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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)
	v • d • e

{{#Wiki_filter:' ED IN9EV EMERGENCY PLAN PROCEDURES INDEX PAGE 1 RECUVUI ){~ REvo 16 ; 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 05/25/82 0 05/25/82 : J 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 2 04/08/S2 AND RESPIRATORY PROTECTION GROUP 04/Od/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 ( 05/11/82 3 05/11/82 EP-2078 PERSONNEL ACCOUNTABILITY 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 04/01/81 0 04/01/81 EP-208 SECURITY TEAM 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 EP-209 FIEL D SUPPORT PERSONNEL l 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 04/01/81 0 04/01/81 POND PAGE SYSTEM e EP-303 PARTIAL PLANT EVACUATION 12/22/81 1 12/22/81 .EP-304 'D E L.E T ED 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 REVIEW AND REVISId4~0F EMERGENCY ( EP-500 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. 1.3 If the most severo cvents or condi tions are cl.inni t'ieti.in i { 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) double low level alarm (-48") and 2) any scram other than planned 3) triple low level alarm (-130") and 4) increase in containment pressure to greater than 1 psig but 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

4) activo fuel range Icvc1 indication (2 psig) and shows less than -226" on 11-2/3-/-

Sa) containment pressure 10 psig or 3-9]A, H and greater un PR 2/JSOU g b) failure to rusel triple juw level iSb) containment dose rate greater than alarm after 3 minutos and 105 R/hr on RI-8/9103A/C 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 INJURY WITH EXCESS RADIATION EXPOSURE OR N/A I 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 -.-.----..1 e

Al'l'EN!JAX Fl*- 1 U l l'.ago 3 o f l a, so.v. S PRIMARY CONTAINMENT i r 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 high rad alarm and inability to volume per 24 hrs at 49.1 psig or_ maintain pressurc greater than 2) N2 makeup system is not capable of 0.25 psig on narrow range maintaining pressure (not due to PR-2/3508 or lack of N ). 2 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, and i

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 abnormally high, a,nd Reactor nldg. RADIATION l l vent rad effluent high alarm, or i) Main Stack Rad offluent on PR 0 containmenL high pressure alarm. (2.0 psig), and 051 increasing due to SGTS opera-2) scram, and tion. 3) conteniemeent <loso rate greater Liian ( lof* R/br on HI-it/9103A/c.init au-st/ 910311/11, and 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 I ACTUAL OR POTl;NTIAI. RMI. CASE O.01 lu;M i SPECS WiiO!.C h0DY OH 0.05 Id.M TilYuolls

1) A spike on rad effluent monitors:

1) Uncontrollable release for more than I a) Main Stack greater than 6 x 103 20 minutes from the: cps on RR O-17-051, or b) Reactor Bldg vent greater than a) main stack greater than 1 x 103 8 m 4 on RR 0-17-051 or 1 4 x 10 cpm on RR-2/3979 or b)

2) Analysis of particulate filters or Reactor Bldg vee greater than

[ 5 x 104 cpm on kR-2/3979 or charcoal cartridgc:

2) Continuod particulato or iodinc re-a) Main Stack greater than 5, x 10 1 uCi/sec, o_r lease such that analysis of particu-r b) Reactor Bldg vent greater than late filter or charcoal cartridge t

4 x 101 results in the following estimated i uci/sec relcaso rates: a) main stack greater than 5 x 10 uci/ l 2 sec or RELEASE EXCEPDING TECll SPEC l b) ReacEr Bldg vont greater than QUARTERLY LIMIT 3 x 103 uCi/ soc,o_r { 3) 1 A report of the summation of Containment dose rate greater than 1) 104 individual release data within R/hr on RI-8/9103 A/C and l RI-8/9103 B/D 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)

Uncontrollabic releauc for m re than than 20 minutes from the: 20 minutes from the: a) main stack greater than 1 x 104 a) main stack great.cr than J x 105 cps on RR 0-17-051 o_r cp3 on RR 0-17-051 or b) Reactor Bldg. vont yrcatcr than 5 x 100 h) Huaut or hiely vent greater th.us c1xn on HR-2/3979 or 5 x 100 cpm on RH 2/3979 g 2) 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 latu l'ilter ear charcoal ca r t e isl< n-results in the following estimated results in the tullowing usLimated release rates: release rates: a) main stack greator than 5 x 103 a) main utocl.- greater Lhan 's x IU4uCi/ uCi/sec or sec or b) Reactor Bldg vent greater than b) Reactor Bldg vont greater than 4 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 TO LEAD TO OTHER GENERAL I from SSV EMERGENCILS 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)

Conowingo Pond level on LI-2/~1274tA,H, B,C: 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) failare of all dicsol generators,to 2) loss of voltage on the four 4160 energica their,buuucs.

volt emergency busses or 480 volt e; [ load centers supplied from the four wSS OF ALL DC POWEk POH LCSS TIMN 15' MIN. 4160 volt emergency busses for more than 60 seconds. 1) less than 105 volts on the 2/3A,B,C & D distribution panels as indicated on 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 hours N/A 9 o 9 9 e t SITE EMERGENCY GENElML EMERGudCY N/A N/A e

QQ' }$ffjf QW RWY . - ' TQ: ^ " * \\ J ^ -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 ~ - - - ~

? l'. o p

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

s - -.. ~ - - - - ~ FUEL D AM AGE UNUSUAL EVEttr

(

Angscr POSSIBLE FUCL DAMACC PUEL DAMAGU

1) Air ejector discharge rad monitor

1) Air ejector discharge rad monitor high alarm and an increase of 500mR/

hr within 30 minutes or a level of indicating greater than 2.5 x 10 mR/ 4 hr on RR 2/3-17-152, or 2.5 x 103 mR/hr as indicated on 2) RR-2/3-17-152, o_r High coolant activity of 300 uCi/gm r 2) high reactor coolant activity as dose equivalent I-131, and main steam determined by sample analysis equal line high-high radiaticn alarm with resultant ucr.am al.orm, or l to or greater than 2 uti/gm dosc 3) spent fuel damage resulting in a equivalent I-131 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:

1) When at least 2 of 4 containment rad a) failure of control rods to fully moisitorn indicate levoln gre. iter insert on a scram and than 106 b) higher than normal readings on R/hr on RI-8/9103A/C and 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. UNUSUAL EVENT ( Al l~: lit s MODERATE IIAZARDS SEVEs<E jlAf.Ajp<,N

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

2) Significant explosion on or near Bldg. Diesel Generator Bldg. or 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 as dotormined by Shift Supervision plant s.ifety.i:. tietermineel liy Slii rt Supervision g 3)

