.4 PERFURM W UF THE EMERGENCYACTIONS SITUATION. AS NECESSARY'TO MITIGATE CO 1.S

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D E T ER MINE WHICN ADDI TIONAL SUPPORT PERSONNCL A I NECESSARY FOR EMERGENCY FUNCTIONS AND DIRECT THE V 'UR SHIFT CLE% 0" OTHER ASSIGNED COMMUNICATOR IN TSC EJF TO CONTACI THOST PERSONNEL. 10 PROVIOE SITE PERSONNEL WITH P.A. L/ SPEAXE4 ANNOUNCEMENTS FOR ANY MAJORACTIUN cMERGENCY OF CHANGESLEVELS,INEVACUATIONS PLANT EMERGENCYAND STARTING STATUS AND RADIOACTIVE RLLEASES (IF ANY). V 2.0 S T A T I ON SUPERINTENCENT SHALL: 21 Ad REPORT TO THE T E C HNI C A L SUPPORT CENTER OR CON ROOM. FOR A BRIEFING OF THE SITUATION. 22 v A SSUM E THE ROLE OF EMERGENCY DIRECTOR (IF NOT'AL D ON OF Th!S E ) BY FORMALLY RELIEVING THE INTERIM RESPONSIb!LITY. EMER M ANNOUNCE THAT HE HAS ASSUMED THE R OL PERSONNEL. CENTER E OF EMERGENCY DIRECTOR TO THE ASSEMBLE 2.3 V ER IF Y THE EMERGE NCY CLASSIFICATION. 2.4 VERIFY THAT THE TECHNICAL SUPPORT CENTER, EMERGENCY OPERATIONS HAVE FACILITY BEEN ACIIVATED. AND THE UPERATIONS SUPPORT C 3.0 135' ELEV. ( I 31 TURBINE BLDG. OPE R ATIONS SUPPORT CENTE NUTIF Y THE INTERIM E uTM EN C Y DIRECTOR OR EMERGEN l DIREC TOR ACIIVATEv. WHEN THE OPE 9ATIONS SUPPORT C EN T E R IS e l i

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EP-104 PAGE S OF 9

            *                                                                    ,'   REV. S EGF:WAF
          #k kv            32 S U/ PO R NECESSARY. T THL CONTROL RDOM AND SHIFT SUPERVISION A bv
.              4.0 RADIATION PROTECTIUN TE AM LE ADER SHALL:

41 NOTIFY THE. EMERGENCY DIRECTOR WHE N THE EMERGENCY ODE RA TIONS F AC ILI T Y IS MANNED. 42 R E POct T

     %W DOSE CALCULATIONSPh0G4E AND ON AND OFF      SS AND RESULTS OF CUMU SITE R ADI ATION SURVEYS
 - Le                           TONCCESSARY.

AS THE SITE EV.ERGENCY COORDINATOR AND EMERGENC 43 NOTIFY THE, SIT E EMERGENCY COORDINATOR 0F THE NEED FOR

    %v ASSIST ANCE FROM R ADI ATION MANAGEMENT CORPOR ATIO As         S.D SHIFT CLERK OR ASSIGNED TSC OR EOF COMMUNICNTOR 51 IF NUT ALREADY DONE, NOTIFY ADDITIONAL S UP POR T PERSONNEL
    %r                         TO REPORT DIRECTCR.        TOTO REFER    THE   PLANT LP 209       AS DIRECTED BY THE EMERGEN DOCUMENT ON APP EP 101-2 I

52 ' Av 'nHEN NOTIFY EMERGENCY THE ADDITIONAL SUPPORT DIRECTOR OR SITE EMERGENCY PERSONNEL HAVE BEEN NOTIFIED. 60 ICC TECHNICIANS SHALL: (IF be NOT ALREADY PERFORMED AS PER EP-103) 6.1 INFORM IF THE EMERGCNCY NOT PREVIOUSLY DONE. DIRECTOR WHEN THE CENTE ' \e 62 MAN THE TSC 04 EOF DATA DISPLAY (CCTV) POSITIONS . %,e AS DIRECT ED BY THE EkERGENCY DIRECTOR. v Y NY e O M ( h

g -.. - EP-lO4 g- PAGE 6 OF 9 REV. 5 EGF: AF L . Lv ' AEEESD11_1DS:1 SIIE_hdEBGESCX_$0IlEICA11D3_CSECEDEE_LISI dESSAGE1 THIS (IS) (IS NOT) A ORILL. THIS (IS) (IS NOT) A ORILL. CALLING TO REPORT THIS IS PEACH BOTTOM A T O'i ! C POWER STATION L, _____. TIME AND DATE A. SITE OF EMERGENCY HAS BEEN DECLARED ON UNIT IS ____________. SI TE EMERGENCY CL ASSIFIC ATION THE BA SIC PROBLEM THE PLANT STATUS ISIS______________________________________. (STABLE) (IMPROVING) ( DEGR AD ING ) (NOT KNOWN). THERE (HAS NOT BEEN) (IS POTENTIAL FOR) (HAS BEEN) (IS PRE

        %w          A R A010 AC T !' VE (AIRDURNE) (LIQUIO) RELEASE FROM THE PLANT (

LEVEL PRO TEC TBI VE ELACO'n IHAT TION CONSIGEkED A PUBL IC H AZ ARD) (AT A LEV IS ADVISABLE). ARE (NONE) RECOMMENDED PR O T EC T I VE AC TION S

       %r THE AFFEC Td D POPUL A TION AREA      ________________________________________________.

IS (NONE) THIS (IS) (IS NOT) A ORILL. ____________________. THIS (IS) (IS NOT) A DRILL. 4e NO T I F I C A TI ONS : PERSON TIME OF EaBII BESEQbDISG COMMUNICAT04'S bh SD11E1CaI10U S T A T I ON S UP ER IN T ENDEN T __________ 12111aLS______ ( ____________ LOAD DISPATCHER be __________ ( TELL HIM TO INITIATE CALL LIST "C " ) L PENNSYLVANIA EMERGENCY MANAGEMENT AGENCv0 (BLUE PHONE OR ____________ ______________ v MARYL AND CIVIL DEFENSE AGENC Y V _ _ , _ _ _ (BLUE PHONE OR' ____________ ______________ s YORK COUNTY EMERGENCY

            . MANAGEMENT AGENCY (BLUE PHONE OR                                                    ____________       ______________

L ANC AS TER COUNT Y EMERGENCY MANAGE-MENT AGENCY

 +-                                                        _ _ _ _ . - _ _

(BLUE PHUNE CR ___-________ _____________- CHESTER C OU N T Y EMER-GENCY MAN AG EMEN T AGENCY (BLUE PHONE OR ____________ ______________ i' H AR F URD C OUN T Y CIVIL DEFENSE A Gt NC Y ( BL UE PHONE OR ____-_-_____ c.,. . n *

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PAGE 7 OF 9 i REV. 5 EGF: WAF 4 .

AEEESD11_1Di:1_1C0ullD1 311E_EJ'ESGESCX_dDI1EICAIIDS_CUECEDEE_Llil

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CECIL COUNTY CIVIL ~

DEFENSE A GL' NC Y

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PENNSYLVANIA STATE POLICE - YORK

  %s PA. BRP p                       _---__-_          ____________.       ______________
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NRC OPERATIONS CENTERce (RED PHONE)

 %9 TIME NOTIFICATION UF P A R T I C S A BO VF C OM PL E T E D . ________________
   ;                    VEk!FIED BY _______________

DATE __________ kw EM'RGENCY t DIRECTOR FILE SYs-3-1 ks MUST NOT IF Y PE*A OY U SE- OF COMMERC I AL TELEPHONE NO. O (dLUE PnONE NOT MANNEO eY PEMA 04 BACKSHIFTS). Le oc IF NRC PREVIOUSLY NOT IF I E D DURING ALERT CONDITION. THE ASSIGNED PO COMMUNICATOR CONTINUOUSLY MANNING RED PHONE IN v CONTROL HOWEVER, CHECK ROO4 WITHSuuutD CONTROL HANOLE ROOM TO THIS DE SURE. NOTIFICATION AUTOMATICALLY CATION IS MADE. THIS NOTIFI- %,4 e o V s md

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_Dt'_D3DJP Lc L_E_ALL__ REC 0_S_0 V DI SPOSI TION OF C ALL NAME OF ESTIMATED TIME, NO TIME OF g, CALL EESSD3. _C_A LL.e)r ___C_A LLLaJ____Aed 4

95. E.R.___3 uS _Y___ ___ __A _R _R 1LA L _ ___ __ C D_#_

W ___________________________ ______________________________m_________ W ___~___________________________ W _____________________________ __________ ____________________________ w w ________ _______________________ ______________________________________ . Y w _____________________________ v _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - . __ v _____________________________ w ____e._________eleque________ s emes __euh_eumeumy________4eID_emb-_______.us_______e.___ee__e.--_

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                                                                                          '        PAGE 9 OF 9 REV. 5 g          /                                                                                      EGF: WAF AEEESD11 EE_106-3 EdESGESCI EZEDSUEE_LIMIIS PROJECTED WHOLE DODY EUML1133                                 THYR 0!D
                                               - DuSE                   gg3g                          H RIZE0 I .L IFE S A VING AND REDUCTION OF INJURY                                ~

75 REMO 375 REM ENERGENCY00 - \v 2.UPERATION OF DIRECTJ4 E QUI P ME N T TO

      , %r             MITIGATE AN                                                                              .

EMERGENCY g 25 ' REM

125 REM EMERGENCY 00 he DIRECTOR-3.PROTEC T ION OF HEALTH AND SAFETY kr OF THE PUBLIC .

5 REN 25 REM EMERGENCY DIDECTOR 4w 4.OTHER EMERGENCY 10 CFR 20 AC TI VI T IE S LIvlTS 10 CFR 20 EMERGENCY LIMITS DIRECTOR L, 5.R E-EN TR Y/RE-COVERY ADMINISTRATIVE GUIDE L INES A DMINI S TR A T I VE ACTIVITIES GUIDE LINES N/A h, O REFT.FNCE: 00SUCH EXPOSURE E P A-5 20/I- 75 SHALL BE-001 ON TABLE A 2.1 v VOLUNTARY BASIS

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j .. EGF: WA g I Qgg ' ggf 2 3 iM2 l t PH IL ADEL PHI A ELEC1 HIC COMPANY - i

                                      ,        c,.                               - ! :PEACH 00TTOM UNITS 2 AND 3
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                                                                        -~E N ERUE NC Y P L AN IMPLEMENTING PROCEDURE EE-lDf2_ _LESEBAL_1f.!EEGESC1_tiESEDSSE EUSEDSE                                                           -

TO DEFINE THE SITE RESPONSE IN THE E' VENT OF A GENERAL EMER GE N.CY.

BdEEEEUCES 1.

PE ACH BOTTOM ATOMIC POWER ST A TION EMERGENCY PLAN SECIIDS IIILE . 4.1.4 GLNEKAL EMERGENCY 50 ORGANIZATIONAL' CONTROL OF EMERGLNCIES 61.4, GENERAL EMERGENCY -

2. NUREG 0654 C R I TE R I A' FOR PREPARATION AND EVALUATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPAREDNESS IN SUPPQRT OF NUCLEAR POWER PLANTS.

3. EP-101 -

CLASSIFICATION OF EMERGENCIES AEEENDlEEL i EP 105-1 GENERAL EMERGENCY CHECK 0FF LIST l EP 10,5-2 PERSONNEL CALL HECORD EP 10$-3 EMERGENCY EXPOSURE LIMITS (EMERGENCY PLAN TABLE 6.1) E8ECAUIIDSS t 1.

               .               PLANNED RADIATION EXPOSURES SHOULO BE LIMITED TV THC ADMINISTRATIVE GUIDE LEVELS IN APPENDIX EP 105-4 EMERGENCY EXPOSURE *LIMI TS.

IMEalAIE_ACI1QMS ' { 1.0 SHIFT SUP E R V I S I ON SHALL: 'I 1.1 ASSUME THE ROLE OF INTERIM EMERGENCY OldECTOR. j 12 ACTIVATE EMERGENCY TEAMS AS NECESSARY IF NOT ALREAJY l I

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                 /                                                                                REV. S EGF:WAF

( MEMBER TO ODTAIN A SITE BOUNDARY DOSE RATE AS 5004 AS PRACTICADLt. 1.14 IF NECESSARY, INITIATE IMPLEMENTATION OF EP-316 AND

                   ~"                       EP-317, DIRECT RECOMMENDAJIONS TO COUNTY EMERGENCY MAN AGE-i
                                          ' MENT AGENCIES.      .

2.0 COMMUNICATOR SHALL: 2'.1 . PERFORM NOTIF ICATIONS ON APPENDIX CP 105-1 USING THE S TANDARD PROMP T NOT.! FIC A T ION ME SS AGE INCLUDED. SEE EP 209, APPENDIX A, FOR TELEPHONE NUMBERS. 2.2 dEPDAT TO THL , EMERGENCY DIRECTOR WHEN THE NOTIFICATIONS ARC C OMPLE T ED. . . . 2.3 MAN THE RED NRC TELEPHONE IF REQUIRED BY.A-31 UNTIL SITUATION ST ABILIZES ANU RED TELEPHONE COMMUNIC ATIONS MAY BE SECURED. 3.0 OPERATIONS SUPPORT Crurl R COORDINA TOR OR HIS DESIGNEE SHALL: 3.1 ACTIVATE THE t ..fbNS SUPPORT CEN TER, IF IT IS hah!TABLL, IN k ACCORDANCE ri! T H EP 202. IF THE OPERATIONS SUPPOR T CENTER IS NOT HAb!TABLL REPORT TO THE CONTROL ROOM. t + 4.0 RADIATION PROTECTION TE4.'l LEADER SHALL: . 41 INITIATE ON AND OFF SITE RADIATION S UR VE YS IN ACCORDANCE WITH EP 20$, MA01ATION PROTECTION TEAM WHEN DIRECTED BY THE EMERGENCY DIRECTOR. IF THIS PERSON.IS ALSO THE HP ENGINEER HE SHOULD\ REPORT TO THE . EOF TO COORDINATE THIS FUNCTION. 5.0 SH IF T ICC TECHNICIANS SHALL: 5.1 ACTIVATE THd TSC AND EOF (IF NOT ALREADY ACTIVATED

              -                          DURING ALERT OR SITE EMERGENCY S TAG 1:) IN ACCudDANCE WITH EP 201 AND EP 703.

6.0 SHIFT CLERK SHALL: / 6.1 IF NOT ALRf ADY .!MPLCMEN TED DURING AL LR T' 04 SITL LNEdCCNCY STAGE, CONTACT INDIVIDUALS ON EP ?O9 APP P TO CALL IN THOSE INDIVIDUALS TO MAN THE TSC AND EOF 160 MINUTE CALL LIST). DOCUMENT CONT ACTS ON EP 209 APP P. 6.'2 IP30RM INTERI M EMERGENCY DIRECTOR OR EMERGENCY DIRECTOR WHEN CONT ACTS ARE COMPL E TED. { EOLLQW:uE_ACIl035 ~ 1.0 EMERGE NCY DIRECTOR SHALL:

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                                                                            ,                                    PAGE 4 0F 9 RCV. S
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                                             -      PERIODICALLY EVALUATE THE EVENT CLASSIFICATION IN ACCORD-

ANCE WITH EP 101, CLASSIFICATION OF EMERGENCIES. IF THE CONDITIONS CHANGL, DEESCALATE TO AN APPROPRIATE CLASSIFI-CATf0N.

