ML20133H226
| ML20133H226 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/18/1985 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20133H225 | List: |
| References | |
| PROC-850918-01, NUDOCS 8510160319 | |
| Download: ML20133H226 (375) | |
Text
- <
' ' +
- , EP Index
- %g ' JMERGENCY PLAN PPOCEDURES INDEX Page 1
, % Rev. 53 *
. PEACH BOritM INITS 2 AND 3 09/18/85
- I
' ('
Review Rev. Revision Number Title Date No. Date -
r
- EP-101 Classificatica of Emergencies 09/13/85 14 09/13/85
- l EP-102 Unusual Event Rescanse 09/13/85 11 09/13/85
- l EP-105 General Emergency Response 06/14/85 11 06/14/85 EP-110 Personnel Assembly and Accountability 06/20/83 1 06/20/83 EP-201 Technical Support Center (TSC)
Activatim 10/12/84 7 10/12/84 EP-202 Operations Support Center (OSC)
Activation 01/23/85 7 01/23/85 4
EP-203 Bnergency Operations Facility (ET)
Activation 10/12/84 7 10/12/84
( EP-203A Alternate Emergency Operations Facility (ET) Activatim 10/12/84 0 10/12/84 EP-205 DELETED 09/12/84 EP-205A Chemistry Sanpling and Analysis Group 09/18/84 5 09/18/84 EP-205A Operation of Post Accident Sampling 4
.1 Station 09/20/84 5 09/20/84 EP-205A Obtaining Drywell Gas Smuples
.2 fra Contairunent Atnosphere Dilution Cabinets 05/26/E2 0 05/26/02 EP-205A Retrieving and Changing Sample
.3 , Filters and Cartridges fra the
! Drywell Radiation Monitor During
- Emergencies- 04/25/83 1 04/25/83 l
EP-205A Obtaining Drywell Gas Samples il .4 fr a the Drywell Radiation Monitor l' Sangling Station 05/25/82 0 05/25/82
, EP-205A Obtaining Reactor Water Sanples
- .5 fra Sanple Sinks Following Accident e l Canditions 05/25/82 0 05/25/82 EP-205A Obtaining Canal Discharge Water t
8510160319 850926
- . . . - - . . . ,~.n,_... - - -.
L_ m
.EP Index l
DERGENCY PIAN PROCEDURES INEEX Page 2
- Rev. 53
- i PEACH BOFIm IMI'IS 2 AND 3 09/18/95
- J Review Rev. Revision Nttrber Title Date No. Date l
.6 Samples Following Radioactive Liquid Releases After Accident Conditions 05/25/82 0 05/25/82 ;
EP-205A Obtaining the Iodine and Particulate
.7 Sanples frm the Main Stack and Roof Vents Following Accident Conditions 11/21/83 2 11/21/83 EP-205A Obtaining Liquid Radwaste Samples
.8 frca Radwaste Suple Sink Following Accident Conditions 05/25/82 0 05/25/82 EP-205A Obtaining Sanples from Condensate
.9 Sanple Sink Following Accident Canditions 05/25/82 0 05/25/82 EP-205A Obtaining Off-Gas Sanples fran
.10 the Off-Gas Hydrogen Analyzer Following Accident Conditions 05/25/82 0 05/25/82 EP-205A Sample Preparation and Handling
.11 of Highly Radioactive Liquid Sanples 02/29/84 2 02/29/84
[~ EP-205A Sample Preparation and Handling
.12 of Highly Radioactive Particulate Filters and Iodine Cartridges 01/10/84 3 01/10/84 EP-205A Sample Preparation and Handling of
.13 Highly Radioactive Gas Sanples 02/29/84 2 02/29/84 -
EP-205A Offsite Analysis of High Activity
.14 Sanples 11/23/83 0 11/23/83 EP-205A Guidelines for the Order of
.15 Analysis on Post-Accident Sanples 02/29/84 0 02/29/84 EP-205A Storage of Post-Accident
.16 Sanples 09/12/85 0 09/12/85
- EP-206B Damage Repair Group 05/31/83 3 05/31/83 I. EP-207 Personnel Safety Team Activation 09/20/84 6 09/20/84 s -
. e = = :- = -- -
EP Index DERGENCY PUC4 PROCEDURES INDEX Page 3 J} '
i
, Rev. 53
- PEACH B0r1TM LNITS 2 AND 3 09/18/85
- Review Rev. Revision
( Ntaber Title Date No. Date EP-207A Search and Rescue - 07/31/85 4 07/31/85 EP-207B DELETED 04/27/84 i' EP-207C DELETED 06/26/85 EP-207D Evacuation Assembly Group 09/16/85 4 09/16/85
- i EP-207E DELETED 08/28/85
- EP-207F DELETED 08/28/85
- q EP-207G Plant Survey Groups 09/09/85 0 09/09/85
- EP-207H Dosimetry, Bioassay, and Respiratory Group 09/16/85 0 09/16/85
- EP-208 Security Team 05/31/83 1 05/31/83 1 EP-209 Telephone List For Emergency Use 05/20/85 10 06/11/85 EP-209 Imediate Notification Call List Appendix A h[ 09/16/85 10 09/16/85
Appendix C -
09/16/85 17 09/16/85 *
, EP-209 On Site Emergency Team Leaders Appendix D-1 09/14/85 13 09/14/85
- Appendix D-3 09/14/85 15 09/14/85
- 1 1
EP-209 Personnel Safety Team Appendix D-4 09/14/85 18 09/14/85 *
- EP-209 Security Team Appendix D-5 09/14/85 13 09/14/85
- E?-209 naH:ntry and Recovery Tean Appendix D-6 09/04/85 4 01/11/85 EP-209 Technical Support Center Group Appendix D-7 09/16/85 17 09/16/85
- t . _. . _ . _
l
- EP Index I i
, DIERGENCY PLAN PROCEDURES INDEX Page 4
. Rev. 53
- PEACH BorKM UNITS 2 AND 3 09/18/85
- I Review Rev. Revision
( Niznber Title Date No. Date l EP-209 Chemistry Sampling & Analysis Team 09/16/85 3 09/16/85
- l Appendix D-8 EP-209 Corporate Emergency Team Leaders and Appendix E Support Personnel 09/16/85 14 09/16/85
- EP-209 U. S. Government Agencies Appendix F 05/20/85 5 06/24/83 i
EP-209 Emergency Management Agencies L Appendix G 09/15/85 7 09/16/85
- EP-209 Ccupany Consultants Appendix H 09/14/85 12 09/14/85
- EP-209 Field Support Personnel Appendix I-l 09/14/85 18 09/14/85
- EP-209 Chenistry & Health Physics Contractor 4
Appendix I-2 Call List 09/16/85 17 09/16/85 *
( EP-209 Nearby Public and Industrial Users Appendix J Of Downstream Waters 09/04/85 7 05/03/85 EP-209 Miscellaneous .
Appendix K 09/16/85 7 09/16/85
- EP-209 Imcal PECo Phones _
Appendix L 09/04/85 6 01/11/85
! EP-209 DELETED 10/21/84 1
Appendix M i EP-209 Medical Support Groups Appendix N 09/04/85 9 06/14/85 EP-209 Staffing Augmentation - 60 Minute Appendix P Call Procedure 09/04/85 12 06/12/85 -
EP-210 Dose Assessment Teen 09/18/84 1 09/18/84 l
l EP-210A Field Survey Groups 09/09/85 0 09/09/85 *
[ EP-211 Emergency Radiation W ye i Guidelines and Controls 06/28/85 0 06/28/85 EP-212 Technical Support Team Activation 0 09/09/85 *
( 09/09/85 EP-301 operating the Evacuation Alarm and '
EP Ind;x
, DER 2NCY PIAN PROCEDURES INDEX Page 5
. Rev. 53 *
{ PEACH DCTPICM UNITS 2 AND 3 09/18/85 *
. Review Rev. Revision -
( Number Title Date No. Date ,
Pond Page System 09/09/85 2 09/09/85
- EP-303 Partial Plant Evacuation 08/30/85 3 08/30/83
- EP-304 DELETED 12/04/81 EP-305 Site Evacuation 06/21/83 5 06/21/83 EP-306 Evacuation of the Information Center 05/25/82 2 05/25/82 EP-307 Reception and Orientation of Support Perscenel 09/16/85 2 09/16/85
- EP-311 C mtaminated Injury 06/28/85 4 06/28/85 i EP-312 Radioactive Liquid Release (Emergency Director Functions) 09/20/84 2 09/20/84 EP-313 Control of Thyroid Blocking (KI)
Tablets 09/12/85 2 09/12/85
- EP-315 Corporate Ccaputer Dose Calculations 10/12/84 0 10/12/84 EP-316 Cisnulative Population Dose Calculations for Airbourne Releases Manual Method 09/17/85 7 09/17/85
- EP-316 Worksheets/ Meterological Calculations Appendix A 09/17/85 8 09/17/85
- EP-316 Activity After Reactor Shutdown Appendix B 09/17/85 7 09/17/85
- EP-316 Index of X/Q Outputs for Off-Gas Appendix C Stack Releases 09/17/85 7 09/17/85
- EP-316 Relative Dispersion Values for Emer-Appendix D gency Dose Calculation Procedure 09/17/85 7 09/17/85
- EP-316 SGIS Efficiency vs Decontamination Appendix E Factor 09/17/85 7 09/17/85
- EP-316 Percent Ccupesition of Isotopic Appendix F Distribution 09/17/85 7 09/17/85
- EP-316 Cmposite Whole Body Dose Appendix G Conversion Factors vs Time Since Reactor Shutdown 7 09/17/85
- 09/17/85 EP-316 I-13'l/I-133 Conposite Thyroid Dose -
EP Index '
, , ENERGD3CY PLAN PROCEDUIES INDEX Page 6 Rev. 53
- PFAG BOFICM UNITS 2 AND 3 09/18/85
- Review Rev. Revision Number Title Date No. Date
( ;
Appendix H Conversian Factors vs Time Since Reactor Shutdown 09/17/85 7 09/17/85
- EP-316 Population Distribution by Cam ===
Appendix I Sector-Sununer Day 09/17/85 0 09/17/85
- EP-316 I/D1/I-133 Percent Abundance vs Appendix J Time Since Reactor Shutdown 09/17/85 0 09/17/85
- J EP-316 Index of Plume Shine outputs Appendix L for Off-Gas Stack Releases 09/17/85 0 09/17/85
- Ep-316 Pitzne Shine value for Emergency Appendix M Dose Calculation Procedure 09/17/85 0 09/17/85
- EP-316 Refined Dose Assessment of Appendix N Urunanitored Ground Release 09/17/85 0 09/17/85
- EP-316A Reading the Rapid Dose Assess-
{ ment I Program into the TI-59 10/03/84 1 10/03/84 i EP-316B Calculating Rapid Dose Assessment on the TI-59 10/03/84 1 10/03/84 EP-316C Reading the Refine Dose Assessment I Program onto the TI-59 -
10/15/84 0 10/15/84 -
! EP-317 Direct Reccmnendations to County i Emergency Management and civil Defense Agencies 10/12/84 3 10/12/84 EP-318 L'iquid Release Dose Calmlation Method for Intake Water at l Downstream Facilities 04/D/83 1 04/13/83 EP-319 Liquid Release Dese enlmlation
- 4ethod for Fish 04/D/83 1 04/U/83 EP-320 Procedure for Leaking Chlorine 03/12/82 1 03/12/82 EP-325 Use of the Containment Radiation M' o nitor to Estimate Release Source Term 06/09/82 0 06/09/82
,e EP-401 Entry for Emergency Repair and .
l l. Operations 09/15/84 5 09/15/84 l
-. ... .. - . . - - . . . . - - . . - - . . - ~ . . - . -
- ---na--m,e .-- . - --,,-,-r,- - - .
EP Index
',. ENERECl PIAN PN INDEX Page 7
- Rev. 53
- PEACH BOITCH UNITS 2 AND 3 09/18/85
- Review Rev. Revision
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Nh Title Date No. Date L EP-500 Review and Revision of Emergency Plan (FSAR Appendix 0) 04/01/81 0 04/01/81 P
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s Paach Bottom Atomic Powar Station Niccf MD i i Delta, Pennsylvania l 17314 ${p201985.'
TO: dpht? - [autaruff; fA24f/tggg DATE: [ f /WI f {_ i
SUBJECT:
PRO NDURE Ag,LETIONS
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.,. - N The following procedures have been deleted. Please remove them from your procedure books:
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 AND 3 u fM~
EMERGENCY PLAN IMPLEMENTING PROCEDURE ggg7ggLLg APPROM @@
101D PREVIOUS ISSUI EP-lOl CLASSIFICATION OF EMERGENCIES pistg130 TION PER A-S i PURPOSE:
i To define the method of classification of an event or condition into one of four emergency classifications as described in the Emergency Plan.
Additionally this procedure details the method of de-escalation from one emergency action level to another.
REFERENCES:
- 1. Peach Bottom Atomic Power Station Emergency Plan
- 2. NUREG 0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
- 3. EP-lO2, Unusual avent Immed1..c. Actions
- 4. EP-103, Altrt Immediate Actions
( 5. EP-lO4, Site Emergency Inunediate Actions
- 6. EP-1d5, General Emergency Immediate Actions ACTION LEVEL:
Implemented this procedure whenever Shift Supervision detects conditions which meet the Emergency Action Levels in Appendix EP 101, Classification Table.
I IMPLEMENTATION OF THIS PROCEDURE DCES NOT CONSTITUTE i IMPLEMENTATION OF THE EMERGENCY PLAN.
PRECAUTIONS:
i THE JUDGEMENT OF THE EMERGENCY DIRECTOR IS VITAL IN PROPER CONTROL OF AN EMERGENCY AND TAKES PRECEDENCE OVER GUIDANCE IN THE EMERGENCY PLAN PROCEDURE.
l-IMMEDIATE ACTIONS:
1.0 Shift Supervision or Emergency Director shall:
l.1 Select affected categories related to station events
[ , or conditions.
l5 li li
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-) EP-101 I' < Ptg2 2 of 3, Rev. 14
?!
( IMMEDIATE ACTIONS (cont'd)
, , Reference
.[ Pages in Appendix
'* Category EP-lOl Unplanned Shutdown 1 Personnel Injury 2 Primary Containment
-j Integrity 3 Radioactive Material Release 4 Fire 5 Environmental 6
! Loss of Power 7 Secondary Containment 8
( Instrument Failure 9 Fuel Damage 10 Hazards to Station l Operation '
11 1
- Control Room Evacuation 12
! Security See contingency Plan 1.2 Beginning at the indicated page in Appendix EP 101, review the Emergency Action Levels for all categories selected.
1.3 If the most severe events or conditions are classified as an Unusual Event, implement EP 102, " Unusual Event Response."
1.4 If the most severe events or conditions are classified as p an Alert, implement EP 103, " Alert Isumediate Response."
t;
', 1.5 If the most severe events or conditions are classified as
'; a Site Emergency, implement EP 104, " Site Emergency Response."
, r 1.4 If the most severe events or conditions are classified as a k General Emergency, implement EP 105, " General Emergency Response."
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,EP-101 I
- T 4
Pigs 3 of 3, R3v. < 14 -
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FOLLOW-UP ACTIONS
(
- 1.0 If event is classified as Alert, Site Emergency, or General Emergency, Shift Supervision or Emergency Director shall:
1.1 Periodically evaluate the event classification as listed on attached Appendix EP-101. Based upon results of corrective l 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 Interis Emergency Director. (It is preferable, but not mandatory, to obtain concurrence from the site Emergency Coordinator and ]
Corporate Headquarters prior to classification reduction). The NBC and appropriate off-site authorities at the Emergency operations Facility all be informed of the decision to move from one emergency class to the next. All agencies or personnel listed in checkoff lists of EP's 102, 103, 104, and 105 shall be informed as a minianna.
l 1.2 Provide written sununary within eight hours to the NRC concerning
- basis and circumstances surrounding reduction of amargency action level or closeout of the emergency.
. 2.0 If event is classified as an Unusual Event, Shift Supervision or Emergency Director shall periodically evaluate the event classifi-cation as listed on attached Appendix EP-101 and escalate or de-i
[ escalate the emergency action level if necessary. All appropriate agencies or personnel shall be notified using the appropriate check-
- off lists of EP-102, 103, 104, 105.
3.0 When the emergency has been mitigated and the power plant and auxiliaries
! have been placed in a safe (Jiutdown condition, only.then will a decision l be made as to whether a recovery phase is justified. To enter the
- l recovery phase after the emergency or accident situation is considered
- I no longer in effect, the concurrence of the site Emergency.
l Coordinator, Emergency Director, the Emergency Control Officer at i Corporate Headquarters, and Federal and State Government Liaison is required. The recovery phase is'a departure from an emergency situation. The Site Emergency Coordinator and Emergency Director evaluates plant operating conditions as well as tb3 in-plant and l
out-of-plant radiological con.iitions in this decision. Notifications l + to the various individuals and agencies that the recovery phase has been implemented is the responsibility of the Site Emergency coordinator.