Chlorine gas detected in the Control Room l 1' ( SITE EMERG124CY GENEl<AL. EMERGENCY (. .._._.i

o - f$ ?Y ? 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 established at remote shutdown panels t g as determined by Shift Supervision r i n 4 4 SITE EMERGENCY --..i. 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 PH I L A D'E L P H I A EL ECTRIC COMP ANY hr PE ACH BOT TOM UtJI TS ? AND 3 dMERGENCY PLAN I MPL emf tJ T ING Pit 0C E DUh .__....-a %e EE:192_:_uG25UAL_E2E31_EESE30SE %e be EUBEDSE TO DEFINE SITL RESPONSE IN THE. EVENT OF AN Ub< USUAL hv 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 4-5.0 i I DRG At<I Z AT I ON A L CONTROL OF EVERGENCIES b.l.1 UNUSUAL EVENTS b. 2. NOREG 0654 CRITERIA FOR PREPARATION ANO EVALUATION OF 1 HADIOLOGICAL EMERGENCY RESPONSE PLANS AND PRC P ARE DNESS IN SUPDORT OF NUCLE AR Par!ER v 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 IM2fDIAIE_AEll0DS s 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 REFEA IU THE FOLLOWING PROCEDURE: i 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 EP-102 e' PAGE 2 OF 3 I nev. s EF: WAF L '15 FILL QUT THE STANDARD PROMPT NOTIFICATION MESSAGE EP 102-1 Ah7 GIVE IN APPENDI. IT TO THE ASSIGNED COMMUNICATOP, (PO OR HIGHER CLASSIFICATION) AND. DIRECT THE COMMUNICA COMMENCE NOTIFICATION OF THE APPROPRI A TE PART IE s SPECIFIED IN THAT APPENDIX. y NOTE: 00 NOT.uSL BLUE RINGDOWN PHONE FOR THESE CALLS. d 1.6 CLOSELY MDNITOR CONDITIONS TO DETERMINE PRESENT HAZARDS TO PERSONNEL AND POTENTIAL ACCIDENT CONDITIONS e-DEVELOP. 2.0 CCMMUNICATOR SHALL* d 21 PERFORM NOTIFICATIONS ON APPENDIX EP 102-1 USING THE STANDARD PROMPT NOTIFICATION MESSAGE p INCLUDED IN THAT APPENDIX. SEE EP 209, APPENDIX A FOR ADDITIONAL TELEPHONE NUMBERS IF NECESSARY. 9 EOLLDs:UE_AC11DbS 1.0 EMERGENCY DIRECTOR SHALL: 9 11 PERIODICALLY EVALUATE THE EVENT CLASSIFICATION IN ACC0dDANCE WITe EP AND ESCALATE Oh 101, CLASS 1F,1 CATION OF EMERGENCIES 9 DEESC AL A TE THE CL ASSIFIC ATIDN AS NEC ES 12 UE TERMINE 4HICH SUPPORT PERSONNEL ARE,NFCESSARY FOR 9 EMERGENCY FUNCTIONS.AND DIRECT THE SHIFT CLCRK TO CONTACT THOSE PERSONNEL. IF SHIFT CLERK IS NOT AVAILABLt TnIS FUNCTION SHALL BE ASSIGNED TO ANY I AVAILAdLt INDIVIDUAL. 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 (HAS bEEN)(HAS NOT BEEN) AN ( A[R60RNE)(L IQUID) R ADIOAC TI VE RELEAS FROM T H E P L A.'. T. 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 COM'1UN I C A TOR ' PARTY

PERS3N_dESPDSDING UD11EICA1103 INIIIALS 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 A3bVE kAki((S~CUkPLETED_((((((((_((____((((!~~~ ~ ~ VERIFIEU BY CATC (EMEkG.~UIEECTUki~~~~ ' ~~~~~~~~~~~ FILE SYS-3-1

n. e-EP-103 r..;. 3.. ;. -,, - ; r,y, -'l - DAGF 1 0F 6 l REvo hls 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*'*

= -

ee,, g 9

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. ,4 2.3 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 PRil T EC T I ON TEAM WHEN DIRECTED SY THE EMEHGENCY DIRILIOR. 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 TO MAN TSC AND REQUIRED EMEPGENCY TEAMS (60 MINUTE CALL 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 AND ONSITE RADIATION SURVEYS FROM THE RADIAT PRDIECTION TE AM LEADER, AS NECESSARY. 1.3 PERFJRM ACTIONS AS NECESSARY TO MITIGATE CONDITIONS OF THt LMERGENCY SITUATION. 1.4 3ETERMINE WHICH 1DDITIONAL SUPPORT PERSONNEL ARE NECESSARY EMERGENCY FUNCTIONS AND DIRECT THE SHIF T CLERK OR OTHE R FOR ASSIGNED COMMUNICATOR IN TSC TO CONTACT ,A THOSL PERSONNEL. 1.5 PROVlat Stif PERSONNIL AITH P.A. SPEAKER AN OD'NfENENTS FOR ANY 6AJOR CHANGES IN PLANT EMERGENCY STATUS. SUCH AS C HA L ME0 6fhC Y ACTION LEVELS, FVACUATIONS AND STARTING AND STOPPINJ. OF RAJIDACTIVE RELEASES (IF ANY). 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 SUPDORT THE CONTROL ROOM Afl0 SHIFT $0PERVISION AS t .NECESSARY. I 4.0 RADIAilqN pry!LCTION TE AM LEADER SHALL: c 4., REP.. , GR,,, .,D RE,UL,, OF CU UL.,,VE POPULAT,0, 00si CALCULATIONS AND SITE RADIATION SURVEYS TO THE - IMtqh{hCY DIRECTOR AS NECESSARY.

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. A' ~ s e. d e 9 O e e, I (' ..h ' .,_ _,, q,,,,

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e / EP-RO3 e 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 4 ,/ b .e,,. +,,, _ w.n.. n n ._..;-----.. -...... ~.. - - - - ,m ~ rc,.

I .. g. EP-103 PAGE B or 8 REV. tr (, f ED:WAF t (_ AEEENQl!_EE_lD3-3 E5EEGEhC1_EEE05uBE_L15111 t -PRC ICTED WHOLE BODY THYRDIO Ed3L11Du QQ1E DQSE AUTHORIZED B1 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 HLALTH, C ~ 3. PHOT EC T ION OF .'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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C' l g EP-104 PAGE 1 0F 9 i HEV. 5 QDN EGF :'n A F ( 14m 3 WI ~ v PHILADELPHIA EL ECTRIC CO"P ANY ~ FETCH BOTTOM UNITS 2 AN0 3 Et4RGENCY PLAN IMPLEMENTING PR O C T U'# R E s, 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 SEC110u 111Li v 4 1.3 SITE EMERGENCY 5.0 kv G4GANIZATIONAL CONTROL OF EMERGENCIES 6.1.3 SITE EMERGENCY ( 2. NUREd 0654 CHITERIA FOR kW 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 SITE EMERGENCY NOTIFICATION CHECKOFF L IS T EP-104-2 PERSONNEL CALL.(ECORD LP 104-3 EMERGENCY EXPUSURE LIMITS (EMERGENCY PLAN TABLE 6 1) ESECAU11 DSS ' 1. PLANNED RADIATION EXPOSURES' SHOULD BE LIMITED ADMIN IS TR AT ION GUIDE LE VEL S TO THE 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 IF NOT AL4 LADY DONE AT AN EARLIER EMERGENCY ACTION LEV k ACTIVATE E ME R G L NC Y TEAMS AS NECESSARY. 13 DIRECT THE EVACUATION OF REFER TO THE FOLL OWit!G PROCE00k ES :AFFECTED AREAS A e

%d 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 ATE P ARTI ES AS SPEC IFIEO IN SECTION 2.1 UF THIS PROCEDURE. 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 ' THE PHONE SHOULD BE OBTAINED FROM NRC PRIOR TO SECURIN THIS TELEPHONE. 1.6 IF NOT ALREADY ACC OMPL ISHED A T THE ALERT STAGE. OlkECT THE SHIF1 CLERK TO ACTIVATE THE 60 MINUTE CALL LIST USING EP 209 APP P. IF SHIFT CLERK IS NOT AVAILABLE, THIS FUNCTION V MAY BE ASSIGNED TO ANY AVAILABLE INDIVIDUAL. 1.7 DIRECT ONE OF THC ON-SHIFT IEC TECHNICIANS TG ACTIVATE ks TECHNICAL SUPPORT CENT.ER AND EMERGENCY OPERATIONS FA IN ACCORDANCE WITH EP 201 AND 203 IF NOT ALREADY ACTIVAT IF NOT ALRCADY PERFORMED PREVIOUSLY, INFORM THE SHIFT CLERK W v IEC TECHNICIAN WILL ACTIVATE THE CENTERS AT UNIT 1 IN THE CLERK KNOW UHICH REMAINING ICC TECHNICIAN TO CAL PROMPT MOSILIZATION PROCEDURE. 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 DONE IN ACCORDANCE WITH EP 205, RADIATION PROTECTION TEAM. 1.9 INI TI A TE THE IMPLE MENT AT ION OF EP 316, CUMULATIVE POPULATION COSE C ALCUL A T IONS, AS NECESSARY. 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

CENTER AND TO ACTIVATE IT IN ACCORDANCE W H ABIT ABL E.