12 OBTAIN RESULTS OF THE CUMUL'ATIVE POPUL A ION DOSE CALCU-

                                                                                                                                            ,.(
                                         '         L ATIONS AND ONSITE/OFFSITE RADI ATION SURVEYS FROM THE
                                               .. RADIATION PRO TEC TION TE AM L EADER.           .                                   $

1.3 REFERRING TO E P-317, PROVIDE APPROPRIATE INFORMATION FROM THE PREVIOUS EVALUATIONS AND PROTECTIVE ACTION RECOMMENDATIONS TO A. COMMUNICATOR IN THE EOF FOR NOTIFICATION OF THE UUREAU OF RADIATION PROTECTION.

14 PERFORM ACTIUNS AS NECESSARY TO MITIGATE CONDITIONS OF THE EMERGENCY SITUATION.
1.5 IF NOT ALREADY PERFORMED. OETERMINE 4HICH ADUITIONAL SUPPORT PERSONNEL ARE NEC'ESSARY FOR EMERGENCY FUNCTIONS AND DIRECT THE SHIFT CL ERK OR THE COMMUNICAf0R IN THE TSC 04 EOF TO CONT ACT THOSE PERSONNEL.

1. 6 ' PROVIDE SITE PER50NNLL WITH PA SPEAKLR ANNOUNCtMENTS FOR k ANY MAJOR CHANGES IN PL ANT EMERGENCY S TA TUS, SUCH AS CHANGING E .95 R G EN C Y ACTION LEVELS, TVACUATIONS, AND STARTING AND STOPPING OF RADIDACTIVE RELEASES (IF ANY). .

2.0 ST ATION SUPERIN TENDENT SHALL:

2.1 HEPORT TO THt TECHNICAL SUPPORT CENTIR OH CONTdOL ROOM, FOR A BRIEFING OF'THE SITUATION.

2.2 ASSUME THE ROL E OF EMERGENCY DIRECTOR (IF NOT ALREADY DONE) BY FORMALLY RELILVING THE INTERIM cMERGENCY DIRECTOR. ANNOUNCE THAT' HE H A S A S SUMED THE ROL E OF EMERGENCY DIRECTOR TO THE ASSEMBLED TECHNICAL SUPPORT CENTER PERSONNEL. . 2.3 VERIFY THE EMERGENCY CLASSIFICATION. t . 2.4 VERIFY THAT THE TECHNIC A L SUPPOR T CENTER, EMERGENCY OPERATIONS FACILITY AND THE OPERATIONS SUPPORT CENTEx HAVE BEEN AC T I VA TE D. ' 3.O* OPERAT IONS SUPPORT CENTER COORDINATOR SHALL; 3.1

NOTIFY THE INTERIM EMENGENCY DIREC TOR WHEN THE OPERATIONS SUPPORT CENTER IS ACTIVATED. .

32 SUPPORT THE CONTROL ROOM AND SHIFT SUPERVISION AS

                                                ,NECESSARY.                                              '
                    . 4.0 RADIATION PROTECTION TEAM LEADER SHALL:                         .

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                                                                                                 <:c l                             EP-IOS.

i '. e ' PAGE 5 0F 9 REV. S EGF:WAF

   . (-

4.1 NO11FY THE EMERGCNCY DIRECTOR WHEN THE CMERGENC'.' OPER AT IONS F AC IL ITY. IS. AC TIVA TED. ' 4.2 R EPORT PROGRE SS AND RESULTS OF CUMUL ATIVE POPUL AIION ' DOSE CALCULATIONS AND ON AND OFF SITE MADIATION SURVEYS TO THE EMERGENCY DIRECTOR, AS NECESSARY. 43 NOTIFY THE SITE EMERGENCY COORDINATOR OF THE NEED FOR ASSISTANCd FROM RADI ATION MANAGCMENT CORPOR A TION. 5.0 SHIFT CLERK OR ASSIGNED.TSC OR EOF COMMUNICATOR SHALL:

 .                                  5.1 WHEN REQUESTED, NOTIFY ADDITIONAL SUPPORT PERSONNEL TO REPORT TO THE PL ANT 'AS DIRECTED BY THE EMERGENCY OIRECTOR.       REFCR TO EP 209.                          .

S.2 NOTIFY EMER0ENCY DIRdCTOR OR SITE EMERGENCY C00RDINATOR

             .                              WHEN ADDI TIONAL SUPPORT PERSONEL HAVE BEEN NOTIFIED.

DOCUMENT ON APP EP-105-2. 6.0 ICC TECHNICIANS SHALL: (IFNO[ALREADY PERFORMED AS RER

                                ,   EP-103 0:1 CP-104) 61 INFORM THE ENERGENCY DIRECTOR WHEN CENICd5 ARE ACTIVAT 6.2 MAN THE TSC AND EOF DATA DISPLAY (CCTV) POSITIONS AS DIRECTED BY THE EMERGENCY DIRECTOR.

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EP-105 e

PAGE 6 OF 9

                                                                                                                                    .               MEV. 5 EGF:WAF                   ,

( . ABEEUELE_EE_105:1 GEULSAL_E5EECCUCY_UDILELCAIl0N_CudCduEE_LLSI s MESSAGEl THIS (IS) (IS NOT) A DRILL. THIS (IS) (IS NOT) A

 *       *       "' DRILL.   #                THIS IS PE ACH .BUT TON ATOMIC POWER S T A TI ON C ALLING TO RE PORT A GENERAL EMERGENCY HAS BEEN DECLARED ON UNIT NO. _____.                                                                           TIME
                '        AND DATE OF GENERAL EMERG.ENCY CLASSIFICATION IS __________.                                                                              THE BASIC PROBLEM IS __ _                         ___                 ____

THE PLANT STATUS IS (STABLE) (IMPROVING) (DEGRADING) (NOT KNDWN).

             '           THERE (IS PRESENTLY) (HAS NOT HEEN) (IS POTENTIAL FOR) (HAS BEEN)

A RADI0 ACTIVE (AIRBORNE) -( L IO UI D ) RELEASE FROM THE PLANT (AT A LEVEL

                       'OELOW THAT CONSIDERED A PUBLJC HAZARD) (AT A LEVEL AT WH IC H PRO TE C T I VL
                        ~A C T,I ON IS ADVISABLE).                         RECOMMENDEO PROTECTIVE ACTIONS ARE (NONE)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ ____. THE AFFECTED POPULATION

                      . AREA IS (NONE)                     ___    _        _ _
                                                                                                                                             .. MY NAME IS __                       _____        ______                          ___.            THIS (IS) (IS NOT) A DRILL.               THIS (IS) (IS NOT) A ORILL.          ,

U011E1CAIIDdSi PERSON . TIME OF COMMUNICAT03'S CARTY SESPGSQLyG UDLIEJCALLDS 'lyLLILLS M TATION SUPERINTENDENT ____________ ____________ ______________ LOAD DISPATCHER _______ - ( ' ____________ ______________ (TELL HIM TO INITI A TE , . CALL LIST."C")

      .                 PENNSYLVANIA EMERGENCY MANAGLMLNT AGENCY 0                                           _ _ _                           ______          _

(BLUE PHONE OR . l j MARYLAND C IVIL DEFENSE AGENCY __________ ____________ ______________ (BLUE PHONE OR YORK COUNTY EMERGENCY MAN AGE MENT AGENC Y _____ ____________ ______________

                ,       (DLUE PHONE OR LANCASTER COUNTY EMERCENCY MANAGEMENT AGENCY                                                                                                         '

(DLUE PHONE Ok l CHESTER COUNTY ENERGENCY MANAGEMENT ' AGENCY _____ _____ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (BLUE PHONE OR i ( H ARFOR D COUNTY CIVIL DEFENSE AGENCY .________ ____________ ______________ i

       /      ,         (BLUE PHONE OR 1

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EP-IOS PAGE 7 OF 9 REV. > EGF:WAF - AEEEUQiK_EE_iQh-1_iCO31101 GENEdAL_EMESGENEX_UDE1E1CAIl00_LUELEDEE_LISI

                        . CECIL COUN TY CIVIL                         ,                   -          -      -
                  ' "" DEFENSE AGENCY                                                              -

(BLUE PHONE OR , PENNSYLVANIA STATE POLICE .- YORK . (1-848-6355) - PA BRP (WH,ITE PHONE OR

NRC OPERATIONS CENTER ** (dE0 PHONd) TIME NOT IF IC A T ION OF P A RTI F S ADQVE COMPL E TE D _._______________ VERIFIED BY - d>r DATE __________ '

                                                      ' EMERGENCY DIRECTOR                                 '

s FIL6 - SYS-3-1 c MUST NOTIFY PEMA BY USE OF COMMERCIAL TELEPHONb NO. ON BACKSHIF I BLUE PHONC NOT MANNLD BY PEMA ON BACKSHIFTS. .

                         ** IF NRC PREVIOUSLY NOTIFIED DURING ALER T OR SITE EMERGENCY CONDITION, THE ASSIGNED PO COMMUNICATOR CONTINUOUSLY MANNING THE RED PHONE IN CONTROL ROOM huQuLQ HANDLE THIS NOTIFICATION AUTOMATICALLY. HOWEVER, CHECK WITH CONTROL ROOM TO BE SURE THIS NOTIFICATION IS MADE.

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P. E V . *> 4GF:WAF e e s( - AEEENtiLEfL10hl r a EEBSUSS. EL_G ALLWBEEDED DISPOSITION OF CALL - -

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                                                                                                                                 ~

ESTIM5TED CALL s O e M.eflmEAL. LED __w".a" LLE0me e Ae.d~ W e8 P me DUS.Y em.'LidEemDr# e. ABl.4.leVAL_mED. Men P Lf _T EDe ".eeY

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memM N hm WDM m e eumamme eem6 m e enem EDemW me e e _ mem M w mem e emeee ee em em m W mW m e en ese mW m meneneemm ew_ _ m _ _ _ _ _ _ m _ m _ 6 _ _ m me.m _ m me m W W W - _ _e.m m _ _ _ _ _ e m m m m W W m _ W _ W W _ _ _ m e m W- = S 8 e NW m hm absme em eD er em 6 We euS esembeup66 m3 em WW WW h euD GNM GDW e 6 m em mepW WemWem MMeem eqm WDe mWem N emmeen- - e- useemen e- - m en emme e en me m en == ==We.memm amme= me=em -ames ame Wem em upepGW e3meIDeme5m erepp WS epene emes eh aseD e em W emep m en eDWADes __ h Neures emWelp GN epen eDemess ED meespee Se em AID Wee e hmemM mem We e em WWW e eW mem G em66 es e go as emen me esem 6 mWWW _ h heDW h eDW emmene9 WW es eIDemem em mew e _ We6Ne 6 m M WW WWW ememee mWM ee e W esW W -- 4 mmm 6 mmM M M em N ee e e W m eut empemenW emp W eSem m mem 6 enem me3 6 mm Wm e em e@ em W 6 m W e m6 ed es M WWe e e e m W e emMM wme emme em eem m m eememeeeeowWW 6 emmeme6 6 enem m eWWeeeemumWmWWepemaeemeWesempeeee emme - --- _Z 9 MM em enemm m emesem w WM em up we _ eWW 6 m - '- - _ _ - - eum Mesh em W em W We up --- 0 __mmeesememeeemesenemw w 9 _me_me _ m _ m.mu.a._ew_meme.W_e.mme.m _ m_ _ mm-e.e._me.mt.mme.W_Wm.WWM_e.meWW_e. e m e W ee m-pepe Neues Melsep eD eum humum Weeep W e 6memW emetenem W _ _ M eIDW W mID em WWWm m6 m 6 MW W e e9 m e em e e e eem e em emem me- ====== enemmenama emeum e e emmen emme me eem == um egen enemmen meme. == eu, en _

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 *                                     *    -                                                                               EP-105 PAGE 9 0F 9 REv. 5 EGF:WAF

I .

AEEEbD11_EE_191:3 E5E&GENEI_EEE01USE_ LIM 111

               * ^
                                                                 .              PROJECTED             --"--

WHOLE. BODY THYROID s EuuCILDU QUSE AUTH0Rilt DDSL - Bt

1. L'IFE SAVING AND -

REDUCTIJN OF INJURY 75 REMC EMERGENC)

                                                                            ,                                     375 REM             DIRECT 0d

2. OPERATION OF EQUIPMENT..

TO MITIGATE AN, cMERGENCY C ME R G E.NC ) 25 REM 8 125 REM DI REC TOR

3. PROTECTION OF HEAL TH AND SAFETY OF THE PUBLIC '

5 REM

                                                                                                     '                               EMERGENCY 25 REM          DI REC TOR

4. OTHER EMERGENCY 10 CFR 20 10 CFR 20 ACTIVITIES EMERGENCY L I M I .T S LIMITS DIRECTOR

5. R E- EN T RY/R t C O V ER Y ACTIVITIES ADMINISTRATIVE ADMINISTRATIVE GUIDELINES GUIDELINCS N/A

REFERENCE:

CPA-520/1-75-001 TABLE 2.1 -

                 **SUCH EXPOSURE.SHALL DE ON A VOLUNTARY BASIS
 .                                                                           i e

S e e e e

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Y* * (s . [ EP-705A (

         ' "j j'      PAGE 1 OF T    .
        ,                                                                                                       REV. 4
                                                                                                    '          EF:T H JN$

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                '                                                                                                          ^

La nM 2 5 %1 PHILADELPHIA ELECTRIC COMP,ANY V l .l'LACH i_.__. _ . 3 !!OTTOM UNITS ,2 AND 3 EfERGENCY PLAN

     'N                                                                          IMPLEMENTING PROCEDURE
          %r E-2.01A___Ct1Et!1Sla1_hidELiaG_itiD EuaEasE

_ dye ASALXS TO DEFINE - GROUP.* THE ACTIONS OF . v Br.EEELUCES THE CefEMISTRY S AMPLING . IS AND AN

   ;.3v 1.

l l PEACH BOTTOM ATOMIC N POWER'STATIO EMERGENCY PLAN

   ' ke                             SEC1109
  ]                                                       IllLE

i 5 2 2 2 1.E

  '   \v i                                 6* 2.I                 CHEMISTRY SAMPLING AND ANALYSIS i

W ( 2. ASSESSMENT METHODS FOR DETERMI OF RELEASE TO THE ATMOSPHERE NING MAGNITUDE V

                        .HEt.altiSEEAL TH PHYS ICS OPER ING                                   A TING PROCEDURES
                                                                                                               /CHEMISTR Y
                                                               *IIILE HP0/CO-4
 \s RADIATION WORK PERMITS 3.

NUREG 0654 s PREPARATION AND EVALUATION OF R EMERGENCY NUCLEAR AEEEND1E POWER PLANTS. RESPONSEIN SUPPOR PLANS T OF AND EP 205A-1 . AC110S_LEZEL EMERGENCY EXPUSURE LIMITS (EMERGENCY PLAN TABLE 1) 6 g THE CHEMISTRY THE DISCR ET ION OFS AMPLING AND ANAL YSIS GROUP ' EBEtau110S$ - THE R ADI ATION PROTEC TION. WILL BE ACTIVATED TEAM LEADER. . 1. IN ALL STEPS OF . ( S AMPLING AND ANALYSIS GROUP MEMBERTHIS PROCEDUR CONCEPT TO THE LIMITS. EXPOSURE ADMINISTRATIVE VEL GUIDE S. IN LE IS MANDA TORY. APPENDIX'S EXPOSURE CON TR OL THE IR OWN CHEMIS TRY SAMPL EP EXP3SURES. ING 205AND A-1, EMERGENC Y ANALYSIS GROUP MEMBERS e

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                                                                               --                 - ~      _ _ . _             3
        + k)         '

EP-205A j, PAGE 2 0F 7 REV. 4 b( EF: TTH 2. REQUIREMENTS OF HPU/CO-4, RADIATION WORK PERMITS, IMME01alf_4L110bi ARE NOT APPLIC ADLE. Le 1 0 RADIATION PROTECTION TE AM L EADER. SHALL: '

   ,6 11      CONT AC T THE., CHEMIS TRY DIRECT HIM TO COLLECT SAMPLING AND ANALYSIS GROUP                 LEAUER, SAMPLES IN ACCORDANCE WITHSAMPLES, AS NECESSARY,
       *s                    SUPPORT GROUPS FOR                   HP0/CO       PROCEDURES:      AND ANALYZE THE THE ANAL YSES.