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- APPENDIX EP-101 peg 2 1 of 12, R:v. "11 I
I UNPLANNED SHUTDOWN UNUSUAL EVENT ALERT
{
UNPLANNED SliUTDOWN .
SCRAM WITH TRIPLE g LEVEL
- 1) controlled shutdown due to failure 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 less than 2 psig on PR-2/3508 SCRAM WITH SMALL LEAK
. 1) scram alarm and
- 2) double low level alarm (-48") and
- 3) triple low level alarm (-130") and
- 4) containment high pressure alarm g (2 psig) and
- 5) containment pressure 2 psig or greater on PR 2/3508 SITE E. M CY GENERAL EMERGENCY SCRAM WITH IOCA SCRAM WITH LOCA,& NO ECCS
- 2) double low level alarm (-48") and 2) . double low level alarm (-48") and
- 3) triple low level alarm (-130") and 3) triple low level alarm (-130") and
- 4) containment high pressure alarm 4) active fuel range level indication (2 psig) and shows less-than -226" on LI-2/3 Sa)' containment pressure 10 psig or 3-91A, B and greater on PR 2/3508 g 5) failure to reset triple low level Sb) containment dose rate greater than alarm after 3 minutes and 105 R/hr on RI-8/9103A/C and 6) containment high pressure alarm RI-8/9103B/D (2psig) and
,7) containment pressure greater than j 20 psig on PR-2/3508 or l
- 8) containment dose rate greater than 106 R/hr on RI-8/9103A/C and .
RI-8/9103 B/D .
APPENDIX EP-101
- , Pag 3 2 of 12, Rev. 14 4
PERSONNEL INJURY ,
( UNUSUAL EVENT ALERT d
N/A INJURY WITli EXCESS RADIATION EXPOSURE OR CONTAMINATION
- 1) Contaminated injury warranting off-e site :nedical treatment og
. . 2) an acute whole body exposure i greater than 3 R t
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APPENDIX EP-101 i
Pag 3 3 of 12, Rev.,14 PRIMARY CONTAINMENT NON-ISOLABLE LEAKAGE : LOSS OF PRIMARY CONTAINMENT INTEGRITY
- 1) Primary containment leakrate 1) Reactor Building vent rad effluent is greater than 0.5 percent of high rad alarm and inability to volume per 24 hrs. at 49.1 psig o maintain pressure 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 flood alarm with level decrease in torus FAILURE 'IO ISOLATE PENETRATION WHEN ISOLATED BY A TRANSIENT
- 1) incorrect valve position during Group I, II, or III isolation alarms SITE E. M CY GENERAL EMERGENCY LOSS OF PRIMARY CONTAINMENT INTEGRITY WITH LOCA .
- 1) erratic containment pressure N/A
. fluctuations above alarm setpoints of 1.5 psig, and
- 2) Group II and III isolation alarms, and
- 3) Containment dose rate greater than 105 R/hr on RI-8/9103A/C and RI-8/9103B/D and g
- 4) Reactor Building area high temper- g to s P 2 8 88 0 "
N abnormally high, and Reactor Bldg.
vent rad effluent high alarm, or 1) containment high pressure alarm.
Main Stack Rad effluent on PR 0 (2.0 psig), and
,_ 051 increasing due to SGTS opera- 2) scram, and tion. 3) containment dose rate greater than
(. 105 R/hr on RI-8/9103A/C and RI-8/
9103B/D, and
- 4) Reactor BTatf Area Kad Monitors Alarming, and
- 5) Vent Stack Rad Effluent monitor high alarm
.'..----.,2..
\ APPENDIX EP-101 PIq3 4 of 12, Rsv. 1 RADIOACTIVE RELE ASE ALERT
( UNUSUAL EVENT INSTANTANEOU3 RELEASE EXCEEDING TECH ACTUAL OR POTENTIAL RELEASE 0.01 REM SPECS , WHOLE BODY OR O.05 REM THYROID
- 1) Liquid effluent release exceedin9 1) Uncontro.llable release for more than Tech. Spec. 3.8.B.1 '20 minutes from the
- 2) Gaseous effluent release exceeding al main stack greater than 1.0 x 10 5 Tech. Spec. 3.8.C.l'which may be cps on RR- 0-17-051 -or detected by the following:
- b. Reactorgldgventgreaterthan
- a. If all releases are from one 6.0 x 10 cpm on RR-2/3979 g l release point.
- 2) Continued particulate or iodine re-
- 1. A spike on the main stack greater lease such that analysis of particu-than 1.8 x 104 eps on late filter or charcoal cartridge RR-0-17-051 E results in the following estimated
- 2. A spike on the reactor bldg. re ease rates vent greater than 3 x 105 cpm a. main stack greater than 9.7 x 10 t
on RR-2/3979 or uCi/sec or I b. If the release is from more than one release point b. Reactor Bldg vent greater than 1.1 x 102 uCi/sec or
- 1. A spike on the main stack greater than 6 x 103 cps on RR-0-17-051 3) Containment dose rate greater than or 104 R/hr on RI-8/9103 A/C and f 2. A spike on the reactor bldg. RI-8/9103 B/D.
( vent greater than 1 x 105 cpm on RR-2/3979.
SITE EMERGENCY M ERAL M R M W ACTUAL OR POTENTIAL RELEASE 0.1 REM ACTUAL OR POTENTIAL RELEASE 1.0 REM WHOLE BODY OR 0.5 REM THYROID WHOLE BODY OR 5.0 REM THYROID I 1) Uncontrollable release for more than 20 minutes from the 1) Uncontrollable release for more than 20 minutes from ther
- a. main stack greater than 2.0 x 10 8 cps on RR-7127 or a. main stack greater than 2 x 10 9 on RR-7127 or
- b. Reactor Bldg. vent greater than f 6 x 106 cpm on RR-2/3979 or- b. Reactor : Bldg vent greater than 6 x 107 cpm on RR 2/3979 or-
- 2) Continued particulate or iodine re-lease such than analysis of particu- 2) Continued particulate or iodine re-
~
1 ate filter or charcoal cartridge lease such than analysis of particu-results in the following estimated
~
late filter or charcoal cartridge release rates: results in the following estimated release rates:
- a. main stack greater than 9.7 x 103
- a. main stack greater than 9.7 x 104 uCi/see or- uCi/sec or b.
g Reactor Bldg vent greater than
( l b. Reactor Bldg vent greater than 1.1 x 103 uCi/see or- '
1.1 x 104 uCi/sse or 1 3) Containment dose rate greater than 105 R/hr on RI-8/9103A/C and ) ogtainment dose rate greater than RI-8/9103B/D RI-8/9103B/D l u._ .
APPENDIX EP-101
. - Ptg3 5 of 12, R;v. 14 FIRE UNUSUAL EVENT ALERT FIRE IN PROTECTED AREA LASTINd 10 MIN. FIRE WHICH COULD MAKE AN ECCS INOP OR MORE AFTER INITIAL ATTEMPTS TO EXTINGUISH IT 1) Fire alarm and verbal report from SSV
- 1) Alarm and verbal report from SSV
(-
SITE EMERGENCY GENERAL EMERGENCY FIRE WHICH MAKES AN ECCS INOP FIRE WHICH CAUSES DAMAGE TO PLANT SYSTEMS SUFFICIENT TO LEAD TO OTHER GENERAL .
- 1) Fire alarm and verbal report EMERGENCIES from SSV ,
, 1) Fire alarm and verbal report from SSV, and LOCA symptoms, ECCS, or containment failure I ,-
i
AirEdDIX EP-101
, Pig 2 6 of 12, R v.14 ENVIRONMENTAL l UNUSUAL EVENT ALERT EARTHQUAKE , EARTHQUAKE
- 1) An actual earthquake detected by 1) An actual earthquake beyond the seismic instrumentation systems Operating Basis Earthquake (OBE)
ABNORMAL POND LEVEL ABNORMAL POND LEVEL
- 1) Conowingo Pond level on LI-2/3278A, 1) Conowingo Pond level on LI-2/3278A,B, B,C: C:
a) greater than 113 feet or a) greater than 115 feet or b) less than 104 feet without prior b) less than 98.5 feet without prior notification by L.D. notification by L.D.
TORNADO TORNADO
- 1) A tornado is observed on site 1) A tornado strikes the Power Block with identifiablet plant damage -
HURRICANE HURRICANE
- 1) Hurricane is expected to cross 1) Station is experiencing a hurricane the station with winds greater than 100 mph SITE EMERGENCY GENERAL E. M ENCY EARTHQUAKE
- 1) An-earthquake greater than Design Earthquake as detected on seismic
, instruments ABNORMAL POND LEVEL
- 1) Conowingo Pond level on LI-2/3278A,B,C exceeding the following limits:
a) greater than 116 feet or b) less than 87 feet eew . = e .am--s-e.e-~e- -w.-**%.. .w-... = , .....,.w.- .. .
APPENDIX EP-101
. Paga 7 of 12, Rav.14 LOSS OF POWER
{ UNUSUAL EVENT ALERT LOSS OF OFFSITE OR ONSITE; LOSS OF OFFSITE AND ONSITE AC POWER FOR POhTR -
LESS THAN 15 MINUTES
- 1) turbine generator trip with Startup 1) turbine generator trip with Startup Auxiliary transformer SU2 and SU3 Auxiliary transformer SU2 and SU3 unavailable for service for more unavailable for service and than 60 seconds or 2) failure of all diesel generators to
- 2) loss of voltage on the four 4160 energize their busses, volt emergency busses or 480 volt load centers supplied from the four LOSS OF ALL DC POWER FOR LESS THAN 15 MIN.
4160 volt emergency busses for more
, than 60 seconds. 1) less than 105 volts on the 2/3A,B,C
& D distribution panels as indicated on Panels 2/3AD03, 2/3CD03, 2/3BD03, 2/3DD03 and
- 2) less than 21 volts on the 24 volt distribution panels as indicated on Panels 2/3AD28, 2/3CD28, 2/3BD28, 2/3DD28 and
- 3) loss of all alarms
(
SITE EMERGENCY GENERAL EMERGENCY LOSS OF OFFSITE AND ONSITE AC POWER FOR LOhGER 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 II)NGER THAN 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.
l l
' l APPENDIX EP-lOl
,- Ptga 8 of 12, Rev. 14 SECONDARY CONTAINMENT UNUSUAL EVENT ALERT l
LOSS OF SECONDARY CONTAINMENT HITEGRITY
- 1) loss of secondary containment integrity for greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> N/A SITE EMERGENCY GENERAL EMERGENCY N/A N/A e
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- APPENDIX EP-lOl Paga 9 of 12, R3v.,14 INSTRUMENT FAILURE UNUSUAL EVENT ALERT SIGNIFICANT IDSS OF ASSESSMENT OR COM-MUNICATION CAPABILITY IN THE MAIN CONTROL ROOM
- 1) complete loss of all Main Control Room communication equipment N/A e
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O e SITE EMERGENCY GENERAL EMERGENCY e
6 N/A N/A e
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_ - - - - - _ - - - __ _ _g y - --
APPENDIX EP-101 Pega 10 of 12, Rev. 14 i
FUEL DAMAGE '
UNUSUAL EVENT ALERT POSSIBLE FUEL DAMAGE FUEL DAMAGE
- 1) Air ejector discha*ge rad monitor 1) Air ejector discharge rad monitor high alarm and an increase of 500mk/ indicating greater than 2.5 x lO 4mR/
hr within 30 minutes or a level of hr on RR 2/3-17-152, or
! 2.5 x 103 mR/hr as in Ecated on 2) High coolant activity 7 f 300 uCi/gm RR-2/3-17-152, g dose equivalent I-131, and main steam
- 2) high reactor coolant activity as line high-high radiation alarm with determined by sample analysis equal resultant scram alarm, or to or greater than 2 uCi/gm dose 3) spent fuel damage resulting in a aquivalent I-131 refueling floor area radiation monitor
. alarm or a high radiatien alarm on refuel floor exhaust rad monitor
~
SITE EMERGENCY GENERAL EMERGENCY FUEL DAMAGE FUEL DAMAGE
- 1) Following conditions occur 1) When at least 2 of 4 containment rad a) failure of control rods to fully monitors indicate levels greater
) -
insert on a scram and than 106 R/hr on RI-8/9103A/C and
! b) higher than normal readings on RI-8/9103B/D and containment pressure LPRMs adjacent to not-fully- exceeds 10 psig on PR 2/3508 inserted rods and c) at least 2 of the 4 con *=4n= ant rad monitors indicate levels greater than 105 R/hr on' RI-8/9103A/C and RI-8/9103B/D.
- 2) Major damage to spent fuel in fuel pool or uncovering of spent fuel as confirmed by a fuel pool area radiation monitor alarm and: .
a) refuel floor exhaust radiation monitor high alarm, or b) refuel floor area radiation
('
i monitor alarm or j
!1 3) observed major da Ege to spent fuel ;
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APPENDIX EP-lOl PEga 11 of 12, R3v.14 HAZARDS
[ UNUSUAL EVENT ALERT .
MODERATE HAZARDS 'E SEVERE HAZARDS
- 1) Aircraft crash on or near site 1) Aircraft crash on the facility or as determined by shift Supervision missile impacts into the Reactor or r Bldg. Diesel Generator Bldg. or
- 2) Significant explosion on or near HPSW pump structure as determined site as determined by shift by Shift Supervision or Supervision or 2) Explosion damage to facility affecting
- 3) Toxic gas release on or near site plant safety as determined by Shift as determined by shift Supervision Supervision o_rr
- 3) Chlorine gas detected in the Control Room 4
SITE EMERGENCY GENERAL EMERGENCY l
APPENDIX EP-101
,}
Paga 12 of 12, R;v.,14 CONTROL ROOM EVACU ATION
( UNUSUAL EVENT ALERT
, REMOTE CONTROL ESTABLISHED
- 1) Evacuation of Main Control Room anticipated or required and control established at remote shutdown panels as determined by Shift Supervision
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SITE EMERGENCY GENERAL EMERGENCY REMOTE CONTROL NOT ESTABLISHED
- 1) Evacuation of Main Control Room and control of shutdown systems not established at remote shutdown panels in 15 minutes as determined N/A by Shift Supervision 37 s
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EP-102 Page 1 of 7, Rev.11 JJT:clg A
f/f 5 PHIIADELPHIA ELECTRIC COMPANY PEAG BOFIm WITS 2 AND 3 CONTROLLED APPROVED COPY-EMERGE 7CI PLAN IMPLDOTTING PIOCEDURE YOID PREVIOUS ISSur DISTRI3UTION PER A-2 EP-102 - UNUSUAL EVENT RESPCNSE PURPOSE The purpose of this procedure is to provide guidelines for response to an Unusual Event.
RESPWSIBILITIES:
1.1 The Shift Superintendent or designated alternate shall assume the duties of the Emerg D ector and implement this procedure, until relieved.
1.2 The Stati nt or designated alternate shall relieve the Emerge r -- --m 7 e ties of Emergency Director and continue i_=1 i u' ' , ,
ble.
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PREDU.7FICNS: % .f/ ,/ l
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PROCEDURE:
1.0 IMEDIATE ACTINS 1.1 The Shift Superintendent shall:
1.1.1 Assume duties of the Emergerrf Director 1.1.2 Activate Emergency Teams as necessary and designate appropriate team and group leaders.
1.1.3 Ccntact the Station Superintendent and the Shift Technical Advisor and inform them of the situation.
1.1.4 Canplete the Unusual Event notification message in Appendix EP 102-1 and direct the cmmunicator (PO or higher) to notify the
( . appropriate parties as specified in Appendix EP-102-1 Urusual Event Telephone Listing.
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c EP-102 Page 2 of 7, Rev.11
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DO NOT USE BLUE RINGDON PHCNE EUR THESE CALLS. -
1.1.5 Closely monitor conditions to determine present hazards to personnel and potential accident conditions that may develop.
1.1.6 Designate a Licensed Operator to notify the NRC cn the red phone. After ocmpleting the notification request concurrence of the NBC to terminate the telephone conversation, prior to hanging up the phone.
1.1.7 Provide station personnel with instructions over the Public l Address System on any major changes in plant status, escalation !
or de-e=<-alation of the <-laaalfications, etc. The following i messages are exatples: l MESSAGE ES (IS) (IS Nor) A DRILL, REPEAT, MS (IS) (IS Nor) A DRIII. l ATTENTICN ALL PERSONEL. ATTENTIN ALL PERSONEL. THE ENERGENCY '
DIRECIOR HAS DECIARED AN IMUSUAL EVENT. ALL CN SHIFT PERSONEL REPORP l TO THE CNTR2. ROCM. ALL OIHER PERSONEL STANDBY EUR FURIHER l ANNOLNCEMENTS. MS (IS) (IS NOr) A DRILL, REPEAT, THIS (IS) (IS NDP)
A DRIIL.