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 AN9 POTENTI AL ACCIDENT CONDITIONS THAT M DEVEL OP. 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 TO GitTAIN A SITE bDUNDARY DOSE RATF AS SODN AS PRACl IC ABLE. 1 13 IF NECESSARY, INITIATE IMPLEMENTATION OF EP-316 AND EP-317, DIRECT R LC.UMME ND A T IOr.S T O C OUN T Y EMERGENCY MANAG AGENCIES. 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 TO THE E M ER GE NC Y DIRECTOR WHEN THE NOTIFIC ARE COMPLE T ED. 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 DESIGNEE SHALL: V 3.1 ACTIVATE ThE OPERATIONS SUPPORT CENTER ON 135' ELEV TUR BLDG, IF IT IS HABITABLE. IN ACCORDANCE WITH EP 202. IF THIS OPEPATIONS SUPPORT CENTER IS NOT HABITABLE REPO V TO THE CONTROL ROOM. 9.0 RADIATIOtw PROTECT!0'4 TE AM L EAOCR SHALL. V 91 INITIATE ON-AN] OFF SITE RADIATION SURVEYS IN ACCORDANCE WITH EP 2D5. RADIATION PROTECTION TEAM,'WHEN V 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 COCRUINATE THIS F UNC T I ON. s.- 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 MAN TSC AND EOF (60 MINUTE ChtL LIST). DOCUMENT C ON EP 209 APP P. 62 I NF OR M INTERIM EMERGENCY DIRECTOR OR EMERGENCY WHEN CONTACTS ARE COMPLETED.

y - - ~ I EP-IoA

v 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 ACCORDANCE.NITH EP 101, CLASSIFICATION OF EMdRGENCIES Y, AND LSCALATE OR DEESCALATE THE CLASSIFICATION. AS NECESSARY. ss 12 OBT AIN RESULTS OF THE CUMULATIVE POPULATION DOSE CALCULATIONS AND ONSITE/OFFSITE RADIATION SURVEYS IHE RADIATION FRO" PROTECTION TE AM L EADER, AS NECESS ARY. v 13 PROVIDE APPROPRI AT E INFORMATION FROM THE PREVIO EVALUATIONS TO COMMUNIC ATOR Le IN THE EOF FOR NOTIFI-C ATION OF THE BUREAU OF RADIATION PROTECTION. I.4 PERFURM THE EMERGENCYACTIONS AS NECESSARY'TO MITIGATE CO W UF SITUATION. 1.S D E T ER MINE WHICN ADDI TIONAL SUPPORT PERSONNCL A \\* NECESSARY FOR EMERGENCY FUNCTIONS AND DIRECT THE ' SHIFT CLE% 0" OTHER ASSIGNED COMMUNICATOR IN TSC I UR EJF TO CONTACI THOST PERSONNEL. V 10 PROVIOE SITE PERSONNEL WITH P.A.SPEAXE4 ANNOUNCEMENTS FOR ANY MAJOR CHANGES IN PLANT EMERGENCY STATUS L/ cMERGENCY ACTIUN LEVELS, EVACUATIONS AND STARTING AND OF RADIOACTIVE RLLEASES (IF ANY). V 2.0 S T A T I ON SUPERINTENCENT SHALL: 21 REPORT TO THE T E C HNI C A L SUPPORT CENTER OR CON Ad ROOM. FOR A BRIEFING OF THE SITUATION. 22 A SSUM E THE ROLE OF EMERGENCY DIRECTOR (IF NOT'AL v D ON E ) BY FORMALLY RELIEVING THE INTERIM EMER OF Th!S RESPONSIb!LITY. ANNOUNCE THAT HE HAS ASSUMED THE R OL E OF EMERGENCY DIRECTOR TO THE ASSEMBL M CENTER PERSONNEL. 2.3 V ER IF Y THE EMERGE NCY CLASSIFICATION. 2.4 VERIFY THAT THE TECHNICAL SUPPORT CENTER, EMERGENCY OPERATIONS FACILITY AND THE UPERATIONS SUPPORT C HAVE BEEN ACIIVATED. 3.0 135' ELEV. TURBINE BLDG. OPE R ATIONS SUPPORT CENTE I ( 31 NUTIF Y THE INTERIM E uTM EN C Y DIRECTOR OR EMERGEN DIREC TOR WHEN THE OPE 9ATIONS SUPPORT C EN T E R IS l ACIIVATEv. e l i

,mf EP-104 PAGE S OF 9 REV. S EGF:WAF

k kv 32 S U/ PO R T THL CONTROL RDOM AND SHIFT SUPERVISION A NECESSARY.

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 DOSE CALCULATIONSPh0G4E SS AND RESULTS OF CUMU %W AND ON AND OFF SITE R ADI ATION SURVEYS TO THE SITE EV.ERGENCY COORDINATOR AND EMERGENC AS NCCESSARY. - Le 43 NOTIFY THE, SIT E EMERGENCY COORDINATOR 0F THE NEED FOR ASSIST ANCE FROM R ADI ATION MANAGEMENT CORPOR ATIO %v S.D SHIFT CLERK OR ASSIGNED TSC OR EOF COMMUNICNTOR As 51 IF NUT ALREADY DONE, NOTIFY ADDITIONAL S UP POR T PERSONNE TO REPORT TO THE PLANT AS DIRECTED BY THE EMERGEN DIRECTCR. REFER TO LP 209 DOCUMENT ON APP EP 101-2 %r 52 ' NOTIFY EMERGENCY DIRECTOR OR SITE EMERGENCY I nHEN THE ADDITIONAL SUPPORT Av PERSONNEL HAVE BEEN NOTIFIED. 60 ICC TECHNICIANS SHALL: (IF NOT ALREADY PERFORMED AS PER EP-103) be 6.1 INFORM THE EMERGCNCY DIRECTOR WHEN THE CENTE IF NOT PREVIOUSLY DONE. ' \\e 62 MAN THE TSC 04 EOF DATA DISPLAY (CCTV) POSITIONS AS DIRECT ED BY THE EkERGENCY DIRECTOR. . %,e 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. THIS IS PEACH BOTTOM A T O'i ! C POWER STATION CALLING TO REPORT A. SITE EMERGENCY HAS BEEN DECLARED ON UNIT L, TIME AND DATE OF IS ____________. SI TE EMERGENCY CL ASSIFIC ATION THE BA SIC PROBLEM IS______________________________________. THE PLANT STATUS IS (STABLE) (IMPROVING) ( DEGR AD ING ) (NOT KNOWN). THERE (HAS NOT BEEN) (IS POTENTIAL FOR) (HAS BEEN) (IS PR A R A010 AC T !' VE (AIRDURNE) (LIQUIO) RELEASE FROM THE PLANT ( %w LEVEL B EL O'n IHAT CONSIGEkED A PUBL IC H AZ ARD) (AT A LEV PRO TEC T I VE AC TION IS ADVISABLE). RECOMMENDED PR O T EC T I VE AC TION S ARE (NONE) %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 COMMUNICAT04'S EaBII bh BESEQbDISG SD11E1CaI10U 12111aLS______ S T A T I ON S UP ER IN T ENDEN T ( 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' YORK COUNTY EMERGENCY MANAGEMENT AGENCY s (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