OR USE OFFSITE 2.0 CHEMI STRY Ls 41 S AMPL ING' AND ANAL YSI S GROUP SHALL: L EADER AS SLMcLE THE CHEMIS TRY

  ,%v               22 ' DIRECT                             S AMPL ING AND- Al9ALYSI S GR OUP.

MONITORS, THE MONITORING WITH PRECAUTION AND PROCESS

                                                   'l,.ABOVE.

AND SAMPLING, AIR MONITORS AS REQUIRED AND O'F RELEA

   %v                                                                                      IN ACCORDANCh 2.3 ANALYZ E THE DAT A AND EFF LUENT INSTRUMENT              READINGS.FROM S AMPLES,      READINGS.PROCESS I
  %d 2.4 ISOTOPIC COMPOSITION ANDFROM RELEASE
                                                                                  . THIS DATAR DE A TES TE R MINE
                            #ROVIDE THE DOSE                                         .

l/

                          . AN0' DI REC T GROUP MEMuGRSASSESSMENT                                  GROUP WITH PERTINENT INF04MATION TO ASSIST, AS NECESSARY, WITH 00SF RATE CALCUL ATIONS AND                          DETERMINATION         NSEQUENCES.OF RADIO W                         .

2

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EP-205A ! s, - PAGE 3 OF T I REV. 4

EF: TTH

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l, 3.0 CHEMISTRY SAMPLING AND ANALYSI S GROUP MEMBERS SHALL: 31 g bs 'SAMPLES. ASSEMBLE PR6 LTHE AJEL ALL I4GLtSSARY EQUIPMENT NEEDED TO ODTAIN AN USE APPENDIX LP 205 A-2 TOSAMPLE CONTAINERS BEFORE SAMPLING. INSURE ALL STEPS IN THE . HPO/CO SAMPLING FOLLOWED. . AND ANALYSIS PROCEDURES ARE

 %s                                          ~                                                                            .

v 3.2 ' WITH SAMPLE PRIMARY THE FOLLO' JING PROCEDURES: COOLANT AND DP.YWELL ATEOSPHERE A S

                                       .EP 205A.I                                OPERATION OF POST ACCIDENT We                                   '

S AMPLING ST AT ION.FOLLOWING

                                                                        ' ACCIDENT CONDITIONS w                                         EP 205A.2 OBTAINING DRYWELL. GAS SAMPLES FROM CONT AINMENT ATMOSPHERE DILUTION CABINETS

w r EP 205A.3 RETRIEVING AND CHANGING SAMPLE J

FILTERS AND CARTRIDGES FROM THE DRYWELL RADIATION MONITOR , EP 205A.4 s I. OBT AINIf4G DRYWELL G AS S AMPLES FROM THE DRYWELL R ADI AT ION MONITOR SAMPLING STATION s EP 205A.5 ORTAINING REACTOR WATER SAMPLES

                                   .                                       FROM SAMPLE SINKS FOLLOWING ACCIDENT CONDITIONS..

s 33 IN THE EVENT OF A L ARGE R ADI0 ACTIVE LIQUID SPILL, OBTAIN SAMPLES OF THC RIVED WATER IN ACCORDANCE WITH: s EP 205A.6 UDTAINING CANAL DISCHARGE WATER SAMPLES FOLLOWING RADIOACTIVE LIQUID RELEASES FOLLOWING ACCIDENT CO,NDITIONS. 3.4 USE THE FOLLOWING PROCEDURES VARIUs5 SAMPLE POINTS. TO OBTA'IN SAMPLES FROM THE MAIN SLACK E ROOF VENTS EP 20SA.7 OBTAINING THE IODINE ANO PARTICULATE SAMs ES FROM THE MAIN STACK AND ROOF VENTS FOLLOW!NG ACCIDENT CONDITIONS. ( L ICUID R AQsA S TE EP 205t.B OBTAINING LIQUID RA0 WASTE

s '. .

                                  *                                                                            . e EP-205A
                                                                                  '    '               PAGE 4 0F 7 j      REV. 4 EF:TTH
        '., (
        ..-                                                       S AMPLES FROM. THE R ADWAS TE SAMPLE SINK FOLLOWING ALCIDENT CONDI,TIONS.

CONDENSATE -

5. . - ,

EP.20$A.9 ss ~ OUTAINING SAMPLES FROM CONDENSATE SAMPLE SINK FOLLOWING ACCIDENT ' *

    .%d                                                        . CONDITIONS.

DFF GAS

     %s EP 20SA.lO      OFFGkSSAMPLESFROM                  THE
                              ,                                OFF GAS HYDROGEN ANALYZER

.t w FOLLOWI'G N ACCIDENT CONDITIONS. ' r - Rh BUILDING UR TO4US ATMOSPHERE w En 205A.ll DPERATION OF POST ACCIDENT . SAMPLING STATION. V 3.5 5 USE THE FOLLOWING PROCEuuRES FOR

'                                 H'IGHLY RADICACTIV6 SA'MPLES.                       THE PREPARATION AND ANALYSIS OF

( v , EP 2 0 5 A .1,1 S ALMPL E PREPAR ATION AND CHEMIC AL

us ANALYSIS OF' HIGHLY RADI0 ACTIVE LIQUID SAMPLES.

EP 205A.12 V S AMPL E PREPARATION AND ANALYSIS OF HIGHLY RA'DIDACTIVE PARTICULATE FILTERS AND IODINE CARTRIDGE S. v EP 20bA.13 SA'4PLE PREPARATION AND ANALYSIS 0F HIGHLY RADIOACTIVE ~ GAS. SAMPLES. 36 v AT T ACH ALL DATA SHEETS EP 205A-2(CHEM SAMPLING AND C ANALYSIS REPORTS TO APPENDIX SAMPLE TAKEN. ANALYSIS C.O.L.) FOR EACH b GIVE THIS INFORMATION TO THE CHEM SAMPLING AND AN ALYSIS GROUP LEADER. ~ EQLLUE u2_ACIl005 ke 1 0 R ADI A TI ON PROTECT ION TL AM LEADER SHALL: 11

-                               REPURI THE RESULTS OF THESE ANALYSES TO THE SITE EMERGENCY 12 COO.4DINATOR (IF ACTIVATED) AND THE EMERGENCY. 0! R k<                               PROVIDE GROJP MEwuE RS WITH PERIODIC                             PL ANT STATUS

( CHANGES I ACLUDING SIGNIFIC ANT R ADI ATION CONT AMINA TION PRUDLEMS WHICH EXPOSURE AND R ADI AC TIVE MAY AFFECT THE FUNCTIONS OF TH,E TEAM. 2 0 CHEMISTRY SAMPLING AND ANALYSI S GROUP L EADER SHALL e

r .

m i: '.t. .

                                                          ".                                           EP-205A y     .     .
                                                                                                .. PAGE 5 0F.7
                                                                                               /       REV; 4
                                                                                   .                   EF:TTH          -

vt

 ,      V              21 RC01DJRT Pet EC T 10NRESULTS        CF S T E A P. LEADER. AMPLLS AND AN ALYSES TO THE RADIATION I

V - I V - n W .

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                                                                              $-            =

EP-205A

                                                                                                                      . PAGE 6-OF 7
                                                                                                                     /;     REV. 4 EF: TTH
 'v                                                                   AEEEMIX_EE_ZbSA:1 E5EEGESC1_E4EQSUEE_L15115 v                                                              PROJECTED                                             . .
                                                                     'WHOLE BODY                                THYROID                AUTHORIZE 0 EDUCIID3             '

DQSE DDSE 'El

1. LIFE SAv!NG AND .

EMERGENCYCC REQUCTIUN OF INJURY 75 REM * '375 REM y' . DIR EC TOR

2. -OPERATION OF EQUIPMENT

TO MITIGATE AN EMERGENCYe*

W EMERGENCY 25 REMC *

                              ~                                                                                125 REM                 DIRECTOR

3. PROTECTION OF HEALTH '

      %#                      AND SAFETY OF THE                                         '

EMERGENCY ** PUBLIC 5 REM 125 REN DIRFCTOK W 4.' OTHER ENERGENCY 10 CFR 20 10 CFR 20 EMERGENCY ACTIvlTIES

DIREC TOR

     %r              5.       RE-ENTRY / RECOVERY                     ADMINISTRATIVE                           ADMINISTRATIVE ACTIVITIES                              GUIDELINES                               GUIDELINES
                                                          '                                                                           N/A

( V' C

REFERENCE:

E P A-52 0/1-7 5- 001 T A BL E 2 1

                    **SUCH EXPUSURE SHALL BE ON A VOLUNTARY BASIS v

> \s e e d

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EP-205A

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PAGE 7 0F 7 4

                   .                                                                             [        REV. 4 EF:TTH 5

1h ws AEEENDIL_LE LD5L 2

      !                                                  Cu25_SABEL1BG_L ANALYSIS C204La
      .  " %s SAMPLE                                                                                 .

{ TIME __________ . oAre __________ s!_ %v

_______ __~

l ' SAMPLING:

%W

(# SAMPLE CONTAINER PRELABELED __________ LEAD CARRYING PIG OBTAINEO ______ {(!bv g SAMPLING EQUIPMENT PROC EDURE REVIEWED ASSEMBLE 0 ___ ___________

RWP ISSUED.OR HP AVAILABLE__________ bv ' i SAMPLE STZE SAMPLE DOSE R A TE (CONTACT) __________

V __________

ANALYSIS:

 " 4/,                         EQUIPMENT ASSEMBLE 0 LAB SET UP FOR ANALYSIS __________

TO MINIMIZE EXPOSURE

As ( PROCEDURE REVIEWE0 __________

ANAL YSIS PERFORMED: ! ATTACH GELI SCAN RESUL TS OF ANALYSIS) V - CHLO. RIDE ANALYSIS __________

BORON ANALYSIS __________

GAS CHROMATOGRAPHY __________ V OTHER (EXPLAIN) __________ __________ s M SAMPLE VOLUME USED FOR AfjALYSIS l __________ ~ t * { t Y

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                                            ~~

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                                                                                    'y
                                                                   . . .a PHILADELPHIA ELECTRIC COMPANY

PEACH BOTTOM UNITS 2 AND 3 t * .

EP 205A.3 RETRIEVING AND CHANGING SAMPLE FILTERS AND CARTRIDGES FROW THE DRYWELL RADIATION MONITOR DURING EMERGENCIES PURPOSE: This procedure provides gu'idelines in retrieving and changing particulate filters and charcoal cartridges (or silver xeolite cartridges) located at the drywell rad monitor following accident conditions with major fuel damage. APPARATUS: . 3 Appropriate health physics survey equpment Respiratory protective equipment Anti-contamination clothing Low-volume air sampler i Designated remote handling devices

     '        Transport containers (shielded)

Digital-alarming dosimeters Extr,a rad monitor filter holder Extra rad monitor cartridge holder PRECAUTION: NOTE: A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in preplanning evolutions in changir.g and obtaining drywell rad monitor filters and cartridges. In addition to reviewing this procedure, an ALARA review of the sampling process should be performed prior to obtaining the filters. If the sample is not really needed, and lower dose methods

                         ,to   determine the gross data that the sampic provides exist, the sample should not b e obt a i n e d .

B. At no time may NRC exposure limits (either airborne or body dose) be exceeded during the surveying for rampling or obtaining the sample. If it appears that an overexposure could reasonably proceed without writtenoccur when obtaining the sampic, do not NRC approval. m....--....._._._-- - - _ _ _ _ e

_ ~ - - . e

             '                                                                       EP 205A 3 P;ge 2 of 4, Rev. 0 PROCEDURE:
     ,               1. It has been determined that the particulate filter and iodine g

cartridge are required to be changed e.at the drywell rad

monitor on 135' elevation of the Reactor Building. 2. Area radiation monitors shall be checked and if the monitors in the area of the drywell rad monitor are indicating greater than 10 R/hr, changing the sample should very possibly not be concidered.

3.

Have a health physics technician accompany the chemistry technician assigned to obtain samples in order to perform area surveys. Brief health physics personnel on the route to be taken and the time to get to the survey pcint. Attached as appendices are the location of the particulate filter and the iodine cartridge. Survey maps are also provided. 4, NOTE:

1. The time to travel from the 116' elevation entrance to the Turbine Building to the drywell rad monitor is approximately four minutes.

L

2. Other routes may be considered. The times expected would be approximately four minutes for these routes, as well.

4. Health physeis personnel shall take appropriate survey and protective equipment (e.g. SCBA, Mti-Cs , lead carrying container, etc.) Before making entry to the power block, ensure survey equipment is turned on and calibrated.

5. Upon entering the power block, the surveyors will note trends in general radiation levels enroute to the drywell rad monitor. If dose rates exceed 10 R/hr gamma or 10 rad /hr beta prior to arrivi:

i at the door leading to Rx 135 and upon further investigation this dose rate remains stable or it. creases, exit immediately and report to health physics supervision. If dose rates exceed 5 R/hr at the door leading to Rx 135, leave the area immediately and report to health physics supervision.

6. Survey the area c on c en t ra t i r. g especially on the particulate filtc.

pig, iodine cartridge pig and sample lines. Ensure that a low-volume air rample is taken (in tne " breathing zone"). Special note of window open readings must be made because of the submersion ai'r dose beta fields.

(

w - O O ,,20s,.3 P;ge 3 cf 4, Rev. O s NOTE: ' A. It will take approximately two minutes to pull and change both the filter and cartridge. B. Ensure the samples. that survey equipment is required when retrieving C. Consider discarding samples in place at the time of the accident as they will likely be too radioactive to count for gamma spectroscopy. For more meaningful data, a shorter sampling time should be determin'ed for the replacement particulate filter and iodine cartridge.

7. Suggested filter and cartridge change method (This procedure may be changed after an ALARA review.)

A. Obtain radiation monitor. the extra filter holder and cartridge holder for the drywe t B. Insert a .ew particulate filter and charcoal cartridge into these holders. Consider the use of silver zeolite cartridges in the place of charcoal to limit thc noble gas buildup. C. Obtain two "J" hooks for removing the holders which are presently in service. Use the "J" hooks for transporting the holders at a distance from the body. D. At the drywell radiction monitor

1. place radiation monitor in purge l 2. remove thutb screws on holders

3. place "J" hook on the "O" ring of the holder

4. pull the holder from the pig.

5. survey filter or cartridge and remove from area with "J" hool

, if required by HP. ) 6. ' slide new holder into the pig

7. repeat steps D(3) to D(6) for the other holder

8. replace one thumb screw in each holder

9. return radiation monitor to service l 10. exit the area.

8. Consideration of expected dose rates from the samples must also be considered. In this regard, the time to take the filter and cartridge to the hot lab versus shielding the sample must

( be considered. The personnel who will obtain shall be briefed on all alternatives and will provide input into practical methods of remotely handling the samples. t l * -

O O EP 205A.3 Page 4 of 4, Rev. 0 9. A RWP shall be assigned for the retrieval and changing of the

   '                           filter and cartridge evolution. The RWP shall be followed

( by all personnel handling the sample.