( PESSAE MS (IS) (IS Nor) A DRILL, REPEAT, THIS (IS) (IS Nor) A DRILL.
METENTICN ALL PERSCNE.. ATIENTIOT ALL PERSONEL. THE UNUSUAL EVENT HAS BEEN DE-ESCALATED. ALL PERSONEL SHALL REIURN TO THEIR NORRL DUTIES. ES (IS) (IS Nor) A DRILL, REPEAT, MS (IS) (IS NDP) A IRIIL.
1.1.8 Direct the evacuation of affected areas as necessary. Refer to the following procedure:
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- 1. 2 Shift Clerk or designated person shall:
1.2.1 Notify additional emergency response / support personnel to report to the station as directed by the Emergemcy Director / Shift Supervision us[ng the appropriate Appendix to EP-209, Telephone List for hywy use.
1.2.2 Perform the notification of the off site agencies and personnel within 15 minutes as directed by the Emergency Director using Appendix EP-102-1, Unusual Event Ma===;= and Appendix EP-102-3, Unusual Event Telephone Listing.
2.0 ECLIOMJP ACTICNS 1
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EP-102 Page 3 of 7, Rev.11
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2.1 Emergency Director shall:
2.1.1 Periodically evaluate the event classification in accordance with EP-101, Classification of Emergencies and escalate or de-escalate the classification as necessary.
DO NOP USE THE BLUE RING-DOW PfGES FOR THESE CALLS.
2.1.2 If classification is f.; = alated, cmplete Appendix EP-102-3, Unusual Event De-Escalation Message and give it to the
, cmmunicator and direct ocenunicator to perform the notifications in accordance with Appendix EP-102-2.
J DO Nor USE THE BLUE RING-DOW PIDIES 2.1.3 Perform actions mamry to mitigate conditions of the emergency situation.
, 2.1.4 Provide site personnel with public address announcements for any major changes in plant status, such as changing emergency actions level and evacuations.
2.2 Shift Clerk shall: .
2.2.1 Notify additicnal support perscnnel to report to the plant;as directed by the Emergency Director.
2.2.2 Perform notifications, as directed by Emergency Directors to the off-site agencies.
FIMAL CDIDITICNS:
1.0 Contaminated injured person (s) transported to hospital 2.0 Fire is out, or under control, fire watch has been posted 3.0 All vital areas requiring occupancy are habitable
- 4.0 Site Security is established 5.0 Plant is in stable condition and core is cooling i
j 6.0 In plant radiation levels are decreasing or are stable 7.0 All engineering safeguards are operable 8.0 Release of radioactive materials is being controlled and no significant uncontrolled releases are contemplated f
j' . . ,. . . . . _ , , _ _ - . . . , _
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. EP-102 Page 4 of 7, Rev. 11
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9.0 All emergency plan implementing procedures are closed out or they have been assigned to an individual for closure APPENDICES Apperdix EP-102-1, Unusual Event Notification Message Appendix EP-102-2. Unusual Event Notification Telephone Listing Appendix EP-102-3, Unusual Event DHscalation Message REFERENCE .
PBAPS Emergency Plan EP-101 Classification of Emergencies GP-15, Local Evacuation EP-209 Telephone Listing for Emergency Use.
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. EP-102 Page 5 of 7, Rev. 11 k~
APPENDIX EP 102-1 INUSUAL EVDfr NOTIFICATION MESSAGE MIERT MS (IS) (IS Nor) A DRILL. REPEAT THIS (IS) (IS Nor) A DRIII.
MS IS PEACH BOITCM ATCMIC POWA STATICN CALLING TO REPORP AN UNUSUAL EVENT FOR UNIT . MY NAME IS TELEPfENE NINBER IS . PEAG B0 RICH IS REPORTING AN UNUSUAL EVENT AT , . THE BASIS PICBLEM (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock time) (date)
IS THERE (HAS) (HAS Nor) BEEN AN (AIRBORNE) (LIQUID) RADIOACTIVE RELEASE FRCM THE PIANT. THE PIANT IS (STABLE) (IMPROVING) (DEGRADING) (Nor ENOR4). THERE ARE NO PIDPECTIVE ACTICNS BEING RECONENDED AT MS TIME.
MS (IS) (IS Nor) A DRIIL. REPEAT, MS (IS) (IS NOT) A DRILL.
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EP-102 Page 6 of 7, Rev. 11
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IRISUAL EVENT DE-ESCAIATIN MESSA2 EVRRT
'IHIS (IS) (IS N0r) A DRIIL. REPDT, THIS (IS) (IS Nor) A DRIII. ,
'IHIS IS PEAG BOTICM ATCHIC POWER SDCIM CALLING '1D REPORP A CHANE IN THE ENERENCY CIASSIFICATIN FOR INIT NO. . MY NAME IS .
'IELEPH3E NIMER IS . 'IHE thvJUAL EVENT HAS BEEN TERMINATED.
TDE AND DATE ARE , .
(24 hr. clock time) (Date)
'IHE PIANT STATUS IS (SSBLE) (IMPROVING) . THIS (IS) (IS NDP) A DRILL, REPEAT, THIS (IS) (IS NOT) A IRILL.
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I EP-104 Pag 3 1 of 12, Rev. 12 JJr:
f/A PHIIADELPHIA ELECIRIC CCMPANY f-/545 PEAG DOrIOt UNITS 2 AND 3 DERGENCY PIAN IMPIDIENTING Pid.;tu;ur; CONTROI1ED APPROVED COPY 1 YOID PREVIOUS ISSUE DISTRIBUTION PER A-2 i EP-104 SITE DERGENCY RESPCNSE PURPOSE:
4 The purpose of this procedure is to provide guidelines for respcxise to a Gite Emergency.
RESPCNSTRTT.TTIIS:
1.0 Shift Superintendent or designated alternate shall ' the rol of the Emergency Director when a Site Emergency is decl: ess the Station y Superintendent is present, and perform the in this procedure.
d 1.1 The Station Superintendent or his alte role of the Emergency Director, report to 41 bote or Control Roan 4 and relieve the Shift Superini i bilities as the Emergency
- Director. ,#
1.2 Site Emergency Cma :o the Emergency Operations Facility or r - rations Facility and implement the appropri t( rocedure, if n - wry.
AcrIm LEVEIS: I
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p This procedure s 1 e implemented when an event occurs that is classified j as a Site Emerg per EP-101, Classification of Emergencies.
PREIAUTICNS:
Planned radiaticn exposures should be limited to the Administration Guide Levels in Appendix EP-104-4, Emergency Exposure Limits.
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IM4EDIATE AcrICNS S';ylQ;.7' . ' t .
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i q/ 1.1 Shift Supervision shall:
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$ 1.1.1 Assume the duties of Emergency Director.
1.1.2 If not already done at an earlier emergency action level, acti-vate Emrgency Teams as necessary, designate appropriate team
, and group laaaars.
- 1.1.3 Ccntact the Station Superinterdent and the Shift Technical Advisor, inform them of the situation.
l . . I I .
EP-104 <
Page 2 of 12, Rev. 12 i
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l.1.4 Fill out Appendix EP-104-1, Site Emergency Notification Message and give it to the Ccanunicator (PO or higher classification) and direct ':.he comunicator to omnence notification of the appropriate parties per Appendix EP-104-3, Site Emergency Notification Telephone Listing.
1.1.5 Direct the Comunicator to man the NRC RED Telephone on a con-tinuous basis, if required by A-31. If Comunicator is required for urgent plant operations related to the emergency, the con-currence for securing the phone should be obtained fran NRC prior to securing this telephone.
1.1.6 If not already anmnplished at the ALERP stage, direct the chift clerk to activate the 60 minute call list using EP-209 Appendix P, If shift clerk is not available, this function may be assigned to any available individual. -
1.1.7 Direct one of the on-shift Isc technicians to activate the Tech-nical Support Center and Emergency Operations Facility in accor-dance with EP-201 and 203, if not already activated. If not already performed previously, inform the shift clerk which Isc Technician will activate the centers at Unit 1 in order to let the clerk know which remaining Isc Technician to call for the prompt mobilization prnns+re.
1.1.8 Direct the Dose Assessment Team Leader to initiate off-site radiation surveys, as necessary, if not already done in accor-dance with EP-205B, Radiation Survey Groups.
i
! 1.1.9 Direct the Personnel Safety Team LaaAar to initiate on-site radiation surveys as nea==aary, if not already done in accor&
anoe with EP-205B Radiatim Survey Groups.
1.1.10 Assign an Operations Support Center Coordinator (Shift PO) if not already done and direct availahle shift personnel to report to this Operations support Center and to activate it in accoc-dance with EP-202 if habitable. If the Operations Support Center is not habitable, direct shift personnel to report to the m .:-
Control Rom. .m::- A :a .. ' 1o .:. . : w~. a.~ .a.
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? n 1.1.11 c1naaly monitor conditions to determine :present hazards to .
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a u- personnel and potential accident conditions that may develop.
l l 1.1.12 For amples, direct on-shift Chemistry Technician or Chemistry Si bg1 and Analysis Tema Leader to implement EP-205A, l
Chemistry E 71bg and Analysis Tema Activation.
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1.1.13 For Fire and Damage Repair, direct the Maintenance Shift Assis ,
tant Foreman or the Fire and Damage Team Leader to inplement EP-206A, Fire Fighting Group an4/oc EP-206B, Damage Repair Group.
1.1.14 For a liquid relaama, amplement EP-312, Radioactive Liquid Release, if required.
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EP-104 Page 3 of 12, Rev.12
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l.1.15 For Security matters, contact Security Shift Supervision and I direct implementation of EP-208, Security Team Activaiton, if l necessary. '
l.1.16 If appropriate, direct the evacuation of affected areas as o necessary. Refer to the following procedures:
! GP-15 Imcation Evacuation i EP-303 Partial Plant Evacuaticm EP-305 Site Evacuation EP-306 Evacuation of the Information Center 1.1.17 Provide station personnel with instructions over the Public Address System on any major changes in plant status, upgrading or downgrading the classifications, etc. The following messages
, are an example
! MESSAs MS (IS) (IS NOT) A DRILL, REPEAT, THIS (IS) (IS Nor) A IRILL.
ATHNTICN ALL PERSCNNEL. ATTENTIN ALL PERSON!L. THE DERGENCY DIRECitR HAS IECIARED A SITE 1!NERGENCY. AIL CN SHIFT PERSON!L
,. REPORF TO TfE CCNTR2. BOCM. ALL lesERS T THE DERGENCY i
( RESPGISE CBGANIZATICM REPCRP TO EXR DERGENCY FACILITII!S OR DERGEN".Y IDCATICNS. A SITE EVACUATICN HAS BEEN IECIARED. ALL NCN-I!SSENTIAL PERSCNEL SHALL REPGtr TO ('fMTR NCRK IDCATICNS)
(NGtIE stb STATICN) (PRESIDENT'S UTILITY BUILDING) (IE[HR SERVICE BUILDING). ALL VISITORS WILL REPORP WITH THEIR !!S00fttS TO THE SECURITY AIMINISTRATICN BUILDING AND ANhIT FURtHER INSTRUCTIQlS. '!HIS (IS) (IS NOT) A DRILL, REPEAT, THIS (IS)
(IS NOT) A DRILL.
BESSA2 THIS (IS) (IS Nor) A IRILL, REPERT, '!HIS (IS) (IS NOT) A IEILL.
ATH!NTICH ALL PERSONNEL. ATTD7FION ALL PERSON!L. THE STIE DERGENCY HAS BEEN (DE-liSCRIJm!D TO AN (IMUSUAL EVI!NF) (ALERP)
^, (TEltmRTED) . ALL PERSCNNEL SRALL AMkIT INSTRUCTIGIS FRCM THEIR Y_ - c', ~ . TEAM IEADERS Gt SUPERVIS3t., ' MIS (IS) (IS NOT) A DRIII, REPl!hT,
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M , THIS (IS) (IS NOT) A DRIIL. In " ' ~-
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. ; 8.:.. 9c 1.1.18 If mry, direct Dose Assaaammt Team Leader to initiate the implementation of EP-315, Corporate Cauputer Dose calmil ations, or EP-316, Cumulative Population Dose Palailations, and EP-317, E Direct Parvumarulations to County Emergency Management and Civil L Defense Agencies.
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2.0 RLIDHJP ACTICNS .
2.1 Emergency Director shall:
, 2.1.1 verify that the Technical Support Center, Operations support Center and Aux. OSC have been activated.
2.1.2 Periodically evaluate the event classification in accordance with EP-101, Classification of Emergencies and eenlate or de-aealate the classification, as necessary.
2.1.3 If the classification is d: . mlated, ccznplete Appendix EP-104-3, Site Emergency De-Escalation Notification Message and give it to the ccanunicator to perform notifications in accor-dance with Appendix EP-104-2.
2.1.4 Obtain results of the EP-316, Ctmulative Population Dose Cal-culations and offsite radiation surveys frca the Dose Assess-ment Team r a.c.
2.1.5 Obtain on-site Plant Radiation Surveys frm the Personnel Safety Team Leader, as necammary, 2.1.6 Provide appropriate information fra the previous evaluations
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to Ctanunicator in the ECF for notification of the Bureau of Radiation Protection.
2.1.7 Perform actions as necessary to mitigate ocnditions of the
, emergency situation.
- 2.1.8 If not already performed, determine which additional support
! , personnel are peammary for emergency functions and direct the shift clerk or other assigned ocanunicator to ocntact those personnel.
2.1.9 Provide site personnel with P.A. speaker announcements for any major changes in plant emergency status, such as changing emergency actica levels and evacuations.
. 5 .. . .
,d ;h .l 23.50 Difecd the Evacuatica 'of affected areas as necessary. Refer to
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L EP 303 Partial Plant Evacuaticm EP 305 Site Evacuation EP 306 Evacuation of the Information Center 2.2 Station Supar$ntendent shall:
i L 2.2.1 Report to the Technical Support Center or Control Roczo, for a briefing of th.. situation, if n3t already acting as the Emer-gency Director.
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EP-104 Page 5 of 12, Rev.12 1
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2.2.2 Assume the role of Emergency Director (if not already done) by' l formally relieving the Shift Superintendent of this responsi- l bility. Announce that he has assumed the role of the Emergency Director to the assembled Technical Support Center personnel.
2.2.3 Verify the emergency classification.
2.2.4 Verify that the Technical Support Center, Emergency Operations Facility and the Operations Support Center have been activated.
2.3 operaticos Support Center Coordinator shall:
2.3.1 Notify the Emergency Director when the Operations Support Center is activated.
2.3.2 Provide support to the Control Rocan and Shift Supervision as e y.
2.4 Auxiliary Operations Support Center Coordinator shall:
2.4.1 Notify the Personnel Safety Team or Emergency Director that the Auxiliary Operations Support Center is activated.
2.4.2 Provide Health Physics support to teams as directed by Personnel
(, Safety Team Leader.
2.5 Dose Assessment Tean Leader shall:
2.5.1 N Eme Director when the Emergency Operations 2.5.2 Report progress and results of EP-316, Cumulative Population Dose Calculations and off site radiation surveys.
2.5.3 Notify the Site Emergency Coordinator of the need for assistance fran Radiaticn Management Corporation.
2.6 Personnel Safety Team Leader shall:
2.6.1 Repoct progress a' nd results. of on-site radiation surveys to the
,- Emergency Director as waary. . . , , , ', - -
,. .. __. 4 2.7 Shift Clerk or other assigned person shall:
2.7.1 If not already done, notify additimal support personnel to report to the plant as directed by the Emergency Director.
Refer to the appropriate appendix of EP-209.
l 2.7.2 Notify Emergency Director or Site Emergency Coordinator when the t.
additional support personnel have been notified.
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_ _ - - - - , .__ ; ;-. 7; ,
l EP-104
- Page 6 of 12, Rev. 12 i
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2.8 Isc Technicians sha n: (if not already performed as per EP-103) 2.8.1 Inform the Emergency Director when the centers are activated, if not previously done.
' 2.8.2 Man the TSC or ECF data display (OCIV) positions as directed by the Emergency Director.
2.9 Chemistry Satpling and Analysis Team Leader shan 2.9.1 Report progress and results of any ammpling activities and their results, if appropriate to the Emergency Director.
2.10 Security Tema Leader shan:
2.10.1 Provide a briefing of the security situation, as required, to the Emergency Director, providing status on the Security Force manning.
2.H Fire and Damage Team Leader shan:
2.H.1 Provide a briefing on fire and damage assessment activities to the Emergency Director, if appropriate.