~~ EP-104 \\# PAGE 7 OF 9 i REV. 5 EGF: WAF 4 AEEESD11_1Di:1_1C0ullD1 311E_EJ'ESGESCX_dDI1EICAIIDS_CUECEDEE_Llil %d s

CECIL COUNTY CIVIL DEFENSE A GL' NC Y

~ %W PENNSYLVANIA STATE POLICE - YORK %s PA. BRP p %d ' NRC OPERATIONS CENTERce (RED PHONE) TIME NOTIFICATION UF P A R T I C S A BO VF C OM PL E T E D. ________________ %9 VEk!FIED BY DATE __________ EM'RGENCY DIRECTOR t kw FILE SYs-3-1 MUST NOT IF Y PE*A OY U SE-OF COMMERC I AL TELEPHONE NO. O ks (dLUE PnONE NOT MANNEO eY PEMA 04 BACKSHIFTS). oc IF NRC PREVIOUSLY NOT IF I E D DURING ALERT CONDITION. THE Le ASSIGNED PO COMMUNICATOR CONTINUOUSLY MANNING RED PHONE IN CONTROL ROO4 SuuutD HANOLE THIS NOTIFICATION AUTOMATICALLY HOWEVER, CHECK WITH CONTROL ROOM TO DE SURE. THIS NOTIFI-v CATION IS MADE. %,4 e o V s md ~ O q *y e p ___

%d EP-to4 'y PAGE 8 OF 9 j REV. 5 e EGF:WAF .d APDESD1_X_E_A_10_4_-2 .w _Dt'_D3DJP Lc L_E_ALL__ REC 0_S_0 V DI SPOSI TION OF C ALL ESTIMATED NAME OF

TIME, NO TIME OF CALL g,

EESSD3. _C_A LL.e)r ___C_A LLLaJ____Ae

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

d 4 W ______________________________m_________ W ___~__________________________________________________________________ W w w Y w v _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - -. __ v w .(s ____e._________eleque________ emes __euh_eumeumy________4eID_emb-_______.us_______e.___ee__e.--_ s O FILE S Y S 1 i I e h

-x v_ %J ga EP-IO4 PAGE 9 OF 9 REV. 5 g / EGF: WAF AEEESD11 EE_106-3 EdESGESCI EZEDSUEE_LIMIIS PROJECTED WHOLE DODY THYR 0!D EUML1133 - DuSE H RIZE0 gg3g I.L IFE S A VING AND REDUCTION OF INJURY ~ 75 REMO 375 REM ENERGENCY00 2.UPERATION OF DIRECTJ4 \\v E QUI P ME N T TO MITIGATE AN , %r EMERGENCY g 25 ' REM

125 REM EMERGENCY 00 he 3.PROTEC T ION OF DIRECTOR-HEALTH AND SAFETY OF THE PUBLIC 5 REN kr 25 REM EMERGENCY DIDECTOR 4.OTHER EMERGENCY 10 CFR 20 4w AC TI VI T IE S 10 CFR 20 LIvlTS EMERGENCY LIMITS 5.R E-EN TR Y/RE-DIRECTOR L,

COVERY ADMINISTRATIVE ACTIVITIES GUIDE L INES A DMINI S TR A T I VE GUIDE LINES N/A h, O REFT.FNCE: E P A-5 20/I-75 -001 TABLE 2.1 00SUCH EXPOSURE SHALL BE ON A VOLUNTARY BASIS v

s. e se

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-- y. v... ~-- .. 7 EP-10% 7, -, 4 PAGE 1 0F 9 C- - l 'AhV. $ EGF: WA j g I Qgg ggf 2 3 iM2 l PH IL ADEL PHI A ELEC1 HIC COMPANY t c,. - ! PEACH i 00TTOM UNITS 2 AND 3 -~~' -~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. 12 ACTIVATE EMERGENCY TEAMS AS NECESSARY IF NOT ALREAJY j l I

., t p- - - y, (;;; EP-105 4 PAGE 3 0F 9 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- ~" ' MENT AGENCIES. i 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 ACCORDANCE ri! T H EP 202. IF THE OPERATIONS SUPPOR T CENTER IS NOT k HAb!TABLL REPORT TO THE CONTROL ROOM. 4.0 RADIATION PROTECTION TE4.'l LEADER SHALL: t + 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:

" q.. l'* -S ' ~ ' ' s " ' ' " '~ .n i EP-105 i e. PAGE 4 0F 9 RCV. S EGF:WAF ( t 11 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 ANY MAJOR CHANGES IN PL ANT EMERGENCY S TA TUS, SUCH AS CHANGING k

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. 2.4 VERIFY THAT THE TECHNIC A L SUPPOR T CENTER, EMERGENCY t 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: e b e 4

gg 3. 3 e,,y, .. e <: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. o 9 O e 8 e 9 0 e

j' 3 EP-105 e PAGE 6 OF 9 MEV. 5 EGF:WAF ( ABEEUELE_EE_105:1 GEULSAL_E5EECCUCY_UDILELCAIl0N_CudCduEE_LLSI 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 s 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 e c.w

m. y , m-.,. m.:,...1 s. 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 DATE __________ d>r ' EMERGENCY DIRECTOR FIL6 - SYS-3-1 s 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. e D g e f ,e.w n '~

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7,:,.r ..:..y - mp 1 y,.,,z 3...s c v~ EP-105 PAGE 9 0F 9 REv. 5 EGF:WAF

I AEEEbD11_EE_191:3 E5E&GENEI_EEE01USE_ LIM 111 PROJECTED
^

WHOLE. BODY THYROID AUTH0Rilt EuuCILDU QUSE DDSL Bt s 1. L'IFE SAVING AND REDUCTIJN OF INJURY 75 REMC 375 REM DIRECT 0d EMERGENC) 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 EMERGENCY 5 REM 25 REM DI REC TOR 4. OTHER EMERGENCY 10 CFR 20 10 CFR 20 EMERGENCY ACTIVITIES L I M I.T S LIMITS DIRECTOR 5. R E-EN T RY/R t C O V ER Y ADMINISTRATIVE ADMINISTRATIVE ACTIVITIES 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

Y* ~~ (s [ EP-705A ( j' PAGE 1 OF T ' "j REV. 4 EF:T H N$ ^ J La OA nM 2 5 %1 PHILADELPHIA ELECTRIC COMP,ANY V l .l'LACH !!OTTOM UNITS,2 AND 3 i_.__. _. 3 EfERGENCY PLAN 'N IMPLEMENTING PROCEDURE E-2.01A___Ct1Et!1Sla1_hidELiaG_itiD ASALXS EuaEasE dye %r TO DEFINE GROUP.* THE ACTIONS OF THE CefEMISTRY S AMPLING AND AN v IS Br.EEELUCES

.3v 1.