10. Iffthe samples are too " hot" for gamma spectroscopy, they will be brought to the hot lab to await. final disposition. Any shielding, remote handling devices or other protective measure shall be in place 'and ready to accept the samples prior to their a77 val.

i

11. After the samples are properly stored, responsible supervision si discuss and decide upon final disposition.

12. If the samples are able to be analyzed for gamma spectroscopy, the particulate filter and iodine cartridge shall be processed

. in a manner such that the detector does not become contaminated.

13. Following final analysis of'the sgeple, results shall be reported to appropriate supervision.

4 h a

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                                   ,O                                O    Ee 20sA.3        A,,emaice, EP 20sA.3 APPENDICES k

A. Photographs of sa:nple points. Original photographs are kept on file with lloalth Physics Supervision. B. Pla'nt layout maps.

C. ' Survey maps. '

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Peach Bottoe. Units 2 and 3 EP 205A.5 - OBTAINING REACTOR WATER SAMPLES FROM SAMPLE SINKS FOLLO).'ING ACCIDENT CONDITIONS PURPOSE: The purpose of this procedure is to. provide some guidelines prior to, during . and after obtaining a reactor water sample following accident conditions with major fuel damage. APPARATUS: g, - Appropriate llealth Physics Survey Equipment Air Sanplcr (low volume) Anti-C clcthing Digital-Alarming dosametry 30 c: sample bott?e with lid Tongs or remote tooling for holding the sample bottle during sampling Respiratory protective equipraent PRECAUTION: A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in preplanning sampling evolutions for reactor water samples during an accident. In addition to reviewing this procedure, an ALARA review of the sampling process should be perfomed prior to obtaining the sample. If the sample is not really needed, and lower dose methods to determine the gross data that the sample provides exist, the sample should not be obtained. B. At no time may NRC exposure limits (either airborne or body dose) be exceeded during the surveying for sampling or obtaining the sample. If it appears that an overexposure could reasonably occur when obtaining the sample, do not proceed without written NRC approval. PROCEDURE :

1. It has been determined that a reactor water sample is required. Two

                 '        locations (for each Unit) where the sample may be taken from are available:

a. Feedwater Sample Sink - Reactor Bldg. 165' elevation

b. RWCU Sample Sink - Reactor Bldg. 165' elevation

(

EP 205A.5 0 0 e s> 2 Cr 4 . arv o PROCEDURE: (continued)

2. Determination of which sample sink the sampIt is to be taken from must be

( made. Consideration of which sample sink to use should be based upon plant conditions (i.e. is it stable?), which sample is operational, the tiee it will take to get there and dose rates from area radiation monitors in Various locations, etc. , approximate times and suggested routes are

              ..           described:

A. Feedwater Sample Sink, three routes are suggested:

1. Entering at the normal, Turbine 116', plant entrance, up the stairs past the Control Room to the stairs near the Reactor Bldg. elevator, and up to 165' elevation.

THE: Approx. 5 minutes

2. Entering the Radwaste Building,135' elevation, proceeding to the stairs near.the Reactor Building elevator, and up to 165' elevation.

TIME: Appro.x. 4 minutes

3. Entering the Recombiner Building,116' elevation, up the stairs to 165' elevation.

THE: Approx. 4 minutes (For Unit 3 only) B. Rh'CU Sample Sink, The same three routes are suggested, corresponding approximated times are:

1. 6 minutes

2. 5 minutes d

3. 3 minutes (For Unit 3 Only) 3.

Have a Health Physics technician accompany the Chemistry technician assig.ed to obtain samples in order to perform area surveys. Brief Health Physics persennel on the route to be taken and the time to get to the survey point. Attached en appendices are the locations of the sample points. Survey maps are also provided 4. Health Physics personnel shall take appropriate survey equipment and protective equipnent (e.g. SCBA gear lAN6-CIS Icad carrying container, etc.) . Before making entry to the Power Block, ensure survey equipment is turned on and calibrated. Chemistry valve in grab personnel shall make initial entry to assist with the survey and to sample point.

5. Upon entering the Power Block, the surveyor (s) will note trends in general radiation levels enroute to the sample point. If dose rates exceed 10 R/hr gamma or 10 rad /hr beta prior to arriving at the point specified below-and upon further investigation this dose rate remains stable or increases-exit immediately and report to Health Physics Supervision. The following dose rates shall be determined prior to entry:

    . -   _ _ _ _                                                      i

Pag ~/ 3 Cf 4, R;v. 0 PROCEDURE: (continued) A. If the dose rate e xceeds 5 R/hr at the door leading to RX 165, leave the area itnediately and report to liealth ( Physics Supervislain with this information. With dose rates le ss than 5 R/hr, enter the 165' elevation through that door. Take c:areful note of the dose rates. I B. If the sample is to be drawn from the Feedwater Sample Sink, Survey the area concentrating,. especially, on the Sample Sink , verify that dose rates do not exceed 5 R/'.nr. Survey the grab sample point (Beta & Gamma), with samn: flowing, ensure that. the low-volume air siinple l's taken at the hood, in the

                                                                                                                ^
                             " Breathing ::one".           Special note of window open readings must be made becaus<

of the high beta fields expected in the sample sink, as well as, submersion air dose beta fieleis. Survey maps and photographs are provided as part of the Appendix of th: s procedure.

                 . C.      If the sarple is te be drawn from the RECU Sampic Sink, continue past the feedwater sampIe sink. Prior to' turning the corner located just before the RWCU sangple sink, verify that dose rates do not exceed 10 R/hr (Return immediately to llealth Physics Supervision if they do; otherwise continue.)              .L Survey the area conicentrating, especially, on the sample sink and Non-Regen licat Exchanger roo-- (U/2 is ' A' Non-Regen lleat Exchanger, U/ 3 is 'B' Non-Regen llent Exchange-r) , verify that dose rates do not exceed 5 R/hr. Survcy the grab sartple po_nt (Beta & Gamma) with the sampic flowina. Ensure that a Icw-volume air s .2=ple is taker. at the :. ooc'., in the " Breathing Zone."

Special note of wi-.dow open readings must be made because of the high beta fields expected in the sample sink, as well as, subnersion air dose beta ficids. Survey maps and photographs are provided as part of the Appendix of this procedure. *

6. The following are times. required to obtain the sa:nples:

LOCATION TIME TO SAMPLE Feedwater Sample Sink 3 mins. or less depending on flow RhCU Sample Sink 3 min. or less depending on flow Suggested Sampling Metinod (This method may be changed after the ALARA review) Obtain the smallest sanple necessary for analysis to be perfomed. Obtain a 1 or sample (about 1" up from bottom) or less in a 3 oz bottle. Use tongs or other remote handling t.ools which hold the sample bottle without operator attention. When required amount of sample is obtained remove bottle from hood, ( quickly place lid on be,ttle and transport with tongs or other remote tools or lead carrying container.

           *I  "

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Pag; 4 cf 4, Rev.0 PROCEDURE : (c:ntinu;d) 7 Consideration of expected dose rates from the sample, itself, must also te

(, made. In this regard, the time to take the sample to the hot lab versus shielding the sample must be considered. The personnel who will obtain the sample shall be briefed on all alternatives and will provide input into practical methods of remotely handling the sample. Before the sample is taken at least 3 dry runs using Demin water shall be made using the remote tooling or intended method. 8 A RWP shall be assigned for the sampling evolution. The Rh? shall be followed by all personnel handling the sample. 9 . Prior to the sample entering the hot lab, any shielding, remote tooling or other protective measure shall be in place and ready to accept the sample.

10. Upon introduction of the sample into the hot lab, the sample will be handled in a manner such that it will cause an ALARA whole body dtse to personne) involved. Unnecessary personnel shall not remain in the hot lab.

11. Proper?v in place'and shielded, the sample will be processed remotely (wherc .ad when possible) . Careful handling of the sample is candatory in preparation for anal ~ysis so contanination is not spread, airborne preblens are held at a minimum, and a new sample isn't required.

12 . Following final analysis of the sample, results shall be reported to appropriate supervision. s h a e I t

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EP 205A.5 O O ArresorcEs (. EP 205A.5 APPENDICES A. Photographs of Sample Points - Original Photographs are kept on file with Health Physics Supervision. B. Plant layout maps. C. Survey maps. e S %

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                                    --                     '                       EP 205A.8

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                                                                                  P;g3 1 of 8, Rev. 0
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{ -7{ 2 25im 1 k~. ---PHILADEL. .. " PHIA ELECTRIC COMPANY PEACH BCfrION UNITS 2 AND 3 EP 205A.8 OBTAINING LIQUID RADWASTE SAMPLES FROM RADWASTE SAMPLE SINK FOLLOWING ACCIDENT CONDITIONS PURPOSE: The purpose of this procedure is to provide some guidelines prior to, during and after obtaining samples from the radwaste sample sink. APPARATUS: Appropriate Health Physics Survey Equipment Air Sampler (low volume) Anti-C clothing Digital-Alarming dosimetry 3 oz sample bottle with lid

   !    Tongs, remote tooling or lead carrying container for holding the sample bottle during sampling respiratory protective equipment PRECAUTION:

A. In all steps of this procedure, an ALARA concept is mandatory. This procedure for samples provides during an some philosophy in preplanning sampling evolutions accident. In addition to reviewing this procedure, an ALARA review obtaining the sample. of the sampling process should be performed prior to If the sample is not really needed, and lower dose methods the sample to determine should the gross data that the sample provides exist, not be obtained. B. At no time may NRC exposure limits (either aarborne or body dose) be exceeded during the surveying for sampling or obtaining the sample. If it appears that an overexposure could reasonably occur when obtaining the sample, do not proceed without written NRC approval. PROCEDURE: 1. It has been required. determined that a sample from the radwaste sample sink is

2. Two routes are suggested a.

enter at the normal turbine building 116' plant entrance, time = approximately two minutes e

EP 205A.8 P;g) 2 cf 8, Rev. O b. k entering at the roll up doors at either the north (Ur.it 3) or i south (Unit 2) wall of turbine building 116' . time = approximately four minutes 3. Have a health physics technician accompany the chemistry tech i i n c an assigned to obtain samples in order to conduct area surveys .

                                  & Chemistry the            sample point.        personnel on the route to be taken and the tiBrief                                            Health Physics me to get to points.

Survey maps are also provided. Attached as Appendices are the loca 4. Health Physics protective equipment personnel shall take appropriate survey equip ment and (e.g. SCBA gears and Anti-C 's, etc. ) . Pefore making and entry to the Power Block, ensure survey equipmente isonturn d calibrated. with the survey and to valve in grab sample pointChemistry perso . 5. Upon entering the Power Block, the surveyor (s) will note ends tr in general radiation levels enroute to the sample point. 10 R/hr gamma or 10 rad /hr beta prior to arriving at the point If dose rates exceed specified below and upon further investigation this dose rate remains a e or st bl increases exit immediately and report to Health Physics Sup ervision. The following dose rates shall be determined prior to entry: A. If the dose rate exceeds 5 R/hr at any portion of the either door (

                                        , Physics Supervision with this information. leading                                                                           ealth     to RW With     dose rates less than 5 R/hr, enter the Radwaste Buildi that door.                                                                                                             ng through Take careful note of the dose rates.

B. the grab sample pointSurvey the area concentrating, especially, e Sink. Survey on the S the low-volume air sample is taken at the hood (Beta & Gamma), with beta fields expected in the sample sink, dose beta fields. useas well of the

                                                                                                                                                        , submersion air highasSpec the Appendix of this procedure. Survey maps and photographs are provided as pa

! 6. The following are times required to obtain the samples : LOCATION TIME TO SAMPLE . Radwaste Sample Sink 3 mins or less depending on flow Suggested Sampling Method (This method may be cha

7. nged after the ALARA review)

Obtain the smallest sample necessary for analysis t 1 oz sample (about 1" up from bottom) o be performed. Obtain a other remote handling tools which hold the sample bottle attention. Use tongs withor lessor in a 3 o out operator When required amount of sample is obtained remov quickly p1 Lee lid on bottle and transport with tongs or othere bottle from h ( remote tools.

           - - . _ .      .       - - . _ _ -         , . . - . _ . _ ~ .- - - _ . - . . ,         _ _ . _ _ _ _ _ _ , . - _ . . _ . -

                         ~                                      -                  -~                   '~~~~

EP 225A.8 P;g? 3 cf 8, Rev. 0 8. (~ Consideration made, of expected dose rates from the s shielding the sample must be considered.in o the hotthis lab regard, versus the prectical methods of remotely handling the provide input intosamp taken at least 3 dry runs using Demin wat . Before the sample is tooling or intended method. er shall be made using the remote 9. by all personnel handling the sample.A u on. RWP shall be a The RNP shall be followec 10. Prior to the sample entering the hot lab other protective measure shall be in place and read, any shielding, rem

11. y to accept the sample, Upon introduction of the sample into the hot l b personnel in handled a manner such that it will cause an ALa , the sample will be involved.

32. Unnecessary personnel shall not remain in thARA whole e hot lab.

Properly in place (where and when possible) . and shielded, the sample will b e processed remotely preparation for analysis so contamination is not spCareful hand 13. are held at a minimum, and a new sample isn't red. requiread, airborne pro Following final analysis of the sample appropriate supervision. , results shall be reported to ( EP 205A.8 APPENDICES A. plant layout maps B. survey maps C. photographs ( l

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EP 205A,9

                                                           - +                               Pig 3 1 Of 12, Rev.
          ,

MPUstth r

AW!- E *** b 198? I

          &       i                              b               ;

PHIIADELPHIA ELECTRIC COMPANY t PEACH BCfI"ICM UNITS 2 AND 3 EP 205A.9 OBTAINING SAMPLES FROM CONDENSATE SAMPLE SINK FOLIDWI ACCIDENT CONDITIONS PURPOSE: The purpose of this procedure is to provide some guidelines prior to, during and after obtaining samples from the condensate sample sink following accident conditions with major fuel damage. APPARATUS: Appropriate Health Physics Survey Equipment

Air Sampler (low volume)

Anti-C Clothing Digital-Alarming Dosimetry i 3 Oz. Sample Bottle with Lid

   .                      Tongs or Romote Tooling or Imad Carrying Container for Holding the Sample Bottle During Sampling Respiratory Protect.ivo Equipmont t

PRECAUTION: A. In all eteps of this procodure, an ALARA concept is mandatory. This procedure provides some philosophy in preplanning sampling l evolutions for samples during an accident. In addition to reviewing this procedure, an ALARA review of the sampling process should be performed prior to obtaining the sample. If the sample is not really needed, and lower dose methods to determine the gross data that the sample provides exist, the sample should not be obtained. l B. l At no time may NRC exposure limits (either airborno or body doso) bo exceeded during the su~rveying for sampling or obtaining the samplo. l If it appears that an overexposure could reasonably occur when obtaining the sample, do not proceed without written NRC Opproval. PROCEDURE: 1. It has been determined that a sample from the condensato samplo sink is required.

2. Two routcs are suggested:

A. Entering at the normal turbine building 116' plant entrance. Time = approximately two minutes ( B. Entering at the roll up doors at oither the north (Unit 3) or South (Unit 2) wall of turbine building 116'. I l Time = approximatley three minutes

                                               -       w    -

MP 205A.9

                                     ,                                                              Paga 2 of 12, Rev.

3. Have a Health Physics Technician accompany the Chemistry Technician assigned to obtain samples in order to parform area surveys. brief Health Physics & Chemistry personnel on the route to be taken and the time to get to the samp3e point. are the locations of the sample points. Survey Attached as Appendices maps are also provided. 4. Health Physics protective personnel shall take appropriate survey equipment and equipment (e.g. SCBA gear, Anti C's etc. ) . Before making entry to the power block, ensure survey equipment is turned on and calibrated. Chemistry personnel shall make initial entry to assist with the survey and to valve in grab sample point. 5.