( 2.12 Technical Support Team rer shan:
2.12.1 Dispatch available ocnnunicators, status board keepers, etc.
to support the activities in the various energency response centers.
! 2.12.2 Provide engineering amaaameents on th esmergency situation, as
)
requested by the Ese.WJy Director.
FINAL CINDITICNS:
1.0 Contaminated injured person (s) transported to hospital.
2.0 Fire is out, or under control, firewatch has been posted.
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3.0. All vital areas. requiring occupancy are habitableh. Q
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.W M1P 5.0 Plant is in stable condition and core is cooling.
6.0 In plant radiation levels are decreasing er are stable.
7.0 All engineering safeguards are operable.
! 8.0 Release of radioactive materiais is being controlled and no significant uncontrolled releases are contemplated.
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EP-104 Page 7 of 12, Rev.12 l
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9.0 All Emergency Plan implementing procedures are closed out or they have been assigned to an individual for closure.
APPENDICES:
Appendix EP-104-1, Alert Notification Message Appendix EP-104-2, Alert NotificatiorvTelephone Listing Appendix EP-104-3, Alert De-Racalation Maanage Appendix EP-104-4, Emergency Pre Guidelines REE'ERENCES:
PBAPS Emergency Plan NUREG 0654 EP-101, Classification of Emergencies GP-15, Local Evacuation EP-303, Partial Plant Evacuation EP-305, Site Evacuation EP-306, Evacuaticrt of Information Center
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APPENDIX EP-104-1 SITE EME:RGENCY NOYIFICATICN CHEXXFF LIST Message: This (is) (is not) a drill. This (is) (is not)a drill. This is Peach Bottom Atomic Power Station calling to report a Site Emergency has been declared on Unit . My name is , telephcne ntsnber is . Time and date of Site Emergency classification is , . The basic problem is (24 hr clock) (Data)
There (has not been) (is potential for) (has been) (is presently) a radioactive (airborne) (liquid) release frca the plant. The plant status is (stable) (inproving) (degrading) (not known). Reccanended protective
( acticms are (none) .
This (is) (is not) a drill. This (is) (is not) a drill.
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APPENDIX LMgh2
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ilTE EMEPGENCY NOT IF LC A TIDN ILLE PHOSE _L113tif,
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APPENDIX EP-104-3 SITE DERENCY'DE-ESCALATION NOTIFICATICN MESSAGE MS (IS) (IS NOT) A DRIIL. REFFAT, THIS (IS) (IS N0r) A DRIIL. M S IS PEAG BOrlm AIMIC POWER STATICN CAILING TO REPORP A CHANGE IN THE DERGENCY ACTICN LEVEL. MY NAME IS , 'IY1EPfENE NCNBER . EE SITE DERGENCY CN WIT NO. HAS BEEN -
DE-ISCAIATED TO (AN INUSUAL EVENP) (AN ALERP) (AN SITE DERGENCY) ( M MD WrED).
TDE AND DATE ARE , . THE PIANT SMUS IS (SMBIE)
(24 hr clock) (Date)
(IMPBOVING) . MS (IS) (IS NOr) A DRILL. REPEAT, MS (IS) (IS NOr) A IRIII.
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EP-104 Page 12 of 12, Rev.12 APPENDIX EP-104-4 DERGENCY EXPTURE GJIDELINES Projected Whole Body Thyroid Autiorized Function Dose Dose By
- 1. Life Saving and Emergency **
Reduction of Injury 75 ren* 375 ran Director
- 2. Operation of Equipnent to Mitigate an Emergency **
Emergency 25 rem
- 125 ren Director
- 3. Protecticn of Health and Safety of the Emergency Public 5 ran 25 ren Director
- 4. Other Emergency 10 GR 20 10 CFR 20 Emergency Activities limits limits Director
- 5. Re-Entry / Recovery Adninistrative Adninistrative
(, Activities Guidelines Guidelines N/A
Reference:
EPA-520/1-75-001 Table 2.1
- Such exposure shall be on a voluntary basis W'
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EP-205A.16 Page 1 of 2, Rev. O s
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Ps--IA EucraIC Cmur SEP12(985 Peach Bottcm Units 2 and 3 Emergency Plan Implementing Procedure CONTROLLED APPROYED COPY-VOID PREVIOUS ISSUE DISTRIBUTION PER A-2 EP-205A.16 SIGAGE T POErr-NT'WWF SAMPLES PURPOSE:
The purpose of this prm adure is to provide guidelines for the storage of post-accident samples.
RESPCNSIBILITIES:
1.1 The Chemistry Sampling and Analysis Tean Leader will deParmine the need to store ==rlaa.
1.2 Health Physics personnel will be responsible for surveying the sample and posting the results.
ACTICN LEVELS:
Not applicable.
PRECAUPICNS:
Not ==1 b*1 e.
P903DORE:
1.0 DM!lDIATE ACTICNS 1.1 The Chemistry Sampling and Analysis Team Leader shall:
1.1.1 Determine the need for storing post-accident samples.
1.1.2 Direct the samples to be adequately identified and dated, then transported to and stored at the PBAPS Unit 1 source vault.
1.1.3 Direct that appropriate dev,==ritation regarding the sample be stored in an appropriate location.
1.2 The Chemistry Siling and Analysis Team Members shall:
1.2.1 Attach a label, tag or other iden*ifying device to the sample container.
1.2.2 Place the sample in the Unit 1 source vault.
( 1.2.3 Record the saigle identification in a separate reference
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l.3 Health Physics personnel shall: .
1.3.1 Survey the. source vault and post results in accordance with HrOA2>-ll.
1.3.2 Perfoon periodic surveys during the emergency and maintain posting up-to date.
2.0 POLIGHJP ACTIGIS:
2.1 Health Physics personnel shall:
2.1.1 Survey the samples cx:mtained in the Unit 1 source vault and post results on a scathly basis.
2.2 Director - Radiation Protection Section shall:
2.1.1 Determine when stored samples be discarded and so instruct the Station Ch try.
FINAL CDIDITIO35:
Survey requirements should be terminated when all
,. samples have been discarded.
(
APPENDICES:
Not applicable.
REFERENCES:
10GR20 Standards for Protection Against Radiation.
HPQ/tD-1 Radiation Dose Rate Survey Techniques HPOA2)-ll Establishing and Pcating Radiologically Controlled Areas EP-205A.1 Operation of Post-Accident Sampling Station f
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EP-206A Page 1 of 23, Rev. 7
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PHIIADELPHIA ELECIRIC COMPANY PENII BOI'IQi INITS 2 AND 3
[M" N PIAN IMPIDDTfING PROCEDURE CONTROLLED APPROYED EP-206A VOID PREVIOUS ISSUE FIRE FIGTfING GROUP D S RIBUTION PER A-2 PURPOSE To define the actions of the Fire Fighting Group.
REETRENCES
- 1. Peach Bottom Atomic Power Station Emergency Plan
. Section Title 5.2.1.5.8 Fire and Damage Team
- 2. EP 401 Entry for Emerge a lal 4
( 3. EUREG 0654 .
a a c
he i ear Power Plants. .
- 4. 10TR50 on K
- 5. EP-209 Appendix D-3 Fire and Damage Team Notification List APPENDIX
- EP-206A-1 Fire Fighting Group Organization and Responsibilities by Job Title EP-206A-2 Fire Fighting Group Standard Actions EP-206A-3 Autcznatic Fire Protection System Initiation and Reset EP-206A-4 Classes of Fires and Types of Extinguishants EP-206A-5 Portable Fire Fighting Etpipnent Available On Site EP-206A-6 Emergency Exposure Levels (Emergency Plan Table 6.1)
EP-206A-7 Available methods of safe shutdown t
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EP-206A Page 2 of 23, Rev. 7
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wrICu IzvEL h e Fire Fighting Group will be activated whenever there is a situation onsite which, in the judge ent of the Dnergency Director or Shift Supervision, requires their servi s. %e Fire Fighting' Group shall also be activated upon any initiation of the Fire Systen.
l PRECAUTICNS
- 1. Team msnber's exposure should be limited to the administrative guide levels in Appendix EP 206A-6, Dnergency Exposure Limits. We Emergency Director shall approve any team member exceeding Peach Bottczn quarterly exposure limits. The Fire and Damage ham Ieader should ensure that au teen members are controlling their own exposure in accordance with ATARA con pts.
- 2. %e Outside Shift Supervisor or other mernber of shift supervision, as determined by the Shift Superintendent, Interim Fire and Damage ham Imader until relieved by the Fire and Damage Team Ieader for fire-fighting and damage repair duties.
- 3. %e Engineer-Maintenance and the Assistant Engineer-Maintenance are qualified in. fire-fighting techniques which aHows them both to be Fire and Damage Team Imaders if required. However, as a general rule, the site
(- maintenan personnel are not fire-fighting qualified. %ese persmnel can mly assist in fire-fighting activities with the shift operators if requested by the operators due to an in-extremis situation.
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- 4. If off-site assistance is required, ensure a representative of the fire-fighting group meets the fire department at the entrance to the site to inform them of the situation and provide guidance to the fire locaticn.
Request Security and Dosimetry support for off-site fire cmpanies.
- 5. Requirements of HPO/CIM, Radiation Work Permits, are not applicable. Se HP em_-9-iying the Fire Fighting group will serve as the RWP.
- 6. If team members are required to enter a hazardous area, there shan be a minimum of two people per group entering.
PROCEDURE:
/-w 1.0 Parsonnel who identify fires shah: -m 1.1 Innediately determine if the fire by a quick action such as using a nearby fir quickly
. exti sh the f ift Supervisicn (ext e location and type and actuate
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Warning: For a fire in fuel storage areas, flooding new fuel with water or applying a water fog should be avoided to prevent a possible criticality in new fuel.
1.2 After sounding the alarm remain close to the area, at a safe distance fran snoke, fumes and fire, to provide direction to the fire location
- to the fire fighting group.
2.0 Shift personnel who receive report of fire shall:
2.1 If a fire is reported to the control rean via phone or P.A. the irdividual who receives the report shall advise the chief operator of the location and fire description.
2.2 Ifpanel the fire notification was initiated via the fire alarm annunciator the dilef operator should chtain the exact words on the j annunciator window, and use them n the announcement.
i 2.3 The Chief Operator should make repected announcements of the fire type (if known), location, and fire fighting group assembly area. He may at this time, or later, if requested to do so by the Team M r, announce an assembly area for general plant personnel. This assembly area
(-- should be chosen based upon the additional needs of the fire fighting group as indicated by the leader. (E.G. manpower - at fire locatierVportable fire fighting equipnent - per locations indicated in Appendix EP-206A-5/ turnout coats, boots, gloves, scott 4.5 SCBA - cage e
located at Unit 3 13 KV area.)
2.4 consider evacuation using the following promdures:
GP Iccal Evacuation EP-303 - Plant. Evacuation L EP-305 - Site Evacuation 3.0 Bnergency Director shall:
3.1 Call the fire and damage team leader. If the situation permits, i
discuss the problem with the fire and damage team leader so be can assess the situation and determine how many and what type of team munbers will be necessary to correct the problem.
3.2 If necessary, direct the designated connunicator to contact fire and danage Team members; refer to EP 209 Appendix D-3 for telephone raabers. Inform the teen members where to assemble.
3.3 If necessary, contact off-site agencies for assistance. The site i
7-. emergency coordinator should be consulted if outside assistance is
( desired before contacting any off-site agencies.
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D-206A Page 4 of 23, ray. 7
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3.4 In the event that the fire has the potential to empletely disable all equipnent
'F' in and cabling passing through the fire area, reference the procedure for the area and Appendix EP-206-A7 to obtain guidance in determining the renaining available systems to acomplish safe shutdown of the affected unit.
4.0 Interim Fire and Damage Team Imader (Shift Supervisor) shall:
4.1 Obtain 'mwn information fran Chief Operator.
4.2 If time permits, review the applicable "F" procedure for the affected fire s m e.
4.3 Obtain all necessary keys for the fire zone in the event of doors are locked or the security keycard device does not function.
4.4 Cbtain two radios; one for the leader and one for the inspection team
- leader.
4.5 Call the Auxiliary Operations Support Center and request an HP to report to the assembly area.
4.6 Proceed to the fire scene and assemble the fire fighting group.
(
4.7
- nimin fighting the gro situation and what has to be done in detail to the fire
- g. Also inform them of any hazards or precautions encountered on way to fire.
4.8 Prior to leaving the assembly area decide the number of personnel necessary (minimum of 2 plus an H.P.), designate equipnent to be used (see D-206-A Appendix 1), ensure team members have adequate protection
< to fight the fire, and ensure the team leader and group have portable radios.
k 4.9 If entry into a hazardous area is necessary, do so in accordance with W 401, entry for emergency repair, operations and search and rescue.
4.10 Direct the fire-fighting efforts in accordance with appendix D -206A-1, fire and danage team organization and reponsibilities and appendix EP-206A-2, fire fighting group standard actions. Use portable and installed fire protection equipment in accordance with EP-206A-3, autanatic fire protection system initiation and reset, Appendix EP-206A-4, classes of fires and types of extinguishants, and Appendix EP-206A-5, portable fire fighting equipment available on-site.
4.11 Advise the Control Roca concerning the need for de-energizing or removing equipnent or systems fran service and the significanoe of damage sustained and the inpact on plant operations and safety.
,; Request as required *2: shutdown of ventilation system (s).
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EP-206A Page 5 of 23, Rev. 7 k -
4.12 Be alert to radiological, electrical, and toxic hazards to personnel involved in fire fighting. Seek advice frczn the Fire and Danage Team raadar on radiological or toxic agent hazards.
4.13 Periodically update the emergency director or interim emergency director of the status of the situation, request the emergency director or interim emergency director to ask for assistance frczn the Delta-Cardiff fire and ambulance ocupany, if necessary.
4.14 Coordinate the activities of off-site fire fighting support groups.
4.15 Advise the Interim Emergency Director or Emergency Director concerning Bnergency Exposure Limits for team members involved in emergency work and repairs, attempt to minimize radiation exposure and contamination as much as possible. (See Appendix EP-206-8 for exposure limits).
l 5.0 Fire Fighting Group Members shall:
5.1 Report to the assembly area with equipnent, as assigned in Appendix EP-206A-1, assume the responsibilities assigned in Appendix EP-206A-1, and fight the fire under direction of the team leader.
6.0 Fire and Damage Team r eadar shall:
6.1 Report to the technical support center (when activated). Contact Bnergency Director when on-site and cotain status of the current situation.
6.2 Establish ocmnunications with the Interim Fire and Danage Team Leader and obtain status of the fire fighting group.
6.3 Provide additional personnel support if necessary. Use EP 209 Appendix D-3 for additional qualified fire fighters or maintenance support personnel. Contact them and provide information on where to report.
Assign designated plant staff to direct one or more Fire Fighting Teams as necessary. Assign at least three personnel to each team, as required. Direct the tean to relieve or assist the Interim Team members as necessary.
6.4 Periodically provide fire and damage group leader with plant status changes and significant radiation exposure and radioactive contamination problems which may affect the functicas of the team.
Assign a member of the Fire Fighting Group to man the SCBA system on the First Floor of Unit 1.
~
7.0 Auxiliary Operations Support Center Coordinator shall:
( 7.1 Assign an HP Technician to each fire fighting group.
l I
. I D-206A Page 6 of 23, Rev. 7
( l 8.0 HP technicians shall: 1 8.1 (btain required equignent and report to assembly area. Obtain information fran and inform interim team leader of any known radiation hazards associated with the situation.
8.2 Ensure safe radiological conditions in the fire fighting area.
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D-206A Page 7 of 23, Rev. 7
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_ APPENDIX EP-206A-1
- _ FIRE FIGrfING GROUP CRGWIZATICN AND REsaNSIBILITIES
~ A.
i - following assigned equipnent:'Ibe Fire Fighting Group e should rep P
Shift Supervisor:
k - Two radios and necessary keys Plant Operator No. 1:
CD2 portable fire extinguisher Plant Operator No. 2:
Purple K dry chemical fire extinguisher Ass't Plant Operator:
Purple K dry chemical fire extinguisher
- Auxiliary Operator:
P Innediately proceed to the fire fighting group I ~ equipment cage,116' El. by joy air empressor or cart El.165' by L 2 turbine assembly area. shield wall and obtain one Scott 4.5 SCBA and procee so by leader. Innediately obtain additicnal SCBA if requested to do B.