PEACH BOTTOM ATOMIC POWER'STATIO l l N EMERGENCY PLAN ' ke SEC1109 ] IllLE i 5 2 2 2 1.E CHEMISTRY SAMPLING AND ANALYSIS ' \\v i 6 2.I ASSESSMENT METHODS FOR DETERMI i ( OF RELEASE TO THE ATMOSPHERE W 2. NING MAGNITUDE .HE AL TH PHYS ICS OPER A TING /CHEMISTR Y V t.altiSEE ING PROCEDURES

IIILE HP0/CO-4 RADIATION WORK PERMITS

\\s 3. NUREG 0654 PREPARATION AND EVALUATION OF R EMERGENCY s POWER PLANTS. RESPONSE PLANS AND NUCLEAR AEEEND1E IN SUPPOR T OF EP 205A-1 EMERGENCY EXPUSURE LIMITS AC110S_LEZEL (EMERGENCY PLAN TABLE 6 1) THE CHEMISTRY THE DISCR ET ION OFS AMPLING AND ANAL YSIS GROUP g THE R ADI ATION PROTEC TION. WILL BE ACTIVATED EBEtau110S$ TEAM LEADER. 1. IN ALL STEPS OF S AMPLING AND ANALYSIS GROUP MEMBERTHIS PROCEDUR TO THE ADMINISTRATIVE GUIDE LE CONCEPT IS MANDA TORY. ( VEL S. IN APPENDIX'S EXPOSURE EXPOSURE LIMITS. CON TR OL THE IR OWN CHEMIS TRY SAMPL ING AND EP 205 A-1, EMERGENC Y EXP3SURES. ANALYSIS GROUP MEMBERS e

w - ~ 3 + k) EP-205A PAGE 2 0F 7 j, REV. 4 b( EF: TTH 2. REQUIREMENTS OF HPU/CO-4, RADIATION WORK PERMITS, IMME01alf_4L110bi ARE NOT APPLIC ADLE. Le 1 0 RADIATION PROTECTIONTE AM L EADER. SHALL: 11 CONT AC T THE., CHEMIS TRY ,6 SAMPLING AND ANALYSIS GROUP DIRECT HIM TO COLLECT SAMPLES IN ACCORDANCE WITHSAMPLES, AS NECESSARY,LEAUER, SUPPORT GROUPS FOR HP0/CO PROCEDURES: AND ANALYZE THE

s OR USE OFFSITE THE ANAL YSES.

2.0 CHEMI STRY S AMPL ING' AND ANAL YSI S GROUP L EADER SHALL: Ls 41 AS SLMcLE THE CHEMIS TRY S AMPL ING AND-Al9ALYSI S GR OUP. 22 ' DIRECT THE MONITORING AND SAMPLING O'F RELEA ,%v

MONITORS, AND PROCESS MONITORS AS REQUIRED AND

, AIR WITH PRECAUTION 'l,.ABOVE. IN ACCORDANCh %v 2.3 ANALYZ E THE DAT A INSTRUMENT READINGS.FROM S AMPLES, PROCESS AND EFF UENT L READINGS. ISOTOPIC COMPOSITION AND RELEASE R A TES FROM THIS DATA DE TE R MINE %d 2.4

ROVIDE THE DOSE

. AN0' DI REC T GROUP MEMuGRSASSESSMENT GROUP l/ WITH PERTINENT INF04MATION TO ASSIST, AS NECESSARY, WITH 00SF RATE CALCUL ATIONS AND DETERMINATION OF RADIO NSEQUENCES. W 2 e I i I i I I P e +

'. / e EP-205A ! s, PAGE 3 OF T I REV. 4 EF: TTH 'i ( l, 3.0 CHEMISTRY SAMPLING AND ANALYSI S GROUP MEMBERS SHALL: 31 ' ASSEMBLE THE I4GLtSSARY EQUIPMENT NEEDED TO ODTAIN A SAMPLES. PR6 L AJEL ALL g SAMPLE CONTAINERS BEFORE SAMPLING. bs USE APPENDIX LP 205 A-2 TO INSURE ALL STEPS IN THE HPO/CO SAMPLING AND ANALYSIS PROCEDURES ARE FOLLOWED. %s ~ 3.2 ' SAMPLE PRIMARY COOLANT AND DP.YWELL ATEOSPHERE A S WITH THE FOLLO' JING PROCEDURES: v .EP 205A.I OPERATION OF POST ACCIDENT S AMPLING ST AT ION.FOLLOWING We ' ACCIDENT CONDITIONS EP 205A.2 OBTAINING DRYWELL. GAS SAMPLES w FROM CONT AINMENT ATMOSPHERE DILUTION CABINETS w r EP 205A.3 RETRIEVING AND CHANGING SAMPLE FILTERS AND CARTRIDGES FROM THE J DRYWELL RADIATION MONITOR EP 205A.4 OBT AINIf4G DRYWELL G AS S AMPLES I. FROM THE DRYWELL R ADI AT ION s MONITOR SAMPLING STATION EP 205A.5 ORTAINING REACTOR WATER SAMPLES s 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 TO OBTA'IN SAMPLES FROM THE VARIUs5 SAMPLE POINTS. 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

e s '. 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 OUTAINING SAMPLES FROM ss ~ CONDENSATE SAMPLE SINK FOLLOWING ACCIDENT ' .%d . CONDITIONS. DFF GAS %s EP 20SA.lO OFFGkSSAMPLESFROM THE OFF GAS HYDROGEN ANALYZER FOLLOWI'G ACCIDENT CONDITIONS. .t w N 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 ANALYSIS OF' HIGHLY RADI0 ACTIVE us LIQUID SAMPLES. EP 205A.12 S AMPL E PREPARATION AND ANALYSIS V OF HIGHLY RA'DIDACTIVE PARTICULATE FILTERS AND IODINE CARTRIDGE S. EP 20bA.13 SA'4PLE PREPARATION AND ANALYSIS v 0F HIGHLY RADIOACTIVE ~ GAS. SAMPLES. 36 AT T ACH ALL DATA SHEETS AND ANALYSIS REPORTS TO APPENDIX v EP 205A-2(CHEM SAMPLING C ANALYSIS C.O.L.) FOR EACH SAMPLE TAKEN. GIVE THIS INFORMATION TO THE CHEM SAMPLING AND AN ALYSIS GROUP LEADER. b ~ 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 COO.4DINATOR (IF ACTIVATED) AND THE EMERGENCY. 0! R 12 k< PROVIDE GROJP MEwuE RS WITH PERIODIC PL ANT CHANGES I ACLUDING SIGNIFIC ANT R ADI ATION STATUS ( 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 PAGE 5 0F.7 y / REV; 4 EF:TTH vt V 21 RC DJRT RESULTS CF S AMPLLS AND AN ALYSES TO THE RADIATION Pet 01 EC T 10N T E A P. LEADER. I V I V n W .y V i V 1 (/ a 3 v w \\e# v t i teuf a i E O e v

.y = EP-205A PAGE 6-OF 7 /; REV. 4 EF: TTH AEEEMIX_EE_ZbSA:1 'v 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 DIR EC TOR y'. 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 'W e of ( h 1

,y EP-205A 4 PAGE 7 0F 7 [ REV. 4 EF:TTH 1h 5 ws AEEENDIL_LE LD5L 2 Cu25_SABEL1BG_L ANALYSIS C204La " %s { SAMPLE TIME s!_ %v oAre l ~ SAMPLING: %W (# SAMPLE CONTAINER PRELABELED LEAD CARRYING PIG OBTAINEO {(! bv SAMPLING EQUIPMENT PROC EDURE REVIEWED ASSEMBLE 0 ___________ g RWP ISSUED.OR HP AVAILABLE ^ bv ' SAMPLE STZE i 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 OTHER (EXPLAIN) V s SAMPLE VOLUME USED FOR AfjALYSIS M l ~ t { t Y / s l l .o ( O o

.I c ;;- g p ge 1 cr 4, a v. o ~~ i MGstth MM 2 5 G1 hN-l s ( '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 occur when obtaining the sampic, do not proceed without written 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 that survey equipment is required when retrieving the samples. 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 the extra filter holder and cartridge holder for the drywe radiation monitor. 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 i a77 val. 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.