       ;                           Upon entering the Power Block, the surveyor (s) will note trends in
       '                           general radiation levels enroute to the sample point. If dose ratos exceed 10 R/hr gamma er 10 rad /hr beta prior to arriving at the
        .                          point specified below.and upon further investigation this dose rate remainsSupervision.

Physics stable or increases exit immediately and report to Health the Sample Sink. Survey the area concentrating, especially, on Survey the grab sample point fBeta & Gamma),

    ,                             with sample flowing, ensure that the low-volume air sample is taken at the hood, in the " Breathing Zone".
   ,                                                                              Special note of window open readings must be made because of the high beta fields expected

in the sample sink, as well as, submersion air dose beta fields .

 ,                                Survey of   this maps    and photographs procedure.               are provided as part of the Appendix l                         6.
                \

The following are times required to obtain the samplos: Condensate Samplo Si'.k - 3 mins. or loss doponding on flow Suggested Sampling Metiod (This method may be changed after the ALARA review) Obtain athe Obtain smallost 1 oz. sample samplo necessary for analysis to be performod. bottle. (about 1" up from bottom) or less in a 3 oz. Use tongs or other remote handling tools which hold the sample bottle without operator attention. When requirod amount of sample is obtained romove bottle from hood, quickly place lid on bottle and transport with tongs, other romoto tools or lead carrying container. 7. Consideration also be made. of expected dose ratos from tho samplo, itself, must In this regard, the time to take the sample to the hot lab versus shielding the sample must be considered. The personnel who will obtain the sample shall be briefed on all alternatives and will sample. provide input into practical mothods of remotoly handling the Before the sample is taken at least 3 dry runs using demin I water shall be made using the remote tooling or intended method. 8. I A RWP shall be assigned for the sample evolution. followed by all personnel handling the sample. The RWP shall be 9. l ( Prior or otherto protoctive tho sample ontoring the hot lab, any shiolding, romoto tooling measure the sample. shall bo in placo and roady to accept i I O e

EP 205A.9

                                       .                                                                                               Pag 3 3 of 12, Rov.

10. Upon introduction of the sample into the hot lab, the sample will

      .                                be handled dose   to personnelininvolved.

in hot lab. a manner such that it will causeoyan Unnecessary personnel shall not remain AIAR 11. Properly in place and shielded, the samplo will be process remotely (whsre and when possible) . e d is mandatory in preparation for analysis so contamination s not iCareful h spread, isn't required. airborne problems are held at a minimum, and a new sasipl 12. Following final appropriato analysis of the sample, results shall be supervision. reported to EP 205A.9 APPENDICES A. Plant Layout Maps B. Survey Maps . C. Photographs t I ( e v , - -- , - , , -- ,_.---,-,,-,,-a . - - , - . . - - - - . - .- , _ . , , , -. . , . - - , , - -

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1. It has been determined that 3 hydrogen analyzer is required.an off-gas sample from the off-gas !

2. Three paths to the analyzers are suggested:

A. Entering the normal turbine building 116' plant entrance up the Unit 3 reactor building stairs to 165' elevation through the recombiner building door then down the stairs to 157' elevation. Time = approximately 10 minutes B. Entering the recombiner building 135' at the door next to the railroad airlock, north side of Unit 3 (key needed for locked door) up the stairs to 157' elevation. Time = approx'cately 3 minutes C. Going up the outside stairs of the recombiner building west wall to 157' elevation recombiner building door (key needed). Time = approximately 2 minutes 3. Once a path is selc$ted, obtain the appropriate keys for locked doors from shift supervision. The key needed for the hydrogen analyzer rooms is key number 8457 4. llave a llealth Physics Technician accompany the el emistry technician assigned to obtain samples in order to perform area surveys. Brief lical*.h Physics G Chemistry personnel on the route to be taken and the time to get to the sample point. Attached as Appendices are the locations of the sample points. Survey maps are also provided. 5. Ilealth Physics personnel shall take appropriate survey equipment and protective equipment (e.g. SCBA gear, anti-C's, etc.). Before making entry to the Power Block, ensure survey equipment is turned on and calibrated. Chemistry personnel shall make initial entry to assist with the survey and to valve in grab sample point. 6. Upon entering the Power Block, the surveyor (s) will note trends in general radiation levels enroute to the sample point. If dose rates exceed 10 R/hr gamma or 10 rad /hr beta prior to arriving at the point specified below and upon further investigation this dose rate remains stable or increases, exit immediately and report to liealth Physics Supervision. , If the dose rate at any door that has to be opened is greater than 5 R/hr, leave the area immediately and report to llealth Physics Supervision with this information. With the dose rates less than 5 R/hr, enter the area but take careful notice of the dose rates. Once the hydrogen analyzer room is entered, survey the hydrogen analyzer inlet line as well as the general area. Ensure that the low-volume air sample is taken in the " Breathing Zone". Survey ( maps procedure. and photographs are provided as part of the appendix of this --____._...._......____....______......__.............._____....,._..._.___........._m. Q !

r LubA.10 PZg] 3 cf 10, Rev. 0 PROCEDURE: (C:nt'd) 7.

The following are the times required to obtain the samples: ( Location Time to Sample H2 Analyzer Recombiner Bldg. 157' 5 minutes

Suggested Sampling Method (this procedure may be changed based on the ALARA Review)

Use Appendix A (HP0/CO-130) for sampling procedure. Obtain smallest sample necessary for analyses to be performed. 8. Consideration of expected dose rates from ,the sample itself must also be made. the 11 Review survey data for t~he sample inlet line and , 2 analyzer inlet line as compared to general field for approximation of sample dose. In this regard the time to take the sample to the hot considered. Igb versus shielding the sample must be The personnel who will obtain the sample shall be briefed on all alternatives and will provide input into practical methods of remotely handling the sample. 9. A RWP will be assigned for the sample collection and analysis. The RKP shall be followed by all personnel handling the sampic. ( 10. Prior to the sample entering the hot lab, any shielding, remote toolingthe accept or other protective measure shall be in place and ready to sample. 11. Upon introduction of the semple into the hot lab, the sample will be handled in a manner such that it will cause an ALARA whole body dose to personnel involved. in the hot lab. Unnecessary personnel shall not remain 12. Properly in place and shielded, the sample will be processed remotely (where and when possibic). is mandatory in preparation for analysis so contamination is notCareful hand is not required. spread, airborne problems are held at a minimum, and a new sam 13. If the containment sample is too hot to count directly, a 0.1 m1 sample can be taken from the off-gas sample vial after the vial is adjusted to A31, pressure with syringe needed and transferred to another evacuated 14.4 ml off-gas vial. Repeat if needed. 14. , Following to finalsupervision. appropriate analysis of the sample, results shall be reported ( ---~..~.4-_..._...~.._._..__.-....-.,._,._,.........- , . . . . _ . , Er 4 USA.1U PCgD 4 ef 10, R2v. 0 HP0/C0 APPENDICES s A. HF0/CO-130 Obtaining Off-Gas Samples from the Off-Gas Hydrogen Analyzers B. Plant Layout Maps , C. Survey Maps D. Photographs e e l e 1 (. l .7._...........__.._._.. EP205A.1d . ( APPENDIX A . P g'2 S cf 10, Rt s (- HPO/CO-130 Page 1 of 1, Ec APPENDIX A HIJi/RJS:a1a !gggg l MIILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 & 3 HPONO .130 . OBTAINING OFF-GAS H7 ANALYZlltS __ . SAMPLES FROM TiiE OFF-GAS ~ PURPOSE: 4 - The purpose off-gas from 112 of this procedure Analyzer. is to provide some guidelines for obtaining APPARATUS: \ Air sampler (low volume) Appropriate Health Physics survey equipment Respiratory protective equipc..ent Anti-C clothing (as requi. red) . 14.4 mlvalve Septum off gas vial with septums Sample tee with valve _PRCCEDURE: 1. Prior to obtaing the gas sample, a Radiation C (R-C-A) survey shall be performed ontamination-Airborne and a ned. an RNP obt i 2. Suggested Sampling Method A. Install sampling tee (if not present) by e following: th (1) Place the 112 in purge. (2) and verify the sample valve isonclosed. piping Install the samp (3) Return the 112 [ to stabilize before sampling. Analyzer to normal operation allow read gs . . . - - - - i N w ?M 15 .R0 - v KT anir A B. Prerequistos Pcg2 6 cf 10, F (1) V;rify th) sample valve is closed.

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( (2) The septum valve installed with a 1/4" to 1/8" reducer ( (if required) into the sample valve. (3) . Close septum valve (push red buttoa all the way in). C. Obtain a sample by the following methods * (4) Open the sample valve. (5) Open the septum valve (push green button all the way in) (6) Install the syringe needle through the septum valve and sample valve into the sample tee. valve (push green button all the way in). .Open syringe (7) Flush the microsyringe by taking a m1 sample and returned the sample to the sample tee by pressin'g the plun0er twice. ' (8) Obtain a 5.O' m1 sar.ple from the sample in the microsyringe and close syringe valve (push red button all the way in) (9) Close all thethe waycarple in). valve and the septum valve (push red button \ (10) Place the 5.0 m1 sample into a evaculated 14.4 ml ott-gas vial af ter incerting nt:cJle into vial and opening syringe valve (push green button all the way in). (11) Exit the area with the off-gas vial. * (12) Remove coptum valve and replace pipe plug. When sample progran is complete. No more than 2 weeks. 9 e 9 '-~~~---..---.-_,..,,e._.,..---~~~---~ .e ~---~.-.-... e - Q RJ - APPENUIx y Pcgg 7 er 30, cc.s ow>l s k N @ . .e 6 7 7

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a - {. i, s F " ' " P ' ' m Tr q y , ,,.. ,: ,g ; ., 'l i !* i. p ,4- . j W i' j-m.-- .t j , ; t_ J i ' g . r ; ,l 9 1 mm.c, % .yu+,1.n1 ( JMT3 opp sp S . NMO G6As h/1t Y2Grd ppp;,,,p,, p ~ - - - - ~ r . EP 205A311 P.igo 1 of 3, llev. 0 , MPGtwaf gg,s MT 2 51582 k f i PHILADELPHIA ~EMCTRIC COMPANY PEACH BOTTOM UNITS 2 & 3 EP 205A.ll SAMPLE PREPARATION AND CHEMICAL ANALYSIS OF HIGHLY RADIOACTIVE LI, QUID SAMPLES PURPOSE: , The purpose of this procedure is to provide some guidelines for consideration during sample preparation and chemical analysis of highly radioactive samplea following accident conditions with major fuel damage. . APPARATUS: Appropriate Health Physics Survey Equi,aent Air Sampler (lov volume) Respirator Protection Equipment if required Anti-C Clothing Digitul-Alarming 1A,uimeLry Appropriate Lead Shielding ( Appropriate Microsyringes Equipment for cl-Analyulu by Electrode Equipment for Boron Analysis by Monital 1k.h ml Off Cac Vials with Septums Pit MCAUT f 0N" . A. In all steps of this procedure, an ALARA concept iu mandnLory. Thic procedure provides some philosophy in pre-pleuming for usunnic preparation and analynin of hinhly radiortetive 1.quiel usunplen. In sublition to re-. viewing this procedure, an ALARA review of the neuriple preparation and analysis methods should be performed nrioF/hecinninn proprarution and analysis. If an analysis is not really needed or a lover dose method is possible to obtain the same data, do not perform the unnlycia. B. At na time, may NRC exposure limits (either nirborne or body dose) be exceeded during the sample preparation and chemical analycis. If it appears that an overexposure could reanonnlity occur durisu'. unmp]c preparation or analysis, D0_ NOT proceed without written NRC approval. P_R,0C_ED_UR_E_:

1. Obtain the survey data obtained when the sample vns taken and transported to the Chemical Lab. Brief Health Physico personnel on the sample prepn--

ration and chemical analysis to be performm1. llenith Playnieu nuptarvluion chall dcLorminc esi r unmpling requiremenLu. i . a m *e m EP 205A.ll e l'un e 2 o f 3, Hev. O N. 2. Health Physics personnel shall monitor dose rates during the sample '( _ preparation and analysis. Based ou their analysis, stay times shall be determined. Durine. sample preparation and analysis, extremity doses should be limiting. However, whole body exposure shall also be concidered. Extremity docimetric devices uhall be worn. ! An HWP shall be assigned to this activity. !

3. Sample preparation shall be done in a ventilation bood or other ventilated area where respiratory protection equipment is not required if possible. l When possible sample analysis shall also be done in a ventilation hood or where other engineering controls (like portable HIEPA/ charcoal vent, units) may be used.

h. Consider the use of tongs 'or other remote tooling during sa=ple preparation and analysis. 5 Lead shielding shall be used when handling undiluted reactor coolant At a minimum, lead bricks stacked around the sample shall be used. A small gap between the top lead bricks may be made for the insertion of a microsyringe needle into the sample bottle. The amount of cample removed and the dilution volume shall depend on the sample dose rate. After removing a sample close the gap the lead brick top to reduce dose rates. Monitor the dose to the hands during micropipeting. 6. Concider the une of more e.luborute uhieJding during menple preputalion if dose ratec merit its use. 7 Chloride and boron analycic on undiluted uwnples uhuuld be dunc by remote methods. The chloride analysis may be performed by the electrofe method. With this method, the electrode can be placed in the sample through a hole in a lead brick and injection of standard solution be made through a second hole in the brick. 'Itc boron analycic may be performed the came way. llealth Phyuiec curveyu shall be made on all electrodes, pipets or microsyringes after their use and appropriate disposal or storage methodc uced. 8. Consider the use of more elaborate shielding or remote analysis tooling if ertremity dose rates merit its use.

9 Liquid samples for gamma isotopic analycis chn11 Le pinced in n 1h.h

' ml off-gac vial. Thic vial chall be cupped wiLh a rubber uoptum and wrapped saran vrap to prevent contamination of counting equipment. The dose rate from these samples shall be 4 200 nacm/hr on contract or additional dilution is required.

10. The Ik.h liquid off-gas samples for gamma isotopic analysis (Geli) may

) be counted on the 3 cm or 30 cm nholf. Tho 10 cm chell' geometry can ' analyze samples with dose rates 4: 200 mrem /hr on contact. Check the dead time while placing the sample in the counting cave. Samples with 1 ;> 30% dead time may be counted but do not exceed 50% dead time.

11. Before actual sample preparation or chemical anal- i:. pe r n. mned i at least three dry runs using demin, vater shall oe made. An ALAMA review shall also be done. Based on these dry rur.s and the ALARA review, changes to sample preparation and analysis procedures shielding

( EP 205A.11 s ' Pag 2 3 of 3, TCv. O i or equipment shall be made to minimize exposure. 'k Health Physics supervision shall also review the possibility of not performing the sample preparation and analysis at all. 12. Consideration chall be given to the final dinpoultion of the sampica, the remainder of the coolant sample and the vaste produced. 13. Samples and the remainder of the coolant sample which are kept for additional analysis shall be stored in an appropriate location based on their dose rate and radiological hazard. e l I ( . r- . 'G - Page 1 cf 4 Rev. ( * ~ MPC:tth e . g~...._ C. ....- f l _ 1 l 4 W 25 W t .( Uk .- ) . e . l _- ~__._..- ~ " PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 & 3 EP 205A.12 - SAMPLE PREPARATION AND ANALYSIS OF HIGHLY RADIOACTI PARTICULATE FILTERS AND IODINE CARTRIDGES PURPOSE: The purpose of this procedure it during sample preparation (sample reduction)to provide some guidelines for consideration and isotopic analysis of highly radioactive particulate filters and iodine cartridges following accident conditions with major fuel damage. APPARATUS: ( Appropriate Health Physics survey equipment Air Sample r (Iow volume) Respirator protection equipment if required Anti-C clothing Digital - alarming Dosimetry Appropriate lead shielding Whatnan 452 filter paper Cork borers or metal punch 14.4 ml off gas vials with septums Plastic tape ,' Filter towerpurging Cartridge for Whatman system452 filters (25 mm) , Supply PRECAUTIONS: of nitrogen (bottled) or breathing air (bottled) A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in pre-planning for sample preparation and analysis of highly radioactive samples. In addition to reviewing this procedure, an ALARA review of the sample preparation methods should be performed prior beginning preparation (sample reduction). If an analysis is not really needed or o lower dose method is possible to obtain the same data, do not perform the analysis. B. At no time may NRC exposure limits (either airborne or body dose) be exceeded during the sample preparation and analysis. If it appears that l an overexposure could reasonable occur during sample preparation or ' ( analysis, DO_ NOT proceed without written NRC approval. I l . t ""T6 ywgr -w ,, - r WW - g g Pogo 2 of 4, ugy, @ g . / 1 PROCEDURE:

1. Obtain the survey data obtained when the sample was taken and transported to the Chemical Lab. Brief Health Physice personnel ori the sample preparation (if required) and analysis to be performed.