'1he following responsibilities to are guidelines the Group members: which should be used to assign
. . Shift Supervisor:
Interim Fire and Damage Team Leader Plant Operator No. 1: 1) Inspection Team Leader
- 2) Ass't Interim Fire and Damage Team Leader (i.e. Shift Supervisor designated alternate)
- 3) Noszle man on No. 2 Fire Hose
- 4) Extinguichant with 002 Plant Operator No. 2:
- 1) Nozzle man on No.1 Fire Rose
- 2) Extinguishnent with purple K dry chemical
.4 3) Lighting and Snoke Removal Ass't Plant Operator:
- 1) Inspection Team (along with P.O. No.1)
- 2) Backup man on No. 2 Fire Hose
- 3) Extinguishment using purple K dry chemial Auxiliary Operator:
( (inside) 1) Equipnent Manager
- 2) Backup man on No.1 Fire Hose
- 3) Extinguishnent using CD2 J
~ ~~
q,.
- e. 7 - , - . p..._, .-
i EP-206A Page 8 of 23, Rev. 7 (A
)
APPENDIX EP-206A-2
- FIRE FIGfTING GROUP SIANDARD ACTICNS CAUTICN:
r THE Fidu;ni CF CDEUSTICN CF CERTAIN MATERIAIS (e.g
.SOE EIECIRICAL CABIES, PIA 9 TICS, OIIE) ARE VERY TOXIC, IF HIGI t' TOKIC GAS IEVELS ARE Submam, IF M OXYGEN LEVEL IS IESS THAN 19.5%, OR IF THE CARDOX SYS7EM HAS BEEN ACTIVAE!D, k i SO7IT 4.5 AIR PACK 5 MJST BE USED.
?
1.
BLergency Director, or his designee (via phone, .
or or P
- 2. Fire Assessment
- e a.
is unopened, look for abnormalities such zone es phy discoloration, peeling paint or other evidence of high temperatur ,
an attenpt extreme to determine caution to open door. the proximity of the fire to the access.Use e in
' expected, move a charged line in prior to opening door.If door is h b.
(. The enterFire Fighting the area of theGroup fire. Leader should direct the Inspection m to Tea fire extinguishers. The Inspection Team should have portable conditions the inspection team may use a Scott 4.5 SCB lifeline,line charged or by portable inspectionlife lines tean). at the Leaders discretion a(or use o c.
The Inspection Team should stand to the side, (charging lin available) access. while remaining low, and slowly crack eopen, must bethen open th (If required, the site forcible entry tool is located in the d.
security building, Auxiliary SAS, under the windows of the North W .
If the fire is determined, by the Inspection Team Ter, to be obviously extinguishable, with their portable extinguishers, innedia action shall be taken to do so.
d If the fire is of such magnittrie that innediate extinguishment s i
.d beyond the capabilities of the Inspection ham, the Inspection ha Leader shall report, to the Fire Fighting Group I4ader m j ,
the nature of
,a
'4 with the fire hazards in the vicinity (e.g. nvolved oil tan canpressed gas lines, cylinders, or tanks, propane lines ,orand tanks) any apparent effects of the ventilation systen on the fire.
3.
/
' Upon the report of the Inspection Team, the Fire Fighting eader Group L described in Appendix EP-206A-3, if appropriate equipnent preparation and associated actions. g ng extensions and extinguish same. Also check for fire i i
l' l l
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EP-206A Pige 9 of 23, Rev. 7
(
- 4. .
At this time and periodicany thereafter the Fire Fighting Group Leader 4
should report Bergency the fire scene situation to the Interim Emergency Director or Director.
~~
(The Interim Bnergency Director at the Emergency Director, based upon control Roan indications, and review of the applicable u "F" ghe should make reconmendatims as deemed necessary).
, a.
f Ventilation - The "F" procedure for the fire zone indicates normal
' ventilation flow rates. This data, along with Inspection Tean
" observations should be evaluated to determine degree of inpact fran the normal fire zone ventilation. In general, direct the ehutdown of the supply ventilation snother the fire. system servicing the fire area to isolate and help Exhaust ventilation may renain in service to either aid in increasing visibility (smoke removal), remove potential toxic or
! explosive fumes, or to introduce cool air. Otherwise, supply and
. achaust ventilation should both be shutdown initiany. If ventilation I is coupletely shutdown the Fire Fighting Group Imader should direct
/ (e.g. General Plant Personnel Leader) that areas serviced by the sane
- ventilation those areas.system be surveined to assure smoke is not migrating into to aneviate this condition.If so, exhaust fans should be sequenced on periodim u 5.
. The Fire Fighting Group should then, under the direction of the fire and 4 -
damage team leader, enter and extinguish the fire. The guidelines
{ ( presented this effort.in Appendix EP-206A-1 should be used to aid in coordination of j The guidelines presented in Appendix IP-206A-4 should be used to employ the proper extinguishant for the type of' fire which is present.
6.
If deemed necessary, the Fire Fighting Group Imader should direct i additional general plant personnel either directly or via the Interim Bnergency Director or the Emergency Director. He should request additimal
'i
] portable fire fighting equipment, as listed in Appendix EP-206A-5 and additimal personnel to fight the fire.
7.
Upon extinguishment of the fire or as is necessary designated plant
- personnel should applicable " ventilate" the area using guidance contained in the "F" procedure.
{ re oval equipment are contained in Procedure S.13.1. Instructions for use of the i
8.
1
- Upon extinguishment of the fire, a fire watch shall be established, in the area, in the event of a reflash of the fire. The duration of the fire i watch shan be proportional to the magnitude of the fire, but in no case shan be less than 1/2 hour.
IU 9.
!~
3 Fire fighting proper storage equignent location. shall be inventoried, replaced and returned to its If Scott airpacks have been used, the cylinders must be refined and then inspected by the Respiratory Protection o
Administrator through performance of ST 17.2.B.
7 10. At some time after the fire PIEo Form No. 196-44002, " Report of Fire" Fcrm,
( should andbe canpleted Teenand forwarded to the Safety Department by the Interim ,
Fire Damage Leader. i l
l h
1 7
EP-206A Page 10 of 23, Rev. 7
(
APPENDIX EF-206A-3 AU10& TIC FIREiPICIECTICN SYS'IEM INITIATICN AND RES Y'
g i
[' below with a brief description of systen actuation and Auto g Control Room alarm.actuatim of any of these systens will initiate a coded signal an
,t l.
Se following equipnent is protected by open head errinklers supplied by Water Deluge Valves which are initiated autanatically upon heat detection
! or manually by opening and pushing the lever in the manual station located at the Deluge Valve in the Condensate Pump Roan.
under control, reset these valves per Procedure S.13.2.1.G.After a fire is out or a.
Main transformers 2AX01, 2BK01, and 2CX01 (3AX01, 3Bx01 and 3CX
- b. Auxiliary transformer 20K02 (30K02)
{ c.
I - Condensate pump transformers 2AX07, 2Bx07, 2CX07 (3AX07, 3BX d.
Start up and emergency auxiliary transformer 00XO3
( 2.
De following equipment is protected by open head sprinklers supplie Water Flooding Valves which are initiated autanatically upon heat detection 3 or manually by opening and pushing the lever in the manual station located
. at the Deluge Valve near the protected equipnent.
tmder control, reset these valves per Procedure S.12.3 ...
2 1 ItAfter a fire is out or a.
- '. Hydrogen seal oil tait (Units 2 & 3) b.
A and B standby gas treatment system filters c.
A and B rectabiner building ventilation filters l 3.
Head " Nitrogen-filled dry sprinkler system."Se Turbine Hatd
~'
head (s), releases the nitrogen pressure, and causes a fire alarmHeat . Se treaks
- _, by one of the following methods
- sprinkler system for the Turbine Ha
'i .
, a.
sq Pushing Roca. the remote pushbutton located on panel 20C01 in the Centrol
, b.
OpeningCard:nc Building the local unit.electr m ual box mounted next to the Turbine c.
( Opening and pushing the lever in the manual station located at the Deluge Valve El.116' near Turbine Bldg. elevator.
i f
..___.._,,_.._____,,,,,_,__...,,_..a._W._.____.
1
)
l 1
EP-206A Page 11 of 23, Rev. 7 1
( j
- d. . !
After the fire S.13.2.1.G. is out or under control, reset this valve perureproced 1 3 4.
P-p-
'!he fonowing areas are protected by Heat Sensitive closed head ers
- ~ supplied heat sensitive Sprinkler sprinkler Alarm Valves (SAV) which initiate upon actuation heads. of i
w but the Sprinkler Alarm Valve fails to open, the local manual sta located at the individual SAvs may be used to open the SAV.
g3 is out or under control, reset these valves per Procedure AfterS a13fire 21 H l
(
- a. j I: Turbine Lube Oil Reservoir Room (Unit 2 & 3) 1 b.
.i 'nzrbine Lube Oil Storage Rocn (Unit 2 & 3) c.
Main Steam Stop Valve Area (Unit 2 & 3) d.
East and west feedwater heater service platforms (Units 2 & 3)
- e. .
.j
-, Areas
- 3) . under east and west main turbine generator platforms (Unit f.
Auxiliary Boiler Building 5.
( 'the fonowing rocans are protected by sprinkler systems which
,upon equipnent in the rocm. actuation of a heat sensitive sprinkler head, giv j
systems by closing the corresponding Manual Block Valv !
- actuated sprinkler head, and restoring the block valve to an
- a. :
open l A, B, and C RFP Turbine Lube Oil Reservoir Rooms (Units 2 & 3 b.
Diesel Fire Pump Roca (CDEN) c.
El.116' lube oil storage roczn Unit No. 3 Turb. Bldg.
d.
El. H 6' lube oil storage rocm in Admin. Bldg.
- e. El.135' Radwaste Ccupaction Area 6.
", 'Ihe turbine bearing oil line below the pedestal (Unitsected 2 & 3) are p 1 by a " Heat Sensitive Closed Head Nitrogen-fined dry sprinkler syste d Heat initiates breaks a fire the sprinkler head (s), releases the nitrogen alarm. pressur e and
'j w
oil following lines below pedestal may then be manua n y initiated by methods:
a.
- b. At the local stations located at North and South ends of t .
/
\ Deluge Valve (165' elevation near generatore . Opening ;
or under control, reset this valve per proce) dure S.13.2.1.G.After the valve i '
l
. 3'P-206A Page 12 of 23, Rev. 7
(
7.
De Diesel Generator Cardox System, if not disarmed, will initiate Corrpartments.autcmaticany upon heat detection in each of the individual Diesel ha be manuany Cmpartment door. initiated using the pushbutton station outsid Upon failure of the pushbutten statim, manuany Electro-Manual Pilot Valve (located outside of th t
h .
move seconds, thethenleverclose to the theOPENpilot valve. position to open the Master Select Valve for 60 Manual Pilot Valve lever %2st be mcved to the menn position te discharge of CD2 to the. Diesel Ccupartment. ,
?
system, reset the syLean per Procedure S.13.2.2.B.After initiatics of the Cardox !
CO2 tank, located in the Booster Pump Roon, holds S e Diesel 5500 Generator lbs. of CO2 A
single 2200 sixty lbs. se.cnd discharge to any of the Diesel Generator rocas .
uses Therefore, " double shot" protection is provided. i
-, 8.
described above for the Diesel Generator Cardax Syste
" S e Electro-Manual Pilot Valve Cardox Storage for Tank. the HPCI rocm is located at the Unit 2(3) Wrbine Bld .
Manual discharge is performed by moving the Electro-
~ Manualthe closing Pilot DSC. Control (EMPC) lever to the OPEN position for 60 seconds
, then
(
Each Turbine Building CX)2 Tank (Unit 2 and Unit CO2. . of
- 3) holds 1 lbs. %erefore " multiple shot" protection is provided.A sing 9.
either side of the Ccmputer Roem.%e CompJter Roan Cardox Sy If pushbutton initiation fails, the Electrc>
the Select Valve Manual must Pilot be noved Controlto the OPEN (EMPC) position levers for 125forseconds the Maste
. The EMPC CD2 StorageforTank. the Se MasterEMPC Select Velve is located at the Unit 2 Turbine Cable Spreading Rocn. x the Select Valve is located outside the be returned to the nim position after 125 seconds.Whr Anitiated manu Procedure S.13.2.2.D may then be acccuplished. System reset per Upon C mputer Room 002 in betion, the tie valve between the n Unit 2 an 3 tanks opens, providing a total 002 capacity of 24,000 lbs. A single 125 i'
" multiple shot" protection is provided.second discharge Werefa e,to the ocnp 3 .
lN l
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- Su-
_ - _ _ - - _ - - - _ _ _ _ _ _ ----wm -- r -dv mi-' n- -ww- - - = *--w w e1--- - - -m -
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. EP-206A Page 13 of 23, Rev. 7
(
- . -10.
The cable Spreading Room Cardax System is initiated y by autcmatica Cable Spread Room.
actuation of both channels of a two channel smke d the system If snoke detector autmatic may Spreading be actuated manually by using initiation the pushbutton does not ,
sta
- outside either Cable Rom door.
moved to the OPEN position for 125 seconds.the ust be Dec le i
Valve is located at the Unit 2 Turbine Building CD2 storage tankThe B@
2 for the Select Valve is located outside the cable spreading . The DEC rom l When l
initiated after annually, the Sec levers must be returned to 125 seconds.
the on CTA armelished. System reset per Mmdure S.13.2.2.D may then be I!
{~ Upon Cable Spreading Roam CO2 injection the tie valve betwee and Unit 3 tanks opens, providing a total m2 capacity of 24,000 lbs.
single 125 second disdarge to the Cable Spreadir.g ARam use CO2.
j h -
Therefore " double shot" protection is provided. .
11.
.7 equipped with CO2 hose reels.The main control Room reas are and the Un holder the hose reel and header autanatically pressurizeWhen . Dis &arge is the ho accueplished by depressing the nozzle hand lever.
I If hose reel header
( REEL BSC valve to the CF5i position to pressurize. e E fai reel is ccuplete, return the D@C valve to the nran position.When us 12.
prat. Gad by dry chemical furnished through a se
- are event of a fire at the t4 sings
- In the -
i [,i a.
Move bearing. the 350-rnax! wheeled Ansul dry chemial unit to the ap rae b.
Connect fitting at the the quick connect hose from the Ansul triit bearing. c connect to the qui k c.
j
( ..;
cylinder and actuating the hand lever for discharg 13.
!(
iC The Mi Set Room (Unit 2 & 3) and the Mil Set Lube Oil n Pump & 3)
Rom (
ij Smoke Detector Pressurized Sprinkler System.are protected b ,
s alarms valve.
ficoding and pressurizes the sprinkler header with water by opening th
.4 fire.
j ~*
b ,, The system can be pressurized with water manual the procedure manual station located at the flooding valve.
per S.13.2.1.K. The system is then reset
\, (
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EP-206A Page 14 of 23, Kev. 7
(
- 14. .
The No. operated a manually 6 fuel oil foam tank and the auxiliary boiler building are prote system.
- open the foam solution tank inlet and outlet valves.To apply foam inside the the manual hose reel and nozzle, unreel the entire hose, open the founTo aI
- using the " Pistol Grip" shutoff valve. solution tank inlet valve, t restore the system per procedure S.13.1.1.When fire is out, close valves and I 15.
by water curtains whis can be actuated either m .
1.
Manuany by puning the manual pill station at the ficoding valve whi stairwen for UnitIt2.is located may also in the be actuated by southwest renoving the stairwell f
. frangible lock frcm the remote electrical station box in the El. 135' Rx. Bldg. elevator stairwen, and actuating the pull box within.
&' 2. Autmatically by heat detectors.
' ~
separated into 2 zones with 2 detectors per zone.End unit's west corridor are both north and south of each unit's center line.The detector zones Automatic given zone are received (i.e., 2 out of 2 ence logic).ac 3.
(.
These systems must be initiated manually if, in the opinion of the Shift Supervisor, the fire cannot be controned with normal manual fire suppression equipnent and has the potential to effect cables in these areas.
4.
After theS.13.2.1.M.
procedure fire is out and under control, reset these valves per 1
- )
or i'
me.,
EP-206A Page 15 of 23, Rev. 7 l
APPENDIX EP-206A-4 CIASSES T FIRES AND 'ITPES T EXFINCUISHANTS
,4 j' Hose Station Portable Fire Extinguishers Purple K Pressurized l Classes of Fires Fbg/5trean 002 Dry Chemical Water m ama A Yes No, except Yes (Heat of Yes (Defined as wood, very snall Ccmbustion may
- paper, cloth,etc.) (See Note 4) fires remain)
Class B (Defined as flae- Yes,POG CHLY Yes Yes No mable Liquids) (See note 1)
I ; Class C (Defined as ener- No Yes Yes No (See l- gized Electrical No Yes Yes No (See Rplignent) (See Note 2) (Note 3) Note 2)
('
]- Note la When using water to cx:mbat a Class B fire special techniques are
! necessary. The Use of a direct hose stream should be avoided to minimize spreading the fire. However, " cooling" may be provided via
' hose stream to heat sensitive equipnent in the vicinity of the fire.