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f MAY 2 5 "t? 3 ~. l L.. PillLADELPill A ELECTRIC COMPANY r .g.. y 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 Health Physics personnel shall take appropriate survey equipment and protective 4. 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 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 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.

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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 ~ l 1 N

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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 i h a e

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1 EP 205A.8 t '-i i P;g3 1 of 8, Rev. 0 } MPG:tt L /MI { -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 provides some philosophy in preplanning sampling 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. 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 determined that a sample from the radwaste sample sink is required. 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) south (Unit 2) wall of turbine building 116'. or i time = approximately four minutes 3. Have a health physics technician accompany the chemistry tech i i to obtain samples in order to conduct area surveys n c an assigned & Chemistry personnel on the route to be taken and the tiBrief Health Physics the sample point. me to get to Survey maps are also provided. Attached as Appendices are the loca points. 4. Health Physics personnel shall take appropriate survey equip protective equipment (e.g. SCBA gears and Anti-C 's, etc. ). ment and making entry to the Power Block, ensure survey equipment is turn d Pefore and calibrated. with the survey and to valve in grab sample pointChemistry perso e on 5. Upon entering the Power Block, the surveyor (s) will note tr radiation levels enroute to the sample point. ends in general 10 R/hr gamma or 10 rad /hr beta prior to arriving at the point If dose rates exceed below and upon further investigation this dose rate remains st bl specified increases exit immediately and report to Health Physics Sup a e or following dose rates shall be determined prior to entry: ervision. The A. If the dose rate exceeds 5 R/hr at any portion of the eith , Physics Supervision with this information. leading to RW er door ealth ( With dose rates less than 5 R/hr, enter the Radwaste Buildi that door. Take careful note of the dose rates. ng through B. the grab sample pointSurvey the area concentrating, especially, on the e Sink. Survey the low-volume air sample is taken at the hood (Beta & Gamma), with beta fields expected in the sample sink, as well asSpec use of the high dose beta fields. , submersion air 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 nged after the ALARA review) 7. 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 withor less in a 3 o Use tongs or attention. When required amount of sample is obtained remov out operator 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 of expected dose rates from the s (~

made, shielding the sample must be considered.in this regard, the o the hot lab versus prectical methods of remotely handling the samp provide input into 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 RWP shall be a u on. 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 y to accept the sample, 11. Upon introduction of the sample into the hot l b handled in a manner such that it will cause an ALa, the sample will be personnel involved. Unnecessary personnel shall not remain in thARA whole 32. Properly in place and shielded, the sample will b e hot lab. (where and when possible). e processed remotely preparation for analysis so contamination is not spCareful hand are held at a minimum, and a new sample isn't requiread, airborne pro red. 13. 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 AW!- r E *** b 198? I b i 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 3 Oz. Sample Bottle with Lid i 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 evolutions for samples during an accident. l 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. At no time may NRC exposure limits (either airborno or body doso) bo l 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 Time = approximatley three minutes l 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. Attached as Appendices are the locations of the sample points. Survey maps are also provided. 4. Health 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. 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 remains stable or increases exit immediately and report to Health Physics Supervision. Survey the area concentrating, especially, on the Sample Sink. 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 maps and photographs are provided as part of the Appendix of this procedure. 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 the smallost samplo necessary for analysis to be performod. Obtain a 1 oz. sample (about 1" up from bottom) or less in a 3 oz. bottle. 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 of expected dose ratos from tho samplo, itself, must also be 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 mothods of remotoly 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. I 8. I A RWP shall be assigned for the sample evolution. followed by all personnel handling the sample. The RWP shall be 9. Prior to tho sample ontoring the hot lab, any shiolding, romoto tooling l ( or other protoctive 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 be handled in a manner such that it will cause an AIAR will dose to personnel involved. oy in hot lab. Unnecessary personnel shall not remain 11. Properly in place and shielded, the samplo will be process d remotely (whsre and when possible). e is mandatory in preparation for analysis so contamination iCareful h spread, airborne problems are held at a minimum, and a new sasipl s not isn't required. 12. Following final analysis of the sample, results shall be appropriato 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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( en-n c l 'GCMMIMM ow/r.3 cwoan e S4n?ta S w m O .,,_p- j_ l (] EP 205A.10 Pcg7 1 Cf 10, Rev. O t MPG:::cf PHILADELPHIA ELECTRIC COMPANY a k v ( ' TEACH BOTTOM UNITS 2 6 3 ' EP -305A.10 OBTAINING OFF-GAS SAMPLES FROM THE OFF-GAS HYDROGEN ANALYZER FOLLOWING ACCIDENT CONDITIONS PURPOSE: The purpose of this procedure is to provide guidelines for consid-eration prior to, during, and after obtaining an off-gas sample from the off-gas hydrogen analyzer following accident conditions with major fuel damage. APPARATUS: Appropriate health physics survey equipment Air sampler (Iow volume) Respiratory protective equipment Anti-C clothing Digital-alarming dosimetry 14.4 ml off-gas vial with septums 0-1 m1 microsyringe Septum valve Sample tee with valve Tongs or other remote tooling or lead carrying container PRECAUTION: ) A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in pre-planning sampling evolutions for off-gas 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 exist to determine the gross data that the sample provides, 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. ( l b e y g er zudA,Io PlO 2 Cf 10, Rev. 0 PROCEDURE : 1. It has been determined that hydrogen analyzer is required.an off-gas sample from the off-gas 3 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 Once a path is selc$ted, obtain the appropriate keys for locked 3. 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 and photographs are provided as part of the appendix of this procedure. --____._...._......____....______......__.............._____....,._..._.___........._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 H Analyzer 2 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. Review survey data for t~he sample inlet line and the 112 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 Igb 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. 9. A RWP will be assigned for the sample collection and analysis. RKP shall be followed by all personnel handling the sampic. The ( 10. 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. 11. Upon introduction of the semple into the hot be handled in a manner such that lab, the sample will 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 final analysis of the sample, results shall be reported to appropriate supervision. ( ---~..~.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 !gg gg 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 of this procedure is to provide some off-gas from 112 Analyzer. 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 ml off gas vial with septums Septum valve Sample tee with valve _PRCCEDURE: 1. Prior to obtaing the gas sample, a Radiation C (R-C-A) survey shall be performed and an RNP obt i ontamination-Airborne a ned. 2. Suggested Sampling Method A. Install sampling tee (if not present) by th e following: (1) Place the 112 in purge. (2) and verify the sample valve is closed. Install the sam on piping (3) Return the 11 to stabilize before sampling. Analyzer to normal operation allow read [ 2 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 the carple valve and the septum valve (push red button all the way in). (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 ~ - - - ~. -. -... RJ Q APPENUIx y Pcgg 7 er 30, cc.s ow>l s k N 6 ..e 7 7 d Y'E h.._ I

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r 3 e i i ~a d.: . ; !.y OT' N / 31 I"*, ! v: i J,.. \\\\ i t s. a. s. r I o .s. le - l 4 N l k-<-)J}!. i ).*. H .,.S.# - J i i ]fq-QR,,v M.. -. 31 L-:%22L-, y }j { f ^_' j -{ 4 -

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-g {. a i, s F " ' " P ' ' m Tr q y,,,..,:,g ; 'l i p i. 4-j ,W j i' .t j m.-- t_ J g i 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 i chall dcLorminc esi r unmpling requiremenLu. a m

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EP 205A.ll l'un e 2 o f 3, Hev. O e 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. 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. The Ik.h liquid off-gas samples for gamma isotopic analysis (Geli) may 10. ) 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

> 30% dead time may be counted but do not exceed 50% dead time.