. Health Physics Supervision shall determine air sampling requirement. *

2. Health Physics personnel shall monitor dose rates durir$g 'the sample preparation and analysis. Based on their analysis stay times shall be determined. During sample preparation and analysis, extremity doses should be limiting. However, whole body exposure shall also be considered. Extremity dosimetric devices shall be worn. An RWP shall be assigned to this activity.

3. Sample preparation shall be done in a ventilation bood or other ventilated area where respiratory protection equipment is not re-quired if possible.

4. Consider the use of tongs or other remote tooling during sample preparation.

5. Determine the contact dose rate from the particulate filter and the charcoal cartridge.

If the contact dose rate is c:: 200 mrem /hr the sample may be analyzed directly by the Geli analysis on the 3 cm or 30 cm shelf. Check the dead time while placing the sample in the counting cave. Samples with > 30% dead time may be counted but do ( not exceed 50% dead time. 6. Samples by with contact dose rates p200 mrem /hr shall be analyzed only counting a small portion of the original samples or by purging the nobles gas from the cartridge (for iodine sampling cartridges only)by step 13. After purging, if the dose rate is still > 200 mrem /hr, reduce the sample size. Lead shiciding shall be considered for use while removing smaller samples. At a minicur lead bricks stacked around the sample shall be used. Monitor the dose rate to the hands during sample preparation. 7. Particulate filters with contact dose rates of > 200 mrem /hr may be analyzed by punching out a small area from the center of the filter. This may be done with a metal punch or a cork borer (rubber stopper cutter). The punched area shall be dissolved with nitric acid and Placed in a 14.4 ml off gas bottle for gamma isotopic analysis. Before analysis the off gas vial shall be capped with a rubber septum and wrapped with saran wrap to prevent spread of contamination. The original activity on the filter can be determined by'multipling the total activity measured in the off-gas vial by the ratic of the total area of the filter to the punched area. Check the dead time while placing the sample in the counting cave. Samples with > 30% dead time may be counted but do not exceed .50% dead time. Samples

8. 1 50% dead time require further reduction in area.

Iodine cartridges with contact dose rates of>200 meem/hr after - purging the noble gas may be analyzed by core boring or removing ( a small section (or volume) from the center of the cartridge. Try to remove a uniform core of charcoal or silver zeolite from the cartridge. Weigh the amount of filter material removed. Mount this filtermaterial in a dose equivalent sample geometry (Whatman 452 on a card). with a filter tower. Trt.nsfer DC !M usethis water material or any to a Wnatman 452 filter "~~'~~~v---v- g - mem.y. ,.7. . . .we. ,, 2. . wg _ . . . .,,y . .s._, ., . . , . . . m _ ,. . W ' W / ,Page U C f 4, Rev. C cth;r solvent to tr:n;fc;r tha mat: riel. Weigh tha amount of mat;rini on the Whatman 452 filter. Place the Whatman filt,*r and material on a card and cover with plastic tape. Count this Geometry on the 3 cm { shelf. Check the dead time while placing the samples in the counting cave. Samples with > 30% dead time may be counted but do not exceed 50s dead time. Samples > 50% dead time require further reduction of volume. The original activity of the cartridge can be determined ~ by multipling the total activity measured on the Whatman 452 filter by the ratio of the weight of a cartridge to the weight of material on the Whatman filter.

9. Consider the use of more elaborate shielding during sample preparatio,n if dose rates merit its use.

10. Before actual sample volume reduction is performed at least 3 dry runs using clean filters and cartridges shall be made. An ALARA Review shall also be done. Based on these dry runs and the ALARA Review changes to sample volume reduction procedures shielding or equipment shall be made to minimize exposure. Health Physics super-vision shall also review the possibility of not perforning the sample volume reduction and analysis at all. .

11. Consider shorter sampling times so tliat the filfer and cartridges may be analyzed directly. During accident condition this may require that grab samples be taken periodically instead of continuous sampling.

12. Consider the use of silver zeolite cartridges in the place of charcoal cartridges to reduce the noble gas interference during isotopic analysis.

I The use of silver zeolite will allow samples which contain more I-131 (as compared to charcoal) to be counted with less dead time.

13. Samples with high noble gas backgrounds can be flushed to reduce the noble gas interference by the following method:

a. Setup the purge system as shown in Figure HP0/CO-127-1 in a low background area where the release of nobic gas would not present a personnel exposure or equipment (counting room) problem.

b. Load the filter holder as shown in Figure HP0/CO-127-1. Place the " hot" side of the cartridge toward the quick-disconnect.

Hold the cartridge in place with a filter backing ring but do not use a particule filter. Place the filter holder on the quick disconnect.

c. Flow nitrogen or breathing air through the cartridge at the same flow rate as used for sampli ng for two hours or less.

After purging stop purge flow ar remove cartridge. Repeat step 5 through 12.

14. Consideration shall be given to the final disposition of the samples, the remainder of the original sample and the waste produced.

15. Samples and the remainder of the original sample which are kept for additional analysis shall be stored in an appropriate location based

( on their dose rate and radiological hazard. #%9 *%7%% W W9.$*TSQ$Wp S # 8% * %9 % .. %* $ De f .y bI Y O N'* p {**. 99 fT, . W W Pogo.4 ef 4, Rov. O ~ ~, 4 st n t u .( R. .%w R . . _ - - -- - _:4 N yQ ,f i m'h7;, J ' a% $s 'i,' m< ' ' ',1 4-i. 0/$$Yk.'k'tlllb' Y. a. n 4.i d' %. .+ - 7 ,s s l '4 . ']" 1 6 'k l ^ b .i N 4 s . I 3 h, c m. I 't K H'. O ' ( 'J T. . , ,i ( e ij 4: i !j - ,I /{ ';' s o q e i g 1 \, J - N s !l( ' e .'. , _U . d ( v< s' e v J[ l l ( l - - - - - . - - - - - - - - - - ~~.- FrTy ___ - _ d - __Page 1 Ef 3, Rev. 0 MPG:wJ,f M4 2 5 lin 5k PilILADELPi!I A ELECTRIC COMPANY Peach Bottom Units 2 and 3 EP-205A.13 - SAMPLE PREPARATION AND ANALYSIS OF llIGilLY RADIOACTIVE GAS SAMPLES PURPOSE: The purpose of this procedure is to provide some guide lines for consideration during sample preparation and isotopic analysis of highly radi,oactive gas samples following accident conditions with major fuel damage.

APPARATUS:

Appropriate liealth Physics survey equipment Air Sampler (Iow volume) Respirator protection equipment if required Anti-C clothing Digital-Alarming Dosimetry Appropriate lead shielding Appropriate microsyringes ( 14.4 ml off gas vials with septums PRECAUTIONS: A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in pre-planning for sample preparation (dilution) and analysis of highly radioactive gas samples. In addition to reviewing this procedure, an ALARA review of the sample preparation (dilution) method should be performed prior beginning preparation and analysi s . If an analysis is not really needed or a lower dose method is , possible to obtain the same data, do not perform the analysis. B. At no time may NRC exposure limits (either airborne or body dose) be exceeded during the sample preparation and analysis. If it appears that an overexposure could reasonable occur during sample preparation or analysis IKl NOT proceed without written NRC approval. PROCEDURE : 1. Obtain the survey data obtained when the sample was taken and transported to the chemical lab. Brief llealth Physics personnel on the sample preparation (dilution) if required and analysis to be performed. flealth Physics supervision shall determine air sampling requirements. . . _ . . . . .s ~- - *' h# Q Ege 2 :f 3 , Rev". O PROCEDURE: (c[ntinu;d)

2.

H=1th Physics p;rs:.nnal shall monitor dose rates during the sample preparation and analysis. Based on their analysis stay times shall be .f determined. During sample preparation and analysis, extremity doses 1 should be limiting. However whole body exposure shall also be considered. Extremity dosimetriedevices shall be worn. An RKP shall be assigned to this activity. 3. ~ Off-gas vials with contact dose rates of 4 2 mRen/hr may be analyzed by Geli isotopic analysis directly on the 3cm shelf. Samples that are > 2 mrem /hr. . shall be diluted to reduce the dose rate in the vial to 4 2 mrem /hr. 4. Check dead time while placing the sample in the counting cave. Samples with > 30% dead time may be counted but do not exceed 50'. dead time. Samples > 50% shall be diluted to reduce the dead time.

5. Suggested sample dilution procedure:

a. Adjust the pressure in the off-gas vial to atmospheric pressure by inserting a microsyringe needle and allow the pressure to equalize.

b. Evaculate a new 14.4 ml off-gas vial with septum.

c. Determine amount of dilution required. Based on this dilution,

d. determine the amount (volume) of gas to remove from the hot off-gas vial.

Inject a volume of air with a microsyringe into the hot off-gas vial which is equal to volume of gas to be removed for dilution, e. Mix the gas in the hot off-gas vial by pumping the microsyringe in and out.

f. Set the microsyringe to the volume of gas to be removed from the hot off-gas vial and remove the microsyringe.

( g. Inject the gas in the microsyringe to a new evaculated 14.4 ml off-gas vial. h. Measure is necessary.the dose rate of the vial to determine if additional dilution i. Additional dilutions may be done by repeating Step 5. 6. Eample dilution shall be done in a ventilation hood or other ventilated area where respiratory protection equipment is not required, if possibic. 7. Consideristhe dilution use of tongs or other remote tooling if additional sample required. 8. 7 Lead shielding shall be used, when handling samples > 200 mrem /hr. At a minimum, lead bricks stacked around the sample shall be used. A small gap betweeninto needle thethe topsample lead bricks may be made for the insertion of a microsyringe bottle. Before removing a volume gas for dilution i insert a to atmospheric.microsyringe needle into the bottle to adjust the bottle pressure The amount depend on the sample dose rate. of sample removed and the dilution volume shall , Before removing a volume of gas from the via1, inject a equal amount of air to compensate for the volume removed. Mix i l well top tobeforereduceremoving sample, After removing a sample close the can the Icad brici dose rates. Monitor the dose to the hands during micropipeting. , 9. ! Consider the use of more elaborate shielding during sample dilution if dose rates merit its use. t l l , , _ mm w--------' O_ , (v:) Page 3 cf 3, Rev. O s PROCEDURE: (c5ntinu:;d) 10. Before actual sample dilution is performed at least 3 dry runs using air shall be made. An ALARA review shall also be done. Based on these dry I( runs and the ALARA review changes to sample dilution procedure shielding .or equipment shall be made to minimize exposure. Health Physics Supervision shall also review the possibility of not performing the s. ample dilution and analysis at all. 11. Consideration shall be given to the final disposition of the samples, the remainder of the gas sample and the waste produced.-- ~ ~ ~--

12. Samples and the remainder of the gas sample which are kept for additional analysis shall be stored in an appropriate location based on their dose rate and Radiological hazard.

( s W -. *- I C. s o _ , o w, PAG,5 g ~ , I REV. 2 , j ; Mb EOF:LJM kW ' MAY 2 31381 1 %.- ' PHILADELPHIA ELECTRIC COMPANY , [ __ ~~ ~ ~ PbCH BOTTOM UNITS 2 A40 3 Le EMERGENCY DiAN IMPLEMENTING PROCEDURE V . EE:EDhB___EMENCELCX_EEddl3_GEDUE V EUhEQ5i (J TO DEFINE T HE ACTIONS UF THE EMERGENCY REPAIR (DAMAGE CONTROL) GROUP. b' BEEEEEUCES (/ 1. PEACH uGTTOM A TOMI C PO,s E R STATION EMERGENCY PLAN V SECllOU li1LE ' 'S.2 2.2.3 FIRE AND OAMAGE TEAM V 2. EP 401 ENTRY FOR EMERGENCY REPAIR, OPERATIONS, AND SEARCH AND RESCUE. %/ 3. NUREG 0654 CRITERIA FOR, PREPARATION AND EVALUATION - OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND v PR E P A R E DN E S S IN SUPPORT OF NUCLEAR POWER PLANTS. AEdEGQ11 EP-206B-1 EMERGENLY EXPOSURE LIMITS (EMERGENCY' PLAN TABLE 6 1J ACIIDB_ LEVEL f THE E ME R G EN CY REPAIR GROUP WILL BE AC TIVATED WHENEVE R

THERE IS A SITUATION JN SITE THA) THE FIRE AND DAMAGE TEAM '

LEADER 06 EMS THE!R ScRvlLES NECSSSARY. s EBECAU11U5 ' 1. .., TEAM MEMBER'S EXP75URE SHOULO 85 LIMITED TO THE ADMINIS-TRATIVE GUIDE LEVELS IN APPENDIX EP 206B-1, EMERGENCY EXPOSURE LIMITS. THE EMERGENCY DIRECTCR SHALL APPROVE ANY TEA LIAliS. M MEMBER EXCEEDING PEACH BOTTOM QUARTERLY EXPOSURt THE INDIVIDUAL FIRE AND DAMAGE TEAM MEM6ERS SHOULO ENSURE WITH ALARA THAT THEY CONCEPTS. CONTROL ThEIR OWN EXPOSURES IN ACCORDANCE e id ED-2066 PAGE 2 v' - t R E V . '2 EGF:LJM 'l

2. REQUIRE MENT S OF HPC/CD-4, RADIATION WORK PERMITS, ARE Le NOT APPLICABLE. THE MP ACCOMP ANYING THE REP AIR GROUP WILL SERVE A5 196 20!P.