If necessary, due to the size of the fire being beyond the capabilities
! of multiple Purple K dry chemical extinguishers, a water " fog" iJ application NOT DIRECFLY APPLIED to the fire may be used for
( additicmal suppression.
Note 2: In the case of High Voltage B3uipnent, the Associated Cabling and Control Devices shall always be de-energized prior to the use of water as a suppresant. High density cable runs of generally lower voltage are a specific concern at PBAPS. Water OLY in the form of a FOG may be used. Water should be used only in maximum fog form at the maxisman o
effective distance (to eliminate electrical conduction) when fighting a I fire in low voltage energized cable. Fog should first be established, not in contact with the fire, and separation distance should slowly be
.i decreased. When electrical equipnent is de-energized then, the fire Q may be considered as Class A and may be fought as such.
Note 3: Due to the highly corrosive characteristics of Purple K dry chemical extinguishant usage en electrical equipnent should be minimized.
I
\
. Page 16 of 23, Rev. 7
(
md m"m"m"E3 g ARus, accomo a na m.m C POSSIBIE CRITICALITY m a m 4 BE AVOIIED TO PREVDrf A
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. EP-206A Page 17 of 23, Rev. 7
(
APPENDIX EP-206A-5
'~ ~
A. PCRmBIE FIRE FIGITING EQUIPMENT AVAILAR
}
L Turbine BuiWng, adjacent to the joy air age located on otrnFire El.116', Br 165' inshore shield wall for Unit 2 turbine). pressor. Cart located on El.
i M hour self phoenix hardcontained hats. breathing apparatus, turnout coatsContents inc t , boots, gloves, and B.
I Bnergency Fire Cabinets 1.
_ Cabinet shield wall). No.1 (Iocated at 165' El. adjacent to Unit 2 co Contents include smoke removal blower, instruction manual, flexible duct, and vent duct to flexible duct adapter r duct, and extension equipment, electricalcord.
tapes, tools and fittings , door bar back
, masking, 2.
I _rays Cabinet and Chemox No.canisters.
2 (Sane location as No.1).
Contents incitrie half mile 3.
Cabinet No. 3 (Iocated at 116' El. adjacent wall). n to pla t Cabinet No. 1. Contents incitx5e two smoke removal entranceblowers shield plus s
( ame itens as C.
Additional in-plant Hcse Carts:
. 1. .
Unit No. 2 Reactor Bldg:
,l a.
- b. Hose Cart No. H-137 El 165', southeast corner n Hose Cart No. H-135 El.195', northeast corner ear hatch.of fir
- 2. e tower.
Unit No. 3 Reactor Bldg:
a.
- b. Hose Cart No. H-138 El.165', northeast corner ne D. Hose Cart No. H-136 El. 195', southeastar corner hatch. by ower.
fire t 350 lb. Wheeled Ansul Units:
- }' 1. Elevation 116' -
s 3 a.
lj
- b. Unit No. 2 Turb. Bldg. southwest corner.
~ c. Turb. Bldg. Center SWGR. Area South.
- d. Turb. Bldg. Center SWGR. Area North.
Unit No. 3 Turb. Bldg. Northwest Corner.
2.
Elevation 165's a.
Unit No. 2 nirbine Hall:
1.
- 2. Riverside wall North Riverside wall South
.--=w +we++-
.,*r= '""*** b yw., - v -
-+---m -,.
IP-206A
, Page 18 of 23, Rev. 7
(. 3.
4.
Downriver Southwest corner. -
Adjacent to Control Rocm entrance.
. b. Unit No. 3 Turbine Hall:
- 1. Riverside wall North F* >
- 2. Riverside wall South
- 3. Northwest Corner lI 4. Center near generator E.
t, Portable wall mounted 002, Purple K Dry Chemical t extinguishers and self-contained breathing appara,tus. pressurized water fire
'i
-5 .
ih,'
+ 4
/
- :s
'4 i
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D-206A Page 19 of 23, Rev. 7
(
APPENDIX EP 206A-6 DEMENCY EXPmWE LIMrfS
-- Projected yy Whole Body 'Ihyroid Functicm Dose Authorized Dose i .'
- l. Life Saving and Reduction of Injury Emergency **
75 rem
- 375 rem i 1 Director
- 2. Operation of Et[uipnent to Mitigate an l Bnergency Emergency **
25 rem
- 125 rem I Director
- 1
. 4. Other anergency Activities 10 TR 20 10 TR 20 Bnergency
.O limits limits Director
- 5. Re-Entry / Recovery Activities Adninistrative Administrative Guidelines Guidelines N/A
( *
Reference:
DA-520/1-7'5-001 Table 2.1
- Such expmure shall be on a voluntary basis 9
- ]
. L2 s
~~.
t'
EP-206A Page 20 of 23, Rev. 7 l
APPDOIX 206A-7 i
AVAIIABII: Mimf0DS T SAFE SiAnumN
' ~
Twenty-five methods of providing reactor shutdown and decaywere heat remo utilized as the basis for a safe shutdown analysis.
The individual "F" s
procedure for each fire zone indicates those method i
fire.
A design basis fire is assumed to disable all equipment located with fire zone zone. and all equipment associated with rabling passing through the
'Ihis analysis assumes complete loss of equipnent functica even if a caponent is not required to change its normal line up status to perform satisfactorily.
j Ea6 of these methods includes a system by whid water can be added to reactor vessel, a system by which energ e and any support systems needed to a.u ..y can be renoved frcm the reactor vessel,
- sink or to return water to its supply source.uiute energy removal to an ultimate heat i alternate power supplies.several alternatives derived frcm multiple flow
, or L~
(, Following is a description of these 25 methods of providing reactor sh t u own.
Methods utilizing the condensate pmps or condensate pumps pumps:
c or feed and rea
' 1.
j Water is supplied frcan the condensate storage tank (CST) by the
, 4 condensate and reactor feed pumps to the reactor vessel. Energy is removed is returned via to the theCST.
turbine bypass valves (TBV) to the cendenser and w water system.
This is a n:n-safety related method.The condenser is c 2.
l Water is supplied to the reactor vessel.from the CST by the condensate and reactor pumps feed valves (MSRV) to the torus. Energy is renoved via the main steam relief l
- heat and pumps removal (ICR)topumps water is returned the CST. and the high pressure servic method. m is is a non-safety related
, 3.
Water is supplied to the reactor vessel. frcm the CST by the condensate and umps reactor fe O injection (HPCI) steam drag to the torua. Energy is removed via high pre the MR and HPSW planps and water is returned to the CST.%e torus is cooled non-safety related method. Bis is a 4.
The reactor is depressurized to 650 psig . Wateror less sel.
Energy the CST. is removed via the TBV to the condenser and water is return t
The condenser his is a non-safety relatedismethod.
cooled by the circulating water system.
l l
l .. .
IP-206A Page 21 of 23, Rev. 7
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- 5. .
'the reactor is depressurized to 650 psig or less using the MSRV . Water Energy is renoved via the MSRV to the torus.is supplied e.
i the IER and HPSW pungs and water is returned to the CST.'!he This is atorus is coo F2 non-safety related method.
r-Methods utilizing the RCIC plag:
" 6.
Water (RCIC) is supplied from the CST by the reactor mre isolation coolin the u.a.ptsup C .ser.to the reactor vessel. Energy is removed via the 'IBV to 3
systen. 'the condenser is cooled by the circulating water the tocus is cooled by the RRR and HP97 pumps. Water is returned to the GT. 'this is a non-safety related method.
7.
<r Energy is renoved via the PERV to the tecus. Water is sts .
,F* the RER and HPSW pumps and water is returned 'the torus to theisCST. cooled by t non-safety related method. '!his is a
.I 8.
Water is supplied from the CST by the RCIC pump to the reactor vessel Energy is removed via HPCI steam drag to the torus. .
- 'the torus is This is a non-safety related method. cooled by the RRR and H
[ 9.
- Water vessel. is supplied frca the torus by the RCIC pump to the reactor
! is cooled by the circulating water systen. Energy is removed
'!he condenser the RRR and HPSW pungs and water is returned to the torus.The torus is m non-safety related method. This is a 4
10.
i Water vessel. is supplied from the tocus by the RCIC pump to the reactor r cooled using the RER and HPSW pumps. Energy 'the torus is isrenoved via seismic criteria. considered a safety related system, it is designed considered a safety related method,Because of this design, this method can b 11.
Water vessel. is supplied from the tocus by the RCIC planp to the reactor p is cooled by the RER and HPSW pumps. Energy The istorus removed v considered a safet Although the RCIC system is not
! [~
' seismic criteria. y related system, it is designed to satisfy Class I considered a safety related method.Because of this design, this method can be Methods utilizing the HPCI pump:
12.
Water is supplied from the CST by the HPCI pump to the reactor vessel Energy is removed via the 'IBV to the condenser. .
(' cooled by the circulating water system. 'Ihe condenser is i ERR and HPSW pumps and water is returned to the GT.The torus is cooled usin i safety related method. This is a non-m __
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. . - . . . - . - - . . . ~
!!P-206A i Page 22 of 23, Rev. 7 I
' [ 13. Water is supplied fra the CST by the HPCI pnp to the reactor vessel.
Energy is renoved via the ISRV to-the torus. The torus is cooled by ji the RER and HPSW pumps and water is returned to the CST. Bis is a non-safety related method.
- 6 i Energy is removed via HPCI staan drag to the torus. S e torus is ocoled by the RRR and HPSW pungs and water is returned to the CST.
21s is a non-safety related method.
.e
- 15. Water is supplied fra the torus by the HPCI pump to the reactor
- E *' vessel. Energy is removed via the 1BV to the condenser. Se condenser
' is cooled by the circulating water system. The torus is cooled by the RRR and HPSW pays and water is returned to the torus. His is a nom safety related method. i
- 16. Water is supplied fr a the torus by the HPCI pump to the reactor i vessel. Energy is removed via the MSRV to the torus. Se torus is
- , , oaoled by the RER and HPSW peps. his is a safety related method.
,' 17. Water is supplied from the torus by the HPCI gump to the reactor 5
vessel. Energy is removed via HPCI stem drag to the torus. The torus is cooled by the RRR and HPSW peps. his is a safety related method.
e Methods applicable after the reactor is depressurized to 300 psig or less:
(,
i
- 18. The reactor is depressurized using the TBV. Water is supplied fra the torus by an RRR pump to the reactor vessel. Energy is removed via the
] TBV to the condenser. S e w A ser is cooled by the circulating water system. Water is returned to the torus. his is a non-safety related 3, .
method.
$ * '.)I 19. S e reactor is depressurized using the MSRV. Water is supplied fra I
the torus by an ERR pump to the reactor vessel. Energy is removed via '
the MSRV to the torus. The torus is cooled using the RRR and HPSW pups. his is a safety related method.
[ Methods applicable after the reactor is depressurized to 350 psig or less:
- 20. Se reactor is depressurized using the TBV. Water is supplied frm the iM CST by a core spray pump to the reactor vessel. Energy is removed via the TBV to the wAser. % e condenser is cooled by the circulating
.1 water system. Water is returned to the CST. This is a non-safety related method. mis method is an alternate to method 22 below, i.e.,
i ! ~ -l.
- d water is supplied fr a the CUT in place of the torus. Use of this
' 1 water supply requires opening a manual valve in the core spray pap suction line.
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EP-206A Page 23 of 23, Rev. 7 I
- 21. The reactor is depressurizing using the MSRV. Water is supplied from the CST by a core spray pump to the reactor vessel. hergy is removed via the MSRV to the torus. The torus is cooled by the RHR and HPSW punos and water is returned to the CST. This is a non-safety related
' - method. This method is an alternate to method 23 below, i.e. water is
)4 supplied fran the Csr in place of the torus. Use of this water supply requires opening a manual valve in the core spray punp suction line.
- [
'. > 22. The reactor is depressurized using the TBV. Water is supplied from the
- e !
torus by a cxre spray pap to the reactor vessel. Ehergy is removed i
via the TBV to the condenser. The u..hc.s is cooled by the circulating water systen. Water is returned to the torus. This is a non-safety related method.
- 23. The reactor is depressurized using the MSRV. Water is supplied fran the torus by a core spray pay to the reactor vessel. Ehergy is renoved via the MSRV to the torus. The torus is cooled by the RRR and HPSW pc ps. This is a safety related method.
- r,
- 24. The reactor is depressurized using the TBV. Water is supplied from the
'* river by a HPSW plunp to the reator vessel. Ehergy is removed via the i
TBV to the condenser. The condenser is cooled by the circulating water systen. Water is returned to the CSr which overflows to radwaste.
This is a non-safety related method.
[ 25. The reactor is depressurized using the MSRV. Water is supplied fran the river by a HPSW pump to the reactor vessel. Energy is renoved via the MSRV to the torus. The torus is cooled by the RHR and HPSW pumps.
This is a safety related method.
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EP-207D Page 1 of 17, Rev. 4
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PHILADELPHIA ELETRIC CWPANY g \9 h +
PEAG BorIOi INITS 2 AND 3 I
kj DERGENCY PIAN IMPIBCTfING PTO eu]RE
- , OMRollED APPRO7
)' TOID PREVIOUS I EP-207D EVACUATICN AcMNBLY GROUP DISTRIBUTION PE
=s PURPOSE 1.0 Vehicle and Evacuee Control Group.To define the actions of the 1 &
- 2.0 a. Site To establish Evacuation. perscnnel and vehicle monitoring procedures to be 3.0 To establish a vehicle decontaination procedure to be used during a Site Evacuation.
b RESPCNSIBILITIES:
(~
l.0 The Personnel Safety Team Leader will be responsible for the designatio
' the Group Leaders and Group Menbers for groups outlined in this procedu 2.0 .
t vehicle tasks as and Evacuee outlined Control Group Leader is responsible for assignme in this procedure.
3.0 t
The Security Team Leader shall assist the Personnel Safety Team
- providing necessary security officers to direct traffic, provide assistance and portable radios as required in a Site Evacuation.
AcrICH LEVELS:
1.0
, The vehicle Safety and Evacuee Tem Leader when: Control Group shall be activated by the Personnel
- T 1.1 A Site Evacuation is iminent or declared, or
{'j 1.2 Personnel suspected or vehicle contamination or detected, or outside the protected area is 1.3 The Emergency Director directs the activation of the vehicle and Evacuee Control Group based on his assessment of plant conditions, or l [ 1.4
\ Vehicle decontamination will be performed whenever vehicles are found beta /gartrna) .to be contaminated (greater than 1000 dpt/100 an2 smeara
. . - - _ =- -
\' .
Ee-207D 1 Page 2 of 17, Rev. 4 i i
(
PREGUTIONS:
1 1.0 Evacuee Control: .
I i
1.1 I
- . )aj Evacuation shall be done in an organized and controlled. manner
\
e g - 1.2 i .
Evacuees will be instructed during announcements of the Site y ,
~
Evacuation by the Emergency Director to proceed to one of the
[ with their vehicles until instructed otherwise by Vehicle and Evacuee Control Group.
i 1.3 4
- l Evacuees the mv '=1ts. Personnel may be allowed to proceed provide are not required to 1
i unless the Emergency Director deems necessary.be detained any further
, 1.4 If a release has occurred, designate the routes to be taken after vehicles are allowed to leave the evacuation assembly area to ens they do not travel through the pitne path. '
i
! , 2.0 Contamination Monitoring:
g 2.1techniques. Caution should be used during therobefriskin 2.2 i; -
I( l, Caution should a vehicle should or be evacuee usedbe tofound ensure contaminated. cross contaminatio 1
- 2.3 Each of the predesignated evacuation assembly areas contain a Decontanination Control Kit.
deemitaminaate at least 25 vehicles.at the North Su
( Additional material can be obtained other utilities. fran the plant (if accessible) or outside support agencies 1
2.4
,m Personnel monitoring areas should have a backgroundanlevel less th 300 cpn and preferably less than 100 cym.
I i
] 3.0 vehicle Decontamination:
- d i-3.1
'- Personnel anti-C clothing involved in vehicle demntamination shall wear ae approp Group Leader (co,nsideration should be given -
- s. to wat 3.2 Care deocntamination. shall be taken to minimize the spread of contanination du i
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EP-207D Page 3 of 17, Rev. 4 3.3 Ensure that all materials used for decontaination are disposed of properly.
~
3.4 r- The vehicle decontamination area will consist of a large enough area to ensure any containation that may be spread will be contained
- within this area.
3.5 Boundaries will be surveyed periodicall
).
~
has spread outside the vehicle decont to determine if containaticm nation area.
i 3.6 Minimize wipes as much the use of water when decontainating vehicles; use masslin as practicable.
ifu.w uRE:
1.0 IIHEDIATE ACTICNS q 1.1 Personnel Safety Tem Leader shall:
1.1.1 4
Assign vehicle and Evacuee Control Group members from the available personnel at the Personnel Safety Tem Assmbly Areas (OSC/ Aux. OSC) and have the a%1e at the Aux. CSC.