1 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 Pag 2 3 of 3, TCv. O s i'k or equipment shall be made to minimize exposure. 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 ~ f g~...._ l e 1 C. l W 25 W 4 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 tower for Whatman 452 filters (25 mm) Cartridge purging system Supply of nitrogen (bottled) or breathing air (bottled) PRECAUTIONS: 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 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 / 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 with contact dose rates p200 mrem /hr shall be analyzed by 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. original activity on the filter can be determined by'multipling the 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. 1 50% dead time require further reduction in area. Samples

8. 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 material in a dose equivalent sample geometry (Whatman 452 filter on a card). Trt.nsfer this material to a Wnatman 452 filter with a filter tower. DC !M use water or any "~~'~~~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.

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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. this activity. An RKP shall be assigned to 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: Adjust the pressure in the off-gas vial to atmospheric pressure by a. inserting a microsyringe needle and allow the pressure to equalize. b. Evaculate a new 14.4 ml off-gas vial with septum. Determine amount of dilution required. Based on this dilution, c. determine the amount (volume) of gas to remove from the hot off-gas vial. d. 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 the dose rate of the vial to determine if additional dilution is necessary. 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. Consider the use of tongs or other remote tooling if additional sample dilution is required. 7 8. 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 between the top lead bricks may be made for the insertion of a microsyringe needle into the sample bottle. Before removing a volume gas for dilution insert a microsyringe needle into the bottle to adjust the bottle pressure i to atmospheric. The amount of sample removed and the dilution volume shall depend on the sample dose rate. Before removing a volume of gas from the via1, inject a equal amount of air to compensate for the volume removed. Mix i well before removing sample, After removing a sample close the can the Icad brici l top to reduce 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 O_ mm w--------' (v:) Page 3 cf 3, Rev. O PROCEDURE: (c5ntinu:;d) s 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 EOF:LJM Mb kW j MAY 2 31381 1 PHILADELPHIA ELECTRIC COMPANY ~ ~ bCH BOTTOM UNITS 2 A40 3 [ P ~~ 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 SECllOU li1LE V '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 PR E P A R E DN E S S IN SUPPORT OF NUCLEAR POWER PLANTS. v 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. EBECAU11U5 s 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 M MEMBER EXCEEDING PEACH BOTTOM QUARTERLY EXPOSURt LIAliS. THE INDIVIDUAL FIRE AND DAMAGE TEAM MEM6ERS SHOULO ENSURE THAT THEY CONTROL ThEIR OWN EXPOSURES IN ACCORDANCE WITH ALARA CONCEPTS. e id ED-2066 PAGE 2 t R E V. '2 v' 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 ELECTRICAL AND MECH ANIC AL M AINTENANCE PERSONNEL AVAILASLE + L/ 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 uu ! P ME N T TO e s 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 10 CFR 20 EMEnGFNCY ( ACTIVITIES Llh!TS LIM 1TS DIRECTOP m 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 1* OEV. 2 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 10 THE VISITORS. l 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 TO LEAVE THE CENTER VI A THE UNIT 1 ACCESS ROAD 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 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 5 'o o o o o i t o o 9 k g e &-l

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"l 7L ow 4 WM eu o 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 .u. e 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 -4 w q m.s, ,.y b MO we a e 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, __DAIE__ 2 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 05/25/82 4 05/25/82 LP-205A OBI A INING DRYn!L L GA% SAMPLES o? 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 05/25/02 0 05/25/82 LP-205A 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 05/25/82 0 05/25/82 LP-205A OBTAINif.G CANAL DISCHARGE WATER e6 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 OBTAIN1 FAG LIQUID RA0 WASTE SAMPLES on 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 05/26/82 * ' PEACH BOTTOM UNITS 2 AND 3 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(

REVIEW REV. REVISION TU5 Bgg 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 * ( REVIEW REV. REVISION NUBSEB lilLE __QaIE__ 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 WITH SERIOUS O 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 { EP INDEX l EMERGENCY PLCN PRO'CEDURES INDEX PAGE 5 REV. 19

PEACH BOTTOM UNITS 2 AND 3 05/26/82

l

' ( MMER \\ REVIEW REY. REVISION TITLE _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 MPbe 1 cf 8, R;v. 0 Pc

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( My ab4F. ' L }%;'?cd' ~/ 1 l l s/u/r2-2 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 all steps of this procedure, an ALARA concept is mandatory. This procedure provides evolutions for drywell gassome philosophy in pre-planning s==pling sampics during an accident. In addition to reviewing this procodurc, 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 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 ~ could reasonably occur whenhobtaining the sample. Do NOT l 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 core spray (" Triangle") room reactor building, 116' elevation. S. Torus cooling CAD cabinet - core' spray (" Triangle") room reactor Building, 116' elevation. / C. CAD cabinot, reactor building 195' (U/2 south ond, U/3 north end). 2. Determination of which cabinet the sample is to be takon from must be made. Consideration of which cabinet to be.used should be based upon plant conditions (i.e., is it stable?), which analyzers are operating, the time it will take to get there, and doso rates from area monitors in various locations, etc., approximate times and suggested routes are described: A. Core spray ("Trianglo") room - elevation. roactor building 116' 9 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 CUnit 2) or south' (Unit 3) wall of turbino 116' i elevation. Time = approx, two minutes. B. CAD on reactor building 195' olovation. Throu routos to this CAD arc suggestod: 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. l Entering recombiner building 116' elevation up the stairs up(*th stairs.4eoroceed to the stairs near reactor building olovator, an 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 technician assi to obtain samp Ls in order to y.rform area surveys. gned Brief health physics personnel on the. route to be taken and the time to get to the survey point -- Attache a appendices,are the location of the sampin points. are...,o provided. Survey maps 4 Health physics personnel shall take appropriate and protective survey equipment equipment (e.g. scsA gear 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, in general radiation levels the surveyor will note trends enroute to the sample point. If dose rates exceed 10 R/hr gamma, 10 Rad /hr beta, at the point rate remains stablespecified below and upon further invcstigationprior to arriving dose this or increases, immediately report health physics supervision. The to shall be determined prior to entry:foi, lowing radiation dose rates A. If the sample will be taken from theccore room, measure the dose rate at the watertight door located spray ("Triangic") ~ near the precoat area. If dose ratos exceed 5 R/hr at the door, leave the area immediately and report to health physics supervision with this information. v If dose ratcs aro 1 css than 5 R/hr ontor the stairwell note dose rates. in the stairwell rnd increase as the door toIf dose rates arc greator than and 5 R/hr room is the approached or if the doso rate on contact "Triang1c" door exceeds 5 R/hr, oxit immediately and with this physics report to hoalth supervision with this information. With dose rates less than 5R/hr at room, enter the area taking the door to "Triangic" Survey the room, concentrating ospecially oncareful note of the dose rates. Survey the inlet the CAD' cabinets. isolation valves line to the CAD analyzer (line with two see pictures). take a gen,eral survey.and survey the inletOpen the CAD analyzer panc1, analyzer ( \\" heat traced line with/without sampic tec - see line to the 02 pictures). Ensure that the in the " Breathing Zone" low-volume air sample is taken Survey maps and photographs .provided as part of the arc ( noto of window appendix of this procodure. Special i opon reaalings must bo inado because of submersion air dose beta fields expected. B. If the samole will be eleva' tion, measure the dose rateta".<on fram the CAD on reactor building 1958 at the door loading to tho lo :g corridor. If dose rates excoed 5 R/hr at the door, l'e' ave the, avez immediately and report [ 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 and pipes may add significantly to the whole body dose. 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 maps and photographs are provided as part of the appendix of this 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.. This procedure shall be dry run at least throc timos before actual sample 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 tee has been installed continuo 'with stop 7.B. Install a sampling tee 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 into the 02 analyzer and install sampling too. Soc figure HPO/CO-121-1. 3. Reconnect tubing and return tho 02 analyzcr to survice. '\\. After 02 readi. w 4 ( ng's have stabilized, obtain a sample with section 7.B. e

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- - - ~ - - - - ' ~ ~ -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. Tako off gas a 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 be handled in a manner such that it will causo an ALARA whole body dose to personnel 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.