4v 3. THE FUNCTIUNS OF THE INTERIM FIRE AND DAMAGE TEAM LEADER ARE P ER F OR M L'O ilY THE SHIFT SUPERVISOR IN THE CONTROL ROOM U.NTIL THE MAINTENANCE ENGINEER (OR ALTERNATL) V RELIEVES HIM OF THESE RE SPONSI BIL ITIE S. IMMEDLA!EhCLIQui . V 1.0 INTEKIM FIRE AND CAMAGE TEAM LEADER SHALL: kr 1.1 ASSEMBLE THE E MER GE NC Y RE PA I R GROUP. ENSURE AN HP IS , INCLUDED IN THE GROUP'TO PROVIDE RADIOLOGICAL INFORMATION WHERE NEEDED BY THE TLAM. '%d 12 EXPLAIN THE SITUATION AND WHAT HAS TO BE 1DNE, TO THE GROUP IN DETAIL. 13 DETERMINL IF HE NEEUS TO DESIGNATE AN EMERGENCY REPAIR GROUP LEADER UUE TG THE SITUATION AT HAND. IF THIS IS NECESSARY. GIVE HIM INSTRUCTIONS ON WHAT ACTIONS SHOULD BE TAKEN MY THE GROUP. { - 2.0 EMERGElsCY REPAIR GROUD MEMBERS SHALL: 21 RLPORT TO 1HE AREA DESIGNATED PY THE GROUP LEADdR. v 1.2 ASSEMdLE NECESSARY EQUIPMENT (I.E, TOOLS. PARTS, ETC. FUR THE PCNJING OPERATIONS) FROM LOCATIONS ON JR OFF-v SI TE DESIGN ATED DY THE FIRE AND DAMAGE TEAM LEADER. THE OPERATIONS SUPPCRT CENTER FOR HP'S (ON 116' ELEVATION TURu!NE SUILOING, UNIT 2 SIDE) SHOULD BE CONTACTE0 FCK RADIATIUN MONITORING EQUIPMENT NEEDED TO SUPPORT THE REPAIR EFFORT. 2.3 FOLLOW THE DIRCCTIONS OF THE GR O'U P LEADER. 2.4 UT I L I Z E ALL COMMUNICAi!ONS MEANS AVAILABLE TO KEEP

s. THE FIRE AND CAMAGE TEAM LEADER (IN THE TECHNICAL SUPPORT CENTEh) UPDATED AS TO CURRENT STATUS OF EMERGENCY REPAIR EFFORTS, a

EOLLQE ue_ALILOUS 4 . 1.0 INTERIH FIRE AhD D AM AGE T E A:4 LEADER SHALL: 1.1 PE RIOD IC AL L Y UPDATE THE EMERGENCY DIRECTOR OF THE STATUS OF THE REPAIR WORK. 2.0 FIRE AND DAMAGE TEAM LEADER SHALL: %s

iP-20hu PAGE 3

'f* s - / REV. 2 EGF:LJM 21 IF POSSICLE. REPORT TG THE AREA THAT HAS DEEN DAMAGED, V GR THE TECHNICAL SUPPORT CENTER AS DIRFCTED BY THd E M EltGE NC Y D i d i: C l aa . Le 22 ' 00TAIN AN UPDATE OF THE SITUATION AND RELI, EVE THE INTERIM FIRE AND DAMAGE LEADER. ~ L/ 23 DIRECT AND CD0RDINATE EMERGENCY REPAIR OPERATIONS AS NECESSARY. ENSURE SELECTION OF THE MOST EXPERIENCED + L/ ELECTRICAL AND MECH ANIC AL M AINTENANCE PERSONNEL AVAILASLE FOR THE PAftTICULAR REPAIR EFFORT AT HAND. 2.4 (> PR OV ID E TEAM MEMBERS WITH PERIODIC PLANT STATUS CHANGES INCLUoING SIGN!FICANT RADIATION EXPOSURE AND RADIOACTIVE CONTAMINATION PRDULEMS WHICH MAY AFFECT THE FUNCTIONS OF THE TEAM. V 2.5 PERIODICALLY UPDATE THE EMERGENCY DIRECTOR OF THE STATUS OF THE REPAIR'WGRK. Y ( . O 90 6 k i %/ .. s 3 e a E P-7 0 6il ,_ PAGE 4 .. . l REV. 2 . EGF: LJM -( . AEELUDlL EE EDhh:1 - CEELGEhCY_ELEOSUEE_LIMil5 PROJECTED WHOLE 00DY THYROIO AUTHORIIED EUBC1122 .,001C DQSE SX a

1. LIFE SAVING AND REDUCTI ON EMERGENCY 0t e OF INJURY 75 RE4C 375 REM OIRECTOP

2. OPER A TION OF ,

e s E uu ! P ME N T TO MITIGATE AN LMERGENCYCC EMERGENCY 25 REMc 125 REM , D I R E C TO?. v

3. PROTECTION OF HEALTH ANO .

- SAFETY OF THE EMERGENCY PUBLIC S REM 25 REM DIRECTOR w 4. OTHER EMERGENCY 10 C FR 20 m ( ACTIVITIES Llh!TS 10 CFR 20 LIM 1TS EMEnGFNCY DIRECTOP 5. RE-ENTRY / RECOVEkY ADMINISTRATIVE ADMINISTRATIVE L/ AC T I V I T IE S GUIDELINES GUIDELINES N/A v ORE F ER E:.C E : EPA-520/1-75-001 T A BL E 2.1 cCSUCH EXPUSURc SHALL i!E 0:4 A VOLUNTARY BASIS v V .e 4 9 4 r ~ EP-306 - PAGE 1 OEV. 2 1*

WJK:WAF ,

. ., s a ( PHILADELPHIA EL ECTRIC COMPANY PEACH BOTTOM UNITS 2 ANO 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE . EP- Qft___EV AEUillDb QE_lBE_NFORM A T10N_CEEER EUREDSE TO DEFINE THE ACTIONS TO BE PERFORMED If) THE EVENT THAT THE INFORM A T I ON CEN TER MUST BE EVACUATED. BEEEEESCES ,

1. PEACH B'OTTOM ATOMIC POWER FTATION EMERGENCY PLAN SEEll0S TITLE 4

60 EMERGENCY MEASURES --

2. NUREG 0654 CRITERIA FOR PREPARAT!0N AND EVALUATION OF R ADIOLOG IC AL EME RGENCY RESPONSE PLANS AP.0 PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS.

APEEbQ1[ES EP 306-1 VISITOR'S LIST , ACLLON_LEYEL ? 1. THE I NF ORM A T ION CEN TER WILL BE EVACUATED AT THE DISCRETION OF THE EMERGENCY DIRECTOR.

2. A SIT E EV ACU ATION IS ANNOUNCED IN ACCORDANCE WITH EP 305.

EBEChu1LDU5

1. ALL EFFORTS ARE TO BE MADE TO KEEP Tyl,E VISITORS CALM.

2. NO INFORMATION RELATING TO THE EMERGENCY IS TO BE DTVULGEO l

10 THE VISITORS. l.

3. VISITORS WHO SHOW CONT AMIN ATION LEVELS OF iOO CPM OR GREATER ABOVE B ACKGROUND WILL REQUIRE OECONT AMINATION.

Oj 4. ENSURE CONTAMihATED VISITORS REPORT TO THE DESIGNATED l EV ACU AT ION ASSEMBLY AREA FOR DECONTAMINATION. l id3E01AIE_AEllRN1 , 1,0 INFORMATl0N CENTER STAFF SHALL: o r . EP-306 DAGE 2 , , REvo 2 WJK:WAF g, 1.I WHEN DIRECTED BY THE EMERGENCY DIRECTOR, INFORM THE , VISITORS THAT THE SITUATION IN THE STATION REDUIRES THEM l TO LEAVE THE CENTER VI A THE UNIT 1 ACCESS ROAD l 12 INFORM THE VISITORS YHAT IF THEY FOLLOW INS TR UC T IONS THERE SHOULD BE NO PROBLEM. 13 BEFORE EXITING THE INFORMATION CENTER, PERFDP.M THE FOLLOWING: 1.3.1 HAVE THE VISITORS PROVIDE THEIR NAMES AND ADDRESSES ON APPENDIX EP 306-1. . 13.2, FRISK T FE VISITORS FOR CONT AMINATION. USING A , . j RM-14 OR EQUIVALENT FRISKER, IF THERE IS ANY l CONT AMLINATION ABOVE SACKGROUND F.ECORD THE i LEVEL IN APPENDIX EP 306-1. VISITORS WHO SHOW , LQ811A51HillD3 LEVELS OF 100 CPM GREATER'THAN BACKGROUND WILL NEED TO BE DECONTAMINATED AT THE DESIGN A TED EV ACUATION ASSEMBLY AREA. - 1.3.3 THOSE VISITORS NOT CONTAMINATED SHOULD BE INS TRUC T ED TO LEAVE T HE AIC AND PROCEED HOME. 14 IF THE RADI ATION LEVEL IN THE PARKING LOT IS LE SS THAN OR EQUAL TO 10D0 CPM ABOVE BACKGROUND, ALLOW THE VI SI TORS THAT HAVE BEEN FRISKED AND ARE DOCUME NT ED AS

CLEAN" TO LEAVE THE CENTER AND PROCEE D HOME AND THOSE CONTAMINATED VISITORS TO LEAVE THE CENTER AND PROCEED TO DESIGNATED EVACUATION ASSEMBLY AREA.

EDLLDH:ue_AC110HS 1.D INFORMAi!ON CENTER STAFF SHALL: o 11 FURW ARD THE INFORM ATION CENTER DOSIMETRY BADGES TO THE PERSONNEL SAFETY TEAM LEADER FOR' PROCESSING. l / u. ,s -w ' "~ ~ ~ ' .c . e o o o 55o 6'o o o 5 'o o o o o i t 9 k g e -l -

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"l 7L WM ow eu o 4 >~ l . Om ma &M l w. wb O *4 in &M - .E. E. 4 4 C .E. .E 4 E E I 5 8 u o .J K W 4 Y I O # e .u. 6 3 W w & D tid I E e e a o . E d N M d e d > e e m & > % 4 s s s e at a o e * * * '"& m.s, ,.y _ *" b MO - we a e -4 w q _. __ __ _ , EP INSEY EMERGENCY PLAN PROCEDURES INDEX - PAGE 1 RONMEDI PEACH BOTTOM UNITS 2 AND 3 05/ 6 2* JUN - 21982 REVIEW REV. R E V I S I Dtd (~1*DL3 lill __ Dale __ UD, 2 __DAIE__ EP-101 CLASSIFICATION OF EMERGENCIES 05/23/82 5 05/23/82 EP-1d2 UNUSUAL EVENT RE SPONSE 05/23/82 5 05/23/82 EP-103 ALERT RLSPONSE 05/23/82 b 5' 05/23/92 A EP-104 SITE EMERGENCY RE SPON S E 05/23/82 5 05/23/S2 EP-105 GENERAL UMERGLNCY RESPONSE 05/23/62 5 05/23/92 LP-110 PE R5 07.NE L ASSE*BL Y ,ANO ACCCUNT ABIL I TY 04/14/82 0 04/14/82 EP-201 TECHNIC AL SUPPORT CENTER (TSCI ACTIVAi!ON 05/11/92 3 05/11/92 EP-202 OPERATIONAL SUPPORT CENTER (USC) AC TI V A T ION . 04/08/92 2 04/09/M2 EP-203 EMERGENCY OPERATIONS FACILiiY (EDF) ACTIVATION 05/11/82 3 05/11/92 "-205 RADIATION PROTELTION TEAM ACTIVATIOf. 04/08/82 3 04/09/S2 EP-205A CHEMISTRY S AVPL I NG AND ANALYSIS GRCUP LP-205A 05/25/82 4 05/25/82 o? OBI A INING DRYn!L L GA% SAMPLES FROM CON T A lfi"f N T ATiOSPHERE DILUTION CABINETS 05/26/62 0 05/26/a2 0 EP-205A RE TR IE VING AND CH ANG!f;G S Ai;PL E .3 FILTERS AND CARTRIDGES FROM THE ORYWELL RADIAT:0N MUNITOR DURING EMERGENCILS LP-205A 05/25/02 0 05/25/82 OBI A IN! NG DR Y'aEL L GAS SAMPLES

e4 FROM THL DRYAELL RADIATION MONITOR SAuPLING STATION 05/25/82 0 05/25/92 0 EPk205A OBT AINING RE ACTOR WATER S A MPL E S e5 FROM SAMPLE SINKS FOLLOn~ LNG ACC10ENT CONDITIONS -

LP-205A 05/25/82 0 05/25/82 e6 OBTAINif.G CANAL DISCHARGE WATER SAMPLES FOLL OWING R ADIC AC T i vE L!QUIO RELE ASE S AFTER ACCIDENT CONDITIONS 05/25/82 0 05/25/92 EP-205A on OBTAIN1 FAG LIQUID RA0 WASTE SAMPLES FROV RACWA&lf SAMPLL S I NK FOLLOa!NG [ ACCIDENT C 0t40 ! T I CNS "- 05/25/82 0 05/25/82 EP-2054 OBT A INING S A*PLE S FROM CONDENSATE . EP INDEX EMERGENCY PLAN PROCEDURES INDEX PAGE 2

REY. 10 0

' PEACH BOTTOM UNITS 2 AND 3 . 05/26/82

REVIEW REV. REVISION s NUMBEE IIILE __D&IE__ NDa __DAIE__

o9 SAMPLE SINK FOLLOWING ACCIDENT

CONDITIONS 05/25/82 O 05/25/82 e

EP-205A OBTAINING OFF-GAS SAMPLES FROM e10 THE OFF-GAS HYOROGEN ANALYZER FOLLOWING ACCIDENT CONDITIONS 05/25/82 0 05/25/82 EP-205A SAMPLE PREPARATION AND CHEMICAL .11 ANALYSIS OF HIGHLY RADI0 ACTIVE ' LIQUID SAMPLES 05/25/82 0 05/25/82 EP-205A SAMPLE PREPARATION AND ANALYSIS o12 0F HIGHLY RADIDACTIVE PARTICULATE FtLTERS AND IODINE CARTRIDGES 05/25/82 0 05/25/82 EP-205A SAMPLE PREPARATION AND ANALYSIS OF .I3 HIGHLY RADIDACTIVE GAS SAMPLES 05/25/82 0 05/25/82 EP-205B RADI ATION SURVEY GROUPS 04/08/,82 2 04/08/82 ED-205C PERSON'!EL 00SIMETRY BIDASSAY AND RESPIRATORY PROTECTION GROUP , 04/08/82 2 04/08/82 EP-206 FIRE AND DAMAGE T EAM ACTIVATION 04/19/;2 4 04/19/82 EP-206A FIRE FIGHTING GROUP '04/19/82 2 04/19/82 EP-206B EMERGENCY R E P AI R GR OU P 05/23/82 2 05/23/82 EP-20T PERSONNEL SAFETY TEAM ACTIv,A, TION, 05/11/82 4 05/11/82 EA-207A SEARCH AND RESCUE 04/14/82 2 04/14/82 EP-207B PERSONNEL ACCOUNTABILITY 05/11/82 3 05/11/82 EP-207C FIRST AID '. , 04/14/82 2 04/14/82 EP-207D PERSONNEL MONITORING AND DE CO NT A MIN A T I ON 04/08/82 2 04/08/82 EP-207E VEHICLE AND EVACUEE CONTROL PROCEDURE 04/08/82 0 04/08/82 EP-207F VEHICLE DECONTAMINATION PROCEDURE 04/14/82 0 04/14/82 EP-208 SECURITY TEAM 04/01/81 O 04/01/81 P-209 1ELEPHONE LIST FOR EMERGENCY USE 04/26/82 4 04/26/82 EP-209 IMMEDI ATE NOT IF IC ATION CALL LIST * . APPENDIY A 04/26/82 4 04/26/R2 EP INDEX , EMERGENCY PLAN PRO &EDURES INDEX PAGE 3 REV. 19 0 PEACH BOTTOM UNITS 2 AND 3 05/26/82

V(TU5 Bgg REVIEW REV. REVISION TITLE __ Dale __ NDa __DAIE__

EP-209 PHILADELPHIA EL EC TR IC ' APPENDIX B COMP ANY OFFICIALS 07/23/81- 1 07/23/81 EP-209 PEACH BOTTOM STAT!DN SUPERVISION APPENDIX C 04/08/82 4 04/08/82 EP-209 ON SITE EMERGENCY TEAM LEADERS APPENDIX D-1 04/08/82 3 04/08/82 EP 209 RADIATION SURVEY TEAM cPPENDIX D-2 04/26/32 3 04/26/82 EP-209 FIRE AND DAMAGE TEAM ~ APPENDIX D-$ . . 04/26/82 3 04/26/82 EP-209 PERSONNEL SAFETY TEAM . APPENDIX D44 04/26/82 3 04/26/92 EP-209 SECURITY TEAM

APPENDIX D- 5 04/26/82 3 04/26/82 h.'-209 RE-ENTRY AND RECOVERY TEAM APPENDIX D-6 04/26/82 2 04/26/82
EP-209 TECHNICAL SUPPORT CENTER TEAM
APPENDIX D .7 04/26/82 3 04/26/82 EP-209 CORPORA TE EMERGENCY TE AM L E ADERS AND .