I 1.1.2 Appoint the most qualified individual of the group as the Vehicle and Section 2.0 ofEvacuee Control Group Leader and have him carry out this procedure.
i .
, 1.1.3 j Brief the Vehicle and Evacuee Control Group Leader on the
.g anticipated a==hly areatime of evacuation, the selected evacuation assably area,, and any potential, significant hazards orth conditions which the Group Leader should be aware of.
1.1.4 Designate a method of ocmunication between the evacuation assembly area (Group Leader) and the Personnel Safety Tem Leader in the 'ISC.
'.p Tem Leader. State information to be canunicated to 1.2 it The Vehicle and Evacuee Control Group Leader shall:
g 1.2.1
, j Assign the following tasks and specific duties to the assembled 42 group menbers as necessary:
a.
, One area, individual to direct traffic at the evacuation assembly
- b. Two individuals to perform surveys of evacuees and vehicles.
c.
Three individuals to set up receiving area for evacuees and vehicles in accordance with Appendices EP-207D-1, 2, or 3.
l
_ __, -- ~~~
_ _- . - - - - - . - - - - - -- ] __.
EP-2070 Page 4 of 17, Rev. 4 1
( '
These individuals will be responsible for performirv3 decontamination of evacuees and vehicles as necessary. , and assisting the other members of the Vehicle and Evacuee Control Group as their workload permits.
[
r: 1.2.2 Direct available team members to obtain the following equipnent fra the sources:
a.
- Four PIN-6 portable friskers or equivalent r apahle of batt.ary operation in the field which have been properly calibrated, source checked, and battery checked, b.
One PAC 45 survey instrument or equivalent.
- c. Four RO-2A survey meters or equivalent, d.
Six orange vests (located at the North substation assembl area).
e.
Ten full sets of Anti-C clothing.
f.
- . - Keys for the designated area from the security building.
1.2.3 Have (personal each tem msnber vehicles will be used).report t.o the evacuation assably area
(
for identification of group msnbers. Orange vests are available 1.2.4 Upon Team Safety arrival, establish Leader. cm munications with the Personnel I
1.2.5 j Organize functions at the evacuation control area and set up the areas for contaminated parking, clean parking, vehicle 1
directing personnel to these different areas. surveyin 1.2.6 Ensure proper frisking of vehicles and evacuees is being performed at all times and documentation of all surveys is being recorded on the vehicle Survey Registration Forms.
4 1.2.7 Inform the Personnel Safety Team Leader when vehicles or l
extent of contamination. evacuees are found to be contminated in I! -
1.2.8 j Using current HPO/CD and EP procedures, determine fra the
,j which personnel decontamination will be perform 1.2.9 of all vehicles and evacuees. Inform the Personnel Safety T
(
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EP-207D Page 5 of 17, Rev. 4 i'
( l.3 Vehicle and Evacuee Control Group Members s
!, 1.3.1 Group sesber assigned as a traffic controller shall shall:
1.3.1.1 (
- p. Dependent upon the layout of the evacuation control i
area, set up the traffic control patterns in ;
accordance with the attached Appendices EP-207D-1, EP-207F 2, or EP-207D-3 for the area specified. I
- l tf 4 1.3.1.2 Direct evacuees to park in an orderly fashion and j await further directions until the area is set up for 4
monitoring operations. :
1.3.1.3 organize traffic control of vehicles with the vehicle and Evacuse following Control Group Leader. Consider the factors:
t.
j :
i a) ,
ir Posting of contaninated and clean parking areas.
- s b) organizing of vehicles prior to frisking.
[~ -
c)
Boutes to be taken by vehicles to contaminated or i , clean parking areas upon ocupletion of vehicle I
surwys.
j F.
{ d) organizing parking of vehicles in the different areas.
- ; 1.3.2 Group numbers assigned to survey evacuees and vehicles shall y
1.3.2.1 Dress in appropriate Anti-C clothing and obtain two
' ) PIGHi friskers or equivalent. (Anti-C requirementa at ,
, discretion of the Vehicle and Evacuse Control Group (
Leader.)
4 i
1.3.2.2 Proceed to the area designated to be the sonitoring l
i area and, using the frisker, take background ;
i contamination level reading. If the reading is greater than 300 cpa, inform the group leader and
{o i
await his decision whether to set up the monitoring ;
I station lower backgroundin this area level.or to choose another area with a j 1,
1.3.2.3 Set g a monitoring station:
l.a '
j a) set up a contanination control point (e.g., step -
i off pad, radiation rope).
1 b) !
Using rad tape or rad-rope, set up boundaries to direct the personnel to the step-off !
J 1
( '
control the spread of contamination. pad and to ,
i !
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- ~.. - . - - .- - ._.- .- - . - - - - - - - - -. -- __ . -
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EP-207D E
Page 6 of 17, Rev. 4 i i
{. I l' c) i i: Provide empty containers near the step eff pad for receivingcontainatedobjects.
L -
- 1 f,
For Personnel without Vehicles
!! l.3.2.4
}. Direct the people to be acnitored toward the contamination control point. !
[' .
- ' ~ 1.3.2.5 ,
j Direct each person to recove anti-contamination i clothing (as applicable) using HP0/ t%>5 Step 3.0 as a guide.
I
(
i 1.3.2.6 .
j Frisk the hands of the person to be monitored. If the t
hands are himself, pernot contaminated, let the person frisk HP0/tIb6.
- a) l i
If the person's hands are contaminated, frisk the !
1 i --
4 rest of the body and bottom of shoes. If no other t containation is found 1
on anti-contaminationco,tton gloves and to go to '
i '
one of other the of parts decontaination the body are found areas to listed be below. If !
contaminated, direct the person to p ;
j '.
/
(. , cont a inated clothing, as necessary,ut to on prevent anti- !
the spread of containation. See RPCWCF7, !
!- Personnel Dooontamination. !
N t .
- - . +
n c l ' PER8CNEL IE03frAMDOLTICM AREAS 5
- 1) RADOWfrE BUIIDING, ELEVNPION 135' 2)
PIEBIIENr'$ i
- 3) In tNI Sta m RTIUFILITY W BUIIDING (MR)
- 4) IEL1R SERVI 2 BUILDING ,
! 5) t j tMIT 1 NERtRNCY GNIER (IST FI40R) !'
1 b) im Priority for decontamination shall be given to
" personnel found to have the highest levels of I i* containation.
!,M to have ingeste4/ inhaled radioactivity shall beA !
given a whole body count to assess their internal exposure.
{ See NP0/tXF7, Personnel id Decentamination.
i V.
For Personnel Arriving in Vehicles z'
j 1.3.2.7 Coordinato with the vehicle and Evacuse Control Group Leader as to the area needed to be raped off for containated vehicle parking and necessary signs to be posted.
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EP-207D l
Page 7 of 17, Rev. 4 l 1
- - ( l.3.2.8 Establish parking area anmaexit area in which persomel leaving the l contamination. y be monitored for possible j j l.3.2.9 Inform personnel who have parked vehicles in the i
J 4
contaminated parking area to follow directions.
4 i
1.3.2.10 Personnel found to be contaminated shan be reported j to the Vehicle and Evacuse Control Group Leader.
l (N0!Et The Grotp Leader will determine the technique i and process in which these personnel win be l decontaminated using established persennel i
decontamination procesures and techniques contained in current HPO/CD procedures.)
1 i 1.3.2.H Periodically survey the egress step off area for contanination.
- , g.-(
i , 1.3.2.12 Upon cumpletion of an perscnnel monitoring, inform the Vehicle and Evacuee Control Group Leader.
- j. .
1.3.2.13 Decontaminate the step-off area if m ry and a dispose of an radioactive waste appropriately.
!' ( 7 1.3.2.14 Any are found to be greater than 1000 dpv100 cm2
't
, gross beta-ganna above background, or any detectable alpha will be reported to the Vehicle and Evacuee Control Group Leader. The report will define the location and maximum reading of the contamination.
) .4 1.3.2.15 Complete and record an information for each 4
C N D MDeaED vehicle on a contanineted Vehicle
! Registration Form, Appendix EP-207D-4. (One form for i each contaminated vehicle.) List all CLEhN vehicles t ,
on the Clean vehicle Registration Form, Appendix EP-207D-5. l
- i. i 1.3.2.16 Vehicles found contaminated will be directed to park lC in the contaninater.) vehicle parking area or decontaminated on the spot. ;
!!i
- g l 1.3.2.17 Instructions to be given to driver and occupants of i r.1 contaminated vehicles
- !
i ,x 4 a.
! Follow the posted traffic signs to the i
contaminated parking area.
i
- b. Leave keys in the ignition.
I 1
- c. Decontaninetion win ocumence as soon as possible, h with regards to the amount of contanination on the
~. vehicle and the amount of vehicles to be surveyed.
I' i
I
. . - . - . . . i
a --
j EP-207D Page 8 of 17, Rev. 4
( d. Do not brush against other vehicles in the .
contminated parking area to preven tpossible or further containation.
I e.
FoHow the directions of the monitoring personnel t: after exiting the vehicle.
6 1.3.2.18 Vehicles found to be uncontminated win have the emmants step out of the vehicle and win then
' '2 - ' '
perform a whole body frisk of the individual. If e m e=nts are found to be containated greater than 100 cpm gross beta-gama above background, they will be directed to follow the same procedure as delineated in Step 1.3.2.6.
1.3.2.19 Instructions to be given to drive whose vehicle and
< m m=nts are found uncontainated a.
If the driver is designated for an amergency team,
, fonow posted traffic signs to the clean parking area or proceed to emergency team designated assably area.
L b.
If the driver has no emergency response duties, he may be anowed to leave the area, but shan be I
advised to the direction of plume track (if applicable).
1.4 Group menbers assigned to deconta inate vehicles shallt 1 1.4.1 Determine fran vehicle Survey Registration Forms (Appendix EP-
' 207D-4) which vehicles may be decontaminated in the contaminated parking area and which vehicles have to be sent to the vehicle Decontmination Station.
(NorEt Determination of these two catagories of vehicles win be dependent upon areas of the vehicle contaminated, total area contaminated, containation levels, and the facilities i available at which the vehicles are parked.)
'f a.
N 1 Vehicles which can be decontminated at the parking area win have contmination on the flat surfaces and possibly 13 inside. Deconta ination will be in the same manner as cleaning up an area of dry, loose surfre contamination.
- b. Vehicles requiring decontamination at the Vehicle Decontamination Station might be contminated around the wheel wens, undercarriage, or grill area and possible the air filter.
- ^ * ' ' *
- t
--- _ _ _ _ _ _ _ _ . _ . _ . - - - - -- ~
l e-2o7D Page 9 of 17, Rev. 4
( l.4.2 Assign 3 ausbers to the Vehicle Decontmaination Station to set the area up for receiving contm inated vehicles.
1.4.3
- When informed that the Vehicle Decontamination Station is ready to receive vehicles, direct contaminated vehicles to the area.
h4 1.4.4 A - Personnel assigned to set up the Vehicle Dooontaination Area:
)
i
( 4 1.4.4.1 Take or obtain as necessary the following equipannt
- a. two PNHi friskers or equivalent.
- b. Vacuum cleaner with high efficiency exhaust filter.
- c. One PAC 48 survey instraent or equivalent.
o
- d. Two 10-2 survey meters or equivalent.
1.4.4.2 set up the vehicle Decontamination Area for the
}. decontamination of vehicles.
1.4.5 Inform the Vehicle & Evacuse Control Group Leader when the I '
vehicle Decontamination Area is ready to receive vehicles.
1.4.6 Upon vehicle arrival, direct the driver into the decontmaination area. U possible contmaination. pon exiting, frisk the driver for 1.4.7 Review the Vehicle survey Registration Form and determine the method by which this vehicle will be decontmainated.
, Nort:
Items to consider on vehicle decontaminations a.
Inside of contamination the vacu m cleaner, on seats can be decentminated by use b.
Wheel well and undercarriage can be decontanineted by use
.,., of very low pressure water rinsing and if subsecpent decantaminations are required, brushes may be used to loosen centmaination.
- c. Air filters found contanineted will be disposed of as radioactive weste.
~
1.4.8 Upen ormpletion of decontaination, resurvey the areas of the vehicle that were contmainated. The vehicle may be considered deocntaminated when all areas of the vehicle are less than 1000 dps/100 cm2 smearable gross bete game above background and no detactable alpha.
+4 W W + hemee 4=9 he g en. o g, =4 + 4 % +
- wa
EP-207D Page 10 of 17, Rev. 4
( l.4.9 Doctanentation of decontaminations and subsequent surveys will be recordedForm.
Registration in the remarks section of the Vehicle Survey - ,
W 1.4.10 Extreme care will be exercised during car washing g.. decontamination to prevent the possible spread of contamination.
used if all other decontamination methods fall.)(i.e.,
t ,
,, a 1.4.11 Upon empletion of vehicle decontaination, inform the vehicle i & Evacuee Control Group Leader that the vehicles have been decontainated and the vehicle is being sent back to the clean area parking, or on his way.
i ,, 2.0 FOLIN UP ACTIONS-
- ( , 2.1 ig Direct personnel to deposit contaminated articles in the containers provided.
b' 2.2 Direct the clean area. personnel who have been frisked and are " clean" to be a
. the site. This may require sending people hcne who have evacuated
( 2.3 Disassemble operations are emplete. the containation control point when the monitoring transport to the radwaste building. Seal the containers with rad-tape for l Properly mark containers as to l contents and radiation levels.
equipnent to proper locations. Return monitoring and deocat mination 2.4 Between vehicle decontaminations, periodically survey roped boundar and the actual decontamination area to determine contm present.
(NOIE:
either be decontaminated or have the barrier ropes mo include these areas, whichever is more feasable contaminated levels within the bat' rier ropes may.either Areasbeof highly decontaminated by use of rags or water rinsing by washing the loose
[I contamination into the drain.)
=1 2.5 Vehicles which cannot be decontaminated shall be reported to the Personnel Safety contaminated parkingTem area.Leader and these vehicles wiu be left at the i i"
.~
2.6 l
Upon empletion of all vehicle decontaminations, a thorough surve i less than 1000 dpV100 cm2 amearablethe area will be conduc
- background, and no detectable alpha. gross beta-gama above n .
m mm . -
. . . ~ ~
. oe
-- - -- - - - - r-, . w-c-
- w-% , - w w r
EP-207D Page 11 of 17, Rev. 4
( 2.7 Contaminated rags and other materials used for decontaminat e begged normal HPas radioactive procedures. waste and .ransported back to the site via m
- ) 4 FINAL CCNDITICNS
1.0 i .
Personnel, and, vehicles and equipnent are decontaminated to ean acce i '
2.0 Site Evacuation functions are terminated and, 3.0 Radiological releases are terminated or at an acceptable level and 4.0 ,
r vehicle and Evacuee control Group function. Emergency
- a Pm
[; APPENDIQ!S t
!L . EP-207D-1, North Substation Lqyout EP-207D-2, j EP-207D-3, President's Utility Building (PUB) Layout
( EP-207D-4, Delta Service Building Layout EP-207D-5, Vehicle Survey Registration Form P
- Uncontaminated Vehicle Registration Form r
REFERENCES:
'r i
f NUREG 0654 3 j
, 4 PBAPS 5.2.1.5.7.3, Emergency Evacuation Aasatly Plan, Section GroLp 6.2.1.5.7, Personnel Safetyecticn Team Lea Health Physic Operations / Chemistry Operating Procedures HP0/0>-5, HP0/Q>-6, Selection and Use of Anci-Contamination Clothing HP0/to-7, Personnel Contamination Survey Techniques HP0/CO-8, Personnel Decontamination Procedure HP0/tD43, Decontaination of Tools and Equipnent
- HP0/CD-100, Radioactive Materials Health Physics Guides used in the Cont
. ,e .
- I f
L
- a. . , - , - - - - . - , ,, . . - - . - - , , - . , , , . - - - - - --
EP-207D APPENDIX EP-207D-1 Page 12 of 17, Rev. a g" ~ N0flTit S US S TA T10N fs l OUTSIDE FAUCET (ON/OFF VALVE INSIDE)
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- PE-207D i
APPENDIX EP-2070-2 Page 13 of 17 Rev.