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

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(q (] EP 205A.4 I [ *Page 1 cf 5, Mev, o MPGatth I _ _- f .ii-l =< 2 s p 'C , y, &(rw - ii I (....__..'. -- - 8 r. PHILADELPHIA ELECTRIC COMPANY PEACH BOTIOM UNITS 2 & 3 EP 205A.4' o'BTAINING DRYWELL GAS SAMPLES FROM THE DRY!* ELL RADIATION MONITOR SAMPLING STATION / PURPOSE: The purpose of this procedure is to provide some guidelines for consideration prior to, during and after obtaining a drywell gas sample following accident conditions with major fuel damage. APPARATUS: ( Appropriate Health Physics survey equipment Air sampler (low volume) Respiratory protective equipment Anti-C clothing Digital - alarming dosimeter 14.4 nl off-gas vial with septums O-1 m1 microsyringe Septum valve Sample tee with valve P_RECAUTIONS: A. In all steps of this procedure, an ALARA concept is mandatory. ' Itis procedure provides some philosophy in pre-planning sampling evolutions for drywell gas samples during an accident. In addition to revievring this procedure, an ALARA review of the sampling process should be perforTued 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 of body dose) be exceeded during the surveying for sampling or obtaining the sample. If it appears that an overexposure cculd reasonably occur when obtaining the sample, do'not proceed without written NRC approval. ( l l L w ~ -~=m ~ w. w.. -'w,m. m.. n _ _ _ _
i "f (O EP 205A.4 L/ P ge 2 cf 5, Rev. PROCEDURE: 1. It has been dete m ined that a drywell gas sample is required. The location to obtain the gas sample is at the drywell rad. Monitor located on the 135' elevation of the Reactor Building. (North end of both Units near accumulators). s ~ 2., Area Radiation Monitors shall be checked and if monitors in the area of the Drywell Rad. Monitor are indicating greater than 10 R/hr, obtaining the sample should very possibly not be considered. 3; Have a health physics technician accoutpany the chemistry technician assigned to obtain samples in order to perform area surveys. Brief Health Physics pe~sonnel on the route to be taken and the time to get to the survey point. Attached as Appendices are the location of the samnle point. NOTE: 1. The time to travel from the 116' elevation entrance to A the Turbine Building to the Drywell Rad. Monitor is approximately 4 minutes. 2. Other routes may be considered. The travel times expected for these routes would be 4 minutes, as well. ( Health Physics personnel shall take appropriate survey and protective 4. equipment (e.g. SCBA, Anti-Cs, lead carrying container, etc.) Prior to 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 arriving l at the door leading to RX-135 and upon further investigation, this dose rate remains stable or increases, exit immediately and report to Health Physics supervision. If dose rates exceed 5 R/hr at the door leading to PX-135, leave the area immediately and report to Health Physics supervision. 6. Survey the area concentrating especially on the sample lines and sample point located at the Drywell Rad. Monitor. Ensure that a low volume air sample is taken (in the " Breathing Zone"). Special note of window open readings must be riade because of submersion air dose beta fields. e G. ( -. - : ~ <w /
.v (d -. n - e s 1 e 2 V EP 2,05A.4 .j Pace.~3 cf 5, Rev. C NOTE: (- It will take approximately 4 minutes to sample to obtain a sample with a sample tee and approximately 10 minutes without a sample tee. 7 Suqqested Sampling Method -(This procedure may be changed based on the ALARA review). At least 2 dry runs of the sampling method shall be performed before the actual sampling. Based on these dry runs and ALARA review appropriate changes"shall be made. A. Install sampling tee (if not present) by the following: (1) Place monitor in purge. (2) Remove gas injection tee from in front of the gas monitor (n:iddle lead pig).. See photos in the Appendix. (3) Install sample tee and verify the sa$nple valve is closed. (4) Return monitor to normal operation allow readings to stabilize before sampling. B. Obtain a sample by the following method: k (1) Verify the sample valve is closed. (2) Re1N.s the pipe plug fro.n the sample valve (see figure HPO/CO 125-1). (3) Install the septum valve with a 1/4" to 1/8" reducer into the sample valve. (4) Open the sample valve. (5) Open ths septum valva. (6) Install the microsyringe needle through the septum wLive and sample valve into the sample tee. (7) Flush the nicrosyringe by taking a 0.1 m1 sample .and returning the sample to the sample tee by pressing the plunger twice. (8) Obtain a 0.1 m1 sample from the sample in the microsyringe and remove the needle from the sample tee. (9) Close the sample valve and the septum valve. (10) Plac N e 0.1 ml sample into a evacuated 4.4 al { off-gas vial. (11) Exit the area with the off-gas vial. e v-w
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i O 7/ !.~ \\ ~ rJ, - 2os^ 4 Pag) 4 of 5, Rev. O J l 84 Consideration of expected dose rates from the sample, itself, must also be made. Review survey data for the sample inlet line as com-(_ pared to general field for approximation of sample dose. ~ 9 If the samples is too " hot" for gamma spectroscopy, it will be brought to the hot lab to await final disposition. Any shieldina, remote handling, devices or other protective measure shall be in place and ready to accept the samples prior to its arrival. 10. After the sample is properly stored, responsible supervision shall discuss and decide upon final disposition. 11. If the sample is able to be analyzed for gamma spectroscopy, the sample shall be processed in a manner such that the detector does not become contaminated. 12 - Following final analysis of the sample, results shall be reported to appropriate supervision. O e G S 9 e he 9 ( a M Q % M Mw ' M ~
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EP 205A.6 < C' ~ ~ ' ~ Pag 3 1 cf 2, Rev. 0 N'4 MPGatth f /Id? c_ yy#w ~ ~ ~ ' ~ ' ' PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 AND 3 EP 205A.6 OBTAINING CANAL DISCHARGE WATER SAMPLES FOLLOWING RADIOACTIVE LIQUID RELEASES AFTER ACCIDENT CONDITIONS PURPOSE: The purpose of this procedure is to provide some guidelines to obtain canal discharge water samples following radioactive liquid releases after accident conditions. APPARATUS: Appropriate Health Physics survey equipment i liter samplo bottle with lid plastic bags ( tape PROCEDURE: 1. As soon as possible after a radioactive liquid release (either planned or accidental) following accident conditions, a grab samplo can be taken. Also daily composite samples can be taken following accident conditions. 2. To take a grab sample of canal dischargo water, two locations are usod: A. Tako the samplo from the chlorino analyzer samplo pump dischargo located in the gate control shack at the end of the canal. B. An alternate location would be to take the sample directly from canal by a dip sample. 3. To take a daily canal discharge composite sample: A. The composite canal discharge tank is located in the gate control shack at the end of the canal. l B. Turn on the mixer in the tank to mix the liquid in the tank. t C. Take a dip samplo from this tank. D. Drain the tank to reset the daily canal discharge composite samplo. l 1
EP 205A.6 1>aga 2 of 2, 1(cv. 0 E. Plush the tank with the water hose to clean it out. F. Make sure the drain is closed and verify that an appropriate sample flow is entoring the tank from the composito samplo pump. 4. Take the samples (canal discharge and/or canal composite discharge) to the appropriate counting room to scan for activity. G I I 1 t 1 1 i l 8 .}}

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