APPENDIX E SUPPORT PERSONNEL , , , , 94/26/82 4 04/26/82 EP-209 U. S. GOVERNMENT AGENCIES APPENDIX F 04/08/82 2 04/08/82 EP-209 EMERGENCY MANAGEMENT AG ENC I ES 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 SUPPOR T PE R SONNEL ~ APPENDIX I- 1 04/14/82 6 04/14/82 EP-209 RAD SERVICES CALL LIST APPENDIX I-2 05/06/82 4 05/06/82 EP-209 NEARBY PUBLIC AND INDUSTRIAL UhERS PPENDIX J 07/23/81 1 07/23/81 EP-209 MISCELLANEOUS APPENDIX K 07/23/81 1 07/23/81 I . EP INDEX , EMERGENCY PLAN PRCCEDURES INDEX PAGE C e REYo 1@ O ' PEACH BOTTOM UNITS 2 AND 3 05/26/82 * ( NUBSEB lilLE REVIEW __QaIE__ REV. REVISION NQa __QAIE_. EP-709 LOC AL.'PECO PHONES . APPENDIX L 07/23/81 1 0T/23/81 EP-209 0 ELE TED D-E L ET ED APPENDIX M '

EP-209 MEDICAL SUPPORT GROUPS APPENDIF. N 04/26/82 3 04/26/82

~ EP-209 STAFFING AUGMENTATION - 60 MINUTE APPENDIX P CALL PROCEDURE 03/05/82 1 03/05/82 EP-301 OPERATING THE EVACUATION ALARM AND POND PAGE SYSTEM 04/01/81 0 04/01/81 EP-303 , PARTIAL PLANT EVACUATION 12/22/81 1 12/22/81 Er-104 0ELET ED EP-305 SITE EVACUATION 03/05/82 3 03/05/82 kcP-306 EVACUATION OF THE INFORMATION CENTER 05/25/82 2 05/25/82 EP-307 RECEPTION AND ORIENTATION OF SUPPORT

l PERSONNEL 04/12/82 0 04/12/82 EP-311 HANDLING PERS'NNEL O WITH SERIOUS , .

INJURIES, R ADI0 ACTIVE CONT AMINATION EXPOSURE, OR EXCESSIVE RADIATION - ) EXPOSURE EMERGENCY DIREC70K FUNCTIONS d4/08/82. 3 04/08/82 1 . I EP-31? RADIDACTIVE LIOUID RELEASE (EMERGENCY

DIREC TOR FUNC TI ONS1 04/01/81 0 04/01/81 EP-313 CONTROL OFTHYROIDBLOCKING(Kh)
T ABL E TS 04/08/82 0 04/08/82 EP-316 CUMULATIVE POPULATION DOSE l CALCULATIONS 05/06/82 2 05/06/82 l EP-317 DIRECT RECOMMENDATIONS TO COUNTY EMERGENCY MANAGEMENT AND '

CIVIL DEFENSE AGENCIES 04/14/82 , 0 04/14/82 - EP-318 LIQUID RELEASE DOSE CALCULATION I METHOD FOR DRINKI NG WAT ER 05/06/82 0 05/06/82 ll.P-319 L IQU ID RELEASE DOSE C ALCUL ATION METHOD FOR FISH 05/06/82 0 05/06/82 l . { l

EP INDEX EMERGENCY PLCN PRO'CEDURES INDEX PAGE 5 REV. 19
1 PEACH BOTTOM UNITS 2 AND 3 05/26/82
l REVIEW \

' ( MMER TITLE REY. REVISION : _Q&TE-- 110a _ DAIE.__ EP-320 PROCEDURE FOR LE AKING CHLORINE 03/12/82 1 03/12/82 EP-401 ENTRY FOR EMERGENCY REPAIR, * ; .w . . . OPER ATIONS. AND S EARCH AND RESCUE 04/08/82 3 04/08/82 EP-500 REVIEW AND REVISION OF EMERGENCY PLAN {FSAR APPENDIX 0) 04/01/81 0 04/01/81 6 e t O o , 4e t S9 I e e S e 9 T.,' i = ( ' O* ** "~ .. . . , get.ntw t m ."_ c ry. ; - EP 2054.2 l Pc MPbe :waf1 cf 8, R;v. 0 i L , ( My ab4F. ' }%;'?cd' ~/ 1 l 2 l . s/u/r2-g _ _ . . , - - -- -' . . PHILADELPHIA ELECTRIC COMPANY .. PEACH BOTTOM UNITS 2 AND 3 EP 205A.2 _ OBTAINING DRYWELL GAS SAMPLES FROM CONTAINMENT ~ ATHOSPHERE DILUTION CABINETS ~ ~ " " " '

PURPOSE:

The purpose of this procedure is to provide some guidelines for consideration prior to, during and aftor obtaining a drywell gas sample following accident conditions with major fuel damage. APPARATUS: - Appropriate health physics survey equipment Air sampler (low volume) Respiratory protectivo equipment. Anti-C clothing Digital-alarming dosimotry ( 14.4 ml off-gas vial with septums 0-1 al microsyring.1 Septum ~ valve Sample tee with valre PRECAUTION: A. In allprocedure This steps of this procedure, an ALARA concept is mandatory. provides evolutions for drywell gassome philosophy sampics during in anpre-planning accident. s==pling In addition to reviewing this procodurc, an ALARA review of.the sampling sample. process should be performed prior to obtaining the If the sample is not really needed, and lower dose methods to dete.mine the gross data that the sample provides exist, the sample should not be obtained. B.

At no time may NRC exposure limits (either airborne or body dose) be exceeded during the surveying for sampling or obtaining the samplo. If it appears that an ovoroxposure

~ l could reasonably occur whenhobtaining the sample. Do NOT proceed without written NRC approval. N m O e [ EP 205A.2 Paga 2 of 8, Rev. C . 4 p PROCEDURE: - 1. It has been determined that a drywell gas sample is required. Three locations exist whoro tho samplo may bo taken from: A. Core spray CAD cabinet reactor building, 116' elevation. core spray (" Triangle") room S. Torus cooling CAD cabinet - core' spray (" Triangle") room reactor Building, 116' elevation. / , C. . CAD cabinot, north end). reactor building 195' (U/2 south ond, U/3 2. Determination must be made. of which cabinet the sample is to be takon from , Consideration upon plant conditions of which cabinet to be.used should be based (i.e., is it stable?), which analyzers are operating, the time it will take to get there, and doso rates times from area monitors routesinare various locations, etc., approximate and suggested described: A. Core spray ("Trianglo") room - roactor building 116' 9 elevation. Two routes are suggested: 1. Entoring at tho normal, turbino 116', plant catranco. Time = approx. four minutos.

2. . Entering at the roll up doors at oither the north i CUnit 2) or south' (Unit 3) wall of turbino 116' elevation.

Time = approx, two minutes. B. CAD on reactor building 195' olovation. to this CAD arc suggestod: Throu routos 1. Entering at the normal turbine 116' plant entrance, up the stairs past control room to the stairs noar the reactor building elevator. Time = approximately sovon minutes. 2. Enteri.sg radwasto building 135' olovation, proccoding to staars by the reactor building clovator and up the stairs to 195' olevation. - Time = approximately six minutes. 3. Entering recombiner building 116' elevation up the stairs l an up(*th stairs.4eoroceed to the stairs near reactor building olovator, 195' olovation. NOTE: It is suggosted that this routo notebo used (due to time consideration) for Unit 2. Time = approximately six minutes (to Unit 3, 195') l' - __ m- . . - . _ _ _ _ , , , , , . . _ . . _ _ . ~ . - - g - , , , , , _ _ , _ _ _ j JP 205A.2 , Page 3 of 8, Rev.0 3 ( Have a heal u physics technician accompany the chemistry techniciangned assi

to obtain samp Ls in order to y.rform area surveys. Brief health physics personnel on the . route to be taken and the time to get to the survey point

-- Attache a appendices,are are ...,o provided.

the location of the sampin points. Survey maps .

4 Health physics personnel shall take appropriate and protective equipment (e.g. scsA gear survey equipment anti-c 's , e tc . ) . Before making on and calibrated. entry to the power block, ensure surve,y equipment is turned 5. Upon entering the power block, the surveyor will note in general radiation levels trends dose rates enroute to the sample point. If at the pointexceed 10 R/hr gamma, 10 Rad /hr beta, dose rate remains stablespecified below and upon further invcstigationprior to arriving this health physics supervision. or increases, The immediately report to shall be determined prior to entry:foi, lowing radiation dose rates A. If the sample will be taken from theccore > spray ("Triangic") ~ room,the near measure precoatthe area. dose rate at the watertight door located the door, leave the area immediately If dose ratos exceed and report to health5 R/hr at physics v supervision with this information. If dose ratcs aro note dose rates. 1 css than 5 R/hr ontor the stairwell and in the stairwell rnd increase as the door toIf dose 5 R/hr arc greator than rates room is the approached or if the doso rate on contact "Triang1c" door exceeds physics 5 R/hr, oxit immediately and report towith hoalth this supervision with this information. With dose rates less than 5R/hr at the door to "Triangic" room, enter the area taking Survey Survey the the room, inletconcentrating ospecially oncareful note of the rates.dose isolation valves line to the CAD analyzer (line with two the CAD' cabinets. see pictures). take a gen,eral survey.and survey the inletOpen the CAD analyzer panc1, analyzer ( pictures). \"Ensure heat traced line with/without line to the sampic tec 02 - see that the low-volume air sample is taken in the " Breathing Zone" .provided as part of the appendix Survey maps and photographs arc noto of window of this procodure. Special ( opon reaalings must bo inado because of i submersion air dose beta fields expected. B. If the samole will be 1958 eleva' tion, measure the dose rateta".<on fram the CAD on reactor building to tho lo :g corridor. at the door loading door, l'e' ave the, avez immediately If dose rates andexcoed report 5 R/hr at the [ supervision with this i n fo rm a tio n . to hoalth physics ~ b U F.P 205A.2 * >. ..ju 4 ..I u, 14. v . 0 . t . I If dose rates do not exceed 5 R/hr enter the area noting 'g{* dose raten. Take special care walking down the lor.g corridor towards the CAD cabinet; dose rates from the ventilation body dose. and pipes may add significantly to the whole If dose rate trends indicate dose rates - exceeding 10 R/hr gamma or 10 Rad /hr beta, exit the area immediately and report to health physics supervision with this information. With dose rates less than 5 R/hr along the corridor, survey

the area concentrating especially on the CAD cabinet, if dose rates exceed 5 R/hr exit the area immediately and report to health physics supervision with this information. Survey the inlet line to the CAD analyzer (line with two isolation valves

- see pictures). Open the CAD analyzer panel, take a general survey and survey the inlet line to the 02 analyzer (i" heat traced line with/without sample tee - see pictures). Ensure ' that the low-volume air sample is taken in the " Breathing zone". ' i Survey of this maps and photographs are provided as part of the appendix procedure. Special note of window open readin'Js must be made because of submersion air dose beta fields expected.

6. .

The following are the times required to obtain the samples: Loc *ation Time to Sampic s( Drywell CAD (T-116) (Not including time to Torus CAD (T-116) and from sampic point) Dryweli CAD (Rx 195) Pour minutcs with sample tec Ton minutos without sampic tee Suggested Sampling Method (this procodure may be changed based on the ALARA Review) F. ave sampling team (HP person (s) taking the samplo) road tho following procedure.. actual sampleThis procedure shall be dry run at least throc timos before is takon. Obtain three evacuated 14.4 al off gas vials, septum valve and two 1.0 m1 microsyringes (see figure HP0/C0 121.1). A. If a sampling Install a samplingtee has tee been installed continuo 'with stop 7.B. as follows: .

1. Take local control of the CAD analyzor panol and put zero gas into the 02 analyzer. .

2. When analyzer reads I 0, break the swagolok filter figure HPO/CO-121-1. and install sampling too. Soc into the 02 analyzer

3. .

Reconnect tubing and return tho 02 analyzcr to survice. '\4 . After 02 readi.ng's w have stabilized, obtain a sample with ( section 7.B. , e

w. ... - - - ~ - - - - ' ~ ~

-r - EP 205A.2 i s . . . '. . . n , u. .v . 0 I ,- B. Obtain a 0.1 al gas samplo as follows:

1. Verify that the pample valve is closed

2. Remove the 1/4" pipe plug from the samplo valve

~ 3. Install the septum valve (a 1/4-1/8 reducer is required). 6

4. Close the septum valvo

5; Open the sample valve -

6. Open the septum valve

7. Insert the 1 ml micro yringe through the septum valve and the sample valve into the sample.tec.

8. Flush the microsyringe by taking a 0.1 al sample and injecting it back into the sample tee two times.

9. Take a 0.1 m1 sample and remove microsyringo from the sample tee. Inject sampic into a evacuated sample 14.4 off ga,s vial. Inject sample into an evacuated sample ,

14.4 off gas vial. Handle off gas vial with romoto holdor.

10. Close the septum valvo and sampic valvo.

a Tako off gas vial and Icave the area. Obtain smallest sample necessary for analyses to be performed.

7. Consideration of expected dose rates from the sample itself must also be made. Review survey data for the sample inlet line and the 02 analy:er inlet line as compared to goncral ficld for' approximation of sample doso. In this regard the time to take the sample to the hot lab versus shielding the sample must be considered. The personnel who will obtain the sampic shall be briefed on all alternatives and will provide input into practical methods of remotely handling the sample. -

8. Prior to the samplo entering the hot lab, any shiolding, remote tooling or other protective measure shall be in place and ready to accept the ample. 9. Upon introduction of the samplo into the hot lab, the sample will bebody whole handled doseintoapersonnel manner such that it will causo an ALARA invol'ved. Unnecessary personnel shall not remain in the hot lab..

10. Properly- in place and shieldael, the' sample will be processed remotely (where and when possible) . Careful handling of the sample is mandatory in preparation for analysis so contamination is not spread, aETborno prgkloms aru hcid at a minienum, und a

(' new sample is not required. O v . .f,P 201A_7 , I'.ago I, ul' IJ , i<uv. 0 t

11. If the contains.ent sample is too hot to count directly, a 0 .1.~m l sample can be taken frog the off gas samplc vial after the vial is adjusted to ATM, pressure with syringe needed and transferred to another ovare ted.14.4 al off gas vial. Repeat if necdod. l

12. Following final analysis of the sanh1c, results shall bc

. . reported to appropriate supervision. \ l 9 ' e .v( e ( h g EPe205A.2 ? FIGURE 1 h P ga 7 cf 8, Rr.v. 0 M hL h (2tV S / ! 02 -l bdw f b y la. e.4,u "

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QSE fff/0Af TAPE ON Nt-Fe~te su s

,, 4ec h fjpg aggy/pg e Egaal ( \ 1 _ , y__-____________-_______.______-- l EP 205A.2 Appendices EP 205A.2 Appendices ( A. Photographs of sample points. Original photographs are kept on file with Health , Physics supervision. .B. Plant layout maps. C. Survey maps. . f C. ( _________m _ . - . _ _ _ . 7 /I W V [W , , . -,, . ^ ~ ' 2 EP 205A.2 APPENDIX A

i. .- -

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