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,, APPENDIX EP-207D-3 Page 14 of 17. Rev. 4 l
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CONTAMINATED -VEHICLE SURVEY REGISTRATlON FORM
( RETURN COMPLETED FORMS TO VEHICLE & EVACUEE GROUP LEADER )
VEHICLE CWNER; D ATE:
TIME:
ADDRESS:
DRIVER'S N AMEt CCCUPANTS NAM 2(S):
VEHICLE DESCRIPTION:
! MAKE: MODEL: CCLCR: LICENSE NO:
DESCRIPTION OF EXTENT OF VEHICLE CONTAMIN ATION AND LOCATION:
( CONTINUE OM REVERSE SibE IF MECE55 ARY 1 REMARKSt I
SIGNATURE:
- EP-207D APPENDIX EP-207D-4 Paga 16 of 17, R3v. 4
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( RETURN COMPLETED TORMS TO VEHICLE & EVACUEE GROUP LEADER )
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- Page 17 of 17, Rev. 4 l
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Page 1 of 7, Rev. 0 '
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PsIIm2.PuIA ErmrRIC emmu SEP 0 91985 m m acIS 2 AND 3 CONTROLLED APPROVED Colt-VOID PREVIOUS ISSUE g g MING Pf0CEDURE DISTRIBUTION PER A.2 EP-207G PfRE SURVEY GOUPS PURPCSE:
To define the actions of the Radiation Survey Groups.
RESPWSIBILITIES:
1.0 The Senior Health Physics Technician on shift will report to Aux. OSC and assume the duties of the Personnel Safety Team Leader, until relieved of
- these responsibilities, and take directions fran the Emergency Director.
2.0 The Operations Health Physics Technician will report to the Operations Support Center and assist the CBC Coordinator on matters pertaining to
}
Health Physics.
( ACTIN IZVEL:
The Plant Survey Group will be activated as necessary by the Personnel Safety Team Leader.
PRIDMICNS i 1. The grog mester's exposure should be limited to Station Administrative Limits, see Appendix EP-207G-3. Exposure exceeding Station Administrative Limits must be authorized by the Dnergency Director and shall be in accordance with EP-211, Emergency Radiation W r e Guidelines and Controls. Group manters should control their exposures in accordance with AIARA u,.c+t2 at all times.
- 2. If the equipnent in use during a survey falls or malfunctions, it must be repaired or replaced; otherwise, the survey tean shall retreat to a safe area until the equipnent is replaced or repaired.
- 3. Requirenants of HPOAD-4, Radiation Work Permits, are not applicable.
PRDQIURE:
1.0 DeeDIATE ACTIGIS 1.1 Personnel Safety Teen Leader shall:
- 1.1.1 Report to the TSC (3rd floor Unit 1).
. ma eDaise, -..ene -e.e wwaen**. -- + w e ee+ as- g+ + a- m ,o e en
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! ' Page 2 of 7, Rev. O I
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i 1.1.2 Appoint a Plant Survey Group Leader to direc' Plant Survey
- Squads and assist with I@t Radiation Su voys.
i :
i 1.1.3 Inform the Plant Survey Group Leader of the areas to be ;
i surveyed. '
l I
i i 1.1.4 Instruct the Plant Survey Group Leader to report the progrees i and results of the surveys on a periodic basis to the Auxiliary 1 j Cec or Tec, if activated. !
j 1.1.5 Appoint one grog number to stay in the Auxiliary CBC or to
- i. establish and maintain comunications with the Plant Survey
- i.
- Grcq and to perfona habitability checks at the Auxiliary Cec.
) 1.2 Plant Survey Grcq Leader shan:
1.2.1 Report to the Auu. Cec (Unit 2 Turbine Building El u6'). ,
- 1.2.2 Dispatch squads to survey areas in the plant and on-site.
i Areas should be surveyed while escorting plant personnel in j ceder to espedite entries and maintain survey squad and worker
- exposures, AEAlm. A squad consists of two PBCo. H.P.
Technicians or qualified vendor technicians.
n t 1.2.3 Post areas as necessary to prevent the spread of contamination p and ===d= tion of large doses of radiation to operating '
personnel.
4 1.2.4 Relay the results of the surveys to the Personnel Safety Team 1 Leader and the Control Roem, j 1.2.5 Provide Plant Survey Grcq members with sufficient plant status 3 regarding radiation and contamination hasards to anow then to
} maintain radiation and contamination exposure within approved t levels.
i I
l 1.3 Plant Survey Group Members shaus 4
l 1.3.1 Report to the Aum. Cec (Unit 2 Turbine Building El. u6').
1.3.2 Obtain may equipment for con & acting the surveys as j assigned by the Plant Survey Gr Leader. Equipment can be cbtanned frca emergency kits at Auw. Cec or, in the
- anergency operations Facility or fran normal storage location of Er portable instruments. i i !
l 1.3.3 Check that sanitoring equipment is functional before leaving l
- for surveys. Additionauy, susbers shan possess the proper l j personnel dosimetry and pocket dosimeter is serood, prior to l
, leaving to con &act surveys. -
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~Page 3 of 7, Rev. 0
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1.3.4 conduct surveys as directed by the Plant Survey Group Leader.' i Fill out appropriate sections of Appendix EP-205B-1. l 1.3.5 During transit to specified areas, observe the energized survey instruments for changes above background levels. Instrtsnent probe should be waist high fran the ground.
i 1.3.6 Use the CM survey meter to scan close to ground surfaces to '
detect deposits of contamination. Obtain shi=1 dad and unshielded readings to determine Beta / Gamma ratio.
1.3.7 Post areas as necessary to prevent the spread of contamination !
and - - 1= tion of large doses of radiation to operating personnel.
1.3.8 Report data to the Plant Survey Group Leader via the best avai1=h1= cxzummications method.
1.3.9 Air saples are to be taken to count roan facilities either at j Units 2 and 3, Unit 1. or IOC van.
l.3.10 Frisk before leaving any area which may be contaminated. ;
!h 2.0 RI24W-UP ACFIGE i 1 2.1 Plant Survey Group Members shall:
2.1.1 Perform habitability checks of normally occupied spaces, i.e.,
Chemistry Lab, CBC, Control Roan, on a per1Mir a1 basis as detenmined by the Personnel Safety Team Leader.
2.1.2 Plant Survey Group Cannunicator in the Aux. CSC shall perform i habitability checks of the Aux. CSC as directed. '
j :
APPBWICES:
EP-207&l Survey Data Sheet - 196-21268, Doctype 502 ,
EP-207G-2 Air Analysis Data Sheet - M-21942, Doctype 009 L EP-207G-3 Bnergency Exposure Limits (Bnergency Plan Table 6.1) !
3EFEMBCus:
- 1. Peach mottaa Atanic Power Station Energency Plan
- section Title 5.2.1.5.5.1 Field Surveys jf 5.2.1.5.7.2 Plant Surveys
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' Page 4 of 7, Rev. 0 l
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- 2. Health Physics Operating /t2maistry Operating Procedures !
Nusber Title HPQ/tD-4 Radiation Work Permits I
HPOA2>6 Decontamination of Tools and Equipnent IEWOO-ll Establishing and Posting Radiologically Centrolled Areas HPOA3>-60 Field Use of Eberline Ion Chamber Model 10-1 Radowl !
HPO/tD-62 Field Use of Eberline CM Detector Model E-400 l HPCA3F63 Field Use of Eberline Containation Monitor Model IM-14 HPO/t3F64 Field Use of Eberline IM-14 and HP-210 Probe as a Field
- Scalar HPO/t3F65 Field Use of a Low Volume Portable Air Sampler HPQ/t2F67A Field Use of TC5 Air Sampling Systen for the Deter-
{. mination of Iodine
- 3. NUREG 0654 Criteria for Preparation and Evaluation of Radiological !
, Emergency Response Plans and Preparedness in Support of
, Nuclear Power Plants
- 4. NUREG 0696 Functional Criteria for Baergency Response Facilities h
t i
4
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f APPENDIX EP-207G-1 EP-207G 1
Prq7 5 of 7, R*v. O PBAPs RADIATION - CONTAMINATION - AIRBORNE SURVEY t
g ;2,irsg v g p : /e UNIT 2 - UNIT 3 R.W.P. NO.
SURVEY NO.
D ATE - TIME - SURVEY BY -
AR E A -
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R ADI ATION - INSTRUMENT SERI AL NO. _
SETA GAMMA NEUTMONS TOTAL ITEM MnAoinn Mn/wn Mstu/wn MnEuiun DISTANCE 1
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! 8 CONTAMINATION - INSTRUMENT AIRBORNE - INSTRUMENT SERIAL NO. SERI AL NO.
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4 14
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15 16 REMARKS:
ORIGINAL
, APPENDIX EP-207G-2 P gs 6 Of 7, R:v. 0 4 l
( AIM ANALYSIS DATA SHEET M -21942 142 PEACHBOTTOM '
00CTYPE oc, STATION ~ UNIT 2 30 M00.NO-RwP WORK LOCATION NUMBER COUNTING WORK CONDITIONS DATE SAMPLE C0t.LECTION DATE TIME FLOW RATE (CND TYPE - HI VOL. LOW VOL LAEEL (CIRCt.E ONE)
$ERIAL No.
MEDtUM - PARTICULATE "
CM'. RCOAL t CIRCLE MEcauM usto 3 SAMPLE Oum ATtoN AVC. Flow R A Tt' SAWpLE VOLuwE TECHNICMN WIN. CFM FT I BETA A LPNA I CIRCLE ONE 1 1
TIE FROM THE END OF SAMPUNG TO THE BEGINNING OF COUNTING COUNTING EQUIPMENT AND IDENTIFICATION NUMBER GROSSCOUNTS LENGTN OF COUNT ( MlH. )
( 1_) NET CPM (2) COUNTER EFF.
(3) VOLUME (FT3 /
(4) ACTIVITY ( uCl/cm3) s (1)
NET CPM
_ (4) 41/c)
COUNTER EPP. X VOL. (FT3 ] X 4.0 X 1010 -
(2) (3) l
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l EP-207G f ' Page 7 of 7, Rev. 0
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. APPENDIX EP-207G-3
, Emergency Wre Limits !
Projected Whole Body Thyroid Authorized Function Dome Dose By i
- 1. Life Saving and Reduction of Emergency **
, Injury 75 ree* 375 rea Director i
i.
! 2. Operatie of Equipment to nitigate m Emergency **
Emergenr.y 25 ren* 125 ran Director
- 3. Protection of Health and Safety Emergency of the Public 5 ren 25 rem Director
- 4. Other Emergency 10 CFR 20 10 GR 20 Emergency
(. Activities limits limits Director
- 5. M txy/ Recovery Administrative Administrative Activities Guidelines Guidelines N/A 4
- References EPA-520/1-75-001 Table 2.1 i
- Such exposure shall be on a voluntary basis i
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' " " ' " " " ' ^ " " " ' """ i PEAOI BOFITM UNITS 2 AND 3 SEP 161985 N M N ING W M CONTROLID APPROYD COPY-
- 101D PREVIOUS ISSUE i- DISTRIBUTION PER A-2 l EP-207H DQiIME
- rRY, BIGASSAY, AND RESPIRNITXW GIOUP PURPQiE:
{
- To define the actions of the Desmetry, Bionssay and Respiratory Group.
! RESPCNSIBILITIES:
1.0 The Personnel Safety Tean Leader shall activate the Dosimetry, Binanamy and 3
Respiratory Group and designate a Group Leader to direct the actions of this group.
2.0 The Dosimetry, Bioassay and Respiratory Group Leader will ocuplete all necessary steps outlined in this procedure.
I PPDCE URE:
1
' (. 1.0 DMEDIATE ACTIQ 4S l 1.1 Personnel Safety Teen rMr shall:
1 1.1.1 Determine what type cf services are required of the Dosimetry, Bhany and Respiratory Group, direct the Group Leader to perform the service requested. Direct the Group Leader to assemble the required equipment, supplies and personnel and j dispatch the Group. .
- 1.2 Dosimetry, Bionssay and Respiratory Group Leader shall
1 i 1.2.1 Asse21e the equipment and supplies necessary to perform the task.
i 1.2.2 Provide a briefing to the Group members and dispatch them to the appropriate location.
I 1.3 Emergency Dosimetry Issuance j 1.3.1 Dosimetry, Bionssay and Respiratory Group Leader or his L designee shall:
[ 1.3.2 Arrange to obtain a supply of dosimetric devices, i
l.3.3 Transport the emergency dosimetric devices to the area
]
4
(.. designated by the Personnel Safety Team Leader.
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!4 EP-207H Page 2 of 6, Rev. 0 1.3.4 Coordinate with the Senior Security Officer, on shift, issuing dosimetry to Emergency Tem Personnel aM Offsite Emergency Response Tems (lae., ambulance crews, fire-fighting crews,
- etc.), in accordance with HPO/tD-13a, Control of Personnel l
- Dosimetry Badges.
1.3.5 Maintain a list of the personnel to whan dosimetric devices are distributed. See Appendix EP-205C-1, Dosimetric Devices Log.
1.3.6 Designate an individual to issue dosimetry at Unit 1, Ground
. Floor Guard Station, to all emergency response organization j maahars who are responding to the energency. Maintain a roster of individuals issued dosimetry.
1.4 Personnel Bioassay ;
1.4.1 Dosimetry, Bionssay, and Respiratory Group Leader shall: l l
1.4.1.1 Report to the designated area when directed by the [
Personnel Safety Tean Leader and pick up satple '
~
containers nar====ry for bioassay specimens.
1.4.1.2 Obtain a list of personnel who may require mcmitoring for internal contamination from the Personnel Safety i- Tema Leader.
, 1 1.4.1.3 As soon as practicable, locate these people and obtain r=r*= mary sanples in accordance with HPO/CD-26, Personnel Bioassay Progran.
1.5 RESPIRMCRY PICIBCTICN 1.5.1 Desimetry, Bionssay, and Respiratory Group Leader shall:
1.5.1.1 Report to the area requiring respiratory equipnent fitting and supervision, as specified by the Personnel Safety Team Leader.
1.5.1.2 Supervise the respiratory fit personnel during the distribution and fit of respiratory protective equignent in accordance with HPO/OO-9, Respiratory Protection Program, HPO/OO-9b, Respiratory Protective Equipment Selection and Use, HPO/CD-9c, Respiratory Protective Equipnent Maintenance and Quality Assurance.
2.0 PGZDFUP ACTIGIS 2.1 Dosimetry, Bionssay, and Respiratory Group Leader shall:
2.1.1 Establish a dosimetric device collection station.
( 2.1.2 Obtain any renaining information necessary to ccuplete Appendix EP-205C-1, Dosimetric Log. y s
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EP-207H Paga 3 of 6, Rev. 0
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( 2.1.3 Arrange to have dosimetric devices processed.
2.2 Dosimetry, Bioassay, and Respiratory Group Leader shall:
2.2.1 Canpare the results of the bioassay analysis with the most recent analysis performed on the person (if available) prior to the emergency.
2.2.2 Report results to the Personnel Safety Team Leader.
2.3 Dosimetry, Bioassay, and Respiratory Group Leader shall:
2.3.1 Recover respiratory equipment and process for re-use in accordance with applicable section of HPO/CD-9c.
FINAL O'NDITICNS:
1.0 Radiological releases are terminated or at an acceptable levels.
2.0 Emergency Director directs Personnel Safety Team Leader to terminate Personnel Dosimetry, Bioassay, and Respiratory Group functions.
APPENDICES:
,. EP-205C-1, Dosimetric Devices Log EP-205C-2, Bionssay Record Form
(
REFERENCES:
PBAPS Emergency Plan, Section 5.2.1.5.7.4, Dosimetry, Respiratory and Bioassay Group NUREG 0654 Health Physics Operating / Chemistry Operating Procedures
., HPO/tD-9, Respiratory Protection Program i
HPO/CMb, Respiratory Protection Equipnent Selection and Use HPO/tD-9c, Respiratory Protection Equignent Maintenance and Quality Assurance HPO/00-13a, Control of Personnel Dosimetry Badges HPO/CD-26, Personnel Bioassay Program e.
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CO5IROLLED APPROYED COPY- @
Unusual Event Imnediate Notification Call List YOID PREVIOUS ISSUE DISIRIBUTION PER A.2
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- a. Emergency Director Centrex r -
y 1 Alterna
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- c. Pennsylvania Emergency I , ManageTent Agency
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Agencies l (1) York County 24 hrs. I
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' General Emergency Irmediate Notification Call List
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APPEDIX C
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COETROLLID APPR07 u COPIs EP-209 VOID PREVIOUS ISSUE APPENDIX E DISTRIBUTION PER 1-2 Page 1 of 10, Rev. 14 EP-209 APPENDIX E - CDRPORATE DERGENCY TEAM LEADERS AND sueruxr PERSCNEL kEP 161985 Ecme Phme Centrex Site Emergency Coordinator s Site Emercency Coordinator Alternat M .. - Supt. Nuclear Services Site Emergency Coordinator Alternate ck EP&C Ccordinator Director, . { HP&C Coor r e l I icis , Rad. Prot. Sect. l Environmental Samoling Coordinator A
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